Hydride reorientation and its impact on ambient temperature mechanical properties of high burn-up irradiated and unirradiated recrystallized Zircaloy-2 nuclear fuel cladding with an inner liner

2017 ◽  
Vol 494 ◽  
pp. 114-126 ◽  
Author(s):  
Q. Auzoux ◽  
P. Bouffioux ◽  
A. Machiels ◽  
S. Yagnik ◽  
B. Bourdiliau ◽  
...  
Keyword(s):  
Mechanical Properties ◽  
Ambient Temperature ◽  
Nuclear Fuel ◽  
Fuel Cladding ◽  
Nuclear Fuel Cladding ◽  
Hydride Reorientation

Nanoindentation measurements of the mechanical properties of zirconium matrix and hydrides in unirradiated pre-hydrided nuclear fuel cladding

2014 ◽  
Vol 452 (1-3) ◽  
pp. 69-76 ◽  
Author(s):  
A. Rico ◽  
M.A. Martin-Rengel ◽  
J. Ruiz-Hervias ◽  
J. Rodriguez ◽  
F.J. Gomez-Sanchez
Keyword(s):  
Mechanical Properties ◽  
Nuclear Fuel ◽  
Fuel Cladding ◽  
Nuclear Fuel Cladding

Failure Criteria for Unirradiated PWR Cladding Subjected to Ring Compression Tests

2015 ◽  
Author(s):  
Jesus Ruiz-Hervias ◽  
Miguel Angel Martin-Rengel ◽  
Francisco Javier Gomez-Sanchez
Keyword(s):  
Radial Direction ◽  
Experimental Testing ◽  
Failure Criteria ◽  
Spent Fuel ◽  
Compression Tests ◽  
Fuel Cladding ◽  
Ring Compression Test ◽  
Ring Compression ◽  
Nuclear Fuel Cladding ◽  
Hydride Reorientation

The ring compression test applied to nuclear fuel cladding is relatively easy to perform but difficult to interpret. It can be representative of the loading state associated to a hypothetical spent fuel assembly drop accident. This is particularly important for spent fuel cladding subjected to drying operations previous to storage and transportation, because they may produce hydride reorientation along the radial direction of cladding. In this paper, experimental testing and numerical simulations are combined to obtain operative failure criteria from the results of the ring compression tests on unirradiated pre-hydrided samples with radial hydrides, simulating drying, storage and subsequent transport conditions.

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