- 著者
-
石田 倫彦
林 芳昭
上田 吉徳
吉田 一雄
- 出版者
- 一般社団法人 日本原子力学会
- 雑誌
- 日本原子力学会和文論文誌 (ISSN:13472879)
- 巻号頁・発行日
- vol.9, no.1, pp.71-81, 2010 (Released:2012-02-08)
- 参考文献数
- 17
- 被引用文献数
-
1
2
A special committee on “Research on the analysis methods for accident consequence of nuclear fuel facilities (NFFs)” was organized by the Atomic Energy Society of Japan (AESJ) under the entrustment of Japan Atomic Energy Agency (JAEA). The committee aims to research on the state-of-the-art consequence analysis method for Probabilistic Safety Assessment (PSA) of NFFs, such as fuel reprocessing and fuel fabrication facilities. The objective of this research is to obtain the useful information related to the establishment of quantitative performance objectives and to risk-informed regulation through qualifying issues needed to be resolved for applying PSA to NFFs. The research activities of the committee were mainly focused on the analysis method of consequences for postulated accidents with potentially large consequences in NFFs, e.g., events of criticality, spill of molten glass, hydrogen explosion, boiling of radioactive solution, and fire (including rapid decomposition of TBP complexes), resulting in the release of radioactive materials into the environment. The results of the research were summarized in a series of six reports, which consist of a review report and five technical ones. In this technical report, the research results about basic experimental data related to the consequence of the radiolytically generated hydrogen gas explosion postulated in the radioactive solution reserve tank caused by the loss of dilution air supply were summarized.