Heat transfer processes during intermediate and large break loss-of-coolant accidents (LOCAs)

Technical Report · Mon Sep 01 00:00:00 EDT 1986

DOI:https://doi.org/10.2172/5358072· OSTI ID:5358072

Vojtek, I

The general purpose of this project was the investigation of the heat transfer regimes during the high pressure portion of blowdown. The main attention has been focussed on the evaluation of those phenomena which are most important in reactor safety, such as maximum and minimum critical heat flux and forced convection film boiling heat transfer. The experimental results of the 25-rod bundle blowdown heat transfer tests, which were performed at the KWU heat transfer test facility in Karlstein, were used as a database for the verification of different correlations which are used or were developed for the analysis of reactor safety problems. The computer code BRUDI-VA was used for the calculation of local values of important thermohydraulic parameters in the bundle.

• Research Organization: Gesellschaft fuer Reaktorsicherheit m.b.H. (GRS), Garching (Germany, F.R.); US Nuclear Regulatory Commission (NRC), Washington, DC (United States). Office of Nuclear Regulatory Research
• OSTI ID: 5358072
• Report Number(s): NUREG/IA-0002; ON: TI87900006
• Country of Publication: United States
• Language: English

Related Subjects

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BWR TYPE REACTORS
LOSS OF COOLANT
HEAT TRANSFER
HYDRAULICS
PWR TYPE REACTORS
BOILING
FAILURES
INTERNATIONAL AGREEMENTS
MATHEMATICAL MODELS
RESEARCH PROGRAMS
US NRC
ACCIDENTS
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ENERGY TRANSFER
FLUID MECHANICS
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NATIONAL ORGANIZATIONS
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WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210100 - Power Reactors
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