基于SAC-3D系统软件的FFTF未能紧急停堆失流实验的数值模拟  

Simulation of FFTF Loss of Flow without Scram Test Based on System Code SAC-3D

作　　者：陆道纲[1,2] 吕思宇 隋丹婷 LU Daogang;LYU Siyu;SUI Danting(School of Nuclear Science and Engineering,North China Electric Power University,Beijing 102206,China;Beijing Key Laboratory of Passive Safety Technology for Nuclear Energy,North China Electric Power University,Beijing 102206,China)

机构地区：[1]华北电力大学核科学与工程学院,北京102206 [2]非能动核能安全技术北京市重点实验室,北京102206

出　　处：《原子能科学技术》2021年第8期1345-1352,共8页Atomic Energy Science and Technology

基　　金：IAEA国际合作科研项目(RC-22973);国家自然科学基金(11705057)。

摘　　要：本文利用系统分析软件SAC-3D对美国快通量试验堆(FFTF)堆芯及一回路进行了建模,并根据国际原子能机构(IAEA)提供的FFTF未能紧急停堆的失流实验的边界条件数据进行了事故瞬态仿真计算。计算得到堆芯热工水力及中子物理关键参数,仿真结果与实验测量数据符合较好。对比结果验证了SAC-3D在模拟液态金属冷却快堆事故工况中的有效性与准确性,也证明了FFTF堆型具有可靠的非能动安全性。The system analysis software SAC-3D was used to model the core and primary loop of the U.S.Fast Flux Test Facility(FFTF)in the paper.The accident transient simulations were carried out based on the boundary condition data of FFTF loss of flow without scram test provided by the International Atomic Energy Agency(IAEA).The thermal-hydraulic and neutron physical key parameters of the core were calculated,and the simulation results are in good agreement with the experimental measurement data.The comparison results verify the validity and accuracy of the SAC-3D in simulating the accident conditions of liquid metal cooled fast reactors and prove that the FFTF reactor type has reliable passive safety.

关 键 词：SAC-3D 快通量试验堆 未能紧急停堆的失流事故 非能动安全 液态金属冷却快堆 

分 类 号：TL364[核科学技术—核技术及应用]