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David Guzonas

Chalk River Laboratories
Atomic Energy of Canada Limited

41

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568

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Material research for the supercritical water-cooled reactor—summary and open issues

2020
- Radek Novotny
- David Guzonas
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Radiation effects and mechanical properties

2018
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Environmentally assisted cracking

2018
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Corrosion behavior of alloy 316L stainless steel after exposure to supercritical water at 500 °C for 20,000 h

2017 Journal of Supercritical Fluids
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Characterization of oxide layer and micro-crack initiation in alloy 316L stainless steel after 20,000 h exposure to supercritical water at 500 °C

2017 Materials Characterization
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Internal oxidation and crack susceptibility of alloy 310S stainless steel after long term exposure to supercritical water at 500 °C

2017 Journal of Supercritical Fluids
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Corrosion phenomena induced by supercritical water in Generation IV nuclear reactors

2017
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Materials and Water Chemistry for Supercritical Water-cooled Reactors

2017
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A comparative study on the oxidation of austenitic alloys 304 and 304-oxide dispersion strengthened steel in supercritical water at 650 °C

2017 Journal of Supercritical Fluids
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GENERATION OF ULTRAFAST TRANSIENT ACID SPIKES IN HIGH-TEMPERATURE WATER IRRADIATED WITH LOW LINEAR ENERGY TRANSFER RADIATION

2016
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Citations (2)