Posttest RELAP4 analysis of LOFT experiment L1-4
Results of posttest analysis of LOFT loss-of-coolant experiment L1-4 with the RELAP4 code are presented. The results are compared with the pretest prediction and the test data. Differences between the RELAP4 model used for this analysis and that used for the pretest prediction are in the areas of initial conditions, nodalization, emergency core cooling system, broken loop hot leg, and steam generator secondary. In general, these changes made only minor improvement in the comparison of the analytical results to the data. Also presented are the results of a limited study of LOFT downcomer modeling which compared the performance of the conventional single downcomer model with that of the new split downcomer model. A RELAP4 sensitivity calculation with artificially elevated emergency core coolant temperature was performed to highlight the need for an ECC mixing model in RELAP4.
- Research Organization:
- EG and G Idaho, Inc., Idaho Falls, ID (United States)
- DOE Contract Number:
- EY-76-C-07-1570
- OSTI ID:
- 5288041
- Report Number(s):
- TREE-NUREG-1183; TRN: 78-002633
- Country of Publication:
- United States
- Language:
- English
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LOFT REACTOR
LOSS OF COOLANT
COMPUTER CODES
FLOW RATE
HYDRAULICS
PRESSURE GRADIENTS
SIMULATION
TEMPERATURE GRADIENTS
ACCIDENTS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTORS
RESEARCH AND TEST REACTORS
TANK TYPE REACTORS
TEST REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
220600* - Nuclear Reactor Technology- Research
Test & Experimental Reactors