Computational analysis of neutronic parameters for TRIGA Mark-II research reactor using evaluated nuclear data libraries ENDF/B-VII.0 and JENDL-3.3
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Published:2015-06
Issue:
Volume:80
Page:21-27
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ISSN:0306-4549
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Container-title:Annals of Nuclear Energy
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language:en
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Short-container-title:Annals of Nuclear Energy
Author:
Altaf M.H.,Badrun N.H.,Chowdhury M.T.
Subject
Nuclear Energy and Engineering
Reference8 articles.
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