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Criticality Safety Bias in VVER-440 Calculations by farkasg is a document available to read on EtoBox.

This document discusses determining criticality safety calculation bias using different Monte Carlo N-Particle Transport Code (MCNP) versions and nuclear cross section libraries. It presents criticality calculations for 21 benchmark problems related to VVER-440 reactors using JEFF-3.1, ENDF/B-VII, and JENDL 4.0 libraries with MCNP5-1.40 and MCNP5-1.60. The benchmarks vary in fuel enrichment, moderator, absorber, cladding, and temperature. Calculations were performed on two computer clusters at the author

Author

farkasg

Language

EN