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Research article

First published 2017-12

In situ imaging of corrosion processes in nuclear fuel cladding

Alice Laferrere, Robert Burrows, Carol Glover [...]

Corrosion Engineering,Science and Technology: The International Journal of Corrosion Processes and Corrosion Control

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Research article

First published 2022-12

Characterisation of AlCrCuFeMo x high entropy alloys for nuclear fuel cladding

Xincheng Zhu, Zhenrui Tao, Chunji Wang [...]

Materials Science and Technology

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Research article

First published 1988-5

Spallation of oxide from stainless steel AGR nuclear fuel cladding: Mechanisms and consequences

H. E. Evans

Materials Science and Technology

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Research article

First published 2013-8

An assessment of delayed hydride cracking in zirconium alloy cladding tubes under stress transients

K S Chan

International Materials Reviews

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Research article

First published 1983-04

The Valuation of Nuclear Power in The Post-Three Mile Island Era

Martin B. Zimmerman

The Energy Journal

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Research article

First published 2012-2

Environmentally friendly application of hydrides to nuclear reactor cores

K. Konashi, M. Yamawaki

Advances in Applied Ceramics: Structural,Functional and Bioceramics

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Research article

First published 2010-3

Characterisations of electrospark deposition Stellite 6 alloy coating on 316L sealed valve used in nuclear power plant

C. J. Chen, M. C. Wang, D. S. Wang [...]

Materials Science and Technology

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Research article

First published 1968-4

Non-elastic stresses in composite plates under transient thermal conditions

D J Lewis, J S Campbell

The Journal of Strain Analysis for Engineering Design

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Research article

First published 2016-4

Effect of temperature on corrosion and semiconducting properties of oxide films formed on M5 zirconium alloy

R. A. Antunes, M. C. Lopes de Oliveira, J. A. Batista de Souza

Corrosion Engineering,Science and Technology: The International Journal of Corrosion Processes and Corrosion Control

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Research article

First published 1974-1

The Physical Metallurgy of Nuclear Fuel Elements in Sweden.

G. Östberg

International Materials Reviews

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