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Report No.
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Research on consequence analysis method for probablilistic safety assessment of nuclear fuel facilities, 5; Evaluation method and trial evaluation of criticality accident

Yamane, Yuichi ; Nakajima, Ken*; Abe, Hitoshi ; Hayashi, Yoshiaki*; Arisawa, Jun*; Hayami, Satoru*

A special committee of "Research on the analysis methods for accident consequence of nuclear fuel facilities (NFF)" was organized by the AESJ under the entrustment of JAEA, which aims to research on the state-of-the-art of consequence analysis method for PSA of NFF such as fuel reprocessing and fuel fabrication facilities. Its research activities were focused on the analysis method of consequence for postulated accidents with potentially large consequence, e.g. events of criticality, spill of molten glass, hydrogen explosion, boiling of radioactive solution and fire, resulting in release of radioactive material to the environment. The research results were summarized in a series of six reports. In this report, the evaluation methods of criticality accident, such as simplified methods, one-point reactor kinetics codes and quasi-static method, were investigated and their features were summarized to provide useful information for the safety evaluation of nuclear fuel facilities.

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