Ghent University Academic Bibliography

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The plasma-facing materials of tokamak thermonuclear reactors : requirements, thermal stabilization, and tests (a review)

Guido Van Oost (UGent) , A. V. Dedov and V. P. Budaev

(2021) THERMAL ENGINEERING. 68(3). p.185-200
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- Journal Article
- A1
- open access
Overview of power exhaust experiments in the COMPASS divertor with liquid metals

R. Dejarnac, J. Horacek, M. Hron, M. Jerab, J. Adamek, S. Atikukke, P. Barton, J. Cavalier, J. Cecrdle, M. Dimitrova, et al.

(2020) NUCLEAR MATERIALS AND ENERGY. 25.
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Modeling of COMPASS tokamak divertor liquid metal experiments

J. Horacek, R. Dejarnac, J. Cecrdle, D. Tskhakaya, A. Vertkov, J. Cavalier, P. Vondracek, M. Jerab, P. Barton, Guido Van Oost (UGent) , et al.

(2020) NUCLEAR MATERIALS AND ENERGY. 25.
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Thermal shock behaviour of H and H/He-exposed tungsten at high temperature

Nathan Lemahieu, Henri Greuner, Jochen Linke, Hans Maier, Gerald Pintsuk, Marius Wirtz, Guido Van Oost (UGent) and Jean-Marie Noterdaeme (UGent)

(2016) PHYSICA SCRIPTA. T167.
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Estimation of the contribution of gaps to tritium retention in the divertor of ITER

Dmitry Matveev (UGent) , A Kirschner, K Schmid, A Litnovsky, D Borodin, M Komm, Guido Van Oost (UGent) and U Samm

(2014) PHYSICA SCRIPTA. T159.
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Study of radioactive inventory generated from W-based components in ITER and PPCS fusion designs

Mikaël Desecures, L El-Guebaly, F Druyts, Philien Van Iseghem, V Massaut and Guido Van Oost (UGent)

(2013) FUSION ENGINEERING AND DESIGN. 88(9-10). p.2674-2678
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Mechanical properties and microstructural characterizations of potassium doped tungsten

Hua Sheng (UGent) , Inge Uytdenhouwen (UGent) , Guido Van Oost (UGent) and Jozef Vleugels

(2012) NUCLEAR ENGINEERING AND DESIGN. 246. p.198-202
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- Journal Article
- A1
- open access
Modelling of impurity deposition in gaps of castellated surfaces with the 3D-GAPS code

Dmitry Matveev (UGent) , A Kirschner, A Litnovsky, M Komm, D Borodin, V Philipps and Guido Van Oost (UGent)

(2010) PLASMA PHYSICS AND CONTROLLED FUSION. 52(7).
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Carbon transport in the stochastic magnetic boundary of TEXTOR

G Telesca, E Delabie, O Schmitz, S Brezinsek, KH Finken, M von Hellermann, M Jakubowski, M Lehnen, Y Liang, A Pospieszczyk, et al.

(2009) JOURNAL OF NUCLEAR MATERIALS. 390–391. p.227-231
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Modelling of radiative power exhaust by sputtered and seeded impurities in fusion reactors with carbon and molybdenum target plates

Giuseppe Telesca (UGent) , R. Zagorski, D. Kalupin, R. Stankiewicz, M. Z. Tokar and Guido Van Oost (UGent)

(2007) NUCLEAR FUSION. 47(11). p.1625-1633

Academic Bibliography

The plasma-facing materials of tokamak thermonuclear reactors : requirements, thermal stabilization, and tests (a review)

Overview of power exhaust experiments in the COMPASS divertor with liquid metals

Modeling of COMPASS tokamak divertor liquid metal experiments

Thermal shock behaviour of H and H/He-exposed tungsten at high temperature

Estimation of the contribution of gaps to tritium retention in the divertor of ITER

Study of radioactive inventory generated from W-based components in ITER and PPCS fusion designs

Mechanical properties and microstructural characterizations of potassium doped tungsten

Modelling of impurity deposition in gaps of castellated surfaces with the 3D-GAPS code

Carbon transport in the stochastic magnetic boundary of TEXTOR

Modelling of radiative power exhaust by sputtered and seeded impurities in fusion reactors with carbon and molybdenum target plates

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