Research on consequence analysis method for probabilistic safety assessment of nuclear fuel cycle facilities, 3; Fundamental data for consequence evaluation of the radiolytically generated hydrogen gas explosion

Ishida, Michihiko ; Hayashi, Yoshiaki*; Ueda, Yoshinori*; Yoshida, Kazuo 

A special committee of "Research on the analysis methods for accident consequence of nuclear fuel cycle facilities (NFCF)" was organized by the Atomic Energy Society of Japan (AESJ) under the entrustment of Japan Atomic Energy Agency (JAEA) for a research on the state-of-the-art of consequence analysis method for Probabilistic Safety Assessment (PSA) of NFCF such as fuel reprocessing and fuel fabrication facilities. The objectives of this research is to obtain the basic useful information related for establishing the quantitative performance requirement and for risk-informed regulation through qualifying issues needed to be resolved for applying PSA to NFCF. In this technical report, it was summarized that the research result 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.