Posttest REALP4 analysis of LOFT experiment L1-3A
This report presents selected results of posttest RELAP4 modeling of LOFT loss-of-coolant experiment L1-3A, a double-ended isothermal cold leg break with lower plenum emergency core coolant injection. Comparisons are presented between the pretest prediction, the posttest analysis, and the experimental data. It is concluded that pressurizer modeling is important for accurately predicting system behavior during the initial portion of saturated blowdown. Using measured initial conditions rather than nominal specified initial conditions did not influence the system model results significantly. Using finer nodalization in the reactor vessel improved the prediction of the system pressure history by minimizing steam condensation effects. Unequal steam condensation between the downcomer and core volumes appear to cause the manometer oscillations observed in both the pretest and posttest RELAP4 analysis.
- Research Organization:
- SEE CODE- 9502158 EG and G Idaho, Inc., Idaho Falls (USA). Idaho National Engineering Lab.
- DOE Contract Number:
- EY-76-C-07-1570
- OSTI ID:
- 5194460
- Report Number(s):
- TREE-NUREG-1137
- Country of Publication:
- United States
- Language:
- English
Similar Records
Posttest RELAP4 analysis of LOFT experiment L1-4
Experimental data report for LOFT nonnuclear test L1-3A
Preliminary posttest analysis of LOFT loss-of-coolant experiment L2-2
Technical Report
·
Mon Oct 31 23:00:00 EST 1977
·
OSTI ID:5288041
Experimental data report for LOFT nonnuclear test L1-3A
Technical Report
·
Tue Nov 30 23:00:00 EST 1976
·
OSTI ID:7225027
Preliminary posttest analysis of LOFT loss-of-coolant experiment L2-2
Technical Report
·
Fri Jun 01 00:00:00 EDT 1979
·
OSTI ID:6200503
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
BLOWDOWN
COMPUTER CODES
ENERGY TRANSFER
HEAT TRANSFER
HYDRAULICS
LOFT REACTOR
LOSS OF COOLANT
MATHEMATICAL MODELS
PRESSURIZERS
PWR TYPE REACTORS
R CODES
REACTOR ACCIDENTS
REACTORS
RESEARCH AND TEST REACTORS
TANK TYPE REACTORS
TEST REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
BLOWDOWN
COMPUTER CODES
ENERGY TRANSFER
HEAT TRANSFER
HYDRAULICS
LOFT REACTOR
LOSS OF COOLANT
MATHEMATICAL MODELS
PRESSURIZERS
PWR TYPE REACTORS
R CODES
REACTOR ACCIDENTS
REACTORS
RESEARCH AND TEST REACTORS
TANK TYPE REACTORS
TEST REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS