严重事故分析程序MOSAP堆内早期现象分析模型验证  

Validation of the early in-vessel phenomenon analysis model of the severe accident analysis code MOSAP

作　　者：郭超 吴世浩 赵传奇 张亚培[2] 魏超 巫英伟[2] GUO Chao;WU Shihao;ZHAO Chuanqi;ZHANG Yapei;WEI Chao;WU Yingwei(Nuclear and Radiation Safety Center,Beijing 100082,China;Xi'an Jiaotong University,Xi'an 710049,China)

机构地区：[1]生态环境部核与辐射安全中心,北京100082 [2]西安交通大学,西安710049

出　　处：《核技术》2024年第12期103-112,共10页Nuclear Techniques

基　　金：国家重点研发计划项目(No.2019YFB1900700)资助。

摘　　要：为了对国内自主开发的反应堆严重事故一体化分析程序MOSAP(Modular Severe accident Analysis Program)的堆内早期现象分析模型进行验证,分别利用MOSAP程序和国际通用严重事故分析程序,对国际标准题ISP31和ISP46实验进行了建模计算。将MOSAP程序计算获得的燃料和控制棒温度、氢气产生以及主要放射性核素释放率等参数计算结果,与实验和国际通用程序计算结果进行对比和分析。结果表明:MOSAP程序计算结果与实验和国际通用程序计算结果均符合性良好,主要参数计算值与实验值偏差在20%以内。表明自主开发的MOSAP程序能够实现堆芯过热,燃料、包壳和控制棒氧化,以及裂变产物释放等严重事故堆内主要早期现象的模拟。[Background]Severe accident is complex coupling processes involving multiple components,phases,and physical fields,and related research is a complex and challenging systematic engineering project.In recent years,relevant scientific research institutions have placed greater emphasis on the development of integrated analysis codes for severe accident in order to address the issue of program autonomy,and modular severe accident analysis program(MOSAP)is one of them independently developed by Xi'an Jiaotong University,China.[Purpose]This study aims to validate the early in-vessel phenomenon analysis model of the self-developed integrated analysis code MOSAP for severe accident.[Methods]The MOSAP code and the internationally recognized severe accident analysis code were used to model and calculate experiments on international standard questions ISP31 and ISP46.The calculation results of fuel and control rod temperature,hydrogen production,and major radioactive nuclide release rates obtained by the MOSAP were compared and analyzed with experimental and internationally recognized code calculation results.[Results]The results show that the MOSAP calculation results are in good agreement with the experimental and internationally recognized code calculation results,and the deviation between the main parameter calculation values and the experimental values is within 20%.[Conclusions]The self-developed code MOSAP can simulate the early in-vessel phenomena of severe accident such as core overheating,fuel,cladding,and control rod oxidation,as well as fission product release.

关 键 词：严重事故 堆内现象 国际标准题 程序验证 

分 类 号：TL364[核科学技术—核技术及应用]