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Title: RELAP5 modeling of the Westinghouse model D4 steam generator

Abstract

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.

Authors:
; ;  [1]
  1. Univ. of Ljubljana (Slovenia)
Publication Date:
OSTI Identifier:
6741108
Resource Type:
Journal Article
Journal Name:
Nuclear Technology; (United States)
Additional Journal Information:
Journal Volume: 101:2; Journal ID: ISSN 0029-5450
Country of Publication:
United States
Language:
English
Subject:
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

Citation Formats

Mavko, B, Petelin, S, and Gortnar, O. RELAP5 modeling of the Westinghouse model D4 steam generator. United States: N. p., 1993. Web.
Mavko, B, Petelin, S, & Gortnar, O. RELAP5 modeling of the Westinghouse model D4 steam generator. United States.
Mavko, B, Petelin, S, and Gortnar, O. 1993. "RELAP5 modeling of the Westinghouse model D4 steam generator". United States.
@article{osti_6741108,
title = {RELAP5 modeling of the Westinghouse model D4 steam generator},
author = {Mavko, B and Petelin, S and Gortnar, O},
abstractNote = {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.},
doi = {},
url = {https://www.osti.gov/biblio/6741108}, journal = {Nuclear Technology; (United States)},
issn = {0029-5450},
number = ,
volume = 101:2,
place = {United States},
year = {Mon Feb 01 00:00:00 EST 1993},
month = {Mon Feb 01 00:00:00 EST 1993}
}