Analytical modeling of fuel rod ramp experiment. [PWR]
Conference
·
· Trans. Am. Nucl. Soc.; (United States)
OSTI ID:5289415
None
- Research Organization:
- Babcock and Wilcox Co., Lynchburg, VA
- OSTI ID:
- 5289415
- Conference Information:
- Journal Name: Trans. Am. Nucl. Soc.; (United States) Journal Volume: 27
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210100* -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
COMPUTER CODES
FUEL CANS
FUEL ELEMENTS
FUEL RODS
PERFORMANCE
PWR TYPE REACTORS
REACTOR COMPONENTS
REACTORS
STRESSES
TRANSIENTS
WATER COOLED REACTORS
WATER MODERATED REACTORS
210100* -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
COMPUTER CODES
FUEL CANS
FUEL ELEMENTS
FUEL RODS
PERFORMANCE
PWR TYPE REACTORS
REACTOR COMPONENTS
REACTORS
STRESSES
TRANSIENTS
WATER COOLED REACTORS
WATER MODERATED REACTORS