2015
DOI: 10.2172/1229703
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Modeling of the Reactor Core Isolation Cooling Response to Beyond Design Basis Operations - Interim Report

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Cited by 10 publications
(34 citation statements)
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“…The computer aided drafting and CFD accomplishments described in Reference [6] have critically informed the latest system-level model solution (i.e., the homologous-curve solution) with respect to:…”
Section: Melcor Modeling Effortsmentioning
confidence: 99%
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“…The computer aided drafting and CFD accomplishments described in Reference [6] have critically informed the latest system-level model solution (i.e., the homologous-curve solution) with respect to:…”
Section: Melcor Modeling Effortsmentioning
confidence: 99%
“…As part of the efforts to understand the unexpected "self-regulating" mode of the RCIC systems in the Fukushima Daiichi Unit 2 accidents and extend BWR RCIC and PWR AFW operational range and flexibility, mechanistic models for the Terry turbine, based on Sandia's 2015 efforts [6], have been developed and implemented in the RELAP-7 code to simulate the RCIC system. RELAP-7 is a new reactor system safety analysis code currently under development at Idaho National Laboratory [7][8].…”
Section: Relap-7 Modeling Effortsmentioning
confidence: 99%
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