论文部分内容阅读
目前,国内中子剂量仪表的校准主要利用241Am-Be和252Cf中子源进行。这类参考辐射场与工作场所的中子能谱差别很大,远不能满足中子剂量校准的要求,因此,需对校准场进行补充,增加与工作场所能谱相近的参考辐射场。本项目以5SDH-2串列加速器D(d,n)3He反应产生的5MeV中子为初始源项,然后利用MCNP4C程序模拟计算了该源中子经一定几何的贫铀转换体、铁层、水层和聚乙烯散射慢化体后产生的中子能谱,再得到校准区的平均中子周围剂量当量等参数。
At present, the calibration of domestic neutron dosimeters mainly uses 241Am-Be and 252Cf neutron sources. Such reference radiation field and neutron energy spectrum in the workplace vary greatly, far from meeting the requirements of neutron dose calibration. Therefore, the calibration field needs to be supplemented to increase the reference radiation field similar to the energy spectrum in the workplace. In this project, 5MeV neutrons generated by 5SDH-2 Tandem accelerator D (d, n) 3He reaction are used as initial source term. Then, the MCNP4C program is used to simulate the calculations. Layer and polyethylene scatter the neutron energy spectrum produced by the moderator, and then get the calibration area average neutron dose equivalent and other parameters.