该文讨论了如何应用概率安全评价(PSA)方法对核电站的维修风险进行管理,给出维修风险管理的4个阶段,并重点对其中的短期维修计划制订中的风险管理进行了详细分析,包括实施过程、评价的风险指标以及可以采取的一些风险管理行动,通过实际...该文讨论了如何应用概率安全评价(PSA)方法对核电站的维修风险进行管理,给出维修风险管理的4个阶段,并重点对其中的短期维修计划制订中的风险管理进行了详细分析,包括实施过程、评价的风险指标以及可以采取的一些风险管理行动,通过实际案例介绍了所开发的M RM(m a in tenance risk m on itor)系统。应用PSA方法,可以对电站各种风险来源以及缓解系统的能力进行综合分析,从而得到定量化的、全面的风险信息,实现对电站维修风险的有效控制和管理,避免出现高风险配置状态。展开更多
Success criteria analysis(SCA) bridges the gap between deterministic and probabilistic approaches for risk assessment of complex systems. To develop a risk model,SCA evaluates systems behaviour in response to postulat...Success criteria analysis(SCA) bridges the gap between deterministic and probabilistic approaches for risk assessment of complex systems. To develop a risk model,SCA evaluates systems behaviour in response to postulated accidents using deterministic approach to provide required information for the probabilistic model. A systematic framework is proposed in this article for extracting the front line systems success criteria. In this regard, available approaches are critically reviewed and technical challenges are discussed. Application of the proposed methodology is demonstrated on a typical Westinghouse-type nuclear power plant. Steam generator tube rupture is selected as the postulated accident. The methodology is comprehensive and general; therefore, it can be implemented on the other types of plants and complex systems.展开更多
Probabilistic safety assessment(PSA) is important in nuclear safety review and analysis. Because the design and physics of the fluoride salt-cooled high temperature reactor(FHR) differ greatly from the pressurized wat...Probabilistic safety assessment(PSA) is important in nuclear safety review and analysis. Because the design and physics of the fluoride salt-cooled high temperature reactor(FHR) differ greatly from the pressurized water reactor(PWR), the methods and steps of PSA in FHR should be studied. The high-temperature gascooled reactor(HTR-PM) and sodium-cooled fast reactors have built the PSA framework, and the framework to finish the PSA analysis. The FHR is compared with the PWR, HTR-PM and sodium-cooled fast reactors from the physics, design and safety. The PSA framework of FHR is discussed. In the FHR, the fuel and coolant combination provides large thermal margins to fuel damage(hundreds of degrees centigrade). The tristructuralisotropic(TRISO) as the fuel is independent in FHR core and its failure is limited for the core. The core damage in Level 1 PSA is of lower frequency. Levels 1 and 2 PSA are combined in the FHR PSA analysis. The initiating events analysis is the beginning, and the source term analysis and the release types are the target. Finally, Level3 PSA is done.展开更多
文摘该文讨论了如何应用概率安全评价(PSA)方法对核电站的维修风险进行管理,给出维修风险管理的4个阶段,并重点对其中的短期维修计划制订中的风险管理进行了详细分析,包括实施过程、评价的风险指标以及可以采取的一些风险管理行动,通过实际案例介绍了所开发的M RM(m a in tenance risk m on itor)系统。应用PSA方法,可以对电站各种风险来源以及缓解系统的能力进行综合分析,从而得到定量化的、全面的风险信息,实现对电站维修风险的有效控制和管理,避免出现高风险配置状态。
文摘Success criteria analysis(SCA) bridges the gap between deterministic and probabilistic approaches for risk assessment of complex systems. To develop a risk model,SCA evaluates systems behaviour in response to postulated accidents using deterministic approach to provide required information for the probabilistic model. A systematic framework is proposed in this article for extracting the front line systems success criteria. In this regard, available approaches are critically reviewed and technical challenges are discussed. Application of the proposed methodology is demonstrated on a typical Westinghouse-type nuclear power plant. Steam generator tube rupture is selected as the postulated accident. The methodology is comprehensive and general; therefore, it can be implemented on the other types of plants and complex systems.
基金Supported by Chinese Academy of Science Strategy Precursor Science and Technology Project(No.XDA0205050)
文摘Probabilistic safety assessment(PSA) is important in nuclear safety review and analysis. Because the design and physics of the fluoride salt-cooled high temperature reactor(FHR) differ greatly from the pressurized water reactor(PWR), the methods and steps of PSA in FHR should be studied. The high-temperature gascooled reactor(HTR-PM) and sodium-cooled fast reactors have built the PSA framework, and the framework to finish the PSA analysis. The FHR is compared with the PWR, HTR-PM and sodium-cooled fast reactors from the physics, design and safety. The PSA framework of FHR is discussed. In the FHR, the fuel and coolant combination provides large thermal margins to fuel damage(hundreds of degrees centigrade). The tristructuralisotropic(TRISO) as the fuel is independent in FHR core and its failure is limited for the core. The core damage in Level 1 PSA is of lower frequency. Levels 1 and 2 PSA are combined in the FHR PSA analysis. The initiating events analysis is the beginning, and the source term analysis and the release types are the target. Finally, Level3 PSA is done.
