Comparison study of the Westinghouse model E steam generator using RELAP5/MOD2 and RETRAN-02
Conference
·
· Trans. Am. Nucl. Soc.; (United States)
OSTI ID:6942619
The response of a steam generator during both operational and transient conditions is of major importance in studying the thermal-hydraulic behavior of a nuclear reactor coolant system. The objective of this study is to predict the behavior of the secondary side of the Westinghouse Model E steam generator using the RELAP5/MOD2 computer code. Steady-state conditions and a loss-of-feedwater (LOFW) transient were predicted and compared with a previous study using the RETRAN-02 computer code. The comparison showed an agreement with the previous study for steady-state calculations.
- Research Organization:
- Texas A and M Univ., College Station (USA)
- OSTI ID:
- 6942619
- Report Number(s):
- CONF-8711195-
- Conference Information:
- Journal Name: Trans. Am. Nucl. Soc.; (United States) Journal Volume: 55
- Country of Publication:
- United States
- Language:
- English
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210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
BOILERS
COMPUTER CODES
COOLING SYSTEMS
ENERGY SYSTEMS
ENERGY TRANSFER
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
LOSS OF COOLANT
MECHANICS
PRIMARY COOLANT CIRCUITS
PWR TYPE REACTORS
R CODES
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR SAFETY
REACTORS
SAFETY
SECONDARY COOLANT CIRCUITS
STEAM GENERATORS
TIME DEPENDENCE
VAPOR GENERATORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
WESTINGHOUSE STANDARD REACTOR