不同冷却剂对铅冷快堆堆芯物理参数的影响与分析  

Impact and Analysis of Different Coolants on the Core Physics Parameters of Lead-cooled Fast Reactors

作　　者：李凯旋 张子雄 魏强林[1,2] 刘义保 张勤拓[1,2] 赵石 LI Kai-xuan;ZHANG Zi-xiong;WEI Qiang-lin;LIU Yi-bao;ZHANG Qin-tuo;ZHAO Shi(Engineering Research Center of Nuclear Technology Application,Ministry of Education(East China University of Technology),Nanchang 330013,China;School of Nuclear Science and Engineering,East China University of Technology,Nanchang 330013,China;Taishan Nuclear Power Joint Venture Co.,Ltd.,Taishan 529228,China)

机构地区：[1]东华理工大学核技术应用教育部工程研究中心,南昌330013 [2]东华理工大学核科学与工程学院,南昌330013 [3]台山核电合营有限公司,台山529228

出　　处：《科学技术与工程》2024年第28期12152-12158,共7页Science Technology and Engineering

基　　金：国家自然科学基金(11965001);核技术应用教育部工程研究中心开放基金(HJSJYB2021-9);东华理工大学博士启动基金(DHBK2021005);江西省质谱科学与仪器重点实验室开放基金(JXMS202111)。

摘　　要：随着中国能源结构深化改革的推进,积极发展核能已成为主要趋势。第四代核能系统代表着核电发展的趋势和技术前沿,因此铅冷快中子反应堆的研究在国际上备受关注。基于麻省理工学院(Massachusetts Institute of Technology,MIT)开发的反应堆蒙特卡洛中子输运方程开源软件OpenMC,以铅冷快中子欧洲示范堆(advanced lead fast reactor European demonstrator,ALFRED)为研究对象,选取两种不同的堆芯冷却剂开展铅冷快堆堆芯物理计算。结果表明:在装载相同燃料的情况下,采用铅-铋冷却剂可以提高堆芯的初始反应性271×10-5;堆芯在正常商运状态下具有更高的堆芯有效缓发中子份额;堆芯的中子能谱更宽、更硬;对于燃料中的239 Pu核素,燃烧效果更好。因此,ALFRED堆芯采用铅-铋合金冷却剂时,具有更高的有效增殖因子,有望提高堆芯的控制性和燃耗性能,并有效减少放射性废物的产生。研究成果为铅冷快中子反应堆欧洲示范堆堆芯设计和性能优化提供了有益的参考。With the deepening reform of China's energy structure,actively developing nuclear energy has become a major trend.The fourth-generation nuclear energy system represents the trend and technological frontier of nuclear power development,therefore,the research on lead-cooled fast neutron reactors has attracted much attention internationally.Based on the open-source software OpenMC developed by the Massachusetts Institute of Technology(MIT)for the Monte Carlo neutron transport equation in reactors,the advanced lead fast reactor European demonstrator(ALFRED)was selected as the research object,and two distinct coolant materials were used to conduct physical calculations of the lead cooled fast reactor core.The results show that under identical fuel loading conditions,the utilization of lead-bismuth coolant yields a significant enhancement in the reactor core's initial reactivity by 271×10-5.Moreover,the reactor core manifests a heightened proportion of effective delayed neutrons during normal commercial operation.Additionally,the neutron spectrum of the reactor core exhibits broader and harder characteristics,while also showcasing improved burning efficacy for the 239 Pu nuclide within the fuel matrix.Consequently,the employment of lead-bismuth alloy coolant within the ALFRED reactor core culminates in a heightened effective multiplication factor.This augmentation holds promise for enhancing the controllability and burnup performance of the reactor core,while concurrently mitigating the generation of radioactive waste.The research results furnish valuable insights into the design and performance optimization of the reactor core for the lead-cooled fast neutron reactor European demonstrator.

关 键 词：铅冷快中子欧洲示范堆(ALFRED) 冷却剂 有效增殖因子 燃耗计算 

分 类 号：TL326[核科学技术—核技术及应用]