Analysis of a control rod ejection accident in a boron-free small modular reactor with coupled neutronics/thermal-hydraulics code

Author:

Alzaben Y.,Sanchez-Espinoza V.H.,Stieglitz R.

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference22 articles.

1. Core neutronics and safety characteristics of a boron-free core for Small Modular Reactors;Alzaben;Ann. Nucl. Energy,2019

2. Rod Ejection Accident 3D-dynamic analysis in trillo NPP with RELAP5/PARCS V2.7;Barrachina,2010

3. Basualdo, J.R., Sánchez-Espinoza, V.H., Stieglitz, R., Macián-Juan, R., 2017. PARCS-SUBCHANFLOW-TRANSURANUS Multiphysics Coupling For Improved PWR’s Simulations, in: Proceedings of ICAPP. Fukui and Kyoto, Japan.

4. Key reactor system components in integral pressurized-water reactors (iPWRs);Belles,2015

5. A review of the thermophysical properties of MOX and UO2 fuels;Carbajo;J. Nucl. Mater.,2001

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1. Bold application of the sNDM diffusion method to REA in a D2O/H2O-cooled thorium-fueled SMR core with azimuthal mesh;Progress in Nuclear Energy;2024-10

2. Multi-physics analysis of SBLOCA by coupled Neutronics/Thermal-Hydraulics full plant model;Nuclear Engineering and Design;2024-08

3. Verification of the Coupled Code PARCS/TWOPORFLOW with Rod Ejection Accident Calculations for Small Modular Reactors;Nuclear Science and Engineering;2024-06-13

4. References;Handbook on Thermal Hydraulics in Water-Cooled Nuclear Reactors;2024

5. References;Handbook on Thermal Hydraulics in Water-Cooled Nuclear Reactors;2024

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