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 |
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 |
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
Title | Demo. of Full Resistant to Pellet-cladding Interaction Phase 1 Final Report PDF eBook |
Author | |
Publisher | |
Pages | |
Release | 1979 |
Genre | |
ISBN |
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 |
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
Title | Energy Research Abstracts PDF eBook |
Author | |
Publisher | |
Pages | 388 |
Release | 1986 |
Genre | Power resources |
ISBN |
Energy Research Abstracts
Title | Energy Research Abstracts PDF eBook |
Author | |
Publisher | |
Pages | 600 |
Release | 1984-03 |
Genre | Power resources |
ISBN |
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 |
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.