原子能科学技术2012，Vol.46Issue(z1)：403-405,3.
原型微堆低浓化初步研究
Primary Research for Conversion of Prototype Miniature Neutron Source Reactor With Low Enrichment Uranium
摘要
Abstract
The parameters of prototype miniature neutron source reactor (MNSR) with high enrichment uranium (HEU) , such as keff, worth of the central control rod, worth of top beryllium reflector and the neutron flux density, were calculated using the Monte-Carlo code. The comparison was made between the calculated results and the experimental results, and they fit with each other very well. Without changing the core dimensions of the prototype MNSR, but substituting the HEU fuel with LEU fuel of UO2 with 12. 5% enrichment and Al cladding with zircaloy cladding, keff worth of the central control rod and neutron flux density were calculated again, and thermal dynamic features of releasing 4. 0 mk excess reactivity were analyzed using RELAP5 code.关键词
原型微堆/低浓化/keffKey words
prototype miniature neutron source reactor/ low enrichment/ keff分类
能源科技引用本文复制引用
李义国,杜开文,夏普,吴小波,彭旦..原型微堆低浓化初步研究[J].原子能科学技术,2012,46(z1):403-405,3.基金项目
国际原子能机构协调研究项目资助(13956) （13956）
