Dr Robert Harrison

Dalton Research Fellow

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ORCID: 0000-0003-1186-6056
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Related information

Publications

On the Oxidation Mechanism of U3Si2 Accident Tolerant Nuclear Fuel

Research output: Contribution to journal › Article

Atomistic Level Study of Ce3Si2 Oxidation as an Accident Tolerant Nuclear Fuel Surrogate

Research output: Contribution to journal › Article

Cascade size and dose rate effects on α′ precipitation in ion-irradiated Fe14Cr alloy

Research output: Contribution to journal › Article

View all (35)

Activities

Atomistic level study of Ce3Si2 oxidation as an accident tolerant nuclear fuel surrogate

Activity: Talk or presentation › Oral presentation

On the use of ion beams to emulate the neutron irradiation behaviour of tungsten

Activity: Talk or presentation › Invited talk

A New in-situ Dual Ion Beam System for Investigation of Ion Implantation and Damage

Activity: Talk or presentation › Invited talk

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Media coverage and contribution

Nuclear fuel alternatives after Fukushima have challenges ahead

Press/Media: Research

Can tungsten face up to fusion power?

Press/Media: Research

Tungsten 'too brittle' for nuclear fusion reactors

Press/Media: Research

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Datasets

Intermetallic Re phases form in ion irradiated WRe alloy

Dataset

A Transmission Electron Microscopy study of the neutron-irradiation response of Ti-based MAX phases at high temperatures

Dataset

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Prizes

Tony Evans Memorial prize 2015/16

Prize: Prize (including medals and awards)

McLean Medal 2015/16

Prize: Prize (including medals and awards)

View all prizes (2)