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Sander Van Til

Observed names: S. Van Til, S. van Til, Sander van Til, VAN TIL S., VAN TIL, Sander, van Til, S.
ORCID: 0009-0004-5927-699X
Observed ORCID: 0009-0004-5927-699X
OpenAlex ID: A5069105591
Status of ceramic breeder pebble bed thermo-mechanics R&D and impact on breeder material mechanical strength
2012 · Alice Ying, Jörg Reimann, et al. · Fusion Engineering and Design · 62
Current Status of Beryllium Materials for Fusion Blanket Applications
2014 · Pavel Vladimirov, Dmitry Bachurin, et al. · Fusion Science & Technology · 43
Ceramic Breeder Materials
2012 · J.G. van der Laan, A.V. Fedorov, et al. · Elsevier eBooks · 37
Post irradiation characterization of beryllium and beryllides after high temperature irradiation up to 3000 appm helium production in HIDOBE-01
2015 · A.V. Fedorov, S. van Til, et al. · Fusion Engineering and Design · 36
Characteristics of microstructure, swelling and mechanical behaviour of titanium beryllide samples after high-dose neutron irradiation at 740 and 873K
2013 · P. Kurinskiy, A. Moeslang, et al. · Fusion Engineering and Design · 32
Evolution of beryllium pebbles (HIDOBE) in long term, high flux irradiation in the high flux reactor
2011 · S. van Til, J.B.J. Hegeman, et al. · Fusion Engineering and Design · 29
Tritium release and retention properties of highly neutron-irradiated beryllium pebbles from HIDOBE-01 experiment
2013 · V. Chakin, R. Rolli, et al. · Journal of Nuclear Materials · 25
Lithium orthosilicate surfaces: Characterization and effect on tritium release
2012 · M.H.H. Kolb, M. Bruns, et al. · Journal of Nuclear Materials · 23
The MARINE experiment: Irradiation of sphere-pac fuel and pellets of UO 2−x for americium breading blanket concept
2016 · E. D'Agata, P.R. Hania, et al. · Nuclear Engineering and Design · 18
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Analysis of tritium retention in beryllium pebbles in EXOTIC, PBA and HIDOBE-01 experiments
2013 · Alexander V. Fedorov, Sander van Til, et al. · Journal of Nuclear Materials · 18
Study of ceramic pebble beds in Post Irradiation Examination of the Pebble Bed Assemblies irradiation experiment
2012 · S. van Til, A.V. Fedorov, et al. · Fusion Engineering and Design · 18
Characterization of constrained beryllium pebble beds after neutron irradiation at HFR at high temperatures up to helium production of 3000appm
2013 · V. Chakin, R. Rolli, et al. · Fusion Engineering and Design · 17
Outcomes of the PELGRIMM project on Am-bearing fuel in pelletized and spherepac forms
2018 · A. Gallais-During, F. Delage, et al. · Journal of Nuclear Materials · 16
Tritium release from beryllium pebbles after high temperature irradiation up to 3000appm He in the HIDOBE-01 experiment
2013 · S. van Til, A.V. Fedorov, et al. · Journal of Nuclear Materials · 10
Out of pile tritium release behaviour and microscopic investigation of lithium metatitanate irradiated in the High Flux Reactor in Petten
2010 · S. van Til, A.J. Magielsen, et al. · Fusion Engineering and Design · 10
Tritium permeation in EUROFER in EXOTIC and LIBRETTO irradiation experiments
2013 · A.V. Fedorov, S. van Til, et al. · Fusion Engineering and Design · 8
Applying HAZOP analysis in assessing remote handling compatibility of ITER port plugs
2013 · L.P.M. Duisings, S. van Til, et al. · Fusion Engineering and Design · 8
Irradiation performance and first examinations of Americium bearing blanket fuel from the MARINE irradiation experiment
2023 · S. van Til, P.R. Hania, et al. · Journal of Nuclear Materials · 6
Tritium permeation and desorption in reduced activation martensitic steels studied in EXOTIC-9/1 irradiation experiment
2013 · A.V. Fedorov, S. van Til, et al. · Journal of Nuclear Materials · 6
Development of a dynamic-mesh porosity transport model for multi-dimensional fuel performance codes
2025 · Edoardo Luciano Brunetto, Carlo Fiorina, et al. · Journal of Nuclear Materials · 4
Determination of effective thermal conductivity of beryllium pebble beds during progressive neutron irradiation up to 6000appm He in the HIDOBE experiments
2013 · S. van Til, A.J. Magielsen, et al. · Fusion Engineering and Design · 4
First Post Irradiation Examinations on a fast reactor grade MOX fuel (U0.6,Pu0.4)O2 for Pu-burning application, irradiated in the High Flux Reactor
2025 · S. van Til, A.V. Fedorov, et al. · Journal of Nuclear Materials · 3
Advanced interpretation of the SPHERE irradiation experiment with neutronics and fuel performance codes
2024 · Marc Lainet, Lelio Luzzi, et al. · Nuclear Engineering and Technology · 3
Oxidation behaviour of neutron irradiated Be pebbles
2020 · N. Catarino, L.C. Alves, et al. · Nuclear Materials and Energy · 3
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LFR related R&D in the Dutch PIONEER program
2025 · Ferry Roelofs, Paul Breijder, et al. · Nuclear Engineering and Design · 1
Works count: 33
Citation count: 443
H-index: 13
I10-index: 15
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