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Background: Definition and grouping of initiating events (IEs) are important basics for probabilistic safety assessment (PSA). An IE in a spent fuel reprocessing plant (SFRP) is an event that probably leads to the release of dangerous material to jeopardize workers, public and environment. The main difference between SFRPs and nuclear power plants (NPPs) is that hazard materials spread diffusely in a SFRP and radioactive material is just one kind of hazard material. Materials and Methods: Since the research on IEs for NPPs is in-depth around the world, there are several general methods to identify IEs: reference of lists in existence, review of experience feedback, qualitative analysis method, and deductive analysis method. While failure mode and effect analysis (FMEA) is an important qualitative analysis method, master logic diagram (MLD) method is the deductive analysis method. IE identification in SFRPs should be consulted with the experience of NPPs, however the differences between SFRPs and NPPs should be considered seriously. Results and Discussion: The plutonium uranium reduction extraction (Purex) process is adopted by the technics in a model reprocessing plant. The first extraction cycle (FEC) is the pivotal process in the Purex process. Whether the FEC can function safely and steadily would directly influence the production process of the whole plant-production quality. Important facilities of the FEC are installed in the equipment cells (ECs). In this work, IEs in the FEC process were identified and categorized by FMEA and MLD two methods, based on the fact that ECs are containments in the plant. Conclusion: The results show that only two ECs in the FEC do not need to be concerned particularly with safety problems, and criticality, fire and red oil explosion are IEs which should be emphatically analyzed. The results are accordant with the references.
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참고문헌 (13)
참고문헌 신청
International Atomic Energy Agency / 2002 / Procedures for conducting probabilistic safety assessment for non-reactor nuclear facilities / IAEA-TECDOC-1267 :1~10
International Atomic Energy Agency / 1992 / ocedures for conducting probabilistic safety assessments of nuclear power plants :28~30
Walls SJ / 1989 / Applications of probabilistic risk assessment at BNFL, Sellafield / The International Topical Meeting on Safety Margins in Criticality Safety
Bowers WJ / 1988 / Probabilistic risks assessment applied to nuclear chemical and waste management plants / Czechoslovak-British Nuclear Power Seminar
Sheppard GT / 1992 / The safety case for the thermal oxide reprocessing plant at Sellafield / Technical Committee Meeting of Use of Probabilistic Safety Assessment for Nuclear Installations with Large Inventory of Radioactive Material :7~11
International Atomic Energy Agency / 1992 / ocedures for conducting probabilistic safety assessments of nuclear power plants :28~30
Walls SJ / 1989 / Applications of probabilistic risk assessment at BNFL, Sellafield / The International Topical Meeting on Safety Margins in Criticality Safety
Bowers WJ / 1988 / Probabilistic risks assessment applied to nuclear chemical and waste management plants / Czechoslovak-British Nuclear Power Seminar
Sheppard GT / 1992 / The safety case for the thermal oxide reprocessing plant at Sellafield / Technical Committee Meeting of Use of Probabilistic Safety Assessment for Nuclear Installations with Large Inventory of Radioactive Material :7~11
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