Sodium Loop Safety Facility W-2 experiment fuel pin rupture detection system. [LMFBR]
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; TRN: 80-012482
- Resource Relation:
- Conference: American Nuclear Society annual meeting, Las Vegas, NV, USA, 8 Jun 1980
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
FUEL ELEMENT FAILURE
TEST FACILITIES
LMFBR TYPE REACTORS
FAILED ELEMENT DETECTION
TRANSIENT OVERPOWER ACCIDENTS
FAILED ELEMENT MONITORS
HEAT TRANSFER
HYDRAULICS
FFTF REACTOR
FUEL CANS
FUEL PINS
PERFORMANCE TESTING
REACTIVITY INSERTIONS
REACTOR SAFETY
SIMULATION
ACCIDENTS
BREEDER REACTORS
DETECTION
ENERGY TRANSFER
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FLUID MECHANICS
FUEL ELEMENTS
LIQUID METAL COOLED REACTORS
MECHANICS
REACTIVITY
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
SAFETY
SODIUM COOLED REACTORS
TEST REACTORS
TESTING
220900* - Nuclear Reactor Technology- Reactor Safety
210500 - Power Reactors
Breeding
220600 - Nuclear Reactor Technology- Research
Test & Experimental Reactors