Burn-up calculation of different thorium-based fuel matrixes in a thermal research reactor using MCNPX 2.6 code
Language: English
Page range: 129 - 136
Submitted on: Aug 27, 2013
Accepted on: Aug 8, 2014
Published on: Dec 30, 2014
Published by: Institute of Nuclear Chemistry and Technology
In partnership with: Paradigm Publishing Services
Publication frequency: 4 issues per year
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© 2014 Zohreh Gholamzadeh, Seyed Amir Hossein Feghhi, Leila Soltani, Marzieh Rezazadeh, Claudio Tenreiro, Mahdi Joharifard, published by Institute of Nuclear Chemistry and Technology
This work is licensed under the Creative Commons Attribution-NonCommercial-NoDerivatives 3.0 License.