Pre-test evaluation of LLTR Series II Test A-6. [Large Leak Test Facility]
Purpose of this report is to present pre-test predictions of pressure histories for the A6 test to be conducted in the Large Leak Test Facility (LLTF) at the Energy Technology Engineering Center. A6 is part of a test program being conducted to evaluate the effects of leaks produced by a double-ended guillotine rupture of a single tube. A6 will provide data on the CRBR prototypical double rupture disc performance.
- Research Organization:
- General Electric Co., Sunnyvale, CA (USA). Advanced Reactor Systems Dept.
- DOE Contract Number:
- AT03-76SF70030
- OSTI ID:
- 5832596
- Report Number(s):
- DOE/SF/70030-T36; ON: DE81026726; TRN: 82-000544
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
CLINCH RIVER BREEDER REACTOR
LEAKS
RELIEF VALVES
PERFORMANCE TESTING
LMFBR TYPE REACTORS
MOLTEN METAL-WATER REACTIONS
PRESSURIZING
SODIUM
ALKALI METALS
BREEDER REACTORS
CONTROL EQUIPMENT
ELEMENTS
EPITHERMAL REACTORS
EQUIPMENT
FAST REACTORS
FBR TYPE REACTORS
FLOW REGULATORS
LIQUID METAL COOLED REACTORS
METALS
POWER REACTORS
REACTORS
SODIUM COOLED REACTORS
TESTING
VALVES
220900* - Nuclear Reactor Technology- Reactor Safety
210500 - Power Reactors
Breeding
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
CLINCH RIVER BREEDER REACTOR
LEAKS
RELIEF VALVES
PERFORMANCE TESTING
LMFBR TYPE REACTORS
MOLTEN METAL-WATER REACTIONS
PRESSURIZING
SODIUM
ALKALI METALS
BREEDER REACTORS
CONTROL EQUIPMENT
ELEMENTS
EPITHERMAL REACTORS
EQUIPMENT
FAST REACTORS
FBR TYPE REACTORS
FLOW REGULATORS
LIQUID METAL COOLED REACTORS
METALS
POWER REACTORS
REACTORS
SODIUM COOLED REACTORS
TESTING
VALVES
220900* - Nuclear Reactor Technology- Reactor Safety
210500 - Power Reactors
Breeding