Calculation of reactor accident safety goals
Calculation of reactor accident safety goals
复制标题
反应堆事故安全目标的计算
DOI：
10.1016/0951-8320(93)90038-z
复制
发表时间：
1993
影响因子：
8.1
通讯作者：
R. Breeding
中科院分区：
文献类型：
--
作者：
J. C. Helton;R. Breeding
美国核管理委员会正在制定核电站运行的安全目标。目前，这一发展产生了两个安全目标（个体早期死亡风险和个体潜在癌症死亡风险）和三个定量风险目标（严重事故频率、遏制失败的条件概率和大释放频率）。这些目标中的每一个都要求数量的期望值小于指定的值，其中期望是在分析中所需的不精确的已知参数上计算的。本报告描述了确定这些目标所涉及的计算，包括不确定性分析、灵敏度分析和期望值估计。作为NUREG-1150分析的一部分，对Surry核电站内部引发的事故进行的概率风险评估获得的结果用于说明。
The US Nuclear Regulatory Commission is in the process of developing safety goals for the operation of nuclear power plants. At present, two safety goals (individual early fatality risk and individual latent cancer fatality risk) and three quantitative risk goals (severe accident frequency, conditional probability of containment failure and large release frequency) are emerging from this development. Each of these goals requires that the expected value for a quantity be less than a specified value, where the expectation is calculated over imprecisely known parameters required in the analysis. This presentation provides a description of the calculations involved in the determination of these goals, including uncertainty analysis, sensitivity analysis and estimation of expected values. Results obtained in a probabilistic risk assessment performed for internally initiated accidents at the Surry Nuclear Power Station as part of the NUREG-1150 analyses are used for illustration.