Research on Consequence Analysis Method for Probabilistic Safety Assessment of Nuclear Fuel Facilities (V) Evaluation Method and Trial Evaluation of Criticality Accident

Author:

YAMANE Yuichi,NAKAJIMA Ken,ABE Hitoshi,HAYASHI Yoshiaki,ARISAWA Jun,HAYAMI Satoru

Publisher

Atomic Energy Society of Japan

Subject

Safety, Risk, Reliability and Quality,Nuclear Energy and Engineering

Reference42 articles.

1. 1) K. Yoshida, H. Abe, Y. Yamane et al., Research on the State-of-the-art of Probabilistic Safety Assessment for Non-reactor Nuclear Fcilities (II), JAEA-Research2007-002 (1989), [in Japanese].

2. 2) T. P. McLaughlin et al., A Review of Criticality Accidents 2000 Revision, LA-13638 (2000).

3. 3) 原子力安全委員会 ウラン加工工場臨界事故調査委員会,「ウラン加工工場臨界事故調査委員会報告」(1999).

4. 4) N. Watanabe, H. Tamaki, Review and Compilation of Criticality Accidents in Nuclear Fuel Processing Facilities Outside of Japan, JAERI-Review 2000-006 (2000), [in Japanese].

5. 5) Nuclear Criticality Safety Handbook Version 2, JAERI 1340, (1999), [in Japanese].

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