TRAC large-break loss-of-coolant accident analysis for the AP600 design
Conference
·
OSTI ID:10121197
This report discusses a TRAC model of the Westinghouse AP600 advanced reactor design which has been developed for analyzing large-break loss-of-coolant accident (LBLOCA) transients. A preliminary LBLOCA calculation of a 80% cold-leg break has been performed with TRAC-PF1/MOD2. The 80% break size was calculated by Westinghouse to be the most severe large-break size. The LBLOCA transient was calculated to 92 s. Peak clad temperatures (PCT) were well below the Appendix K limit of 1478 K (2200{degrees}F). Transient event times and PCT for the TRAC calculation were in reasonable agreement with those calculated by Westinghouse using their WCOBRA/TRAC code.
- Research Organization:
- Los Alamos National Lab., NM (United States)
- Sponsoring Organization:
- Nuclear Regulatory Commission, Washington, DC (United States)
- DOE Contract Number:
- W-7405-ENG-36
- OSTI ID:
- 10121197
- Report Number(s):
- LA-UR--94-121; CONF-940402--4; ON: DE94006237
- Country of Publication:
- United States
- Language:
- English
Similar Records
TRAC analysis of an 80% pump-side, cold-leg, large-break loss-of-coolant accident for the Westinghouse AP600 advanced reactor design
Updated TRAC analysis of an 80% double-ended cold-leg break for the AP600 design
AP600 large-break loss-of-collant-accident developmental assessment plan for TRAC-PF1/MOD2
Book
·
Thu Aug 01 00:00:00 EDT 1996
·
OSTI ID:271913
Updated TRAC analysis of an 80% double-ended cold-leg break for the AP600 design
Technical Report
·
Sat Jul 01 00:00:00 EDT 1995
·
OSTI ID:90222
AP600 large-break loss-of-collant-accident developmental assessment plan for TRAC-PF1/MOD2
Technical Report
·
Mon Jul 01 00:00:00 EDT 1996
·
OSTI ID:366497
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210200
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900
99 GENERAL AND MISCELLANEOUS
990200
COMPUTER CALCULATIONS
COMPUTERIZED SIMULATION
HEAT TRANSFER
HYDRAULICS
LOSS OF COOLANT
MATHEMATICS AND COMPUTERS
POWER REACTORS
NONBREEDING
LIGHT-WATER MODERATED
NONBOILING WATER COOLED
PWR TYPE REACTORS
REACTOR SAFETY
T CODES
TRANSIENTS
210200
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900
99 GENERAL AND MISCELLANEOUS
990200
COMPUTER CALCULATIONS
COMPUTERIZED SIMULATION
HEAT TRANSFER
HYDRAULICS
LOSS OF COOLANT
MATHEMATICS AND COMPUTERS
POWER REACTORS
NONBREEDING
LIGHT-WATER MODERATED
NONBOILING WATER COOLED
PWR TYPE REACTORS
REACTOR SAFETY
T CODES
TRANSIENTS