Neutronic simulation of a research reactor core of (Th, U)O fuel using MCNPX2.6 code.
Autor: | FEGHHI, SEYED1, REZAZADEH, MARZIEH2, KADI, YACINE, TENREIRO, CLAUDIO, AREF, MORTEZA3, GHOLAMZADEH, ZOHREH4 cadmium_109@yahoo.com |
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Zdroj: | Pramana: Journal of Physics. Jan2013, Vol. 80 Issue 1, p105-120. 16p. 2 Diagrams, 4 Charts, 15 Graphs. |
Databáze: | Academic Search Ultimate |
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