TRAC independent assessment for PWR analysis
LANL is developing the Transient Reactor Analysis Code (TRAC) for application to PWRs. Goal was to analyze large-break loss-of-coolant accidents (LOCAs), and the TRAC-P1A and TRAC-PD2 codes primarily addressed the large-break LOCA. The TRAC-PF1 code contained modifications which enhanced the computational speed of the code and improved its application to small-break LOCAs. The TRAC-PF1/MOD1 code added improved steam-generator modeling, a turbine component, and a control system together with modified constitutive relations to model the balance of plant on the secondary side and to extend the applications to non-LOCA transients. During the past year we assessed TRAC-PD2, TRAC-PF1, and TRAC-PF1/MOD1, using LOFT and Semiscale experiments.
- Research Organization:
- Los Alamos National Lab., NM (USA)
- DOE Contract Number:
- W-7405-ENG-36
- OSTI ID:
- 5517249
- Report Number(s):
- LA-UR-83-3127; CONF-8310143-20; ON: DE84001744
- Country of Publication:
- United States
- Language:
- English
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210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
COMPUTER CALCULATIONS
COMPUTER CODES
LOFT REACTOR
LOSS OF COOLANT
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR SAFETY EXPERIMENTS
REACTORS
RESEARCH AND TEST REACTORS
T CODES
TANK TYPE REACTORS
TEST REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS