Validation of SSC using the FFTF natural-circulation tests

Conference · Fri Jan 01 00:00:00 EST 1982

OSTI ID:5194884

Horak, W C; Guppy, J G; Kennett, R J

As part of the Super System Code (SSC) validation program, the 100% power FFTF natural circulation test has been simulated using SSC. A detailed 19 channel, 2 loop model was used in SSC. Comparisons showed SSC calculations to be in good agreement with the Fast Flux Test Facility (FFTF), test data. Simulation of the test was obtained in real time.

• Research Organization: Brookhaven National Lab., Upton, NY (USA)
• DOE Contract Number: AC02-76CH00016
• OSTI ID: 5194884
• Report Number(s): BNL-NUREG-31437; CONF-820925-1; ON: DE82017630; TRN: 82-018883
• Resource Relation: Conference: NRC meeting on advances in reactor physics and core thermal hydraulics, Kiamesha Lake, NY, USA, 22 Sep 1982
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
FFTF REACTOR
LOSS OF FLOW
COMPUTER CALCULATIONS
FLOW RATE
HEAT TRANSFER
HYDRAULICS
NATURAL CONVECTION
REACTOR SAFETY
TEMPERATURE GRADIENTS
ACCIDENTS
CONVECTION
ENERGY TRANSFER
EPITHERMAL REACTORS
FAST REACTORS
FLUID MECHANICS
LIQUID METAL COOLED REACTORS
MECHANICS
REACTOR ACCIDENTS
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
SAFETY
SODIUM COOLED REACTORS
TEST REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
220600 - Nuclear Reactor Technology- Research
Test & Experimental Reactors