Transient feedback from fuel motion in metal IFR (Integral Fast Reactor) fuel

Conference · Mon Jan 01 00:00:00 EST 1990

OSTI ID:6817951

Rhodes, E A; Stanford, G S; Regis, J P; Bauer, T H; Dickerman, C E

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; TRN: 90-020014
• Resource Relation: Conference: International topical meeting on fast reactor safety, Snowbird, UT (USA), 12-16 Aug 1990
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
IFR REACTOR
TRANSIENT OVERPOWER ACCIDENTS
BURNUP
CLADDING
ELONGATION
FAILURE MODE ANALYSIS
FEEDBACK
FFTF REACTOR
FUEL ELEMENTS
HODOSCOPES
IMAGES
IRRADIATION
POWER DENSITY
REACTIVITY
REACTOR SHUTDOWN
RISK ASSESSMENT
SIMULATION
TRANSIENTS
TREAT REACTOR
TWO-DIMENSIONAL CALCULATIONS
ACCIDENTS
AIR COOLED REACTORS
DEPOSITION
ENRICHED URANIUM REACTORS
EPITHERMAL REACTORS
EXPERIMENTAL REACTORS
FAST REACTORS
GAS COOLED REACTORS
GRAPHITE MODERATED REACTORS
HOMOGENEOUS REACTORS
LIQUID METAL COOLED REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
SHUTDOWNS
SODIUM COOLED REACTORS
SOLID HOMOGENEOUS REACTORS
SURFACE COATING
SYSTEM FAILURE ANALYSIS
SYSTEMS ANALYSIS
TEST REACTORS
THERMAL REACTORS
ZERO POWER REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
220600 - Nuclear Reactor Technology- Research
Test & Experimental Reactors
050700 - Nuclear Fuels- Fuels Production & Properties