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Assessment of Corrosion Resistance of Candidate Alloys for Accident Tolerant Fuel Cladding under Reactor Conditions

Published online by Cambridge University Press:  04 August 2017

Slavica Grdanovska
Affiliation:
Notre Dame Radiation Laboratory, University of Notre Dame, Notre Dame, IN, USA
Peng Wang
Affiliation:
Nuclear Engineering and Radiological Science, University of Michigan, Ann Arbor, MI, USA
Gary Was
Affiliation:
Nuclear Engineering and Radiological Science, University of Michigan, Ann Arbor, MI, USA
David Battels
Affiliation:
Notre Dame Radiation Laboratory, University of Notre Dame, Notre Dame, IN, USA

Abstract

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Type
Abstract
Copyright
© Microscopy Society of America 2017 

References

[1] Pukari, M. & Wallenius, J. “Cladding materials and radiation damage,” Dep. React. Phys. K. Tek. Hogskolan, 2010.Google Scholar
[2] M. Billone, Y. Yan, T. Burtseva, R. Daum, and others, “Cladding embrittlement during postulated loss-of-coolant accidents,” Argonne National Laboratory (ANL), 2008.CrossRefGoogle Scholar
[3] NEA, “Pellet-clad Interaction in Water Reactor Fuels,” presented at the CEA Cadarache/DEN/DEC, 2005.Google Scholar