基于LOCUST程序的事故容错燃料大破口失水事故安全分析  

Safety Analysis on Accident-tolerant Fuel during LBLOCA Based on LOCUST Code

作　　者：熊怡然 马泽华 梁任 林支康 琚忠云 彭振驯 Xiong Yiran;Ma Zehua;Liang Ren;Lin Zhikang;Ju Zhongyun;Peng Zhenxun(China Nuclear Power Technology Research Institute Co.,Ltd.,Shenzhen,Guangdong,518000,China)

机构地区：[1]中广核研究院有限公司,广东深圳518000

出　　处：《核动力工程》2024年第S01期138-144,共7页Nuclear Power Engineering

基　　金：中国博士后科学基金项目(2022M712983)。

摘　　要：事故容错燃料(ATF)旨在提高核燃料在正常运行工况和事故工况下的安全特性。为评估ATF在大型商业压水堆大破口失水事故(LBLOCA)中的安全性能,本研究基于LOCUST程序,对采用UO_(2)-Cr涂层锆合金包壳燃料的华龙一号(HPR1000)在LBLOCA不同阶段的主要热工水力现象和关键影响参数进行了分析和说明。结果表明,相比传统的UO_(2)-Zr燃料,UO_(2)-Cr涂层锆合金包壳燃料能降低LBLOCA下的包壳峰值温度(PCT)和包壳氧化膜厚度,提升了事故安全裕量,具有更好的事故容错性。Accident tolerant fuel(ATF)aims to improve the safety characteristics of nuclear fuel under normal operating conditions and accidents.In order to evaluate the safety performance of ATF in large break loss-of-coolant accident(LBLOCA)of large commercial pressurized water reactor,based on LOCUST code,this study analyzes and describes the main thermal hydraulic phenomena and key influencing parameters of HPR1000 using using UO_(2)-Cr coated zirconium alloy cladding fuel at different stages of LBLOCA.The results indicate that compared to the traditional UO_(2)-Zr fuel,UO_(2)-Cr coated zirconium alloy cladding fuel can reduce the peak cladding temperature(PCT)and the thickness of cladding oxide film under LBLOCA,improve the safety margin in accidents,and have better accident-tolerance characteristics.

关 键 词：事故容错燃料(ATF) 大破口失水事故(LBLOCA) 华龙一号(HPR1000) 安全分析 

分 类 号：TL33[核科学技术—核技术及应用]