-
为校验次临界能源堆的概念设计,建立了贫化铀/聚乙烯球壳交替系统, 采用活化法测量238U的中子俘获率. 贫化铀片置于系统内与入射D离子束成90o的方向上活化 ,用HPGe探测器测量238U俘获中子衰变产生的239Np 衰变产生的277.6 keV特征射线计数,实验修正了贫铀片对277.6 keV 射线的自吸收, 得到了交替系统中238U (n, )反应率的径向分布,反应率的相对不确定度为3.5%3.7%, 并计算得到系统上整个贫铀区中238U的总中子俘获率为2.24 0.09. 用MCNP5程序在常用ENDF库下进行了模拟计算, 238U (n, )反应率分布计算与实验一般在5%以内符合, 总俘获率在1%以内符合.
-
关键词:
- 14 MeV中子 /
- 238U中子俘获 /
- 自吸收修正 /
- Monte-Carlo模拟
In order to check the conceptual design of subcritical reactor, an alternate depleted uranium/polyethylene-shell simulation device was established, to carry out uranium-238 neutron capture rate experiment using activation technique. The depleted uranium foils were activated at 90o to the incident. By measuring the 277.6 keV -ray emitted from 239Np generated by 238U (n, ) 239U reaction and correcting self-absorption of uranium experimentally, the 238U (n, ) reaction rate with an uncertainty between 3.5% and 3.7% and a total neutron capture of 2.24 0.09 of the system were obtained. The experiment was simulated using MCNP5 code with ENDF libraries. The simulations and measurements accord within 5% for the 238U (n, ) reaction rate and within 1% for the total neutron capture rate of 238U.-
Keywords:
- 14 MeV neutron /
- neutron capture of 238U /
- self-absorption correction /
- Monte Carlo simulation







下载: