Evaluation of the FLECHT-SEASET correlation for use in peak cladding temperature predictions during reflood
The FLECHT-SEASET correlation was evaluated to determine its ability to support a conservative prediction of peak cladding temperature (PCT) for the hottest fuel rod during reflooding of a reactor core following a loss-of-coolant accident (LOCA). A computer program, FLECSET, was written to facilitate the evaluation. Using FLECSET, 15 FLECHT-SEASET tests and ten FLECHT tests were benchmarked to determine the applicability of the correlation to 15 x 15 and 17 x 17 fuel assembly configurations. These tests spanned the range of applicability for the correlation (flooding rates: 0.59 to 6.1 in./s; pressures: 20 to 60 psia; initial cladding temperatures: 496 to 1636/sup 0/F; peak power; 0.4 to 1.0 kW/ft and variable flooding rates). The study demonstrated that the correlation must be further refined before being used in the analysis of a hot pin heatup during reflood.
- OSTI ID:
- 5538014
- Report Number(s):
- CONF-851115-; TRN: 86-024145
- Journal Information:
- Trans. Am. Nucl. Soc.; (United States), Vol. 50; Conference: American Nuclear Society winter meeting, San Francisco, CA, USA, 10 Nov 1985
- Country of Publication:
- United States
- Language:
- English
Similar Records
PWR FLECHT SEASET unblocked bundle, forced and gravity reflood task data report. Volume 1
Analysis of FLECHT and FLECHT-SEASET reflood tests with RELAP5/MOD2
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
BWR TYPE REACTORS
LOSS OF COOLANT
REACTOR SAFETY
HEAT TRANSFER
HYDRAULICS
PWR TYPE REACTORS
FUEL CANS
FUEL ELEMENTS
REACTOR ACCIDENTS
VERY HIGH TEMPERATURE
ACCIDENTS
ENERGY TRANSFER
FLUID MECHANICS
MECHANICS
REACTOR COMPONENTS
REACTORS
SAFETY
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210100 - Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled