検索対象:     
報告書番号:
※ 半角英数字
 年 ~ 
 年

HTTR(高温工学試験研究炉)の試験・運転と技術開発; 2009年度

Operation, test, research and development of the High Temperature Engineering Test Reactor (HTTR); FY2009

高温工学試験研究炉部

Department of HTTR

日本原子力研究開発機構大洗研究開発センターのHTTR(高温工学試験研究炉)は、熱出力30MWの黒鉛減速ヘリウムガス冷却型原子炉で、我が国初の高温ガス炉である。平成21年度は、高温試験運転にて50日間の連続運転を行い、炉心の燃焼特性,ヘリウムの純度管理,高温機器の性能,炉内構造物等の健全性等に関するデータを取得・評価するとともに、熱化学水素製造等の熱源として利用可能であることを実証した。本報告書は、平成21年度(2009年)のHTTRの運転と保守及び各種技術開発の状況等について紹介する。

The High Temperature Engineering Test Reactor (HTTR) constructed at the Oarai Research and Development Center of the Japan Atomic Energy Agency (JAEA) is the first high-temperature gas-cooled reactor (HTGR) in Japan. The HTTR is a graphite-moderated and helium gas-cooled reactor with 30 MW of thermal power. In fiscal year 2009, the HTTR carried out 50 days operation with high temperature test operation mode. In the operation, many kinds of data such as core burnup characteristics, helium purification performance, performance of high temperature components, data related to integrity of core components, etc. have been accumulated. Moreover, it is demonstrated that HTGRs could be utilized as a heat source for thermo-chemical hydrogen production system. This report summarizes activities and results of HTTR operation, maintenance, and several R&Ds, which were carried out in the fiscal year 2009.

Access

:

- Accesses

InCites™

:

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.