Verification of the Coupled Code PARCS/TWOPORFLOW with Rod Ejection Accident Calculations for Small Modular Reactors
Author:
Affiliation:
1. Karlsruher Institut für Technologie, Institut für Neutronenphysik und Reaktortechnik, Eggenstein-Leopoldshafen, Germany
2. Universidad Politécnica de Madrid, Madrid, Spain
Funder
Bundesministerium für Bildung und Forschung
Publisher
Informa UK Limited
Link
https://www.tandfonline.com/doi/pdf/10.1080/00295639.2024.2357953
Reference23 articles.
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2. The multiscale thermal‐hydraulic simulation for nuclear reactors: A classification of the coupling approaches and a review of the coupled codes
3. The Virtual Environment for Reactor Applications (VERA): Design and architecture
4. Current Status and On-Going Development of VTT’s Kraken Core Physics Computational Framework
5. An Evaluation of the Rod Ejection Accident in Westinghouse Pressurized Water Reactors Using Spatial Kinetics Methods;RISHER D. H.;WCAP-7588, Rev. 1A, Westinghouse Electric Company,1975
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