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Validation of deterministic code OpenNTP for the analysis of the C5G7-1D benchmark with different configurations
M Lahdour1, T El Bardouni1, O El Hajjaji1
1Radiations and Nuclear Systems Laboratory, ERSN, Faculty of Sciences, Abdelmalek Essaadi University, Tetuan, Morocco.
The OpenNTP code accurately solves neutronics problems, as verified by analyzing the C5G7 benchmark with varying control rod configurations. This demonstrates its capability for high-performance and exact neutron transport calculations.
Area of Science:
- Nuclear Engineering
- Computational Physics
Background:
- Neutronics codes are essential for nuclear reactor design and analysis.
- Verifying code accuracy is crucial for reliable simulations.
Purpose of the Study:
- To validate the OpenNTP (Open Neutron Transport Package) code's performance.
- To assess the code's ability to reproduce exact calculation results for heterogeneous benchmarks.
Main Methods:
- Analysis of the one-dimensional C5G7 benchmark with varied control rod positions.
- Sensitivity studies on multiplication factors using different spatial and angular meshes.
- Investigation of control rod influence on scalar fluxes and power distribution.
Main Results:
- OpenNTP code results showed good agreement with reference values.
- Significant assembly power distribution errors were observed for the unrodded C5G7 benchmark case.
- Spatial and angular discretization sensitivity was evaluated.
Conclusions:
- The OpenNTP code accurately solves neutronics problems.
- The code is suitable for high-performance and exact neutron transport calculations.
- The study highlights the importance of accurate modelling for heterogeneous systems.
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