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The neutron flux of a252Cf neutron activation analysis device using the MCNP code |
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| Authors: | L. Zhao E. Johnson L. Robinson |
| Affiliation: | (1) Technical Physics Institute of Heilongjiang Science Academy, P. R. China;(2) Chemical and Analytical Sciences Division, Oak Ridge National Laboratory, P. O. Box 2008, 37831-6375 Oak Ridge, TN, USA;(3) Environmental Sciences Institute, Florida A. & M. University, 32307 Tallahassee, FL, USA |
| Abstract: | This report presents results from the application of the Monte Carlo N-Particle (MCNP) computer code to the252Cf 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. |
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