大型先进压水堆弹棒事故模拟及敏感性分析  

Control rod ejection accident simulation and sensitivity analysis of large advanced pressurized water reactor

作　　者：兰兵 潘昕怿 于世和[2] 依岩 LAN Bing;PAN Xinyi;YU Shihe;YI Yan(Nuclear and Radiation Safety Center,Beijing 100082,China;Shanghai Institute of Applied Physics,Chinese Academy of Sciences,Shanghai 201800,China)

机构地区：[1]生态环境部核与辐射安全中心,北京100082 [2]中国科学院上海应用物理研究所,上海201800

出　　处：《核技术》2023年第2期68-74,共7页Nuclear Techniques

基　　金：国家科技重大专项(No.2019ZX06005001);国家重点研发计划(No.2018YFB1900305)资助。

摘　　要：相对于传统堆型,大型非能动先进压水堆堆芯设计具有重大改变,这些改变对弹棒事故分析具有重要影响,进而影响反应堆的安全性。通过选取典型的四类工况(寿期初满功率、寿期初零功率、寿期末满功率和寿期末零功率),利用中子动力学软件和燃料性能分析程序开展大型先进压水堆CAP1400的弹棒事故模拟计算,验证大型先进压水堆弹棒事故工况下的安全性,并针对弹棒事故分析关键输入参数开展敏感性分析。计算分析结果表明:大型先进压水堆发生弹棒事故时,其结果能够满足验收准则的要求,反应堆处于安全可控状态;弹棒事故分析中功率峰值对弹棒价值最敏感,事故分析结果对停堆反应性敏感性较小。[Background] Compared with the traditional pressurized water reactor(PWR), the core design of large advanced PWR CAP1400 has significant changes, such as the increase in the number of fuel assemblies, the increase in reactor power, the increase in the average temperature of core coolant, etc. These changes have an important impact on the results of rod ejection accident, and then affect the safety of reactor. [Purpose] This study aims to verify the safety of large advanced PWR under rod ejection accident condition and the influence of key input parameters on accident analysis results. [Methods] Based on the neutron dynamics software TWINKLE and fuel performance analysis program FACTRAN, the typical four types of operating conditions, including the beginning of life the hot full power and the hot zero power, the end of life the hot full power and the hot zero power, were selected to carry out the simulation calculation of the control rod ejection accident analysis for large advanced PWR, and the sensitivity analysis of key input parameters of rod ejection accident conditions was performed by using the direct numerical perturbation method. [Results & Conclusions] Simulation results show that the power peak is the most sensitive to the worth of rod ejection, but less sensitive to shutdown reactivity. The consequences of the control rod ejection accident designed for CAP1400 can meet the requirements of acceptance criteria and the reactor is in the safe and controllable state.

关 键 词：压水堆 弹棒事故 安全性 敏感性 功率峰值 

分 类 号：TL364.4[核科学技术—核技术及应用]