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14回
断層変位に対するリスク評価と工学的な対応策 (4)機器・配管系の解析評価事例
著者:
佐藤 邦彦,Kunihiko SATO,鈴木 優,Yutaka SUZUKI,新間 聡,Satoshi SHINMA,原口 龍将,Ryusuke HARAGUCHI,神谷 昌伸,Masanobu KAMIYA,小川 勤,Tsutomu OGAWA,上屋 浩一,Koichi KAMIYA
発刊日:
公開日:
The structural integrity of equipment and piping systems to a fault displacement depends on the damage state of a reactor building. When there is no damage in a reactor building, the supporting function of equipment and piping systems is maintained. In this case, FEM analysis can estimate the allowable state of the entire system of the important safety equipment. In this part, an example of the analysis evaluation for the equipment and piping systems, which are important for safety, in the case of loading a...
英字タイトル:
Risk Evaluation Method for Faults Displacement by Engineering Approach (4)The Analysis Evaluation of Equipment and Piping System