300#研究堆寿期内上联箱铝材中子注量分析  

Calculating the accumulative neutron fluence rate of Al alloy on upper link chest of Swimming Pool Research Reactor-300

作　　者：冯琦杰[1] 刘耀光[1] 杨万奎[1] 张松宝[1] 石炳元[1] 杨锐[1] 

机构地区：[1]中国工程物理研究院核物理与化学研究所,四川绵阳621900

出　　处：《强激光与粒子束》2015年第7期295-299,共5页High Power Laser and Particle Beams

基　　金：核能开发科研项目

摘　　要：材料在辐照过程中所受的中子注量是辐照性能研究中的一个重要参数。上联箱铝材作为300#研究堆关键结构材料,经历了从反应堆首次临界到退役的全过程,极具材料辐照效应研究价值。为获取整个反应堆运行寿期内的上联箱中子注量水平,须克服堆芯装载变化频繁与堆芯不断扩大装载两大关键难点,故提出了堆芯归并等效计算方法。通过该方法的成功应用,得到了300#研究堆寿期内上联箱铝材的中子注量,并进行了误差分析。Researching the material performance under neutron irradiation requires accumulative neutron fluence rate which is an important parameter. A1 alloy on the upper link chest as a key structural material of Swimming Pool Research Reactor 300 fSPRR 300）, goes through the whole life of reactor under high neutron irradiation. Hence, the alloy is full of research value. To get the accumulative fluence rate of reactor upper link chest during the whole life span of reactor operation, this paper proposes a solution, namely core merging equivalent calculation method, aiming to deal with the frequent core configuration changing and ex panding rationally. Applying this method, we have acquired the accumulative neutron fluence rate and conducted the pertinent er rot analysis.

关 键 词：中子注量 300#研究堆 蒙特卡罗方法 等效计算 

分 类 号：TL329[核科学技术—核技术及应用]