热管冷却反应堆采用非能动传热技术,热响应速度快,可避免堆芯单点失效,具有功率密度大、寿命长、环境适应性强、工作性能稳定等特点,是目前空间核反应堆研究的热点。基于清华大学开发的反应堆蒙特卡洛中子输运程序RMC(reactor Monte Car...热管冷却反应堆采用非能动传热技术,热响应速度快,可避免堆芯单点失效,具有功率密度大、寿命长、环境适应性强、工作性能稳定等特点,是目前空间核反应堆研究的热点。基于清华大学开发的反应堆蒙特卡洛中子输运程序RMC(reactor Monte Carlo code),以美国爱荷华国家实验室(Idaho National Laboratory,INL)设计的热管冷却反应堆INL Design A为研究对象,选取3种热管工质开展热管冷却反应堆堆芯物理计算。计算结果表明:锂热管工质不仅拥有很好的热物性参数,并且使用锂热管工质的热管冷却反应堆缓发中子有效份额最大、中子能谱较硬、燃耗反应性损失最小、增殖性能最佳,有利于热管冷却反应堆堆芯小型化与长寿命。因此,推荐锂为热管冷却反应堆的热管工质。展开更多
The accurate modeling of depletion,intricately tied to the solution of the neutron transport equation,is crucial for the design,analysis,and licensing of nuclear reactors and their fuel cycles.This paper introduces a ...The accurate modeling of depletion,intricately tied to the solution of the neutron transport equation,is crucial for the design,analysis,and licensing of nuclear reactors and their fuel cycles.This paper introduces a novel multi-group Monte-Carlo depletion calculation approach.Multi-group cross-sections(MGXS)are derived from both 3D whole-core model and 2D fuel subassembly model using the continuous-energy Monte-Carlo method.Core calculations employ the multi-group Monte-Carlo method,accommodating both homogeneous and specific local heterogeneous geometries.The proposed method has been validated against the MET-1000 metal-fueled fast reactors,using both the OECD/NEA benchmark and a new refueling benchmark introduced in this paper.Our findings suggest that microscopic MGXS,produced via the Monte-Carlo method,are viable for fast reactor depletion analyses.Furthermore,the locally heterogeneous model with angular-dependent MGXS offers robust predictions for core reactivity,control rod value,sodium void value,Doppler constants,power distribution,and concentration levels.展开更多
文摘热管冷却反应堆采用非能动传热技术,热响应速度快,可避免堆芯单点失效,具有功率密度大、寿命长、环境适应性强、工作性能稳定等特点,是目前空间核反应堆研究的热点。基于清华大学开发的反应堆蒙特卡洛中子输运程序RMC(reactor Monte Carlo code),以美国爱荷华国家实验室(Idaho National Laboratory,INL)设计的热管冷却反应堆INL Design A为研究对象,选取3种热管工质开展热管冷却反应堆堆芯物理计算。计算结果表明:锂热管工质不仅拥有很好的热物性参数,并且使用锂热管工质的热管冷却反应堆缓发中子有效份额最大、中子能谱较硬、燃耗反应性损失最小、增殖性能最佳,有利于热管冷却反应堆堆芯小型化与长寿命。因此,推荐锂为热管冷却反应堆的热管工质。
基金supported by the National Natural Science Foundation of China(Nos.12105170,12135008)Science and Technology on Reactor System Design Technology Laboratory.
文摘The accurate modeling of depletion,intricately tied to the solution of the neutron transport equation,is crucial for the design,analysis,and licensing of nuclear reactors and their fuel cycles.This paper introduces a novel multi-group Monte-Carlo depletion calculation approach.Multi-group cross-sections(MGXS)are derived from both 3D whole-core model and 2D fuel subassembly model using the continuous-energy Monte-Carlo method.Core calculations employ the multi-group Monte-Carlo method,accommodating both homogeneous and specific local heterogeneous geometries.The proposed method has been validated against the MET-1000 metal-fueled fast reactors,using both the OECD/NEA benchmark and a new refueling benchmark introduced in this paper.Our findings suggest that microscopic MGXS,produced via the Monte-Carlo method,are viable for fast reactor depletion analyses.Furthermore,the locally heterogeneous model with angular-dependent MGXS offers robust predictions for core reactivity,control rod value,sodium void value,Doppler constants,power distribution,and concentration levels.
