Study of criticality safety and neutronic parameters of UO2 fuel in MTR research reactors using the MCNP4C code
| Autor: | Shaaban, Ismail, Albarhoum, Mohamad |
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| Zdroj: | In Annals of Nuclear Energy December 2016 98:144-156 |
| Databáze: | ScienceDirect |
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Full Text from ScienceDirect