Kyushu University Academic Staff Educational and Research Activities Database
List of Papers
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


Papers
1. Makoto OYA, Ryosuke IKEDA and Kazunari KATAYAMA, Atomic and Molecular Processes in Plasma Decomposition Method of Hydrocarbon Gas, Plasma and Fusion Research, 15, 2405032, 2019.03.
2. Hideaki Matsuura, Ryo Okamoto, Yuki Koga, Takuro Suganuma, Kazunari Katayama, Teppei Otsuka, Minoru Goto, Shigeaki Nakagawa, Etsuo Ishitsuka, Kenji Tobita, Li-rod structure in high-temperature gas-cooled reactor as a tritium production device for fusion reactors, Fusion Engineering and Design, 146, A, 1077-1081, 2019.03.
3. Teppei Otsuka , Takuma Shimada , Kenichi Hashizume , Kazunari Katayama & Toshiaki Hiyama , Development of a Monitoring Technique for the Permeation Behavior of Tritium in Pure Nickel to Pure Water, Fusion Science and Technology, 76, 578-582, 2020.05.
4. Kohki Kumagai, Teruya Tanaka, Takuya Nagasaka, Juro Yagi, Takashi Watanabe, Gaku Yamazaki, Fuminobu Sato, Shingo Tamaki, Isao Murata, Satoshi Fukada, Kazunari Katayama and Akio Sagara, Tritium Release from Molten FLiNaBe under Low Flux Neutron Irradiation, Plasma and Fusion Research, 14, 1405044, 2019.03.
5. R. Hiwatari, K. Katayama, M. Nakamura, Y. Miyoshi, A. Aoki, N. Asakura, H. Utoh, Y. Homma, S. Tokunaga, N. Nakajima, Y. Someya, Y. Sakamoto, K. Tobita, Joint Special Design Team for Fusion DEMO, Development of plant concept related to tritium handling in the water-cooling system for JA DEMO, Fusion Engineering and Design, 143, 259-266, 2019.06.
6. Tatsuro Hyuga, Kazunari Katayama, Kazuya Furuichi, Toshiharu Takeishi, Satoshi Fukada, Comparison of release behavior of water vapor and tritiated water vapor from natural soil by heating, Nuclear Materials and Energy, 17, 62-68, 2018.12.
7. J. Izumino, K. Katayama, H. Matsuura, S. Fukada, Study on hydrogen absorption in Zr powder used for tritium confinement in a production system of tritium for fusion reactors with a high-temperature gas-cooled reactor, Nuclear Materials and Energy, 17, 289-294, 2018.12.
8. Kazunari Katayama, Haruaki Sakagawa, Tsuyoshi Hoshino, Satoshi Fukada, Evaluation of Li mass loss from Li2TiO3 with excess Li pebbles in water vapor atmosphere, Fusion Engineering and Design, 136, Part A, 362-366, 2018.11.
9. 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 module and irradiation method for tritium production using high temperature gas-cooled reactor, Fusion Engineering and Design, 136, Part A, 587-591, 2018.11.
10. Satoshi Fukada, Terunori Nishikawa, Mao Kinjo, Kazunari Katayama, Study of hydrogen recovery from Li-Pb using packed tower, Fusion Engineering and Design, 135, Part A, 74-80, 2018.10.
11. Kazunari Katayama, Jyunichi Izumino, Hideaki Matsuura, Satoshi Fukada , Evaluation of hydrogen permeation rate through zirconium pipe, Nuclear Materials and Energy, 16, 12-18, 2018.08.
12. Satoshi Fukada, Yoshiaki Miho, Kazunari Katayama, Tritium separation performance of adsorption/exchange distillation tower packed with structured packing
Research article, Fusion Engineering and Design, 133, 64-69, 2018.08.
13. Toshiharu Takeishi, Kazuya Furuichi, Kazunari Katayama, Yoshiya Kawabata, Satoshi Fukada , Disposal procedure for contaminated surface of tritium handling facility in the decommissioning operation, Fusion Engineering and Design, 128, 231-234, 2018.03.
14. Seiki Saito, Hiroaki Nakamura, Soemsak Yooyen, Naoko Ashikawa and Kazunari Katayama, Effect of polycrystalline structure on helium plasma irradiation of tungsten materials, Japanese Journal of Applied Physics, 57, 1S, 01AB06-1-01AB06-9, 2017.11.
15. M. Noguchi, K. Katayama, Y. Torikai, N. Ashikawa, A. Taguchi, S. Fukada, Measurement of tritium in tungsten deposition layer by imaging plate technique after exposure to gaseous tritium, Fusion Engineering and Design, 124, 257-261, 2017.11, It is important to understand tritium desorption behavior from plasma-facing materials of a fusion reactor in order to discuss effective tritium recovery method from in-vessel components. However, basic behavior of hydrogen isotopes in W deposition layer is not understood completely. In this study, characterized tungsten deposition layer formed by hydrogen plasma sputtering was exposed to gaseous tritium at 300 °C or 500 °C and tritium desorption behavior by vacuum heating was investigated by the imaging plate technique. For comparison, bare tungsten substrates were exposed to gaseous tritium in the same condition. Initial tritium activity in the deposition layer was much higher than that in the bare substrate. Tritium desorption behavior from tungsten deposition layer was different by the temperature of the layer during tritium exposure process. By heating at 500 °C for 1 h, 97.5% of tritium was desorbed from the layer exposed to tritium at 300 °C. On the other hand, by heating at 500 °C for 2 h, only 44.6% of tritium was desorbed from the layer exposed to tritium at 500 °C. To recover most tritium from W deposition layer and W substrate, heating at above 700 °C is required..
16. Ryotaro Yamamoto, Kazunari Katayama, Tsuyoshi Hoshino, Toshiharu Takeishi, Satoshi Fukada , Li mass loss from Li2TiO3 with excess Li pebbles fabricated by optimized sintering condition, Fusion Engineering and Design, 124, 787-791, 2017.11.
17. Ryosuke Nishiumi, Satoshi Fukada, Jun Yamashita, Kazunari Katayama, Akio Sagara, Juro Yagi, Hydrogen Permeation Through Fluoride Molten Salt Mixed with Ti Powder, Fusion Science and Technology, 72, 4, 747-752, 2017.11.
18. Kenji Tobita, Nobuyuki Asakura, Ryoji Hiwatari, Youji Someya, Hiroyasu Utoh, Kazunari Katayama, Arata Nishimura, Yoshiteru Sakamoto, Yuki Homma, Hironobu Kudo, Yuya Miyoshi, Makoto Nakamura, Shunsuke Tokunaga, Akira Aoki, the Joint Special Design Team for Fusion DEMO, Design Strategy and Recent Design Activity on Japan’s DEMO, Fusion Science and Technology, 72, 4, 537-545, 2017.11.
19. K. Katayama, N. Ashikawa, F. Ding, H. Mao, H.S. Zhou, G.N. Luo, J. Wu, M. Noguchi, S. Fukada, Deuterium retention in deposited W layer exposed to EAST deuterium plasma, Nuclear Materials and Energy, 12, 617-621, 2017.07,
 The deposited W layers formed on the W plate by hydrogen plasma sputtering were exposed to deuterium plasma in EAST together with bare W plate. In TDS measurement, the deuterium release was clearly observed from the deposited W layer in addition to the release of hydrogen which was incorporated during the sputtering-deposition processes. On the other hand, the release of hydrogen isotope was not detected from the bare W plate. This suggests that the formation of deposited W layers increases tritium inventory in the plasma confinement vessel. Although the thermocouple contacting to the backside of the W plate did not indicate a remarkable temperature rise, deuterium release peaks from the W layer were close to that from the W layer irradiated by 2 keV D2 + at 573 K. It was found by glow discharge optical emission spectrometry analysis that retained deuterium in the W layer has a peak at the depth of 50 nm and gradually decreases toward the W substrate. From X-ray photoelectron spectroscopy analysis, it was evaluated that W oxide existed just at the surface and W atoms in the bulk of deposited W layer were not oxidized. These data suggest that hydrogen isotopes are not retained in W oxide but grain boundaries..
20. M. Kinjo, S. Fukada, K. Katayama, Y. Edao, T. Hayashi, Experiment on Recovery of Hydrogen Isotopes from Li17Pb83 Blanket by Liquid-Gas Contact, Fusion Science and Technology, 71, 4, 520-526, 2017.05.
21. Y. Yamasaki, S. Fukada, K. Hiyane, K. Katayama, Study on Transfer Behavior of Hydrogen Isotopes from Fluidized Li to Y for Li Blanket, Fusion Science and Technology, 71, 4, 501-506, 2017.05.
22. Kazunari Katayama, Satoshi Fukada, Direct Decomposition Processing of Tritiated Methane by Helium RF Plasma, Fusion Science and Technology, 71, 3, 426-431, 2017.04,
 With the aim of developing a method for the recovery of tritium from tritium-bearing hydrocarbons, it was shown experimentally that methane can be decomposed directly into hydrogen and carbon in RF plasmas via reactions initiated by electrons. Measurements performed with CH4 and CH3T in a helium RF plasma indicate that the degree of decomposition of CH3T is substantially smaller than that of CH4. This is considered to be caused by a very low concentration of CH3T. It was found that a majority of tritium dissociated from CH3T is retained in the plasma reactor. However, a certain amount of retained tritium could be removed by a discharge-cleaning of oxygen..
23. Kazunari Katayama, Youji Someya, Kenji Tobita, Hirofumi Nakamura, Hisashi Tanigawa, Makoto Nakamura, Nobuyuki Asakura, Kazuo Hoshino, Takumi Chikada, Yuji Hatano, Satoshi Fukada, Estimation of Tritium Permeation Rate to Cooling Water in Fusion DEMO Condition, Fusion Science and Technology, 71, 3, 261-267, 2017.04,
 The approximate estimation of tritium permeation rate under the acceptable assumption from a safety point of view is surely useful to progress the design activities for a fusion DEMO reactor. Tritium permeation rates in the blanket and the divertor were estimated by the simplified evaluation model under the recent DEMO conditions in the water-cooled blanket with solid breeder as a first step. Plasma driven permeation rates in tungsten wall were calculated by applying Doyle & Brice model and gas driven permeation rates in F82H were calculated for hydrogen-tritium two-component system. In the representative recent DEMO condition, the following tritium permeation\rates were obtained, 1.8 g/day in the blanket first wall, 2.3 g/day in the blanket tritium breeding region and 1.6 g/day in the divertor. Total tritium permeation rate into the cooling water was estimated to be 5.7 g/day..
24. Kazuma Hiyane, Satoshi Fukada, Yushin Yamasaki, Kazunari Ryosuke Yoshimura, Satoshi Fukada, Taiki Muneoka, Mao Kinjo, Kazunari Katayama , Study on hydrogen isotope behavior in Pb-Li forced onvection flow with permeable wall, Fusion Engineering and Design, 113, 190-194, 2016.12.
25. Kazuma Hiyane, Satoshi Fukada, Yushin Yamasaki, Kazunari Katayama, Eiichi Wakai , Removal of low-concentration deuterium from fluidized Li loop for IFMIF, Fusion Engineering and Design, 109-111, Part B, 1340-1344, 2016.11.
26. Ryosuke Nishiumi, Satoshi Fukada, Akira Nakamura, Kazunari Katayama , Hydrogen permeation through Flinabe fluoride molten salts for blanket candidates, Fusion Engineering and Design, 109-111, Part B, 1663-1668, 2016.11.
27. Kazuya Furuichi, Kazunari Katayama, Hiroyuki Date, Toshiharu Takeishi, Satoshi Fukada , Tritium sorption behavior on the percolation of tritiated water into a soil packed bed, Fusion Engineering and Design, 109-111, Part B, 1371-1375, 2016.11.
28. Kazunari Katayama, Mizuki Noguchi, Hiroyuki Date, Satoshi Fukada, Hydrogen incorporation into tungsten deposits growing by hydrogen plasma sputtering, Fusion Engineering and Design, 109-111, Part B, 1227-1231, 2016.11.
29. Kazuya Furuichi, Kazunari Katayama, Hiroyuki Date, Tatsuro Hyuga, Satoshi Fukada, Evaluation of Tritium Sorption Rate in Soil Packed Bed by Numerical Analysis, Plasma and Fusion Research, 11, 2405050-1-2405050-4, 2016.04.
30. K. Katayama, M. Shimozori, T. Hoshino, R. Yamamoto, H. Ushida, S. Fukada, Pebble structure change of Li2TiO3 with excess Li in water vapor atmosphere at elevated temperatures, Nuclear Materials and Energy, Available online, 2016.03.
31. Kazunari Katayama, Mizuki Noguchi, Hiroyuki Date, S. Fukada, Hydrogen incorporation into tungsten deposits growing by hydrogen plasma sputtering, Fusion Engineering and Design, Availavle online, 2016.01.
32. R.J. Pawelko, M. Shimada, K. Katayama, S. Fukada, P.W. Humrickhouse, T. Terai, Low tritium partial pressure permeation system for mass transport measurement in lead lithium eutectic, Fusion Engineering and Design, 102, 8-13, 2016.01.
33. Satoshi Fukada, Taiki Muneoka, Mao Kinjyo, Rhosuke Yoshimura, Kazunari Katayama , Hydrogen transfer in Pb–Li forced convection flow with permeable wall, Fusion Engineering and Design, 96-97, 95-100, 2015.12.
34. Kazunari Katayama, Hiroki Ushida, Hideaki Matsuura, Satoshi Fukada, Minoru Goto, Shigeaki Nakagawa, Evaluation of Tritium Confinement Performance of Alumina and Zirconium for Tritium Production in a High-Temperature Gas-Cooled Reactor for Fusion Reactors, Fusion Science and Technology, 68, 3, 662-668, 2015.10,
 Tritium production utilizing nuclear reactions by neutron and lithium in a high-temperature gas-cooled reactor is attractive for development of a fusion reactor. From viewpoints of tritium safety and recovery efficiency, tritium confinement is an important issue. It is known that alumina has high resistance for gas permeation. In this study, hydrogen permeation experiments in commercial alumina tubes were conducted and hydrogen permeability, diffusivity and solubility were evaluated. By using obtained data, tritium permeation behavior from an Al2O3-coated Li-compound particle was simulated. Additionally, by using literature data for hydrogen behavior in zirconium, an effect of Zr incorporation into an Al2O3 coating on tritium permeation was discussed. It was indicated that the majority of produced tritium was released through the Al2O3 coating above 500 °C. However, it is expected that total tritium leak is suppressed to below 0.67 % of total tritium produced at 500 °C by incorporating Zr fine particles into the inside of Al2O3 coating, assuming tritium pressure inside particle is kept at the plateau pressure of the Zr hydride generation reaction..
35. Hiroyuki Nakaya, Hideaki Matsuura, Kazunari Katayama, Minoru Goto, Shigeaki Nakagawa , Study on a method for loading a Li compound to produce tritium using high-temperature gas-cooled reactor, Nuclear Engineering and Design, 292, 277-282, 2015.10.
36. Yasuko Kawamoto, Hiroyuki Nakaya, Hideaki Matsuura, Kazunari Katayama, Minoru Goto, Shigeaki Nakagawa, Study on Operation Scenario of Tritium Production for a Fusion Reactor Using a High Temperature Gas-Cooled Reactor, Fusion Science and Technology, 68, 2, 397-401, 2015.09.
37. Kazuya Furuichi, Kazunari Katayama, Hiroyuki Date, Toshiharu Takeishi, Satoshi Fukada, Tritium Desorption Behavior from Soil Exposed to Tritiated Water, Fusion Science and Technology, 68, 2, 458-464, 2015.09.
38. Taiki Muneoka, S. Fukada, R. Yoshimura, K. Katayama, Y. Edao, T. Hayashi, Experiment on Recovery of Hydrogen from Fluidized Li17Pb83 Blanket, Fusion Science and Technology, 68, 2, 443-447, 2015.09.
39. K. Katayama, K. Uehara, H. Date, S. Fukada, H. Watanabe, Temperature dependence of deuterium retention in tungsten deposits by deuterium ion irradiation, Journal of Nuclear Materials, 463, 1033-1036, 2015.08.
40. Kazunari Katayama, Naoko Ashikawa, Keiichiro Uehara, Satoshi Fukada, Carbon and Hydrogen Accumulation on Exhaust Duct in LHD, Plasma Fusion Research, 10, 3405039-1- 3405039-5, 2015.04, To consider carbon balance and hydrogen isotope balance in the fuel cycle system and tritium safety management of a fusion reactor, the evaluation of carbon and hydrogen isotope accumulation not only in the vacuum vessel but also in the exhaust system is necessary. In the present work, type 316 stainless steel substrates were installed at 4 locations in the exhaust duct of the Large Helical Device (LHD) during the 13th experimental campaign. By using the combustion method, the amount of carbon slightly adhering to the substrates, which cannot be measured by electric microbalances, was successfully quantified to be 2 g/cm2. The hydrogen release behavior from the substrate was consistent with that from carbon deposition layer formed by hydrogen plasma sputtering. H/C ratio on the substrate was estimated to be about 1-1.5. Hydrogen incorporated into the metal deposit formed from type 316 stainless steel in the sputtering-deposition device in the laboratory can remain in the deposit even under high vacuum condition in the exhaust duct for a long period..
41. Motoki Shimozori, Kazunari Katayama, Tsuyoshi Hoshino, Hiroki Ushida, Ryotaro Yamamoto, Satoshi Fukada, Water vapor concentration dependence and temperature dependence of Li mass loss from Li2TiO3 with excess Li and Li4SiO4, Fusion Engineering and Design, Available online, 2015.04, In this study, weight reduction of Li2TiO3 with excess Li and Li4SiO4 at elevated temperatures under hydrogen atmosphere or water vapor atmosphere were investigated. The Li mass loss for the Li2TiO3 at 900 oC was 0.4 wt% under 1000 Pa H2 atmosphere and 1.5 wt% under 50 Pa H2O atmosphere. The Li mass loss for the Li2TiO3 increased proportionally to the water vapor pressure in the range from 50 to 200 Pa at 900 oC and increased with increasing temperature from 700 to 900 oC although Li mass loss at 600 oC was significantly smaller than expected. It was found that water vapor concentration dependence and temperature dependence of Li mass loss for the Li2TiO3 and the Li4SiO4 used in this work were quite different. Water vapor is released from the ceramic breeder materials into the purge gas due to desorption of adsorbed water and water formation reaction. The released water vapor possibly promotes Li mass loss with the formation of LiOH on the surface..
42. Keiichiro Uehara, Kazunari Katayama, Hiroyuki Date, Satoshi Fukada, Hydrogen gas driven permeation through tungsten deposition layer formed by hydrogen plasma sputtering, Fusion Engineering and Design, Available online, 2015.03, It is important to evaluate the influence of deposition layers formed on plasma facing wall on tritium permeation and tritium retention in the vessel of a fusion reactor from a viewpoint of safety. In this work, tungsten deposition layers having different thickness and porosity were formed on circular nickel plates by hydrogen RF plasma sputtering. Hydrogen permeation experiment was carried out at the temperature range from 250 oC to 500 oC and at hydrogen pressure range from 1013Pa to 101300Pa. The hydrogen permeation flux through the nickel plate with tungsten deposition layer was significantly smaller than that through a bare nickel plate. This indicates that a rate-controlling step in hydrogen permeation was not permeation through the nickel plate but permeation though the deposition layer. The pressure dependence on the permeation flux differed by temperature. Hydrogen permeation flux through tungsten deposition layer is larger than that through tungsten bulk. From analysis of the permeation curves, it was indicated that hydrogen diffusivity in tungsten deposition layer is smaller than that in tungsten bulk and the equilibrium hydrogen concentration in tungsten deposition layer is enormously larger than that in tungsten bulk at same hydrogen pressure..
43. Satoshi Fukada, K. Katayama, T. Takeishi, Y. Edao, Y. Kawamura, T. Hayashi, T. Yamanishi, Correlation of Rates of Tritium Migration Through Porous Concrete, Fusion Science and Technology, 68, 2, 339-342, 2015.03.
44. Takuya Honda, Kazunari Katayama, Keiichiro Uehara, Toshiharu Takeishi, Satoshi Fukada, Percolation Behavior of Tritiated Water Into a Soil Packed Bed, Fusion Science and Technology, 67, 2, 382-385, 2015.03.
45. Shohei Matsuda, Kazunari Katayama, Motoki Shimozori, Satoshi Fukada, Hiroki Ushida, Masabumi Nishikawa, Hydrogen Permeation Behavior Through F82H at High Temperature, Fusion Science and Technology, 67, 2, 467-470, 2015.03.
46. Fang Ding, Guang-Nan Luo, Richard A. Pitts, Andrey Litnovsky, Xianzu Gong, Rui Ding, Hongmin Mao, Haishan Zhou, William R. Wampler, Peter C. Stangeby, Sophie Carpentier, Maren Hellwig, Rong Yan, Naoko Ashikawa, Masakatsu Fukumoto, Kazunari Katayama, Wenzhaang Wang, Huiqian Wang, Liang Chen, Jing Wu, Overview of plasma–material interaction experiments on EAST employing MAPES, Journal of Nuclear Materials, 455, 1-3, 710-716, 2014.12.
47. Satoshi Fukada, Ryu Shimoshiraishi, Kazunari Katayama, Enhancement of hydrogen production rates in reformation process of methane using permeable Ni tube and chemical heat pump, International Journal of Hydrogen Energy, 39, 35, 20632-20638, 2014.12.
48. Kazunari Katayama, Keiichiro Uehara, Hiroyuki Date, Satoshi Fukada, Hideo Watanabe, Temperature dependence of deuterium retention in tungsten deposits by deuterium ion irradiation, Journal of Nuclear Materials, Available online, 2014.12, The influence of the deposition conditions on hydrogen incorporation into metal deposits was investigated by exposing tungsten (W) or stainless steel (SS) to hydrogen and argon mixed plasma. The sputtering yield of SS was lower than expected from a sputtering yield of iron and was close to that of Mo. The hydrogen incorporated into W deposits was released by heating up to 600 oC. On the other hand, the release of hydrogen from SS deposits continued until 1000 oC. The H/W ratio in W deposits decreased with decreasing the H/W flux ratio toward the growing surface and increasing substrate temperature. The H/W ratio in W deposit formed at at 500 oC was 0.005. The H/Metal ratio in SS deposits was varied in the range between 0.03 and 0.3 depending on the target bias but the influences of the H/Metal flux ratio and substrate temperature were not observed..
49. Hideharu Kashimura, Masabumi Nishikawa, Kazunari Katayama, Shohei Matsuda, Motoki Shimozori, Satoshi Fukada, Tsuyoshi Hoshino, Mass loss of Li2TiO3 pebbles and Li4SiO4 pebbles, Fusion Engineering and Design, 88, 9-10, 2202-2205, 2013.10, 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 (1000 Pa H2/Ar), and mass loss of Li2TiO3 (NFI) and Li2TiO3 with additional Li which is in a developmental stage (JAEA) under water vapor atmosphere (50 Pa 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..
50. Kazunari Katayama, Hideharu Kashimura, Tsuyoshi Hoshino, Toshiharu Takeishi, Shohei Matsuda, Masabumi Nishikawa, Satoshi Fukada, Sorption and desorption behavior of tritiated water on lithium titanate with additional Li
, Fusion Engineering and Design, 88, 9-10, 2400-2403, 2013.10, 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..
51. Kazunari Katayama, Yasuhito Ohnishi, Takuya Honda, Keiichiro Uehara, Satoshi FUKADA, Masabumi Nishikawa, Naoko Ashikawa, Tatsuhiko Uda, Hydrogen incorporation into metal deposits forming from tungsten or stainless steel by sputtering under mixed hydrogen and argon plasma at elevated temperature
, Journal of Nuclear Materials, 438, 1010-1013, 2013.07.
52. Kazunari Katayama, Yasuhito Ohnishi, Satoshi Fukada, Masabumi Nishikawa, Hydrogen incorporation into tungsten deposits growing under hydrogen and argon mixed plasma, Journal of Plasma and Fusion Research SERIES, 10, 89-93, 2012.10, 将来の基幹エネルギー源として期待されている核融合炉は、放射性物質であるトリチウムを燃料とする。そのため、炉心でのトリチウム移動現象の解明は、核融合炉の安全性に関わる重要な課題である。炉心では高エネルギー粒子衝突による内壁の損耗が避けられず、損耗により生じた内壁構成原子により堆積層が形成されることになる。長時間連続運転を見据えた場合、損耗速度の小さなタングステン等の高Z材料においても、堆積層形成が水素同位体挙動に与える影響を定量的に評価しなければならない。著者らは、未解明であった金属堆積層形成に伴う水素同位体移動現象の研究に世界に先駆けて取り組み、水素同位体プラズマ照射下で形成されるタングステン堆積層やステンレス鋼堆積層には、条件によっては、従来考えられていたよりも遥かに高い濃度で水素同位体が捕捉されることを実験的に明らかにした。.
53. Hideaki Kashimura, Masabumi Nishikawa, Kazunari Katayama, Shohei Matsuda, Satoshi Fukada, Tsuyoshi Hoshino, Mass Loss of Li2TiO3 pebbles in atmospehere containing hydrogen, Journal of Plasma and Fusion Research SERIES , 10, 18-21, 2012.10.
54. Hideki Yamasaki, Hideaki Kashimura, Shohei Matsuda, Tatsuhiko Kanazawa, Tomoki Hanada, Kazunari Katayama, Satoshi FUKADA, Masabumi Nishikawa, Effect of water vapor on tritium permeation behavior in the blanket system, Fusion Engineering and Design, 87, 5-6, 525-529, 2012.08.
55. Kazunari Katayama, Hideaki Kashimura, Tsuyoshi Hoshino, Masabumi Nishikawa, Hideki Yamasaki, Ishinichiro Ishikawa, Yasuhito Ohnishi, Release behavior of water vapor and mass loss from lithium titanate, Fusion Engineering and Design, 87, 5-6, 927-931, 2012.08.
56. Shinichiro Ishikawa, Kazunari Katayama, Yasuhito Ohnishi, Satoshi FUKADA, Masabumi Nishikawa, Sorption and desorption behavior of hydrogen isotopes from tungsten deposits caused by deuterium gas or deuterium plasma exposure, Fusion Engineering and Design, 87, 7-8, 1390-1394, 2012.08.
57. Yuki Edao, Satoshi FUKADA, Y. Nishimura, Kazunari Katayama, T. Takeishi, Y. Hatano, A. Taguchi, Effect of hydrophobic paints coating for tritium reduction in concrete materials, Fusion Engineering and Design, 87, 7-8, 995-998, 2012.08.
58. Satoshi Fukada, Makoto Ueda, Takaaki Izumi, Go Wu, Kazunari Katayama, Effects of Preadsorbed H2O and CH4 on H2 and He Adsorption on Activated Carbon at Cryogenic Temperature, Fusion Science and Technology, 61, 4, 282-289, 2012.05.
59. S.Fukada, Y.Edao, K.Sato, T.Takeishi, K.Katayama, K.Kobayashi, T.Hayashi, T.Yamanishi, Y.Hatano, A.Taguchi, S.Akamaru, Transfer of tritium in concrete coated with hydrophobic paints, Fusion Engineering and Design, 87, 1, 54-60, 2012.01.
60. Kazunari Katayama, Satoshi Fukada, Masabumi Nishikawa, Demonstration of Tritium Extraction from Tritiated Methane in Helium by Utilizing Plasma Decomposition, Fusion Science and Technology, 60, 4, 1379-1382, 2011.11.
61. S. Kasahara, K. Katayama, T. Fujiki, S. Ishikawa, S. Fukada, M. Nishikawa, A Study on Carbon and Hydrogen Co-Deposition Behavior in Methane-Hydrogen Mixed Plasma, Fusion Science and Technology, 60, 4, 1487-1490, 2011.11.
62. T. Kanazawa, M. Nishikawa, H. Yamasaki, K. Katayama, H. Kashimura, T. Hanada, S. Fukada, Study on Tritium Release Behavior from Li2ZrO3, Fusion Science and Technology, 60, 3, 1167-1170, 2011.10.
63. H. Yamasaki, K. Kashimura, T. Kanazawa, K. Katayama, N. Yamashita, S. Fukada, M. Nishikawa, Effect of Water Formation Reaction on Tritium Release Behavior from Li4SiO4, Fusion Science and Technology, 60, 3, 1151-1154, 2011.10.
64. S. Fukada, Y. Edao, K. Sato, T. Takeishi, K. Katayama, K. Kobayashi, T. Hayashi, T. Yamanishi, Y. Hatano, A. Taguchi, S. Akamaru , Tritium transfer in porous concrete materials coated with hydrophobic paints, Fusion Science and Technology, 60, 3, 1061-1064, 2011.10.
65. P. Calderoni, J. Sharpe, M. Shimada, B. Denny, B. Pawelko, S. Schuetz, G. Longhurst, Y. Hatano, M. Hara, Y. Oya, T. Otsuka, K. Katayama, S. Konishi, K. Noborio, Y. Yamamoto , An overview of research activities on materials for nuclear applications at the INL Safety, Tritium and Applied Research facility, Journal of Nuclear Materials, 417, 1-3, 1336-1340, 2011.10.
66. Kazunari Katayama, Sansiro Kasahara, Shinichiro Ishikawa, Satoshi Fukada, Masabumi Nishikawa, Hydrogen incorporation in tungsten deposits growing by deuterium plasma sputtering, Fusion Engineering and Design, 86, 9-11, 1702-1705, 2011.10, 核融合炉の安全性の観点から、炉心プラズマ容器内に蓄積される燃料トリチウム量の評価は重要な課題である。本研究では、プラズマ対向壁候補材料であるタングステンに注目し、プラズマ-材料相互作用により形成されるタングステン堆積層への水素同位体取り込み量の評価を行った。具体的には、重水素プラズマスパッタリングにより形成されるタングステン堆積層中の水素同位体濃度と放電ガス圧の関係を調査した。プラズマ中の重水素ガス圧の増加に伴い堆積層密度は減少し、また水素同位体捕捉量も減少することがわかった。堆積層密度の減少は水素同位体捕捉サイトと成りうる空隙が増加することを意味するが、堆積層成長表面に入射する高エネルギー重水素イオン重水素分子との衝突によって減少し、結果として、重水素ガス圧の増加に伴って水素同位体捕捉量が減少するものと考察した。.
67. Toshiya Fujiki, Kazunari Katayama, Sansiro Kasahara, Satoshi Fukada and Masabumi Nishikawa, Effect of oxygen on hydrogen retention in W deposition layers formed by hydrogen RF plasma, Fusion Engineering and Design, 7-9, 85, 1094-1097, 2010.12.
68. Kazunari Katayama. Satoshi Fukada and Masabumi Nishikawa, Direct decomposition of methane using helium RF plasma, Fusion Engineering and Design, 7-9, 85, 1381-1385, 2010.12.
69. Y.Edao, S.Fukada, H.Noguchi, Y.Maeda, K.Katayama, Isotope effects of hydrogen isotope absorption and diffusion in Li0.17Pb0.83 eutectic alloy, Fusion Science and Technology, 56, 2, 831-835, 2009.08.
70. K. Katayama, Y. Uchida, T. Fujiki, M. Nishikawa, S. Fukada, N. Ashikawa, T. Uda, Hydrogen release from deposition layers formed from 316 stainless steel by hydrogen plasma sputtering, Journal of Nuclear Materials, 390-391, 689-692, 2009.06.
71. Y.Uchida, K.Katayama, T.Okamura, K.Imaoka, M.Nishikawa, S.Fukada, Hydrogen retention in deposition layers formed from type 316 stainless steel, Fusion Science and Technology, 54, 2, 545-548, 2008.08.
72. K. Katayama, K.Imaoka, M.Tokitani, M.Miyamoto, M. Nishikawa, S. Fukada, N.Yoshida, Deuterium and helium release and microstructure of tungsten deposition layers formed by RF plasma sputtering, Fusion Science and Technology, 54, 2, 549-552, 2008.08.
73. H.Takata, K.Furuichi, M.Nishikawa, S.Fukada, K.Katayama, T.Takeishi, K.Kobayashi, T.Hayashi, H.Namba, Concentration profiles of tritium penetrated into concrete, Fusion Science and Technology, 54, 1, 223-226, 2008.07.
74. K. Katayama, T. Okamura, K. Imaoka, M. Sasaki, Y. Uchida, M. Nishikawa, S. Fukada, Incorporation of Hydrogen in Carbon-Tungsten Co-Deposition Layers Formed by Hydrogen Plasma Sputtering, Fusion Science & Technology , Volume 52 · Number 3 · October 2007 · Pages 640-644, 2007.10.
75. T. Okamura, K. Katayama, K. Imaoka, Y. Uchida, M. Nishikawa, S. Fukada , Erosion Behavior of Carbon Deposition Layers Formed by Hydrogen Plasma Sputtering
, Fusion Science & Technology , Volume 52 · Number 3 · October 2007 · Pages 645-648, 2007.10.
76. K. Katayama, K. Imaoka, T. Okamura, M. Nishikawa, Helium and hydrogen trapping in tungsten deposition layers formed by helium plasma sputtering, Fusion Engineering and Design, Volume 82, Issues 15-24, October 2007, Pages 1645-1650, 2007.10.
77. S. Fukada, K. Katayama, T. Terai, A. Sagara, Recovery of Tritium from Flibe Blanket in Fusion Reactor, Fusion Science & Technology, Fusion Science & Technology · Volume 52 · Number 3 · October 2007 · Pages 677-681, 2007.10.
78. S. Fukada, M.F. Simpson, R.A. Anderl, J.P. Sharpe, K. Katayama, G.R. Smolik, Y. Oya, T. Terai, K. Okuno, M. Hara, D.A. Petti, S. Tanaka, D.-K. Sze, A. Sagara, Reaction rate of beryllium with fluorine ion for Flibe redox control, Journal of Nuclear Materials, Volumes 367-370, Part 2, 1 August 2007, Pages 1190-1196
, 2007.08.
79. Kazuya Furuichi, Hiroki Takata, Kazunari Katayama, Toshiharu Takeishi, Masabumi Nishikawa, Takumi Hayashi, Kazuhiro Kobayashi, Haruyuki Namba, Evaluation of tritium behavior in concrete, Journal of Nuclear Materials, 367-370, 1243-1247, 2007.10.
80. K.Katayama, T. Kawasaki, Y. Manabe, H.Nagase, T. Takeishi, M. Nishikawa, Hydrogen retention in carbon-tungsten co-deposition layer formed by hydrogen RF plasma, Thin Solid Films, 506-507 (2006) 188-191, 2006.05.
81. K. Katayama, H. Nagase, C. Nishinakamura, T. Takeishi, M. Nishikawa, Erosion of carbon deposition layer by hydrogen RF plasma, Fusion Engineering and Design, 81 (2006) 247-252, 2006.01.
82. T. Takeishi, K. Katayama, M. Nishikawa, K. Masaki, N. Miya, Tritium release from bulk of carbon-based tiles used in JT-60U, Journal of Nuclear materials, 349 (2006) 327-338, 2006.01.
83. T. Kinjyo, M. Nishikawa, K. Katayama, T. Tanifuji, M. Enoeda and S. Beloglazov, Release behavior of bred tritium from irradiated Li4SiO4, Fusion Science and Technology, 48, 1, 646-649, 48-1 (2005) 646-649, 2005.01.
84. T. Kawasaki, Y, Manabe, K. Katayama, T, Takeishi, M. Nishikawa, Hydrogen retention in a tungsten re-deposition layer formed by hydrogen RF plasma, Fusion Science and Technology, 48, 1, 581-584, 48-1 (2005) 581-584, 2005.01.
85. T. Takeishi, K. Katayama, M. Nishikawa, N. Miya, K. Masaki, Recovery of retained tritium from graphite tiles of JT-60U, Fusion Science and Technology, 48, 1, 565-568, 2005.01.
86. K. Katayama, T. Takeishi, Y. Manabe, H. Nagase, M. Nishikawa, N. Miya, Tritium release behavior from the graphite tiles used at the dome unit of the W-shaped divertor region in JT-60U, Journal of Nuclear materials, 10.1016/j.jnucmat.2004.11.005, 340, 1, 83-92, 340 (2005) 83-92, 2005.04.
87. K. Katayama, T. Takeishi, H. Nagase, Y. Manabe, M. Nishikawa, Release behavior of hydrogen isotopes from JT-60U graphite tiles, Fusion Science and Technology, 48, 1, 561-564, 48-1 (2005) 561-564, 2005.01.
88. K. Katayama, H. Nagase, Y. Manabe, Y. Kodama, T. Takeishi, M. Nishikawa, Formation of graphite re-deposition layer by hydrogen RF plasma, Thin Solid Films, 10.1016/j.tsf.2003.12.030, 457, 1, 151-157, 457 (2004) 151, 2004.06.
89. K. Katayama, M. Nishikawa, T. Takeishi, Isotope exchange reaction between tritiated water and hydrogen on SiC, Journal of Nuclear materials, 10.1016/j.jnucmat.2003.09.002, 323, 1, 138-143, 323 (2003) 138, 2003.11.
90. T. Takeishi, M. Nishikawa, K. Katayama, Surface contamination of used tritium gas cylinder, Fusion Engineering and Design, 10.1016/S0920-3796(02)00102-3, 61-62, 591-597, vol.61-62 (2002) 591, 2002.11.
91. K. Katayama, M. Nishikawa, J. Yamaguchi, Isotope effect in hydrogen isotope exchange reaction on first wall materials, Journal of Nuclear Science and Technology, 10.3327/jnst.39.371, 39, 4, 371-376, vol.39 (2002) 371, 2002.04.
92. K. Katayama, M. Nishikawa, Release behavior of tritium from graphite material, Fusion Science and Technology, 41, 1, 53-62, vol.41 (2002) 53, 2002.01.