混合堆芯中腐蚀产物沉积和一回路放射性水平的影响研究  

Study of Corrosion Products Deposition and Primary Circuit Source Term Levels in Hybrid Core

作　　者：邱斌 毛玉龙 严亚伦 胡艺嵩 蒙舒祺 QIU Bin;MAO Yulong;YAN Yalun;HU Yisong;MENG Shuqi(China Nuclear Power Technology Research Institute,Shenzhen of Guangdong Prov.518000,China)

机构地区：[1]中广核研究院有限公司,广东深圳518000

出　　处：《核科学与工程》2023年第1期25-29,共5页Nuclear Science and Engineering

基　　金：国家自然科学基金(U20B0211,针对堆芯氧化腐蚀产物材料-热工-中子行为的多物理耦合机理);国家自然科学基金(52171085,模拟压水堆一回路冷却剂中燃料包壳管表面污垢沉积行为与机理研究)。

摘　　要：为提升核电站的经济效益和满足高燃耗的需要,越来越多先进高效的核燃料组件被研究制造,并采用与原有组件混合布置的方式进行性能评估,从而形成混合堆芯。燃料污垢(CRUD,Chalk Rivers Unidentified Deposit)的沉积及一回路冷却剂中源项水平对于大修人员辐射防护有着重要影响,由于两种组件结构和材料上的差异,造成混合堆芯热工水力条件的变化,可能会对一回路腐蚀产物沉积和一回路放射性水平造成一定影响。本文针对某压水堆引入改进型AFA-3G燃料组件的过渡循环,对比计算了不同混合堆芯方案下的冷却剂源项和主管道停堆沉积源项(dose rate)水平。计算结果表明,不同混合堆芯方案下一回路冷却剂源项变化较小,引入改进型AFA-3G燃料组件对于降低主管道dose rate具有积极作用。In order to improve the economic benefits of nuclear power plants and meet the needs of high fuel consumption,more and more advanced and efficient nuclear fuel assemblies have been studied and manufactured.Mixing two fuel assemblies for performance evaluation will form hybrid core.Fuel CRUD deposition and source term level in primary coolant have great impact on radiation protection of overhauls.Due to the difference of structure and material between the two components,the thermal hydraulics conditions will change in hybrid core,which may affect the deposition of corrosion products and radioactivity levels in the primary circuit.In this paper,the coolant source term and main pipe dose rate of a PWR with an improved AFA-3G fuel assembly are compared and calculated under different hybrid core schemes.The calculated results show that the coolant source term levels under different hybrid core schemes is not significant,while the introduction of improved AFA-3G fuel assembly has positive effect on the reduction of main pipeline dose rate.

关 键 词：压水堆 混合堆芯 腐蚀产物 污垢 放射性源项 

分 类 号：TL364[核科学技术—核技术及应用]