微型中子源反应堆内部辐照位置快中子通量的测量。

Measurement of the fast neutron flux in the MNSR inner irradiation site.

作者信息

Khattab K

机构信息

Nuclear Engineering Department, Atomic Energy Commission, P.O. Box 6091, Damascus, Syria.

出版信息

Appl Radiat Isot. 2007 Jan;65(1):46-9. doi: 10.1016/j.apradiso.2005.11.020. Epub 2006 Sep 14.

DOI:10.1016/j.apradiso.2005.11.020

PMID:16973369

Abstract

The WIMSD4 code was used to calculate the fast neutron flux spectrum and the fast neutron fission cross-sections for (238)U, using six energy groups ranging from 0.5 to 10 MeV. These results, with the measured radioactivities of the (140)Ba, (131)I, (103)Ru, (95)Zr and (97)Zr fission products emerging from the fission of the (238)U foil covered with a cadmium filter, were used to measure the fast neutron flux in the Syrian Miniature Neutron Source Reactor inner irradiation site.

摘要

采用WIMSD4编码，利用六个能量范围从0.5到10 MeV的能组，计算了(238)U的快中子通量谱和快中子裂变截面。这些结果，结合覆盖镉滤片的(238)U箔裂变产生的(140)Ba、(131)I、(103)Ru、(95)Zr和(97)Zr裂变产物的测量放射性，用于测量叙利亚微型中子源反应堆内部辐照场所的快中子通量。