Flux calculation in LSNAA using an 241Am-Be source

被引：0
|
作者：
R. Khelifi
P. Bode
A. Amokrane
机构：
[1] Université Saad DAHLAB,Department de Physique
[2] Interfaculty Reactor Institute,undefined
[3] Faculté de Physique,undefined
来源：
Journal of Radioanalytical and Nuclear Chemistry | 2007年 / 274卷
关键词：
Neutron Source; Flux Distribution; Neutron Spectrum; Thermal Flux; Flux Calculation;
D O I：
暂无
中图分类号：
学科分类号：
摘要：
The CITATION code based on neutron diffusion theory is used for flux calculation inside voluminous sample in prompt gamma activation analysis with an isotopic neutron source (241Am-Be). The code used the specific parameters related to energy spectrum source, irradiation system materials (shielding, reflector, etc.), geometry and elemental composition of the sample. The flux distribution (thermal and fast) was calculated on three-dimensional geometry for the system: source, air, and polyethylene and water cylindrical sample of 125 liters. The thermal flux was calculated in series of points inside the sample, and agreed with the results obtained by measurements with good statistical uncertainty. The maximum thermal flux was measured at distance of 4.1 cm and calculated at 4.3 cm by the CITATION code. Beyond a depth of 7.2 cm, the ratio of thermal flux to fast flux increases up to twice and allows us the optimization of the detection system in the scope of in-situ PGNAA.
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页码：639 / 642
页数：3
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