Comparison study of the Westinghouse model E steam generator using RELAP5/MOD2 and RETRAN-02

Conference · Thu Jan 01 00:00:00 EST 1987 · Trans. Am. Nucl. Soc.; (United States)

OSTI ID:6942619

Blanchat, T K; Hassan, Y A

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-; TRN: 88-033606
• Journal Information: Trans. Am. Nucl. Soc.; (United States), Vol. 55; Conference: American Nuclear Society winter meeting, Los Angeles, CA, USA, 15 Nov 1987
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
STEAM GENERATORS
HEAT TRANSFER
HYDRAULICS
R CODES
WESTINGHOUSE STANDARD REACTOR
REACTOR SAFETY
LOSS OF COOLANT
PRIMARY COOLANT CIRCUITS
SECONDARY COOLANT CIRCUITS
TIME DEPENDENCE
ACCIDENTS
BOILERS
COMPUTER CODES
COOLING SYSTEMS
ENERGY SYSTEMS
ENERGY TRANSFER
FLUID MECHANICS
MECHANICS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTORS
SAFETY
VAPOR GENERATORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210200 - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled