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Analysis of neutron flux measurement in Thai Research Reactor-1/Modification 1 using the Monte Carlo method
Author(s)
Date Issued
January 1, 2014
Type
Conference Paper
Abstract
This study adopts the Monte Carlo method to analyze the neutron flux measurement technique in Thai Research Reactor-1/Modification 1(TRR-1/M1) by performing simulations using MCNPX computer program. The neutron flux measurement technique being analyzed is called "gold foil activation technique". The simulation model consists of gold foil located in the middle of in-core irradiation which is in the center of the reactor core. The variation in the calculated neutron flux is assessed by varying the gold foil thickness from approximately 500 - 800 μcm. It is found from the simulation that the calculated neutron flux can differ by 33% when increasing the gold foil thickness by 60%. In addition, more detailed simulations to determine neutron flux distribution within the gold foil are performed to study and explain the variation in neutron flux calculated at different foil thicknesses. The simulation result shows that self-shielding effect has significant impact to the neutron flux distribution within the gold foil, and hence to the average neutron flux. © (2014) Trans Tech Publications, Switzerland.
Citation
Advanced Materials Research, 979, 23-26, 2014