Inter-Code Comparison of Computational VERA Depletion Benchmark Using OpenMC, OpenMC-ONIX and DRAGON

Inter-Code Comparison of Computational VERA Depletion Benchmark Using OpenMC, OpenMC-ONIX and DRAGON

This research focuses on the comparative analysis of the PWR fuel assembly based on VERA depletion benchmark problems using community-developed open source Monte Carlo code OpenMC, python based burnup code system ONIX (a coupling interface for Monte Carlo code OpenMC), and deterministic DRAGON code....

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Bibliographic Details
Main Authors: A. Islam, T. A. Rahim, A. S. Mollah
Format: Article
Language:English
Published: Center for Development of Nuclear Informatics, National Nuclear Energy Agency (BATAN) 2022-12-01
Series:Atom Indonesia
Subjects:
vera, depletion, openmc, onix, dragon
Online Access:https://aij.batan.go.id/index.php/aij/article/view/1191

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