Flow instability testing of annular geometry fuel elements for LOCA and slow ramp transient with upflow of coolant

Conference · Wed Jan 01 00:00:00 EST 1992

OSTI ID:6479817

Smith, A C ^[1]; Blake, J E; Childerson, M T; Ohrn, T R; Privette, R M ^[2]

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1. Westinghouse Savannah River Co., Aiken, SC (United States)
2. Babcock and Wilcox Co., Alliance, Oh (United States)

This report discusses testing performed to provide data for evaluation and benchmarking of computer codes used for predicting the performance of reactor fuel elements of annular geometry with upward flow of coolant.

• Research Organization: Westinghouse Savannah River Co., Aiken, SC (United States)
• Sponsoring Organization: USDOE; USDOE, Washington, DC (United States)
• DOE Contract Number: AC09-89SR18035
• OSTI ID: 6479817
• Report Number(s): WSRC-MS-92-406; CONF-930830-8; ON: DE93008794
• Resource Relation: Conference: National conference and exposition on heat transfer, Atlanta, GA (United States), 8-11 Aug 1993
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
99 GENERAL AND MISCELLANEOUS//MATHEMATICS, COMPUTING, AND INFORMATION SCIENCE
FLUID FLOW
STABILITY
PRODUCTION REACTORS
ANNULAR FUEL ELEMENTS
LOSS OF COOLANT
HEAT TRANSFER
HYDRAULICS
R CODES
REACTOR SAFETY
TEST FACILITIES
TESTING
ACCIDENTS
COMPUTER CODES
ENERGY TRANSFER
FLUID MECHANICS
FUEL ELEMENTS
MECHANICS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTORS
SAFETY
220900* - Nuclear Reactor Technology- Reactor Safety
220600 - Nuclear Reactor Technology- Research
Test & Experimental Reactors
990200 - Mathematics & Computers