第7回
ステンレスにおける水素同位体透過挙動の解明
著者:
押尾 純也,Junya OSUO,倉田 理江,Rie KURATA,小林 真,Makoto KOBAYASHI,鈴木 優斗,Masato SUZUKI,王 万景,Wanjing WANG,大矢 恭久,Yasuhisa OYA,奥野 健二,Kenji OKUNO
発刊日:
公開日:
キーワードタグ:
Stainless steel is used in various nuclear installations as a major structural material. Tritium is produced by several nuclear reactions in these facilities. It is considered that the hydrogen isotope included tritium permeated for stainless steel through the interaction such as dissolution, diffusion and recombination, and is released on the atmosphere. Therefore, it is important to clarify permeation behavior of tritium in stainless steel from the viewpoint for improvement of the social acceptability o...
英字タイトル:
Study on permeation behavior of hydrogen isotope in stainless steel
第5回
核融合実験炉ITER用ダイバータ受熱機器における非破壊検査技術の開発
著者:
江里 幸一郎,Koichiro EZATO,鈴木 哲,Satoshi SUZUKI,大楽 正幸,Masayuki DAIRAKU,横山 堅二,Kenji YOKOYAMA,秋場 真人,Masato AKIBA
発刊日:
公開日:
キーワードタグ:
Non-destructive examination (NDE) methods for joint interfaces between different materials in high heat flux components of ITER divertor should be urgently developed to assure qualit y and reliability of joining techniques. This paper reports the present R&Ds status of NDE for ITER divertor and its outlook. The detection ability of joint defect by using ultrasonic wave and thermography NDE are examined in the joint interface between armor tiles and a cooling tubes of divertor mock-ups. The results of both ...
英字タイトル:
Development of Non-destructive technique for ITER divertor high heat flux component
第5回
赤外熱画像を用いた核融合実験炉ダイバータ用非破壊検査装置の開発
著者:
横山 堅二,Kenji YOKOYAMA,鈴木 哲,Satoshi SUZUKI,江里 幸一郎,Kouichiro EZATO,関 洋治,Yohji SEKI,榎枝 幹夫,Mikio ENOEDA,秋場 真人,Masato AKIBA
発刊日:
公開日:
キーワードタグ:
An infrared thermography NDE facility which is utilized in the acceptance test of ITER d ivertor components has been developed in JAEA. This NDE facility can inspect the integri ty of the bonding interface of the divertor components based on its surface temperature response by means of switching of hot (95 deg C)/cold (5 deg C) water. The advantages of this facility are 1) to have active coolant purging system which enables rapid temperatu re change and 2) to inspect the surface and the both side walls of...
英字タイトル:
Development of a non destructive evaluation system using infrared images for divertor on nuclearfusion experiment reactor