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Characterization of stress-rupture behavior of nuclear-grade C26M2 FeCrAl alloy for accident-tolerant fuel cladding via burst testing

  • Published:2020-07 Issue: Volume:791 Page:139753
  • ISSN:0921-5093
  • Container-title:Materials Science and Engineering: A
  • language:en
  • Short-container-title:Materials Science and Engineering: A

Author:

Joshi P.,Kombaiah B.,Cinbiz M.N.,Murty K.L.

Funder

U.S. Department of Energy

National Science Foundation

Publisher

Elsevier BV

Subject

Mechanical Engineering,Mechanics of Materials,Condensed Matter Physics,General Materials Science

Reference24 articles.

1. Accident tolerant fuels for LWRs: a perspective;Zinkle;J. Nucl. Mater.,2014

2. Accident tolerant fuel cladding development: promise, status, and challenges;Terrani;J. Nucl. Mater.,2018

3. Material selection for accident tolerant fuel cladding;Pint;Metall. Mater. Trans. E.,2015

4. Report on Exploration of New FeCrAl Heat Variants with Improved Properties;Yamamoto,2019

5. Biaxial creep behavior of Nb-modified zircaloys;Joshi;Nucl. Technol.,2019

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