Thermal-hydraulic analysis of annular fuel pins in a low-power-density PWR

Conference · Sun Jan 01 00:00:00 EST 1984 · Trans. Am. Nucl. Soc.; (United States)

OSTI ID:6077757

Carey, C; Anghaie, S; Dugan, E T

• Research Organization: University of Florida Gainesville, FL 32611
• OSTI ID: 6077757
• Report Number(s): CONF-841105-
• Journal Information: Trans. Am. Nucl. Soc.; (United States), Vol. 47; Conference: Joint meeting of the American Nuclear Society and the Atomic Industrial Forum, Washington, DC, USA, 11 Nov 1984
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
FUEL PINS
HYDRAULICS
THERMODYNAMICS
PWR TYPE REACTORS
LOSS OF COOLANT
POWER DENSITY
REACTOR CORES
REACTOR FUELING
REACTOR SAFETY
STEADY-STATE CONDITIONS
ACCIDENTS
FLUID MECHANICS
FUEL ELEMENTS
MECHANICS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTORS
SAFETY
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210200 - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled