A comparative study of STCP and SCDAP simulation of PBF SFD Test 1-1

Conference · Thu Jan 01 00:00:00 EST 1987

OSTI ID:6258341

Yang, J W; Khatib-Rahbar, M

This paper presents the results of a detailed comparison of the Source Term Code Package (STCP) and the SCDAP computer codes for simulation of the Power Burst Facility (PBF) Severe Fuel Damage (SFD) test 1-1. The SCDAP code is mechanistic, and has been benchmarked against a wide range of severe accident data. The SFD 1-1 test was designed to simulate the heatup and resulting fuel damage in the upper half of a 3000-Mw(t) PWR core approximately 2 to 3 hours after initiation of a small break accident, when the core is approximately 75% uncovered. 6 refs., 1 fig.

• Research Organization: Brookhaven National Lab., Upton, NY (USA)
• DOE Contract Number: AC02-76CH00016
• OSTI ID: 6258341
• Report Number(s): BNL-NUREG-39917; CONF-871101-19; ON: DE87011296; TRN: 87-035136
• Resource Relation: Conference: California State Air Resources Board, Los Angeles, CA, USA, 15 Nov 1987
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
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LOSS OF COOLANT
COMPUTERIZED SIMULATION
PWR TYPE REACTORS
FISSION PRODUCT RELEASE
FUEL ASSEMBLIES
HYDROGEN
PBF REACTOR
REACTOR CORES
REACTOR SAFETY EXPERIMENTS
S CODES
SOURCE TERMS
ACCIDENTS
COMPUTER CODES
ELEMENTS
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REACTOR ACCIDENTS
REACTOR COMPONENTS
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WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210200 - Power Reactors
Nonbreeding
Light-Water Moderated
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