PCI fuel failure analysis: a report on a cooperative program undertaken by Pacific Northwest Laboratory and Chalk River Nuclear Laboratories.
- comps.
Reactor fuel failure data sets in the form of initial power (P/sub i/), final power (P/sub f/), transient increase in power (..delta..P), and burnup (Bu) were obtained for pressurized heavy water reactors (PHWRs), boiling water reactors (BWRs), and pressurized water reactors (PWRs). These data sets were evaluated and used as the basis for developing two predictive fuel failure models, a graphical concept called the PCI-OGRAM, and a nonlinear regression based model called PROFIT. The PCI-OGRAM is an extension of the FUELOGRAM developed by AECL. It is based on a critical threshold concept for stress dependent stress corrosion cracking. The PROFIT model, developed at Pacific Northwest Laboratory, is the result of applying standard statistical regression methods to the available PCI fuel failure data and an analysis of the environmental and strain rate dependent stress-strain properties of the Zircaloy cladding.
- Research Organization:
- Battelle Pacific Northwest Labs., Richland, WA (United States); Atomic Energy of Canada Ltd., Chalk River, Ontario. Chalk River Nuclear Labs.
- DOE Contract Number:
- EY-76-C-06-1830
- OSTI ID:
- 5664136
- Report Number(s):
- NUREG/CR-1163; PNL-2755; TRN: 80-003124
- Country of Publication:
- United States
- Language:
- English
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Mechanistic considerations used in the development of the probability of failure in transient increases in power (PROFIT) pellet-zircaloy cladding (thermo-mechanical-chemical) interactions (pci) fuel failure model
Pacific Northwest Laboratory Monthly Activities Report for February 1967: Division of Reactor Development and Technology Programs
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
BWR TYPE REACTORS
FUEL ELEMENT FAILURE
FUEL-CLADDING INTERACTIONS
MATHEMATICAL MODELS
PHWR TYPE REACTORS
PWR TYPE REACTORS
COMPUTER CALCULATIONS
FUEL CANS
FUEL RODS
STRESS CORROSION
STRESSES
ZIRCALOY
ACCIDENTS
ALLOYS
CHEMICAL REACTIONS
CORROSION
FUEL ELEMENTS
HEAVY WATER COOLED REACTORS
HEAVY WATER MODERATED REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTORS
TIN ALLOYS
WATER COOLED REACTORS
WATER MODERATED REACTORS
ZIRCONIUM ALLOYS
ZIRCONIUM BASE ALLOYS
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Light-Water Moderated
Boiling Water Cooled
210200 - Power Reactors
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