Demonstration of fuel resistant to pellet-cladding interaction. Phase 2. First semiannual report, January-June 1979. [BWR]

Technical Report · Wed Aug 01 04:00:00 EDT 1979

DOI:https://doi.org/10.2172/5847691· OSTI ID:5847691

Rosenbaum, H. S. ^[1]

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1. 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 are being developed for possible demonstration within this program: (a) Cu-barrier fuel and (b) Zr-liner fuel. These advanced fuels (known collectively as barrier fuels) have special fuel cladding designed to protect the Zircaloy cladding tube from the harmful effects of localized stress and reactive fission products during reactor service. This is the first semiannual progress report for Phase 2 of this program (January-June 1979). Progress in the irradiation testing of barrier fuel and of unfueled barrier cladding specimens is reported.

• Research Organization: General Electric Co., San Jose, CA (USA). Nuclear Energy Engineering Div.
• DOE Contract Number: EN-77-C-02-4473
• OSTI ID: 5847691
• Report Number(s): GEAP-25163-1
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210100* -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
BWR TYPE REACTORS
FUEL ASSEMBLIES
FUEL CANS
FUEL ELEMENTS
FUEL RODS
FUEL-CLADDING INTERACTIONS
PERFORMANCE TESTING
REACTOR COMPONENTS
REACTORS
RESEARCH PROGRAMS
TESTING
WATER COOLED REACTORS
WATER MODERATED REACTORS