軽水炉炉内構造物の点検評価ガイドラインの体系化－ガイドラインの評価および構造と体系－ 山下 裕宣,Hironobu YAMASHITA,酒井 和夫,Kazuo SAKAI,青木 孝行,Takayuki AOKI......

軽水炉炉内構造物の点検評価ガイドラインの体系化－将来の技術課題とその改善、高度化の方向性－ 山下 裕宣,Hironobu YAMASHITA,千種 直樹,Naoki CHIGUSA,青木 孝行,Takayuki AOKI,小山 幸司,Koji KOYAMA,元良 裕一Yuuichi MOTORA,藤森 治男,Haruo FUJIMORI......

Based on the fundamentals of facility maintenance, a way of maintenance for long-term safe operation of nuclear power plants was discussed. As a result, several technical issues were listed up....
英字タイトル:
Consideration on How Maintenance for Long-term Operation of Nuclear Power plants should be

System safety is considered to secure safety in a comprehensive manner as an entire plant by multiple elemen ts serving an entire plant for a common purpose of safety and an interdependent relationship among elements. nder this concept, we considered how the scheme of fatigue crack management in nuclear power plants should b e and also considered the problems to be solved to establish the effective and efficient management system....
英字タイトル:
Conderation onHow to Manage Fatigue Cracking in Nuclear Power Plants from the viewpoint of Non-destructive Evaluation

This paper reports an outline of the prototype database system which can provide with information on needs and seeds for new inspection and mon itoring technology, which is applicable to the actual nuclear power plan ts for understanding ageing degradation conditions of plant components....
英字タイトル:
Needs and seeds database of new inspection and monitoring technology for ageing equipment

A sodium cooled fast breeder reactor (FBR) has unique systems and components and different degradation mechanism from light water reactor (LWR) so that need to establish maintenance technology in accordance with its features. The examination of the FBR maintenance technology is carried out in the special committee for considering the maintenance for Monju established in the Japan Society of Maintenology (JSM). As a result of the study such as extraction of Monju maintenance feature, maintenance technol...
英字タイトル:
Principles of MONJU Maintenance - Characteristic of MONJU maintenance and reflection of LWR maintenance experience to FBR-

Because a fast breeder reactor (FBR) uses sodium as a coolant and there exist systems and components unique to FBR, aging phenomena to be considered in FBR are quite different from ones in a light water reactor (LWR). Therefore it is required to make a maintenance plan for FBR by considering the characteristics of FBR. In the Japanese LWRs, aging phenomena which occur in every part of all safety-related components have been extracted based on the O&M experiences and the technical evaluation on aging pheno...
英字タイトル:
Principles of MONJU Maintenance - Ageing phenomena of FBR for maintenance-

A Ni-base alloy weld, including cracks due to stress corrosion cracking found in the reactor internal of the oldest BWR in Japan, Tsuruga unit 1, in 1999, was examined by three (3) types of UT method. After this examination, a depth of each crack was confirmed by carrying out a little excavation with a grinder and PT examination by turns until each crack disappeared. Then, the depth measured by the former method was compared with the one measured by the latter method. In this fashion, performances of...
英字タイトル:
Evaluation on Ultrasonic Examination Methods applied to Ni-base Alloy Weld including Cracks due to Stress Corrosion Cracking found in BWR Reactor Internal

２．設備保全における活動と標準化１． はじめに保全学の構築と体系化に向けて、これまで｢保全科学｣｢保全工学｣｢保全社会学｣さらには｢保全最適化｣などについて日本保全学会内で論じられ、それらの一部が学会誌に掲載されてきた [1]～[7] 。これらの議論を踏まえ、日本保全学会企画運営委員会では残された重要課題である「保全規格・基準」への取り組みについて検討を重ねるため、「規格・基準への取り組み」と題する特集を組むこととし、これまで「保全における規格・基準の意義」と｢社会からの要求と規格・基準｣と題する解説記事......