PWR steamline break analysis assuming concurrent steam generator tube rupture

Conference · Tue Jan 01 00:00:00 EST 1980

OSTI ID:5025979

Shier, W G; Levine, M M

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.

• Research Organization: Brookhaven National Lab., Upton, NY (USA)
• DOE Contract Number: AC02-76CH00016
• OSTI ID: 5025979
• Report Number(s): BNL-NUREG-26903; CONF-801002-9; TRN: 80-017840
• Resource Relation: Conference: ANS/ASME topical meeting on reactor thermal-hydraulics, Saratoga, NY, USA, 9 Oct 1980
• 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
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