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Benchmark study of OPAL research reactor using MCNP codes
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N. M. A. Mohamed
Veröffentlicht/Copyright:
23. Februar 2021
Abstract
This work is a part of the International Atomic Energy Agency (IAEA) Coordinated Research Project (CRP) titled: \Benchmarks of Computational Tools against Experimental Data on Fuel Burnup and Material Activation for Utilization, Operation and Safety Analysis of Research Reactors". The OPAL research reactor has been modelled using MCNP codes as a benchmark study. Neutron flux profiles, critical configurations, control rod worths, fuel burnup and kinetic parameters have been calculated. Comparisons between the calculated results and the experimental data given in the OPAL benchmark have been performed.
Online erschienen: 2021-02-23
Erschienen im Druck: 2019-12-06
© 2020 by Walter de Gruyter Berlin/Boston
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Artikel in diesem Heft
- Frontmatter
- CALENDAR OF EVENTS · VERANSTALTUNGSKALENDER
- Thermal hydraulic characteristics of two-phase natural circulation for secondary side passive residual heat removal system
- Operating experience feedback from incidental fluctuations of the power measurement channel at ETRR-2
- Benchmark study of OPAL research reactor using MCNP codes
- Method based on directed graph and binary decision diagram to break logic loops
- CFD code-to-code benchmarking on simulation of fire and smoke propagation for nuclear applications
- TRACE simulations of IIST cooldown experiments
- Flow and heat transfer characteristics in rough micro-channels
- Technical Note
- In memoriam
- Note · Imprint
Artikel in diesem Heft
- Frontmatter
- CALENDAR OF EVENTS · VERANSTALTUNGSKALENDER
- Thermal hydraulic characteristics of two-phase natural circulation for secondary side passive residual heat removal system
- Operating experience feedback from incidental fluctuations of the power measurement channel at ETRR-2
- Benchmark study of OPAL research reactor using MCNP codes
- Method based on directed graph and binary decision diagram to break logic loops
- CFD code-to-code benchmarking on simulation of fire and smoke propagation for nuclear applications
- TRACE simulations of IIST cooldown experiments
- Flow and heat transfer characteristics in rough micro-channels
- Technical Note
- In memoriam
- Note · Imprint
