TRAC-PF1/MOD-1 analysis of Loss-Of-Flow Test L9-4
Los Alamos National Laboratory is developing the Transient Reactor Analysis Code (TRAC) to provide advanced best-estimate predictions of postulated accidents in pressurized water reactors (PWRs) and for many thermal-hydraulic experimental facilities. As part of our independent assessment of code version TRAC-PF1/MOD1, we analyzed Loss-of-Fluid Test (LOFT) L9-4 and compared the test data to the calculated results. This was an anticipated-transient-without-scram test in which the pumps were tripped, the steam generator main feedwater discontinued, and the main steam-outlet valve closed. This data comparison is the first extensive test of TRAC's reactor-kinetics models. The comparisons show that TRAC can calculate the power generation within a nuclear reactor if the program is supplied with adequate reactor-kinetics input specifications. The data comparisons also indicate that TRAC calculated the thermal-hydraulic parameters within LOFT well with only minor discrepancies. A number of models within TRAC-PF1/MOD1 were verified for the first time. They include the reactor-kinetics models, the trip-activated time-step controls, and the LOFT pump-coastdown calculations. In general, the final input description is adequate to analyze the experiment. The calculations indicate the importance and difficulty of obtaining accurate and applicable reactor-kinetics input data. They also indicate the need to include the effects of xenon-poisoning buildup in the analysis.
- Research Organization:
- Los Alamos National Laboratory (LANL), Los Alamos, NM (United States)
- DOE Contract Number:
- W-7405-ENG-36
- OSTI ID:
- 5341544
- Report Number(s):
- LA-UR-85-945; CONF-851007-4; ON: TI85010106
- Resource Relation:
- Conference: 3. international meeting on reactor thermal hydraulics, Newport, RI, USA, 15 Oct 1985
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
LOFT REACTOR
LOSS OF FLOW
SIMULATION
PWR TYPE REACTORS
ATWS
COMPUTER CODES
T CODES
ACCIDENTS
REACTOR ACCIDENTS
REACTORS
RESEARCH AND TEST REACTORS
TANK TYPE REACTORS
TEST REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210200 - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled