Neutronic calculations for the VVER-1000 MOX core computational benchmark using the OpenMC code

Neutronic calculations for the VVER-1000 MOX core computational benchmark using the OpenMC code

The goal of this study is to perform neutronic calculations of the VVER-1000 MOX core computational benchmarks with an OpenMC code along with ENDF/B-VII.1 nuclear data library. The results of neutronic analysis using the OpenMC Monte Carlo code for the VVER-1000 MOX core, containing 30% mixed oxide...

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Bibliographic Details
Main Authors: Md Imtiaj Hossain, Abdus Sattar Mollah, Yasmin Akter, Mehraz Zaman Fardin
Format: Article
Language:English
Published: National Research Nuclear University (MEPhI) 2023-11-01
Series:Nuclear Energy and Technology
Subjects:
VVER-1000 MOX core
OpenMC
Low En
Online Access:https://nucet.pensoft.net/article/91090/download/pdf/

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