検索対象:     
報告書番号:
※ 半角英数字
 年 ~ 
 年

Development of the maintenance technologies for the future high-temperature gas cooled reactor (HTGR) using operating experiences acquired in high-temperature engineering test reactor (HTTR)

HTTRにおける実績を用いた将来型高温ガス炉のための保守点検技術の開発

島崎 洋祐 ; 本間 史隆; 澤畑 洋明 ; 古澤 孝之 ; 近藤 雅明

Shimazaki, Yosuke; Homma, Fumitaka; Sawahata, Hiroaki; Furusawa, Takayuki; Kondo, Masaaki

This paper describes the lessons learned of the maintenance technologies, which has been and will be developed by using the high temperature engineering test reactor (HTTR), which should be expected to apply to the future HTGRs. The maintenance technologies for the reactor system, which have been developed by using HTTR, are categorized as followings; (1) Establishment of the maintenance technologies specific to the HTGRs. (2) Development of the maintenance technologies for the future HTGRs. (3) Efficient maintenance works for the general equipment.

Access

:

- Accesses

InCites™

:

パーセンタイル:30.92

分野:Nuclear Science & Technology

Altmetrics

:

[CLARIVATE ANALYTICS], [WEB OF SCIENCE], [HIGHLY CITED PAPER & CUP LOGO] and [HOT PAPER & FIRE LOGO] are trademarks of Clarivate Analytics, and/or its affiliated company or companies, and used herein by permission and/or license.