Sodium Loop Safety Facility W-2 experiment fuel pin rupture detection system. [LMFBR]
Conference
·
OSTI ID:5352957
The objective of the Sodium Loop Safety Facility (SLSF) W-2 experiment is to characterize the combined effects of a preconditioned full-length fuel column and slow transient overpower (TOP) conditions on breeder reactor (BR) fuel pin cladding failures. The W-2 experiment will meet this objective by providing data in two technological areas: (1) time and location of cladding failure, and (2) early post-failure test fuel behavior. The test involves a seven pin, prototypic full-length fast test reactor (FTR) fuel pin bundle which will be subjected to a simulated unprotected 5 cents/s reactivity transient overpower event. The outer six pins will provide the necessary prototypic thermal-hydraulic environment for the center pin.
- Research Organization:
- Hanford Engineering Development Lab., Richland, WA (USA)
- DOE Contract Number:
- AC14-76FF02170
- OSTI ID:
- 5352957
- Report Number(s):
- HEDL-SA-1966-FP; CONF-800607-67
- Country of Publication:
- United States
- Language:
- English
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Fri Dec 31 23:00:00 EST 1982
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OSTI ID:5757078
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210500 -- Power Reactors
Breeding
22 GENERAL STUDIES OF NUCLEAR REACTORS
220600 -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
BREEDER REACTORS
DETECTION
ENERGY TRANSFER
EPITHERMAL REACTORS
FAILED ELEMENT DETECTION
FAILED ELEMENT MONITORS
FAST REACTORS
FBR TYPE REACTORS
FFTF REACTOR
FLUID MECHANICS
FUEL CANS
FUEL ELEMENT FAILURE
FUEL ELEMENTS
FUEL PINS
HEAT TRANSFER
HYDRAULICS
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
MECHANICS
PERFORMANCE TESTING
REACTIVITY
REACTIVITY INSERTIONS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR SAFETY
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
SAFETY
SIMULATION
SODIUM COOLED REACTORS
TEST FACILITIES
TEST REACTORS
TESTING
TRANSIENT OVERPOWER ACCIDENTS
210500 -- Power Reactors
Breeding
22 GENERAL STUDIES OF NUCLEAR REACTORS
220600 -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
BREEDER REACTORS
DETECTION
ENERGY TRANSFER
EPITHERMAL REACTORS
FAILED ELEMENT DETECTION
FAILED ELEMENT MONITORS
FAST REACTORS
FBR TYPE REACTORS
FFTF REACTOR
FLUID MECHANICS
FUEL CANS
FUEL ELEMENT FAILURE
FUEL ELEMENTS
FUEL PINS
HEAT TRANSFER
HYDRAULICS
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
MECHANICS
PERFORMANCE TESTING
REACTIVITY
REACTIVITY INSERTIONS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR SAFETY
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
SAFETY
SIMULATION
SODIUM COOLED REACTORS
TEST FACILITIES
TEST REACTORS
TESTING
TRANSIENT OVERPOWER ACCIDENTS