Fabrication, characterization, and testing of Cr-coated Zr alloy nuclear fuel rod cladding for enhanced accident tolerance

A.K. Evans, P. J. Kelly, D T Goddard, A Cole-Baker, G Obasi, Michael Preuss, E. P. Vernon

Research output: Chapter in Book/Conference proceeding › Conference contribution › peer-review

Original language	English
Title of host publication	Light Water Reactor Fuel Performance Conference (TOP FUEL 2019)
Publisher	American Nuclear Society (ANS)
Pages	864-873
Number of pages	10
ISBN (Print)	9781713814054
Publication status	Published - 2020

Access to Document

Evans, A. K., Kelly, P. J., Goddard, D. T., Cole-Baker, A., Obasi, G., Preuss, M., & Vernon , E. P. (2020). Fabrication, characterization, and testing of Cr-coated Zr alloy nuclear fuel rod cladding for enhanced accident tolerance. In Light Water Reactor Fuel Performance Conference (TOP FUEL 2019) (pp. 864-873). American Nuclear Society (ANS). https://www.proceedings.com/55241.html

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title = "Fabrication, characterization, and testing of Cr-coated Zr alloy nuclear fuel rod cladding for enhanced accident tolerance",

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year = "2020",

language = "English",

isbn = "9781713814054",

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Fabrication, characterization, and testing of Cr-coated Zr alloy nuclear fuel rod cladding for enhanced accident tolerance. / Evans, A.K.; Kelly, P. J.; Goddard, D T et al.
Light Water Reactor Fuel Performance Conference (TOP FUEL 2019). American Nuclear Society (ANS), 2020. p. 864-873.

Research output: Chapter in Book/Conference proceeding › Conference contribution › peer-review

TY - GEN

T1 - Fabrication, characterization, and testing of Cr-coated Zr alloy nuclear fuel rod cladding for enhanced accident tolerance

AU - Evans, A.K.

AU - Kelly, P. J.

AU - Goddard, D T

AU - Cole-Baker, A

AU - Obasi, G

AU - Preuss, Michael

AU - Vernon , E. P.

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M3 - Conference contribution

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BT - Light Water Reactor Fuel Performance Conference (TOP FUEL 2019)

PB - American Nuclear Society (ANS)

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