• Title/Summary/Keyword: PSA Fire hazard

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Present Status of Fire PSA Methodology for Risk-Informed Application (위험도 정보 활용을 위한 화재 PSA 방법론 개선 연구 현황)

  • 이윤환;양준언
    • Fire Science and Engineering
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    • v.17 no.1
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    • pp.40-45
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    • 2003
  • In this paper many vulnerable areas of the present fire PSA methodology were revealed to apply risk-informed fire protection to nuclear power plants. The results and insights from the fro PSA should be used as a part of a risk-informed decision making process rather than the complete technical basis for decision making. The degree of support and scope of applications is dependent on the accuracy and validity of the model used in the fire PSA. Accordingly; the usefulness of the fire PSA will increase as ongoing research and development efforts lead to improvements in the state of the art technology and as improvements in the implementation of the state of the art technology lead to more consistent results.

A Study of System Analysis Method for Seismic PSA of Nuclear Power Plants (원자력발전소 지진 PSA의 계통분석방법 개선 연구)

  • Lim, Hak Kyu
    • Journal of the Korean Society of Safety
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    • v.34 no.5
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    • pp.159-166
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    • 2019
  • The seismic PSA is to probabilistically estimate the potential damage that a large earthquake will cause to a nuclear power plant. It integrates the probabilistic seismic hazard analysis, seismic fragility analysis, and system analysis and is utilized to identify seismic vulnerability and improve seismic capacity of nuclear power plants. Recently, the seismic risk of domestic multi-unit nuclear power plant sites has been evaluated after the Great East Japan Earthquake and Gyeongju Earthquake in Korea. However, while the currently available methods for system analysis can derive basic required results of seismic PSA, they do not provide the detailed results required for the efficient improvement of seismic capacity. Therefore, for in-depth seismic risk evaluation, improved system analysis method for seismic PSA has become necessary. This study develops a system analysis method that is not only suitable for multi-unit seismic PSA but also provides risk information for the seismic capacity improvements. It will also contribute to the enhancement of the safety of nuclear power plants by identifying the seismic vulnerability using the detailed results of seismic PSA. In addition, this system analysis method can be applied to other external event PSAs, such as fire PSA and tsunami PSA, which require similar analysis.

Initiating Events Study of the First Extraction Cycle Process in a Model Reprocessing Plant

  • Wang, Renze;Zhang, Jiangang;Zhuang, Dajie;Feng, Zongyang
    • Journal of Radiation Protection and Research
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    • v.41 no.2
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    • pp.117-121
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    • 2016
  • 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.