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
Zdroj: Pramana: Journal of Physics. Jan2013, Vol. 80 Issue 1, p105-120. 16p. 2 Diagrams, 4 Charts, 15 Graphs.
Databáze: Academic Search Ultimate