Publications
Post-test examination of a Li-Ta heat pipe exposed to H plasma in Magnum PSI, Fusion Eng. Des. 146 (2019) 2603-2607.
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Testing of a high temperature radiatively cooled Li/Ta heat pipe in Magnum-PSI, Fusion Eng. Des. 146 (2019) 482-485.
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Mitigation of divertor heat loads by strike point sweeping in high power JET discharges, Phys. Scr. 2017 (2017) 014040.
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Physics conclusions in support of ITER W divertor monoblock shaping, Nucl. Mater. Energy 12 (2017) 60-74.
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JET experiments with tritium and deuterium–tritium mixtures, Fusion Eng. Des. 109–111, Part A (2016) 925-936.
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Contrasting H-mode behaviour with deuterium fuelling and nitrogen seeding in the all-carbon and metallic versions of JET, Nucl. Fusion 754 (2014) 073016.
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Experiences With Tungsten Plasma Facing Components in ASDEX Upgrade and JET, IEEE Transactions on Plasma Science 42 (2014) 552-562.
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Tungsten divertor erosion in all metal devices: Lessons from the ITER like wall of JET, J. Nucl. Mater. 438, Supplement (2013) S42-S47.
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Residual carbon content in the initial ITER-Like Wall experiments at JET, J. Nucl. Mater. 438, Supplement (2013) S303-S308.
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Impact of the ITER-like wall on divertor detachment and on the density limit in the JET tokamak, J. Nucl. Mater. 438, Supplement (2013) S139-S147.
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Disruption heat loads and their mitigation in JET with the ITER-like wall, J. Nucl. Mater. 438, Supplement (2013) S102-S107.
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Impact and mitigation of disruptions with the ITER-like wall in JET, Nucl. Fusion 953 (2013) 093007.
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The impact of the ITER-like wall at JET on disruptions, Plasma Phys. Control. Fusion 1254 (2012) 124032.
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Overview of experimental preparation for the ITER-Like Wall at JET, J. Nucl. Mater. 1415 (2011) S936-S942.
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