独立乏燃料贮存装置垫块分析与设计现状综述

Gunup Kwon, Khaled J. Ata
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引用次数: 0

摘要

核电站的乏燃料最初储存在乏燃料池中。然后,水冷燃料被转移到一个混凝土或钢桶中,并运输到燃料处理大楼(FHB)或反应堆大楼(RB)外进行长期现场储存。用过的燃料桶通常储存在一个板上级发射台上。根据美国核管理委员会NUREG-1536和NUREG-1567设计的板级发射台。这两个标准审查计划为监管机构审查桶存储系统许可证申请提供指导。ISFSI平台的分析与设计必须考虑各种载荷条件,如地震和龙卷风载荷以及正常运行的载荷条件。ISFSI垫层的地震分析需要考虑垫层与支承土之间的相互作用。还必须考虑在发射台上的各种桶装载配置。由于缺乏具体的指导方针,许多ISFSI垫设计显示过于保守的加固。本研究为核工业中典型使用的ISFSI衬垫的设计提供了指导方针和程序。人们认为,本研究中描述的指导方针和实践有助于设计工程师理解NRC标准评审计划中提供的一般指导。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Overview of Current Practice for Analysis and Design of Independent Spent Fuel Storage Installation Pads
Nuclear power plant spent fuels are initially stored in the spent fuel pool. Then, the water cooled fuels are transferred in a concrete or steel cask and transported outside of the Fuel Handling Building (FHB) or the Reactor Building (RB) for long term on site storage. The spent fuel casks are typically stored on a slab-on-grade pad. The slab-on-grade pad is designed according to the U.S. Nuclear Regulatory Commission NUREG-1536 and NUREG-1567. The two Standard Review Plans provide guidance to the regulators for the review of cask storage system license application. The ISFSI pad analysis and design have to consider various loading conditions, such as earthquake and tornado loadings as well as normal operating loading conditions. Seismic analysis of the ISFSI pad requires considering interaction between the pad and the supporting soil. Various cask loading configurations on the pad also have to be considered. Due to the lack of specific guidelines, many ISFSI pad designs show overly conservative reinforcement. This study provides guidelines and procedure for the design of the ISFSI pad that are typically used in the nuclear industry. It is considered that the guidelines and practices described in this study help design engineers understand general guidance provided in the NRC Standard Review Plans.
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