Jonah S A, Ibrahim Y V, Akaho E H K
Centre for Energy Research and Training, Ahmadu Bello University, P.M.B. 1014, Zaria, Nigeria.
Appl Radiat Isot. 2008 Oct;66(10):1377-80. doi: 10.1016/j.apradiso.2008.04.001. Epub 2008 Apr 7.
A comparator method based on the resonance integral of (197)Au(n,gamma)(198)Au reaction has been used to determine fast neutron spectrum-averaged cross-section data of some dosimetry reactions in a miniature neutron source reactor (MNSR) facility. Target materials of low- and medium-mass nuclei, which are of interest in reactor dosimetry and NAA were investigated. Irradiation was performed under Cd cover in an inner irradiation channel of the Nigeria Research Reactor-1 (NIRR-1) currently fueled with highly enriched uranium (HEU). Spectrum-averaged cross-section data were calculated on the basis of the epithermal neutron flux monitored by the Al-0.1%Au foil irradiated along with the target materials. Results of (n,p) reaction on (27)Al, (28)Si, (29)Si, (46)Ti, (47)Ti, (56)Fe, (58)Ni, and (n,alpha) reaction on (30)Si were found to be in good agreement with recommended data within standard deviation. However, data obtained for the (27)Al(n,alpha) (24)Na and (64)Zn (n,p) (64)Cu reactions using the Al-0.1%Au foil as the flux monitor for both the comparator approach and the conventional method are higher than recommended data from the literature by over 25%.
一种基于（197）Au（n，γ）（198）Au反应共振积分的比较方法已被用于确定微型中子源反应堆（MNSR）设施中一些剂量学反应的快中子谱平均截面数据。研究了反应堆剂量学和中子活化分析中感兴趣的低质量和中等质量核的靶材料。在目前以高浓缩铀（HEU）为燃料的尼日利亚研究堆-1（NIRR-1）的内照射通道中，在镉覆盖下进行辐照。根据与靶材料一起辐照的Al-0.1%Au箔监测的超热中子通量计算谱平均截面数据。发现（27）Al、（28）Si、（29）Si、（46）Ti、（47）Ti、（56）Fe、（58）Ni上的（n，p）反应以及（30）Si上的（n，α）反应的结果在标准偏差范围内与推荐数据吻合良好。然而，使用Al-0.1%Au箔作为通量监测器，通过比较器方法和传统方法获得的（27）Al（n，α）（24）Na和（64）Zn（n，p）（64）Cu反应的数据比文献推荐数据高出25%以上。
