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PROBABILISTIC RISK ASSESSMENT OF BOLTED DRY SPENTFUEL STORAGE CASKS: REVISITED

机译:重新审视的干式海绵状储物桶的概率风险评估:

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EPRI performed a Probabilistic Risk Assessment (PRA) of a bolted dry spent fuel storage cask inrnDecember of 2003. The study was performed for a bolted cask at a "generic" pressurized waterrnreactor (PWR) site. A generic site was chosen so that the widest variety of challenges could bernconsidered. The study calculated the annual individual radiological risk and consequencernassociated with a single cask lifecycle where the lifecycle is divided into three phases: loading,rnon-site transfer and on-site storage. The study used standard methods of PRA with the followingrnanalysis tasks: initiating events, data analysis, human reliability analysis, structural analysis,rnthermal-hydraulic analysis, accident sequence analysis and consequence analysis. The results ofrnthe original study show that risk is extremely low with no calculated early fatalities and a firstrnyear risk of latent cancer fatality of 3.5E-11 per year per cask. Subsequent year risk to therngeneral public is even lower; with, again no early fatalities and a cancer risk of 4.2E-12 per caskrnper year.rnIn 2004, EPRI revised the spent fuel cask PRA assessment to remove selected conservativernassumptions associated with various analysis simplifications. The updated study calculates arnfirst year cancer risk of 5.6E-13 per year per cask with no early fatalities. This corresponds to arn98% reduction in the latent cancer radiological risk. The update study calculates a subsequentrnyear risk is 1.7E-13 per year per cask. This corresponds to a decrease of 96% decrease in thernlatent cancer radiological risk.rnThe conclusions of the original study and its subsequent update confirm the extremely lowrnradiological risk to the general public of the dry storage of spent nuclear fuel. In addition, thernextremely low radiological risks associated with the dry storage of nuclear fuel indicates arnpotential for increased risk-informing of regulations associated with the design of spent nuclearrnfuel casks and facilities as well as the handling of spent nuclear fuel.
机译:EPRI在2003年12月对一个用螺栓固定的干乏燃料存储桶进行了概率风险评估(PRA)。该研究是在“通用”加压水反应堆(PWR)现场对一个用螺栓固定的桶进行的。选择了一个通用站点,以便可以考虑各种各样的挑战。该研究计算了与单个木桶生命周期相关的年度个体放射风险和后果,该生命周期分为三个阶段:装载,非现场转移和现场存储。该研究使用PRA的标准方法进行以下分析任务:启动事件,数据分析,人员可靠性分析,结构分析,热工水力分析,事故序列分析和后果分析。原始研究的结果表明,风险极低,没有预先计算的死亡人数,每年每桶每年潜在的癌症死亡人数为3.5E-11。来年以后,公众的风险更低。而且,没有早期死亡,每年每桶的癌症风险为4.2E-12。2004年,EPRI修改了乏燃料桶PRA评估,以消除与各种分析简化相关的选定保守假设。最新研究计算得出,每桶每年的第一年癌症风险为5.6E-13,无早期死亡。这对应于潜在放射线风险降低arn98%。更新研究计算出随后的风险是每桶每年1.7E-13。这相应地使潜在癌症的放射风险降低了96%。rn原始研究的结论及其后续更新证实,干电池乏燃料对公众的放射风险极低。此外,与核燃料干存储有关的极低的放射风险表明,有可能增加与乏核燃料容器和设施的设计以及乏核燃料的处理有关的法规的风险。

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