References
- Y. OGAWA, “Fusion Studies in Japan,” J. Phys. Conf. Ser., 717, 012003 (2016); https://doi.org/10.1088/1742-6596/717/1/012003.
- T. YAMANISHI et al., “Recent Technical Progress on BA Program: DEMO Activities and IFMIF/EVEDA,” Fusion Eng. Des., 109–111, 1272 (2016); https://doi.org/10.1016/j.fusengdes.2015.12.045.
- Y. KAWAMURA et al., “Progress of R&D on Water Cooled Ceramic Breeder for ITER Test Blanket System and DEMO,” Fusion Eng. Des., 109–111, 1637 (2016); https://doi.org/10.1016/j.fusengdes.2015.11.002.
- K. OCHIAI et al., “Design Progress of Advanced Fusion Neutron Source for JA/DEMO Fusion Reactor,” presented at 27th International Atomic Energy Agency Fusion Energy Conference (FEC2018), Gandhinagar, India, October 22–27, 2018, FIP/P3-6.
- T. MUROGA and H. TANIGAWA, “Japanese Fusion Materials Development Path to DEMO,” Fusion Sci. Technol., 72, 389 (2017); https://doi.org/10.1080/15361055.2017.1330641.
- K. OKANO et al., “An Action Plan of Japan Toward Development of Demo Reactor,” Fusion Eng. Des., 136, 183 (2018); https://doi.org/10.1016/j.fusengdes.2018.01.040.
- “A Roadmap Toward Fusion DEMO Reactor (First Report),” Science and Technology Committee on Fusion Energy (July 24, 2018); http://www.mext.go.jp/component/b_menu/shingi/toushin/__icsFiles/afieldfile/2018/11/08/1408259_2_1_1.pdf (current as of May 17, 2018).
- T. YAMANISHI et al., “Recent R&D Results on Fusion Nuclear Technology for ITER and DEMO Reactor in Japan,” Fusion Sci. Technol., 72, 233 (2017); https://doi.org/10.1080/15361055.2017.1330625.
- M. OSAKABE et al., “Current Status of Large Helical Device and Its Prospect for Deuterium Experiment,” Fusion Sci. Technol., 72, 199 (2017); https://doi.org/10.1080/15361055.2017.1335145.
- Y. TAKEIRI, “The Large Helical Device: Entering Deuterium Experiment Phase Toward Steady-State Helical Fusion Reactor Based on Achievements in Hydrogen Experiment Phase,” IEEE Trans. Plasma Sci., 46, 2348 (2018); https://doi.org/10.1109/TPS.2017.2784380.
- A. SAGARA et al., “Helical Reactor Design FFHR-d1 and c1 for Steady State DEMO,” Fusion Eng. Des., 89, 2114 (2014); https://doi.org/10.1016/j.fusengdes.2014.02.076.
- H. TAMURA et al., “Design Modification of Structural Components for the Helical Fusion Reactor FFHR-d1 with Challenging Options,” Fusion Eng. Des., 124, 605 (2017); https://doi.org/10.1016/j.fusengdes.2017.03.031.
- J. MIYAZAWA et al., “Maintainability of the Helical Reactor FFHR-c1 Equipped with the Liquid Metal Divertor and Cartridge-Type Blankets,” Fusion Eng. Des., 136, 1278 (2018); https://doi.org/10.1016/j.fusengdes.2018.04.118.
- T. TANAKA et al., “Analysis of Radiation Environment at Divertor in Helical Reactor FFHR-d1,” Fusion Eng. Des., 89, 1939 (2014); https://doi.org/10.1016/j.fusengdes.2014.02.071.
- S. IMAGAWA et al., “Plan for Testing High-Current Superconductors for Fusion Reactors with a 15 T Test Facility,” Plasma Fusion Res., 10, 3405012 (2015); https://doi.org/10.1585/pfr.10.3405012.
- S. HAMAGUCHI, “Commissioning Test Results of Variable Temperature Helium Refrigerator/Liquefier for NIFS Superconducting Magnet Test Facility,” IEEE Trans. Appl. Supercond., 26, 9500404 (2016); https://doi.org/10.1109/TASC.2016.2525935.
- Y. TERAZAKI et al., “Measurement and Analysis of Critical Current of 100-Ka Class Simply-Stacked HTS Conductors,” IEEE Trans. Appl. Supercond., 25, 6977909 (2015); https://doi.org/10.1109/TASC.2014.2377793.
- S. IMAGAWA et al., “Test of ITER-TF Joint Samples with NIFS Test Facilities,” IEEE Trans. Appl. Supercond., 28, 4200405 (2018); https://doi.org/10.1109/TASC.2017.2774368.
- T. OBANA et al., “Conductor and Joint Test Results of JT-60SA CS and EF Coils Using the NIFS Test Facility,” Cryogenics, 73, 25 (2016); https://doi.org/10.1016/j.cryogenics.2015.11.001.
- A. SAGARA et al., “First Operation of the Flinak/LiPb Twin Loop Oroshh2i-2 with a 3T SC Magnet for R and D of Liquid Blanket for Fusion Reactor,” Fusion Sci. Technol., 68, 303 (2015); https://doi.org/10.13182/FST15-126.
- S. NAKAMURA et al., “MHD Pressure Drop Measurement of PbLi Flow in Double-Bended Pipe,” Fusion Eng. Des., 136, 17 (2018); https://doi.org/10.1016/j.fusengdes.2017.12.009.
- Y. UEKI et al., “Ultrasonic Doppler Velocimetry Experiment of Lead-Lithium Flow with Oroshhi-2 Loop,” Fusion Sci. Technol., 72, 530 (2017); https://doi.org/10.1080/15361055.2017.1330636.
- T. NAGASAKA, “High-Temperature Creep Properties of NIFS-HEAT-2 High-Purity Low-Activation Vanadium Alloy,” presented at 27th Int. Atomic Energy Agency Fusion Energy Conf. (FEC2018), Gandhinagar, India, October 22–27, 2018, MPT/2-1.
- Y. LI, T. NAGASAKA, and T. MUROGA, “Creep Properties and Microstructure of JLF-1 and CLAM Steels Aged at 823 to 973 K,” Fusion Sci. Technol., 56, 323 (2009); https://doi.org/10.13182/FST09-A8922.
- Y. LI et al., “High-Temperature Mechanical Properties and Microstructure of 9Cr Oxide Dispersion Strengthened Steel Compared with RAFMs,” Fusion Eng. Des., 86, 2495 (2011); https://doi.org/10.1016/j.fusengdes.2011.03.004.
- P. F. ZHENG et al., “Microstructures and Mechanical Properties of Mechanically Alloyed V-4Cr-4Ti Alloy Dispersion Strengthened by Nano-Particles,” Fusion Eng. Des., 89, 1648 (2014); https://doi.org/10.1016/j.fusengdes.2014.03.020.
- T. MUROGA et al., “Technical Advancement in Fabricating Dispersion Strengthened Copper Alloys by Mechanical Alloying and Hot Isostatic Pressing for Application to Divertors of Fusion Reactors,” Mater. Sci. Forum, 941, 778 (2018); https://doi.org/10.4028/www.scientific.net/MSF.941.778.
- T. YAMADA et al., “Development of a Dispersion Strengthened Copper Alloy Using a MA-HIP Method,” Nucl. Mater. Energy, 9, 455 (2016); https://doi.org/10.1016/j.nme.2016.05.007.
- H. NOTO et al., “Development of High Strength W/V/Au/ODS-Cu Joint Using HIP Process,” Nucl. Mater. Energy, 9, 411 (2016); https://doi.org/10.1016/j.nme.2016.05.013.
- Y. HAMAJI et al., “ACT2: A High Heat Flux Test Facility Using Electron Beam for Fusion Application,” Plasma Fusion Res., 11, 2405089 (2016); https://doi.org/10.1585/pfr.11.2405089.
- M. TOKITANI, “Fabrication of Divertor Mock-Up with ODS-Cu and W by the Improved Brazing Technique,” Nucl. Fusion, 57, 076009 (2017); https://doi.org/10.1088/1741-4326/aa6bb3.
- Y. HAMAJI et al., “Damage and Deuterium Retention of Re-Solidified Tungsten Following Vertical Displacement Event-Like Heat Load,” Nucl. Mater. Energy, 12, 1303 (2017); https://doi.org/10.1016/j.nme.2016.11.003.
- K. YAKUSHIJI et al., “Erosion and Morphology Changes of F82H Steel Under Simultaneous Hydrogen and Helium Irradiation,” Fusion Eng. Des., 124, 356 (2017); https://doi.org/10.1016/j.fusengdes.2017.03.045.
- Q. ZHOU et al., “Helium Retention Behavior in Simultaneously He+-H2+ Irradiated Tungsten,” J. Nucl. Mater., 502, 289 (2018); https://doi.org/10.1016/j.jnucmat.2018.02.035.
- N. YANAGI et al., “Magnet Design with 100-kA HTS STARS Conductors for the Helical Fusion Reactor,” Cryogenics, 80, 243 (2016); https://doi.org/10.1016/j.cryogenics.2016.06.011.
- Y. OGAWA et al., “Design, Fabrication and Persistent Current Operation of the REBCO Floating Coil for the Plasma Experimental Device Mini-RT,” Plasma Fusion Res., 9, 1405014 (2014); https://doi.org/10.1585/pfr.9.1405014.
- S. KAWABATA, R. MOTOMURA, and T. HIRAYAMA, “AC Loss Measurement of High-Tc Superconducting Coils Wound with Stacked Conductors,” IEEE Trans. Appl. Supercond., 23, 5900904 (2014); https://doi.org/10.1109/TASC.2013.2241381.
- H. HASHIZUME et al., “Development of Remountable Joints and Heat Removable Techniques for High Temperature Superconducting Magnets,” Nucl. Fusion, 58, 026014 (2018); https://doi.org/10.1088/1741-4326/aa874f.
- S. ITO, T. NISHIO, and H. HASHIZUME, “Bending Characteristic of a Bridge-Type Mechanical Lap Joint of REBCO Tapes,” IEEE Trans. Appl. Supercond., 27, 4600105 (2017); https://doi.org/10.1109/TASC.2016.2625748.
- Y. KIMURA et al., “Development of a Prototype Winding Machine for Helical Coils Using High-Temperature Superconducting Tapes,” IEEE Trans. Appl. Supercond., 26, 7412701 (2016); https://doi.org/10.1109/TASC.2016.2531979.
- M. KONDO et al., “Metallurgical Study on Corrosion of RAFM Steel JLF-1 in Pb-Li Alloys with Various Li Concentrations,” Fusion Eng. Des., 125, 316 (2017); https://doi.org/10.1016/j.fusengdes.2017.04.058.
- V. TSISAR et al., “Effect of Li on Mechanical and Corrosion Properties of Electron Beam Welds of V-4Ti-4Cr Alloy (NIFS-HEAT-2),” J. Nucl. Mater., 442, 528 (2013); https://doi.org/10.1016/j.jnucmat.2013.07.013.
- R. NISHIUMI, S. FUKADA, and A. NAKAMURA, “Hydrogen Permeation Through Flinabe Fluoride Molten Salts for Blanket Candidates,” Fusion Eng. Des., 109–111, 1663 (2016); https://doi.org/10.1016/j.fusengdes.2015.10.035.
- S. FUKADA et al., “Experiment to Recover Tritium from Li-Pb Blanket and Understanding Chemistry of the Li17Pb83–H System,” Fusion Sci. Technol., 72, 374 (2017); https://doi.org/10.1080/15361055.2017.1327293.
- F. OKINO et al., “Tritium Recovery Efficiency from an Array of PbLi Droplets in Vacuum,” Fusion Sci. Technol., 71, 575 (2017); https://doi.org/10.1080/15361055.2017.1290972.
- N. SETO et al., “Heat Transfer Enhancement in Sphere-Packed Pipes Under High Reynolds Number Conditions,” Fusion Eng. Des., 83, 1102 (2008); https://doi.org/10.1016/j.fusengdes.2008.07.044.
- T. CHIKADA et al., “Deuterium Permeation Through Monoclinic Erbium Oxide Coating,” Fusion Eng. Des., 133, 121 (2018); https://doi.org/10.1016/j.fusengdes.2018.06.001.
- Y. HISHINUMA, “Formation of Double Oxide Insulator Coating for an Advanced Breeding Blanket,” Fusion Sci. Technol., 66, 221 (2014); https://doi.org/10.13182/FST13-762.
- H. MUTA et al., “Properties of Cold-Pressed Metal Hydride Materials for Neutron Shielding in a D-T Fusion Reactor,” Plasma Fusion Res., 10, 3405021 (2015); https://doi.org/10.1585/pfr.10.3405021.
- J. YAGI et al., “Hydrogen Inventory Control for Vanadium by Ti Metal Powder Mixing in Molten Salt FLiNaK,” Fusion Eng. Des., 124, 748 (2017); https://doi.org/10.1016/j.fusengdes.2017.04.093.
- T. MUROGA, “Refractory Metals and Alloys as Core Materials for Generation IV Nuclear Reactors,” Structural Materials for Generation IV Nuclear Reactors, Vol. 106, p. 415, P. YVON, Ed., Woodhead Publishing in Energy (2016).
- T. MUROGA et al., “Present Status of Vanadium Alloys for Fusion Applications,” J. Nucl. Mater., 455, 263 (2014); https://doi.org/10.1016/j.jnucmat.2014.06.025.
- T. NOZAWA et al., “Japanese Activities of the R&D on Silicon Carbide Composites in the Broader Approach Period and Beyond,” J. Nucl. Mater., 511, 582 (2018); https://doi.org/10.1016/j.jnucmat.2018.05.045.
- A. KIMURA et al., “Oxide Dispersion Strengthened Steels for Advanced Blanket Systems,” Plasma Fusion Res., 11, 2505090 (2016); https://doi.org/10.1585/pfr.11.2505090.
- T. MUROGA et al., “NIFS Program for Large Ingot Production of a V-Cr-Ti Alloy,” J. Nucl. Mater., 283–287, 711 (2000); https://doi.org/10.1016/S0022-3115(00)00281-6.
- T. MUROGA et al., “Fabrication and Characterization of Reference 9Cr and 12Cr-ODS Low Activation Ferritic/Martensitic Steels,” Fusion Eng. Des., 89, 1717 (2014); https://doi.org/10.1016/j.fusengdes.2014.01.010.
- H. SERIZAWA et al., “Influence of Friction Stir Welding Conditions on Joinability of Oxide Dispersion Strengthened Steel/F82H Ferritic/Martensitic Steel Joint,” Nucl. Mater. Energy, 9, 367 (2016); https://doi.org/10.1016/j.nme.2016.09.018.
- H. Y. FU et al., “Dissimilar-Metals Bonding Between NIFS-HEAT-2 Vanadium Alloy and Hastelloy X Nickel Alloy by Controlling Intermetallics,” Fusion Sci. Technol., 72, 680 (2017); https://doi.org/10.1080/15361055.2017.1347469.
- T. HINOKI et al., “Silicon Carbide and Silicon Carbide Composites for Fusion Reactor Application,” Mater. Trans., 54, 472 (2013); https://doi.org/10.2320/matertrans.MG201206.
- S. KONDO, T. KOYANAGI, and T. HINOKI, “Irradiation Creep of 3C–SiC and Microstructural Understanding of the Underlying Mechanisms,” J. Nucl. Mater., 448, 487 (2014); https://doi.org/10.1016/j.jnucmat.2013.09.004.
- H. WATANABE et al., “Microstructural Changes of Y-Doped V-4Cr-4Ti Alloys After Ion and Neutron Irradiation,” Nucl. Mater. Energy, 9, 447 (2016); https://doi.org/10.1016/j.nme.2016.06.001.
- N. HASHIMOTO et al., “Analysis of Helium and Hydrogen Effect on RAFS by Means of Multi-Beam Electron Microscope,” J. Nucl. Mater., 442, S796 (2013); https://doi.org/10.1016/j.jnucmat.2012.11.047.
- M. FUKUDA et al., “Tensile Properties of K-Doped W-3%Re,” Fusion Eng. Des., 89, 1033 (2014); https://doi.org/10.1016/j.fusengdes.2014.02.062.
- K. TSUCHIDA et al., “Recrystallization Behavior of Hot-Rolled Pure Tungsten and Its Alloy Plates During High-Temperature Annealing,” Nucl. Mater. Energy, 15, 158 (2018); https://doi.org/10.1016/j.nme.2018.04.004.
- B. HUANG et al., “In-Situ Fabrication of Yttria Dispersed Copper Alloys Through MA-HIP Process,” Nucl. Mater. Energy, 16, 168 (2018); https://doi.org/10.1016/j.nme.2018.06.024.
- S. M. S. AGHAMIRI et al., “Microstructure and Mechanical Properties of Mechanically Alloyed ODS Copper Alloy for Fusion Material Application,” Nucl. Mater. Energy, 15, 17 (2018); https://doi.org/10.1016/j.nme.2018.05.019.
- H. YAO et al., “Development of ODS-Cu Using a Water-Cooled High Energy Ball Mill,” presented at 18th Int. Conf. Fusion Reactor Materials, Aomori, Japan, November 6–11, 2017, 6PT108.
- C. HU et al., “Influence of Carbon-Dominated Deposition Layer on He Retention and Desorption in Tungsten,” Fusion Eng. Des., 112, 117 (2016); https://doi.org/10.1016/j.fusengdes.2016.08.006.
- Y. UEMURA et al., “Effect of Helium Irradiation on Deuterium Permeation Behavior in Tungsten,” J. Nucl. Mater., 490, 242 (2017); https://doi.org/10.1016/j.jnucmat.2017.04.041.
- Y. HATANO et al., “Deuterium Retention in W and W-Re Alloy Irradiated with High Energy Fe and W Ions: Effects of Irradiation Temperature,” Nucl. Mater. Energy, 9, 93 (2016); https://doi.org/10.1016/j.nme.2016.06.016.
- D. HWANGBO et al., “Erosion of Nanostructured Tungsten by Laser Ablation, Sputtering and Arcing,” Nucl. Mater. Energy, 12, 386 (2017); https://doi.org/10.1016/j.nme.2017.03.004.
- Y. NAKASHIMA et al., “Recent Progress of Divertor Simulation Research Using the GAMMA 10/PDX Tandem Mirror,” Nucl. Fusion, 57, 116033 (2017); https://doi.org/10.1088/1741-4326/aa7cb4.
- E. BERNARD et al., “Temperature Impact on the Micro Structure of Tungsten Exposed to He Irradiation in LHD,” J. Nucl. Mater., 484, 24 (2017); https://doi.org/10.1016/j.jnucmat.2016.10.040.
- Y. NOBUTA et al., “Effects of Modified Surfaces Produced at Plasma-Facing Surface on Hydrogen Release Behavior in the LHD,” Nucl. Mater. Energy, 12, 483 (2017); https://doi.org/10.1016/j.nme.2017.02.025.
- M. TOKITANI et al., “Initial Growth Phase of W-Fuzz Formation in Ultra-Long Pulse Helium Discharge in LHD,” Nucl. Mater. Energy, 12, 1358 (2017); https://doi.org/10.1016/j.nme.2016.11.023.
- S. KAJITA et al., “Morphology and Optical Property Changes of Nanostructured Tungsten in LHD,” Plasma Fusion Res., 10, 1402083 (2015); https://doi.org/10.1585/pfr.10.1402083.
- Tohoku University, Institute for Materials Research website; http://www.imr-oarai.jp/eng (current as of May 17, 2018).
- N. OHNO et al., “Development of a Compact Divertor Plasma Simulator for Plasma-Wall Interaction Studies on Neutron-Irradiated Materials,” Plasma Fusion Res., 12, 1405040 (2017); https://doi.org/10.1585/pfr.12.1405040.
- M. YAJIMA et al., “Kinetics of Deuterium Penetration into Neutron-Irradiated Tungsten Under Exposure to High Flux Deuterium Plasma,” Nucl. Mater. Energy (submitted for publication).
- K. KUSUMI et al., “Study on Thermal Mixing of MHD Liquid Metal Free-Surface Film Flow,” Fusion Sci. Technol., 72, 796 (2017); https://doi.org/10.1080/15361055.2017.1347457.
- H. BI and Y. HIROOKA, “Deuterium Transport in a Liquid Metal GaInSn with Natural Convection Under Steady State Plasma Bombardment,” Fusion Eng. Des., 125, 222 (2017); https://doi.org/10.1016/j.fusengdes.2017.06.020.
- T. GOTO, J. MIYAZAWA, and FFHR DESIGN GROUP, “Estimation of the Pumping Power of the Liquid Metal Divertor REVOLVER-D for the LHD-Type Helical Fusion Reactor FFHR-d1,” Plasma Fusion Res., 12, 1405016 (2017); https://doi.org/10.1585/pfr.12.1405016.
- T. OHGO et al., “Study on Jets Stabilized by Inserting Internal Flow Resistances for the Liquid Metal Divertor in the Helical Fusion Reactor,” Plasma Fusion Res., 13, 1405003 (2018); https://doi.org/10.1585/pfr.13.1405003.
- University of Toyama, Hydrogen Isotope Research Center website; http://www.hrc.u-toyama.ac.jp/en/archives/annual_reports (current as of May 17, 2018).
- M. TANAKA and T. SUGIYAMA, “Development of a Tritium Monitor Combined with an Electrochemical Tritium Pump Using a Proton Conducting Oxide,” Fusion Sci. Technol., 67, 600 (2015); https://doi.org/10.13182/FST14-T89.
- T. SUGIYAMA et al., “Dual Temperature Dual Pressure Water-Hydrogen Chemical Exchange for Water Detritiation,” Fusion Eng. Des., 98–99, 1876 (2015); https://doi.org/10.1016/j.fusengdes.2015.05.054.
- Y. MIHO et al., “Tritium Water Distillation Assisted with Adsorption and Isotopic Exchange,” Fusion Sci. Technol., 71, 326 (2017); https://doi.org/10.1080/15361055.2017.1291235.
- M. MATSUYAMA and S. ABE, “Tracking of Tritium Charged into Stainless Steel by BIXS,” Fusion Eng. Des., 113, 250 (2016); https://doi.org/10.1016/j.fusengdes.2016.08.013.
- T. NORIMATSU et al., “Conceptual Design and Issues of the Laser Inertial Fusion Test (LIFT) Reactor-Targets and Chamber Systems,” Nucl. Fusion, 57, 116040 (2017); https://doi.org/10.1088/1741-4326/aa7f07.
- A. IWAMOTO et al., “FIREX Foam Cryogenic Target Development: Residual Void Reduction and Estimation with Solid Hydrogen Refractive Index Measurements,” Nucl. Fusion, 53, 083009 (2013); https://doi.org/10.1088/0029-5515/53/8/083009.
- S. FUKADA et al., “Tritium Recovery System for Li-Pb Loop of Inertial Fusion Reactor,” Fusion Eng. Des., 83, 747 (2008); https://doi.org/10.1016/j.fusengdes.2008.05.030.
- M. KONDO et al., “Experimental Study on Corrosion and Precipitation in Non-Isothermal Pb-17Li System for Development of Liquid Breeder Blanket of Fusion Reactor,” J. Phys. Conf. Ser., 877, 012001 (2017); https://doi.org/10.1088/1742-6596/877/1/012001.
- K. YAMAMOTO et al., “Investigation of Condensed Liquid Film Flow on Chamber Ceiling of Laser-Fusion Reactor,” Fusion Sci. Technol., 60, 585 (2011); https://doi.org/10.13182/FST11-A12446.
- M. KIRITANI, N. YOSHIDA, and S. ISHINO, “The Japanese Experimental Program on RTNS-II of DT-Neutron Irradiation of Materials,” J. Nucl. Mater., 122, 602 (1984); https://doi.org/10.1016/0022-3115(84)90666-4.
- S. ISHINO, T. KONDO, and M. OKADA, “History, Present Status and Future of Fusion Reactor Materials Research in Japan,” J. Nucl. Mater., 179–181, 3 (1991); https://doi.org/10.1016/0022-3115(91)90005-R.
- K. ABE et al., “Neutron Irradiation Experiments for Fusion Reactor Materials Through JUPITER Program,” J. Nucl. Mater., 258–263, 207 (1998); https://doi.org/10.1016/S0022-3115(98)00424-3.
- K. ABE et al., “Development of Advanced Blanket Performance Under Irradiation and System Integration Through JUPITER-II Project,” Fusion Eng. Des., 83, 842 (2008); https://doi.org/10.1016/j.fusengdes.2008.07.028.
- T. MUROGA, D. K. SZE, and K. OKUNO, “Overview of the TITAN Project,” Fusion Eng. Des., 87, 613 (2012); https://doi.org/10.1016/j.fusengdes.2012.01.034.
- Y. KATOH et al., “Progress in the U.S./Japan PHENIX Project for the Technological Assessment of Plasma Facing Components for DEMO Reactors,” Fusion Sci. Technol., 72, 222 (2017); https://doi.org/10.1080/15361055.2017.1333868.
- Reaction Dynamics at Interfaces in DEMO Divertor Systems and Irradiation Effects (FRONTIER Project) website; http://www.nifs.ac.jp/collaboration/Japan-US/FRONTIER_e.pdf (current as of May 17, 2018).
- “JSPS-CAS Core University Program Seminar on Summary of 10-Year Collaborations in Plasma and Nuclear Fusion Research Area,” Okinawa, Japan, March 9–11, 2011, NIFS-PROC-89, K. TOI and K. WANG, Eds.; http://www.nifs.ac.jp/report/nifsproc.html (current as of May 17, 2018).
- S. MORITA et al., “Fusion Research and International Collaboration in the Asian Region,” Plasma Fusion Res., 13, 3502046 (2018); https://doi.org/10.1585/pfr.13.3502046.
- K. KATAYAMA et al., “Deuterium Retention in Deposited W Layer Exposed to EAST Deuterium Plasma,” Nucl. Mater. Energy, 12, 617 (2017); https://doi.org/10.1016/j.nme.2017.04.004.
- N. ASHIKAWA et al., “Hydrogen Isotope Retention on Coated W with Microcrystalline Structures After Plasma Exposures in KSTAR,” presented at 18th Int. Conf. Fusion Reactor Materials, Aomori, Japan, November 6–11, 2017, 7PT32.
- “Plasma Wall Interaction (PWI TCP),” IEA Technology Collaboration Programmes; https://www.iea.org/tcp/fusionpower/pwi/ (current as of May 17, 2018).
- M. YAJIMA et al., “Investigation of Arcing on Fiber-Formed Nanostructured Tungsten by Pulsed Plasma During Steady State Plasma Irradiation,” Fusion Eng. Des., 112, 156 (2016); https://doi.org/10.1016/j.fusengdes.2016.07.026.
- R. SAKAMOTO et al., “Surface Morphology in Tungsten and RAFM Steel Exposed to Helium Plasma in PSI-2,” Phys. Scr., T170, 014062 (2017); https://doi.org/10.1088/1402-4896/aa93a2.
- T. NAGASAKA et al., “Tensile Properties of F82H Steel After Aging at 400–650°C for 1000–30,000 h,” Fusion Eng. Des., 124, 1011 (2017); https://doi.org/10.1016/j.fusengdes.2017.04.119.
- R. KASADA et al., “Depth-Dependent Nanoindentation Hardness of Reduced-Activation Ferritic Steels After MeV Fe-Ion Irradiation,” Fusion Eng. Des., 89, 1637 (2014); https://doi.org/10.1016/j.fusengdes.2014.03.068.
- H. KISHIMOTO et al., “Destructive and Non-Destructive Evaluation Methods of Interface on F82H HIPed Joints,” Fusion Eng. Des., 109–111, 1744 (2016); https://doi.org/10.1016/j.fusengdes.2015.10.008.
- S. KANO et al., “Microstructure and Mechanical Property in Heat Affected Zone (HAZ) in F82H Jointed with SUS316L by Fiber Laser Welding,” Nucl. Mater. Energy, 9, 300 (2016); https://doi.org/10.1016/j.nme.2016.08.004.
- M. KINJO et al., “Experiment on Recovery of Hydrogen Isotopes from Li17Pb83 Blanket by Liquid-Gas Contact,” Fusion Sci. Technol., 71, 520 (2017); https://doi.org/10.1080/15361055.2017.1293426.
- Y. OYA et al., “Deuterium Permeation Behavior for Damaged Tungsten by Ion Implantation,” J. Nucl. Sci. Technol., 53, 402 (2016); https://doi.org/10.1080/00223131.2015.1052583.
- S. NOGAMI et al., “Fatigue Properties of SiC/SiC Composites Under Various Loading Modes,” Fusion Sci. Technol., 72, 398 (2017); https://doi.org/10.1080/15361055.2017.1333822 .
- Y. YAMAMOTO et al., “Re-Evaluation of SiC Permeation Coefficients at High Temperatures,” Fusion Eng. Des., 109–111, 1286 (2016); https://doi.org/10.1016/j.fusengdes.2015.12.041.
- B. TSUCHIYA et al., “Dynamic Measurements of Radiation-Induced Electrical-Property Modifications in CVD-SiC Under Fast-Neutron Irradiation,” J. Nucl. Mater., 455, 645 (2014); https://doi.org/10.1016/j.jnucmat.2014.08.057.
- Y. FUJII et al., “Hydrogen Retention Behavior of Beryllides as Advanced Neutron Multipliers,” Nucl. Mater. Energy, 9, 233 (2016); https://doi.org/10.1016/j.nme.2016.03.001.
- K. MUNAKATA, “Interaction of Titanium Beryllide with Steam at High Temperatures,” Fusion Eng. Des., 89, 1186 (2014); https://doi.org/10.1016/j.fusengdes.2014.04.067.
- K. KATAYAMA et al., “Pebble Structure Change of Li2TiO3 with Excess Li in Water Vapor Atmosphere at Elevated Temperatures,” Nucl. Mater. Energy, 9, 242 (2016); https://doi.org/10.1016/j.nme.2016.05.006.
- K. MUKAI et al., “Vaporization Property and Crystal Structure of Lithium Metatitanate with Excess Li,” J. Nucl. Mater., 442, S447 (2013); https://doi.org/10.1016/j.jnucmat.2013.04.050.
- M. TOKITANI et al., “Micro-/Nano-Characterization of the Surface Structures on the Divertor Tiles from JET ITER-Like Wall,” Fusion Eng. Des., 116, 1 (2017); https://doi.org/10.1016/j.fusengdes.2017.01.002.
- Y. OYA et al., “Correlation of Surface Chemical States with Hydrogen Isotope Retention in Divertor Tiles of JET with ITER-Like Wall,” Fusion Eng. Des., 132, 24 (2018); https://doi.org/10.1016/j.fusengdes.2018.04.124.
- T. OKITA et al., “Certification of Contact Probe Measurement of Surface Wave of Li Jet for IFMIF,” Fusion Eng. Des., 98–99, 2050 (2015); https://doi.org/10.1016/j.fusengdes.2015.04.035.
- K. HIYANE et al., “Removal of Low-Concentration Deuterium from Fluidized Li Loop for IFMIF,” Fusion Eng. Des., 109–111, 1340 (2016); https://doi.org/10.1016/j.fusengdes.2015.12.030.
- J. YAGI et al., “Fabrication of Nitrogen Trapping Test Loop for IFMIF-EVEDA,” Fusion Eng. Des., 86, 2678 (2011); https://doi.org/10.1016/j.fusengdes.2011.01.096.
- T. YOKOMINE et al., “Neutronic Analysis of IFMIF High Flux Test Module for High Temperature Irradiation,” Fusion Sci. Technol., 68, 657 (2015); https://doi.org/10.13182/FST14-967.
- M. TAKAYASU et al., “Present Status and Recent Developments of the Twisted Stacked-Tape Cable Conductor,” IEEE Trans. Appl. Supercond., 26, 6400210 (2016); https://doi.org/10.1109/TASC.2016.2521827.
- H. KURISHITA et al., “Development of Re-Crystallized W–1.1%TiC with Enhanced Room-Temperature Ductility and Radiation Performance,” J. Nucl. Mater., 398, 87 (2010); https://doi.org/10.1016/j.jnucmat.2009.10.015.
- F. OKINO et al., “Current Status of the Continuous Tritium Recovery Test Campaign Using PbLi Droplets in Vacuum,” Fusion Eng. Des., (2019); https://doi.org/10.1016/j.fusengdes.2019.01.108.