tailieunhanh - Steady state calculations of the PWR MOX/UO2 core with the monte carlo code MCNP6

This paper presents the steady-state analysis results of the OECD/NEA and . NRC PWR MOX/UO2 (MOX: Mixed Oxide) Core Transient Benchmark with the modern MCNP6 Monte Carlo code based on the ENDF/ evaluated nuclear data library. |

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