![](images/graphics/blank.gif)
Rod ejection accident
-
This paper presents the steady-state analysis results of the OECD/NEA and U.S. NRC PWR MOX/UO2 (MOX: Mixed Oxide) Core Transient Benchmark with the modern MCNP6 Monte Carlo code based on the up-to-date ENDF/B-VII.1 nuclear data library.
9p
vicedric
08-02-2023
8
3
Download
-
In this study, the SCALE/TRITON code (based on deterministic method) and the Serpent 2 code (based on Monte Carlo method) were utilized to prepare the group constants of the pressurized water reactor (PWR) mixed-oxide (MOX) fuel assemblies for transient analyses of PWR MOX fueled cores in normal operation and control rod ejection accident condition with 3D reactor kinetics codes.
10p
meyerowitz
25-12-2021
7
0
Download