压水堆核电厂裂变产物包壳破口释放机理的研究与验证  

Study and Verification of the Fission Product Release Mechanism from the Fuel Cladding Defect of PWR

作　　者：郭润春 吕炜枫 高耀毅 熊军 GUO Runchun;LYU Weifeng;GAO Yaoyi;Xiong Jun(State Key Laboratory of Nuclear Power Safety Technology and Equipment,Shenzhen of Guangdong Prov.518172,China;China Nuclear Power Engineering CO.,Ltd.,Shenzhen of Guangdong Prov.518172,China)

机构地区：[1]核电安全技术与装备全国重点实验室,广东深圳518172 [2]中广核工程有限公司,广东深圳518172

出　　处：《核科学与工程》2023年第6期1258-1265,共8页Nuclear Science and Engineering

摘　　要：燃料棒包壳间隙内裂变产物通过包壳破口向一回路冷却剂的释放过程为一回路冷却剂源项计算的关键机理,其包壳释放系数为各一回路源项计算软件中的核心参数。基于一阶动力学模型,建立了一套可描述国内典型压水堆核电厂燃料包壳出现极小破口、小破口、中等破口及大破口情况下的裂变产物包壳释放模型并使用国内典型压水堆核电厂15个燃料破损循环的一回路放化取样数据进行验证,结果表明^(133)Xe、^(131)I、^(133)I等关键核素的计算值与核电厂放化数据实测值符合程度较高。建立的包壳释放模型可应用于一回路冷却剂源项计算软件以及燃料包壳破损诊断软件。The release of fission products in the fuel cladding gap to the primary coolant through the defect is the key mechanism for the calculation of the primary coolant fission products source term,and the gap-to-coolant release coefficient is the key parameter in the source term calculation code.Based on the first-order kinetic model,a model describing the release of fission product from the fuel cladding under the conditions of micro,small,medium and large defects in Chinese typical pressurized water reactors has been established,gap-to-coolant release coefficient is derived and validated by using the primary coolant radiochemical sampling data of 15 fuel failure cycles of Chinese typical pressurized water reactors.The results show that the calculation results of key isotopes of Xe,Kr,I and Cs are in good agreement with radiochemical sampling data and can be applied to the primary coolant fission product source term calculation program and the fuel failures diagnosis program.

关 键 词：裂变产物 包壳破口释放机理 压水堆核电厂 

分 类 号：TL929[核科学技术—核燃料循环与材料]