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一、引言美国联邦法规第10篇50章(10CFR Port 50)50·34节中要求,每个希望获得施工许可证或运行执照的申报者,应提供对反应堆结构、系统及部件的设计和性能所进行的分析与评价,以便估计反应堆运行对公众健康及安全造成的危害。设计基准失水事故乃是用于评价反应堆结构、系统及部件是否满足有关公众健康和安全所要求的若干种假想事故之一。本指南给出用于评价压水堆失水事故放射性后果的诸多可接受的假设。在某
I. INTRODUCTION Section 10 CFR 50 (10 CFR Port 50) requires that each applicant wishing to obtain a construction permit or operating license shall provide design and performance of the reactor structure, system and components Analysis and evaluation carried out in order to estimate the health hazards caused by the operation of the reactor and the safety of the public. Design Basis A water-loss accident is one of several hypothetical accidents that are required to assess whether the structure, systems and components of a reactor satisfy the requirements of public health and safety. This guide gives a number of accepted assumptions for assessing the radiological consequences of a PWR accident. In a