LOFT small break RELAP4 model. [PWR]
Technical Report
·
OSTI ID:5853334
The purpose of this report is to present the RELAP4/MOD6 model developed to study small break transient tests in LOFT. This 19 volume model was based directly on the more detailed 53 node and 29 node models currently in use. Comparisons between LOFT model predictions and data taken from Semiscale Test S-02-6 were completed to show that the model adequately handles small break hydraulic phenomena. A communicative break model based on this small break model was developed and a comparison was made between the two. While the communicative break calculations showed a slower transient, the phenomena seen were basically identical. Therefore, a plant modification to LOFT was not recommended.
- Research Organization:
- Idaho National Engineering Lab., Idaho Falls (USA)
- DOE Contract Number:
- EY-76-C-07-1570
- OSTI ID:
- 5853334
- Report Number(s):
- LTR-20-102
- Country of Publication:
- United States
- Language:
- English
Similar Records
Comparisons of RELAP4/MOD6 to LOFT and semiscale isothermal data. [PWR]
Experiment predictions of LOFT reflood behavior using the RELAP4/MOD6 code. [PWR]
RELAP4/MOD6 prediction comparisons with LOFT LOCE L2-3 data. [PWR]
Technical Report
·
Tue Oct 31 23:00:00 EST 1978
·
OSTI ID:6354265
Experiment predictions of LOFT reflood behavior using the RELAP4/MOD6 code. [PWR]
Conference
·
Mon Oct 16 00:00:00 EDT 1978
·
OSTI ID:6494162
RELAP4/MOD6 prediction comparisons with LOFT LOCE L2-3 data. [PWR]
Technical Report
·
Wed Aug 01 00:00:00 EDT 1979
·
OSTI ID:6024448
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
COMPUTER CALCULATIONS
ENERGY TRANSFER
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
LOFT REACTOR
LOSS OF COOLANT
MATHEMATICAL MODELS
MECHANICS
PRESSURE GRADIENTS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR SAFETY
REACTORS
RESEARCH AND TEST REACTORS
SAFETY
SIMULATION
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
COMPUTER CALCULATIONS
ENERGY TRANSFER
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
LOFT REACTOR
LOSS OF COOLANT
MATHEMATICAL MODELS
MECHANICS
PRESSURE GRADIENTS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR SAFETY
REACTORS
RESEARCH AND TEST REACTORS
SAFETY
SIMULATION
TANK TYPE REACTORS
TEST REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS