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Discrete Dislocation Plasticity Modeling of Hydrides in Zirconium under Thermal Cycling

Published online by Cambridge University Press:  19 June 2017

Mitesh Patel ,
Sana Waheed ,
Mark R. Wenman ,
Adrian P. Sutton  and
Daniel S. Balint
Mitesh Patel*
Affiliation:
Department of Physics, Imperial College London, SW7 2AZ, UK
Sana Waheed
Affiliation:
Department of Mechanical Engineering, Imperial College London, SW7 2AZ, UK
Mark R. Wenman
Affiliation:
Department of Materials and Centre for Nuclear Engineering, Imperial College London, SW7 2AZ, UK
Adrian P. Sutton
Affiliation:
Department of Physics, Imperial College London, SW7 2AZ, UK
Daniel S. Balint
Affiliation:
Department of Mechanical Engineering, Imperial College London, SW7 2AZ, UK
*
† (Email: mp2109@ic.ac.uk)
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Abstract

Understanding the ratcheting effect of hydrogen and hydride accumulation in response to thermal cycling is important in establishing a failure criterion for zirconium alloy nuclear fuel cladding. We propose a simple discrete dislocation plasticity model to study the evolution of the dislocation content that arises as a micro-hydride repeatedly precipitates and dissolves over a series of thermal cycles. With each progressive thermal cycle, we find a steady growth in the residual dislocation density in the vicinity of the hydride nucleation site; this corresponds to a gradual increase in the hydrogen concentration and, consequently, the hydride population. The simulated ratcheting in the dislocation density is consistent with experimental observations concerning the hysteresis in the terminal solid solubility of hydrogen in zirconium, which can be correlated to the plastic relaxation of hydrides.

Keywords

ZrdislocationsH
Type
Articles
Information
MRS Advances , Volume 2 , Issue 55: Energy Storage and Conversion , 2017 , pp. 3353 - 3358
Copyright
Copyright © Materials Research Society 2017 

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Footnotes

*

Equal authorship

References

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