Kyushu University Academic Staff Educational and Research Activities Database
List of Presentations
Kazunari Katayama Last modified date:2020.06.30

Associate Professor / Engineering Science for Advanced Energy System / Department of Advanced Energy Science and Engineering / Faculty of Engineering Sciences


Presentations
1. Ruichong Chen, Kazunari Katayama, Comprehensive Stability Improvement of Core-shell Structured Li4TiO4-Li2TiO3 Tritium Breeding Ceramic Pebbles by Pvp-Assisted Granulation, 日本原子力学会2020年春の年会, 2020.03.
2. DHUNGANA Sujan, KATAYAMA Kazunari, OYA Makoto, ASHIKAWA Naoko, CHIKADA Takumi, NAKAMURA Hirofumi, ISHIYAMA Shintaro, SAGARA Akio, Gaseous products in S-CO2 atmosphere at high temperatures formed in a stainless steel tube, プラズマ・核融合学会 第36回年会, 2019.12.
3. Kazunari Katayama, Studies on Tritium behavior in Kyushu University, JAPAN-CHINA (Post-CUP) COLLABORATION VISIT, 2019.11.
4. Kazunari Katayama, Study on Mass Transfer Phenomena for Realization of Fusion Reactors as a Next Generation Energy Source, 21th Cross Straits Symposium on Energy and Environmental Science and Technology, 2019.11.
5. Daisuke Henzan, Kazunari Katayama, Hideaki Matsuura, Experiment of Tritium Confinement Method with Zr and Alumina in a Tritium Production system, 21th Cross Straits Symposium on Energy and Environmental Science and Technology, 2019.11.
6. Ito Shogo, Katayama Kazunari, Fukada Satoshi, Oya Makoto, Recovering Nonmetallic Impuritiesfrom from Liquid Lithium, 21th Cross Straits Symposium on Energy and Environmental Science and Technology, 2019.11.
7. Makoto Oya, Ryousuke Ikeda and Kazunari Katayama, Atomic and Molecular Processes in Plasma Decomposition method of Hydrocarbon gas, The 28th International Toki Conference on Plasma and Fusion Research, 2019.11.
8. Kazunari Katayama, Dhungana Sujan, Naoko Ashikawa, Takumi Chikada, Mass Transfer at the Interface Between Stainless Steel and Supercritical Carbon Dioxide, The 19th International Conference on Fusion Reactor Materials (ICFRM-19), 2019.10.
9. Akito Ipponsugi, Kazunari Katayama, Tsuyoshi Hoshino, Li mass loss and structure change due to long time heating in hydrogen atmosphere from Li2TiO3 with excess Li
, The 19th International Conference on Fusion Reactor Materials (ICFRM-19), 2019.10.
10. N. Ashikawa, T. Takimoto, K. Katayama, Y. Matsumura, A. Tonegawa, Detection of permeated hydrogen isotopes into plasma facing material using combined specimen with palladium and titanium, The 19th International Conference on Fusion Reactor Materials (ICFRM-19), 2019.10.
11. Kazunari Katayama, Daiki Ishii, Takahiro Matano, Toshiharu Takeishi, Tritium recovery from natural soil immersed in tritiated water, 2019 Japan-Korea Tritium Workshop, 2019.10.
12. Kazunari Katayama, Akito Ipponsugi and Tsuyoshi Hoshino, Influence of Lithium Mass Transfer on Tritium Behavior in Pebbles of Li2TiO3 with Excess Lithium
, 14th International Symposium on Fusion Nuclear Technology (ISFNT-14), 2019.09.
13. Hideki Ito, Kazunari Katayama, Daisuke Mori and Makoto Oya, Hydrogen permeation behavior through tungsten deposition layer growing on nickel substrate by hydrogen plasma sputtering, 14th International Symposium on Fusion Nuclear Technology (ISFNT-14), 2019.09.
14. Toshiharu Takeishi, Kazunari Katayama, Yoshiya Kawabata, Consideration of the low contamination device for the measurement of tritium release rate, 14th International Symposium on Fusion Nuclear Technology (ISFNT-14), 2019.09.
15. T.Takimoto, N.Ashikawa, D.Mori, K.Katayama, V.Rohde, Y.Matsumura, A.Tonegawa, K.N.Sato and K.Kawamura, Development of functional material for deuterium permeation obsevation under divertor plasma exposures, 4th International Workshop on Models and Data for Plasma-Material Interaction in Fusion Devices, 2019.06.
16. Kazunari Katayama, Studies on tritium behavior in materials related to fusion reactors, Molten salt and Tritium mini workshop, 2019.04.
17. Kazunari Katayama, Daiki Ishii, Toshiharu Takeishi, Satoshi Fukada, Measurement of tritium trapped in natural soil by microwave assisted acid dissolution method, 12th International Conference on Tritium Science and Technology, 2019.04.
18. Kazunari Katayama, Studies related to Tritium behavior in Solid breeder blanket, JAPAN-CHINA (Post-CUP) COLLABORATION, 2018.03.
19. Kazunari Katayama, Study on Related to Tritium behavior in Solid breeder blanket, JAPAN-CHINA (Post-CUP) COLLABORATION, 2018.03.
20. Kazunari Katayama, Estimation of Tritium Behavior in Solid Breeder Blanket, 13th Japan-Korea Workshop on Fusion Material Technology Toward Next Fusion Devices, 2018.02.
21. N. Ashikawa, Y.W. Yu, E. Bang, K. Katayama, M. Sakamoto, J. Wu, M.Z. Zhao. S. Son, X.W. Zheng, H. Ding, Progress of plasma wall interaction issues on fusion devices in Japan, China and Korea, 26th International Toki Conference and 11th Asia Plasma & Fusion Association Conference, 2017.12.
22. Yuma Ida, Hideaki Matsuura, Ryo Okamoto, Yuki Koga, Kazunari Katayama, Teppei Otsuka, Study on lithium rod module and irradiation method for tritium production using high temperature gas-cooled reactor, Plasma Conference 2017, 2017.11.
23. Makoto Oya, Kazunari Katayama, Satoshi Fukada, Hydrogen production processes in direct decomposition of hydrocarbon gas using plasma, Plasma Conference 2017, 2017.11.
24. Kazunari Katayama, Junichi Izumino, Hideaki Matsuura, Satoshi Fukada, Evaluation of hydrogen permeation rate through zirconium pipe, 18th International Conference on Fusion Reactor Materials, 2017.11.
25. Tatsuro Hyuga, Kazunari Katayama, Kazuya Furuichi, Toshiharu Takeishi, Satoshi Fukada, Comparison of Release Behaviors of Water Vapor and Tritiated Water Vapor from Soil Particles by Heating, 18th International Conference on Fusion Reactor Materials, 2017.11.
26. Junichi Izumino, Kazunari Katayama, Hideaki Matsuura, Satoshi Fukada, Measurement of Hydrogen Solubility and Diffusivity in Zr Particles for Tritium Production in a High-temperature Gas-cooled Reactor
, 18th International Conference on Fusion Reactor Materials, 2017.11.
27. R. Hiwatari, A. Aoki, K. Katayama, Y. Kawamura, H. Kudo, S. Masuzaki, Y. Someya, H. Utoh, K. Watanabe, Y. Sakamoto, K. Tobita and Joint Special Design Team for Fusion DEMO, Operation Plan of Japan's DEMO toward Steady Electric Power Generation and Prospect of Commercialization, 13th International Symposium on Fusion Nuclear Technology, 2017.09.
28. Naoko Ashikawa, Tuji Torikai, Kazunari Katayama, Yukinori Hamaji, Kenzo Ibano,Akira Taguchi, Masao Matsuyama, Kiyohiko Nishimura, Toshio Ueda, Tritium Decontaminatino of Deposited Carbon and Metal Layers using Glow Dsicharges, 13th International Symposium on Fusion Nuclear Technology, 2017.09.
29. Yuki Koga, Hideaki Matsuura, Yuma Ida, Ryo Okamoto, Kazunari Katayama, Teppei Otsuka, Minoru Goto, Shigeaki Nakagawa, Satoru Nagasumi, Etsuo Ishitsuka, Yosuke Shimazaki, Study on Lithium Rod Test Modukle and Irradiation Method for Tritium Production using High Temperature Gas-cooled Reactor, 13th International Symposium on Fusion Nuclear Technology, 2017.09.
30. Minoru Goto, Keisuke Okumura, Shigeaki Nakagawa, Yoshitomo Inaba, Hideaki Matsuura, Hiroyuki Nakaya, Kazunari Katayama, Feasibility Study on Lithium-loaded High Temperature Gas-cooled Reactor for Tritium Production for Fusion Reactors, 13th International Symposium on Fusion Nuclear Technology, 2017.09.
31. Terunori Nishikawa, Mao, Kinjo, Satoshi Fukada, Kazunari Katayama, Study of Hydrogen isotope Recovery from Li-Pb using Packed Tower, 13th International Symposium on Fusion Nuclear Technology, 2017.09.
32. Jun Yamashita, Ryosuke Nishiumi, Satoshi Fukada, Kazunari Katayama, Akio Sagara, Juro Yagi, Hydrogen Permeation through Flibe and Flinabe Including Ti Powder, 13th International Symposium on Fusion Nuclear Technology, 2017.09.
33. Kazunari Katayama, Haruaki Sakagawa, Tsuyoshi Hoshino, Satoshi Fukada, Evaluation of Li mass loss from Li2TiO3 with excess Li pebbles in water vapor atmosphere
, 13th International Symposium on Fusion Nuclear Technology, 2017.09.
34. Kazunari Katayama, Tritium Release properties, 19th International Workshop on Ceramic Breeder Blanket Interactions, 2017.09.
35. Kazunari Katayama, Satoshi Fukada, Estimation of tritium release and permeation behavior in water cooled solid breeder blanket, 27th IEEE Symposium on Fusion Engineering, 2017.06.
36. Kazunari Katayama, Youji Someya, Kenji Tobita, Kazuya Furuichi, Satoshi Fukada, Tritium permeation to cooling water and environments for DEMO, 4th IAEA DEMO Workshop, 2016.11.
37. M. Noguchi, K. Katayama, Y. Torikai, N. Ashikawa, A. Taguchi, S. Fukada, Tritium measurement for tungsten deposition layer by imaging plate technique after tritium gas exposure
, 29th Symposium on FUsion Technology, 2016.09.
38. Toshiharu Takeishi, Kazunari Katayama, Ryotaro Yamamoto, Yoshiya Kawabata, Preparation of contaminated wall surface of tritium handling facility in the decommissioning operation, 29th Symposium on FUsion Technology, 2016.09.
39. Ryotaro Yamamoto, Kazunari Katayama, Tsuyoshi Hoshino, Toshiharu, Takeishi, Satoshi Fukada, Li mass loss from Li2TiO3 with excess Li pebbles fabricated by optimized sintering condition , 29th Symposium on FUsion Technology, 2016.09.
40. S.Nagasumi, H.Matsuura, T.Otsuka, K.Katayama, M.Goto, S.Nakagawa, STUDY ON TRITIUM PRODUCTION USING HIGH-TEMPERATURE GAS-COOLED REACTOR FOR FUSION REACTORS ~EVALUATION OF TRITIUM OUTFLOW BY NON-EQUILIBRIUM DIFFUSION SIMULATIONS~, 22nd Topical Meeting on the Technology of Fusion Energy (TOFE), 2016.08.
41. Kazunari Katayama, Junichi Izumino, Satoshi Fukada, Hideaki Matsuura, Teppei Otsuka, Minoru Goto, Shigeaki Nakagawa , Study on tritium confinement in tritium production using high-temperature gas-cooled reactor
, 2016 Korea-Japan Tritium Workshop, 2016.07.
42. Kazunari Katayama, Current Tungsten R&D at Kyushu Univ.
Hydrogen incorporation in W deposition layer growing by hydrogen plasma sputtering, PHENIX Task 3 Workshop, 2016.06.
43. K. Katayama, N. Ashikawa, F. Ding, G.N. Luo, M. Noguchi, S. Fukada, Deuterium retention in deposited W layer exposed to EAST deuterium plasma
, 11th International Conference on Tritium Science and Technology (Tritium2016), 2016.05.
44. Kazunari Katayama, Someya Youji, Kenji Tobita, Hirofumi Nakamura, Hisashi Tanigawa, Makoto Nakamura, Nobuyuki Asakura, Kazuo Hoshino, Satoshi Fukada, Yuji Hatano, Takumi Chikada , Estimation of Tritium Permeation Rate to Cooling Water in Fusion DEMO Condition
, 11th International Conference on Tritium Science and Technology (Tritium2016), 2016.04.
45. Kazunari Katayama, Satoshi Fukada, Direct Decomposition Processing of Tritiated Methane by Helium RF Plasma, 11th International Conference on Tritium Science and Technology (Tritium2016), 2016.04.
46. Kazunari Katayama, Satoshi Fukada, Yuji Hatano, Takumi Chikada, Kenji Tobita, Nobuyuki Asakura, Yoshiteru Sakamoto, Hiroyasu Uto, Youji Someya, Makoto Nakamura, Tritium permeation to the primary cooling water, The Workshop in the Task Meeting of the BA Safety Research, 2016.03.
47. Kazunari Katayama, Yuji Torikai, Mizuki Noguchi, Naoko Ashikawa, Satoshi Fukada, Measurement of tritium sorbed in tungsten deposition layer by imaging plate technique, The 25th International Toki Conference (ITC-25), 2015.11.
48. Kazuya Furuichi, Kazunari Katayama, Hiroyuki Date, Satoshi Fukada, Evaluation of tritium behavior in the soil by using tritium permeation model with experimental data, The 25th International Toki Conference (ITC-25), 2015.11.
49. Kazunari Katayama, Ryotaro Yamamoto, Satoshi Fukada, Estimation of tritium behavior from pebble bed of Li2TiO3 by numerical calculation, The 1st Asia Pacific Symposium on Tritium Science (APSOT-1), 2015.11.
50. Kazunari Katayama, Satoshi Fukada, Yuji Hatano, Takumi Chikada, Kenji Tobita, Nobuyuki Asakura, Yoshiteru Sakamoto, Hiroyasu Uto, Youji Someya, Makoto Nakamura, Estimation of Tritium Permeation Behavior in SOlid Breeder Blanket, US and Japan Workshop on Power Plant/Next Steps and Fusion Technology, 2015.10.
51. Kazunari Katayama, Ryotaro Yamamoto, Hiroki Ushida, Tsuyoshi Hoshino, Satoshi Fukada, Pebble structure change of Li2TiO3 with excess Li in water vapor atmosphere at elevated temperature, The 17th International Conference on Fusion Reactor Materials, 2015.10.
52. Hiroki Ushida, Kazunari Katayama, Hideaki Matsuura, Ryotaro Yamamoto, Satoshi Fukada, Minoru Goto, Shigeaki Nakagawa, Tritium permeation behavior through pyrolytic carbon in tritium production using high-temperature gas-cooled reactor for fusion reactors, The 17th International Conference on Fusion Reactor Materials (ICFRM-17), 2015.10.
53. Kazuya Furuichi, Kazunari Katayama, Hiroyuki Date, Satoshi Fukada, Tritium Sorption Behavior on the Percolation of Tritiated Water into a Soil Packed Bed, The 12th International Symposium on Fusion Nuclear Technology (ISFNT-12), 2015.09.
54. Kazunari Katayama, Mizuki Noguchi, Hiroyuki Date, Satoshi Fukada, Hydrogen Incorporation into Tungsten Deposits Growing by Hydrogen Plasma Sputtering, The 12th International Symposium on Fusion Nuclear Technology (ISFNT-12), 2015.09.
55. 片山 一成, Tritium behavior in plasma decomposition process of tritiated methane, 日韓トリチウムワークショップ, 2015.06.
56. Yasuko Kawamoto, Hiroyuki Nakaya, Hideaki Matsuura, Kazunari Katayama, Minoru Goto, Shigeaki Nakagawa, STUDY ON OPERATION SCENARIO OF TRITIUM PRODUCTION FOR FUSION REACTOR
USING HIGH TEMPERATURE GAS-COOLED REACTOR
, Technology of Fusion Energy (TOFE2014), 2014.11.
57. Satoshi Fukada, Daiki Muneoka, Ryosuke Yoshimura, Kazunari Katayama, Yuki Edao, Takumi Hayashi, Experiment on Recovery of Hydrogen Isotopes in Fluidized Li17Pb83, Technology of Fusion Energy (TOFE2014), 2014.11.
58. Kazuya Furuichi, Kazunari Katayama, Hiroyuki Date, Toshiharu Takeishi, Satoshi Fukada, Tritium desorption behavior from soil exposed to tritiated water, Technology of Fusion Energy (TOFE2014), 2014.11.
59. Kazunari Katayama, Hiroki Ushida, Hideaki Matsuura, Satoshi Fukada, Minoru Goto, Shigeaki Nakagawa, Evaluation of tritium confinement performance of alumina and zirconium with tritium production in a high-temperature gas-cooled reactor for fusion reactors , Technology of Fusion Energy (TOFE2014), 2014.11.
60. Kazunari Katayama, Naoko Ashikawa, Keiichiro Uehara, Satoshi Fukada, Carbon and hydrogen accumulation on exhaust duct in LHD, 24th International Toki Conference (ITC-24), 2014.11.
61. Keiichiro Uehara, Kazunari Katayama, Hiroyuki Date, Satoshi Fukada, Hydrogen gas driven permeation through tungsten deposition layer formed by hydrogen plasma sputtering, 28th Symposium on Fusion Technology (SOFT2014), 2014.10.
62. Motoki Shimozori, Kazunari Katayama, Tsuyoshi Hoshino, Hiroki Ushida, Satoshi Fukada, Water vapor concentration dependence and temperature dependence of Li mass loss from Li2TiO3 with excess Li and Li4SiO4, 28th Symposium on Fusion Technology (SOFT2014), 2014.09.
63. Kazunari Katayama, Motoki Shimozori, Tsuyoshi Hoshino, Satoshi Fukada, Influence of Li mass loss on tritium behavior in Li2TiO3 with excess Li, 28th Symposium on Fusion Technology (SOFT2014), 2014.09.
64. Kazunari Katayama, Tritium research at Kyushu Univ., Tritium Focus Group meeting, 2014.09.
65. Kazunari Katayama, Report on Task 3 research at Kyushu Univ., PHENIX Task 3 Planning Workshop, 2014.09.
66. 片山 一成, Percolation behavior of tritiated water into a soil packed bed, Korea-Japan Tritium Workshop, 2014.07.
67. 片山 一成, 上原敬一郎, 伊達宏行, 深田 智, 渡邉 英雄, Temperature dependence of deuterium retention in tungsten deposits by deuterium ion irradiation
, 21st International Conference on Plasma Surface Interactions 2014, 2014.03.
68. Study on tritium production using high-temperature gas-cooled reactor for fusion reactors
(4) Tritium confinement and environment safety.
69. 片山 一成, Hydrogen behavior in W deposits formed by hydrogen plasma sputtering, 日中共同研究検討会, 2014.03.
70. Percolation behavior of tritiated water into a soil packed bed .
71. Study on tritium permeation in tritium production using high temperature gas cooled reactor.
72. A study on permeation of two components hydrogen in tungsten deposition layers.
73. Study on tritium permeation in tritium production using high temperature gas cooled reactor
.
74. Study on percolation behavior of tritiated water into soil packed bed.
75. TRITIUM BEHAVIOR IN PLASMA DECOMPOSITION PROCESS OF TRITIATED METHANE.
76. Percolation behavior of tritiated water into a soil packed bed.
77. HYDROGEN PERMEATION BEHAVIOR THROUGH F82H AT HIGH TEMPERATURE.
78. Effect of burning efficiency on tritium balance in a D-T fusion reactor.
79. Hydrogen permeation in tungsten deposition layers formed by hydrogen plasma sputtering.
80. Mass loss from Li2TiO3 under H2 and H2O atmosphere.
81. Percolation behavior of tritiated water into the soil packed bed.
82. Study on permeation behavior of hydrogen isotopes throught W deposition layer.
83. Effect of surface property on tritiumu release behaviro from Li4SiO4 .
84. Study on hydrogen penetration behavior into W deposition layer under hydrogen plasma exposure.
85. Study on tritium trapping in soil particles.
86. 柏村英明, Masabumi NISHIKAWA, Kazunari Katayama, Shohei Matsuda, Motoki Shimozori, Satoshi FUKADA, Tsuyoshi Hoshino, Mass loss of Li2TiO3 pebbles and Li4SiO4 pebbles, 27th Symposium on Fusion Technology, 2012.09, It has been known that water vapor is released from ceramic breeder materials into the purge gas due to desorption of adsorbed water under dry atmosphere and due to the water formation reaction under hydrogen atmosphere. However, an effect of water vapor in the purge gas to Li mass loss has not been understood. In this study, mass loss of Li2TiO3 (NFI) and Li4SiO4 (FzK) under hydrogen atmosphere (1,000Pa H2/Ar), and mass loss of Li2TiO3 (NFI) and Li2TiO3 with additional Li which is in a developmental stage (JAEA) under water vapor atmosphere (50Pa H2O/Ar) were compared respectively. It was found that under hydrogen atmosphere Li mass loss of Li4SiO4 and Li2TiO3 is same degree although the amount of water vapor released from Li4SiO4 is larger than that from Li2TiO3. It was clarified with regard to Li2TiO3 that Li mass loss in water vapor atmosphere is larger than that in hydrogen atmosphere. Mass loss of Li2TiO3 with additional Li (JAEA) was larger than that of Li2TiO3 (NFI). It was observed by X-ray analysis that Li deposits formed on the inner wall of the quartz tube contain Li2SiO3..
87. Yasuhito Ohnisi, Kazunari Katayama, Masabumi NISHIKAWA, Satoshi FUKADA, Study on hydrogen absorption in tungsten deposits formed by hydrogen plasma sputtering, 27th Symposium on Fusion Technology, 2012.09, Understanding of hydrogen isotope behavior in plasma facing components of a fusion reactor is an important issue from viewpoints of fuel control and radiation safety of tritium. One of candidate materials for plasma facing components is tungsten which has low solubility and low sputtering yield for hydrogen. However, tungsten deposits formed by hydrogen plasma sputtering have porous structure and it can contain a larger amount of hydrogen isotopes than expected from the solubility in tungsten bulk [1-4]. In a long term operation of a fusion reactor, tungsten deposits growing in the plasma confinement vessel may affect the fuel control and tritium inventory. Mass transfer behavior of hydrogen isotopes in metal deposits has not been understood to date. In this study, tungsten deposits formed by hydrogen plasma sputtering were exposed to H2 or D2 gas and the amount of absorbed hydrogen isotope was measured. For comparison, hydrogen behaviors in deposits formed from platinum, which has low hydrogen solubility, and palladium, which has high hydrogen solubility, were also investigated..
88. Kazunari Katayama, Hideaki Kashimura, Tsuyoshi Hoshino, Toshiharu Takeishi, Shohei Matsuda, Masabumi NISHIKAWA, Satoshi FUKADA, Sorption and desorption behavior of tritiated water on lithium titanate with additional Li
, 27th Symposium on Fusion Technology, 2012.09, Tritium sorption capacity is an important parameter to evaluate tritium behavior on lithium ceramic breeder materials. In the present study, sorption and desorption behavior of tritiated water on Li2TiO3 with additional Li, which is in a developmental stage in Japan Atomic Energy Agency as an advanced tritium breeder materials, was observed at 20 oC, 300 oC, 600 oC, 900 oC. Tritium sorption capacity on Li2TiO3 with additional Li is larger than that on Li2TiO3. At 600 oC and 900 oC, the sorption capacity approximately agrees with the sum of physical adsorption capacity and chemical adsorption capacity, but at 20 oC and 300 oC it is smaller than that. The overall mass transfer coefficient for tritium sorption increases with temperature in the range from 20 oC to 600 oC but it decreases considerably at 900 oC. The sorption capacity and the mass transfer coefficient at 600 oC for the sample once used in sorption and desorption experiment at 900 oC are smaller than that for original ones..
89. Kazunari Katayama, Yasuhito Ohnishi, Takuya Honda, Keiichiro Uehara, Satoshi FUKADA, Masabumi NISHIKAWA, HIDEO WATANABE, Deuterium retention in tungsten deposits by deuterium ion exposure, 11th China-Japan Symposium on Materials for Advanced Energy Systems and Fission & Fusion Engineering, 2012.09, Tungsten deposits were produced by a sputtering method using hydrogen RF plasma. Blisters were observed on the surface of the deposit. The density of the deposit was estimated to be 10.7 g/cm3 on overage. The hydrogen concentration in the deposit was estimated to be 0.21 in H/W by thermal desorption method. The sharp release peak of hydrogen was observed at 1140K in addition to the broad peak from 380K to 1000K. The tungsten deposit was irradiated by 2 keV D2+ with a fluene of 1×1021 D2+/m2 at 573K. Deuterium retention and hydrogen retention were estimated to be 0.0021 in D/W and 0.18 in H/W. At the same condition, tungsten foil was irradiated by deuterium ions and deuterium retention in the foil was one-eighteen smaller than that in W deposit. Deuterium retention in W deposit with the unit of D/m2 by deuterium ion exposure is close to an extrapolation line from that by deuterium plasma exposure and these results are in the range of data obtained for two types of polycrystalline tungsten..
90. Study on tritiumu behavior in Solid breeder materials.
91. Hydrogen isotope behavior under deuterium plasma or deuterium gas exposure in tungsten deposits formed by hydrogen plasma sputtering .
92. Study on measurement of tritium solubility in Li-Pb by constant volume method.
93. Hydrogen incorporation into deposits forming from tungsten or stainless steel by sputtering under hydrogen and argon mixed plasma.
94. Hydrogen incorporation into tungsten deposits growing under hydrogen and argon mixed plasma.
95. Study on Li mass loss from Li2TiO3.
96. Study on tritium trapping on solid breeding materials..
97. Study on Li mass loss from solid breeder.
98. A study on formation and hydrogen retention of deposition layers formed from tungsten by hydrogen and argon plasma sputtering.
99. Tritium behavior in solid breeder blanket system.
100. Hydrogen behavior in tungsten deposits.
101. Evaluation of lithium mass transfer and tritium release properties of advanced tritium breeder.
102. Study on hydrogen permeation behavior in plasma-facing wall of a fusion reactor.
103. Hydrogen behavior in tungsten deposition layers.
104. Exhaust gas analysis in deuterium experiment of LHD.
105. Tritium behavior in plasma-facing wall of fusion reactors.
106. Tritium behavior in tungsten deposits.
107. Study on methane decomposition in plasma.
108. A study on formation and hydrogen retention of deposition layers formed from type 316 stainless steel by hydrogen and argon plasma sputtering.
109. Effects of water fomation from ceramic breeders on tritium release.
110. Study on plasma processing method for tritiated methane.
111. Hydrogen retention in metal deposits.
112. Tritium retention in plasma-facing material of fusion reactors.
113. A study on carbon transport to exhaust system.
114. Carbon migration with plasma decomposition of methane.
115. Hydrogen isotope desorption behavior from metal deposition layers caused by plasma exposure.
116. Carbon migration with plasma decomposition of methane.
117. A study on behavior of carbon deposition by methane decomposition.
118. Sorption behavior of hydrogen and deuteirum at a deposition process of sputtered metals.
119. Hydrogen isotope behavior in metal deposition layer.
120. A study on absorption of hydrogen isotope gas to metal deposition layer.
121. A study on formation of carbon deposited layer by methane decomposition.
122. Hydrogen release behavior from W deposition layers formed by RF hydrogen plasma.
123. Hydrogen release behavior from W deposition layers formed by RF hydrogen plasma.
124. Study on tritium behavior in concrete materials.
125. Hydrogen release behavior from metal deposition layers formed by hydrogen plasma.
126. Hydrogen and carbon transfer behavior from carbon deposition layer formed by hydrogen plasma.
127. Hydrogen release behavior from metal deposition layers formed by hydrogen plasma.
128. Formation of hydrogen accumulation thin film by RF plasma.
129. Release behavior of hydrogen isotope from deposition layers formed by sputtering method.
130. A study on decomposition of methane by helium plasma.
131. Formation and hydrogen retention of deposition layers from type 316 stainless steel by hydrogen plasma sputtering
.
132. Study on interaction of SiC and hydrogen plasma.