Core coolability limits in LMFBR loss-of-heat-sink accidents
Considerable attention has been devoted to the loss-of-heat-sink (LOHS) accident after successful reactor shutdown in a liquid-metal fast breeder reactor (LMFBR). It has been estimated that this accident accounts for more than 80% of the risk of hypothetical core disruptive accidents; therefore, attention should be focused on this specific contributor. In this paper, an analytical study has been performed to estimate the decay heat powers that can be safely removed by sustained free convection boiling without causing cladding damage for a complete range of inlet temperatures from nominal to saturation. This study has been performed with the codes LOOP-1C, a one-dimensional (1-D) loop code; LOOP-TH, a two-dimensional (2-D) bundle code with 1-D loop modeling; and THORAX, a 2-D bundle code. The geometry used has been one 19-pin test bundle in parallel with a return leg connected by lower and upper plena.
- Research Organization:
- Oak Ridge National Lab., TN (USA)
- DOE Contract Number:
- AC05-84OR21400
- OSTI ID:
- 6758881
- Report Number(s):
- CONF-840614-66; ON: DE84014254
- Resource Relation:
- Conference: Annual meeting of the American Nuclear Society, New Orleans, LA, USA, 3 Jun 1984; Other Information: Portions are illegible in microfiche products
- Country of Publication:
- United States
- Language:
- English
Similar Records
Two-dimensional modeling of sodium boiling in a simulated LMFBR loss-of-flow test
THORAX pretest prediction of a sodium-boiling transient in a 19-pin simulated LMFBR driver bundle
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
AFTER-HEAT REMOVAL
DRYOUT
HEAT FLUX
HEAT TRANSFER
LMFBR TYPE REACTORS
REACTOR ACCIDENTS
RHR SYSTEMS
FAILURES
AFTER-HEAT
COMPUTER CALCULATIONS
HYDRAULICS
REACTOR SAFETY
ACCIDENTS
BREEDER REACTORS
COOLING SYSTEMS
ENERGY SYSTEMS
ENERGY TRANSFER
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FLUID MECHANICS
LIQUID METAL COOLED REACTORS
MECHANICS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTORS
REMOVAL
SAFETY
220900* - Nuclear Reactor Technology- Reactor Safety
210500 - Power Reactors
Breeding