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1.
核电站反应堆冷却剂系统的排放量的确定是硼回收系统设计运行能力的基本输入。压水堆核电厂硼回收系统的前贮槽、中间贮槽等重要设备容量均以该数值为基础进行设计。本文通过理论分析计算得出了压水堆核电厂硼回收系统的设计基准所需的循环冷却剂排放量,为该系统的工程设计提供了重要的设计依据和分析基础。  相似文献   

2.
论文的目的是研究重水堆钍铀燃料增殖循环方案。基于前期设计的技术路线,以CANDU-6堆芯为参考堆芯,研究了钍基堆芯燃料管理策略,分析了中子学特性,并对乏燃料特性进行了评估,包括放射性毒性、衰变热和伽马射线。在此基础上,建立了钍铀燃料增殖循环方案,其在可持续性关键指标方面优于常规天然铀一次通过循环。  相似文献   

3.
In PWRs, loss of decay heat removal (DHR) during reactor shutdown with the reactor coolant system (RCS) partially drained may result in core boiling in a short time. The subsequent RCS pressurization could prevent water flow into the RCS by gravity feed and consequently the core would be uncovered. This paper analyzes U.S. PWR operating experience involving the DHR loss in such reduced inventory conditions.

Between 1976 and 1990, reported were a total of 63 loss of DHR events which occurred during reactor shutdown with the RCS inventory reduced. Review of the event reports indicated that many loss of DHR events in reduced inventory conditions resulted from air entrainment into the DHR pumps due to lowering the reactor water level too far, loss of coolant inventory, increased pump flow and so on.

The coolant heatup rates were evaluated for 12 events with use of the data such as the time elapsed from reactor shutdown actually reported. The calculated results were in reasonably good agreement with the observed ones and showed that core boiling would take place within 1 h even if the DHR loss would occur in the late stage of shutdown (for example, 30 days after the shutdown).  相似文献   

4.
1997年,美国核管会(NRC)在对被动与改进型先进轻水堆的应急计划进行评估后指出,在现有的技术框架下先进轻水堆的应急计划应当保持不变,但也表明如果考虑到严重事故发生概率更低,事故的延迟时间更长,则有可能简化对先进轻水堆的应急计划要求,减小应急计划区。这意味着,如果在事故选择时不考虑低于某一概率截断值的事故,则有可能对先进轻水堆核电厂应急计划区的划分产生较大的影响。本文以AP1000核电机组为例,参考美国NUREG-0396的方法,使用MACCS程序对选取不同事故概率截断值可能产生的影响进行研究。研究结果表明,只有当概率截断值高于某些相对概率较大、而后果较为严重的事故的发生概率时,才会对先进轻水堆应急计划区的划分产生较大影响。  相似文献   

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