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Probabilistic Risk Assessment Standard for Advanced Non-Light Water Reactor Nuclear Power Plants 先进非轻水堆核电站概率风险评估标准
发布日期: 2021-02-08
本标准规定了用于支持先进非轻水堆(非轻水堆)核电厂(NPP)风险决策的概率风险评估(PRA)要求,并规定了将这些要求应用于特定应用的方法。支持将本标准应用于PRA,用于各种反应堆设计,如模块化高温气冷反应堆(MHTGR)、液态金属冷却快堆(LMR)、熔盐反应堆(MSR)、微型反应堆- 基于非轻水堆技术的反应堆和小型模块化反应堆,以及其他先进的非轻水堆,本标准中的要求是在反应堆技术的基础上制定的。本标准取代了ASME/ANS RAS-1.4-2013[1-1]2的早期试用版本,并纳入了使用该版本的试点研究的反馈。
This Standard states the requirements for probabilistic risk assessments (PRAs) used to support risk-informed decisions for advanced non-light water reactor (non-LWR) nuclear power plants (NPPs) and prescribes a method for applying these requirements for specific applications. To support the application of this Standard to PRAs for a diverse set of reactor designs such as modular high-temperature gas-cooled reactors (MHTGRs), liquid metal-cooled fast reactors (LMRs), molten salt reactors (MSRs), micro-reactors and small modular reactors based on non-LWR technology, and other advanced non-LWRs, the requirements in this Standard were developed on a reactor-technology-inclusive basis. This Standard supersedes an earlier trial use version ASME/ANS RAS- 1.4-2013 [1-1]2and incorporates feedback from pilot studies using that version.
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发布单位或类别: 美国-美国机械工程师协会
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