压水堆燃料组件压紧板弹簧力学分析模型开发与验证

DEVELOPMENT AND VALIDATION OF MECHANICAL ANALYSIS MODEL FOR THE HOLD-DOWN PLATE SPRING IN PWR FUEL ASSEMBLY

  • 摘要: 在反应堆运行期间,冷却剂流动所产生的水力提升力可能引起燃料组件向上跳动。为此,需在燃料组件上管座位置设置压紧系统,其核心部件为压紧板弹簧及相应的紧固螺钉。本文建立能够综合考虑辐照效应、温度效应与弹簧力学特性的力学分析模型,以评估压紧板弹簧在堆内辐照环境下的力学行为,并验证燃料组件压紧系统设计是否满足功能要求。基于该模型,开发了燃料组件压紧板弹簧力学分析软件(简称CACTUS),并采用核电厂池边检查实测数据对软件进行验证。软件计算结果能够包络电厂实测数据,满足工程应用中的保守性要求。该软件的自主研发解决了国内燃料组件压紧板弹簧力学分析工具缺失的问题,可为自主燃料组件顺利入堆提供支撑。

     

    Abstract: During reactor operation, the hydraulic lift generated by coolant flow may cause fuel assemblies to bounce upward. To address this, a hold-down system must be installed at the upper nozzle of the fuel assembly, with its core components being the hold-down plate spring and corresponding fastening screws. This paper establishes a mechanical analysis model that comprehensively considers irradiation effects, temperature effects, and the mechanical properties of the spring to evaluate the mechanical behavior of the hold-down plate spring under in-reactor irradiation conditions, and to verify whether the design of the fuel assembly hold-down system meets functional requirements. Based on the above model, a mechanical analysis software for fuel assembly hold-down plate springs (referred to as “CACTUS") was developed and validated using measured data from in-pool inspection at nuclear power plants. The software calculation results can envelop the actual measured data from power plants, satisfying the conservatism requirements in engineering applications. The independent development of this software addresses the lack of domestic tools for mechanical analysis of fuel assembly hold-down plate springs, providing support for the successful loading of independently developed fuel assemblies into reactors.

     

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