Demonstration of fuel resistant to pellet-cladding interaction : phase 2, final report

Demonstration of fuel resistant to pellet-cladding interaction : phase 2, final report
Title Demonstration of fuel resistant to pellet-cladding interaction : phase 2, final report PDF eBook
Author T. C. Rowland
Publisher
Pages 0
Release 1984
Genre
ISBN

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Demonstration of Fuel Resistant to Pellet-cladding Interaction. Phase I. Final Report

Demonstration of Fuel Resistant to Pellet-cladding Interaction. Phase I. Final Report
Title Demonstration of Fuel Resistant to Pellet-cladding Interaction. Phase I. Final Report PDF eBook
Author
Publisher
Pages
Release 1979
Genre
ISBN

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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 final report for PHASE 1 of this program. Support tests have shown that the barrier fuel resists PCI far better than does the conventional Zircaloy-clad fuel. Power ramp tests thus far have shown good PCI resistance for Cu-barrier fuel at burnup> 12 MWd/kg-U and for Zr-liner fuel> 16 MWd/kg-U. The program calls for continued testing to still higher burnup levels in PHASE 2.

Demo. of Full Resistant to Pellet-cladding Interaction Phase 1 Final Report

Demo. of Full Resistant to Pellet-cladding Interaction Phase 1 Final Report
Title Demo. of Full Resistant to Pellet-cladding Interaction Phase 1 Final Report PDF eBook
Author
Publisher
Pages
Release 1979
Genre
ISBN

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Demonstration of Fuel Resistant to Pellet-cladding Interaction

Demonstration of Fuel Resistant to Pellet-cladding Interaction
Title Demonstration of Fuel Resistant to Pellet-cladding Interaction PDF eBook
Author
Publisher
Pages
Release 1980
Genre
ISBN

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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. In the current report period the nuclear design of the demonstration was begun. The design calls for 132 bundles of barrier fuel to be inserted into the core of Quad Cities Unit 2 at the beginning of Cycle 6. Laboratory and in-reactor tests were started to evaluate the stability of Zr-liner fuel which remains in service after a defect has occurred which allows water to enter the rod. Results to date on intentionally defected fuel indicate that the Zr-liner fuel is not rapidly degraded despite ingress of water.

Energy Research Abstracts

Energy Research Abstracts
Title Energy Research Abstracts PDF eBook
Author
Publisher
Pages 388
Release 1986
Genre Power resources
ISBN

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Energy Research Abstracts

Energy Research Abstracts
Title Energy Research Abstracts PDF eBook
Author
Publisher
Pages 600
Release 1984-03
Genre Power resources
ISBN

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Demonstration of Fuel Resistant to Pellet-cladding Interaction. Phase 2. First Semiannual Report, January-June 1979. [BWR].

Demonstration of Fuel Resistant to Pellet-cladding Interaction. Phase 2. First Semiannual Report, January-June 1979. [BWR].
Title Demonstration of Fuel Resistant to Pellet-cladding Interaction. Phase 2. First Semiannual Report, January-June 1979. [BWR]. PDF eBook
Author
Publisher
Pages
Release 1979
Genre
ISBN

Download Demonstration of Fuel Resistant to Pellet-cladding Interaction. Phase 2. First Semiannual Report, January-June 1979. [BWR]. Book in PDF, Epub and Kindle

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.