Skip to main content
OSTI.GOVU.S. Department of Energy Office of Scientific and Technical Information
U.S. Department of Energy
Office of Scientific and Technical Information
 

Importance of early flow predictions and CHF correlation characteristics in RELAP4/MOD5 best-estimate blowdown calculations. [PWR]

Conference · · Trans. Am. Nucl. Soc.; (United States)
OSTI ID:5250019
None
Research Organization:
EG and G Idaho, Idaho Falls
OSTI ID:
5250019
Conference Information:
Journal Name: Trans. Am. Nucl. Soc.; (United States) Journal Volume: 27
Country of Publication:
United States
Language:
English

Similar Records

Predictions and analysis of the semiscale blowdown heat transfer tests with RELAP4. [PWR]
Conference · Tue Jun 01 00:00:00 EDT 1976 · Trans. Am. Nucl. Soc.; (United States) · OSTI ID:7353695
Subcooled blowdown thrust force calculation using RELAP4/REPIPE. [BWR; PWR]
Conference · Fri Jun 01 00:00:00 EDT 1979 · Trans. Am. Nucl. Soc.; (United States) · OSTI ID:5899080
Prediction of CHF in rod bundles using round-tube CHF correlation. [PWR]
Conference · Sun Dec 31 23:00:00 EST 1978 · Trans. Am. Nucl. Soc.; (United States) · OSTI ID:5317122

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
BLOWDOWN
CRITICAL HEAT FLUX
ENERGY TRANSFER
FLUID FLOW
HEAT FLUX
HEAT TRANSFER
HYDRAULICS
LIQUID FLOW
LOSS OF COOLANT
MATHEMATICAL MODELS
MOCKUP
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR SAFETY
REACTORS
SAFETY
STRUCTURAL MODELS
WATER COOLED REACTORS
WATER MODERATED REACTORS