56. june 8 cirft bevard
Transcript of 56. june 8 cirft bevard
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Nuclear Energy
CIRFT Testing of High-Burnup Used Nuclear Fuel from PWRs and BWRs
J.-A. Wang, H. Wang, H. Jiang, Y. Yan, B. Bevard
Oak Ridge National Laboratory
Used Fuel Disposition Campaign June 8, 2016
Las Vegas, NV
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Random vibration provides the external loading driver to the SNF assemblies; internal vibration drivers could be transient shocks generated by basket & spacer grids and fuel rod interactions
Acceleration-time history shows presence of discrete shock signals superimposed on continuous vibration
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To investigate the effects of vibration on SNF, a unique piece of test equipment was designed
and built at ORNL, the Cyclic Integrated Reversible-Bending Fatigue Tester (CIRFT)
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CIRFT testing provides important fatigue endurance information on SNF
Provides experimental data on fuel/clad system fatigue endurance limits to support model validation
Fatigue endurance testing has been conducted on three types of cladding: • High-burnup pressurized water reactor (PWR) fuel (HB Robinson) – 23
tests • High-burnup boiling water reactor (BWR) fuel (Limerick) – 15 tests • AREVA M5™ clad PWR fuel (North Anna & Catawba MOX) – 19 tests • Testing on sister rods is planned to begin in 2017
Fuel has performed robustly under various loading conditions and under millions of vibration cycles below the fatigue threshold loading • Results are documented in: FY 2015 Status Report: CIRFT Testing of High-
Burnup Used Nuclear Fuel Rods from Pressurized Water Reactor and Boiling Water Reactor Environments
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PWR high-burnup SNF rod used for CIRFT testing reveals good bonding at fuel-clad
interface and the remaining fuel pellet dish
Fuel-clad interface
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High-burnup HBR PWR SNF fatigue data
show a well-defined S-N curve with failure at the P-P interface
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CIRFT fatigue test results reveal some data scatter due to different types/sizes
and burnup of clads tested
W/ two foot drop
W/ one foot drop
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CIRFT strain vs. cycles-to-failure reflects less data scatter taking into
account the clad sizes/types
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A reduction in cycles-to-failure was noted when a drop-induced transient shock was
induced
y = 3.5693x-0.252 R² = 0.8722
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1.00E+03 1.00E+04 1.00E+05 1.00E+06 1.00E+07
Stra
in A
mpl
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(%
)
Number of Cycles or Cycles to Failure
HBR FailureHBR, no failureNA FailureMOX FailureNA, no failurePower (NA Failure)Power (MOX Failure)Power (HBR/NRC Failure)
The data point with red arrows represents test data where the sample experienced a two-foot drop (twice); both MOX specimens were tested with the same dynamic loading of 5N⋅m.
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HBR SNF S-N data indicates a hydrogen content dependency
yLH = 291.5x-0.239 R² = 0.9963
yHL = 324.81x-0.267 R² = 0.8906
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1.00E+03 1.00E+04 1.00E+05 1.00E+06 1.00E+07
Mom
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Nm
)
Number of Cycles-to-Failure
Power (H<=550wppm)
Power (H>=700 wppm)
Hydrogen was estimated from oxide thickness; detailed hydrogen measurements are needed to further quantify any hydrogen-dependent failure mechanism
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BWR CIRFT tested specimen failed at P-P interface
Fracture segments for LMK03/575B-A. (a) and (d) show the specimen ID side of the test segment; (b) and (e) show the mating fracture surface; and (c) and (f) show the opposite specimen ID side of the test segment.
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Hydride reorientation system and associated equipment for in-cell hydride reorientation tests have been tested out
of cell and have been moved in cell
• The hydride reorientation test equipment was constructed and tested out of cell.
• Planned test temperature: 400°C • The max. test pressure: 3500 psi
(24MPa)
Tubing weld system with a welded unirradiated Zry-4 sample
Oxide layer removal device with an oxide layer removed Zry-4 sample
Furnace
Hydride reorientation
system
High pressure system
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Out-of-Cell benchmark tests helped optimize reorientation test parameters
Produced a high ratio of radial hydrides for in-cell hydride reorientation tests with high-burnup HBR fuel segments.
Test conditions to be used for in-cell testing
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Three in-cell hydride reorientation demonstration have been successfully
completed
4”-long HBR fueled specimen for welding
Micrographs showing (a) circumferential hydrides before the hydride reorientation test, (b) radial hydrides after the hydride reorientation test.
• The system was installed in the hot cell. • All equipment functioned as expected.
– Welder: tested with both unirradiated and irradiated cladding samples
– High pressure system: tested at 3500 PSI at room temperature, as well as at elevated temperatures
– Furnace system: tested on an unirradiated sample overnight
– First in-cell reorientation demonstration (welding/thermal cycling) was successfully completed on high burnup SNF at 400°C with a hoop stress ≈145 MPa (see Slide 12 for details of thermal cycles).
(a) (b)
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HR1 break appears to be very different from the previous (non-reoriented) tests
• Fracture appears to have initiated at PPI, however fracture propagated in sheer direction.
• Additional cracks and pellet features can be seen on sheer lip.
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Met of HR1 in Longitudinal Direction
De-bonded fuel-cladding interface
Bonded fuel-cladding interface
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Pellet fragmented – not sure why yet
• Fracture appears to have initiated at PPI. The sheer lip may have ended at the adjacent PPI. • The pellet in the fracture zone broke into many pieces, however the adjacent pellets appear
largely intact. • It is difficult to draw any conclusions about the state of the fuel/clad bond from these images.
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HR3 End View
HR3-A End View HR3-B End View
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HBR and HR CIRFT Test Results Load vs. Failure Frequency
y = 270.85x-0.245 R² = 0.8976
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1.00E+03 1.00E+04 1.00E+05 1.00E+06 1.00E+07 1.00E+08
Mom
ent A
mpl
itude
(N
m)
Number of Cycles or Cycles to Failure
HBR Failure
HBR No failure
HR
Power (HBR Failure)
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HBR and HR CIRFT Test Results Strain vs. Failure Frequency*
y = 3.5693x-0.252 R² = 0.8722
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1.00E+03 1.00E+04 1.00E+05 1.00E+06 1.00E+07 1.00E+08
Stra
in A
mpl
itude
(%
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Number of Cycles or Cycles to Failure
HBR Failure
HBR No failure
HR
Power (HBR Failure)
*HR has much less flexural rigidity compared to that of HBR CIRFT samples
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Observations from the CIRFT testing:
• Pellet-clad-interaction includes P-C bonding efficiency • Hydrogen concentration does affect SNF system strength • The SNF system has significant stress concentrations and
residual stress distributions which can serve to reduce the system strength • Pellet-pellet interface
• Pellet-clad bonding
• Hydride distribution
• It appears that transient shock accumulated damage may reduce the SNF fatigue lifetime
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Future work will focus on detailed analysis of experimental data, testing of Sister rods
(with and without heat treatments), and testing for higher intensity “jolts”
■ Analyze previously obtained experimental SNF test data • Conduct detailed analyses of CIRFT test results • Collect and analyze hydride reorientation test results • Conduct post-irradiation examination (PIE) of hydride reorientation
experiments
■ Sister rod non-destructive tests and destructive tests :