Achievements of DEMO R&D

Achievements obtained in BA Phase II (from April 2020) and those obtained in BA Phase I (from June 2007 to March 2020) are separately shown hereafter. 

　from 2020

As it was the case in BA Phase I, the activities in fusion reactors R&D in BA Phase II continue to support ITER in issues related to Tritium retention in first wall materials, and to contribute to the materials database for future reactors such as DEMO, which will be in part validated in a future IFMIF type installation. DEMO R&D Activities have been chosen based on the results of BA Phase I and discussions with the Design teams, and are focused on the four areas that have been identified as of mutual interest, and where effective collaboration can be implemented between EU and JA. The activities are 1) continuous bred tritium recovery and inventory evaluation, including JET tile and dust analysis, 2) development of structural material for fusion DEMO in-vessel components, 3) neutron irradiation experiments of breeding functional materials, and 4) development of a material corrosion data base. The peer-reviewed papers corresponding to the activities in the four arias mentioned above are presented below.

JET tile and dust analysis

Year IA Title Authors DOI Journal
2022 EU/JA An overview of tritium retention in dust particles from the JET-ILW divertor T. Otsuka, S. Masuzaki, N. Ashikawa, Y. Torikai, Y. Hatano, M. Tokitani, Y. Oya, T. Hayashi, H. Tanigawa, N. Asakura, Y. Iwai, A. Widdowson, M. Rubel, https://doi.org/10.1088/1402-4896/ac445b Physica Scripta
2021 EU/JA Global distribution of tritium in JET with the ITER-like wall S. E. Lee, Y. Hatano, M. Tokitani, S. Masuzaki, Y. Oya, T. Otsuka, N. Ashikawa, Y. Torikai, N. Asakura, H. Nakamura, K. Isobe, H. Kurotaki, D. Hamaguchi, T. Hayashi, A. Widdowson, S. Jachmich, J. Likonen, M. Rubel https://doi.org/10.1016/j.nme.2021.100930 Nuclear Materials and Energy
2020 EU/JA Comparison of hydrogen isotope retention in divertor tiles of JET with ITER-Like Wall exposed during 2011-2012 and 2015-2016 campaigns Y. Oya, S. Masuzaki, M. Tokitani, M. Nakata, Fei Sun, M. Oyaidzu, K. Isobe, N. Asakura, T. Otsuka, A. M. Widdowson, J. Likonen, M. Rubel https://doi.org/10.1080/15361055.2020.1716455 Fusion Science and Technology
2020 EU/JA Determination of retained tritium from ILW dust particles in JET N. Ashikawa Y. Torikai, N. Asakura, A. Widdowson, M. Rubel, M. Hara, T. Otsuka, K. Heinola, Y. Hatano, K. Isobe, M. Oyaidzu, S. Masuzaki, T. Hayashi, A. Baron-Wiechec and JET Contributors https://doi.org/10.1016/j.nme.2019.100673 Nuclear Materials Energy
2020 EU/JA Surface morphology of the bulk tungsten divertor tiles from JET ITER-like wall: Microscopic analysis M. Tokitani, M. Miyamoto, S. Masuzaki, Y. Hatano, Y. Oya, T. Otsuka, M. Oyaidzu, H. Kurotaki, T. Suzuki, D. Hamaguchi, T. Hayashi, N. Asakura, A. Widdowson, S. Jachmich, M. Rubel https://dx.doi.org/10.1088/1402-4896/ab3d09 Physica Scripta
2020 EU/JA Tritium distribution analysis of Be limiter tiles from JET-ITER like wall campaigns using imaging plate technique and β-ray induced X-ray spectrometry S. E. Lee, Y. Hatano, M. Hara, S. Masuzaki, M. Tokitani, M. Oyaizu, H. Kurotaki, D. Hamaguchi, H. Nakamura, N. Asakura, Y. Oya, J. Likonen, A. Widdowson, S. Jachmich, K. Helariutta, M. Rubel, JET Contributors https://doi.org/10.1016/j.fusengdes.2020.111959 Fusion Engineering and Design

Other one Paper has been submitted.

T1 (Tritium Technology)

Year IA Title Authors DOI Journal
2022 EU Operational Tritium Inventories in the EU-DEMO Fuel Cycle J.C. Schwenzer, C. Day, T. Giegerich, A. Santucci https://doi.org/10.1080/15361055.2022.2101834 Fusion Science and Technology
2022 EU Preliminary assessment of tritium permeation and retention in the European Water Cooled Lithium Lead Test Blanket Module with TESSIM-h R. Arredondo, K. Schmid, I. Ricapito, A. Lukenskas, G.A. Spagnuolo https://doi.org/10.1016/j.nme.2022.101228 Nuclear Materials and Energy
2022 EU The role of grain boundaries and denuded zones for tritium retention in high-dose neutron irradiated beryllium N. Zimber, P. Vladimirov https://doi.org/10.1016/j.jnucmat.2022.153855 Journal of Nuclear Materials
2021 JA Basic concept of JA DEMO fuel cycle Y. Iwai, Y. Edao, R. Kurata, K Isobe https://doi.org/10.1016/j.fusengdes.2021.112261 Fusion Engineering and Design
2021 JA Development of a compact real-time process gas analysis system for tritium accountancy for a DEMO fusion reactor by an application of laser Raman spectroscopy S. O'hira, Y. Edao, K. Isobe, Y. Iwai https://doi.org/10.1016/j.fusengdes.2021.112502 Fusion Engineering and Design

T2 (Structural Materials)

Year IA Title Authors DOI Journal
2022 EU Generalized universal equation of states for magnetic materials: A novel formulation for an interatomic potential in Fe Isaac Toda-Caraballo, Jan S. Wróbel, and Duc Nguyen-Manh https://link.aps.org/doi/10.1103/PhysRevMaterials.6.043806 Phys. Rev. Materials
2022 EU Grand Challenges in Nuclear Engineering S. L. Dudarev https://doi.org/10.3389/fnuen.2022.945270 Frontiers in Nuclear Engineering
2022 EU Probabilistic analysis of cleavage fracture in commercial polycrystalline tungsten Mathias Jetter, Jarir Aktaa, https://doi.org/10.1016/j.jnucmat.2022.153757 Journal of Nuclear Materials
2022 EU Volume of a dislocation network Max Boleininger, Sergei L. Dudarev, Daniel R. Mason, and Enrique Martínez https://doi.org/10.1103/PhysRevMaterials.6.063601 Phys. Rev. Materials
2022 JA Development of non-destructive testing (NDT) technique for HIPed interface by Compton scattering X-ray spectroscopy Hiroshi Sakurai, Kosuke Suzuki, Shoya Ishii, Kazushi Hoshi, Takashi Nozawa, Hidetsugu Ozaki, Hiroto Haga, Hiroyasu Tanigawa, Yoji Someya, Masao Tsuchiya, Hiroshi Takeuchi, Naruki Tsuji https://doi.org/10.1016/j.nme.2022.101171 Nuclear Materials and Energy
2022 JA Effect of uniaxial tensile strain on binding energy of hydrogen atoms to vacancy-carbon-hydrogen complexes in α-iron Shintaro Hirayama, Koichi Satoa, Daiji Kato, Hirotomo Iwakiri, Masatake Yamaguchi, Yoshiyuki Watanabe, Takashi Nozawa https://doi.org/10.1016/j.nme.2022.101179 Nuclear Materials and Energy
2022 JA Mechanical properties of self-ion irradiated pure tungsten using nano-indentation test and micro-tensile test J.H. Yu, H. Kurotaki, M. Ando, T. Nozawa https://doi.org/10.1016/j.nme.2022.101145 Nuclear Materials and Energy
2022 JA Phase decomposition of oxide film of flow accelerated corroded F82H steel under high-temperature iron irradiation Sho Kano,Huilong Yang, John McGrady, Motoki Nakajima, Masami Ando, Takashi Nozawa, Hiroaki Abe https://doi.org/10.1016/j.jnucmat.2022.153639 Journal of Nuclear Materials
2022 JA Radiation-induced amorphization of M23C6 in F82H steel: An atomic-scale observation S. Kano, H. Yang, J. McGrady, Y. Watanabe, M. Ando, D. Hamaguchi, T. Nozawa, H. Tanigawa, K. Yoshida, T. Shibayama, H. Abe https://doi.org/10.1016/j.jnucmat.2021.153345 Journal of Nuclear Materials
2021 EU Additive manufacturing technologies for EUROFER97 components S.. Bonk, H. Neuberger, D. Beckers, J. Koch, S. Antusch, M. Rieth https://doi.org/10.1016/j.jnucmat.2021.152859 Journal of Nuclear Materials
2021 EU An estimate for thermal diffusivity in highly irradiated tungsten using Molecular Dynamics simulation DR Mason, M. Reza, F. Granberg, F. Hofmann https://doi.org/10.1103/PhysRevMaterials.5.125407 Physical Review Materials
2021 EU Anisotropy in the hardness of single crystal tungsten before and after neutron irradiation C. Yin, G. Bonny, D. Terentyev https://doi.org/10.1016/j.jnucmat.2020.152759 Journal of Nuclear Materials
2021 EU Comparison of K-doped and pure cold-rolled tungsten sheets: Tensile properties and brittle-to-ductile transition temperatures P. Lied, W. Pantleon, C. Bonnekoh, S. Bonk, A. Hoffmann, J. Reiser, M. Rieth https://doi.org/10.1016/j.jnucmat.2020.152664 Journal of Nuclear Materials
2021 EU Development of CuCrZr via Electron Beam Powder Bed Fusion (EB-PBF) N. Ordas, L.Portolés, M.Azpeleta, A.Gómez, J.R.Blasco, M.Martinez, J.Ureña, I.Iturriza https://doi.org/10.1016/j.jnucmat.2021.152841 Journal of Nuclear Materials
2021 EU Ductile to Brittle Transition Temperature of advanced tungsten alloys for nuclear fusion applications deduced by miniaturized three-point bending tests C. Yin, D. Terentyev, T. Zhang, S. Nogami, S. Antusch, C. Chang, R. H. Petrov, T. Pardoen https://doi.org/10.1016/j.ijrmhm.2020.105464 International Journal of Refractory Metals and Hard Materials
2021 EU Effect of statistically stored dislocations in tungsten on the irradiation induced nano-hardening analyzed by different methods G. Bonny, T. Khvan, A. Bakaeva, Y. Chao, A. Dubinko, C. Cabet, M. Loyer-Prost, N. Castin, A. Bakaev, D. Terentyev https://doi.org/10.1016/j.jnucmat.2020.152543 Journal of Nuclear Materials
2021 EU Effects of stress triaxiality and strain rate on the fracture of a CuCrZr alloy Y. Wang, O.Mohamed, K.Dunn, T.Sui, M.Bashir, P.Cooper, A.Lukenskas, G.Wu, M.Gorley https://doi.org/10.1016/j.jnucmat.2020.152546 Journal of Nuclear Materials
2021 EU Elastic dipole tensors and relaxation volumes of point defects in concentrated random magnetic Fe-Cr alloys J. Wrobel, M.R. Zemla, D. Nguyen-Manh, P. Olsson, L. Messina, C. Domain, T. Wejrzanowski, S. L. Dudarev https://doi.org/10.1016/j.commatsci.2021.110435 Computational Materials Science
2021 EU First principles model for voids decorated by transmutation solutes: Short-range order effects and application to neutron irradiated tungsten DM Nguyen, J. Wrobel, M. Klimenkov, M. Lloyd, L. Messina, S. Dudarev https://doi.org/10.1103/PhysRevMaterials.5.065401 Physical Review Materials
2021 EU Fracture-mechanical behavior of neutron irradiated tungsten E. Gaganidze, A. Chauhan, H.-C. Schneider, D. Terentyev, B. Rossaert, J. Aktaa https://doi.org/10.1016/j.jnucmat.2020.152761 Journal of Nuclear Materials
2021 EU Impact of neutron irradiation on hardening of baseline and advanced tungsten grades and its link to initial microstructure C. Yin, D. Terentyev, A. Dubinko, T. Zhang, M. Wirtz, S. Antush, R. H. Petrov, T. Pardoen https://doi.org/10.1088/1741-4326/abf417 Nuclear Fusion
2021 EU Interaction of Transmutation Products with Precipitates, Dislocations and Grain Boundaries in Neutron Irradiated W MJ Lloyd, A. J. London,M. Gilbert,C. S. Becquart,C. Domain,E. Martinez,M. Moody,P. A. J. Bagot,D. Nguyen-Manh,D. E. J. Armstrong https://doi.org/10.1016/j.mtla.2022.101370 Materialia
2021 EU Machine learning surrogate models for prediction of point defect vibrational entropy C Lapointe, T D Swinburne, L Thiry, S Mallat, L Proville, C S Becquart M-C Marinica https://doi.org/10.1103/PhysRevMaterials.4.063802 Physical Review Materials
2021 EU Macroscopic elastic stress and strain produced by irradiation L. Reali, M. Boleininger, M. R. Gilbert, S.L. Dudarev https://doi.org/10.1088/1741-4326/ac35d4 Nuclear Fusion
2021 EU Microstructural evolution in single tungsten fiber-reinforced tungsten composites during annealing: recrystallization and abnormal grain growth U.M.Ciucani, L.Haus, H.Gietl, J.Riesch, W. Pantleon https://doi.org/10.1016/j.jnucmat.2020.152579 Journal of Nuclear Materials
2021 EU Microstructure and hardening induced by neutron irradiation in single crystal, ITER specification and cold rolled tungsten A. Dubinko, D. Terentyev, C. Yin, W. Van Renterghem, B. Rossaert, M. Rieth, E.E. Zhurkin, A. Zinovev, C.C. Chang, S. Van Dyck, G. Bonny, https://doi.org/10.1016/j.ijrmhm.2021.105522 International Journal of Refractory Metals and Hard Materials
2021 EU Mobility of screw dislocation in BCC tungsten at high temperature in presence of carbon L. Ventelon, G. Hachet, D. Caillard, L. Ventelon, E. Clouet https://doi.org/10.1016/j.actamat.2021.117440 Acta Materialia
2021 EU Molecular dynamics simulations of high-dose damage production and defect evolution in tungsten F Granberg, J. Byggmästar, K. Nordlund https://doi.org/10.1016/j.jnucmat.2021.153158 Journal of Nuclear Materials
2021 EU Parameter-free quantitative simulation of high-dose microstructure and hydrogen retention in ion-irradiated tungsten DR Mason, F. Granberg, M. Boleininger, T. Schwarz-Selinger, K. Nordlund, S.L. Dudarev https://doi.org/10.1103/PhysRevMaterials.5.095403 Physical Review Materials
2021 EU Perspectives on multiscale modelling and experiments to accelerate materials development for fusion MR Gilbert, K. Arakawa, Z. Bergstrom, M.J. Caturla, S.L. Dudarev, F. Gao, M.R. Gilbert, A.M. Goryaeva, S.Y. Hu, X. Hu, R.J. Kurtz, A. Litnovsky, J. Marian, M.-C. Marinica, E. Martinez, E.A. Marquis, D.R. Mason, B.N. Nguyen, P. Olsson, Y. Osetskiy, D. Senor, W. Setyawan, M.P. Short, T. Suzudo, J.R. Trelewicz, T. Tsuru, G.S. Was, B.D. Wirth, L. Yang, Y. Zhang, S.J. Zinkle https://doi.org/10.1016/j.jnucmat.2021.153113 Journal of Nuclear Materials
2021 EU Post-irradiation annealing of the neutron irradiated EUROFER97 A.. Chauhan, Q. Yuan, C. Dethloff, E. Gaganidze, J. Aktaa https://doi.org/10.1016/j.jnucmat.2021.152863 Journal of Nuclear Materials
2021 EU The beneficial effect of rolling on the fracture toughness and R-curve behavior of pure tungsten D. Firneis, S. Wurster, V. Nikolic, R. Pippan, A. Hohenwarter https://doi.org/10.1016/j.msea.2022.142756 Materials Science and Engineering: A
2021 EU The effect on the mechanical response of Cr and Ni segregation on dislocation lines in bcc Fe M.I. Pascuet, G. Bonny, G. Monnet, L. Malerba https://doi.org/10.1016/j.jnucmat.2020.152319 Journal of Nuclear Materials
2021 EU Thermal stability of the microstructure in rolled tungsten for fusion reactors W Pantleon, https://doi.org/10.1088/1402-4896/ac2854 Physica Scripta
2021 EU/JA DEMO Structural Materials Qualification and Development M. Gorley, G. Aiello, J. Henry, T. Nozawa, G. Pintsuk, M. Rieth, H. Tanigawa https://doi.org/10.1016/j.fusengdes.2021.112513 Fusion Engineering and Design
2021 JA Pressurized Thermal Shock Analysis of a Reactor Pressure Vessel for Optimizing the Maintenance Strategy: Effect of Asymmetric Reactor Cooling X. Ruan, K. Morishita https://doi.org/10.1016/j.nucengdes.2020.111021 Nuclear Engineering and Design
2021 JA Status and the challenge of Japanese materials property handbook to facilitate structural design criteria for DEMO in-vessel coponents T. Nozawa, H. Tanigawa, T. Kojima, T. Itoh, N. Hiyoshi, M. Ohata, T. Kato, M. Ando, M. Nakajima, T. Hirose, J. D. Reed, X. Chen, J. W. Geringer, Y. Katoh https://doi.org/10.1088/1741-4326/ac269f Nuclear Fusion
2020 EU Computational analysis of the evolution of the brittle-to-ductile transition of tungsten under fusion conditions M.A.. Oude Vrielink, J.A.W. van Dommelen, M.G.D. Geers https://doi.org/10.1088/1361-651X/abc236 Modelling and Simulation in Materials Science and Engineering
2020 EU Direct observation of dislocation loops shrinkage upon annealing neutron-irradiated Fe-9Cr alloy Q. Yuan, A.Chauhan, E.Gaganidze, J.Aktaa https://doi.org/10.1016/j.jnucmat.2020.152401 Journal of Nuclear Materials
2020 EU Effect of Non-Heisenberg Magnetic Interactions on Defects in Ferromagnetic Iron JBJ. Chapman, P.-W. Ma, S.L. Dudarev https://doi.org/10.1103/PhysRevB.102.224106 Physical Review B
2020 EU Fracture-mechanical properties of neutron irradiated ITER specification tungsten E. Gaganidze, A. Chauhan, H.-C. Schneider, D. Terentyev, G.Borghmans, J. Aktaa https://doi.org/10.1016/j.jnucmat.2020.152761 Journal of Nuclear Materials
2020 EU Indentation testing on 3 MeV proton irradiated tungsten R. Rayaprolu, S. Möller, R. Abernethy, M. Rasinski, J.C. Haley, Ch. Linsmeier https://doi.org/10.1016/j.nme.2020.100776 Nuclear Materials and Energy
2020 EU Multiscale Analysis of Dislocation Loops and Voids in Tungsten PW. Ma, D. R. Mason, S. L. Dudarev https://doi.org/10.1103/PhysRevMaterials.4.103609 Physical Review Materials
2020 EU Statistical mechanics of kinks on a gliding screw dislocation M. Boleininger, M.Gallauer, S.L.Dudarev, T.D.Swinburne, D.R.Mason, D.Perez https://doi.org/10.1103/PhysRevResearch.2.043254 Physical Review Research
2020 EU Technology Readiness Assessment of Materials for DEMO In-Vessel Applications MD. Richardson, M. Gorley, Y. Wang, G. Aiello, G. Pintsuk, E. Gaganidze, M. Richou, J. Henry, R. Vila, M. Rieth, E. Surrey https://doi.org/10.1016/j.jnucmat.2021.152906 Journal of Nuclear Materials
2020 EU The brittle-to-ductile transition in cold-rolled tungsten sheets: Contributions of grain and subgrain boundaries to the enhanced ductility after pre-deformation C. Bonnekoh, P. Lied, S. Zaefferer, U. Jäntsch, A. Hoffmann, J. Reiser, M. Rieth https://doi.org/10.1016/j.nme.2020.100769 Nuclear Materials and Energy
2020 JA Evaluation of fatigue properties of reduced activation ferritic/martensitic steel, F82H for development of design criteria T. Hirose, T. Kato, H. Sakasegawa, H. Tanigawa, T. Nozawa https://doi.org/10.1016/j.fusengdes.2020.111823 Fusion Engineering and Design
2020 JA Helium effect on the sink strength of grain boundaries in F82H M. Zushi, N. Hashimoto, D. Hamaguchi, Y. Watanabe, H. Tanigawa https://doi.org/10.1016/j.nme.2020.100788 Fusion Engineering and Design
2020 JA Hydrogen retention behavior of primary precipitates in F82H steel: Atomistic calculation based on the density functional theory Y. Watanabe, H. Iwakiri, N. Murayosho, D. Kato, K. Sato, H. Tanigawa https://doi.org/10.1016/j.fusengdes.2020.111788 Fusion Engineering and Design
2020 JA Materials atrength standard of F82H for RCC-MRx H. Sakasegawa, H. Tanigawa, T. Hirose, T. Kato, T. Nozawa https://doi.org/10.1016/j.fusengdes.2020.111952 Fusion Engineering and Design
2020 JA Mechanical properties of three kinds of ITER-Grade pure tungsten with different manufacturing process J. Yu, H. Tanigawa, D. Hamaguchi, T. Nozawa https://doi.org/10.1016/j.fusengdes.2020.111679 Fusion Engineering and Design
2019 JA Local Approach for Elastic-Plastic Fracture Assessment of Cracked Component under Mixed Mode Loading K. Shimizu, M. Ohata, H. Shoji, T. Kato, H. Tanigawa https://onepetro.org/ISOPEIOPEC/proceedings-abstract/ISOPE19/All-ISOPE19/ISOPE-I-19-192/20922 International Ocean and Polar Engineering Conference

Other 8 papers have been submitted.

T3 (Functional Materials)

Year IA Title Authors DOI Journal
2022 EU Nanoscale insights into the corrosion of EUROFER by lithium ceramics M. Duerrschnabel, E. Gaisina, R. Gaisin, M. Walter, J. Aktaa, M. Rieth https://doi.org/10.1016/j.corsci.2022.110190 Corrosion Science
2022 EU Recent studies to the impact of ceramic breeder environment on the mechanical properties of EUROFER97 under operating conditions E. Gaisina, M. Duerrschnabel, J. Leys, R. Knitter, J. Aktaa, M. Walte https://doi.org/10.1016/j.jnucmat.2022.153677 Journal of Nuclear Materials
2022 JA Mechanical properties of beryllium-titanium intermetallic compounds fabricated by plasma sintering T. Hwang, J.-H. Kim, S. Nakano, M. Nakamichi https://doi.org/10.1016/j.nme.2022.101117 Nuclear Materials and Energy
2021 EU A first approach towards DEM analysis of plasticity in pebble beds M. Moscardini, S. Pupeschi, M. Kamlah https://doi.org/10.1016/j.fusengdes.2020.112109 Fusion Engineering and Design
2021 EU Ab initio study of hydrogen diffusion in Be and Be12Ti for fusion applications D.V.. Bachurin, C. Stihl, P.V. Vladimirov https://doi.org/10.1016/j.commatsci.2020.109921 Computational Materials Science
2021 EU Assessment of multiscale tritium desorption models from (0001) Be surfaces C. Stihl, P. V. Vladimirov, A. Möslang https://doi.org/10.1016/j.jnucmat.2020.152595 Journal of Nuclear Materials
2021 EU Current status and future perspectives of EU ceramic breeder development O. Leys, J.M. Leys, R. Knitter https://doi.org/10.1016/j.fusengdes.2020.112171 Fusion Engineering and Design
2021 EU/JA Thermo-mechanical behavior of titanium beryllide pebble beds at ambient temperature J. Reimann, B. Fretz, R. Gaisin, A. Goraieb, J. Kim, S. Nakano, M. Nakamichi, P. Vladimirov https://doi.org/10.1016/j.fusengdes.2021.112249 Fusion Engineering and Design
2021 JA Deuterium and helium desorption behavior and microstructure evolution in beryllium during annealing Y. Sugimoto, M. Nakamichi, J.Kim, H. Kurata, M. Haruta, M. Miyamoto https://doi.org/10.1016/j.jnucmat.2020.152686 Journal of Nuclear Materials
2021 JA Deuterium desorption and retention of beryllium intermetallic compounds for fusion applications J. Kim, T. Hwang, S. Nakano, M. Miyamoto, H. Iwakiri, M. Nakamichi https://doi.org/10.1016/j.jnucmat.2021.152936 Journal of Nuclear Materials
2021 JA The influence of the long-term heating under H2 atmosphere on the tritium release behavior from the neutron-irradiated Li2TiO3 A. Ipponsugi, K. Katayama, T. Hoshino https://doi.org/10.1016/j.fusengdes.2021.112495 Fusion Engineering and Design
2020 EU Investigation of high-dose irradiated beryllium microstructure N. Zimber, P. Vladimirov, M.Klimenkov, V. Kuksenko https://doi.org/10.1016/j.jnucmat.2020.152374 Journal of Nuclear Materials
2020 EU Radiation-induced effects in neutron- and electron-irradiated lithium silicate ceramic breeder pebbles J.M. Leys, A.Zarins, J.Cipa, L.Baumane, G.Kizane, R.Knitter https://doi.org/10.1016/j.jnucmat.2020.152347 Journal of Nuclear Materials
2020 JA Compatibility of advanced tritium breeders and neutron multipliers J. Kim, M. Nakamichi https://doi.org/10.1016/j.fusengdes.2020.111581 Fusion Engineering and Design
2020 JA Influence of Lithium Mass Transfer on Tritium Behavior in Pebbles of Li2TiO3 with Excess Lithium K. Katayama, A. Ipponsugi, T. Hoshino https://doi.org/10.1016/j.fusengdes.2020.112011 Fusion Engineering and Design

T4 (Corrosion Database)

Year IA Title Authors DOI Journal
2022 EU Activated Corrosion Products Evaluations for Occupational Dose Mitigation in Nuclear Fusion Facilities Terranova, N.; Breidokaité, S.; Contessa, G.M.; Di Pace, L.; Gasparrini, C.; Kaliatka, T.; Mariano, G. https://doi.org/10.3390/environments9070076 Environments
2022 EU Compatibility of niobium, vanadium and P22 steel in high temperature flowing LiPb A Venturini, S. Bassini, C. Ciantelli, A. Fiore, D. Martelli, F. Papa, M. Utili https://doi.org/10.1016/j.jnucmat.2022.153985 Journal of Nuclear Materials
2022 JA The effect of dissolved oxygen respectively dissolved hydrogen on corrosion behavior of CuCrZr alloy in high temperature water Yen-Jui Huang, Motoki Nakajima, Hironori Kurotaki, Takashi Nozawa https://doi.org/10.1016/j.nme.2022.101190 Nuclear Materials and Energy
2021 EU Comparative study of the mechanical properties after proton irradiation of Al2O3 and Si-SiC ceramics for fusion breeding blanket applications J.M. Garcia, M.Gonzáles, F.Sánchez https://doi.org/10.1016/j.fusengdes.2022.113309 Fusion Engineering and Design
2021 EU Design of the test section for the experimental validation of antipermeation and corrosion barriers for WCLL BB Marco Utili, C. Alberghi, L. Candido, F. Papa, A. Venturini http://dx.doi.org/10.1016/j.fusengdes.2021.112453 Applied Sciences
2021 EU MHD R&D activities for liquid metal blankets C. Mistrangelo, L. Bühler, C. Alberghi, S. Bassini, L. Candido, C. Courtessole, A. Tassone, F. R. Urgorri O. Zikanov https://doi.org/10.3390/en14206640 Energies
2021 EU Preliminary assessment of cooling water chemistry for fusion power plants N. Terranova, E. Lo Piccolo, R. Torella, L. Di Pace, C. Gasparrini, M. Dalla Palma https://doi.org/10.3390/cmd2030027 Corrosion and Materials Degradation
2021 EU The influence of MHD boundary layers on tritium permeation in PbLi flows for fusion breeding blankets F Roca Urgorri, C. Moreno, I.Fernández-Berceruelo and D. Rapisarda https://doi.org/10.1016/j.ijheatmasstransfer.2021.121906 International Journal of Heat and Mass Transfer
2021 EU The microstructural in-sight to the mechanical behavior of alumina after high energy proton irradiation J Mauricio Garcia, M. Gonzáles, M. Roldan, F. Sánchez https://doi.org/10.1016/j.nme.2022.101173 Nuclear Materials and Energy
2020 JA Simultaneous effects of dissolved oxygen and applied stress on surface morphology of steels for cooling systems of blanket module in pressurized water N. Nakazato, Y. Mima, Y. Nemoto, H. Kishimoto, M. Nakajima, T. Nozawa, H. Tanigawa https://doi.org/10.1016/j.fusengdes.2020.111681 Fusion Engineering and Design

One paper has been submitted.

In parallel, the activities in DEMO R&D are presented in the various international conferences and others.

JET tile and dust analysis

Year PI Title Authors Conference
2022 EU/JA Evaluation of tritium distribution in Be limiter tiles used in JET ITER-like wall campaigns S.E. Lee, Y. Hatano, S. Masuzaki, Y. Oya, M. Tokitani, M. Yajima, T. Otsuka, N. Ashikawa, Y. Torikai, N. Asakura, H. Nakamura, H. Kurotaki, T. Hayashi, T. Nozawa, J. Likonen, A. Widdowson, M. Rubel 13th International Conference on Tritium Science and Technology
2021 EU/JA An overview of tritium retention in dust particles from the JET-ILW divertor T. Otsuka, S. Masuzaki, N. Ashikawa, Y. Torikai, Y. Hatano, M. Tokitani, Y. Oya, T. Hayashi, H. Tanigawa, N. Asakura, Y. Iwai, A. Widdowson, M. Rubel, JET Contributors 18th International Conference on Plasma-Facing Materials and Components for Fusion Applications (PFMC-18)
2021 EU/JA Global Distribution of Tritium in JET with the ITER-Like Wall Y. Hatano, S. E. Lee, S. Masuzaki, Y. Oya, T. Otsuka, N. Ashikawa, Y. Torikai, N. Asakura, H. Nakamura, K. Isobe, H. Kurotaki, D. Hamaguchi, T. Hayashi, J. Likonen, S. Koivuranta, A. Widdowson, S. Jachmich, M. Rubel 24th International Conference on Plasma Surface Interactions in Controlled Fusion Devices (PSI-24)
2021 EU/JA Tritium retention in dust particles and divertor tiles of JET operated with the ITER-Like Wall Y. Torikai, G. Kikuchi, S. Masuzaki, T. Otuka, N. Ashikawa, M. Yajima, Y. Oya, Y. Hatano, N. Asakura, T. Hayashi, M. Oyaidzu, A. Widdowson, M. Rubel and JET Contributors The 28th IAEA Fusion Energy Conference (FEC 2020)

T1 (Tritium Technology)

Year IA Title Authors Conference
2022 EU EU-DEMO fuel cycle performance metrics and tritium self-sufficiency criteria J.C. Schwenzer, C. Day 32nd Symposium on Fusion Technology (SOFT2022)
2022 EU Modelling of tritium transport in breeding blankets: influence of neutron trap creation J. Dark, R.Delaporte-Mathurin, E.A.Hodille, J.Mougenot, Y.Charles, C.Grisolia 32nd Symposium on Fusion Technology (SOFT2022)
2022 EU Overview of tritium designs and developments for European DEMO C. Day 13th International Conference on Tritium Science and Technology
2022 EU The effect of co-and counter-permeation on tritium transport in HCPB and WCLL breeding blanket environments S.J. Hendricks, E. Carella, C. Moreno, F.R. Urgorri, J. Molla 13th International Conference on Tritium Science and Technology
2022 EU Tritium transport in WCLL outboard breeding blanket of EU-DEMO reactor under pulsed plasma operation L. Candido, C. Alberghi, P. Arena, F. Moro, S. Noce, M. Utili, M. Zucchetti The Technology of Fusion Energy (TOFE 2022)

T2 (Structural Materials)

Year PI Title Authors Conference
2022 EU A Machine Learned Spin-Lattice Interatomic Potential for Defected Magnetic Iron JBJ, Chapman, P.W.Ma The 15th conference of COmputer Simulation of IRradiation Effects in Solids
2022 EU An eigenstrain-body force multi-scale model for stress, strain and swelling of nuclear reactor components under irradiation L. Reali, M. Boleininger, M. Gilbert, S. Dudarev The 10th International Conference on Multiscale Materials Modeling
2022 EU Anomalous Precipitation of Cr in Fe-rich Ferritic Steels under Irradiation in Presence of C and N Impurities: First Principles Modeling and Experimental Observations M. Fedorov, J. Wróbel, A. London, K. Kurzydłowski, S. Dudarev, D. Nguyen-Manh TMS 2022 Annual Meeting & Exhibition
2022 EU Brittle Fracture Assessment for Tungsten and Tungsten alloy components M. Jetter, J. Aktaa 32nd Symposium on Fusion Technology (SOFT2022)
2022 EU Development & validation of ductility exhaustion criterion for DEMO in-vessel components P. Cooper, Y.Wang, A.Marsh 32nd Symposium on Fusion Technology (SOFT2022)
2022 EU Macroscopic stress and strain produced by irradiation L. Reali, M. Boleininger, M. Gilbert, S. Dudarev TMS 2022 Annual Meeting & Exhibition
2022 EU Multi-scale numerical investigation to predict the irradiation-induced change in engineering properties of fusion reactor materials Mohamed, S , Rhydian Lewis, LLion M. Evans ECCOMAS Congress 2022
2022 EU Review and meta-analysis of Tungsten and Tungsten Alloy Thermophysical Properties: Current Status and Research Needs for the EUROfusion Materials Property Handbook J. Echols, M. Richards, L. Norman, Y. Wang The Nuclear Materials Conference (NuMat2022)
2022 EU The volume of dislocation networks created by irradiation M. Boleiniger, S.L.Dudarev, D.R. Mason, E.Martínez The 10th International Conference on Multiscale Materials Modeling
2022 JA Determining the true stress and true strain curves of reduced-activation ferritic/martensitic steel using miniature tensile specimens Takashi Nozawa, Taichiro Kato, Xiaoyong Ruan, Toshiya Nakata, Shigekazu Suzuki, Xiang Chen, Arunodata Bhattacharya, Mitsuru Ohata, Hiroyasu Tanigawa, Yutai Katoh 32nd Symposium on Fusion Technology (SOFT2022)
2022 JA Effect of transmutation gas atoms on cavity formation around grain boundaries in F82H Naoyuki Hashimoto, Hiroshi Oka, Masami Ando, Yoshiyuki Watanabe, Takashi Nozawa The Nuclear Materials Conference (NuMat2022)
2022 JA Effects of incascade defect clustering and defect cluster migration on microstructural evolution in F82H steel under irradiation: Mean field cluster dynamics simulation Yoshiyuki Watanabe, Kazunori Morishita, Chen Yuting, Zhe Liangfan, Takashi Nozawa 32nd Symposium on Fusion Technology (SOFT2022)
2022 JA Evaluation of tensile ductility using shape change of gauge section of small-tensile specimen Toshiya Nakata, Taichiro Kato, Takashi Nozawa, Hiroyasu Tanigawa 32nd Symposium on Fusion Technology (SOFT2022)
2022 JA Specimen size effects on creep properties of reduced-activation ferritic steel F82H Takuya Nagasaka, Jingjie Shen, Masami Ando, Taichiro Kato, Takashi Nozawa, Hiroyasu Tanigawa The Technology of Fusion Energy (TOFE 2022)
2022 JA The applicability of remote field eddy current testing to outer flaws on cooling tubes in the blanket of a fusion DEMO reactor Mizuki Kako, Takuma Tomizawa, Jiuhao Ge, Xiaoyong Ruan, Takashi Nozawa, Noritaka Yusa 32nd Symposium on Fusion Technology (SOFT2022)
2021 EU A round robin study of specimen size and geometry effects on the fracture toughness measurements of RAFM steels X. Chen, R. Hernandez, M. Serrano, D. Andres, H. Nolles, P. Earp, M. Gorley, M. Jong, M.A. Sokolov, S. Gonzalez de Vicente, Y. Katoh 20th International Conference on Fusion Reactor Materials (ICFRM-20)
2021 EU Brittle Fracture Assessment for Tungsten and Tungsten alloy components M Jetter, J.Aktaa 20th International Conference on Fusion Reactor Materials (ICFRM-20)
2021 EU Determination of fatigue crack growth properties by testing small CT specimens M. Serrano, R. Hernandez, M. Sokolov, X. Chen, M. Walter, J. Aktaa, D. Andres, H. Nolles, P. Earp, M. Gorley, M. Jong 20th International Conference on Fusion Reactor Materials (ICFRM-20)
2021 EU Effect of neutron irradiation on tungsten-copper laminate and tungsten foils A Zinovev, D.Terentyev, C.-C.Chang, C.Yin, M.Rieth, P.Lied, J.Reiser, C.Bonnekoh 20th International Conference on Fusion Reactor Materials (ICFRM-20)
2021 EU Effects of specimen size and geometry in the study of the tensile properties of RAFM steels A. Perez, R. Hernandez, M. Serrano, D. Andres 20th International Conference on Fusion Reactor Materials (ICFRM-20)
2021 EU FRACTESUS project: A European effort to validate the use of sub-sized specimens in fracture mechanics testing of irradiated materials S. Cicero, B. Arroyo, D. Andres, P. Kilgallon, M. Serrano, R. Hernandez 20th International Conference on Fusion Reactor Materials (ICFRM-20)
2021 EU Fracture toughness determination of EUROFER97 by testing small CT specimens DA Andres, Marta Serrano, Rebeca Hernandez, Yiqiang Wang, Mark Richardson 2021 Pressure Vessels & Piping Virtual Conference
2021 EU Fracture toughness of neutron irradiated tungsten E. Gaganidze, A. Chauhan, H.-C. Schneider, D. Terentyev, B. Rossaert, J. Aktaa 20th International Conference on Fusion Reactor Materials (ICFRM-20)
2021 EU Irradiation behaviour of European advanced rafm steels for blanket application E. Gaganidze, M. Rieth, D. Terentyev, C. Cristalli, J. Henry, G. Pintsuk, G. Aiello European Fusion Physics Workshop
2021 EU Macroscopic elastic stress and strain produced by irradiation L Reali, M. Boleininger, M. Gilbert, S. Dudarev ICTP-IAEA Virtual Workshop on Atomistic Modelling of Radiation Damage in Nuclear Systems
2021 EU Multi-scale modelling for voids decorated by transmutation solutes: Short-range order effects and application to neutron irradiated tungsten DM Nguyen, J. Wrobel, M. Klimenkov, M. Lloyd, L. Messina, S. Dudarev 20th International Conference on Fusion Reactor Materials (ICFRM-20)
2021 EU Neutron irradiation effects on the mechanical properties of single crystal tungsten investigated by indentation techniques S Dellis, K. Mergia, S. Messoloras 20th International Conference on Fusion Reactor Materials (ICFRM-20)
2021 EU Post neutron irradiation annealing and defect evolution in single crystalline tungsten D Papadakis, K. Mergia, S. Dellis, E. Manios, D. Terentyev, G. Bonny, A. Dubinko, W. Van Renterghem, M. Konstantinovic and S. Messoloras 20th International Conference on Fusion Reactor Materials (ICFRM-20)
2021 EU Progress of Research in Modelling Fusion Reactor Materials in Europe S Dudarev, G. Apostolopoulos, J.P. Balbuena, M.-F. Barthe, C.S. Becquart, M. Boleininger, G. Bonny, C. Cabet, D. Caillard, N. Castin, M.J. Caturla, R. Coppola, P.M. Derlet, E. Diegele, C. Domain, S.L. Dudarev*, L.M. Dupuy, P. Fernandez, C.-C. Fu, T. Jourdan, E. Gaganidze, A. Gentils, M.R. Gilbert, F. Granberg, F. Hofmann, R. Kembleton, M. Klimenkov, M.Y. Lavrentiev, A. London, P.-W. Ma, M.-C. Marinica, D.R. Mason, K. Mergia, E. Meslin, M. Nastar, D. Nguyen-Manh, K. Nordlund, P. Olsson, C.J. Ortiz, G. Pintsuk, M. Prester, L. Proville, B. Radiguet, M. Rieth, C. Robertson, M. Roldan, A.E. Sand, R. Schäublin, F. Soisson, T.D. Swinburne, T. Tadić, L. Ventelon, F. Willaime, J.S. Wróbel 18th International Conference on Plasma-Facing Materials and Components for Fusion Applications (PFMC-18)
2021 EU Recovery, recrystallization and abnormal grain growth in pure and K-doped tungsten sheets with different degree of deformation P Lied, Wolfgang Pantleon, Carsten Bonnekoh, Michael Dürrschnabel, Andreas Hoffmann, Jens Reiser, Michael Rieth 20th International Conference on Fusion Reactor Materials (ICFRM-20)
2021 EU Thermal stability of thin rolled potassium-doped tungsten sheets during annealing at temperatures up to 1400 °C W Pantleon, D. Tarras Madsen, U.M. Ciucani, A. Hoffmann 20th International Conference on Fusion Reactor Materials (ICFRM-20)
2021 EU/JA From ab initio models to a Virtual Tokamak Fusion Reactor: current status and ongoing challenges S Dudarev, M. Boleininger, M.J. Caturla, P.M. Derlet, C. Domain, M.R. Gilbert, F. Hofmann, P.-W. Ma, J. Marian, D.R. Mason, P. Olsson, H. Tanigawa, E. Tarleton, G. Pintsuk, G. Po, L. Reali, and M. Rieth 20th International Conference on Fusion Reactor Materials (ICFRM-20)
2021 EU/JA Recent progress and issues in development of tensile test guideline using miniature specimens for qualification of fusion DEMO structural materials database within the IAEA CRP on Towards the Standardization of Small Specimen Test Techniques for Fusion Applications T Nozawa, Y. Shen, M. Serrano, D. Andres, M. Sokolov, T. Nagasaka, T. Kato, X. Ruan, R. Chen, H. Liu, R. Hernandez, A. Harte, R. Spencer, A. Marsh, H. Nolles, P. Earp, M. Gorley, M. Jong, X. Chen, J. Shen, H. Tanigawa, S.M. Gonzalez de Vicente 20th International Conference on Fusion Reactor Materials (ICFRM-20)
2021 EU/JA Virtual Tokamak Fusion Reactor: radiation effects on a macroscopic scale S Dudarev, R. Akers, K. Arakawa, C.S. Becquart, M. Boleininger, M.J. Caturla, P.M. Derlet, C. Domain, M.R. Gilbert, F. Granberg , F. Hofmann, M. Klimenkov , W. Ma, J. Marian, D.R. Mason, K. Nordlund, G. Pintsuk, L. Reali , M. Rieth, H. Tanigawa , E. Tarleton 20th International Conference on Fusion Reactor Materials (ICFRM-20)
2021 JA Characterization of micro-scale strength and deformation in ion-irradiated RAFM steel F82H using micro-pillar compression test D. Geng, H. Yu, Y. Okuno, H. Kurotaki, T. Nozawa, M. Ando, H. Tanigawa, S. Kondo, R. Kasada 20th International Conference on Fusion Reactor Materials (ICFRM-20)
2021 JA Correlation of helium cavity accumulation in RAFM steel between different irradiation fields: Reaction rate theory based analysis Y. Watanabe, K. Morishita, M. Ando, T. Nozawa 20th International Conference on Fusion Reactor Materials (ICFRM-20)
2021 JA Development of copper deposition on tungsten with multiple laser beams focusing system H. Serizawa, Y. Sato, M. Tsukamoto, T. Nozawa, H. Tanigawa 20th International Conference on Fusion Reactor Materials (ICFRM-20)
2021 JA Development of non-destructive testing (NDT) technique for HIPed interface by Compton scattering X-ray spectroscopy H. Sakurai, K. Suzuki, S. Ishii, T. Nozawa, H. Ozaki, H. Haga, H. Tanigawa, Y. Someya, M. Tsuchiya, H. Takeuchi, N. Tsuji 20th International Conference on Fusion Reactor Materials (ICFRM-20)
2021 JA Effect of Carbon on Quantitative Evaluation of Hydrogen Atoms Trapped at Vacancy-type Defects Using Positron Annihilation Spectroscopy in Tungsten K. Sato, M. Hirabaru, M. Onoue, M. Hatakeyama, Q. Xu, Y. Watanabe, T. Nozawa 20th International Conference on Fusion Reactor Materials (ICFRM-20)
2021 JA Effect of elastic strain on the stability of vacancy-carbon-hydrogen complexes in α-iron M. Hirayama, K. Sato, D. Kato, Y. Watanabe, T. Nozawa 20th International Conference on Fusion Reactor Materials (ICFRM-20)
2021 JA Evaluation of fracture strength of multi-ion irradiated F82H by using μ-tensile testing M. Ando, T. Nozawa, R. Kasada 20th International Conference on Fusion Reactor Materials (ICFRM-20)
2021 JA Evaluation of Multiaxial Fatigue Strength for High Chromium Steel under Non-proportional Loading at High Cycle Fatigue Region T. Kojima, S. Maeda, N Hiyoshi, L. He, T. Nozawa, T. Itoh 2021 International Symposium on Structural Integrity (ISSI-2021)
2021 JA Interaction of Primary Precipitates in F82H steel with hydrogen atoms: Atomistic Calculation Based on the Density Functional Theory H. Iwakiri, Y. Watanabe, S. Toyozato, K. Sato, D. Kato 20th International Conference on Fusion Reactor Materials (ICFRM-20)
2021 JA Mechanical Properties of Self-Ion Irradiated Pure Tungsten using Mirco Tensile Test J. Yu, H. Kurotaki, M. Ando, T. Nozawa 20th International Conference on Fusion Reactor Materials (ICFRM-20)
2021 JA Probe design for the eddy current inspection of cooling tubes in the blanket of a prototype fusion reactor M. Kako, T. Tomizawa, J. Ge, T. Nozawa, N. Yusa The 30th International Toki Conference on Plasma and Fusion Research
2021 JA Quantification of the change in the nonlinear ultrasonic signals caused by irradiation-induced defect in BCC -Fe by molecular dynamics simulations N. Matsuda, S. Mori, T. Okita, Y. Watanabe 20th International Conference on Fusion Reactor Materials (ICFRM-20)
2021 JA Relaxation volume of irradiation-induced defects in pure iron: Molecular-statics calculation with linear elasticity theory X. Ruan, Y. Watanabe, K. Morishita, M. Ando, T. Nozawa 20th International Conference on Fusion Reactor Materials (ICFRM-20)
2021 JA Research activity to realize sound joints of reduced activation ferritic/martensitic steel F82H toward construction of ITER-TBM and DEMO H. Mori, H. Srizawa, T. Nozawa, H. Tanigawa 20th International Conference on Fusion Reactor Materials (ICFRM-20)
2021 JA Status and the challenge of Japanese materials property handbook to facilitate structural design criteria for DEMO in-vessel coponents T. Nozawa, H. Tanigawa, T. Kojima, T. Itoh, N. Hiyoshi, M. Ohata, T. Kato, M. Ando, M. Nakajima, T. Hirose, J. D. Reed, X. Chen, J. W. Geringer, Y. Katoh The 28th IAEA Fusion Energy Conference (FEC 2020)
2021 JA The impacts of irradiation damage and loading conditions to lifetimes of DEMO in-vessel components made with Ferritic/martensitic steels H. Tanigawa, X. Ruan, Y. Watanabe, M. Ando, T. Nozawa, Y. Katoh 20th International Conference on Fusion Reactor Materials (ICFRM-20)
2020 EU Advances in additive manufacturing of fusion materials H. Neuberger, Francisco A. Hernández, Michael Rieth, Simon Bonk, Ludek Stratil, Oliver Müller, Kai-Uwe Volker 31st Symposium on Fusion Technology (SOFT2020)
2020 EU/JA DEMO Structural Materials Qualification and Development M. Gorley, G. Aiello, J. Henry, T. Nozawa, G. Pintsuk, M. Rieth, H. Tanigawa 31st Symposium on Fusion Technology (SOFT2020)

T3 (Functional Materials)

Year PI Title Authors Conference
2022 EU Hydrogen trapping in intermetallic beryllium alloys P. Vladimirov, D. Bachurin, R. Gaisin, M. Dürrschnabel, C. Stihl 32nd Symposium on Fusion Technology (SOFT2022)
2022 EU Neutron irradiation programme for the EU reference ceramic tritium breeder material J. Leys, O. Leys, M. Ionescu-Bujor, R. Knitter 32nd Symposium on Fusion Technology (SOFT2022)
2022 JA Compatibility of tritium breeders and neutron multipliers as a mixture-packing concept of pebble bed blanket for JA DEMO fusion reactor Jae-Hwan Kim, Taehyun Hwang, Yutaka Sugimoto, Yoshiaki Akatsu, Suguru Nakano, Masaru Nakamichi 32nd Symposium on Fusion Technology (SOFT2022)
2022 JA Compression properties of beryllide pebbles at high temperatures Yoshiaki Akatsu, Jae-Hwan Kim, Taehyun Hwang, Suguru Nakano, Yutaka Sugimoto, Masaru Nakamichi 32nd Symposium on Fusion Technology (SOFT2022)
2022 JA Effect of the inside pressure of helium bubbles on the morphology and mobility in beryllium Yutaka Sugimoto, Jae-Hwan Kim, Taehyun Hwang, Kazutomo Hara, Mitsutaka Haruta, Hiroki Kurata, Mitsutaka Miyamoto, Masaru Nakamichi 32nd Symposium on Fusion Technology (SOFT2022)
2022 JA Tensile properties of titanium beryllium intermetallic compounds Taehyun Hwang, Jae-Hwan Kim, Yutaka Sugimoto, Yoshiaki Akatsu, Suguru Nakano, Masaru Nakamichi 32nd Symposium on Fusion Technology (SOFT2022)
2022 JA Tritium Release Behavior from Neutron-Irradiated Li2TiO3 with 20wt% Li2ZrO3 Pebbles　under Different Atmosphere Akito Ipponsugi, Kazunari Katayama, Tsuyoshi Hoshino 32nd Symposium on Fusion Technology (SOFT2022)
2021 JA Improvement of compatibility for advanced breeding functional materials J. Kim, T. Hwang, S. Nakano, M. Nakamichi 20th International Conference on Fusion Reactor Materials (ICFRM-20)
2021 JA Study of mechanical properties of beryllium intermetallic compounds fabricated by plasma sintering T. Hwang, J. Kim, S. Nakano, M. Nakamichi 20th International Conference on Fusion Reactor Materials (ICFRM-20)
2020 EU Discrete Element Analysis to characterize the thermo-mechanical behaviour of fusion pebble beds M. Moscardini, S. Pupeschi, Y. Gan, R. K. Annabattula, M. Kamlah 31st Symposium on Fusion Technology (SOFT2020)
2020 JA Improvement of compatibility in the breedering blanket by adavnced functional materials Sugur Nakano, Jae-Hwan Kim, Masaru Nakamichi 31st Symposium on Fusion Technology (SOFT2020)

T4 (Corrosion Database)

Year PI Title Authors Conference
2022 EU Aqueous Corrosion of WCLL Breeder Blanket Structural Material Eurofer-97 for Nuclear Fusion Reactors D. Kumar, R Burrows, L Platts, A Siberry, A Gunn, M Zimina, C Harrington, R Springell, T Martin, A Del Nevo Microscopy & Microanalysis 2022
2022 EU Modelling the Transport of Activated Corrosion Products in the WCLL-TBS PbLi Loop with the GETTHEM System-Level Code A. Froio, F. Lisanti, P. Arena, R. Bonifetto, A. Del Nevo, A. Froio, G. A. Spagnuolo, and R. Zanino 32nd Symposium on Fusion Technology (SOFT2022)
2022 JA Corrosion and stress corrosion behavior of CuCrZr alloy in high temperature pure water environment relevant to Japan’s DEMO divertor Yen-Jui Huang, Motoki Nakajima, Naofumi Nakazato, Hrinori Kurotaki, Hirotatsu Kishimoto, Takashi Nozawa 32nd Symposium on Fusion Technology (SOFT2022)
2021 EU Characteristics of diffusion coatings produced from aluminium electroplated on steel substrate C. Schroer, J. Lorenz 20th International Conference on Fusion Reactor Materials
2021 EU Chemical compatibility of alumina coatings by PLD and ALD in static and flowing Pb-16Li for DEMO Breeding Blanket S. Bassini, C. Ciantelli, A. Fiore, S. Cataldo, M. Ferri, A. Antonelli, A. Venturini, F. Papa, D. Martelli, M. Angiolini, B. Paladino, F. Di Fonzo, M. Utili 20th International Conference on Fusion Reactor Materials
2021 EU Protocol for PbLi eutectic alloy analysis and its relevance in fusion applications B Garcinuno, Rocío Fernández-Saavedra, Teresa Hernández, Alberto Quejido, David Rapisarda 20th International Conference on Fusion Reactor Materials
2021 EU Recent studies to the impact of ceramic breeder environment on the mechanical properties of EUROFER97 under operating conditions E Gaisina, M.Duerrschnabel, J.Leys, R.Knitter, J.Aktaa, M.Walter 20th International Conference on Fusion Reactor Materials
2021 JA Compatibility of tritium permeation barrier coatings in water cooled ceramic breeder blanket T. Chikada, M. Nakajima, A. Suzuki, S. Nakano, J. Kim, T. Otsuka, M. Hara, T. Nozawa, T. Hoshino, M. Nakamichi 20th International Conference on Fusion Reactor Materials (ICFRM-20)
2021 JA The incipient corrosion behavior of CuCrZr alloy in hydrogenated high-temperature water relevant to divertor cooling environment Y. Huang, M. Nakajima, T. Nozawa 20th International Conference on Fusion Reactor Materials (ICFRM-20)
2021 JA Water Corrosion behavior of RAFM and Cu-alloy for Japanese DEMO component M. Nakajima, Y. Huang, T. Nozawa 20th International Conference on Fusion Reactor Materials (ICFRM-20)
2020 JA Deuterium permeation through reduced activation ferritic steel F82H after exposure to high pressure water T. Chikada, K. Kimura, M. Nakajima, K. Nakamura, K. Okitsu, T. Tanaka, Y. Hishinuma, T. Otsuka, M. Hara, Y. Sakamoto, Y. Someya, H. Nakamura, T. Nozawa, The Joint Special Design Team for DEMO 3rd Asia Pacific Symposium on Tritium Science (APSOT-3)
2020 JA Tritium Permeation Behaviors through F82H into Pure Water at 353 K T. Otsuka, K. Hashizume, T. Nozawa, M. Nakajima 3rd Asia Pacific Symposium on Tritium Science (APSOT-3)

DEMO R&D activity based on the original procurement arrangements has been summarized in the final report of DEMO R&D activity in December 2017. Also, results of collaborative research on plasma-wall interactions in the JET-ILW experiment are summarized in the final report in December 2019. Herein, scientific and technological achievements related to BA DEMO R&D activity in 2012-2020 are presented. In total, 304 peer reviewed papers were published.

Year PI Title Authors DOI Journal name
2020 JA Compatibility of advanced tritium breeders and neutron multipliers J.-H. Kim, M. Nakamichi https://doi.org/10.1016/j.fusengdes.2020.111581 Fusion Engineering and Design
2020 EU&JA Comparison of Hydrogen Isotope Retention in Divertor Tiles of JET with the ITER-Like Wall Following Campaigns in 2011–2012 and 2015–2016 Y. Oya, S. Masuzaki, M. Tokitani, M. Nakata, F. Sun, M. Oyaidzu, K. Isobe, N. Asakura, T. Otsuka, A. M. Widdowson, J. Likonen, M. Rubel & JET Contributors https://doi.org/10.1080/15361055.2020.1716455 Fusion Science and Technology
2020 EU&JA Determination of retained tritium from ILW dust particles in JET N. Ashikawa Y. Torikai, N. Asakura, T. Otsuka, A. Widdowson, M. Rubel, M. Oyaidzu, M. Hara, S. Masuzaki, K. Isobe, Y. Hatano, K. Heinola, A. Baron-Wiechec, S. Jachmich, T. Hayashi and JET Contributors https://doi.org/10.1016/j.nme.2019.100673 Nuclear Materials and Energy
2020 EU&JA Surface morphology of the bulk tungsten divertor tiles from JET ITER-like wall: Microscopic analysis M. Tokitani, M. Miyamoto, S. Masuzaki, Y. Hatano, S.E. Lee, Y. Oya, T. Otsuka, M. Oyaidzu, H. Kurotaki, T. Suzuki, D. Hamaguchi, T. Hayashi, N. Asakura, A. Widdowson, S. Jachmich, M. Rubel and JET Contoributors https://doi.org/10.1088/1402-4896/ab3d09 Physica Scripta
2019 JA Effect of Hydrogen on Corrosion Properties of Reduced Activation Ferritic/Martensitic Steel, F82H M. Nakajima, T. Nozawa, H. Tanigawa https://doi.org/10.1016/j.fusengdes.2019.03.064 Fusion Engineering and Design
2019 JA Characterization of modified Be13Zr beryllide pebbles as advanced neutron multipliers J.-H. Kim, M. Nakamichi https://doi.org/10.1016/j.fusengdes.2019.04.054 Fusion Engineering and Design
2019 JA Effect of grain size on the sinterability and reactivity of vanadium-beryllium intermetallic compounds J.-H. Kim, M. Nakamichi https://doi.org/10.1016/j.fusengdes.2019.04.081 Fusion Engineering and Design
2019 JA Fabrication and characterization of Be12V pebbles with different diameters P. Kurinskiy, J.-H. Kim, M. Nakamichi https://doi.org/10.1016/j.fusengdes.2019.01.048 Fusion Engineering and Design
2019 JA Reactivity and thermal stability of ternary Be-Zr-V beryllides J.-H. Kim, M. Nakamichi https://doi.org/10.1016/j.fusengdes.2018.12.067 Fusion Engineering and Design
2019 JA Anomalous oxidation behavior in zirconium beryllium intermetallic compounds J.-H. Kim, M. Nakamichi https://doi.org/10.1016/j.jnucmat.2019.03.042 Journal of Nuclear Materials
2019 EU&JA Tritium distributions on W-coated divertor tiles used in the third JET ITER-like wall campaign Y. Hatano, S.E. Lee, J. Likonen, S. Koivuranta, M. Hara, S. Masuzaki, N. Asakura, K. Isobe, T. Hayashi, J. Ikonen, A. Widdowson and JET Contributors https://doi.org/10.1016/j.nme.2019.01.001 Nuclear Materials and Energy
2018 JA Specimen Size Effects on Fracture Behaviour of SiC/SiC Tubes During Circumferential Tensile Test J.-H. Yu, H. Kishimoto, N. Nakazato, J.S. Park and A. Kohyama https://doi.org/10.1080/09243046.2018.1510606 Advanced Composite Materials
2018 EU&JA Correlation of surface chemical states with hydrogen isotope retention in divertor tiles of JET with ITER-Like Wall Y. Oya, S. Masuzaki, M. Tokitani, K. Azuma, M. Oyaidzu, K. Isobe, N. Asakura, A. Widdowson, K. Heinola, S. Jachmich, M. Rubel and JET contributors https://doi.org/10.1016/j.fusengdes.2018.04.124 Fusion Engineering and Design
2018 EU&JA Dust Generation in Tokamaks: Overview of Beryllium and Tungsten Dust Characterisation in JET with the ITER-Like Wall M. Rubel, A. Widdowson, J. Grzonka, E. Fortuna-Zalesna, S. Moon, P. Petersson, N. Ashikawa, N. Asakura, D. Hamaguchi, Y. Hatano, K, Isobe, S. Masuzaki, H. Kurotaki, Y. Oya, M. Oyaizu, M. Tokitani and JET Contributors https://doi.org/10.1016/j.fusengdes.2018.03.027 Fusion Engineering and Design
2018 EU&JA Plasma-Wall Interaction on the Divertor Tiles of JET ITER-Like Wall from the Viewpoint of Micro/Nanoscopic Observations M. Tokitani, M. Miyamoto, S. Masuzaki, R. Sakamoto, Y. Oya, Y. Hatano, T. Otsuka, M. Oyaidzu, H. Kurotaki, T. Suzuki, D. Hamaguchi, K. Isobe, N. Asakura, A. Widdowson, K. Heinola, M. Rubeland JET Contributors https://doi.org/10.1016/j.fusengdes.2018.01.051 Fusion Engineering and Design
2018 EU&JA The effect of wall flow velocity on compatibility of high-purity SiC materials with liquid Pb-Li alloy by rotating disc testing for 3000 h up to 900 °C C. Park, T. Nozawa, R. Kasada, S. Tosti, S. Konishi, H. Tanigawa https://doi.org/10.1016/j.fusengdes.2018.03.042 Fusion Engineering and Design
2018 EU&JA Effect of heat treatment of titanium beryllide on tritium/hydrogen release V. Chakin, R. Rolli, R. Gaisin, R. Kurinskiy, J.-H. Kim, M. Nakamichi https://doi.org/10.1016/j.fusengdes.2018.09.005 Fusion Engineering and Design
2018 JA Effects of test environment on high temperature fatigue properties of reduced activation ferritic/martensitic steel, F82H T. Hirose, H. Sakasegawa, M. Nakajima, T. Kato, T　Miyazawa, H. Tanigawa https://doi.org/10.1016/j.fusengdes.2018.04.072 Fusion Engineering and Design
2018 JA Technical challenges on material and design criteria development for fusion in-vessel components H. Tanigawa https://doi.org/10.1016/j.fusengdes.2018.05.047 Fusion Engineering and Design
2018 JA Characterization of vanadium beryllide pebble bed for the Japan DEMO blanket application M. Nakamichi, J.-H. Kim, P. Kurinskiy https://doi.org/10.1016/j.fusengdes.2018.01.022 Fusion Engineering and Design
2018 JA Fabrication and characterization of Be-Zr-Ti ternary beryllide pebbles J.-H. Kim, M. Nakamichi https://doi.org/10.1016/j.fusengdes.2018.04.024 Fusion Engineering and Design
2018 JA Granulation of Be12V pebbles using the rotating electrode method P. Kurinskiy, J.-H. Kim, M. Nakamichi https://doi.org/10.1016/j.fusengdes.2018.09.011 Fusion Engineering and Design
2018 JA Evaluation of Li mass loss from Li2TiO3 with excess Li pebbles in water vapor atmosphere K. Katayama, H. Sakagawa, T. Hoshino, S. Fukada https://doi.org/10.1016/j.fusengdes.2018.02.032 Fusion Engineering and Design
2018 JA Li vaporization property of Li8ZrO6 and Li5AlO4 as tritium breeders K. Shin-mura, S. Honda, T. Hoshino, K. Sasaki https://doi.org/10.1016/j.fusengdes.2018.04.025 Fusion Engineering and Design
2018 JA Japanese activities of the R&D on silicon carbide composites in the broader approach period and beyond T. Nozawa, K. Ozawa, C. Park, J.S. Park, A. Kohyama, A. Hasegawa, S. Nogami, T. Hinoki, S. Kondo, T. Yano, T. Shibayama, B. Tsuchiya, T. Shikama, S. Nagata, T. Tanaka, H. Iwakiri, Y. Yamamoto, S. Konishi, R. Kasada, M. Kondo, T. Kunugi, T. Yokomine, Y. Ueki, N. Okubo, T. Taguchi, H. Tanigawa https://doi.org/10.1016/j.jnucmat.2018.05.045 Journal of Nuclear Materials
2018 JA Hot crack susceptibility in multi-pass welds of reduced activation ferritic/martensitic steel F82H H. Mori, H. Tanimura, R. Kiyoku, M. Fujiwara, H. Tanigawa https://doi.org/10.1016/j.jnucmat.2018.06.016 Journal of Nuclear Materials
2018 JA Investigation of instability of M23C6 particles in F82H steel under electron and ion irradiation conditions S. Kano, HL Yang, JJ Shen, ZS Zhao, J. McGrady, D. Hamaguchi, M. Ando, H. Tanigawa, H. Abe https://doi.org/10.1016/j.jnucmat.2018.02.004 Journal of Nuclear Materials
2018 JA Fabrication and characterizations of crushed titanium-beryllium intermetallic compounds J.-H. Kim, M. Nakamichi https://doi.org/10.1016/j.jnucmat.2017.10.043 Journal of Nuclear Materials
2018 EU&JA Tritium retention characteristic in dust particles in JET with ITER-like wall T. Otsuka, S. Masuzaki, N. Ashikawa, Y. Hatano, Y. Asakura, Tatsuya Suzuki, Takumi Suzuki, K. Isobe, T. Hayashi, M. Tokitani, Y. Oya, D. Hamaguchi, H. Kurotaki, R. Sakamoto, Hiroyasu Tanigawa, M. Nakamichi, A. Widdowson, M. Rubel and JET Contributors https://doi.org/10.1016/j.nme.2018.11.001 Nuclear Materials and Energy
2018 JA Mechanical properties of neutron irradiated F82H using micro-tensile testing M. Ando, H. Tanigawa, H. Kurotaki, Y. Katoh https://doi.org/10.1016/j.nme.2018.07.008 Nuclear Materials and Energy
2018 JA Micro-tensile testing of reduced-activation ferritic steel F82H irradiated with Fe and He ions T. Miura, K. Fujii, K. Fukuya, M. Ando, H. Tanigawa https://doi.org/10.1016/j.nme.2018.08.004 Nuclear Materials and Energy
2018 JA Microstructure of fatigue-tested F82H steel under multi-axial loadings K. Fukumoto, T Onitsuka, T Itoh, H Sakasegawa, H Tanigawa https://doi.org/10.1016/j.nme.2018.04.008 Nuclear Materials and Energy
2018 JA Effect of plasma sintering on densification and oxygen content of beryllium powder P. Kurinskiy, J.-H. Kim, M. Nakamichi https://doi.org/10.1016/j.nme.2018.11.003 Nuclear Materials and Energy
2018 JA Thermal properties of beryllides as advanced neutron multipliers for DEMO fusion application M. Nakamichi, J.-H. Kim, P. Kurinskiy, M. Nakamura https://doi.org/10.1016/j.nme.2018.02.002 Nuclear Materials and Energy
2017 EU Radiation induced deuterium absorption dependence on irradiation temperature, dose rate and gas pressure for SiC. E.R. Hodgson, A. Moroño and M. Malo, M. Verdu, F.J. Sanchez https://doi.org/10.1016/j.fusengdes.2017.02.081 Fusion Engineering and Design
2017 EU&JA Micro-/nano-characterization of the surface structures on the divertor tiles from JET ITER-Like Wall M. Tokitani, M. Miyamoto, S. Masuzaki, Y. Fujii, R. Sakamoto, Y. Oya, Y. Hatano, T. Otsuka, M. Oyaidzu, H. Kurotaki, T. Suzuki, D. Hamaguchi, K. Isobe, N. Asakura, A.M. Widdowson, M. Rubel and JET Contributors https://doi.org/10.1016/j.fusengdes.2017.01.002 Fusion Engineering and Design
2017 EU&JA Li4SiO4 based breeder ceramics with Li2TiO3, LiAlO2 and LiXLaYTiO3 additions, part I: Fabrication M.H.H. Kolb, K. Mukai, R. Knitter, T. Hoshino https://doi.org/10.1016/j.fusengdes.2016.12.033 Fusion Engineering and Design
2017 EU&JA Li4SiO4 based breeder ceramics with Li2TiO3, LiAlO2 and LiXLaYTiO3 additions, part II: Pebble properties M.H.H. Kolb, K. Mukai, R. Knitter, T. Hoshino https://doi.org/10.1016/j.fusengdes.2016.12.038 Fusion Engineering and Design
2017 JA Characterization of functional materials for liquid blanket systems by cathodoluminescence measurement T. Tanaka, D. Kato, T. Nozawa, B. Tsuchiya, T. Muroga https://doi.org/10.1016/j.fusengdes.2017.04.095 Fusion Engineering and Design
2017 JA Deuterium permeation and retention behaviors in erbium oxide-iron multilayer coatings S. Horikoshi, J. Mochizuki, C. Hu, Y. Oya, T. Chikada https://doi.org/10.1016/j.fusengdes.2017.03.123 Fusion Engineering and Design
2017 JA Deuterium permeation behavior in iron-irradiated erbium oxide coating T. Chikada, S. Horikoshi, J. Mochizuki, C. Hu, F. Koch, K. Yabuuchi, Y. Oya https://doi.org/10.1016/j.fusengdes.2017.01.016 Fusion Engineering and Design
2017 JA Deuterium permeation behavior of tritium permeation barrier coating containing carbide nanoparticles J. Mochizuki, S. Horikoshi, C. Hu, Y. Oya, T. Chikada https://doi.org/10.1016/j.fusengdes.2017.03.154 Fusion Engineering and Design
2017 JA Effect of irradiation hardening on brittle fracture performance of box-shaped blanket fabricated by F-82H T. Miyazawa, H. Tanigawa, M. Ohata https://doi.org/10.1016/j.fusengdes.2017.04.042 Fusion Engineering and Design
2017 JA Tensile properties of F82H steel after aging at 400-650 °C for 1,000-30,000 h T. Nagasaka, M. Ando, H. Tanigawa, H. Sakasegawa, T. Tanaka, T. Muroga, A. Sagara https://doi.org/10.1016/j.fusengdes.2017.04.119 Fusion Engineering and Design
2017 JA Deuterium retention and desorption properties of ternary beryllide pebbles as advanced neutron multipliers J.-H. Kim, M. Miyamoto, M. Nakamichi https://doi.org/10.1016/j.fusengdes.2017.04.037 Fusion Engineering and Design
2017 JA Development of beryllide pebbles with low-hydrogen generation as advanced neutron multipliers M. Nakamichi, J.-H. Kim https://doi.org/10.1016/j.fusengdes.2017.04.039 Fusion Engineering and Design
2017 JA Prevention of hydrogen generation reaction with water vapor by surface modification of beryllides as advanced neutron multipliers M. Nakamichi, J.-H. Kim https://doi.org/10.1016/j.fusengdes.2017.01.033 Fusion Engineering and Design
2017 JA Thermal analyses of beryllide pebbles in water vapor atmosphere as advanced neutron multipliers J.-H. Kim, M. Nakamichi https://doi.org/10.1016/j.fusengdes.2017.03.132 Fusion Engineering and Design
2017 JA Changes in mechanical property and microstructure of lithium metatitanate tritium breeder caused by thermal annealing Y. Otani, K. Shin-mura, S. Ogawa, T. Hoshino, K. Sasaki https://doi.org/10.1016/j.fusengdes.2017.03.158 Fusion Engineering and Design
2017 JA Li mass loss from Li2TiO3 with excess Li pebbles fabricated by optimized sintering condition R. Yamamoto, K. Katayama, T. Hoshino, T. Takeishi, S. Fukada https://doi.org/10.1016/j.fusengdes.2017.04.004 Fusion Engineering and Design
2017 JA Li vaporization properties of candidate materials for tritium breeder with high Li density K. Shin-mura, Y. Otani, S. Ogawa, T. Hoshino, K. Sasaki https://doi.org/10.1016/j.fusengdes.2017.04.053 Fusion Engineering and Design
2017 JA Japanese Fusion Materials Development Path to DEMO T. Muroga, H. Tanigawa https://doi.org/10.1080/15361055.2017.1330641 Fusion Science and Technology
2017 JA Recent R&D Results on Fusion Nuclear Technology for ITER and DEMO Reactor in Japan T. Yamanishi, N. Koizumi, M. Nakahira, Y. Nunoya, S. Siziki, H. Tobari, M. Kashiwagi, T. Isono, T. Inoue, M. Sugimoto, Y. Kusama, Y. Kawamura, H. Tanigawa, M. Nakamichi, T. Nozawa, T. Hoshino, Y. Ueda, Y. Hatano, T. Muroga, S. Fukada https://doi.org/10.1080/15361055.2017.1330625 Fusion Science and Technology
2017 JA Fatigue Properties of SiC/SiC Composites under Various Loading Modes S. Nogami, T. Nozawa, D. Kawai, W. Guan, A. Hasegawa https://doi.org/10.1080/15361055.2017.1333822 Fusion Science and Technology
2017 JA Experiment on recovery of hydrogen isotopes from Li17Pb83 blanket by liquid-gas contact M. Kinjo, S. Fukada, K. Katayama, Y. Edao, T. Hayashi https://doi.org/10.1080/15361055.2017.1293426 Fusion Science and Technology
2017 JA Using a Tritium Imaging Plate Technique to Measure the Hydrogen Solubility and Diffusivity of Zr-Doped BaInO2.5 K. Hashizume, Y. Oki https://doi.org/10.1080/15361055.2017.1291036 Fusion Science and Technology
2017 JA Reactivity and deuterium retention properties of titanium-beryllium intermetallic compounds J.-H. Kim, M. Miyamoto, Y. Hujii, M. Nakamichi https://doi.org/10.1016/j.intermet.2016.11.005 Intermetallics
2017 EU&JA Cutting edge of R and D in solid tritium breeder materials. Toward the ‘Solid’ blankets T. Hoshino, K. Mukai, M.H.H. Kolb, R. Knitter http://www.jspf.or.jp/Journal/PDF_JSPF/jspf2017_02/jspf2017_02-83.pdf Journal of Plasma and Fusion Research (in Japanese)
2017 EU&JA Analyses of microstructure, composition and retention of hydrogen isotopes in divertor tiles of JET with the ITER-like wall S. Masuzaki, M. Tokitani, T. Otsuka, Y. Oya, Y. Hatano, M. Miyamoto, R. Sakamoto, N. Ashikawa, S. Sakurada, Y. Uemura, K. Azuma, K. Yumizuru, M. Oyaizu, T. Suzuki, H. Kurotaki, D. Hamaguchi, H. Nakamura, K. Isobe, N. Asakura, A. Widdowson, K. Heinola, S. Jachmich, M. Rubel and JET contributors https://doi.org/10.1088/1402-4896/aa8bcc Physica Scripta
2017 EU&JA Tritium analysis of divertor tiles used in JET ITER-like wall campaigns by means of β-ray induced x-ray spectrometry Y. Hatano, K. Yumizuru, S. Koivuranta, J. Likonen, M. Hara, M. Matsuyama, S. Masuzaki, M. Tokitani, N. Asakura, K. Isobe, T. Hayashi, A. Baron-Wiechec, A. Widdowson and JET contributors https://doi.org/10.1088/1402-4896/aa8931 Physica Scripta
2016 JA Creep-fatigue life evaluation of high chromium ferritic steel under non-proportional loading T. Morishita, Y. Murakami, T. Itoh and H. Tanigawa https://doi.org/10.3221/IGF-ESIS.38.38 Fracture and structural integrity
2016 EU The reprocessing of advanced ceramic tritium breeder pebbles O. Leys, T. Bergfeldt, M.H.H. Kolb, R. Knitter, A.A. Goraieb https://doi.org/10.1016/j.fusengdes.2016.04.025 Fusion Engineering and Design
2016 EU&JA Recent technical progress on BA Program: DEMO activities and IFMIF/EVEDA T. Yamanishi, N.Asakura, K. Tobita, S. Ohira, G. Federici, R. Heidinger, J. Knaster, S. Clement, N. Nakajima, other BA IFERC and IFMIF/EVEDA contributors https://doi.org/10.1016/j.fusengdes.2015.12.045 Fusion Engineering and Design
2016 EU&JA Mechanical behavior of Be-Ti pebbles at blanket relevant temperatures R. Kurinskiy, R. Rolli, J.-H. Kim, M. Nakamichi https://doi.org/10.1016/j.fusengdes.2016.02.003 Fusion Engineering and Design
2016 JA Circumferential Tensile Test Method for Mechanical Property Evaluation of SiC/SiC Tube J.-H. Yu, H. Kishimoto, J.-S. Park, N. Nakazato, A. Kohyama https://doi.org/10.1016/j.fusengdes.2015.12.047 Fusion Engineering and Design
2016 JA Evaluation of thermal conductivity for liquid lead lithium alloys at various Li concentrations based on measurement and evaluation of density, thermal diffusivity and specific heat of alloys M. Kondo, Y. Nakajima, M. Tsuji, T. Nozawa https://doi.org/10.1016/j.fusengdes.2015.12.029 Fusion Engineering and Design
2016 JA Re-evaluation of SiC permeation coefficients at high temperatures Y. Yamamoto, Y. Murakami, H. Yamaguchi, T. Yamamoto, D. Yonetsu, K. Noborio, S. Konishi https://doi.org/10.1016/j.fusengdes.2015.12.041 Fusion Engineering and Design
2016 JA Hydrogen Permeation through Flinabe Fluoride Molten Salts for Blanket Candidates R. Nishiumi, S. Fukada, and A. Nakamura https://doi.org/10.1016/j.fusengdes.2015.10.035 Fusion Engineering and Design
2016 JA Release behavior of tritium in pure copper and its alloys into pure water at ambient temperature T. Otsuka, Y. Ogawa, H. Horinouchi, K. Hashizume https://doi.org/10.1016/j.fusengdes.2016.08.030 Fusion Engineering and Design
2016 JA Destructive and non-destructive evaluation methods of interface on F82H HIPed joints H. Kishimoto, Y. Muramatsu, Y. Asakura, T. Endo, A. Kohyama https://doi.org/10.1016/j.fusengdes.2015.10.008 Fusion Engineering and Design
2016 JA Evaluation of Impacts of Stress Triaxiality on Plastic Deformability of RAFM steel using various types of tensile specimen T. Kato, M. Ohata, S. Nogami, H. Tanigawa https://doi.org/10.1016/j.fusengdes.2015.11.003 Fusion Engineering and Design
2016 JA Mechanical Properties of F82H Plates with Different Thicknesses H. Sakasegawa, H. Tanigawa https://doi.org/10.1016/j.fusengdes.2015.10.017 Fusion Engineering and Design
2016 JA Beryllide pebble fabrication of Be-Zr compositions as advanced neutron multipliers M. Nakamichi, J.-H. Kim, K. Ochiai https://doi.org/10.1016/j.fusengdes.2015.10.018 Fusion Engineering and Design
2016 JA Synthesis and characteristics of ternary Be-Ti-V beryllide pebbles as advanced neutron multiplier J.-H. Kim, M.Nakamichi https://doi.org/10.1016/j.fusengdes.2015.09.015 Fusion Engineering and Design
2016 JA Synthesis and reactivity of single-phase Be17Ti2 intermetallic compounds J.-H. Kim, H. Iwakiri, T. Furugen, M. Nakamichi https://doi.org/10.1016/j.fusengdes.2015.10.034 Fusion Engineering and Design
2016 JA A New Blanket Tritium Recovery Experiment with Intense DT Neutron Source at JAEA/FNS K. Ochiai, Y. Edao, T. Hoshino, Y. Kawamura, M. Ohtaa, S. Kwon, C. Konno https://doi.org/10.1016/j.fusengdes.2016.01.002 Fusion Engineering and Design
2016 JA Evaluation of tritium release behavior from Li2TiO3 during DT neutron irradiation by use of an improved tritium collection method Y. Edao, Y. Kawamura, T. Hoshino, K. Ochiai https://doi.org/10.1016/j.fusengdes.2016.06.013 Fusion Engineering and Design
2016 JA Pebble Fabrication and Tritium Release Properties of Advanced Tritium Breeder T. Hoshino, Y. Edao, Y. Kawamura, K. Ochiai https://doi.org/10.1016/j.fusengdes.2016.01.012 Fusion Engineering and Design
2016 JA Progress of R&D on Water Cooled Ceramic Breeder for ITER test blanket system and DEMO Y. Kawamura, H. Tanigawa, T. Hirose, M. Enoeda, S. Sato, K. Ochiai, C. Konno, Y. Edao, T. Hayashi, T. Hoshino, M. Nakamichi, H. Tanigawa, H. Nishi, S. Suzuki, K. Ezato, Y. Seki, T. Yamanishi https://doi.org/10.1016/j.fusengdes.2015.11.002 Fusion Engineering and Design
2016 JA Synthesis of high-purity Li8ZrO6 powder by solid state reaction under hydrogen atmosphere K. Sin-mura, Y. Otani, S. Ogawa, E. Niwa, T. Hashimoto, T. Hoshino, K. Sasaki https://doi.org/10.1016/j.fusengdes.2015.10.009 Fusion Engineering and Design
2016 JA A new tritiated water measurement method with plastic scintillator E. Furuta, N. Iwasaki, Y. Kato and Y. Tomozoe https://doi.org/10.1080/10256016.2015.1133618 Isotopes in Environmental and Health Studies
2016 JA No-waste-measurement method with a LSC：effects of surface treatment for plastic scintillator E. Furuta, N. Iwasaki, R. Ohyama, S. Yokota, I. Mori, Y. Kato, K. Ogiwara https://doi.org/10.5453/jhps.50.119 Japaese Journal of Health Physics
2016 JA Hydrogen isotope dissolution, diffusion, and permeation in Er2O3 W. Mao, T. Chikada, A. Suzuki, T. Terai, H. Matsuzaki https://doi.org/10.1016/j.jpowsour.2015.10.091 Journal of Power Sources
2016 JA Experimental assessment of temperature distribution in heat affected zone (HAZ) in dissimilar joint between 8Cr-2W steel and SUS316L fabricated by 4 kW fiber laser welding S. Kano, A. Oba, H. Yang, Y. Matsukawa, Y. Satoh, H.i Serizawa, H. Sakasegawa, H. Tanigawa, H.i Abe https://doi.org/10.1299/mel.15-00481 Mechanical Engineering Letters
2016 EU Plasma etching to enhance the surface insulating stability of alumina for fusion applications M. Malo, A. Moroño and E.R. Hodgson https://doi.org/10.1016/j.nme.2016.05.008 Nuclear Materials and Energy
2016 EU Trapping and thermal diffusion for energetic deuterium implanted into SiC F.J. Sánchez, A. Moroño, M. Malo and E.R. Hodgson https://doi.org/10.1016/j.nme.2016.03.007 Nuclear Materials and Energy
2016 JA Comparison of Passivation behavior of SS316L with That of SS304 Stainless Steel in Tritiated Water Solution M. Oyaidzu, K. Isobe, T. Hayashi https://doi.org/10.1016/j.nme.2016.08.005 Nuclear Materials and Energy
2016 JA Crystallization and deuterium permeation behaviors of yttrium oxide coating prepared by metal organic decomposition T. Chikada, T. Tanaka, K. Yuyama, Y. Uemura, S. Sakurada, H. Fujita, X.C. Li, K. Isobe, T.i Hayashi, Y. Oya https://doi.org/10.1016/j.nme.2016.06.009 Nuclear Materials and Energy
2016 JA Deuterium retention in W and W-Re alloy irradiated with high energy Fe and W Ions: Effects of irradiation temperature Y. Hatano, K. Ami, V. Kh. Alimov, S. Kondo, T. Hinoki, T. Toyama, M. Fukuda, A. Hasegawa, K. Sugiyama, Y. Oya, M. Oyaidzu, T. Hayashi https://doi.org/10.1016/j.nme.2016.06.016 Nuclear Materials and Energy
2016 JA Surface modification and sputtering erosion of reduced activation ferritic martensitic steel F82H exposed to low-energy, high flux deuterium plasma V.Kh. Alimov, Y. Hatano, N. Yoshida, H. Watanabe, M. Oyaidzu, M. Tokitani, T. Hayashi https://doi.org/10.1016/j.nme.2016.01.001 Nuclear Materials and Energy
2016 JA Microstructure and mechanical property in heat affected zone (HAZ) in F82H joined with SUS316L by fiber laser welding S. Kano, A. Oba, H.L. Yang, Y. Matsukawa, Y. Satoh, H. Serizawa, H. Sakasegawa, H. Tanigawa, H. Abe https://doi.org/10.1016/j.nme.2016.08.004 Nuclear Materials and Energy
2016 JA Precipitation of carbides in F82H steels and its impact on mechanical strength S. Kano, H.L. Yang, R. Suzue, Y. Matsukawa, Y. Satoh, H. Sakasegawa, H. Tanigawa, H. Abe https://doi.org/10.1016/j.nme.2016.09.017 Nuclear Materials and Energy
2016 JA Fabrication and characterization of advanced neutron multipliers for DEMO blanket M. Nakamichi, J.-H. Kim, M. Miyamoto https://doi.org/10.1016/j.nme.2016.07.006 Nuclear Materials and Energy
2016 JA Hydrogen retention behavior of beryllides as advanced neutron multipliers Y. Fujii, M. Miyamoto, J.-H.Kim, M.Nakamichi, N. Murayoshi, H.Iwakiri https://doi.org/10.1016/j.nme.2016.03.001 Nuclear Materials and Energy
2016 JA Pebble fabrication of super advanced tritium breeders using a solid solution of Li2+xTiO3+y with Li2ZrO3 T. Hoshino https://doi.org/10.1016/j.nme.2016.05.004 Nuclear Materials and Energy
2016 JA Pebble structure change of Li2TiO3 with excess Li in water vapor atmosphere at elevated temperatures K. Katayama, M. Shimozori, T. Hoshino, R. Yamamoto, H. Ushida, S. Fukada https://doi.org/10.1016/j.nme.2016.05.006 Nuclear Materials and Energy
2016 EU&JA Tritium distributions on tungsten and carbon tiles used in the JET divertor Y. Hatano, K. Yumizuru, J. Likonen, S. Koivuranta, J. Ikonen and JET Contributors https://doi.org/10.1088/0031-8949/T167/1/014009 Physica Scripta
2016 JA Experimental study on chemical behaviors of non-metal impurities in Pb, Pb-Bi and Pb-Li by temperature programmed desorption mass spectrometer analysis M. Kondo, Y. Nakajima, T. Tanaka, T. Nozawa, T. Yokomine https://doi.org/10.1585/pfr.11.2405076 Plasma and Fusion Research
2015 JA A Plastic scintillation counter prototype E. Furuta, T. Kawano https://doi.org/10.1016/j.apradiso.2015.06.035 Applied Radiation and Isotopes
2015 EU Displacement damage effect on the radiation induced deuterium absorption for different types of SiC A. Moroño, E.R. Hodgson and M. Malo https://doi.org/10.1016/j.fusengdes.2015.04.062 Fusion Engineering and Design
2015 EU Oxidation recovery of radiation induced surface damage in aluminas: luminescence qualification M. Malo, A. Moroño and E.R. Hodgson https://doi.org/10.1016/j.fusengdes.2015.05.076 Fusion Engineering and Design
2015 EU Hot extrusion of Be-Ti powder P. Kurinskiy, H. Leiste, A.A. Goraieb, S. Mueller https://doi.org/10.1016/j.fusengdes.2015.04.037 Fusion Engineering and Design
2015 EU Activation calculations for multiple recycling of breeder ceramics by melt processing K. Mukai, P. Pereslavtsev, U. Fischer, R. Knitter https://doi.org/10.1016/j.fusengdes.2015.08.007 Fusion Engineering and Design
2015 JA Study on fabrication method of lithium alloys with metal grains Y. Nakajima, M. Kondo, T. Nozawa https://doi.org/10.1016/j.fusengdes.2015.06.184 Fusion Engineering and Design
2015 JA R&D activities of tritium technologies on Broader Approach in Phase 2-2 K. Isobe, Y. Kawamura, Y. Iwai, M. Oyaidzu, H. Nakamura, T. Suzuki, M. Yamada, Y. Edao, R. Kurata, T. Hayashi, T. Yamanishi https://doi.org/10.1016/j.fusengdes.2015.06.075 Fusion Engineering and Design
2015 JA Material properties of the F82H melted in an electric arc furnace H. Sakasegawa, H. Tanigawa, S. Kano, and H. Abe https://doi.org/10.1016/j.fusengdes.2015.06.103 Fusion Engineering and Design
2015 JA Mechanical properties of TIG and EB weld joints of F82H T. Hirose, H. Sakasegawa, M. Nakajima, H. Tanigawa https://doi.org/10.1016/j.fusengdes.2015.06.133 Fusion Engineering and Design
2015 JA Tensile properties of F82H steel after aging at 400-650°C for 100,000 h T. Nagasaka, H. Sakasegawa, H. Tanigawa, M. Ando, T. Tanaka, T. Muroga, A. Sagara https://doi.org/10.1016/j.fusengdes.2015.06.190 Fusion Engineering and Design
2015 JA Effect of titanium content on mechanical properties and reactivity of titanium beryllide pebbles J.-H. Kim, M. Nakamichi https://doi.org/10.1016/j.fusengdes.2015.06.170 Fusion Engineering and Design
2015 JA Fabrication and hydrogen generation reaction with water vapor of prototypic pebbles of binary beryllides as advanced neutron multiplier M. Nakamichi, J.-H. Kim https://doi.org/10.1016/j.fusengdes.2015.04.026 Fusion Engineering and Design
2015 JA Reactivity of plasma-sintered beryllium in dry air and moisture at high temperature J.-H. Kim, M. Nakamichi https://doi.org/10.1016/j.fusengdes.2015.08.012 Fusion Engineering and Design
2015 JA Experimental Investigation on Tritium Release from Lithium Titanate Pebble under High Temperature of 1073K K. Ochiai, Y. Edao, Y. Kawamura, T. Hoshino, M. Ohta, S. Sato, C. Konno https://doi.org/10.1016/j.fusengdes.2015.07.003 Fusion Engineering and Design
2015 JA Li Vaporization Property of Two-Phase Material of Li2TiO3 and Li2SiO3 for Tritium Breeder S. Ogawa, Y. Masuko, H. Kato, H. Yuyama, Y. Sakai, E. Niwa, T. Hashimoto, K. Mukai, T. Hoshino, K. Sasaki https://doi.org/10.1016/j.fusengdes.2015.01.042 Fusion Engineering and Design
2015 JA Optimization of sintering conditions of advanced tritium breeder pebbles fabricated by the emulsion method T. Hoshino https://doi.org/10.1016/j.fusengdes.2015.04.023 Fusion Engineering and Design
2015 JA Water vapor concentration dependence and temperature dependence of Li mass loss from Li2TiO3 with excess Li and Li4SiO4 M. Shimozori, K. Katayama, T. Hoshino, H. Ushida, R. Yamamoto, S. Fukada https://doi.org/10.1016/j.fusengdes.2015.03.015 Fusion Engineering and Design
2015 JA Correlation of rates of tritium migration through porous concrete S. Fukada, K. Katayama, T. Takeishi, Y. Edao, Y. Kawamura, T. Yamanishi https://doi.org/10.13182/FST14-T25 Fusion Science and Technology
2015 JA Effect of tritium on corrosion behavior of chromium in 0.01N sulfuric acid solution M. Oyaidzu, K. Isobe, T. Hayashi https://doi.org/10.13182/FST14-T69 Fusion Science and Technology
2015 JA Measurement of tritium with plastic scintillator: surface improvement with plasma treatment Y. Yoshihara, E. Furuta, R. Ohyama, S. Yokota, Y. Kato, T. Yoshimura, K. Ogiwara https://doi.org/10.13182/FST14-T103 Fusion Science and Technology
2015 JA Recent progress of tritium technology R&D for fusion reactor in JAEA T. Hayashi, H. Nakamura, Y. Kawamura, Y. Iwai, K. Isobe, M. Yamada, T. Suzuki, R. Kurata, M. Oyaidzu, Y. Edao, T. Yamanishi https://doi.org/10.13182/FST14-T31 Fusion Science and Technology
2015 JA Study on hydrogen isotopes permeation in the fluidized state of liquid lithium-lead S. Yoshimura, R. Yoshimura, M. Okada, S. Fukada, Y. Edao https://doi.org/10.13182/FST14-T104 Fusion Science and Technology
2015 JA Tritium retention in reduced-activation ferritic/martensitic steels Y. Hatano, V.Kh. Alimov, A.V. Spitsyn, N.P. Bobyr, D.I. Cherkez, S. Abe, O.V. Ogorodnikova, N.S. Klimov, B.I. Khripunov, A.V. Golubeva, V.M. Chernov, M. Oyaidzu, T. Yamanishi, M. Matsuyama https://doi.org/10.13182/FST14-T30 Fusion Science and Technology
2015 JA Evaluation of Tritium Release Properties of Advanced Tritium Breeders T. Hoshino, K. Ochiai, Y. Edao, Y. Kawamura https://doi.org/10.13182/FST14-T35 Fusion Science and Technology
2015 JA Comparative study of sinterability and thermal stability in plasma-sintered niovium and vanadium beryllides J.-H. Kim, M. Nakamichi https://doi.org/10.1016/j.jallcom.2015.03.105 Journal of Alloys and Compounds
2015 JA Synthesis of Be-Ti-V ternary beryllium intermetallic compounds J.-H. Kim, M. Nakamichi https://doi.org/10.1016/j.jallcom.2015.04.050 Journal of Alloys and Compounds
2015 EU Solution based synthesis of mixed-phase materials in the Li2TiO3 -Li4SiO4 system D. Hanaor, M. Kolb, Y. Gan, M. Kamlah, R. Knitter https://doi.org/10.1016/j.jnucmat.2014.09.028 Journal of Nuclear Materials
2015 EU&JA 2D tritium distribution on tungsten tiles used in JET ITER-like wall project Y. Hatano, A. Widdowson, N. Bekris, C. Ayres, A. Baron-Wieche, J. Likonen, S. Koivuranta, J. Ikonen and JET EFDA contributors https://doi.org/10.1016/j.jnucmat.2014.12.041 Journal of Nuclear Materials
2015 EU&JA Surface morphology changes and deuterium retention in Toughened, Fine-grained Recrystallized Tungsten under high-flux irradiation conditions M. Oya, H.T. Lee, Y. Ueda, H. Kurishita, M. Oyaidzu, T. Hayashi, N. Yoshida, T.W. Morgan, G. De Temmerman https://doi.org/10.1016/j.jnucmat.2014.11.124 Journal of Nuclear Materials
2015 JA Retention behaviors of tritium loaded near the surface region of metals by gas absorption and plasma implantation T. Otsuka, Y. Ogawa, M. Higaki, Y. Ishitani https://doi.org/10.1016/j.jnucmat.2014.11.038 Journal of Nuclear Materials
2015 JA Kinetic Monte Carlo simulation on influence of vacancy on hydrogen diffusivity in tungsten T. Oda, D. Zhu, Y. Watanabe https://doi.org/10.1016/j.jnucmat.2015.07.054 Journal of Nuclear Materials
2015 JA Deuterium permeation behavior for damaged tungsten by ion implantation Y. Oya, M. Sato, K. Yuyama, M. Oyaidzu, T. Hayashi, T. Yamanishi, K. Okuno https://doi.org/10.1080/00223131.2015.1052583 Journal of Nuclear Science and Technology
2015 JA The effect of point defects on diffusion pathway within α-Fe S. Sakuraya, K. Takahashi, N. Hashimoto, S. Ohnuki https://doi.org/10.1088/0953-8984/27/17/175007 Journal of Physics: Condensed Matter
2015 JA Influence of He implantation on deuterium trapping at defects induced in W by irradiation with MeV-range W ions V.Kh. Alimov, Y. Hatano, K. Sugiyama, B. Tyburska-Pueschel, M. Oya, Y. Ueda, K. Isobe, A. Hasegawa http://www.jspf.or.jp/JPFRS/PDF/Vol11/jpfrs2015_11-001.pdf Journal of Plasma and Fusion Research SERIES
2015 JA Recovery of Hydrogen Isotopes by Liquid-Gas Contactor from Li17Pb83 Blanket S. Fukada, T. Muneoka, R. Yoshimura, K. Katayama, Y. Edao and T. Hayashi http://www.jspf.or.jp/JPFRS/PDF/Vol11/jpfrs2015_11-019.pdf Journal of Plasma and Fusion Research SERIES
2015 EU Characterisation of Be-Ti rod fabricated by extrusion at 900C P. Kurinskiy, A. Moslang, H. Leiste, A.A. Goraieb, R. Rolli, S. Mueller http://dx.doi.org/10.5445/KSP/1000044741 KIT Scientific Reports
2015 JA Super-saturated hydrogen effects on radiation damages in tungsten under high-flux divertor plasma irradiation D. Kato, H. Iwakiri, Y. Watanabe, K. Morishita, T. Muroga https://doi.org/10.1088/0029-5515/55/8/083019 Nuclear Fusion
2015 JA Helium effects on microstructural change in RAFM steel under irradiation: Reaction rate theory modeling Y. Watanabe, K. Morishita, T. Nakasuji, M. Ando, H. Tanigawa https://doi.org/10.1016/j.nimb.2014.12.031 Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms
2015 JA Hydrogen Behavior in Primary Precipitate of F82H Steel: Atomistic Calculation Based on the Density Functional Theory Y. Watanabe, H. Iwakiri, N. Murayoshi, D. Kato, H. Tanigawa https://doi.org/10.1585/pfr.10.1205086 Plasma and Fusion Research
2015 JA Influence of Surface Roughness on Tensile Strength of Reduced-Activation Ferritic/Martensitic Steels Using Small Specimens S. Suzuki, S. Sato, M. Suzuki, H. Kinoshita, S. Sato, S. Jitsukawa, and H. Tanigawa https://doi.org/10.1520/STP157620140019 Small Specimen Test Techniques
2014 JA Measurement of tritium with high efficiency by using liquid scintillation counter with plastic scintillator E. Furuta, R. Ohyama, S. Yokota, T. Nakajyo, Y. Yamada, T. Kawano, T. Uda, Y. Watanabe https://doi.org/10.1016/j.apradiso.2014.04.001 Applied Radiation and Isotopes
2014 EU High-Speed Camera-based Analysis of the Lithium Ceramic Pebble Fabrication Process P. Waibel, J. Matthes, O. Leys, M. Kolb, H.B. Keller, R. Knitter https://doi.org/10.1002/ceat.201300769 Chemical Engineering & Technology
2014 EU In situ luminescence qualification of radiation damage in aluminas: F-aggregation and Al colloids M. Malo, A. Moroño and E.R. Hodgson. https://doi.org/10.1016/j.fusengdes.2014.02.034 Fusion Engineering and Design
2014 EU Radiation induced deuterium absorption for RB-SiC, HP-SiC, silicon and graphite loaded during electron irradiation T. Hernández, A. Moroño, E.R. Hodgson, M. Malo, M. Verdú and F.J. Sánchez. https://doi.org/10.1016/j.fusengdes.2014.06.006 Fusion Engineering and Design
2014 EU Characteristics of microstructure and tritium release properties of different kinds of beryllium pebbles for application in tritium breeding modules P. Kurinskiy, A. Moeslang, P. Vladimirov, R. Rolli, M. Zmitko https://doi.org/10.1016/j.fusengdes.2013.12.024 Fusion Engineering and Design
2014 EU Influence of chemisorption products of carbon dioxide and water vapour on radiolysis of tritium breeder A. Zarins, G. Kizane, A. Supe, M. Kolb, R. Knitter, J. Tiliks Jr., L. Baumane https://doi.org/10.1016/j.fusengdes.2014.01.005 Fusion Engineering and Design
2014 JA Blanket material and technology developments toward DEMO under the Broader Approach framework T. Nishitani, T. Yamanishi, H. Tanigawa, M. Nakamichi, T. Nozawa, T. Hoshino, K. Ochiai https://doi.org/10.1016/j.fusengdes.2014.01.075 Fusion Engineering and Design
2014 JA Evaluating the hydrogen isotope absorption/diffusion coefficient of CVD-SiC at high temperature Y. Yamamoto, T. Karasawa, Y. Murakami, S. Takemoto, D. Yonetsu, K. Noborio, S. Konishi https://doi.org/10.1016/j.fusengdes.2014.01.039 Fusion Engineering and Design
2014 JA Stress envelope of silicon carbide composites at elevated temperatures T. Nozawa, S. Kim, K. Ozawa, H. Tanigawa https://doi.org/10.1016/j.fusengdes.2013.12.032 Fusion Engineering and Design
2014 JA First-principles study of hydrogen adsorption and permeation in reconstructed cubic erbium oxide surfaces W. Mao, T. Chikada, A. Suzuki, T. Terai https://doi.org/10.1016/j.fusengdes.2014.03.019 Fusion Engineering and Design
2014 JA Hydrogen and water vapor adsorption properties on cation-exchanged mordenite for use to a tritium recovery system Y. Kawamura ,Y. Edao, Y. Iwai, T. Yamanishi https://doi.org/10.1016/j.fusengdes.2014.01.064 Fusion Engineering and Design
2014 JA Investigation on degradation mechanism of ion exchange membrane immersed into high-concentration tritiated water under the Broader Approach Activities Y. Iwai, K. Sato, T. Yamanishi https://doi.org/10.1016/j.fusengdes.2014.02.018 Fusion Engineering and Design
2014 JA Measurement of Hydrogen Isotope Concentration in Erbium Oxide Coatings R. Sato, T. Chikada, A. Suzuki, T. Terai, K. Sugiyama https://doi.org/10.1016/j.fusengdes.2014.01.074 Fusion Engineering and Design
2014 JA Trapping of deuterium dissolved in fluidized Li by Y S. Fukada, T. Hiromoto, S. Shigeharu, K. Sugie, Y. Edao https://doi.org/10.1016/j.fusengdes.2014.02.030 Fusion Engineering and Design
2014 JA Depth-dependent nanoindentation hardness of reduced-activation ferritic steels after MeV Fe-ion irradiation R. Kasada, S. Konishi, K. Yabuuchi, S. Nogami, M. Ando, D. Hamaguchi, H. Tanigawa https://doi.org/10.1016/j.fusengdes.2014.03.068 Fusion Engineering and Design
2014 JA Effect of potential factors in manufacturing process on mechanical properties of F82H H. Sakasegawa, H. Tanigawa, H. Tanigawa, and T. Hirose https://doi.org/10.1016/j.fusengdes.2014.02.024 Fusion Engineering and Design
2014 JA Radiological assessment of the limits and potential of reduced activation ferritic/martensitic steels H. Tanigawa, Y. Someya, H. Sakasegawa, T. Hirose, K. Ochiai https://doi.org/10.1016/j.fusengdes.2014.02.052 Fusion Engineering and Design
2014 JA Effect of plasma-sintering consolidation on reactvity of beryllium J.-H. Kim, M. Nakamichi https://doi.org/10.1016/j.fusengdes.2013.12.037 Fusion Engineering and Design
2014 JA Fabrication of beryllide pebble as advanced neutron multiplier M. Nakamichi, J.-H. Kim https://doi.org/10.1016/j.fusengdes.2014.02.081 Fusion Engineering and Design
2014 JA Interaction of titanium beryllide with steam at high temperatures K. Munakata, K. Wada, Y. Akimoto, H. Takeda, A. Nakamura, J.-H. Kim, M. Nakamichi https://doi.org/10.1016/j.fusengdes.2014.04.067 Fusion Engineering and Design
2014 JA DT neutron irradiation experiment for evaluation of tritium recovery from WCCB blanket K. Ochiai, Y. Kawamura, T. Hoshino, Yuki Edao, K. Takakura, M. Ohta, S. Sato, C. Konno https://doi.org/10.1016/j.fusengdes.2014.04.079 Fusion Engineering and Design
2014 JA Trial examination of direct pebble fabrication for advanced tritium breeders by the emulsion method T. Hoshino https://doi.org/10.1016/j.fusengdes.2013.12.052 Fusion Engineering and Design
2014 JA Development of advanced neutron multipliers for the DEMO blankets M. Nakamichi, J.-H. Kim https://doi.org/10.13182/FST13-745 Fusion Science and Technology
2014 JA Preliminary synthesis and mechanical property of titanium beryllide pebbles with different chemical compositions J.-H. Kim, M. Nakamichi https://doi.org/10.1016/j.jallcom.2013.09.103 Journal of Alloys and Compounds
2014 EU&JA Current status and recent research achievements in SiC/SiC composites Y. Katoh, L.L. Snead, C.H. Henager, T. Nozawa, T. Hinoki, A. Ivekovic, S. Novak, S.M. Gonzalez de Vincente https://doi.org/10.1016/j.jnucmat.2014.06.003 Journal of Nuclear Materials
2014 EU&JA Surface morphology and deuterium retention in tungsten and tungsten-rhenium alloy exposed to low-energy, high flux D plasma V.Kh. Alimov, Y. Hatano, K. Sugiyama, M. Balden, M. Oyaidzu, S. Akamaru, K. Tada, H. Kurishita, T. Hayashi, M. Matsuyama https://doi.org/10.1016/j.jnucmat.2014.07.064 Journal of Nuclear Materials
2014 JA Dynamic measurements of radiation-induced electrical-property modifications in CVD-SiC under fast-neutron irradiation B. Tsuchiya, T. Shikama, S. nagata, K. Saito, T. Nozawa https://doi.org/10.1016/j.jnucmat.2014.08.057 Journal of Nuclear Materials
2014 JA Evaluation of damage accumulation behavior and strength anisotropy of NITE SiC/SiC composites by acoustic emission, digital image correlation and electrical resistivity monitoring T. Nozawa, K. Ozawa, Y. Asakura, A. Kohyama, H. Tanigawa https://doi.org/10.1016/j.jnucmat.2014.08.043 Journal of Nuclear Materials
2014 JA Irradiation creep of 3C–SiC and microstructural understanding of the underlying mechanisms S. Kondo, T. Koyanagi, T. Hinoki https://doi.org/10.1016/j.jnucmat.2013.09.004 Journal of Nuclear Materials
2014 JA Retention and thermal release behavior of deuterium and helium implanted in SiC Y. Ishikawa, S. Nagata, M. Zhao, T. Shikama https://doi.org/10.1016/j.jnucmat.2014.08.015 Journal of Nuclear Materials
2014 JA Hydrogen diffusion along grain boundaries in erbium oxide coatings W. Mao, T. Chikada, A. Suzuki, T. Terai https://doi.org/10.1016/j.jnucmat.2014.06.063 Journal of Nuclear Materials
2014 JA Effect of He implantation on fracture behavior and microstructural evolution in F82H K. Yabuuchi, K. Satoh, S. Nogami, A. Hasegawa, M. Ando, and H. Tanigawa https://doi.org/10.1016/j.jnucmat.2014.09.018 Journal of Nuclear Materials
2014 JA Mechanism of instability of carbides in Fe–TaC alloy under high energy electron irradiation at 673 K H. Abe, T. Ishizaki, S. Kano, F. Li, Y. Satoh, T. Mtsunaga, H. Tanigawa, D. Hamaguchi, T. Nagase, H. Yasuda https://doi.org/10.1016/j.jnucmat.2014.08.032 Journal of Nuclear Materials
2014 JA Effect of grain size on the hardness and reactivity of plasma-sintered beryllium J.-H. Kim, M. Nakamichi https://doi.org/10.1016/j.jnucmat.2014.06.019 Journal of Nuclear Materials
2014 JA Reactivity of plasma-sintered beryllium–titanium intermetallic compounds with water vapor J.-H. Kim, M. Nakamichi https://doi.org/10.1016/j.jnucmat.2014.03.026 Journal of Nuclear Materials
2014 JA Radiation-induced electrical degradation under gamma-ray and neutron irradiations B. Tsuchiya http://www.jspf.or.jp/Journal/PDF_JSPF/jspf2014_01/jspf2014_01-47.pdf Journal of Plasma and Fusion Research (in Japanese)
2014 JA Laser Beam Welding for Reduced Activation Ferritic/Martensitic Steel F82H H. Mori, H. Ogiwara, K. Saida, H. Serizawa, T. Hirose and H. Tanigawa https://doi.org/10.4028/www.scientific.net/MSF.783-786.2771 Materials Science Forum
2014 EU&JA Surface Modification and Deuterium Retention in Reduced Activation Ferritic Martensitic Steels Exposed to Low-Energy, High Flux D Plasma and D2 Gas V.Kh. Alomov, Y. Hatano, K. Sugiyama, M. Balden, T. Höschen, M. Oyaidzu, J. Roth, J. Dorner, M. Fußeder, T. Yamanishi https://doi.org/10.1088/0031-8949/2014/T159/014049 Physica Scripta
2014 JA Deuterium Retention in various Toughened, Fine-Grained Recrystallized Tungsten materials under different irradiation conditions M. Oya, H.T. Lee, Y. Ohtsuka, Y. Ueda, H. Kurishita, K. Sugiyama, M. Oyaidzu and T. Yamanishi https://doi.org/10.1088/0031-8949/2014/T159/014048 Physica Scripta
2013 JA Effects of Tritiated Water on Passivation Behavior of SUS304 Stainless Steel M. Oyaidzu, K. Isobe and T. Yamanishi https://doi.org/10.1149/05050.0063ecst ECS Transaction
2013 EU Design and manufacture of an oven for high temperature experiments of erosion–corrosion of SiCf/SiC into LiPb S. Tosti, A. Moriani, A. Santucci https://doi.org/10.1016/j.fusengdes.2013.05.017 Fusion Engineering and Design
2013 EU Ion bombardment induced surface electrical degradation monitoring by means of luminescence in aluminas. M. Malo, A. Moroño, E.R. Hodgson https://doi.org/10.1016/j.fusengdes.2013.03.013 Fusion Engineering and Design
2013 EU Radiation enhanced deuterium absorption for Al2O3 and macor ceramic. A. Moroño, E.R. Hodgson, M. Malo https://doi.org/10.1016/j.fusengdes.2013.05.020 Fusion Engineering and Design
2013 EU Effect of warm pre-stressing on fracture toughness of Eurofer97 steel N. Ilchuk, L. Commin, P. Spätig, G. R. Odette https://doi.org/10.1016/j.fusengdes.2013.05.056 Fusion Engineering and Design
2013 EU Characteristics of microstructure, swelling and mechanical behavior of titanium beryllide samples after high-dose neutron irradiation at 740 and 873 K P. Kurinskiy, A. Moeslang, V. Chakin, M. Klimenkov, R. Rolli, S. van Til, A.A. Goraieb https://doi.org/10.1016/j.fusengdes.2013.05.084 Fusion Engineering and Design
2013 EU&JA Progress and achievements of the BA activities in Rokkasho T. Nishitani, M. Sugimoto, S. Ohira, T. Yamanishi, H. Tanigawa, M. Nakamichi, K. Tobita, Y. Ishii, T. Ozeki, N. Nakajima, H. Matsumoto, Y. Okumura, J. Knaster https://doi.org/10.1016/j.fusengdes.2013.01.085 Fusion Engineering and Design
2013 JA Re-defining failure envelopes for silicon carbide composites based on damage process analysis by acoustic emission T. Nozawa, K. Ozawa, H. Tanigawa https://doi.org/10.1016/j.fusengdes.2013.05.054 Fusion Engineering and Design
2013 JA Adsorption Rate of Hydrogen Isotopes on Ca-Mordenite Y. Kawamura, Y. Edao, T. Yamanishi https://doi.org/10.1016/j.fusengdes.2013.05.021 Fusion Engineering and Design
2013 JA Demonstration on endurance of ion exchange membrane immersed into high-concentration tritiated water under the Broader Approach Activities Y. Iwai, K. Sato, Y. Kawamura, T. Yamanishi https://doi.org/10.1016/j.fusengdes.2013.05.051 Fusion Engineering and Design
2013 JA Formation of lithium-tritide by hot atom reactions of tritium produced in Pb-16Li K. Okuno, M. Kobayashi, T. Yamanishi, Y. Oya https://doi.org/10.1016/j.fusengdes.2013.03.064 Fusion Engineering and Design
2013 JA Recent results on tritium technology in JAEA under BA program T. Yamanishi, Y. Kawamura, Y. Iwai, K. Isobe https://doi.org/10.1016/j.fusengdes.2013.04.046 Fusion Engineering and Design
2013 JA Analysis on precipitation behavior of reduced activation ferritic/martensitic steels with extraction residue tests T. Nagasaka, Y. Hishinuma, T. Muroga, H. Watanabe, H. Sakasegawa, H. Tanigawa, M. Ando https://doi.org/10.1016/j.fusengdes.2013.05.037 Fusion Engineering and Design
2013 JA Technical issues of fabrication technologies of reduced activation ferritic/martensitic steels H. Tanigawa, H. Sakasegawa, T. Hirose https://doi.org/10.1016/j.fusengdes.2013.05.090 Fusion Engineering and Design
2013 JA Novel granulation process of beryllides as advanced neutron multipliers M. Nakamichi, J.-H. Kim, K. Yonahera https://doi.org/10.1016/j.fusengdes.2013.02.077 Fusion Engineering and Design
2013 JA Oxidation property and homogenization treatment of plasma sintered beryllides J.-H. Kim, M. Nakamichi https://doi.org/10.1016/j.fusengdes.2013.03.052 Fusion Engineering and Design
2013 JA Development of fabrication technologies for advanced tritium breeder pebbles by the sol–gel method T. Hoshino https://doi.org/10.1016/j.fusengdes.2013.05.025 Fusion Engineering and Design
2013 JA Mass loss of Li2TiO3 pebbles and Li4SiO4 pebbles H. Kashimura, M. Nishikawa, K. Katayama, S. Matsuda, M. Shimozori, S. Fukada, T. Hoshino https://doi.org/10.1016/j.fusengdes.2013.05.098 Fusion Engineering and Design
2013 JA Sorption and desorption behavior of tritiated water on lithium titanate with additional Li K. Katayama, H. Kashimura, T. Hoshino, T. Takeishi, S. Matsuda, M. Nishikawa, S. Fukada https://doi.org/10.1016/j.fusengdes.2013.05.041 Fusion Engineering and Design
2013 JA Trial synthesis of Li2Be2O3 for high-functional tritium breeders T. Hoshino, F. Oikawa, Y. Natori, K. Kato, T. Sakka, M. Nakamura, K. Tatenuma https://doi.org/10.1016/j.fusengdes.2013.05.013 Fusion Engineering and Design
2013 JA Overall Hydrogen Permeation through Fluidized PbLi Alloy under Natural Convection S. Fukada, M. Okada, Y. Edao, H. Okitsu, S. Yoshimura https://doi.org/10.13182/FST13-A19163 Fusion Science and Technology
2013 JA Comparative study on arc-melted and plasma-sintered beryllides J.-H. Kim, M. Nakamichi https://doi.org/10.1016/j.jallcom.2012.08.098 Journal of Alloys and Compounds
2013 JA Optimization of synthesis conditions for plasma-sintered beryllium-titanium intermetallic compounds J.-H. Kim, M. Nakamichi https://doi.org/10.1016/j.jallcom.2013.04.185 Journal of Alloys and Compounds
2013 JA Sinterability and mechanical properties of plasma-sintered beryllides with different Ti contents J.-H. Kim, M. Nakamichi https://doi.org/10.1016/j.jallcom.2012.12.149 Journal of Alloys and Compounds
2013 EU Radiation enhanced diffusion and redistribution of helium in LiNbO3 A. Moroño, E.R. Hodgson https://doi.org/10.1016/j.jnucmat.2013.02.052 Journal of Nuclear Materials
2013 EU Radioluminescence characterization of SiC and SiC/SiC for 1.8 MeV electron irradiation M. Malo, A. Moroño and E.R. Hodgson, https://doi.org/10.1016/j.jnucmat.2012.10.036 Journal of Nuclear Materials
2013 EU Radioluminescence monitoring of radiation Induced surface electrical degradation in aluminas M. Malo, A. Moroño, E.R. Hodgson, https://doi.org/10.1016/j.jnucmat.2012.11.052 Journal of Nuclear Materials
2013 EU Characterization of ODS (Oxide Dispersion Strengthened) Eurofer/Eurofer dissimilar electron beam welds L. Commin, M. Rieth, V. Widak, R. Lindau https://doi.org/10.1016/j.jnucmat.2012.11.019 Journal of Nuclear Materials
2013 EU Fracture toughness characterization in the lower transition of neutron irradiated Eurofer97 steel. N. Ilchuk, P. Spätig, G. R. Odette https://doi.org/10.1016/j.jnucmat.2013.01.002 Journal of Nuclear Materials
2013 EU Helium bubble morphology of boron alloyed EUROFER97 after neutron irradiation M. Klimenkov, A. Möslang, E. Materna-Morris, H.-C. Schneider https://doi.org/10.1016/j.jnucmat.2013.04.022 Journal of Nuclear Materials
2013 EU On determination of the constitutive behavior of tempered martensitic steels from micro-indentations: Application to Eurofer97 steel P. Spätig, N. Ilchuk https://doi.org/10.1016/j.jnucmat.2013.01.003 Journal of Nuclear Materials
2013 EU Tensile and low cycle fatigue properties of EUROFER97-steel after 16.3dpa neutron irradiation at 523, 623 and 723K E. Materna-Morris, A. Möslang, H.-C. Schneider https://doi.org/10.1016/j.jnucmat.2013.03.038 Journal of Nuclear Materials
2013 EU Tritium Release and Retention Properties of Highly Neutron Irradiated Beryllium Pebbles from HIDOBE-01 Experiment V. Chakin, A. Moeslang, P. Vladimirov, P. Kurinskiy, R. Rolli, H.-C. Schneider, S. van Til, J.B.J. Hegeman, M. Zmitko https://doi.org/10.1016/j.jnucmat.2013.03.032 Journal of Nuclear Materials
2013 EU Fabrication of modified lithium orthosilicate pebbles by addition of titania R. Knitter, M.H.H. Kolb, U. Kaufmann, A.A. Goraieb https://doi.org/10.1016/j.jnucmat.2012.10.034 Journal of Nuclear Materials
2013 EU&JA Deuterium retention in Toughened, Fine-Grained Recrystallized Tungsten M. Oya, K. Uekita, H.T. Lee, Y. Ohtsuka, Y. Ueda, H. Kurishita, A. Kreter, J.W. Coenen, V. Philipps, S. Brezinsek, A. Litnovsky, K. Sugiyama, Y. Torikai https://doi.org/10.1016/j.jnucmat.2013.01.230 Journal of Nuclear Materials
2013 EU&JA Recent Progress of R&D Activities on Reduced Activation Ferritic/Martensitic Steels Q. Huang, N. Baluc, Y. Dai, S. Jitsukawa, A. Kimura, R.J. Kurtz, R. Lindau, T. Muroga, G.R. Odette, B. Raj, R.E. Stollek, L. Tan, H. Tanigawa, A.-A.F. Tavassoli, F. Wan, Y. Wu https://doi.org/10.1016/j.jnucmat.2012.12.039 Journal of Nuclear Materials
2013 EU&JA Recent developments of solid breeder fabrication R. Knitter, P. Chaudhuri, Y.J. Feng, T. Hoshino, I.-K. Yu https://doi.org/10.1016/j.jnucmat.2013.02.060 Journal of Nuclear Materials
2013 JA Recovery behavior of point defects after low-dose neutron irradiation at ∼423 K of sintered 6H–SiC by lattice parameter and macroscopic length measurements T. Yano, Y. Futamura, S. Yamazaki, T. Sawabe and K. Yoshida https://doi.org/10.1016/j.jnucmat.2013.01.296 Journal of Nuclear Materials
2013 JA Effect of Cation Exchange on Hydrogen Adsorption Property of Mordenite for Isotope Separation Y. Kawamura, Y. Iwai, K. Munakata, T. Yamanishi https://doi.org/10.1016/j.jnucmat.2012.11.003 Journal of Nuclear Materials
2013 JA Retention and Release Mechanisms of Tritium in Plasma-Sprayed Tungsten Coatings Exposed to Plasma T. Otsuka, T. Tanabe and K. Tokunaga https://doi.org/10.1016/j.jnucmat.2013.01.229 Journal of Nuclear Materials
2013 JA Study on kinetics of hydrogen dissolution and hydrogen solubility in oxides using imaging plate technique K. Hashizume, K. Ogata, M. Nishikawa, T. Tanabe, S. Abe, S. Akamaru, Y. Hatano https://doi.org/10.1016/j.jnucmat.2013.05.038 Journal of Nuclear Materials
2013 JA Application of master curve method to the evaluation of fracture toughness of F82H steels B.J. Kim, R. Kasada, A. Kimura, E. Wakai, H. Tanigawa https://doi.org/10.1016/j.jnucmat.2013.03.079 Journal of Nuclear Materials
2013 JA Dependence of precipitate formation on normalizing temperature and its impact on the heat treatment of F82H-BA07 Steel K. Fukumoto, T. Sakaguchi, K. Inoue, T. Itoh, H. Sakasegawa and H. Tanigawa https://doi.org/10.1016/j.jnucmat.2013.02.065 Journal of Nuclear Materials
2013 JA Development of fatigue life evaluation method using small specimen S. Nogami, A. Nishimura, E. Wakai, H. Tanigawa, T. Itoh, A. Hasegawa https://doi.org/10.1016/j.jnucmat.2013.05.051 Journal of Nuclear Materials
2013 JA Microsegregation in a F82H plate H. Sakasegawa and H. Tanigawa https://doi.org/10.1016/j.jnucmat.2013.01.322 Journal of Nuclear Materials
2013 JA Nanoindentation hardness and its extrapolation to bulk-equivalent hardness of F82H steels after single- and dual-ion beam irradiation Y. Takayama, R. Kasada, Y. Sakamoto, K. Yabuuchi, A. Kimura, M. Ando, D. Hamaguchi, H. Tanigawa https://doi.org/10.1016/j.jnucmat.2012.12.033 Journal of Nuclear Materials
2013 JA Numerical study of local PWHT condition for EB welded joint between first and side walls in ITER-TBM H. Serizawa, S. Nakamura, H. Tanigawa, H. Ogiwara, H. Murakawa https://doi.org/10.1016/j.jnucmat.2012.12.051 Journal of Nuclear Materials
2013 JA Oxide formation and precipitation behaviors on interface of F82H steel joints during HIPing and hot pressing H. Kishimoto, T. Ono, H. Sakasegawa, H. Tanigawa, M. Ando, T. Shibayama, Y. Kohno, A. Kohyama https://doi.org/10.1016/j.jnucmat.2013.03.003 Journal of Nuclear Materials
2013 JA Toughness characterization by small specimen test technique for HIPed joints of F82H steel aiming at first wall fabrication in fusion H. Kishimoto, T. Ono, H. Sakasegawa, H. Tanigawa, Y. Kohno, A. Kohyama https://doi.org/10.1016/j.jnucmat.2013.05.044 Journal of Nuclear Materials
2013 JA Homogenization treatment to stabilize the compositional structure of beryllide pebbles M. Nakamichi, J.-H. Kim https://doi.org/10.1016/j.jnucmat.2013.02.070 Journal of Nuclear Materials
2013 JA Oxidation behavior of plasma sintered beryllium-Titanium intermetallic compounds as an advanced neutron multiplier J.-H. Kim, M. Nakamichi https://doi.org/10.1016/j.jnucmat.2013.02.066 Journal of Nuclear Materials
2013 JA Oxidation resistance of Be12Ti fabricated by plasma-sintering method K. Wada, K. Munakata, J.-H Kim, K. Yonehara, D. Wakai, M. Nakamichi https://doi.org/10.1016/j.jnucmat.2013.04.093 Journal of Nuclear Materials
2013 JA Preliminary characterization of plasma sintered beryllides as advanced neutron multiplier M. Nakamichi. K. Yonehara, K. Munakata, T. Shibayama, M. Miyamoto https://doi.org/10.1016/j.jnucmat.2012.11.011 Journal of Nuclear Materials
2013 JA The effect of sintering time on synthesis of plasma sintered beryllides J.-H. Kim, M. Nakamichi https://doi.org/10.1016/j.jnucmat.2012.10.013 Journal of Nuclear Materials
2013 JA Development of methods for reprocessing and reuse of tritium breeder materials in broader approach activities T. Hoshino https://doi.org/10.1016/j.jnucmat.2013.03.009 Journal of Nuclear Materials
2013 JA Vaporization property and crystal structure of lithium metatitanate with excess Li K. Mukai, K. Sasaki, T. Terai, A. Suzuki, T. Hoshino https://doi.org/10.1016/j.jnucmat.2013.04.050 Journal of Nuclear Materials
2013 JA Flibe-tritium research for fission or fusion reactors at Kyushu University S. Fukada http://www.jspf.or.jp/JPFRS/PDF/Vol10/jpfrs2013_10-022.pdf Journal of Plasma and Fusion Research SERIES
2013 JA Tritium distribution on the tungsten surface exposed to deuterium plasma K. Isobe, V. Kh. Alomov, A. Taguchi, M. Saito, Y. Torikai, Y. Hatano, T. Yamanishi http://www.jspf.or.jp/JPFRS/PDF/Vol10/jpfrs2013_10-081.pdf Journal of Plasma and Fusion Research SERIES
2013 JA Hydrogen generation property on the surface of plasma sintered Be12Ti K. Wada, K. Munakata, Y. Akimoto, H. Takeda, J.-H. Ki, D. Wakai, K. Yonehra, M. Nakamichi http://www.jspf.or.jp/JPFRS/PDF/Vol10/jpfrs2013_10-098.pdf Journal of Plasma and Fusion Research SERIES
2013 JA Mass loss of Li2TiO3 pebbles in atmosphere containing hydrogen H. Kashimura, M. Nishikawa, K. Katayama, S. Matsuda, S. Fukada, T. Hoshino http://www.jspf.or.jp/JPFRS/PDF/Vol10/jpfrs2013_10-018.pdf Journal of Plasma and Fusion Research SERIES
2013 JA Clarification of Tritium Behavior in Pb-Li Blanket System (Overview) S. Fukada, T. Terai, S. Konishi, K. Katayama, T. Chikada, Y. Edao, T. Muroga, M. Shimada, B. Merrill, D.K. Sze https://doi.org/10.2320/matertrans.MG201203 Materials Transaction
2013 JA Displacement damage rate dependence of defect cluster formation in alpha iron during irradiation Y. Watanabe, K. Morishita, Y. Yamamoto, D. Hamaguchi, H. Tanigawa https://doi.org/10.1016/j.nimb.2013.01.044 Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms
2013 EU Microstructure Analysis of Melt-based Lithium Orthosilicate/Metatitanate Pebbles. O. Leys, C. Odemer, U. Maciejewski, M.H.H. Kolb, R. Knitter https://doi.org/10.3139/147.110194 Practical Metallography
2013 JA Basic Numerical Study on Gap Influence of Residual Stress and Distortion during High-Brightness Laser Butt Welding H. Serizawa, D. Mori and H. Murakawa http://www.jwri.osaka-u.ac.jp/publication/trans-jwri/pdf/422-09.pdf Transactions of JWRI
2012 JA Characterization of Failure Behavior of Silicon Carbide Composites by Acoustic Emission T. Nozawa, K. Ozawa, H. Tanigawa https://doi.org/10.1002/9781118217535.ch7 Ceramic Engineering and Science Proceedings
2012 EU X-Ray Study of Surface Layers of Air-Annealed Be12Ti and Be12V samples using synchrotron radiation P. Kurinskiy, A. Moeslang, V. Chakin, T. Slobodskyy, A.A. Minkevich, T. Baumbach, Ch. Dorn, A.A. Goraieb https://doi.org/10.1016/j.fusengdes.2012.02.047 Fusion Engineering and Design
2012 EU&JA Progress of Fusion Nucleear Technologies in the Broader Approach Framework T. Nishitani, P. Garin, M. Sugimoto, N. Nakajima, R. Heidinger, H. Kimura, K. Okano, K. Tobita, T. Yamanshi, G. Federici, N. Baluc and other BA IFERC and IFMIF/EVEDA contributors https://doi.org/10.1016/j.fusengdes.2012.01.018 Fusion Engineering and Design
2012 JA Determination and prediction of axial/off-axial mechanical properties of SiC/SiC composites T. Nozawa, K. Ozawa, Y.B. Choi, A. Kohyama, H. Tanigawa https://doi.org/10.1016/j.fusengdes.2012.02.026 Fusion Engineering and Design
2012 JA Analysis of diffusion and dissolution of two-component hydrogen (H+D) in lead lithium H. Okitsu, Y. Edao, M. Okada, S. Fukada https://doi.org/10.1016/j.fusengdes.2012.03.004 Fusion Engineering and Design
2012 JA Effect of surface oxide layer on deuterium permeation behaviors through a type 316 stainless steel Y. Oya, M. Kobayashi, J. Osuo, M. Suzuki, A. Hamada, K. Matsuoka, Y. Hatano, M. Matsuyama, T. Hayashi, T. Yamanishi, and K. Okuno https://doi.org/10.1016/j.fusengdes.2012.01.025 Fusion Engineering and Design
2012 JA Measurement of Tritium concentration in water with imaging plate Y. Hatano, M. Hara, H. Ohuchi, H. Nakamura, T. Yamanishi https://doi.org/10.1016/j.fusengdes.2012.02.057 Fusion Engineering and Design
2012 JA Overview of R&D Activities on Tritium Processing and Handling Technology in JAEA T. Yamanishi, H. Nakamura, Y. Kawamura, Y. Iwai, K. Isobe, M. Oyaidsu, M. Yamada, T. Suzuki, and T. Hayashi https://doi.org/10.1016/j.fusengdes.2012.02.043 Fusion Engineering and Design
2012 JA Evaluation of local deformation behavior accompanying fatigue damage in F82H welded joint specimens by using digital image correlation T. Nakata, H. Tanigawa https://doi.org/10.1016/j.fusengdes.2012.01.048 Fusion Engineering and Design
2012 JA Development of a synthesis method of beryllides as advanced neutron multiplier for DEMO reactors M. Nakamichi, J.-H. Kim, D. Wakai, K. Yonehara https://doi.org/10.1016/j.fusengdes.2012.02.053 Fusion Engineering and Design
2012 JA Development of fabrication technologies for advanced breeding functional materials For DEMO reactors T. Hoshino, M. Nakamichi https://doi.org/10.1016/j.fusengdes.2012.01.005 Fusion Engineering and Design
2012 JA Observations on microstructure and crystal structure of sintered lithium metatitanate with excess Li K. Mukai, K. Sasaki, T. Terai, A. Suzuki, T. Hoshino https://doi.org/10.1016/j.fusengdes.2012.02.022 Fusion Engineering and Design
2012 JA Release behavior of water vapor and mass loss from lithium titanate K. Katayama, H. Kashimura, T. Hoshino, M. Nishikawa, M. Yamasaki, S. Ishikawa, Y. Ohnishi, S. Fukada https://doi.org/10.1016/j.fusengdes.2012.02.050 Fusion Engineering and Design
2012 EU&JA Overview of materials research and IFMIF/EVEDA under the ITER Broader Approach framework T. Nishitani, H. Tanigawa, T. Yamanishi S.C. Lorenzo, N. Baluc, K. Hayashi, N. Nakajima, H. Kimura, M. Sugimoto, R. Heidinger, P. Garin, H. Matsumoto https://doi.org/10.13182/FST12-A14137 Fusion Science and Technology
2012 EU Lithium orthosilicate surfaces: Characterization and effect on tritium release M.H.H. Kolb, M. Bruns, R. Knitter, S. van Til https://doi.org/10.1016/j.jnucmat.2012.04.024 Journal of Nuclear Materials
2012 EU Synthesis of tritium breeder ceramics from metallic lithium M.H.H. Kolb, C. Odemer, R. Knitter https://doi.org/10.1016/j.jnucmat.2011.10.008 Journal of Nuclear Materials
2012 JA Determining the shear fracture properties of HIP joints of reduced-activation ferritic/martensitic steel by torsion test T. Nozawa, S. Noh, H. Tanigawa https://doi.org/10.1016/j.jnucmat.2012.05.019 Journal of Nuclear Materials
2012 JA Study on fatigue life evaluation using small Specimen for testing neutron irradiated materials S. Nogami, T. Itoh, H. Sakasegawa, H. Tanigawa, E. Wakai, A. Nishimura, A. Hasegawa https://doi.org/10.1080/18811248.2011.9711679 Journal of Nuclear Science and Technology
2011 JA Microstructural Analysis of Secondary Phases in Silicon Carbide Fabricated with SiC Nano-Powder and Sintering Additives T. Koyanagi, S. Kondo and T. Hinoki https://doi.org/10.1002/9781118095386.ch6 Ceramic Engineering and Science Proceedings
2011 EU Radiation induced electrical and microstructural degradation at high temperature for HP SiC T. Hernández, E.R. Hodgson, M. Malo, A. Moroño https://doi.org/10.1016/j.fusengdes.2010.12.064 Fusion Engineering and Design
2011 EU Effect of post welding heat treatment of the HCPB TBM on the Eurofer and lithium orthosilicate pebbles A. Abou-Sena, B. Löbbecke, Axel von der Weth, R. Knitter https://doi.org/10.1016/j.fusengdes.2011.03.038 Fusion Engineering and Design
2011 EU Comparative study of fusion relevant properties of Be12V and Be12Ti P. Kurinskiy, A. Moeslang, V. Chakin, R. Rolli, E. Alves, L.C. Alves, N. Franco, Ch. Dorn, A.A. Goraieb https://doi.org/10.1016/j.fusengdes.2010.12.065 Fusion Engineering and Design
2011 EU Tritium permeation, retention and release properties of beryllium pebbles V. Chakin, A. Moeslang, P. Kurinskiy, R. Rolli, H.C. Schneider, E. Alves, L.C. Alves https://doi.org/10.1016/j.fusengdes.2011.01.091 Fusion Engineering and Design
2011 EU Enhanced fabrication process for lithium ortho­silicate pebbles as breeding material M.H.H. Kolb, R. Knitter, U. Kaufmann, D. Mundt https://doi.org/10.1016/j.fusengdes.2011.01.104 Fusion Engineering and Design
2011 EU&JA Radioluminescence for in situ materials characterization: First results on SiC for fusion applications M. Malo, B. Tsuchiya, S. Nagata, A. Moroño, T. Shikama, E.R. Hodgson https://doi.org/10.1016/j.fusengdes.2011.01.071 Fusion Engineering and Design
2011 JA Japanese contribution to the DEMO-R&D program under the Broader Approach Activities T. Nishitani, T. Yamanishi, H. Tanigawa, T. Nozawa, M. Nakamichi, T. Hoshino, A. Kohyama, A. Kimura, T. Hinoki, T. Shikama https://doi.org/10.1016/j.fusengdes.2011.07.004 Fusion Engineering and Design
2011 JA Radiation induced changes in electrical conductivity of chemical vapor deposited silicon carbides under fast neutron and gamma-ray irradiations B. Tsuchiya, T. Shikama, S. Nagata, K. Saito, T. Nozawa https://doi.org/10.1016/j.fusengdes.2011.03.065 Fusion Engineering and Design
2011 JA A new approach to evaluate irradiation hardening of ion-irradiated ferritic alloys by nano-indentation techniques R. Kasada, Y. Takayama, K. Yabuuchi, A. Kimura, D. Hamaguchi, M. Ando, H. Tanigawa https://doi.org/10.1016/j.fusengdes.2011.03.073 Fusion Engineering and Design
2011 JA Efects of specimen size on fracture toughness of phosphorous added F82H steels B.J. Kim, R. Kasada, A. Kimura, H. Tanigawa https://doi.org/10.1016/j.fusengdes.2011.04.001 Fusion Engineering and Design
2011 JA Extraction residue analysis on F82HBA07 heat and other reduced activation ferritic/martensitic steels T. Nagasaka, Y. Hishinuma, T. Muroga, Y. F. Li, H. Watanabe, H. Tanigawa, H. Sakasegawa, M. Ando https://doi.org/10.1016/j.fusengdes.2010.11.006 Fusion Engineering and Design
2011 JA Precipitation behavior in F82H during heat treatments of blanket fabrication H. Sakasegawa, H. Tanigawa, S. Kano, M. Enomoto https://doi.org/10.1016/j.fusengdes.2011.03.087 Fusion Engineering and Design
2011 JA Torsion test technique for interfacial shear evaluation of F82H RAFM HIP-Joints T. Nozawa, H. Kishimono, H. Tanigawa https://doi.org/10.1016/j.fusengdes.2011.01.110 Fusion Engineering and Design
2011 JA Trial fabrication of beryllides as advanced neutron multiplier M. Nakamichi, K. Yonehara, D. Wakai https://doi.org/10.1016/j.fusengdes.2011.03.009 Fusion Engineering and Design
2011 JA Effect of Li/Ti ratio on microstructure and thermal diffusivity of lithium titanate for solid breeding material K. Mukai, K. Sasaki, T. Hashimoto, A. Suzuki, T. Hoshino, T. Terai https://doi.org/10.1016/j.fusengdes.2011.01.054 Fusion Engineering and Design
2011 JA Trial fabrication tests of advanced tritium breeder pebbles using sol-gel method T. Hoshino, F. Oikawa https://doi.org/10.1016/j.fusengdes.2011.01.065 Fusion Engineering and Design
2011 JA Tensile, Compressive and In-Plane/Inter-Laminar Shear Failure Behavior of CVI- and NITE-SiC/SiC Composites T. Nozawa, Y.B. Choi, T. Hinoki, H. Kishimoto, A. Kohyama, H. Tanigawa https://doi.org/10.1088/1757-899X/18/16/162011 IOP Conference Series: Materials Science and Engineering
2011 EU Ionizing radiation induced helium release for hot pressed SiC A. Moroño, J. Manzano, M. Malo, E.R. Hodgson https://doi.org/10.1016/j.jnucmat.2010.12.213 Journal of Nuclear Materials
2011 EU Radiation induced modification of electrical conductivity for 3 types of SiC E.R. Hodgson, M. Malo, J. Manzano, A. Moroño, T. Hernandez https://doi.org/10.1016/j.jnucmat.2011.01.069 Journal of Nuclear Materials
2011 EU Microstructural and tritium release examination of titanium beryllides V. Chakin, M. Klimenkov, R.Rolli, P. Kurinskiy, A. Moeslang, C. Dorn https://doi.org/10.1016/j.jnucmat.2010.12.142 Journal of Nuclear Materials
2011 EU&JA Recent progress in blanket materials development in the Broader Approach activities T. Nishitani, T. Tanigawa, T. Nozawa, S. Jitsukawa, M. Nakamichi, T. Hoshino, T. Yamanishi, N. Baluc, A. Möslang, R. Lindau, S. Tosti, E.R. Hodgson, S.C. Lorenzo, A. Kohyama, A. Kimura, T. Shikama, K. Hayashi, M. Araki https://doi.org/10.1016/j.jnucmat.2010.12.304 Journal of Nuclear Materials
2011 JA Estimation of neutron-irradiation-induced defect in 3C–SiC from change in XRD peak shift and DFT study T. Sawabe, M. Akiyoshi, K. Yoshida and T. Yano https://doi.org/10.1016/j.jnucmat.2010.12.180 Journal of Nuclear Materials
2011 JA Recovery behavior of point defects after low-dose neutron irradiation of sintered SiC by thermal diffusivity and swelling measurements S. Yamazaki, K. Yoshida and T. Yano https://doi.org/10.1016/j.jnucmat.2010.12.178 Journal of Nuclear Materials
2011 JA Study on Stress Relaxation Behavior of Silicon Carbide by BSR method K. Abe, S. Nogami, A. Hasegawa, T. Nozawa and T. Hinoki https://doi.org/10.1016/j.jnucmat.2011.02.004 Journal of Nuclear Materials
2011 JA Tensile test technique for composites using small notched specimens T. Nozawa and H. Tanigawa https://doi.org/10.1016/j.jnucmat.2011.01.070 Journal of Nuclear Materials
2011 JA Effect of mechanical restraint on weldability of reduced activation ferritic/martensitic steel thick plates H. Serizawa, S. Nakamura, M. Tanaka, Y. Kawahito, H. Tanigawa, S. Katayama https://doi.org/10.1016/j.jnucmat.2011.01.054 Journal of Nuclear Materials
2011 JA Effect of specimen shape on micro-crack growth behavior under fatigue in reduced activation ferritic/martensitic steel S. Nogami, Y. Sato, A. Hasegawa, H. Tanigawa, M. Yamazaki, M. Narui https://doi.org/10.1016/j.jnucmat.2010.12.048 Journal of Nuclear Materials
2011 JA Effects of cold work and phosphorous on the ductile to brittle transition behavior of F82H steels B.J. Kim, R. Kasada, A. Kimura, H. Tanigawa https://doi.org/10.1016/j.jnucmat.2011.01.099 Journal of Nuclear Materials
2011 JA Hot cracking susceptibility of F82H with controlled Ta content H. Ogiwara, H. Mori, H. Tokuichi, K. Saida, K. Nishimoto, H. Tanigawa https://doi.org/10.1016/j.jnucmat.2011.01.056 Journal of Nuclear Materials
2011 JA Multiple-beam Irradiation Effects in Electron-Beam-Welded F82H Joint N. Hashimoto, N. Shiomi, H. Kinoshita and S. Ohnuki https://doi.org/10.1016/j.jnucmat.2010.12.050 Journal of Nuclear Materials
2011 JA Structural analysis of Li2TiO3by synchrotron X-ray diffraction at high temperature K. Omoto, T. Hashimoto, K. Sasaki, T. Terai, T. Hoshino, M. Yashima https://doi.org/10.1016/j.jnucmat.2010.12.257 Journal of Nuclear Materials
2010 JA Progress of IFERC project in the Broader Approach Activities M. Araki, Y. Sakamoto, K. Hayashi, R. Ohuchi, T. Nishitani https://doi.org/10.1016/j.fusengdes.2010.08.029 Fusion Engineering and Design
2010 JA Recent activities on tritium technologies of BA DEMO-R&D program in JAEA T. Yamanishi, T. Hayashi, Y. Kawamura, H. Nakamura, Y. Iwai, K. Kobayashi, K. Isobe, T. Suzuki, M. Yamada https://doi.org/10.1016/j.fusengdes.2009.12.003 Fusion Engineering and Design
2010 JA Recent R&D results on polymeric materials for a SPE-type high-level tritiated water electrolyzer system Y. Iwai, K. Sato, A. Hiroki, M. Tamada, T. Hayashi, T. Yamanishi https://doi.org/10.1016/j.fusengdes.2010.03.067 Fusion Engineering and Design
2010 JA Cracking Resistance of Silicon Carbide Composites by Single‐ and Double‐Notched Specimen Techniques T. Nozawa and H. Tanigawa https://doi.org/10.1111/j.1744-7402.2009.02469.x International journal of Applied Ceramic Technology
2010 EU Radioluminescence characterization of hot pressed, reaction bonded, and CVD SiC M. Malo, J. Manzano, A. Moroño, E.R. Hodgson https://doi.org/10.1088/1757-899X/15/1/012076 IOP Conference Series: Materials Science and Engineering
2010 EU Optical characterization and enhanced He release for electron irradiated LiNbO3 J. Manzano, M. Malo, A. Moroño, J. Olivares, E.R. Hodgson, F. Agulló-López https://doi.org/10.1088/1757-899X/15/1/012077 IOP Conference Series: Materials Science and Engineering
2009 JA Fracture Resistance of silicon carbide composites using various notched specimens T. Nozawa, H. Tanigawa, J.S. Park, A. Kohyama https://doi.org/10.1002/9780470584002.ch6 Ceramic Engineering and Science Proceedings
2009 EU&JA Fusion materials development program in the broader approach activities T. Nishitani, H. Tanigawa, S. Jitsukawa, T. Nozawa, K. Hayashi, T. Yamanishi, K. Tsuchiya, A. Möslang, N. Baluc, A. Pizzuto, E.R. Hodgson, R. Laesser, M. Gasparotto, A. Kohyama, R. Kasada, T. Shikama, H. Takatsu, M. Araki https://doi.org/10.1016/j.jnucmat.2008.12.146 Journal of Nuclear Materials
2009 JA Crystal structure of advanced lithium titanate with lithium oxide additives T. Hoshino, K. Sasaki, K. Tsuchiya, K. Hayashi, A. Suzukic, T. Hashimoto, T. Terai https://doi.org/10.1016/j.jnucmat.2008.12.289 Journal of Nuclear Materials
2009 JA Preliminary test for reprocessing technology development of tritium breeders T. Hoshino, K. Tsuchiya, K. Hayashi, M. Nakamura, H. Terunuma, K. Tatenuma https://doi.org/10.1016/j.jnucmat.2008.12.297 Journal of Nuclear Materials
2008 JA Adsorption capacity of hydrogen isotopes on mordenite Y. Kawamura, Y. Onishi, K. Okuno, T. Yamanishi https://doi.org/10.1016/j.fusengdes.2008.02.004 Fusion Engineering and Design
2008 JA Hydrogen isotope separation capability of low temperature mordenite column for gas chromatograph Y. Kawamura, Y. Onishi, K. Okuno, T. Yamanishi https://doi.org/10.1016/j.fusengdes.2008.07.001 Fusion Engineering and Design
2008 JA Recent results of R&D activities on tritium technologies for ITER and fusion reactors at TPL of JAEA T. Yamanishi, T. Hayashi, W. Shu, Y. Kawamura, H. Nakamura, Y. Iwai, K. Kobayashi, K. Isobe, T. Arita, S. Hoshi, T. Suzuki, M. Yamada https://doi.org/10.1016/j.fusengdes.2008.08.010 Fusion Engineering and Design