Neutronics and Thermal Hydraulic Coupling Analysis for MTR Reactors | ||
Arab Journal of Nuclear Sciences and Applications | ||
Volume 58, Issue 2, April 2025, Pages 21-28 PDF (787.78 K) | ||
Document Type: Original Article | ||
DOI: 10.21608/ajnsa.2025.354012.1872 | ||
Authors | ||
Asmaa Gamal Abo Elnour* 1; abdelrahman Mahmoud Hassan2; Mohamed Abdullah Mohamed Elsaied3; Abd ElFatah Abd ElMaksoud4; Nader Abdelhaleem5 | ||
1Reactor Department, Nuclear Research Center, Atomic Energy Authority, Egypt. | ||
2Egyptian Atomic Energy Authority, Egypt. | ||
3Reactors Department, Nuclear Research Center, Egyptian Atomic Energy Authority, Egypt. | ||
4Reactors Department-Nuclear Research center. Egyptian Atomic Energy Authority | ||
5Reactors department, Egyptian Atomic Energy Authority | ||
Abstract | ||
The integration of neutronics and thermal-hydraulic in multi-physics coupling analysis plays a crucial role in achieving high-fidelity simulations of nuclear reactor cores. In the current work, the neutronics and thermal hydraulic Multi-physics coupling methodology was proposed for the plate-type fuel assemblies inside Material Test Reactor cores. The coupling technique is based on the two-way and external coupling paradigms and accomplished using Monte Carlo Reactor analysis and subchannel thermal-hydraulic codes. The coupling interface was developed using Python and Modern Fortran programming languages. The three-dimensional reactor physics modelling was developed using MCNP6 code while the one-dimensional thermal-hydraulic model was developed using PARET/ANL v2.1 for a typical MTR plate-type fuel reactor. Subsequently, the coupling analysis was conducted using the developed integrated code system. The simulation results from the coupling and non-coupling methods were compared to validate the feasibility of the coupling approach, revealing that the proposed coupling method offers greater accuracy compared to the traditional approach. | ||
Keywords | ||
MCNP6; PARET/ANL; MTR; Multi physics | ||
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