Analysis of loss-of-flow transients in a pool-type LMFBR using SSC-P
In order to have a general analytical capability for the safety evaluation of any proposed LMFBR system, the USNRC is sponsoring the development and validation of computer codes for both pool- and loop-type plants. The computer code for pool-type LMFBRs is designated SSC-P. This paper is concerned with the application of SSC-P to simulate loss-of-flow accident transients in a pool-type LMFBR. The models required for dynamic plant simulation are briefly highlighted. The system response is calculated for (1) a complete loss of electric power event, with scram, leading the plant into buoyancy-induced natural circulation, (2) a protected pipe rupture accident in the primary pump discharge line, and (3) an unprotected loss of off-site power event. For the last case, the predicted results from SSC-P are compared with the published results of Phenix behavior by NOVATOME.
- Research Organization:
- Brookhaven National Lab., Upton, NY (USA); University of Petroleum and Minerals, Dhahran (Saudi Arabia). Dept. of Mechanical Engineering
- DOE Contract Number:
- AC02-76CH00016
- OSTI ID:
- 6869905
- Report Number(s):
- BNL-NUREG-31679; CONF-820704-27; ON: DE82020527
- Resource Relation:
- Conference: International topical meeting on LMFBR safety, Lyon, France, 18 Jul 1982
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
LMFBR TYPE REACTORS
LOSS OF FLOW
HEAT TRANSFER
HYDRAULICS
COMPUTER CALCULATIONS
PRIMARY COOLANT CIRCUITS
REACTOR CORES
REACTOR SAFETY
TEMPERATURE GRADIENTS
ACCIDENTS
BREEDER REACTORS
COOLING SYSTEMS
ENERGY SYSTEMS
ENERGY TRANSFER
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FLUID MECHANICS
LIQUID METAL COOLED REACTORS
MECHANICS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTORS
SAFETY
220900* - Nuclear Reactor Technology- Reactor Safety
210500 - Power Reactors
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