The neutron flux of a 252Cf neutron activation analysis device using the MCNP code

被引：2
|
作者：
Zhao, L
Johnson, E
Robinson, L
机构：
[1] Oak Ridge Natl Lab, Div Chem & Analyt Sci, Oak Ridge, TN 37831 USA
[2] Florida A&M Univ, Inst Environm Sci, Tallahassee, FL 32307 USA
来源：
JOURNAL OF RADIOANALYTICAL AND NUCLEAR CHEMISTRY | 1999年 / 240卷 / 02期
关键词：
Physical Chemistry; Inorganic Chemistry; Relative Error; Technical Physics; Neutron Activation Analysis;
D O I：
10.1007/BF02349409
中图分类号：
O65 [分析化学];
学科分类号：
070302 ; 081704 ;
摘要：
This report presents results from the application of the Monte Carlo N-Particle (MCNP) computer code to the Cf-252 neutron activation analysis (NAA) Device in the Technical Physics Institute of the Heilongjiang Science Academy of the People's Republic of China. The thermal and epithermal neutron flux at the sample positions and the neutron and photon fluxes on the surfaces of the device were calculated. A comparison between the calculated and experimental thermal and epithermal neutron fluxes at sample positions yield relative errors of less than 10% for the thermal neutron flux.
引用
收藏
页码：531 / 534
页数：4
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