W-1 SLSF experiment. [LMFBR]
Conference
·
OSTI ID:6052676
The Sodium Loop Safety Facility (SLSF) is a doubly-contained, closed sodium loop designed to test full length fast breeder reactor (FBR) fuel pins under simulated hypothetical fast reactor accident conditions. The W-1 experiment has two distinct and separate objectives. The primary objective is to evaluate fuel pin heat release characteristics during loss-of-piping integrity (LOPI) accident flow and power conditions. The Clinch River Breeder Reactor (CRBR) conditions during this accident are being used as representative of FBR's. A progression of four LOPI tests will be conducted to collect data at different fuel pin conditions. These four tests will be performed on fuel pins with (a) fresh, unrestructured fuel, (b) fresh, restructured fuel, (c) irradiated, uncracked fuel (after steady-state irradiation), and (d) irradiated, cracked fuel (after shutdown and startup). The second objective of the W-1 experiment is to determine stable boiling and recovery limits (boiling window) as a function of fuel pin power.
- Research Organization:
- Hanford Engineering Development Lab., Richland, WA (USA)
- DOE Contract Number:
- EY-76-C-14-2170
- OSTI ID:
- 6052676
- Report Number(s):
- HEDL-SA-1688; CONF-781144-18
- Country of Publication:
- United States
- Language:
- English
Similar Records
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W-1 Sodium Loop Safety Facility experiment centerline fuel thermocouple performance. [LMFBR]
Conference
·
Wed Dec 31 23:00:00 EST 1980
·
OSTI ID:6265272
HEDL W-1 SLSF experiment LOPI transient and boiling test results. [LMFBR]
Conference
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Mon Dec 31 23:00:00 EST 1979
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OSTI ID:5260731
W-1 Sodium Loop Safety Facility experiment centerline fuel thermocouple performance. [LMFBR]
Conference
·
Thu May 01 00:00:00 EDT 1980
·
OSTI ID:5284617
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210500 -- Power Reactors
Breeding
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
BOILING
BREEDER REACTORS
ENERGY TRANSFER
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FLUID MECHANICS
FUEL ELEMENTS
FUEL PINS
HEAT TRANSFER
HYDRAULICS
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
LOSS OF COOLANT
MECHANICS
PHASE TRANSFORMATIONS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR SAFETY
REACTOR SAFETY EXPERIMENTS
REACTORS
SAFETY
TEMPERATURE GRADIENTS
TEST FACILITIES
210500 -- Power Reactors
Breeding
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
BOILING
BREEDER REACTORS
ENERGY TRANSFER
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FLUID MECHANICS
FUEL ELEMENTS
FUEL PINS
HEAT TRANSFER
HYDRAULICS
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
LOSS OF COOLANT
MECHANICS
PHASE TRANSFORMATIONS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR SAFETY
REACTOR SAFETY EXPERIMENTS
REACTORS
SAFETY
TEMPERATURE GRADIENTS
TEST FACILITIES