RELAP5/MOD3 subcooled boiling model assessment

Technical Report · Fri May 01 04:00:00 EDT 1998

DOI:https://doi.org/10.2172/654175· OSTI ID:654175

Devkin, A S; Podosenov, A S ^[1]

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1. Russian Research Center, Moscow (Russian Federation). Nuclear Safety Inst.

This report presents the assessment of the RELAP5/Mod3 (5m5 version) code subcooled boiling process model which is based on a variety of experiments. The accuracy of the model is confirmed for a wide range of regime parameters for the case of uniform heating along the channel. The condensation rate is rather underpredicted, which may lead to considerable errors in void fraction behavior prediction in subcooled boiling regimes for nonuniformly or unheated channels.

• Research Organization: Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, Washington, DC (United States); Russian Research Center, Nuclear Safety Inst., Moscow (Russian Federation)
• Sponsoring Organization: Nuclear Regulatory Commission, Washington, DC (United States)
• OSTI ID: 654175
• Report Number(s): NUREG/IA--0025; ON: TI98005215
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
22 GENERAL STUDIES OF NUCLEAR REACTORS
99 GENERAL AND MISCELLANEOUS
BWR TYPE REACTORS
EVALUATION
MATHEMATICAL MODELS
PWR TYPE REACTORS
R CODES
REACTOR ACCIDENTS
SUBCOOLED BOILING
TWO-PHASE FLOW
VOID FRACTION