Severe-damage experiments in irradiated mixed-oxide subassemblies
Conference
·
· Transactions of the American Nuclear Society; (United States)
OSTI ID:6672193
- Kernforschungsanlage Karlsruhe (Germany)
Severe-damage experiments (Mol-7C series) have been performed in the BR-2 reactor at Mol, Belgium. The main objective was to investigate the consequences of local cooling disturbances in liquid-metal-cooled reactor fuel subassemblies. The cooling deficit was generated by a central blockage. During irradiation, this blockage caused significant local damage, including melting of cladding and fuel. As the most important parameter, the burnup of the tested bundles was changed. According to Table I, the burnups varied from 1.7 to 5 and 10 at.%. In this paper, preliminary results of the postirradiation examination (PIE) of Mol-7C/6 are presented and discussed in comparison to the previous experiments.
- OSTI ID:
- 6672193
- Report Number(s):
- CONF-921102--
- Conference Information:
- Journal Name: Transactions of the American Nuclear Society; (United States) Journal Volume: 66
- Country of Publication:
- United States
- Language:
- English
Similar Records
Results of postirradiation examination of the in-pile blockage experiments MOL-7C/4 and MOL-7C/5
The in-pile local blockage experiments Mol-7C/6 and 7; Results and preliminary interpretation
Mol-7B-an 18-pin bundle operating 200 days beyond breach
Journal Article
·
Tue Oct 01 00:00:00 EDT 1991
· Nuclear Technology; (United States)
·
OSTI ID:5712052
The in-pile local blockage experiments Mol-7C/6 and 7; Results and preliminary interpretation
Journal Article
·
Tue Sep 01 00:00:00 EDT 1992
· Nuclear Technology; (United States)
·
OSTI ID:7244123
Mol-7B-an 18-pin bundle operating 200 days beyond breach
Journal Article
·
Wed Mar 31 23:00:00 EST 1982
· Nucl. Technol.; (United States)
·
OSTI ID:7156908
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210500* -- Power Reactors
Breeding
ACCIDENTS
BR-2 REACTOR
BURNUP
COOLING
ENRICHED URANIUM REACTORS
FUEL ASSEMBLIES
FUEL ELEMENT FAILURE
FUEL ELEMENTS
FUEL PINS
IRRADIATION REACTORS
LIQUID METAL COOLED REACTORS
LOSS OF FLOW
MATERIALS TESTING REACTORS
MELTING
PHASE TRANSFORMATIONS
POST-IRRADIATION EXAMINATION
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTORS
TANK TYPE REACTORS
TESTING
THERMAL ANALYSIS
THERMAL REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
210500* -- Power Reactors
Breeding
ACCIDENTS
BR-2 REACTOR
BURNUP
COOLING
ENRICHED URANIUM REACTORS
FUEL ASSEMBLIES
FUEL ELEMENT FAILURE
FUEL ELEMENTS
FUEL PINS
IRRADIATION REACTORS
LIQUID METAL COOLED REACTORS
LOSS OF FLOW
MATERIALS TESTING REACTORS
MELTING
PHASE TRANSFORMATIONS
POST-IRRADIATION EXAMINATION
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTORS
TANK TYPE REACTORS
TESTING
THERMAL ANALYSIS
THERMAL REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS