LOFT core flow study. [PWR]
Technical Report
·
OSTI ID:7321786
The results are presented of the LOFT core flow study to determine the LOFT core flow rates and coolant temperatures so that the LOFT cladding temperature response can best represent that of a typical LPWR. The time to reach CHF is recognized as an important indicator of core behavior. Therefore, computer models of the LOFT and LPWR cores were prepared to determine the time required for each core to reach CHF under different sets of thermal-hydraulic plenum conditions. It is concluded that the LOFT clad temperature response is similar to that of an LPWR when the LOFT initial hot leg fluid temperatures are near the LPWR temperatures (610/sup 0/F to 618/sup 0/F). The initial LOFT core flow rates do not effect its core response in relation to time to CHF. A delay in the time to reach CHF was observed for the LOFT fuel pin for certain core conditions caused by a rewetting of the fuel pin early in the transient. CHF was reached earliest in the LOFT core near the core midpoint while in the LPWR, the earliest CHF location was in the upper portion of the core.
- 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:
- 7321786
- Report Number(s):
- TID-27667
- Country of Publication:
- United States
- Language:
- English
Similar Records
Fuel cladding temperature predictions for LOFT LOCE Ll-5. [PWR]
Preliminary posttest analysis of LOFT loss-of-coolant experiment L2-2
Discussion of different analytical approaches to predicting rewet phenomena in loss-of-coolant experiments. RELAP4/MOD6 and TRAC-P1A predictions of LOFT Experiment L2-3. [PWR]
Conference
·
Sat Dec 31 23:00:00 EST 1977
·
OSTI ID:6607046
Preliminary posttest analysis of LOFT loss-of-coolant experiment L2-2
Technical Report
·
Fri Jun 01 00:00:00 EDT 1979
·
OSTI ID:6200503
Discussion of different analytical approaches to predicting rewet phenomena in loss-of-coolant experiments. RELAP4/MOD6 and TRAC-P1A predictions of LOFT Experiment L2-3. [PWR]
Technical Report
·
Sun Dec 31 23:00:00 EST 1978
·
OSTI ID:5837419
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
220600* -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
FLOW RATE
FLUID MECHANICS
FUEL ASSEMBLIES
FUEL CANS
HYDRAULICS
LOFT REACTOR
MECHANICS
MOCKUP
PRESSURE GRADIENTS
PWR TYPE REACTORS
REACTOR COMPONENTS
REACTOR CORES
REACTORS
RESEARCH AND TEST REACTORS
STRUCTURAL MODELS
TANK TYPE REACTORS
TEMPERATURE GRADIENTS
TEST REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
220600* -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
FLOW RATE
FLUID MECHANICS
FUEL ASSEMBLIES
FUEL CANS
HYDRAULICS
LOFT REACTOR
MECHANICS
MOCKUP
PRESSURE GRADIENTS
PWR TYPE REACTORS
REACTOR COMPONENTS
REACTOR CORES
REACTORS
RESEARCH AND TEST REACTORS
STRUCTURAL MODELS
TANK TYPE REACTORS
TEMPERATURE GRADIENTS
TEST REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS