摘要
钠冷快堆在提高铀资源利用率、实现高放废物最小化等方面优势明显。反应堆内部物理热工存在强烈的反馈机制。本研究基于蒙特卡罗程序RMC和子通道分析程序VERSA开展核-热耦合计算,采用外耦合方式,建立了一套编码体系实现不同物理场之间的网格对应。通过C++语言开发了数据接口进行程序间数据传递。通过对217棒束的燃料组件进行精细化建模,轴向上分为20层,计算得出了精确的三维pin-by-pin功率分布和温度分布信息。计算结果表明,精细化核-热耦合研究可以更加准确地分析功率分布导致的出口温度差异,能够为流量分配方案提供验证,进一步优化堆芯核设计。
The sodium-cooled fast reactor has obvious advantages in improving the utilization rate of uranium resources and minimizing the high level radioactive waste.There is a strong feedback mechanism in the neutronics and thermal of the reactor.In this study,the Monte Carlo codenal RMC and subchannel analysis program VERSA are used to carry out the neutronics-thermal coupling calculation.In this paper,an external coupling method is used to establish a coding system to realize grid correspondence between different physical fields.The data interface is developed by C++to transfer data between programs.The fuel assembly of 217 rod bundles was finely modeled and divided into 20 layers in the axial direction.The accurate 3D pin-by-pin power distribution and temperature distribution information were calculated.The calculation results show that the refined nuclear thermal coupling study can more accurately analyze the outlet temperature differences caused by power distribution,provide validation for flow distribution scheme,and further optimize the reactor core design.
作者
李昊田
吴明宇
霍兴凯
吴宗芸
刘一哲
关则钏
Li Haotian;Wu Mingyu;Huo Xingkai;Wu Zongyun;Liu Yizhe;Guan Zechuan(China Institute of Atomic Energy,Beijing 102413,China)
出处
《电子技术应用》
2024年第S01期206-211,共6页
Application of Electronic Technique
关键词
核-热耦合
精细化
钠冷快堆
neutronics-thermal coupling
high-fidelity
sodium-cooled fast reactor
作者简介
李昊田(1998—),男,硕士研究生,主要研究方向:反应堆物理热工耦合方向;通信作者:吴明宇(1979—),男,研究员,主要研究方向:反应堆设计研究,E-mail:wu_mingyu1979@163.com。
