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Lee, Deokjung
Computational Reactor physics & Experiment lab (CORE Lab)
Research Interests
  • Reactor Analysis computer codes development
  • Methodology development of reactor physics
  • Nuclear reactor design(SM-SFR,PWR and MSR)

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A Hybrid Monte Carlo/Method-of-Characteristics Method for Efficient Neutron Transport Analysis

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Title
A Hybrid Monte Carlo/Method-of-Characteristics Method for Efficient Neutron Transport Analysis
Author
Lee, HyunsukChoi, SooyoungLee, Deokjung
Issue Date
2015-05
Publisher
AMER NUCLEAR SOC
Citation
NUCLEAR SCIENCE AND ENGINEERING, v.180, no.1, pp.69 - 85
Abstract
This paper proposes a new hybrid method combining the Monte Carlo (MC) method and the Method of Characteristics (MOC). The hybrid method employs MC and MOC together to solve a neutron transport problem. The two different methods are applied to different neutron energy ranges. The MC method is used to obtain accurate solutions in the resonance energy range, and the MOC is used for high and low neutron energy ranges to achieve high performance of the new method. The two methods are consistently coupled through scattering and fission source terms during the power iterations and group sweepings. Numerical tests with a model problem confirm that the hybrid method can produce a more accurate solution than a conventional MOC by a factor of 10 and much higher computational efficiency than a conventional MC method by a factor of 90
URI
https://scholarworks.unist.ac.kr/handle/201301/17381
URL
http://www.ans.org/pubs/journals/nse/a_37007
DOI
10.13182/NSE13-102
ISSN
0029-5639
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