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KMID : 0364920130380040172
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Journal of Radiation Protection and Research
2013 Volume.38 No. 4 p.172 ~ p.178
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Evaluation of Neutron Detection Efficiency of the Unified Non-Destructive Assay Using MCNPX Code
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Won Byung-Hee
Seo Hee
Lee Seung-Kyu
Park Se-Hwan
Kim Ho-Dong
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Abstract
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In this study, neutron detection efficiency of the UNDA system, which has been developed for study on nuclear material accountancy in a future pyro-process facility, was evaluated by using the MCNPX code. The detection efficiency was evaluated as a function of (1) positions of 252Cf neutron source in the axial and radial directions, and (2) thicknesses and locations of the container filled with the depleted uranium materials for two different designs of the UNDA. In the case of 252Cf source positions, detection efficiency was distributed from 6.83% to 13.35%. As 252Cf source was positioned at upper part in the axial direction, detection efficiency was decreased after a slight increase. On the other hands, as 252Cf source was positioned at outer part in the radial direction, detection efficiency was increased. In the case of container thickness, there was a slight decline when the thickness was increased. As the container was located at upper part, detection efficiency was decreased and as the container was located at outer part, detection efficiency was increased. Detection efficiency was varied from 10.31% to 13.61%. These values were higher than that of 252Cf source case. The UNDA with polyethylene cover has about 2% higher detection efficiency than the UNDA without the cover.
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KEYWORD
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Unified Non-Destructive Assay (UNDA), MCNPX code, Neutron detection efficiency
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