RELAP5 modeling of the Westinghouse model D4 steam generator

Journal Article · Mon Feb 01 00:00:00 EST 1993 · Nuclear Technology; (United States)

OSTI ID:6741108

Mavko, B; Petelin, S; Gortnar, O ^[1]

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1. Univ. of Ljubljana (Slovenia)

The steam generator is one of the most important components of a pressurized water reactor (PWR) nuclear power plant. Thus, the ability to model and predict the steam generator steady-state and transient thermal-hydraulic behavior is a prerequisite for performing safety analyses of PWR systems. A RELAP5 model of the Westinghouse D4 steam generator with a 70/30 split feedwater system has been developed, and it is tested by simulating five secondary-side-initiated transients. This study of primary-to-secondary heat transfer and the secondary coolant vaporization process has enabled the primary coolant cooldown to be maximized, as required for performing a conservative steamline break analysis. These tests were realized using the RELAP5/MOD2.36.05 and RELAP5/MOD3.5M5 computer codes.

• OSTI ID: 6741108
• Journal Information: Nuclear Technology; (United States), Vol. 101:2; ISSN 0029-5450
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
PWR TYPE REACTORS
REACTOR SAFETY
STEAM GENERATORS
R CODES
EVAPORATION
HEAT TRANSFER
NUCLEAR POWER PLANTS
PRIMARY COOLANT CIRCUITS
SECONDARY COOLANT CIRCUITS
STEADY-STATE CONDITIONS
TRANSIENTS
BOILERS
COMPUTER CODES
COOLING SYSTEMS
ENERGY TRANSFER
ENRICHED URANIUM REACTORS
NUCLEAR FACILITIES
PHASE TRANSFORMATIONS
POWER PLANTS
POWER REACTORS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTORS
SAFETY
THERMAL POWER PLANTS
THERMAL REACTORS
VAPOR GENERATORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210200 - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled