Transient feedback from fuel motion in metal IFR (Integral Fast Reactor) fuel
Conference
·
OSTI ID:6817951
Results from hodoscope data analyses are presented for TREAT transient-overpower tests M5 through M7 with emphasis on transient feedback mechanisms, including prefailure expansion at the tops of the fuel pins, subsequent dispersive axial fuel motion, and losses in relative worth of the fuel pins during the tests. Tests M5 and M6 were the first TOP tests of margin to cladding branch and prefailure elongation of D9-clad ternary (U-Pu-Zr) IFR-type fuel. Test M7 extended these results to high-burnup fuel and also initiated transient testing of HT9-clad binary (U-Zr) FFTF-driver fuel. Results show significant prefailure negative reactivity feedback and strongly negative feedback from fuel driven to failure. 4 refs., 6 figs.
- Research Organization:
- Argonne National Lab., IL (USA)
- Sponsoring Organization:
- DOE/NE
- DOE Contract Number:
- W-31109-ENG-38
- OSTI ID:
- 6817951
- Report Number(s):
- CONF-900804-5; ON: DE90010136
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
050700 -- Nuclear Fuels-- Fuels Production & Properties
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ACCIDENTS
AIR COOLED REACTORS
BURNUP
CLADDING
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ELONGATION
ENRICHED URANIUM REACTORS
EPITHERMAL REACTORS
EXPERIMENTAL REACTORS
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FUEL ELEMENTS
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GRAPHITE MODERATED REACTORS
HODOSCOPES
HOMOGENEOUS REACTORS
IFR REACTOR
IMAGES
IRRADIATION
LIQUID METAL COOLED REACTORS
POWER DENSITY
REACTIVITY
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR SHUTDOWN
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RESEARCH AND TEST REACTORS
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RISK ASSESSMENT
SHUTDOWNS
SIMULATION
SODIUM COOLED REACTORS
SOLID HOMOGENEOUS REACTORS
SURFACE COATING
SYSTEM FAILURE ANALYSIS
SYSTEMS ANALYSIS
TEST REACTORS
THERMAL REACTORS
TRANSIENT OVERPOWER ACCIDENTS
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TWO-DIMENSIONAL CALCULATIONS
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11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
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220600 -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
AIR COOLED REACTORS
BURNUP
CLADDING
DEPOSITION
ELONGATION
ENRICHED URANIUM REACTORS
EPITHERMAL REACTORS
EXPERIMENTAL REACTORS
FAILURE MODE ANALYSIS
FAST REACTORS
FEEDBACK
FFTF REACTOR
FUEL ELEMENTS
GAS COOLED REACTORS
GRAPHITE MODERATED REACTORS
HODOSCOPES
HOMOGENEOUS REACTORS
IFR REACTOR
IMAGES
IRRADIATION
LIQUID METAL COOLED REACTORS
POWER DENSITY
REACTIVITY
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR SHUTDOWN
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
RISK ASSESSMENT
SHUTDOWNS
SIMULATION
SODIUM COOLED REACTORS
SOLID HOMOGENEOUS REACTORS
SURFACE COATING
SYSTEM FAILURE ANALYSIS
SYSTEMS ANALYSIS
TEST REACTORS
THERMAL REACTORS
TRANSIENT OVERPOWER ACCIDENTS
TRANSIENTS
TREAT REACTOR
TWO-DIMENSIONAL CALCULATIONS
ZERO POWER REACTORS