Actions for Demonstration of fuel resistant to pellet-cladding interaction [electronic resource] : Phase 2. Fourth semiannual report, July-December 1980. [BWR].
Demonstration of fuel resistant to pellet-cladding interaction [electronic resource] : Phase 2. Fourth semiannual report, July-December 1980. [BWR].
- Published
- Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy, 1981.
- Additional Creators
- United States. Department of Energy. Office of Scientific and Technical Information
Access Online
- Restrictions on Access
- Free-to-read Unrestricted online access
- Summary
- 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.
- Report Numbers
- E 1.99:geap-25163-4
geap-25163-4 - Subject(s)
- Other Subject(s)
- 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
- Note
- Published through SciTech Connect.
03/01/1981.
"geap-25163-4"
"DE81026958"
Rosenbaum, H.S.
Commonwealth Research Corp., Chicago, IL (USA) - Funding Information
- AC02-77ET34001
View MARC record | catkey: 14373001