节点文献

微型反应堆燃料低浓化可行性初步研究

Primary Research on Conversion of Miniature Neutron Source Reactor With Low Enrichment Uranium

  • 推荐 CAJ下载
  • PDF下载
  • 不支持迅雷等下载工具,请取消加速工具后下载。

【作者】 熊厚华彭旦蔡德富李义国

【Author】 XIONG Hou-hua,PENG Dan,CAI De-fu,LI Yi-guo(China Institute of Atomic Energy,P.O.Box 275-75,Beijing 102413,China)

【机构】 中国原子能科学研究院反应堆工程研究设计所

【摘要】 应用蒙特卡罗计算程序,模拟计算山东微堆的堆芯参数,包括keff、eβff、控制棒价值、上铍效率、内辐照中子通量以及停堆深度,计算结果与实验结果基本一致。保持微堆堆芯尺寸不变,采用低富集度UO2芯体燃料棒替换原来的高浓铀燃料棒,计算不同235U富集度下微堆的有效倍增系数keff,据此确定满足要求的UO2富集度为12.5%。在此基础上计算了富集度为12.5%的低浓堆芯参数,并与高浓堆芯参数进行了比较。结果表明,微堆燃料低浓化是可行的。

【Abstract】 The reactor core parameters of miniature neutron source reactor(MNSR) with high enrichment uranium(HEU),such as keff,βeff,reactivity worth of the center control rod,reactivity worth of the top beryllium,inner irradiation site neutron flux density and shut down margin,were calculated by Monte-Carlo code.Comparison between the calculated and the experimented results was performed,and they were in agreement with each other very well.Without changing the core dimensions of the MNSR,but substituting the HEU fuel with low enrichment uranium(LEU) fuel and Al cladding with zircaloy cladding,the keff was calculated at the 235U enrichment from 12.0% to 12.5%,and the fitting enrichment of 12.5% was chosen.The reactor core parameters of MNSR with LEU of 12.5% were calculated.From the above calculated results,it is concluded that the conversion of MNSR with LEU of 12.5% is feasible.

  • 【会议录名称】 第五届北京核学会核技术应用学术交流会论文集
  • 【会议名称】第五届北京核学会核技术应用学术交流会
  • 【会议时间】2008-10
  • 【会议地点】中国江西南昌
  • 【分类号】TL411.7
  • 【主办单位】北京核学会
节点文献中: 

本文链接的文献网络图示:

本文的引文网络