Gas-cooled fast reactor fuel-rod grid-spacer mechanical interaction
Conference
·
· Trans. Am. Nucl. Soc.; (United States)
OSTI ID:7241081
None
- Research Organization:
- General Atomic Co., San Diego, CA
- OSTI ID:
- 7241081
- Conference Information:
- Journal Name: Trans. Am. Nucl. Soc.; (United States) Journal Volume: 24
- Country of Publication:
- United States
- Language:
- English
Similar Records
Fuel-rod grid-spacer wear and fretting in gas-cooled fast breeder reactor fuel elements
Gas-cooled fast reactor fuel rod--grid spacer mechanical interaction tests
LIFE-GCFR analysis of gas-cooled fast reactor fuel performance
Conference
·
Fri Jun 01 00:00:00 EDT 1973
· Trans. Amer. Nucl. Soc., v. 16, pp. 248-249
·
OSTI ID:4467312
Gas-cooled fast reactor fuel rod--grid spacer mechanical interaction tests
Journal Article
·
Sun Jun 01 00:00:00 EDT 1975
· Trans. Am. Nucl. Soc., v. 21, p. 393
·
OSTI ID:4215468
LIFE-GCFR analysis of gas-cooled fast reactor fuel performance
Conference
·
Wed Dec 31 23:00:00 EST 1980
· Trans. Am. Nucl. Soc.; (United States)
·
OSTI ID:5164972
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210500* -- Power Reactors
Breeding
BREEDER REACTORS
DEFORMATION
DESIGN
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FUEL ELEMENTS
FUEL RODS
GAS COOLED REACTORS
GCFR TYPE REACTORS
PERFORMANCE TESTING
REACTOR COMPONENTS
REACTOR CORES
REACTORS
SPACERS
STRESS ANALYSIS
TESTING
210500* -- Power Reactors
Breeding
BREEDER REACTORS
DEFORMATION
DESIGN
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FUEL ELEMENTS
FUEL RODS
GAS COOLED REACTORS
GCFR TYPE REACTORS
PERFORMANCE TESTING
REACTOR COMPONENTS
REACTOR CORES
REACTORS
SPACERS
STRESS ANALYSIS
TESTING