1) slow reactor
慢中子堆
2) slow reactor
慢中子反应堆
4) thermal graphite reactor
石墨慢化热中子反应堆
5) neutron moderation
中子慢化
1.
In order to use ~(252)Cf source effectively and improve testing sensitivity of the nuclear fuel scanner, appropriate moderation material should be selected carefully, and the process of neutron moderation should be optimized.
对于核燃料棒235U富集度均匀性扫描装置,为了合理有效地利用252Cf中子源,提高检测灵敏度,需要合理选择中子慢化材料,优化中子慢化过程。
6) slow neutron
慢中子
1.
For selecting nuclides to transform slow neutron into gamma photon effectively, the main decisive aspects are analyzed basing on relative cross section data and a specific model is calculated by using S N method.
为选出能有效地实现慢中子 γ光子转换的核素 ,根据有关截面数据分析了主要的决定因素 ,并结合具体模型用离散纵标法作了计算。
补充资料：快堆(见快中子增殖堆)
快堆(见快中子增殖堆)
fast-breeder reactor
l快堆堆。(fast一breeder reaetor)见快中子增殖
说明：补充资料仅用于学习参考，请勿用于其它任何用途。
参考词条