- Volume 38 Issue 4
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Evaluation of Neutron Detection Efficiency of the Unified Non-Destructive Assay Using MCNPX Code
MCNPX 코드를 이용한 통합비파괴측정장치의 중성자 검출 효율 평가
- Won, Byung-Hee (Korea Atomic Energy Research Institute) ;
- Seo, Hee (Korea Atomic Energy Research Institute) ;
- Lee, Seung Kyu (Korea Atomic Energy Research Institute) ;
- Park, Se Hwan (Korea Atomic Energy Research Institute) ;
- Kim, Ho Dong (Korea Atomic Energy Research Institute)
- Received : 2013.10.15
- Accepted : 2013.12.04
- Published : 2013.12.30
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
Supported by : 한국연구재단
- Pelowitz DB. MCNPX user's manual version 2.7.0. LA-CP-11-00438. Los Alamos National Laboratory. 2011.
- Verbeke JM, Hagmann C, Wright D. Simulation of neutron and gamma ray emission from fission and photofission. UCRL-AR-228518. Lawrence Livermore National Laboratory. 2010.