Thermomechanical Microstructural Predictions of Fracture Nucleation of Zircaloy-4 Alloys With δ and ε Hydride Distributions

Mohamed, I.; Hasan, T.; Zikry, M. A.

doi:10.1115/1.4051687

Thermomechanical Microstructural Predictions of Fracture Nucleation of Zircaloy-4 Alloys With δ and ε Hydride Distributions

Journal Article · 19 July 2021 · Journal of Engineering Materials and Technology

DOI:https://doi.org/10.1115/1.4051687· OSTI ID:1980662

Mohamed, I. ^[1]; Hasan, T.; Zikry, M. A.

OSTI

Abstract

A crystalline dislocation-density formulation that was incorporated with a nonlinear finite-element (FE) method was utilized to understand and to predict the thermomechanical behavior of an hexagonal closest packed (h.c.p.) zircaloy system with hydrides with either face-centered cubic (f.c.c.) or body-centered cubic (b.c.c.) hydrides. This formulation was then used with a recently developed fracture methodology that is adapted for finite inelastic strains and multiphase crystalline systems to understand how different microstructurally based fracture modes nucleate and propagate. The interrelated microstructural characteristics of the different crystalline hydride and matrix phases with the necessary orientation relationships (ORs) have been represented, such that a detailed physical understanding of fracture nucleation and propagation can be predicted for the simultaneous thermomechanical failure modes of hydride populations and the matrix. The effects of volume fraction, morphology, crystalline structure, and orientation and distribution of the hydrides on simultaneous and multiple fracture modes were investigated for radial, circumferential, and mixed distributions. Another key aspect was accounting for temperatures changes due to the effects of thermal conduction and dissipated plastic work and their collective effects on fracture. For hydrided aggregates subjected to high temperatures, thermal softening resulted in higher ductility due to increased dislocation-density activity, which led to higher shear strain accumulation and inhibited crack nucleation and growth. The predictions provide validated insights into why circumferential hydrides are more fracture-resistant than radial hydrides for different volume fractions and thermomechanical loading conditions.

Research Organization:: North Carolina State University, Raleigh, NC (United States)

Sponsoring Organization:: USDOE Office of Nuclear Energy (NE)

DOE Contract Number:: NE0008717;

OSTI ID:: 1980662

Journal Information:: Journal of Engineering Materials and Technology, Journal Name: Journal of Engineering Materials and Technology Journal Issue: 1 Vol. 144; ISSN 0094-4289

Publisher:: ASME

Country of Publication:: United States

Language:: English

References (30)

Finite element calculations of the accommodation energy of a misfitting precipitate in an elastic-plastic matrix Leitch, Brian W.; Puls, Manfred P. Metallurgical Transactions A, Vol. 23, Issue 3 https://doi.org/10.1007/BF02675557	journal	March 1992
Correction to: Modeling of the microstructural behavior of hydrided zirconium alloys Mohamed, I.; Zikry, M. A. Computational Mechanics, Vol. 68, Issue 3 https://doi.org/10.1007/s00466-021-02043-z	journal	June 2021
A Simple Method for Calculating the Possible Habit Planes Containing One Set of Dislocations and its Applications to fcc/bct and hcp/bcc Systems Gu, X. -F.; Zhang, W. -Z. Metallurgical and Materials Transactions A, Vol. 45, Issue 4 https://doi.org/10.1007/s11661-013-2125-9	journal	December 2013
The effect of hydrogen and strain rate on the “ductile-brittle” behaviour of zircaloy Fearnehough, G. D.; Cowan, A. Journal of Nuclear Materials, Vol. 22, Issue 2 https://doi.org/10.1016/0022-3115(67)90023-2	journal	May 1967
The precipitation of zirconium hydride in zirconium and zircaloy-2 Bradbrook, J. S.; Lorimer, G. W.; Ridley, N. Journal of Nuclear Materials, Vol. 42, Issue 2 https://doi.org/10.1016/0022-3115(72)90021-9	journal	February 1972
Effects of crystallographic orientation on plastic deformation and SCC initiation of zirconium alloys Kubo, T.; Wakashima, Y.; Amano, K. Journal of Nuclear Materials, Vol. 132, Issue 1 https://doi.org/10.1016/0022-3115(85)90386-1	journal	May 1985
An accurate and stable algorithm for high strain-rate finite strain plasticity Zikry, M. A. Computers & Structures, Vol. 50, Issue 3 https://doi.org/10.1016/0045-7949(94)90004-3	journal	February 1994
The development and applications of zirconium alloys Northwood, Derek O. Materials & Design, Vol. 6, Issue 2 https://doi.org/10.1016/0261-3069(85)90165-7	journal	April 1985
Effect of the circumferential hydrides on the deformation and fracture of Zircaloy cladding tubes Hong, S. I.; Lee, K. W.; Kim, K. T. Journal of Nuclear Materials, Vol. 303, Issue 2-3 https://doi.org/10.1016/S0022-3115(02)00814-0	journal	June 2002
Modeling dislocation storage rates and mean free paths in face-centered cubic crystals Kubin, L.; Devincre, B.; Hoc, T. Acta Materialia, Vol. 56, Issue 20 https://doi.org/10.1016/j.actamat.2008.08.012	journal	December 2008
Simulation of inter- and transgranular crack propagation in polycrystalline aggregates due to stress corrosion cracking Musienko, Andrey; Cailletaud, Georges Acta Materialia, Vol. 57, Issue 13 https://doi.org/10.1016/j.actamat.2009.04.035	journal	August 2009
Dislocation density evolution and interactions in crystalline materials Shanthraj, P.; Zikry, M. A. Acta Materialia, Vol. 59, Issue 20 https://doi.org/10.1016/j.actamat.2011.08.041	journal	December 2011
A finite element method for the simulation of strong and weak discontinuities in solid mechanics Hansbo, Anita; Hansbo, Peter Computer Methods in Applied Mechanics and Engineering, Vol. 193, Issue 33-35 https://doi.org/10.1016/j.cma.2003.12.041	journal	August 2004
A study of intergranular fracture in an aluminium alloy due to hydrogen embrittlement Pouillier, E.; Gourgues, A. -F.; Tanguy, D. International Journal of Plasticity, Vol. 34 https://doi.org/10.1016/j.ijplas.2012.01.004	journal	July 2012
Microstructural modeling of crack nucleation and propagation in high strength martensitic steels Wu, Q.; Zikry, M. A. International Journal of Solids and Structures, Vol. 51, Issue 25-26 https://doi.org/10.1016/j.ijsolstr.2014.08.021	journal	December 2014
Stress-induced reorientation of hydrides and mechanical properties of Zircaloy-4 cladding tubes Hong, S. I.; Lee, K. W. Journal of Nuclear Materials, Vol. 340, Issue 2-3 https://doi.org/10.1016/j.jnucmat.2004.11.014	journal	April 2005
Zirconium alloys for supercritical water reactor applications: Challenges and possibilities Motta, Arthur T.; Yilmazbayhan, Aylin; da Silva, Marcelo J. Gomes Journal of Nuclear Materials, Vol. 371, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2007.05.022	journal	September 2007
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 fracture strength of δ-zirconium hydrides embedded in zirconium matrix at high temperatures Kubo, T.; Kobayashi, Y.; Uchikoshi, H. Journal of Nuclear Materials, Vol. 435, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2012.12.045	journal	April 2013
Comparison of irradiation hardening and microstructure evolution in ion-irradiated delta and epsilon hydrides Oono, Naoko; Kasada, Ryuta; Higuchi, Toru Journal of Nuclear Materials, Vol. 442, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2013.03.013	journal	November 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
Micro-scale fracture experiments on zirconium hydrides and phase boundaries Chan, H.; Roberts, S. G.; Gong, J. Journal of Nuclear Materials, Vol. 475 https://doi.org/10.1016/j.jnucmat.2016.03.026	journal	July 2016
The effect of cooling rate and grain size on hydride microstructure in Zircaloy-4 Birch, Ruth; Wang, Siyang; Tong, Vivian S. Journal of Nuclear Materials, Vol. 513 https://doi.org/10.1016/j.jnucmat.2018.11.011	journal	January 2019
Hydrogen in zirconium alloys: A review Motta, Arthur T.; Capolungo, Laurent; Chen, Long-Qing Journal of Nuclear Materials, Vol. 518 https://doi.org/10.1016/j.jnucmat.2019.02.042	journal	May 2019
Quantification Challenges for Atom Probe Tomography of Hydrogen and Deuterium in Zircaloy-4 Mouton, Isabelle; Breen, Andrew J.; Wang, Siyang Microscopy and Microanalysis, Vol. 25, Issue 2 https://doi.org/10.1017/S143192761801615X	journal	March 2019
Radial-hydride Embrittlement of High-burnup Zircaloy-4 Fuel Cladding Daum, Robert S.; Majumdar, Saurin; Liu, Yung Journal of Nuclear Science and Technology, Vol. 43, Issue 9 https://doi.org/10.1080/18811248.2006.9711195	journal	September 2006
Prediction of Grain-Boundary Interfacial Mechanisms in Polycrystalline Materials Ashmawi, W. M.; Zikry, M. A. Journal of Engineering Materials and Technology, Vol. 124, Issue 1 https://doi.org/10.1115/1.1421611	journal	July 2001
Effect of thermal cycling on the stress orientation and circumferential ductility in Zircaloy-2 Mishima, Y.; Okubo, T. Canadian Metallurgical Quarterly, Vol. 11, Issue 1 https://doi.org/10.1179/cmq.1972.11.1.157	journal	January 1972
Orientation relationships between coherent interfaces in hcp–fcc systems subjected to high strain-rate deformation and fracture modes Ziaei, Shoayb; Wu, Qifeng; Zikry, Mohammed A. Journal of Materials Research, Vol. 30, Issue 15 https://doi.org/10.1557/jmr.2015.207	journal	August 2015
On the Ductile-Brittle Transition in Lath Martensitic Steel Morris, Jr., John William ISIJ International, Vol. 51, Issue 10 https://doi.org/10.2355/isijinternational.51.1569	journal	January 2011

Similar Records

High angle grain-boundary effects and microstructurally induced failure mechanisms in crystalline materials

Conference · 1995 · OSTI ID:175400

Predictive machine learning approaches for the microstructural behavior of multiphase zirconium alloys

Journal Article · 2023 · Scientific Reports · OSTI ID:1968093

Orientation relationships in precipitation systems

Journal Article · 1981 · Acta Metall.; (United States) · OSTI ID:6789508

Related Subjects

Engineering
Materials Science

Thermomechanical Microstructural Predictions of Fracture Nucleation of Zircaloy-4 Alloys With δ and ε Hydride Distributions

Citation Formats

References (30)

Similar Records

Related Subjects