摘要
核设计软件作为压水堆堆芯设计的基础软件,其计算准确性和可靠性直接影响反应堆设计的安全性和经济性,因此,核设计软件工程应用前需进行充分的验证与确认(V&V)。为建立适用于压水堆核设计软件的V&V技术,本研究结合我国自主化核设计软件安全评价与研发实践,开展核设计软件V&V技术研究,通过细化V&V技术指标,探讨V&V矩阵的构建,并选取自主化核设计软件包cosNU开展V&V关键技术应用研究,结果表明建立的V&V技术适用于核设计软件,可为我国自主化压水堆核设计软件的开发和应用提供重要参考。
As the basic code for the design of pressurized water reactor(PWR),the accuracy and reliability of nuclear design code directly impact the safety and economy of reactor design.Therefore,adequate verification and validation(V&V)are essential before the engineering application of nuclear design code.To establish a V&V framework suitable for PWR nuclear design code,this study integrates the safety assessment practices and development experience of China's self-developed nuclear design code.By refining the V&V technical indicators,this paper explores the construction of V&V matrix,and selects the self-developed nuclear design code package cosNU to carry out research on the application of V&V key techniques.The results show that the established V&V technology is applicable to nuclear design code and can provide important reference for the development and application of China's self-developed PWR nuclear design code.
作者
兰兵
潘昕怿
王业辉
Lan Bing;Pan Xinyi;Wang Yehui(Nuclear and Radiation Safety Center,MEE,Beijing,100082,China)
出处
《核动力工程》
北大核心
2025年第6期13-20,共8页
Nuclear Power Engineering
基金
核技术研发科研项目(科工二司[2020]1192号)。
关键词
自主化
压水堆
核设计软件
验证与确认(V&V)
矩阵
Self-developed
Pressurized water reactor
Nuclear design code
Verification and validation
Matrix
