skip to main content
OSTI.GOV title logo U.S. Department of Energy
Office of Scientific and Technical Information

Title: PWR steamline break analysis assuming concurrent steam generator tube rupture

Abstract

Results are presented for a steamline break analysis for a typical, two-loop, 2560 MW(t) pressurized water reactor. The calculations were performed using the IRT reactor system transient analysis code. Included are the analyses of steamline break transients assuming concurrent steam generator tube rupture (up to 30 steam generator tubes). Graphical and tabular results are presented.

Authors:
;
Publication Date:
Research Org.:
Brookhaven National Lab., Upton, NY (USA)
OSTI Identifier:
5025979
Report Number(s):
BNL-NUREG-26903; CONF-801002-9
TRN: 80-017840
DOE Contract Number:  
AC02-76CH00016
Resource Type:
Conference
Resource Relation:
Conference: ANS/ASME topical meeting on reactor thermal-hydraulics, Saratoga, NY, USA, 9 Oct 1980
Country of Publication:
United States
Language:
English
Subject:
22 GENERAL STUDIES OF NUCLEAR REACTORS; 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; PWR TYPE REACTORS; TRANSIENTS; RUPTURES; STEAM GENERATORS; STEAM LINES; THEORETICAL DATA; BOILERS; DATA; FAILURES; INFORMATION; NUMERICAL DATA; 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

Shier, W G, and Levine, M M. PWR steamline break analysis assuming concurrent steam generator tube rupture. United States: N. p., 1980. Web.
Shier, W G, & Levine, M M. PWR steamline break analysis assuming concurrent steam generator tube rupture. United States.
Shier, W G, and Levine, M M. Tue . "PWR steamline break analysis assuming concurrent steam generator tube rupture". United States. https://www.osti.gov/servlets/purl/5025979.
@article{osti_5025979,
title = {PWR steamline break analysis assuming concurrent steam generator tube rupture},
author = {Shier, W G and Levine, M M},
abstractNote = {Results are presented for a steamline break analysis for a typical, two-loop, 2560 MW(t) pressurized water reactor. The calculations were performed using the IRT reactor system transient analysis code. Included are the analyses of steamline break transients assuming concurrent steam generator tube rupture (up to 30 steam generator tubes). Graphical and tabular results are presented.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {1980},
month = {1}
}

Conference:
Other availability
Please see Document Availability for additional information on obtaining the full-text document. Library patrons may search WorldCat to identify libraries that hold this conference proceeding.

Save / Share: