Thermohydraulic and thermal stress aspects of a porous blockage in an LMFBR fuel assembly
Conference
·
OSTI ID:5853834
The current safety scenarios of Liquid Metal Fast Breeder Reactors (LMFBR) under local fault propagation include the study of a hypothetical accident initiated by the formation of an external debris porous blockage in a fuel subassembly. In this preliminary experimental and analytical investigation, a non-heat-generating porous blockage was postulated to cover 18 flow channels of a 37 pin Fast Test Reactor (FTR) type fuel subassembly. The axial extent of the blockage is 50 mm. The blockage material is stainless steel (SS 316) with 30 percent average porosity (percent void volume). The blockage and the pins were modeled with a finite element technique and the thermal field in the blockage was predicted. This thermal field was utilized to do a planar thermal stress analysis of the postulated blockage. To verify the analytical model and also to better understand the thermal-hydraulics of such a porous blockage out-of-pile tests were conducted in a sodium loop. Data from the out-of-pile tests was utilized to calibrate and improve the analytical model.
- Research Organization:
- Argonne National Laboratory (ANL), Argonne, IL (United States)
- Sponsoring Organization:
- USDOE
- DOE Contract Number:
- W-31109-ENG-38
- OSTI ID:
- 5853834
- Report Number(s):
- CONF-790802-62
- Country of Publication:
- United States
- Language:
- English
Similar Records
Sodium flow blockage in liquid-metal fast breeder reactors: sweepout of a planar blockage
Blockages in LMFBR fuel assemblies: a review of experimental and theoretical studies
Survival of peripheral pins during a TOP-HCDA. [LMFBR]
Journal Article
·
Sun Nov 30 23:00:00 EST 1980
· Nucl. Sci. Eng.; (United States)
·
OSTI ID:6883831
Blockages in LMFBR fuel assemblies: a review of experimental and theoretical studies
Technical Report
·
Mon Aug 08 00:00:00 EDT 1977
·
OSTI ID:7301883
Survival of peripheral pins during a TOP-HCDA. [LMFBR]
Conference
·
Sun Jul 01 00:00:00 EDT 1979
·
OSTI ID:5779314
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210500 -- Power Reactors
Breeding
22 GENERAL STUDIES OF NUCLEAR REACTORS
220600 -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
220900* -- Nuclear Reactor Technology-- Reactor Safety
BREEDER REACTORS
ENERGY TRANSFER
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FFTF REACTOR
FLOW BLOCKAGE
FLUID MECHANICS
FUEL ASSEMBLIES
HEAT TRANSFER
HYDRAULICS
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
MATHEMATICAL MODELS
MECHANICS
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
SODIUM COOLED REACTORS
STRESSES
TEMPERATURE DISTRIBUTION
TEST REACTORS
THERMAL STRESSES
210500 -- Power Reactors
Breeding
22 GENERAL STUDIES OF NUCLEAR REACTORS
220600 -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
220900* -- Nuclear Reactor Technology-- Reactor Safety
BREEDER REACTORS
ENERGY TRANSFER
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FFTF REACTOR
FLOW BLOCKAGE
FLUID MECHANICS
FUEL ASSEMBLIES
HEAT TRANSFER
HYDRAULICS
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
MATHEMATICAL MODELS
MECHANICS
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
SODIUM COOLED REACTORS
STRESSES
TEMPERATURE DISTRIBUTION
TEST REACTORS
THERMAL STRESSES