摘要
利用缓发中子计数法对235 U-239Pu混合物中235 U和239 Pu含量的快速测定进行了初步研究。在中国原子能科学研究院30kW微型反应堆(简称微堆)垂直孔道辐照235 U、239 Pu以及235 U-239 Pu混合物样品30s,冷却2s,用缓发中子探测器测量100s,得出235 U和239Pu的探测限分别为0.14和0.18μg;探测器效率为0.015 0±0.001 0;当235 U和239Pu质量比m(235 U)/m(239 Pu)=1.2时,235 U、239 Pu含量计算值与标称值的相对偏差分别为0.8%和6.9%。
The preliminary study on the measurements of 235U and 239Pu in 235U-239Pu mixture using delayed neutron counting method was introduced.All samples were irradiated for 30 s at China Institute of Atomic Energy,cooled for 2 s,and counted for 100 s using a delayed neutron detector.It is found that the detection limits of 235U and 239Pu are 0.14 and 0.18 μg for 235U and 239Pu,respectively.The detection efficiency for delayed neutron is 0.015 0±0.001 0.The relative deviations between calculated mass and measured mass of 235U and 239Pu are 0.8% and 6.9%,respectively,for m（235U）/m（239Pu） of 235U-239Pu mixture sample is 1.2.
出处
《原子能科学技术》
EI
CAS
CSCD
北大核心
2013年第7期1096-1100,共5页
Atomic Energy Science and Technology
基金
中国核工业集团公司预先研究基金资助项目(61601090411)
国家自然科学基金资助项目(11175264)
