Results from the PFR/TREAT Test LO3. [LMFBR]
TREAT experiment LO3 is a multi-pin transient over-power test in the current PFR/TREAT program. The objectives of the test were to simulate reactor conditions expected in a slow transient overpower accident in an LMFBR, and to study the resulting post-failure fuel motion. In this accident, clad failure was expected to be through internal pressurization of the fuel pin before coolant boiling had been initiated. The fuel sample consisted of seven pins, with an active fuel column 91 cm long, pre-irradiated in PFR to about 4 a/o burn-up. The test was conducted in a Mk-III integral loop with flowing sodium as the coolant. The coolant flowrate of 5.4 m/s was chosen to give a prototypical coolant temperature increase across the fuel bundle. The TREAT power transient was designed to be as slow as possible within the constraint of failing the fuel cladding at or before peak power, and within the reactivity limits of TREAT.
- Research Organization:
- Argonne National Lab., IL (USA)
- DOE Contract Number:
- W-31-109-ENG-38
- OSTI ID:
- 5866962
- Report Number(s):
- CONF-831047-32; ON: DE83014576
- Resource Relation:
- Conference: American Nuclear Society winter meeting, San Francisco, CA, USA, 30 Oct 1983
- Country of Publication:
- United States
- Language:
- English
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FUEL ELEMENT FAILURE
LMFBR TYPE REACTORS
TRANSIENT OVERPOWER ACCIDENTS
FLOW RATE
FUEL CANS
FUEL PINS
IN PILE LOOPS
REACTOR SAFETY
TREAT REACTOR
ACCIDENTS
AIR COOLED REACTORS
BREEDER REACTORS
ENRICHED URANIUM REACTORS
EPITHERMAL REACTORS
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FAST REACTORS
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FUEL ELEMENTS
GAS COOLED REACTORS
GRAPHITE MODERATED REACTORS
HOMOGENEOUS REACTORS
LIQUID METAL COOLED REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR EXPERIMENTAL FACILITIES
REACTORS
RESEARCH AND TEST REACTORS
SAFETY
SOLID HOMOGENEOUS REACTORS
TEST REACTORS
THERMAL REACTORS
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