摘要
铅铋合金或铅冷却快堆(LFR)是具有良好应用前景的第四代先进核能系统之一。针对环形芯体金属燃料(UZr,UPuZr)LFR的燃料组件与堆芯,利用Dragon/Donjon程序开展中子学计算,获得了基于ENDF/B 8.0库的172群和295群多群中子数据库、输运方法(SP3)和扩散方法(MCFD)的结果及其与蒙卡程序RMC的偏差。采用SP3算法针对UZr燃料得到的k;偏差小于550×10;对于UPuZr燃料采用MCFD算法得到的k;偏差小于-700×10;。控制棒组件价值的偏差小于7.6%;172群和295群库的结果基本无差异。应用SP3算法的燃料组件功率偏差小于±6.0%;SP3算法的偏差小于MCFD的。结果证明,Dragon/Donjon程序在金属燃料铅铋快堆物理分析中具有可行性。
Lead-bismuth/lead cooled fast reactor(LFR) is one of the fourth-generation advanced nuclear energy systems with good application prospects. Aiming at the application of two metallic fuels(UZr, UPuZr) with annular slug in an LFR fuel assembly and a typical LFR core, the Dragon/Donjon code was used to perform neutronics calculations. The results of 172-group and 295-group neutron databases based on the ENDF/B 8.0 library and the transport method(SP3) and the diffusion method(MCFD) were obtained and compared with the results using RMC code. The k;deviations using SP3 algorithm for UZr fuel are less than 550×10;, and for UPuZr fuel, the k;deviations obtained by MCFD algorithm are less than -700×10;. The maximum deviation of control rod worth is 7.6%, and the results using 172-grouplib and 295-grouplib are basically the same. By using the SP3 algorithm, the fuel assembly power deviations are less than ±6.0%, and the deviation with the SP3 algorithm is less than that with MCFD algorithm. The results preliminarily prove the feasibility of the Dragon/Donjon code for reactor physics analysis of LFR with metallic fuel.
作者
张亮
孙胜
孙寿华
杨文华
Zhang Liang;Sun Sheng;Sun Shouhua;Yang Wenhua(Reactor Operation and Application Sub-Institute,Nuclear Power Institute of China,Chengdu 610213,China)
出处
《强激光与粒子束》
CAS
CSCD
北大核心
2022年第5期30-37,共8页
High Power Laser and Particle Beams
基金
四川省青年科技创新研究团队项目(2022JDTD0006)。
