快堆系统分析程序FASYS堆芯分析模块验证

Verification of Core Analysis Module for Fast Reactor System Analysis Code FASYS

中国原子能科学研究院自主开发了快堆系统分析程序FASYS,已用于中国实验快堆的调试试验分析,目前正用于中国示范快堆的事故分析。FASYS程序包含堆芯分析模块、一二回路模块、事故余热排出系统模块等,其中堆芯分析模块包括点堆、衰变热、反应性反馈、堆芯通道热工水力模型等。本文采用解析解、DINROS程序、SAS4A/SASSYS-1程序验证FASYS程序的点堆模型;采用SAS4A/SASSYS-1程序验证FASYS程序的衰变热、反应性反馈和堆芯通道热工水力模型,各模型的验证结果均符合良好。对FASYS程序堆芯分析模块各模型的计算偏差和整体计算偏差进行评估,为中国示范快堆的事故分析提供参考。

Fast reactor system analysis code FASYS is developed by China Institute of Atomic Energy, which has been used for commissioning test analysis of China Experimental Fast Reactor and is currently being used for accident analysis of China Demonstration Fast Reactor. The FASYS code includes core analysis module, primary and secondary loop modules, and decay heat removal system module, etc. The core analysis module includes point reactor model, decay heat model, reactivity feedback model, and thermal-hydraulic model of core channel, etc. The point reactor model of FASYS code was validated by comparing with analytical solution result, DINROS code result and SAS4 A/SASSYS-1 code result. And decay heat model, reactivity feedback model and core channel thermal-hydraulic model of FASYS code were validated by comparing with SAS4 A/SASSYS-1 code result. The validation results of each model are in good agreement. The calculation deviation of each model for the core analysis module of FASYS code was evaluated. And the proposal for China Demonstration Fast Reactor accident analysis deviation evaluation was given.