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Suzuki, Kenji*; Miura, Yasufumi*; Shiro, Ayumi*; Toyokawa, Hidenori*; Saji, Choji*; Shobu, Takahisa; Morooka, Satoshi
Zairyo, 72(4), p.316 - 323, 2023/04
Suzuki, Kenji*; Kura, Komoe*; Miura, Yasufumi*; Shiro, Ayumi*; Toyokawa, Hidenori*; Saji, Choji*; Kajiwara, Kentaro*; Shobu, Takahisa
Zairyo, 71(12), p.1005 - 1012, 2022/12
This paper describes a stress measurement from a welded part of an austenitic stainless steel using synchrotron X-rays. Difficulty measuring the X-ray stress of the welded part is caused by the broadening of the diffraction spot in the radial and circumferential directions. The bending strains of the rectangular bar made of the welded part were measured using synchrotron white X-rays and the double exposure method. To improve the energy resolution, monochromatic synchrotron X-ray of 70 keV was used. The diffraction pattern showed the sharp arc like a pattern from texture material. The diffraction profile was obtained from the integral of the diffraction intensity in the direction of the circumference. The diffraction angle was determined using the double exposure method. As a result, the distribution of the residual stresses of the welded part could be measured.
Kobayashi, Kazuhiro; Isobe, Kanetsugu; Iwai, Yasunori; Hayashi, Takumi; Shu, Wataru; Nakamura, Hirofumi; Kawamura, Yoshinori; Yamada, Masayuki; Suzuki, Takumi; Miura, Hidenori*; et al.
Nuclear Fusion, 47(12), p.1645 - 1651, 2007/12
Times Cited Count：4 Percentile：11.4(Physics, Fluids & Plasmas)The confinement and removal of tritium are the key subjects for safety of ITER. The ITER buildings are confinement barriers of tritium. In a hot cell building, tritium is often released, as vapor and is in contact with the inner walls. Also those of an ITER tritium plant building will be exposed to tritium in an accident. However, the data are scarce, especially on the penetration of tritium into the concrete of the wall materials. The tritium released in the buildings is removed by the Atmosphere Detritiation Systems (ADS), where the tritium is oxidized by catalysts and is removed as water. Special gas of SF
is used in ITER, and is expected to be released in an accident such as fire. Although the SF gas has the potential as a catalyst poison, the performance of ADS with the existence of SF has not been confirmed yet. Tritiated water is produced in the regeneration process of ADS, and is subsequently processed by the ITER Water Detritiation System (WDS). One of the key components of WDS is an electrolysis cell. The electrolysis cell is made of organic compounds, and there is no data on the durability of the cell exposed to tritium. To overcome these issues in a global tritium confinement, a series of experimental studies have been carried out as an ITER R&D task: (1) tritium behavior in concrete; (2) effect of SF on performance of ADS; and (3) tritium durability of electrolysis cell of ITER-WDS.
Kobayashi, Kazuhiro; Miura, Hidenori*; Hayashi, Takumi; Hoshi, Shuichi; Yamanishi, Toshihiko
Fusion Science and Technology, 52(3), p.711 - 715, 2007/10
Times Cited Count：3 Percentile：25.51(Nuclear Science & Technology)The tritium released in the building is removed by Atmosphere Detritiation System (ADS), where the tritium is oxidized by catalysts and is removed as water. Special gas of SF is used as an electric insulation gas in ITER, and is expected to be released in an accident such as fire. Although SF has the potential as a catalyst poison, the performance of ADS with the existence of SF has not been confirmed yet. Therefore, to study the effect of SF, the performance tests of ADS was carried out with air containing 
1% of hydrogen, 1% of methane and 1% of SF. The SF gas was notably decomposed in the case of the catalyst temperature higher than 673 K. In addition, a part of the water produced by the 473 K catalyst was reduced to hydrogen due to the reaction with the decomposed gas in SF. Consequently, the detritiation factor of ADS was decreased to less than 50 from 
1000 of its initial value.
Kobayashi, Kazuhiro; Isobe, Kanetsugu; Iwai, Yasunori; Hayashi, Takumi; Shu, Wataru; Nakamura, Hirofumi; Kawamura, Yoshinori; Yamada, Masayuki; Suzuki, Takumi; Miura, Hidenori*; et al.
Proceedings of 21st IAEA Fusion Energy Conference (FEC 2006) (CD-ROM), 8 Pages, 2007/03
no abstracts in English
Kobayashi, Kazuhiro; Terada, Osamu*; Miura, Hidenori*; Hayashi, Takumi; Nishi, Masataka
Fusion Science and Technology, 48(1), p.476 - 479, 2005/07
Times Cited Count：10 Percentile：56.74(Nuclear Science & Technology)To construct the ITER with high safety and acceptability, it is necessary to establish and to ensure the tritium safe handling technology. The performance of the detritiation system at the off-normal events has not been confirmed well. To obtain performance data of detritiation system at the off normal events, the detritiation experiment was performed at TPL/JAERI using a scaled detritiation system for the oxidation performance test. The detritiation system consists of two oxidation catalyst beds (473K and 773K) and a molecular sieve drying absorber. Basic performance of the detritiation system for hydrogen and methane in air was evaluated under maximum ventilation flow rate. Obtained oxidation efficiency was more than 99.99% for hydrogen in the catalyst bed of 473K and more than 99.9% for methane in the 773K one, respectively. It was confirmed that these performances were maintained even under carbon dioxide , carbon monoxide if oxygen remained in the process gas.
Suzuki, Kenji*; Miura, Yasufumi*; Shiro, Ayumi*; Toyokawa, Hidenori*; Saji, Choji*; Morooka, Satoshi; Shobu, Takahisa
no journal, ,
