核反应堆堆芯物理分析技术自主化研究及在商用压水堆中的应用  

Autonomous research on reactor core physical analysis technology and its application in commercial pressurized water reactors

作　　者：吴宏春[1] 冯昊 祖铁军[1] 肖喆文 瞿平 万承辉 黄义涵 马宇图 汤勇强 WU HongChun;FENG Hao;ZU TieJun;XIAO ZheWen;QU Ping;WAN ChengHui;HUANG YiHan;MA YuTu;TANG YongQiang(School of Nuclear Science and Technology,Xi’an Jiaotong University,Xi’an 710049,China;Chongqing Jian’an Instruments Co.,Ltd.,Chongqing 400060,China)

机构地区：[1]西安交通大学核科学与技术学院,西安710049 [2]重庆建安仪器有限责任公司,重庆400060

出　　处：《中国科学:技术科学》2025年第1期66-76,共11页Scientia Sinica(Technologica)

基　　金：国家自然科学基金(批准号:12075183);国家重点研发计划(编号:2022YFB1902600)资助项目。

摘　　要：核反应堆是核能应用的核心装置,核反应堆堆芯物理分析是核反应堆设计和运维的核心技术.但长期以来,我国核反应堆堆芯物理分析软件主要依赖进口,在核能技术全面自主化的进程中,核反应堆物理分析软件自主化已成为亟需解决的重大课题.本文介绍了从源头评价核数据库、到应用核数据库制作、再到堆芯物理分析的全过程自主化研究成果,并在我国现役的华龙一号、M310及其改进型、VVER1000等代表性压水堆堆芯分析中实现了工业应用.应用结果表明:基于国产评价核数据库CENDL-3.2、国产核数据处理软件NECP-Atlas和国产压水堆堆芯物理分析软件Bamboo-C,对我国各种型号的压水堆堆芯关键安全参数的计算值与实测值之间的误差均满足工程应用需求,为核反应堆堆芯物理分析技术全过程国产化替代奠定了基础.Nuclear reactors play a central role in nuclear energy applications,with physical analysis being crucial for their design,operation,and maintenance.Historically,China has relied heavily on imported nuclear reactor physical analysis codes.As the nation strives for independent nuclear energy technology,developing proprietary nuclear reactor physical analysis codes has become a pressing need.In this paper,a series of works are introduced,including the evaluated nuclear data file CENDL-3.2,the nuclear data library generated by the NECP-Atlas processing code,and core physic analysis performed by Bamboo-C.These elements create an integrated system that covers the entire process of nuclear reactor physics analysis.The system is applied to analyze representative pressurized water reactors such as the HPR1000,M310 and its improved unit,and VVER1000 operated in China.Results show that the errors between calculated results from the system comprising CENDL-3.2,NECP-Atlas,and Bamboo-C and the measured values of key safety parameters for the PWR core are within acceptable limits for engineering applications.This confirms that the system is suitable for fully localizing the process of nuclear reactor core physical analysis technology.

关 键 词：评价核数据库 热散射律 核数据库制作 堆芯物理分析 

分 类 号：TL351.1[核科学技术—核技术及应用] TM623.91[电气工程—电力系统及自动化]