Demonstration of fuel resistant to pellet-cladding interaction: Phase 2. Fourth semiannual report, July-December 1980. [BWR]
- comp.
This program has as its ultimate objective the demonstration of an advanced fuel design that is resistant to the failure mechanism known as fuel pellet-cladding interaction (PCI). Two fuel concepts have been developed for possible demonstration: (a) Cu-barrier fuel and (b) Zr-liner fuel. These advanced fuels (known collectively as barrier fuels) have special fuel cladding designed to avoid the harmful effects of localized stress and reactive fission products during reactor service. Within the scope of this program one of these concepts had to be selected for a large-scale demonstration in a commercial power reactor. The selection was made to demonstrate Zr-liner fuel and to include bundles which have liners prepared from either low oxygen sponge zirconium or of crystal bar zirconium. The demonstration is intended to include a total of 132 barrier bundles in the reload for Quad Cities Unit 2, Cycle 6. In the current report period changes in the nuclear design were made to respond to changes in the Energy Utilization Plan for Quad Cities Unit 2. Bundle designs were completed, and were licensed for use in a BWR/3. The core specific licensing will be done as part of the reload license for Quad Cities Unit 2, Cycle 6.
- Research Organization:
- Commonwealth Research Corp., Chicago, IL (USA)
- DOE Contract Number:
- AC02-77ET34001
- OSTI ID:
- 6278671
- Report Number(s):
- GEAP-25163-4; ON: DE81026958; TRN: 81-013930
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
36 MATERIALS SCIENCE
BWR TYPE REACTORS
FUEL CANS
FUEL-CLADDING INTERACTIONS
PROTECTIVE COATINGS
RESEARCH PROGRAMS
PERFORMANCE TESTING
ZIRCALOY 2
MICROSTRUCTURE
PHYSICAL RADIATION EFFECTS
STRESS CORROSION
BURNUP
FUEL RODS
LOSS OF COOLANT
SIMULATION
THERMAL STRESSES
ZIRCONIUM
ZIRCONIUM OXIDES
ACCIDENTS
ALLOYS
CHALCOGENIDES
CHEMICAL REACTIONS
CHROMIUM ADDITIONS
CHROMIUM ALLOYS
COATINGS
CORROSION
CRYSTAL STRUCTURE
ELEMENTS
FUEL ELEMENTS
IRON ADDITIONS
IRON ALLOYS
METALS
OXIDES
OXYGEN COMPOUNDS
RADIATION EFFECTS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTORS
STRESSES
TESTING
TIN ALLOYS
TRANSITION ELEMENT COMPOUNDS
TRANSITION ELEMENTS
WATER COOLED REACTORS
WATER MODERATED REACTORS
ZIRCALOY
ZIRCONIUM ALLOYS
ZIRCONIUM BASE ALLOYS
ZIRCONIUM COMPOUNDS
220900* - Nuclear Reactor Technology- Reactor Safety
210100 - Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
360106 - Metals & Alloys- Radiation Effects
360105 - Metals & Alloys- Corrosion & Erosion