Overview of Fusion Engineering Research in Japan Focusing on Activities in NIFS and Universities
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[21] S. Masuzaki,et al. Effects of modified surfaces produced at plasma-facing surface on hydrogen release behavior in the LHD , 2017 .
[22] A. Sagara,et al. Tensile properties of F82H steel after aging at 400–650 °C for 1000–30,000 h , 2015 .
[23] A. Sagara,et al. Magnet design with 100-kA HTS STARS conductors for the helical fusion reactor , 2016 .
[24] Y. Hirooka,et al. Deuterium transport in a liquid metal GaInSn with natural convection under steady state plasma bombardment , 2017 .
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[29] T. Hirayama,et al. AC Loss Measurement of High-Tc Superconducting Coils Wound With Stacked Conductors , 2013, IEEE Transactions on Applied Superconductivity.
[30] T. Muroga,et al. Microstructural changes of Y-doped V-4Cr-4Ti alloys after ion and neutron irradiation , 2016 .
[31] A. Kohyama,et al. Japanese activities of the R&D on silicon carbide composites in the broader approach period and beyond , 2018, Journal of Nuclear Materials.
[32] Takeo Muroga,et al. NIFS program for large ingot production of a V–Cr–Ti alloy , 2000 .
[33] A. Sagara,et al. Hydrogen inventory control for vanadium by Ti metal powder mixing in molten salt FLiNaK , 2017 .
[34] T. Muroga,et al. In-situ fabrication of yttria dispersed copper alloys through MA-HIP process , 2018, Nuclear Materials and Energy.
[35] Akira Kohyama,et al. Neutron irradiation experiments for fusion reactor materials through JUPITER program , 1998 .
[36] S. Masuzaki,et al. Correlation of surface chemical states with hydrogen isotope retention in divertor tiles of JET with ITER-Like Wall , 2018, Fusion Engineering and Design.
[37] Deuterium permeation behavior for damaged tungsten by ion implantation , 2016 .
[38] T. Nagasaka,et al. Formation of Double Oxide Insulator Coating for an Advanced Breeding Blanket , 2014 .
[39] A. Kimura,et al. Oxide Dispersion Strengthened Steels for Advanced Blanket Systems , 2016 .
[40] T. Kunugi,et al. Study on Thermal Mixing of MHD Liquid Metal Free-Surface Film Flow , 2017 .
[41] A. Sagara,et al. Helical reactor design FFHR-d1 and c1 for steady-state DEMO , 2014 .
[42] T. Hinoki,et al. Irradiation creep of 3C–SiC and microstructural understanding of the underlying mechanisms , 2014 .
[43] Masahiro Tanaka,et al. Dual temperature dual pressure water-hydrogen chemical exchange for water detritiation , 2015 .
[44] R. Sakamoto,et al. Micro-/nano-characterization of the surface structures on the divertor tiles from JET ITER-like wall , 2017 .
[45] T. Muroga,et al. Development of a dispersion strengthened copper alloy using a MA-HIP method , 2016 .
[46] A. Sagara,et al. Analysis of radiation environment at divertor in helical reactor FFHR-d1 , 2014 .
[47] S. Fukada,et al. Hydrogen permeation through Flinabe fluoride molten salts for blanket candidates , 2016 .
[48] T. Takeuchi,et al. Tritium Water Distillation Assisted with Adsorption and Isotopic Exchange , 2017 .
[49] T. Muroga,et al. Effect of Li on mechanical and corrosion properties of electron beam welds of V–4Ti–4Cr alloy (NIFS-HEAT-2) , 2013 .
[50] T. Muroga,et al. Microstructures and mechanical properties of mechanically alloyed V–4Cr–4Ti alloy dispersion strengthened by nano-particles , 2014 .
[51] A. Sagara,et al. Heat transfer enhancement in sphere-packed pipes under high Reynolds number conditions , 2008 .
[52] M. Shimada,et al. Effect of helium irradiation on deuterium permeation behavior in tungsten , 2017 .
[53] E. Hoashi,et al. Certification of contact probe measurement of surface wave of Li jet for IFMIF , 2015 .
[54] H. Chikaraishi,et al. Test of ITER-TF Joint Samples With NIFS Test Facilities , 2018, IEEE Transactions on Applied Superconductivity.
[55] Jae-Hwan Kim,et al. Interaction of titanium beryllide with steam at high temperatures , 2014 .
[56] Masahiro Tanaka,et al. Development of a Tritium Monitor Combined with an Electrochemical Tritium Pump Using a Proton Conducting Oxide , 2015 .
[57] S. Fukada,et al. Experiment to Recover Tritium from Li-Pb Blanket and Understanding Chemistry of the Li17Pb83–H System , 2017 .
[58] Hiroshi Azechi,et al. FIREX foam cryogenic target development: residual void reduction and estimation with solid hydrogen refractive index measurements , 2013 .
[59] H. Serizawa,et al. Microstructure and mechanical property in heat affected zone (HAZ) in F82H jointed with SUS316L by fiber laser welding , 2016 .
[60] Takayoshi Norimatsu,et al. Conceptual design and issues of the laser inertial fusion test (LIFT) reactor—targets and chamber systems , 2017 .
[61] T. Muroga,et al. Fabrication and characterization of reference 9Cr and 12Cr-ODS low activation ferritic/martensitic steels , 2014 .
[62] H. Yao. Development of ODS-Cu using a water-cooled high energy ball mill , 2017 .
[63] T. Muroga,et al. Tensile properties of K-doped W–3%Re , 2014 .
[64] A. Hasegawa,et al. Deuterium retention in W and W-Re alloy irradiated with high energy Fe and W ions: Effects of irradiation temperature , 2016 .
[65] T. Muroga,et al. Present Status of Vanadium Alloys for Fusion Applications , 2014 .
[66] Min Xu,et al. Fusion Research and International Collaboration in the Asian Region , 2018 .
[67] T. Muroga,et al. Creep Properties and Microstructure of JLF-1 and CLAM Steels Aged at 823 to 973 K , 2009 .
[68] 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 , 2018, Materials Science Forum.
[69] S. Fukada,et al. Experiment on Recovery of Hydrogen Isotopes from Li17Pb83 Blanket by Liquid-Gas Contact , 2017 .
[70] T. Terai,et al. Vaporization property and crystal structure of lithium metatitanate with excess Li , 2013 .
[71] A. Hasegawa,et al. Recrystallization behavior of hot-rolled pure tungsten and its alloy plates during high-temperature annealing , 2018 .
[72] A. Sagara,et al. Erosion and morphology changes of F82H steel under simultaneous hydrogen and helium irradiation , 2017 .
[73] Mikio Enoeda,et al. Progress of R&D on water cooled ceramic breeder for ITER test blanket system and DEMO , 2016 .
[74] T. Nozawa,et al. Dynamic measurements of radiation-induced electrical-property modifications in CVD-SiC under fast-neutron irradiation , 2014 .
[75] T. Nozawa,et al. DESIGN PROGRESS OF ADVANCED FUSION NEUTRON SOURCE FOR JA / DEMO FUSION REACTOR , 2018 .
[76] S. Konishi,et al. Tritium Recovery Efficiency from an Array of PbLi Droplets in Vacuum , 2017 .
[77] T. Tanaka,et al. Fabrication of divertor mock-up with ODS-Cu and W by the improved brazing technique , 2017 .
[78] T. Muroga,et al. Microstructure and mechanical properties of mechanically alloyed ODS copper alloy for fusion material application , 2018 .
[79] H. Chikaraishi,et al. Conductor and joint test results of JT-60SA CS and EF coils using the NIFS test facility , 2016 .
[80] Takashi Nozawa,et al. Recent R&D Results on Fusion Nuclear Technology for ITER and DEMO Reactor in Japan , 2017 .
[81] A. Hasegawa,et al. Feasibility of Utilizing Tungsten Rod for Fusion Reactor Divertor , 2017 .
[82] J. Miyazawa,et al. Study on Jets Stabilized by Inserting Internal Flow Resistances for the Liquid Metal Divertor in the Helical Fusion Reactor , 2018 .
[83] Takeo Muroga,et al. Development of high strength W/V/Au/ODS-Cu joint using HIP process , 2016 .
[84] T. Muroga,et al. High-temperature creep properties of NIFS-HEAT-2 high-purity low-activation vanadium alloy , 2019, Nuclear Fusion.
[85] Y. Hatano,et al. Kinetics of deuterium penetration into neutron-irradiated tungsten under exposure to high flux deuterium plasma , 2019 .
[86] T. Nagasaka,et al. Influence of friction stir welding conditions on joinability of oxide dispersion strengthened steel / F82H ferritic/martensitic steel joint , 2016 .
[87] T. Terai,et al. Deuterium permeation through monoclinic erbium oxide coating , 2018, Fusion Engineering and Design.
[88] T. Muroga,et al. High-temperature mechanical properties and microstructure of 9Cr oxide dispersion strengthened steel compared with RAFMs , 2011 .
[89] T. Kubota,et al. Analysis of helium and hydrogen effect on RAFS by means of multi-beam electron microscope , 2013 .
[90] A. Sagara,et al. Maintainability of the helical reactor FFHR-c1 equipped with the liquid metal divertor and cartridge-type blankets , 2018, Fusion Engineering and Design.
[91] Kyoko Oba,et al. An action plan of Japan toward development of demo reactor , 2018 .
[92] Jae-Hwan Kim,et al. Hydrogen retention behavior of beryllides as advanced neutron multipliers , 2016 .
[93] Kenji Tobita,et al. Recent technical progress on BA Program: DEMO activities and IFMIF/EVEDA , 2016 .
[94] A. Kohyama,et al. Destructive and non-destructive evaluation methods of interface on F82H HIPed joints , 2016 .
[95] A. Sagara,et al. First Operation of the Flinak/LiPb Twin Loop Orosh2i-2 with a 3T SC Magnet for R&D of Liquid Blanket for Fusion Reactor , 2015 .
[96] S. Ishino,et al. The Japanese experimental program on RTNS-II of DT-neutron irradiation of materials☆ , 1984 .
[97] S. Masuzaki,et al. Investigation of arcing on fiber-formed nanostructured tungsten by pulsed plasma during steady state plasma irradiation , 2016 .
[98] T. Akiyama,et al. Morphology and Optical Property Changes of Nanostructured Tungsten in LHD , 2015 .
[99] Masayoshi Kawai,et al. Development of re-crystallized W–1.1%TiC with enhanced room-temperature ductility and radiation performance , 2010 .
[100] N. Yanagi,et al. Development of a Prototype Winding Machine for Helical Coils Using High-Temperature Superconducting Tapes , 2016, IEEE Transactions on Applied Superconductivity.
[101] T. Muroga,et al. Overview of the TITAN project , 2012 .
[102] N. Yanagi,et al. Plan for Testing High-Current Superconductors for Fusion Reactors with A 15T Test Facility , 2015 .
[103] Temperature impact on the micro structure of tungsten exposed to He irradiation in LHD , 2017 .
[104] S. Masuzaki,et al. Helium retention behavior in simultaneously He+-H2+ irradiated tungsten , 2018 .
[105] T. Muroga,et al. Japanese Fusion Materials Development Path to DEMO , 2017 .
[106] N. Yanagi,et al. Development of remountable joints and heat removable techniques for high-temperature superconducting magnets , 2018 .
[107] T. Mito,et al. Commissioning Test Results of Variable-Temperature Helium Refrigerator/Liquefier for NIFS Superconducting Magnet Test Facility , 2016, IEEE Transactions on Applied Superconductivity.
[108] Joseph V. Minervini,et al. Present Status and Recent Developments of the Twisted Stacked-Tape Cable Conductor , 2016, IEEE Transactions on Applied Superconductivity.
[109] T. Muroga,et al. Experimental study on corrosion and precipitation in non-isothermal Pb-17Li system for development of liquid breeder blanket of fusion reactor , 2017 .
[110] A. Sagara,et al. MHD pressure drop measurement of PbLi flow in double-bended pipe , 2017, Fusion Engineering and Design.
[111] Minami Yoda,et al. Progress in the U.S./Japan PHENIX Project for the Technological Assessment of Plasma Facing Components for DEMO Reactors , 2017 .
[112] A. Sagara,et al. Ultrasonic Doppler Velocimetry Experiment of Lead-Lithium Flow with Oroshhi-2 Loop , 2017 .