目的 为应对我国大型乏燃料后处理设施年处理量激增、供需矛盾凸显的急迫需求,破解传统单组乏燃料组件转运工艺效率低、操作风险高、工程与运行成本高的突出痛点,研发适配国内压水堆核电站典型乏燃料组件的贮运吊篮,实现乏燃料组件高效、安全的接收、贮存与转运。方法 依据后处理厂乏燃料接收贮存系统功能需求、安全分级、接口参数及整体布置,明确吊篮设计准则与核心安全要求,建立设计参数与安全准则的对应映射关系;以国内主流AFA-3G乏燃料组件为基准,兼容12、14英尺（1英尺=30.48厘米）规格组件,采用模块化设计理念开展结构研发,同步完成临界安全、热工水力、结构强度、抗震性能等核心维度参数设计与校核。结果 研发的吊篮单台可容纳9组乏燃料组件,适配AP1000堆型最长组件;采用硼铝复合中子吸收材料与9单元模块化小室三明治结构,配套导向、可调支腿及燕尾槽互锁结构,可形成4×6稳定贮存组,显著降低转运频次与组件跌落风险。结论 吊篮设计符合核安全法规标准,满足后处理设施乏燃料接收贮存工艺与安全需求,有效提升转运效率与工程经济性,为同类设备自主化研发提供技术参考与设计依据。
Abstract
The work aims to develop a storage and transportation basket adapted to typical spent fuel assemblies of domestic PWR nuclear power plants to realize efficient and safe reception, storage and transfer of spent fuel assemblies to meet the annual processing capacity requirements of large-scale spent fuel reprocessing plants in China and address the pain points of low efficiency, high operational risks, and high engineering and operation costs of the traditional single spent fuel assembly transfer process. According to the functional requirements, safety classification, interface parameters and overall layout of the spent fuel reception and storage system of the reprocessing plant, the design criteria and core safety requirements of the basket were clarified, and the mapping relationship between design parameters and safety criteria was established. Based on the mainstream domestic AFA-3G spent fuel assembly, compatible with 12-foot and 14-foot (1 foot = 30.48 cm) specifications, the structure was developed with a modular design concept, and parameter design and verification of core dimensions such as criticality safety, thermal hydraulics, structural strength and seismic performance were completed simultaneously. The developed basket could hold 9 sets of spent fuel assemblies, adapting to the longest assembly of AP1000 reactors. It was made of boron-aluminum composite neutron absorbing material, designed into a sandwich structure of 9-unit modular cells and equipped with guide structure, adjustable supporting pads and dovetail groove interlocking structure, forming a stable 4×6 storage group, significantly reducing transfer frequency and assembly drop risk. The basket design complies with nuclear safety regulations and standards, meeting the technological and safety requirements of spent fuel reception and storage in reprocessing plants, effectively improving transfer efficiency and engineering economy, and providing technical reference and a design basis for independent R&D of similar equipment.
关键词
后处理 /
乏燃料贮运吊篮 /
设计准则 /
结构设计 /
安全分析
Key words
reprocessing /
spent fuel basket /
design criteria /
structural design /
safety analysis
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