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....
| Main Authors: | , , |
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| Format: | Article |
| Language: | English |
| Published: |
Center for Development of Nuclear Informatics, National Nuclear Energy Agency (BATAN)
2022-12-01
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| Series: | Atom Indonesia |
| Subjects: | |
| Online Access: | https://aij.batan.go.id/index.php/aij/article/view/1191 |