Posttest calculation of the PBF LOC-11B and LOC-11C experiments using RELAP4/MOD6. [PWR]
Technical Report
·
OSTI ID:6515484
Comparisons between RELAP4/MOD6, Update 4 code-calculated and measured experimental data are presented for the PBF LOC-11C and LOC-11B experiments. Independent code verification techniques are now being developed and this study represents a preliminary effort applying structured criteria for developing computer models, selecting code input, and performing base-run analyses. Where deficiencies are indicated in the base-case representation of the experiment, methods of code and criteria improvement are developed and appropriate recommendations are made.
- Research Organization:
- Idaho National Engineering Lab., Idaho Falls (USA)
- DOE Contract Number:
- EY-76-C-07-1570
- OSTI ID:
- 6515484
- Report Number(s):
- CVAP-TR-78-016; TRN: 79-002865
- Country of Publication:
- United States
- Language:
- English
Similar Records
Experiment data report for PBF-LOCA tests LOC-11B and 11C. [PWR]
Heat transfer considerations for PBF first nuclear blowdown. [PWR]
Gravity-feed reflood data comparisons using RELAP4/MOD6, Update 3. [PWR]
Technical Report
·
Sun Oct 01 00:00:00 EDT 1978
·
OSTI ID:6515484
Heat transfer considerations for PBF first nuclear blowdown. [PWR]
Conference
·
Sun Jan 01 00:00:00 EST 1978
·
OSTI ID:6515484
Gravity-feed reflood data comparisons using RELAP4/MOD6, Update 3. [PWR]
Technical Report
·
Mon May 01 00:00:00 EDT 1978
·
OSTI ID:6515484
Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
LOSS OF COOLANT
HEAT TRANSFER
HYDRAULICS
PWR TYPE REACTORS
COMPARATIVE EVALUATIONS
FLOW RATE
MATHEMATICAL MODELS
PRESSURE GRADIENTS
REACTOR SAFETY
TEMPERATURE GRADIENTS
ACCIDENTS
ENERGY TRANSFER
FLUID MECHANICS
MECHANICS
REACTOR ACCIDENTS
REACTORS
SAFETY
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210200 - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
LOSS OF COOLANT
HEAT TRANSFER
HYDRAULICS
PWR TYPE REACTORS
COMPARATIVE EVALUATIONS
FLOW RATE
MATHEMATICAL MODELS
PRESSURE GRADIENTS
REACTOR SAFETY
TEMPERATURE GRADIENTS
ACCIDENTS
ENERGY TRANSFER
FLUID MECHANICS
MECHANICS
REACTOR ACCIDENTS
REACTORS
SAFETY
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210200 - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled