Ghent University Academic Bibliography

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Contributions of MYRRHA to the European fusion energy roadmap

Guido Van Oost (UGent) , D. Terentyev and H. A. Abderrahim

(2024) FUSION ENGINEERING AND DESIGN. 198.
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Comparative study of ITER conform tungsten grades exposed to high heat flux and neutron irradiation damage

D. Terentyev, M. Wirtz, T.W. Morgan, T. Nozawa, A. Zinovev, C.C. Chang, Kateryna Poleshchuk (UGent) and J. Elenbaas

(2024) FUSION ENGINEERING AND DESIGN. 200.
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- Journal Article
- A1
- open access
A control oriented strategy of disruption prediction to avoid the configuration collapse of tokamak reactors

Andrea Murari, Riccardo Rossi, Teddy Craciunescu, Jesús Vega, J. Mailloux, N. Abid, K. Abraham, P. Abreu, O. Adabonyan, P. Adrich, et al.

(2024) NATURE COMMUNICATIONS. 15(1).
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- Journal Article
- A1
- open access
Development of RAFM steels for high temperature applications guided by thermodynamic modelling

Olga Kachko, A. Puype, D. Terentyev, G. Bonny, W.Van Renterghem and Roumen Petrov (UGent)

(2022) NUCLEAR MATERIALS AND ENERGY. 32.
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- Journal Article
- A1
- open access
Overview of JET results for optimising ITER operation

J. Mailloux, N. Abid, K. Abraham, P. Abreu, O. Adabonyan, P. Adrich, V. Afanasev, M. Afzal, T. Ahlgren, L. Aho-Mantila, et al.

(2022) NUCLEAR FUSION. 62(4).
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Disruption prediction with artificial intelligence techniques in tokamak plasmas

J. Vega, A. Murari, S. Dormido-Canto, G. A. Rattá, M. Gelfusa, J. Mailloux, N. Abid, K. Abraham, P. Abreu, O. Adabonyan, et al.

(2022) NATURE PHYSICS. 18(7). p.741-750
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- Journal Article
- A1
- open access
Development of RAFM steel for nuclear applications with reduced manganese, silicon and carbon content

D. Terentyev, A. Puype, Olga Kachko, W. Van Renterghem and J. Henry

(2021) NUCLEAR MATERIALS AND ENERGY. 29.
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EBSD characterization of pure and K-doped tungsten fibers annealed at different temperatures

Leandro Paulo De Almeida Reis Tanure, D. Terentyev, V. Nikolić, J. Riesch and Kim Verbeken (UGent)

(2020) JOURNAL OF NUCLEAR MATERIALS. 537.
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Fracture behavior of tungsten-based composites exposed to steady-state/transient hydrogen plasma

Yu Li, T. W. Morgan, J. A. W. Van Dommelen, S. Antusch, M. Rieth, J. P. M. Hoefnagels, D. Terentyev, G. De Temmerman, Kim Verbeken (UGent) and M.G.D. Geers

(2020) NUCLEAR FUSION. 60(4).
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Three mechanisms of hydrogen-induced dislocation pinning in tungsten

Y. Li, T. W. Morgan, D. Terentyev, S. Ryelandt, A. Favache, S. Wang, M. Wirtz, J. P. M. Hoefnagels, J. A. W. van Dommelen, G. De Temmerman, et al.

(2020) NUCLEAR FUSION. 60(8).

Academic Bibliography

Contributions of MYRRHA to the European fusion energy roadmap

Comparative study of ITER conform tungsten grades exposed to high heat flux and neutron irradiation damage

A control oriented strategy of disruption prediction to avoid the configuration collapse of tokamak reactors

Development of RAFM steels for high temperature applications guided by thermodynamic modelling

Overview of JET results for optimising ITER operation

Disruption prediction with artificial intelligence techniques in tokamak plasmas

Development of RAFM steel for nuclear applications with reduced manganese, silicon and carbon content

EBSD characterization of pure and K-doped tungsten fibers annealed at different temperatures

Fracture behavior of tungsten-based composites exposed to steady-state/transient hydrogen plasma

Three mechanisms of hydrogen-induced dislocation pinning in tungsten

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