Full-scale neutronic/thermal–hydraulic coupling analysis of plate-type reactor based on RMC and MOOSE

Author:

Chen Junyi,Liu Guodong,Huang Shanfang,He Ying,Qiu Meiming,Wang Kan,Lu Chuan,Li Zhigang

Publisher

Elsevier BV

Reference29 articles.

1. Extension and validation of the SubChanFlow code for the thermo-hydraulic analysis of MTR cores with plate-type fuel assemblies;Almachi;Nucl. Eng. Des.,2021

2. High-fidelity steady-state and transient simulations of an MTR research reactor using Serpent2/subchanflow;Almachi;Energies,2022

3. Validation of the dynamic simulation capabilities of Serpent2/Subchanflow using experimental data from the research reactor SPERT IV D-12/25;Almachi;Nucl. Eng. Des.,2024

4. Thermal-Hydraulic code for estimating safety limits of nuclear reactors with plate type fuels;Castellanos,2017

5. Petrov–Galerkin finite element stabilization for two-phase flows;Giordano;Internat. J. Numer. Methods Fluids,2006

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