摘要
用MCNP4C程序分别计算了高通量工程试验堆(HFETR)首炉13#电离室和L12元件、第53-I炉13#电离室和7#电离室、第68-II炉12#电离室和1QS的快中子注量率并与实验测量值比较,计算结果是可靠的。通过选择不同类型的堆芯布置,计算了到2004年底HFETR压力容器焊缝所受的快中子注量。截止2004年底,HFETR压力容器焊缝内壁所受到的E≥1MeV、E≥0.1MeV的快中子最大点的注量分别为1.212×1017cm-2和2.514×1017cm-2,远小于设计值。
This paper calculated the fast neutron flux of some places in different HFETR cores, such as the 13^rd ion chamber and L12 fuel rod in the 1st core, the 12nd ion chamber and the 1QS ion chamber in the 68^th -Ⅱ core. Comparison of the calculated and the experimental results was made. It showed that the result was accurate. And we also chose different cores to get the fast neutron fluence of welding line in the reactor pressure vessel of HFETR up to 2004. The result was 1.212×10^17cm^-2 （E ≥ 1MeV） and 2.514×10^17cm^-2（E≥0.1MeV）. It showed that the maximum fast neutron fluence was less than the design data so far.
出处
《核动力工程》
EI
CAS
CSCD
北大核心
2006年第5期58-60,73,共4页
Nuclear Power Engineering
