Analysis of the first core of the Indonesian multipurpose research reactor RSG-GAS using the Serpent Monte Carlo code and the ENDF/B-VIII.0 nuclear data library-Reference-Cited by-同舟云学术

Analysis of the first core of the Indonesian multipurpose research reactor RSG-GAS using the Serpent Monte Carlo code and the ENDF/B-VIII.0 nuclear data library

Published:2020-12 Issue:12 Volume:52 Page:2725-2732
ISSN:1738-5733
Container-title:Nuclear Engineering and Technology
language:en
Short-container-title:Nuclear Engineering and Technology

Author:

Hartanto Donny,Liem Peng Hong

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference20 articles.

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4. Processing of JEFF-3.3 and ENDF/B-VIII.0 and testing with critical benchmark experiments and TRIGA mark II research reactor using MCNPX;Kabach;Appl. Radiat. Isot.,2019

5. Comparison of ENDF/B-VIII.0 and ENDF/B-VII.1 in criticality, depletion benchmark, and uncertainty analyses by McCARD;Park;Ann. Nucl. Energy,2019

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