Skip to main content
OSTI.GOVU.S. Department of Energy Office of Scientific and Technical Information
U.S. Department of Energy
Office of Scientific and Technical Information
 

Effect of incoherency on voiding dynamics in LMFBR wire-wrapped subassemblies

Conference ·
OSTI ID:7105206
; ;
Current accident analysis tools (SAS, etc.) are based upon one-dimensional treatment of the sodium behavior in wire-wrapped subassemblies under accident conditions. As such, calculated values of sodium voiding rates (in the case of loss of flow (LOF) with failure to scram) and dryout and cladding failures (in the case of loss-of-pipe integrity (LOPI) with scram) are on the conservative side in view of the large radial temperature gradients existing at boiling inception. The purpose of this paper is to discuss the intrasubassembly incoherence effects including proposed modeling and experiments to determine the magnitude of these effects in a full-size LMFBR subassembly.
Research Organization:
Argonne National Lab., IL (USA)
DOE Contract Number:
W-31109-ENG-38
OSTI ID:
7105206
Report Number(s):
CONF-770640-1
Country of Publication:
United States
Language:
English

Similar Records

Water tests for determining post voiding behavior in the LMFBR
Technical Report · Tue Jun 01 00:00:00 EDT 1976 · OSTI ID:7149440
Two-dimensional modeling of sodium boiling in a simulated LMFBR loss-of-flow test
Conference · Sat Dec 31 23:00:00 EST 1983 · OSTI ID:6219804
Sodium boiling dryout correlation for LMFBR fuel assemblies
Conference · Sat Dec 31 23:00:00 EST 1983 · OSTI ID:6715007

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210500 -- Power Reactors
Breeding
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
BREEDER REACTORS
DRYOUT
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FUEL ASSEMBLIES
FUEL ELEMENT CLUSTERS
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
LOSS OF FLOW
REACTOR ACCIDENTS
REACTORS
TEMPERATURE GRADIENTS
VOIDS