Determining failure properties of as-received and hydrided unirradiated Zircaloy-4 from ring compression tests

Garrison, Benton; Yan, Yong; TerMaath, Stephanie

doi:10.1016/j.engfailanal.2021.105362

Determining failure properties of as-received and hydrided unirradiated Zircaloy-4 from ring compression tests

Journal Article · Tue Mar 16 00:00:00 EDT 2021 · Engineering Failure Analysis

DOI:https://doi.org/10.1016/j.engfailanal.2021.105362· OSTI ID:1782071

Garrison, Benton ^[1]; ^[2]; ^[3]

Univ. of Tennessee, Knoxville, TN (United States); Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
Univ. of Tennessee, Knoxville, TN (United States)

An integrated experimental and computational approach was developed to determine the plastic strain at fracture and to investigate the fracture energy of as-received and hydrided unirradiated Zircaloy-4 nuclear cladding tubes in the hoop direction at room temperature from ring compression testing (RCT). This work builds on previous methods in the literature that were developed to obtain the mechanical properties of nuclear cladding before fracture (Young’s modulus, yield stress, and strain-hardening parameters) from experimental RCT results and extends the characterization of this material class to include material failure properties. Furthermore, a ductile damage approach was developed and implemented in a validated finite element model to predict material failure, evaluate fracture energy, and quantify the plastic strain at fracture initiation. The hydrogen content of the Zircaloy-4 specimens was varied up to 610 wppm when the failure became brittle. As expected, increasing hydrogen content caused embrittlement of the Zircaloy-4 samples tested and the plastic strain at fracture and fracture energy to decrease.

View Accepted Manuscript (DOE)

Research Organization:: Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)

Sponsoring Organization:: USDOE

Grant/Contract Number:: AC05-00OR22725

OSTI ID:: 1782071

Journal Information:: Engineering Failure Analysis, Journal Name: Engineering Failure Analysis Vol. 125; ISSN 1350-6307

Publisher:: ElsevierCopyright Statement

Country of Publication:: United States

Language:: English

References (24)

Applications of digital-image-correlation techniques to experimental mechanics Chu, T. C.; Ranson, W. F.; Sutton, M. A. Experimental Mechanics, Vol. 25, Issue 3 https://doi.org/10.1007/BF02325092	journal	September 1985
Analysis of crack formation and crack growth in concrete by means of fracture mechanics and finite elements Hillerborg, A.; Modéer, M.; Petersson, P. -E. Cement and Concrete Research, Vol. 6, Issue 6 https://doi.org/10.1016/0008-8846(76)90007-7	journal	November 1976
Effect of strain hardening on the lateral compression of tubes between rigid plates Reid, S. R.; Reddy, T. Yella International Journal of Solids and Structures, Vol. 14, Issue 3 https://doi.org/10.1016/0020-7683(78)90026-4	journal	January 1978
Phenomena associated with the crushing of metal tubes between rigid plates Reddy, T. Yella; Reid, S. R. International Journal of Solids and Structures, Vol. 16, Issue 6 https://doi.org/10.1016/0020-7683(80)90005-0	journal	January 1980
Application of finite element method to ring compression test Yamada, Rayji; Suzuki, Motoe; Harayama, Yasuo Nuclear Engineering and Design, Vol. 44, Issue 1 https://doi.org/10.1016/0029-5493(77)90124-8	journal	October 1977
On obtaining material properties from the ring compression test Yella Reddy, T.; Reid, S. R. Nuclear Engineering and Design, Vol. 52, Issue 2 https://doi.org/10.1016/0029-5493(79)90055-4	journal	April 1979
Reproducing hoop stress–strain behavior for tubular material using lateral compression test Nemat-Alla, Mahmoud International Journal of Mechanical Sciences, Vol. 45, Issue 4 https://doi.org/10.1016/S0020-7403(03)00115-2	journal	April 2003
Finite-element simulation of the lateral compression of aluminium tube between rigid plates Leu, Daw-Kwei International Journal of Mechanical Sciences, Vol. 41, Issue 6 https://doi.org/10.1016/S0020-7403(98)00040-X	journal	June 1999
Failure of Zircaloy cladding under transverse plane-strain deformation Link, T. M.; Koss, D. A.; Motta, A. T. Nuclear Engineering and Design, Vol. 186, Issue 3 https://doi.org/10.1016/S0029-5493(98)00284-2	journal	December 1998
Influence of heterogeneities introduced into the modelling of a ring compression test Bizet, Laurent; Charleux, Ludovic; Balland, Pascale Archives of Civil and Mechanical Engineering, Vol. 17, Issue 2 https://doi.org/10.1016/j.acme.2016.11.002	journal	February 2017
A new model of metal plasticity and fracture with pressure and Lode dependence Bai, Yuanli; Wierzbicki, Tomasz International Journal of Plasticity, Vol. 24, Issue 6 https://doi.org/10.1016/j.ijplas.2007.09.004	journal	June 2008
Hydride reorientation in Zircaloy-4 cladding Chu, H. C.; Wu, S. K.; Kuo, R. C. Journal of Nuclear Materials, Vol. 373, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2007.06.012	journal	February 2008
The issue of stress state during mechanical tests to assess cladding performance during a reactivity-initiated accident (RIA) Desquines, J.; Koss, D. A.; Motta, A. T. Journal of Nuclear Materials, Vol. 412, Issue 2 https://doi.org/10.1016/j.jnucmat.2011.03.015	journal	May 2011
Ductile-to-brittle transition temperature for high-burnup cladding alloys exposed to simulated drying-storage conditions Billone, M. C.; Burtseva, T. A.; Einziger, R. E. Journal of Nuclear Materials, Vol. 433, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2012.10.002	journal	February 2013
Determination of the hoop fracture properties of unirradiated hydrogen-charged nuclear fuel cladding from ring compression tests Martin-Rengel, M. A.; Gómez Sánchez, F. J.; Ruiz-Hervías, J. Journal of Nuclear Materials, Vol. 436, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2013.01.311	journal	May 2013
Effects of hydride morphology on the embrittlement of Zircaloy-4 cladding Kim, Ju-Seong; Kim, Tae-Hoon; Kook, Dong-Hak Journal of Nuclear Materials, Vol. 456 https://doi.org/10.1016/j.jnucmat.2014.09.025	journal	January 2015
A model to describe the mechanical behavior and the ductile failure of hydrided Zircaloy-4 fuel claddings between 25 °C and 480 °C Le Saux, M.; Besson, J.; Carassou, S. Journal of Nuclear Materials, Vol. 466 https://doi.org/10.1016/j.jnucmat.2015.07.026	journal	November 2015
Effects of oxide and hydrogen on the circumferential mechanical properties of Zircaloy-4 cladding Kim, Jun Hwan; Lee, Myoung Ho; Choi, Byoung Kwon Nuclear Engineering and Design, Vol. 236, Issue 18 https://doi.org/10.1016/j.nucengdes.2006.02.010	journal	September 2006
Texture development and anisotropic deformation of zircaloys Linga Murty, K.; Charit, Indrajit Progress in Nuclear Energy, Vol. 48, Issue 4 https://doi.org/10.1016/j.pnucene.2005.09.011	journal	May 2006
Stress and temperature-dependent hydride reorientation of Zircaloy-4 cladding and its effect on the ductility degradation Kim, Young-Jun; Kook, Dong-Hak; Kim, Tae-Hoon Journal of Nuclear Science and Technology, Vol. 52, Issue 5 https://doi.org/10.1080/00223131.2014.978829	journal	November 2014
Characterizing the Material Properties of a Tube from a Lateral Compression Test Rathnaweera, Gayan; Durandet, Yvonne; Ruan, Dong International Journal of Protective Structures, Vol. 2, Issue 4 https://doi.org/10.1260/2041-4196.2.4.465	journal	December 2011
Experimental and Analytical Investigation of the Mechanical Behavior of High-Burnup Zircaloy-4 Fuel Cladding Daum, Robert S.; Majumdar, Saurin; Billone, Michael C. Journal of ASTM International, Vol. 5, Issue 5 https://doi.org/10.1520/JAI101209	journal	January 2008
Evaluation of Hydride Reorientation Behavior and Mechanical Properties for High-Burnup Fuel-Cladding Tubes in Interim Dry Storage Aomi, Masaki; Baba, Toshikazu; Miyashita, Toshiyasu Journal of ASTM International, Vol. 5, Issue 9 https://doi.org/10.1520/JAI101262	journal	January 2008
A comprehensive failure model for crashworthiness simulation of aluminium extrusions Hooputra, H.; Gese, H.; Dell, H. International Journal of Crashworthiness, Vol. 9, Issue 5 https://doi.org/10.1533/ijcr.2004.0289	journal	September 2004

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Related Subjects

36 MATERIALS SCIENCE
failure properties
finite element analysis
mechanical properties
nuclear materials
ring compression test

Determining failure properties of as-received and hydrided unirradiated Zircaloy-4 from ring compression tests

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