Sodium boiling dryout correlation for LMFBR fuel assemblies
Under certain postulated accident conditions for a Liquid Metal Fast Breeder Reactor (LMFBR), such as the failure of the shutdown heat removal system (SHRS), sodium boiling and clad dryout might occur in the fuel assemblies. It is important to predict the time from boiling inception to dryout, since sustained clad dryout will result in core damage. In this paper a dryout correlation is presented. This correlation is based on 21 boiling tests which resulted in dryout from the THORS BUNDLE 6A, a 19-pin full-length simulated LMFBR fuel assembly and from the THORS Bundle 9, a 61-pin full-length simulated LMFBR fuel assembly. All these tests were performed as follows: for each specified bundle power, an initial steady-state high sodium flow was established, for which sodium boiling did not occur in the bundle. The temperature at the outlet of the test section was approx. 700/sup 0/C. Then, using a programmable pump control system, the flow was reduced to a low value and boiling occurred.
- Research Organization:
- Oak Ridge National Lab., TN (USA)
- DOE Contract Number:
- AC05-84OR21400
- OSTI ID:
- 6715007
- Report Number(s):
- CONF-840614-68; ON: DE84014257
- Country of Publication:
- United States
- Language:
- English
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ACCIDENTS
AFTER-HEAT
AFTER-HEAT REMOVAL
BREEDER REACTORS
COOLING SYSTEMS
DRYOUT
ENERGY SYSTEMS
ENERGY TRANSFER
EPITHERMAL REACTORS
FAILURES
FAST REACTORS
FBR TYPE REACTORS
FLUID MECHANICS
FUEL ASSEMBLIES
FUEL CANS
FUEL ELEMENTS
FUEL PINS
HEAT TRANSFER
HYDRAULICS
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
MECHANICS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR SAFETY
REACTOR SHUTDOWN
REACTORS
REMOVAL
RHR SYSTEMS
SAFETY
SHUTDOWNS
TEST FACILITIES