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Ramifications of Risk Measures in Implementing Quantitative Performance Assessment for the Proposed Radioactive Waste Repository at Yucca Mountain, Nevada, USA

机译:美国内华达州尤卡山拟议放射性废物处置库实施定量性能评估的风险措施的后果

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As part of its preparation to review a potential license application from the U.S. Department of Energy (DOE), the U.S. Nuclear Regulatory Commission (NRC) is examining the performance of the proposed Yucca Mountain nuclear waste repository. In this regard, we evaluated postclosure repository performance using Monte Carlo analyses with an NRC-developed system model that has 950 input parameters, of which 330 are sampled to represent system uncertainties. The quantitative compliance criterion for dose was established by NRC to protect inhabitants who might be exposed to any releases from the repository. The NRC criterion limits the peak-of-the-mean dose, which in our analysis is estimated by averaging the potential exposure at any instant in time for all Monte Carlo realizations, and then determining the maximum value of the mean curve within 10,000 years, the compliance period. This procedure contrasts in important ways with a more common measure of risk based on the mean of the ensemble of peaks from each Monte Carlo realization. The NRC chose the former (peak-of-the-mean) because it more correctly represents the risk to an exposed individual. Procedures for calculating risk in the expected case of slow repository degradation differ from those for low-probability cases of disruption by external forces such as volcanism. We also explored the possibility of risk dilution (i.e., lower calculated risk) that could result from arbitrarily defining wide probability distributions for certain parameters. Finally, our sensitivity analyses to identify influential parameters used two approaches: (1) the ensemble of doses from each Monte Carlo realization at the time of the peak risk (i.e., peak-of-the-mean) and (2) the ensemble of peak doses calculated from each realization within 10,000 years. The latter measure appears to have more discriminatory power than the former for many parameters (based on the greater magnitude of the sensitivity coefficient), but can yield different rankings, especially for parameters that influence the timing of releases.
机译:作为准备审查美国能源部(DOE)潜在许可申请的一部分,美国核监管委员会(NRC)正在审查拟议的丝兰山核废料储存库的性能。在这方面,我们使用具有90个输入参数的NRC开发的系统模型,使用蒙特卡洛分析对封闭后存储库的性能进行了评估,该模型具有950个输入参数,其中330个被采样以表示系统不确定性。 NRC建立了剂量的定量符合标准,以保护可能暴露于储存库中任何释放物的居民。 NRC标准限制了平均剂量峰值,在我们的分析中,该平均剂量是通过对所有蒙特卡洛实现的任何时刻的平均潜在暴露量进行平均,然后确定10,000年内的平均曲线的最大值来估算的,遵守期限。该过程以重要的方式与基于每个蒙特卡洛实现的峰值集合的平均值的更常见风险度量形成对比。 NRC之所以选择前者(均值峰值),是因为它更正确地代表了暴露个体的风险。在存储库缓慢降级的预期情况下,计算风险的程序与低概率情况下由于火山等外力破坏而计算的程序不同。我们还探讨了由于任意定义某些参数的较大概率分布而可能导致的风险稀释(即较低的计算风险)的可能性。最后,我们通过敏感性分析来确定影响参数,使用了两种方法:(1)在风险达到峰值(即均值峰值)时,从每个蒙特卡洛实现中获得的剂量集合;以及(2)在10,000年内从每次实现计算出的最大剂量。对于许多参数(基于更大的灵敏度系数),后一种措施似乎具有比前者更大的区分能力,但是可以产生不同的等级,尤其是对于影响释放时间的参数。

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