The influence of stress state on the reorientation of hydrides in a zirconium alloy

Mahmut N. Cinbiz; Donald A. Koss; Arthur T. Motta

doi:10.1016/j.jnucmat.2016.05.013

The influence of stress state on the reorientation of hydrides in a zirconium alloy

Mahmut N. Cinbiz, Donald A. Koss, Arthur T. Motta

Research output: Contribution to journal › Article › peer-review

52 Scopus citations

Abstract

Hydride reorientation can occur in spent nuclear fuel cladding when subjected to a tensile hoop stress above a threshold value during cooling. Because in these circumstances the cladding is under a multiaxial stress state, the effect of stress biaxiality on the threshold stress for hydride reorientation is investigated using hydrided CWSR Zircaloy-4 sheet specimens containing ∼180 wt ppm of hydrogen and subjected to a two-cycle thermo-mechanical treatment. The study is based on especially designed specimens within which the stress biaxiality ratios range from uniaxial (σ₂/σ₁ = 0) to "near-equibiaxial" tension (σ₂/σ₁ = 0.8). The threshold stress is determined by mapping finite element calculations of the principal stresses and of the stress biaxiality ratio onto the hydride microstructure obtained after the thermo-mechanical treatment. The results show that the threshold stress (maximum principal stress) decreases from 155 to 75 MPa as the stress biaxiality increases from uniaxial to "near-equibiaxial" tension.

Original language	English
Pages (from-to)	157-164
Number of pages	8
Journal	Journal of Nuclear Materials
Volume	477
DOIs	https://doi.org/10.1016/j.jnucmat.2016.05.013
State	Published - Aug 15 2016
Externally published	Yes

Funding

This research was funded by the Nuclear Regulatory Commission (NRC Contract 04-10-156) , under the supervision of Harold Scott, and the authors are grateful for this support. We acknowledge helpful discussion with Michael Billone from Argonne National Laboratory . The thorough and insightful comments of Manfred Puls were especially appreciated. The research for this publication was supported by the Pennsylvania State University Materials Research Institute Nano Fabrication Network and the National Science Foundation Cooperative Agreement No. 0335765 , National Nanotechnology Infrastructure Network with Cornell University .

Funders	Funder number
Pennsylvania State University Materials Research Institute Nano Fabrication Network
National Science Foundation
Directorate for Engineering	0335765
U.S. Nuclear Regulatory Commission
National Research Council	04-10-156

Keywords

Hydride reorientation
Hydrides
Stress state
Threshold stress
Zirconium alloys

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10.1016/j.jnucmat.2016.05.013

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title = "The influence of stress state on the reorientation of hydrides in a zirconium alloy",

abstract = "Hydride reorientation can occur in spent nuclear fuel cladding when subjected to a tensile hoop stress above a threshold value during cooling. Because in these circumstances the cladding is under a multiaxial stress state, the effect of stress biaxiality on the threshold stress for hydride reorientation is investigated using hydrided CWSR Zircaloy-4 sheet specimens containing ∼180 wt ppm of hydrogen and subjected to a two-cycle thermo-mechanical treatment. The study is based on especially designed specimens within which the stress biaxiality ratios range from uniaxial (σ2/σ1 = 0) to {"}near-equibiaxial{"} tension (σ2/σ1 = 0.8). The threshold stress is determined by mapping finite element calculations of the principal stresses and of the stress biaxiality ratio onto the hydride microstructure obtained after the thermo-mechanical treatment. The results show that the threshold stress (maximum principal stress) decreases from 155 to 75 MPa as the stress biaxiality increases from uniaxial to {"}near-equibiaxial{"} tension.",

keywords = "Hydride reorientation, Hydrides, Stress state, Threshold stress, Zirconium alloys",

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doi = "10.1016/j.jnucmat.2016.05.013",

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AU - Koss, Donald A.

AU - Motta, Arthur T.

PY - 2016/8/15

Y1 - 2016/8/15

N2 - Hydride reorientation can occur in spent nuclear fuel cladding when subjected to a tensile hoop stress above a threshold value during cooling. Because in these circumstances the cladding is under a multiaxial stress state, the effect of stress biaxiality on the threshold stress for hydride reorientation is investigated using hydrided CWSR Zircaloy-4 sheet specimens containing ∼180 wt ppm of hydrogen and subjected to a two-cycle thermo-mechanical treatment. The study is based on especially designed specimens within which the stress biaxiality ratios range from uniaxial (σ2/σ1 = 0) to "near-equibiaxial" tension (σ2/σ1 = 0.8). The threshold stress is determined by mapping finite element calculations of the principal stresses and of the stress biaxiality ratio onto the hydride microstructure obtained after the thermo-mechanical treatment. The results show that the threshold stress (maximum principal stress) decreases from 155 to 75 MPa as the stress biaxiality increases from uniaxial to "near-equibiaxial" tension.

AB - Hydride reorientation can occur in spent nuclear fuel cladding when subjected to a tensile hoop stress above a threshold value during cooling. Because in these circumstances the cladding is under a multiaxial stress state, the effect of stress biaxiality on the threshold stress for hydride reorientation is investigated using hydrided CWSR Zircaloy-4 sheet specimens containing ∼180 wt ppm of hydrogen and subjected to a two-cycle thermo-mechanical treatment. The study is based on especially designed specimens within which the stress biaxiality ratios range from uniaxial (σ2/σ1 = 0) to "near-equibiaxial" tension (σ2/σ1 = 0.8). The threshold stress is determined by mapping finite element calculations of the principal stresses and of the stress biaxiality ratio onto the hydride microstructure obtained after the thermo-mechanical treatment. The results show that the threshold stress (maximum principal stress) decreases from 155 to 75 MPa as the stress biaxiality increases from uniaxial to "near-equibiaxial" tension.

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KW - Hydrides

KW - Stress state

KW - Threshold stress

KW - Zirconium alloys

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The influence of stress state on the reorientation of hydrides in a zirconium alloy

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