Analytical model for transient gas flow in nuclear fuel rods. [BWR; PWR]
Conference
·
· Trans. Am. Nucl. Soc.; (United States)
OSTI ID:5899098
- Rowe and Association, Bellevue, WA
None
- OSTI ID:
- 5899098
- Report Number(s):
- CONF-790602-(Summ.)
- Conference Information:
- Journal Name: Trans. Am. Nucl. Soc.; (United States) Journal Volume: 32
- Country of Publication:
- United States
- Language:
- English
Similar Records
Analytical modeling of transient two-phase flow. [PWR; BWR]
Analytical model for transient gas flow in nuclear fuel rods. [PWR; BWR]
Dealing with uncertainty in fuel-rod modeling. [BWR; PWR]
Conference
·
Fri Jun 01 00:00:00 EDT 1979
· Trans. Am. Nucl. Soc.; (United States)
·
OSTI ID:5686928
Analytical model for transient gas flow in nuclear fuel rods. [PWR; BWR]
Journal Article
·
Sat Aug 01 00:00:00 EDT 1981
· Nucl. Technol.; (United States)
·
OSTI ID:5329164
Dealing with uncertainty in fuel-rod modeling. [BWR; PWR]
Conference
·
Sun Oct 31 23:00:00 EST 1976
· Trans. Am. Nucl. Soc.; (United States)
·
OSTI ID:7341644
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210100 -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 -- Power Reactors
Nonbreeding
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Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
ALLOYS
BWR TYPE REACTORS
COMPUTER CALCULATIONS
CREEP
DEFORMATION
FUEL CANS
FUEL ELEMENT FAILURE
FUEL ELEMENTS
FUEL RODS
MECHANICAL PROPERTIES
PRESSURE GRADIENTS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR SAFETY
REACTORS
SAFETY
TIN ALLOYS
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
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
ALLOYS
BWR TYPE REACTORS
COMPUTER CALCULATIONS
CREEP
DEFORMATION
FUEL CANS
FUEL ELEMENT FAILURE
FUEL ELEMENTS
FUEL RODS
MECHANICAL PROPERTIES
PRESSURE GRADIENTS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR SAFETY
REACTORS
SAFETY
TIN ALLOYS
WATER COOLED REACTORS
WATER MODERATED REACTORS
ZIRCALOY
ZIRCONIUM ALLOYS
ZIRCONIUM BASE ALLOYS