Out-of-pike experiments for fission gas release in LMFBR fuel subassemblies - gas release into blockage wake region with a wire-wrapped 37-pin bundle
Journal Article
·
· Am. Soc. Mech. Eng., (Pap.); (United States)
OSTI ID:5085362
This paper deals with fuel pin cooling capability under fission gas release into a wake region of local blockage in a fuel subassembly of an LMFBR, as a consequence of pin failure caused by a local blockage. Experiments for fission gas release into a locally blocked 37-pin bundle are described and results are given regarding various fission gas release modes. Data revealed that only at the gas accumulation zone in the wake region did temperature behind blockage increase significantly. The temperature field strongly depends on both coolant velocity and gas release rate. 17 refs.
- Research Organization:
- Toshiba Corp, Kawasaki, Japan
- OSTI ID:
- 5085362
- Journal Information:
- Am. Soc. Mech. Eng., (Pap.); (United States), Journal Name: Am. Soc. Mech. Eng., (Pap.); (United States) Vol. 81-WA/HT-62; ISSN ASMSA
- Country of Publication:
- United States
- Language:
- English
Similar Records
Local sodium boiling in a partially blocked simulated LMFBR subassembly (THORS Bundle 3B)
Comparison of computational results of the SABRE LMFBR pin bundle blockage code with data from well-instrumented out-of-pile test bundles (THORS bundles 3A and 5A)
Maximum wake temperature and Nusselt number behind blockages in sodium-cooled bundles
Technical Report
·
Wed May 04 00:00:00 EDT 1977
·
OSTI ID:7213715
Comparison of computational results of the SABRE LMFBR pin bundle blockage code with data from well-instrumented out-of-pile test bundles (THORS bundles 3A and 5A)
Technical Report
·
Sat Sep 01 00:00:00 EDT 1979
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OSTI ID:5916051
Maximum wake temperature and Nusselt number behind blockages in sodium-cooled bundles
Conference
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Fri Dec 31 23:00:00 EST 1976
·
OSTI ID:5289681
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
EPITHERMAL REACTORS
EVALUATION
FAST REACTORS
FBR TYPE REACTORS
FISSION PRODUCT RELEASE
FLOW BLOCKAGE
FUEL ASSEMBLIES
FUEL ELEMENT FAILURE
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
NUCLEAR FACILITIES
NUCLEAR POWER PLANTS
POWER PLANTS
REACTOR ACCIDENTS
REACTORS
TEMPERATURE DISTRIBUTION
THERMAL POWER PLANTS
210500 -- Power Reactors
Breeding
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
BREEDER REACTORS
EPITHERMAL REACTORS
EVALUATION
FAST REACTORS
FBR TYPE REACTORS
FISSION PRODUCT RELEASE
FLOW BLOCKAGE
FUEL ASSEMBLIES
FUEL ELEMENT FAILURE
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
NUCLEAR FACILITIES
NUCLEAR POWER PLANTS
POWER PLANTS
REACTOR ACCIDENTS
REACTORS
TEMPERATURE DISTRIBUTION
THERMAL POWER PLANTS