Fuel motions in the multi-pin PFR/TREAT test series
Conference
·
OSTI ID:7176384
Fuel motions during the early stages of failure were determined for the seven multi-pin PFR/TREAT tests from an integrated analysis of data from the Fast Neutron Hodoscope and the loop instrumentation. It was observed that motion in TUCOP simulations is in two stages; an initial slow movement at failure followed by abrupt dispersal. It was also found that axial movement of fresh fuel begins promptly at initial failure but that pre-irradiated fuel motion is delayed by 15 ms in both TOP and TUCOP simulations.
- Research Organization:
- Argonne National Lab., IL (USA)
- Sponsoring Organization:
- DOE/NE
- DOE Contract Number:
- W-31109-ENG-38
- OSTI ID:
- 7176384
- Report Number(s):
- CONF-900804-4; ON: DE90010098; TRN: 90-019997
- Resource Relation:
- Conference: International topical meeting on fast reactor safety, Snowbird, UT (USA), 12-16 Aug 1990
- 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
LMFBR TYPE REACTORS
FUEL PINS
REACTOR ACCIDENTS
FUEL-COOLANT INTERACTIONS
COMPUTERIZED SIMULATION
HEAT TRANSFER
HODOSCOPES
HYDRAULICS
PFR REACTOR
REACTIVITY
REACTOR COOLING SYSTEMS
REACTOR SAFETY
TREAT REACTOR
ACCIDENTS
AIR COOLED REACTORS
BREEDER REACTORS
COOLING SYSTEMS
ENERGY SYSTEMS
ENERGY TRANSFER
ENRICHED URANIUM REACTORS
EPITHERMAL REACTORS
EXPERIMENTAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FLUID MECHANICS
FUEL ELEMENTS
GAS COOLED REACTORS
GRAPHITE MODERATED REACTORS
HOMOGENEOUS REACTORS
LIQUID METAL COOLED REACTORS
MECHANICS
POWER REACTORS
REACTOR COMPONENTS
REACTORS
RESEARCH AND TEST REACTORS
SAFETY
SIMULATION
SODIUM COOLED REACTORS
SOLID HOMOGENEOUS REACTORS
TEST REACTORS
THERMAL REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210500 - Power Reactors
Breeding
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
LMFBR TYPE REACTORS
FUEL PINS
REACTOR ACCIDENTS
FUEL-COOLANT INTERACTIONS
COMPUTERIZED SIMULATION
HEAT TRANSFER
HODOSCOPES
HYDRAULICS
PFR REACTOR
REACTIVITY
REACTOR COOLING SYSTEMS
REACTOR SAFETY
TREAT REACTOR
ACCIDENTS
AIR COOLED REACTORS
BREEDER REACTORS
COOLING SYSTEMS
ENERGY SYSTEMS
ENERGY TRANSFER
ENRICHED URANIUM REACTORS
EPITHERMAL REACTORS
EXPERIMENTAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FLUID MECHANICS
FUEL ELEMENTS
GAS COOLED REACTORS
GRAPHITE MODERATED REACTORS
HOMOGENEOUS REACTORS
LIQUID METAL COOLED REACTORS
MECHANICS
POWER REACTORS
REACTOR COMPONENTS
REACTORS
RESEARCH AND TEST REACTORS
SAFETY
SIMULATION
SODIUM COOLED REACTORS
SOLID HOMOGENEOUS REACTORS
TEST REACTORS
THERMAL REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210500 - Power Reactors
Breeding