Length scale effects of micro- and meso-scale tensile tests of unirradiated and irradiated Zircaloy-4 cladding

Lam, Sebastian; Frazer, David; Cappia, Fabiola; Nelson, Malachi Michael; Samuha, S.; Pitts, Stephanie A.; Harris, Brennan K.; Hosemann, Peter

doi:10.1016/j.jnucmat.2024.155469

Length scale effects of micro- and meso-scale tensile tests of unirradiated and irradiated Zircaloy-4 cladding

Journal Article · Mon Oct 28 00:00:00 EDT 2024 · Journal of Nuclear Materials

DOI:https://doi.org/10.1016/j.jnucmat.2024.155469· OSTI ID:2503497

^[1]; Frazer, David ^[2]; Cappia, Fabiola ^[2]; ^[3]; ^[4]; ^[2]; ^[2]; Hosemann, Peter ^[1]

University of California, Berkeley, CA (United States)
Idaho National Laboratory (INL), Idaho Falls, ID (United States)
University of California, Berkeley, CA (United States); Idaho National Laboratory (INL), Idaho Falls, ID (United States)
NCRN - Department of Materials Engineering, Be'er-Sheva (Israel)

Zircaloy-4 is an essential material for cladding structures within fission-based reactors. To explore the changes in properties measured on differing length scales, FIB-machined micro-scale tensile tests were performed on both irradiated and control groups of Zircaloy-4. This was correlated with tensile testing on femtosecond laser-machined meso-scale specimens. Pronounced size effects were found when varying specimen geometry. Increases in tensile geometry size were associated with a reduction in measured yield stress for both irradiated and unirradiated samples. Here, meso-scale testing found strength and strain values similar to that of bulk-scale testing.

View Accepted Manuscript (DOE)

Research Organization:: Idaho National Laboratory (INL), Idaho Falls, ID (United States)

Sponsoring Organization:: USDOE Laboratory Directed Research and Development (LDRD) Program

Grant/Contract Number:: AC07-05ID14517

OSTI ID:: 2503497

Report Number(s):: INL/JOU--24-79634-Rev000

Journal Information:: Journal of Nuclear Materials, Journal Name: Journal of Nuclear Materials Vol. 604; ISSN 0022-3115

Publisher:: ElsevierCopyright Statement

Country of Publication:: United States

Language:: English

References (18)

Demonstration of a High-Throughput Tensile Testing Technique Using Femtosecond Laser-Fabricated Tensile Bars in AISI 316 and Additively Manufactured Grade 91 Steel Harvey, Cayla; Torrez, Avery J.; Lam, Sebastian JOM, Vol. 73, p. 4240-4247 https://doi.org/10.1007/s11837-021-04964-9	journal	October 2021
Femtosecond Laser Machining of Micromechanical Tensile Test Specimens Dong, A.; Duckering, J.; Peterson, J. JOM, Vol. 73, Issue 12 https://doi.org/10.1007/s11837-021-04971-w	journal	October 2021
Short-pulse laser ablation of solid targets Momma, Carsten; Chichkov, Boris N.; Nolte, Stefan Optics Communications, Vol. 129, Issue 1-2 https://doi.org/10.1016/0030-4018(96)00250-7	journal	August 1996
A mechanistic study of grain boundary behaviour during irradiation-induced growth in zirconium Roy, Ronit; Long, Fei; Daymond, Mark R. Acta Materialia, Vol. 276 https://doi.org/10.1016/j.actamat.2024.120075	journal	September 2024
Effect of radial hydrides on the axial and hoop mechanical properties of Zircaloy-4 cladding Chu, H. C.; Wu, S. K.; Chien, K. F. Journal of Nuclear Materials, Vol. 362, Issue 1 https://doi.org/10.1016/j.jnucmat.2006.11.008	journal	May 2007
The effect of sample thickness on micro-mesoscale tensile properties of 304SS, HT-9, and CuCrZr Dong, A.; Vo, H.; Olivas, E. Journal of Nuclear Materials, Vol. 575 https://doi.org/10.1016/j.jnucmat.2022.154207	journal	March 2023
Temperature-Dependent Mechanical Anisotropy in Textured Zircaloy Cladding Nelson, Malachi; Samuha, Shmuel; Kamerman, David Journal of Nuclear Materials, Vol. 595 https://doi.org/10.1016/j.jnucmat.2024.155045	journal	July 2024
Enhanced stress relaxation behavior via basal 〈a〉 dislocation activity in Zircaloy-4 cladding Nelson, Malachi; Samuha, Shmuel; Kombaiah, Boopathy Journal of Nuclear Materials, Vol. 601 https://doi.org/10.1016/j.jnucmat.2024.155337	journal	December 2024
Temperature-dependent axial mechanical properties of Zircaloy-4 with various hydrogen amounts and hydride orientations Bang, Shinhyo; Kim, Ho-a; Noh, Jae-soo Nuclear Engineering and Technology, Vol. 54, Issue 5 https://doi.org/10.1016/j.net.2021.11.007	journal	May 2022
Small-scale mechanical testing on nuclear materials: bridging the experimental length-scale gap Hosemann, Peter Scripta Materialia, Vol. 143 https://doi.org/10.1016/j.scriptamat.2017.04.026	journal	January 2018
Micro- and mesoscale mechanical properties of an ultra-fine grained CrFeMnNi high entropy alloy produced by large strain machining Gigax, Jonathan G.; El-Atwani, Osman; McCulloch, Quinn Scripta Materialia, Vol. 178 https://doi.org/10.1016/j.scriptamat.2019.11.042	journal	March 2020
Comparison of heat-affected zones due to nanosecond and femtosecond laser pulses using transmission electronic microscopy Le Harzic, R.; Huot, N.; Audouard, E. Applied Physics Letters, Vol. 80, Issue 21 https://doi.org/10.1063/1.1481195	journal	May 2002
Multiaxial Plastic Deformation of Zircaloy-4 Nuclear Fuel Cladding Tubes Kamerman, David; Nelson, Malachi Nuclear Technology, Vol. 209, Issue 6 https://doi.org/10.1080/00295450.2022.2160174	journal	February 2023
Materials mechanical size effects: a review Zhu, T. T.; Bushby, A. J.; Dunstan, D. J. Materials Technology, Vol. 23, Issue 4 https://doi.org/10.1179/175355508X376843	journal	December 2008
Mechanical Property Testing of Irradiated Zircaloy Cladding Under Reactor Transient Conditions Daum, R. S.; Majumda, S.; Tsai, H. Small Specimen Test Techniques: Fourth Volume https://doi.org/10.1520/STP10821S	book	January 2002
Small scale mechanical testing of irradiated materials Hosemann, P.; Shin, C.; Kiener, D. Journal of Materials Research, Vol. 30, Issue 9 https://doi.org/10.1557/jmr.2015.26	journal	April 2015
Review of Zircaloy-2 and Zircaloy-4 Properties Relevant to N. S. Savannah Reactor Design Whitmarsh, C. L. https://doi.org/10.2172/4827123	report	July 1962
Novel Methods for the Site Specific Preparation of Micromechanical Structures Wurster, S.; Treml, R.; Fritz, R. Practical Metallography, Vol. 52, Issue 3 https://doi.org/10.3139/147.110331	journal	March 2015

Similar Records

Tensile Hoop Behavior of Irradiated Zircaloy-4 Nuclear Fuel Cladding

Technical Report · Wed Feb 28 23:00:00 EST 2007 · OSTI ID:931509

IN-CELL FABRICATION AND TESTING OF IRRADIATED FUEL ELEMENT CLADDING TENSILE SPECIMENS

Journal Article · Sun Dec 31 23:00:00 EST 1961 · Proc. Hot Lab. Equip. Conf., 10th, Washington, D.C., 1962 · OSTI ID:4768009

Mechanical properties of neutron irradiated F82H using micro-tensile testing

Conference · Wed Aug 01 00:00:00 EDT 2018 · Nuclear Materials and Energy · OSTI ID:1881173

Related Subjects

36 MATERIALS SCIENCE
Fuel cladding
Length scale effects
Small scale mechanical testing
Tensile testing
Zircaloy
Zircaloy-4

Length scale effects of micro- and meso-scale tensile tests of unirradiated and irradiated Zircaloy-4 cladding

Citation Formats

References (18)

Similar Records

Related Subjects