Hostname: page-component-78c5997874-dh8gc Total loading time: 0 Render date: 2024-11-05T02:33:29.529Z Has data issue: false hasContentIssue false
  • English
  • Français

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: [email protected])
Get access

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 

Access options

Get access to the full version of this content by using one of the access options below. (Log in options will check for institutional or personal access. Content may require purchase if you do not have access.)

Footnotes

*

Equal authorship

References

REFERENCES

Puls, M.P., “The Effect of Hydrogen and Hydrides on the Integrity of Zirconium Alloy Components: Delayed Hydride Cracking”, (Springer, 2008).Google Scholar
Jernkvist, L.O. and Massih, A.R., Comp. Mat. Sci. 85 363–382 (2014).Google Scholar
Cui, J., Shek, G.K., Scarth, D.A. and Wang, Z., J. Pressure Vessel Technol. 131 041407 (2009)CrossRefGoogle Scholar
Perovic, V., Weatherly, G.C., and Simpson, C.J., Acta Metall. 31 1381–1391 (1983).Google Scholar
McMinn, A., Darby, E.C. and Schofield, J.S. in The Terminal Solid Solubility of Hydrogen in Zirconium Alloys(Zirconium in the Nuclear Industry: Twelfth International Symposium, ASTM STP 1354, 2003).Google Scholar
Carpenter, G. J. C., Watters, J.F., and Gilbert, R.W., J. Nucl. Mater. 48 262–276 (1973).Google Scholar
Perovic, V., Purdy, G.R. and Brown, L.M., Acta Metall. 27 1075–1084 (1978).Google Scholar
Van der Giessen, E., Needleman, A., Model. Simul. Mater. Sci. Eng. 3 689 (1995).CrossRefGoogle Scholar
Tarleton, E., Balint, D.S., Gong, J., Wilkinson, A.J., Acta Mater. 88 271–282 (2015).CrossRefGoogle Scholar
Patel, M., MSc Thesis, Imperial College London, 2014 Google Scholar