Uncertainty Quantification of the RELAP5 Interfacial Friction Model in the Rod Bundle Geometry
Author:
Affiliation:
1. Institute of Nuclear Safety System, Inc. (INSS), 64 Sata, Mihama-cho, Mikata-gun, Fukui 919-1205, Japan e-mail:
2. MHI Nuclear Engineering Co., Ltd. (MNEC), 3-3-1 Minatomirai, Nishi-ku, Yokohama, Kanagawa 220-8401, Japan e-mail:
Abstract
Publisher
ASME International
Subject
Nuclear Energy and Engineering,Radiation
Link
http://asmedigitalcollection.asme.org/nuclearengineering/article-pdf/doi/10.1115/1.4031377/6066278/ners_2_2_021003.pdf
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3. Secondary-Side Depressurization during PWR Cold-Leg Small Break LOCAs Based on ROSA-V/LSTF Experiments and Analyses;J. Nucl. Sci. Technol.,1998
4. Effects of Secondary Depressurization on Core Cooling in PWR Vessel Bottom Small Break LOCA Experiments With HPI Failure and Gas Inflow;J. Nucl. Sci. Technol.,2006
5. Quantifying Reactor Safety Margins: Application of Code Scaling, Applicability, and Uncertainty Evaluation Methodology to a Large-Break Loss-of-Coolant Accident,1989
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1. Validation of a three-dimensional two-phase code, CUPID, using a rod-bundle boiling test facility, SIRIUS-3D;Annals of Nuclear Energy;2024-12
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