核淡化厂SAR的具体内容

A. Doval, Nestor A. Masriera, C. Mazufri
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引用次数: 2

摘要

虽然人们普遍认为,将海水淡化厂(DP)与核电站(NPP)耦合不会造成任何重大的额外危害,但必须明确地将其视为对设计的重大修改,因此需要发布特别版本的设施安全分析报告(SAR)。关于核脱盐的一般安全方面的文件已经有了,包括标准和适用的要求,以及评估潜在暴露的方法。在本报告中,将具体分析在编写核海水淡化厂安全分析报告时应考虑的主要特点。为清楚起见,我们假设存在一个现有的NPP特别行政区,只考虑特别行政区中要包括的额外信息。这些附加信息的范围很大程度上取决于海水淡化技术和耦合方案。因此,核脱盐过程耦合的类型,即热、机械或电,必须被定义为先前的任务。对SAR的主要内容进行彻底的审查,以便确定相关的点(如果有的话),这些点需要包含在处理耦合的每章中。SAR章节的内容和范围是根据原子能机构的指导方针考虑的。作为安全报告的一部分,必须包括可能的意外事件分析及其后果,因此,必须评估通过DP释放污染的信封情况的确定性分析。分析了这一安全案例的阐述,并提出了量化污染传输机制所需的模型的合理范围。最后,通过使用建模工具DESNU,介绍了用于核电厂确定性安全分析并有效适用于核脱盐厂的最普遍接受的技术和规范。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Specific contents of the SAR for a nuclear desalination plant
Although it is widely accepted that coupling a Desalination Plant (DP) to a Nuclear Power Plant (NPP) does not pose any significant additional hazard, it must clearly be considered as a major modification of the design and, therefore, requires issuing an ad hoc version of the Facility Safety Analysis Report (SAR). Documentation is already available covering general safety aspects of nuclear desalination, including standards and applicable requirements, as well as methodologies for assessing potential exposure. In this report, a specific analysis of the main features to be considered for producing the safety analysis report of a nuclear desalination plant will be presented. For the sake of clarity, it is assumed that there is an existing SAR of the NPP and only the additional information to be included in the SAR will be considered. The scope of this additional information is extremely dependent on the desalination technology and the coupling scheme. Therefore, the kind of nuclear desalination process coupling, i.e. thermal, mechanical or electrical, must be defined as a previous task. A thorough review of the main contents of the SAR is performed in order to identify the relevant points, if any, which need to be included in every chapter coping with the coupling. The SAR chapters' content and scope are considered in accordance with IAEA guidelines. As part of the safety report, possible accidental event analysis and their consequences must be included and, therefore, the deterministic analysis of an envelope case of contamination release through the DP must be assessed. The elaboration of this safety case is analysed, and the justified scope of the models needed to quantify the contamination transport mechanisms is presented. Finally, the most commonly accepted techniques and codes, used for the deterministic safety analysis of nuclear plants and effectively applicable to nuclear desalination plants, are presented by the use of the modelling tool DESNU.
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