Core coolability limits in LMFBR loss-of-heat-sink accidents
Abstract
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.
- Authors:
- Publication Date:
- Research Org.:
- Oak Ridge National Lab., TN (USA)
- OSTI Identifier:
- 6758881
- Report Number(s):
- CONF-840614-66
ON: DE84014254
- DOE Contract Number:
- AC05-84OR21400
- Resource Type:
- Conference
- 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
- Subject:
- 22 GENERAL STUDIES OF NUCLEAR REACTORS; 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
Citation Formats
Rose, S D, and Carbajo, J J. Core coolability limits in LMFBR loss-of-heat-sink accidents. United States: N. p., 1984.
Web.
Rose, S D, & Carbajo, J J. Core coolability limits in LMFBR loss-of-heat-sink accidents. United States.
Rose, S D, and Carbajo, J J. 1984.
"Core coolability limits in LMFBR loss-of-heat-sink accidents". United States. https://www.osti.gov/servlets/purl/6758881.
@article{osti_6758881,
title = {Core coolability limits in LMFBR loss-of-heat-sink accidents},
author = {Rose, S D and Carbajo, J J},
abstractNote = {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.},
doi = {},
url = {https://www.osti.gov/biblio/6758881},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Sun Jan 01 00:00:00 EST 1984},
month = {Sun Jan 01 00:00:00 EST 1984}
}