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Enhanced Verification for RELAP5-3D Parameter and Sensitivity Studies
Volume 3: Thermal-Hydraulics, 2016The RELAP5-3D1 program solves a complex system of governing, closure and special process equations to model the underlying physics of nuclear power plants. For SQA (software quality assurance), the code must be verified and validated (V&V) to ensure proper performance before release to users.
George L. Mesina, Nolan Anderson
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A coupled RELAP5-3D/CFD methodology with a proof-of-principle calculation
Nuclear Engineering and Design, 2001Abstract The RELAP5-3D computer code was modified to make the explicit coupling capability in the code fully functional. As a test of the modified code, a coupled RELAP5/RELAP5 analysis of the Edwards–O'Brien blowdown problem was performed which showed no significant deviations from the standard RELAP5-3D predictions.
D.L. Aumiller +2 more
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Analysis of Leaks Through Microchannel Cracks Using RELAP5-3D
Nuclear Technology, 2009The purpose of the present work is to study the flow leakage through postulated microchannels. In the framework of the leak before break, it is reasonable to assume that a detectable leak develops before a large break occurs. A large pressure difference may exist between the crack inlet and outlet; the fluid residence time is so brief that ...
Angelo Frisani, Yassin A. Hassan
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Thermal Hydraulic Analysis and Modeling of the HTTR Using the RELAP5-3D
Journal of Nuclear Energy Science & Power Generation Technology, 2017A thermal hydraulic model for the HTTR (High Temperature Engineering Test Reactor) has been developed using the RELAP5-3D code. The HTTR is a high temperature gas-cooled reactor (HTGR) developed, designed, constructed, and operated by the Japan Atomic Energy Research Institute (JAERI).
Scari ME, Costa AL, Ramos MC, Pereira C
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In-Vessel Retention Modeling Capabilities of SCDAP/RELAP5-3D©
10th International Conference on Nuclear Engineering, Volume 3, 2002Molten core materials may relocate to the lower head of a reactor vessel in the latter stages of a severe accident. Under such circumstances, in-vessel retention (IVR) of the molten materials is a vital step in mitigating potential severe accident consequences.
D. L. Knudson, J. L. Rempe
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Merger of the Dissolved Gas Method into RELAP5-3D
2022George Mesina, Cole Blakely
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BEPU analysis of a passive decay heat removal system with RELAP5/MOD3.3 and RELAP5-3D
Progress in Nuclear Energy, 2021Fabio Alcaro +2 more
exaly
Linear stability analysis of RELAP5 two-fluid model in nuclear reactor safety results
Annals of Nuclear Energy, 2020P Munshi, C Allison
exaly
Improvements to PHISICS/RELAP5-3D© capabilities for simulating HTGRs
2017The theory for the time step control has been developed and implemented in the PHISICS/RELAP5-3D© coupled code resulting in three different methodologies and two different ways to define the tolerance. More than 2,000 lines have been added to the PHISICS code and to the RELAP5-3D© interface.
Balestra, Paolo +5 more
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