一体化快堆物理-热工耦合分析计算研究  

Integrated Fast Reactor Analysis and Calculation of Neutronics-thermal Coupling

作　　者：李昊田 吴明宇[1] 吴宗芸 周志伟[1] 霍兴凯 肖宇白 LI Haotian;WU Mingyu;WU Zongyun;ZHOU Zhiwei;HUO Xingkai;XIAO Yubai(Department of Nuclear Engineering Design,China Institute of Atomic Energy,Beijing 102413,China)

机构地区：[1]中国原子能科学研究院核工程设计研究所,北京102413

出　　处：《原子能科学技术》2025年第S1期96-103,共8页Atomic Energy Science and Technology

基　　金：中核集团集中研发项目。

摘　　要：一体化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。通过多物理耦合、精细化计算,开展反应堆高精度数值模拟,减少传统计算方法中的各种简化和近似,能够更好地反映反应堆实际运行情况,为反应堆设计方案提供验证。本文采用外耦合模式,基于RMC和VERSA程序开展核热耦合研究,对一体化快堆功率和冷却剂温度进行精细化模拟计算,验证VERSA子通道传热模型设计的合理性与准确性。开展核热耦合迭代计算,采用就近原则为燃料栅元匹配最接近的温度库。结果表明:经过3轮核热耦合迭代计算,燃料中心温度变化在1%以内,实现收敛。使用匹配截面库计算与900 K截面库相比,计算得到的燃料中心温度整体下降。Integrated fast reactor exhibits distinct advantages in enhancing the utilization rate of uranium resources and minimizing high-level radioactive waste.Through multi-physical coupling and refined computations,conducting high-precision numerical simulations of the reactor,and reducing various simplifications and approximations in traditional calculation methods,the actual operation of the reactor can be better reflected,providing verification for the reactor design scheme.This research undertook core nuclear-thermal coupling studies based on the Monte Carlo program RMC and the subchannel analysis program VERSA.With the integrated fast reactor as the research object,the active zone was equally divided into 20 nodes in the axial direction,with one layer each in the upper and lower axial conversion zones,and a total of 22 layers in the axial direction.In the nuclear-thermal coupling calculation,the initial temperature and density distributions were first set,and neutron transport calculations were carried out to obtain power distribution information,which was input into the subchannel program to conduct flow and heat transfer calculations and obtain new coolant temperature,density,and fuel rod temperature parameters.These thermal parameters were fed back to the corresponding lattice cells in the neutron physics geometric module.When conducting the next round of physical calculations,the material parameter settings were updated to calculate the new power distribution.The Doppler effect is relatively prominent in the thermal feedback.The central temperature of the fuel element affects the power distribution calculation by influencing the absorption crosssection.In this study,by creating multiple temperature libraries and adjusting the material cross-section data of the Monte Carlo calculation based on the temperature values from the thermal feedback,the nearest temperature library is assigned to each region based on the proximity principle whenever the thermal temperature is fed back to the physics,ensuring the efficie

关 键 词：一体化快堆 核热耦合 数值模拟 

分 类 号：TL32[核科学技术—核技术及应用]