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Monte Carlo Code MCS as Cross-section Generation Tool for Reactor Core Analysis

Author(s)
NGUYEN, Tung Dong Cao
Advisor
Lee, Deokjung
Issued Date
2023-02
URI
https://scholarworks.unist.ac.kr/handle/201301/74097 http://unist.dcollection.net/common/orgView/200000665595
Publisher
Ulsan National Institute of Science and Technology (UNIST)
Degree
Doctor
Major
Department of Nuclear Engineering

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