LOFT drag-disc turbine tansducer shroud and cover weld analysis and evaluation
The results are presented of stress analysis and evaluation of the drag-disc turbine transducer (DTT) shroud and cover welds used in the Loss-of-Fluid Test (LOFT) facility. The analysis concerns LOFT DTTs currently installed and/or planned for use in future experiments by LOFT Experimental Measurements Branch personnel. Thermal/hydraulic conditions for Experiments L1-5 and L2-4 (for all nuclear tests) were used to predict the loads experienced by the various shroud and cover welds. The results of this analysis include minimum fatigue life for all subject welds, and Applied Mechanics Branch recommendations for improving the structural integrity of critically stressed welds.
- Research Organization:
- Idaho National Engineering Lab., Idaho Falls (USA)
- DOE Contract Number:
- EY-76-C-07-1570
- OSTI ID:
- 6494388
- Report Number(s):
- LTR-141-80
- Country of Publication:
- United States
- Language:
- English
Similar Records
LOFT drag-disc turbine transducer shroud and cover weld
Fluid loads on LOFT DTT shrouds located in reactor vessel downcomer and DTT thermal loads during nuclear LOCE
Design and performance of the drag-disc turbine transducer
Technical Report
·
Sun Nov 26 23:00:00 EST 1978
·
OSTI ID:6348556
Fluid loads on LOFT DTT shrouds located in reactor vessel downcomer and DTT thermal loads during nuclear LOCE
Technical Report
·
Tue May 02 00:00:00 EDT 1978
·
OSTI ID:6741581
Design and performance of the drag-disc turbine transducer
Conference
·
Sun Dec 31 23:00:00 EST 1978
·
OSTI ID:6237784
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
220600* -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
ACCIDENTS
CONFIGURATION
ENGINEERED SAFETY SYSTEMS
FATIGUE
FLUID MECHANICS
HYDRAULICS
JOINTS
LOFT REACTOR
LOSS OF COOLANT
MECHANICAL PROPERTIES
MECHANICS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTORS
RESEARCH AND TEST REACTORS
STRESS ANALYSIS
STRESSES
TANK TYPE REACTORS
TEMPERATURE GRADIENTS
TEST FACILITIES
TEST REACTORS
THERMAL STRESSES
TURBINES
TURBOMACHINERY
WATER COOLED REACTORS
WATER MODERATED REACTORS
WELDED JOINTS
220600* -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
ACCIDENTS
CONFIGURATION
ENGINEERED SAFETY SYSTEMS
FATIGUE
FLUID MECHANICS
HYDRAULICS
JOINTS
LOFT REACTOR
LOSS OF COOLANT
MECHANICAL PROPERTIES
MECHANICS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTORS
RESEARCH AND TEST REACTORS
STRESS ANALYSIS
STRESSES
TANK TYPE REACTORS
TEMPERATURE GRADIENTS
TEST FACILITIES
TEST REACTORS
THERMAL STRESSES
TURBINES
TURBOMACHINERY
WATER COOLED REACTORS
WATER MODERATED REACTORS
WELDED JOINTS