Improving fuel-rod performance. [PWR; BWR]
Journal Article
·
· EPRI J.; (United States)
OSTI ID:6134338
To reduce the risk of fuel-rod failures, utilities operate their nuclear reactors within conservative limits on power increases proposed by nuclear-fuel vendors. Of particular concern to US utilities is that adopting these limits results in an industrywide average plant capacity loss of 3% in BWR designs and 0.3% in PWR designs. To replace lost BWR capacity by other generating means currently costs the utilities $150 million annually, and losses for PWRs are about $20 million. Efforts are therefore being made to identify the factors responsible for Zircaloy degradation under PCI condition and to improve nuclear-fuel-rod design and reactor operation.
- OSTI ID:
- 6134338
- Journal Information:
- EPRI J.; (United States), Journal Name: EPRI J.; (United States) Vol. 6:2; ISSN EPRJD
- Country of Publication:
- United States
- Language:
- English
Similar Records
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Experience in PWR and BWR mixed-oxide fuel management
Fuel rod failure as a consequence of departure from nucleate boiling or dryout. [PWR; BWR]
Conference
·
Thu Dec 31 23:00:00 EST 1987
· Trans. Am. Nucl. Soc.; (United States)
·
OSTI ID:6172655
Experience in PWR and BWR mixed-oxide fuel management
Journal Article
·
Wed Mar 31 23:00:00 EST 1993
· Nuclear Technology; (United States)
·
OSTI ID:6802906
Fuel rod failure as a consequence of departure from nucleate boiling or dryout. [PWR; BWR]
Technical Report
·
Fri Jun 01 00:00:00 EDT 1979
·
OSTI ID:5855304
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210100* -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
36 MATERIALS SCIENCE
360106 -- Metals & Alloys-- Radiation Effects
ACCIDENTS
ACTINIDE COMPOUNDS
ALLOYS
BURNUP
BWR TYPE REACTORS
CHALCOGENIDES
FISSION PRODUCT RELEASE
FUEL CANS
FUEL ELEMENT FAILURE
FUEL ELEMENTS
FUEL RODS
FUEL-CLADDING INTERACTIONS
OXIDES
OXYGEN COMPOUNDS
PERFORMANCE TESTING
PHYSICAL RADIATION EFFECTS
PWR TYPE REACTORS
RADIATION EFFECTS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTORS
TESTING
TIN ALLOYS
URANIUM COMPOUNDS
URANIUM DIOXIDE
URANIUM OXIDES
WATER COOLED REACTORS
WATER MODERATED REACTORS
ZIRCALOY
ZIRCONIUM ALLOYS
ZIRCONIUM BASE ALLOYS
210100* -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
36 MATERIALS SCIENCE
360106 -- Metals & Alloys-- Radiation Effects
ACCIDENTS
ACTINIDE COMPOUNDS
ALLOYS
BURNUP
BWR TYPE REACTORS
CHALCOGENIDES
FISSION PRODUCT RELEASE
FUEL CANS
FUEL ELEMENT FAILURE
FUEL ELEMENTS
FUEL RODS
FUEL-CLADDING INTERACTIONS
OXIDES
OXYGEN COMPOUNDS
PERFORMANCE TESTING
PHYSICAL RADIATION EFFECTS
PWR TYPE REACTORS
RADIATION EFFECTS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTORS
TESTING
TIN ALLOYS
URANIUM COMPOUNDS
URANIUM DIOXIDE
URANIUM OXIDES
WATER COOLED REACTORS
WATER MODERATED REACTORS
ZIRCALOY
ZIRCONIUM ALLOYS
ZIRCONIUM BASE ALLOYS