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Heleen Uitslag-Doolaard

Observed names: H. Doolaard, H. J. Uitslag-Doolaard, H. Uitslag-Doolaard, H. Uitslag-Doolaards, H.J. Uitslag-Doolaard, Heleen Doolaard, Helena Johanna Uitslag-Doolaard, Uitslag-Doolaard Heleen, Uitslag-Doolaard, Heleen
ORCID: 0000-0003-3372-6716
Observed ORCID: 0000-0003-3372-6716
OpenAlex ID: A5001694066
Benchmark exercise for fluid flow simulations in a liquid metal fast reactor fuel assembly
2016 · E. Merzari, P. Fischer, et al. · Nuclear Engineering and Design · 99
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Thermal-hydraulic study of the LBE-cooled fuel assembly in the MYRRHA reactor: Experiments and simulations
2016 · J. Pacio, T. Wetzel, et al. · Nuclear Engineering and Design · 78
Heat transfer to liquid metals in a hexagonal rod bundle with grid spacers: Experimental and simulation results
2014 · J. Pacio, K. Litfin, et al. · Nuclear Engineering and Design · 49
Thermal-Hydraulic Experimental Testing of the MYRRHA Wire-Wrapped Fuel Assembly
2019 · Graham Kennedy, Katrien Van Tichelen, et al. · Nuclear Technology · 26
Towards validated prediction with RANS CFD of flow and heat transport in a wire-wrap fuel assembly
2019 · Ferry Roelofs, Heleen Uitslag-Doolaard, et al. · Nuclear Engineering and Design · 22
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Multiscale modelling of the phénix dissymmetric test benchmark
2019 · H.J. Uitslag-Doolaard, F. Alcaro, et al. · Nuclear Engineering and Design · 21
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Experiment design to assess the inter-wrapper heat transfer in LMFR
2018 · H.J. Uitslag-Doolaard, F. Roelofs, et al. · Nuclear Engineering and Design · 21
Investigation of pressure loss and velocity distribution in fuel assemblies with wire-wrapped rods by using RANS and LES with wall functions
2020 · U. Bieder, H. Uitslag-Doolaard, et al. · Annals of Nuclear Energy · 19
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Numerical prediction of a single phase Pressurized Thermal Shock scenario for crack assessment in an Reactor Pressure Vessel wall
2020 · H.J. Uitslag-Doolaard, L. Stefanini, et al. · Annals of Nuclear Energy · 14
Reduced-resolution RANS approach to grid spacer fuel assemblies
2019 · Akshat Mathur, Heleen Uitslag-Doolaard, et al. · Nuclear Engineering and Design · 12
myMUSCLE, a New Multiphysics, Multiscale Simulation Coupling Environment
2023 · H. J. Uitslag-Doolaard, K. Zwijsen, et al. · Nuclear Science and Engineering · 11
Reduced RANS approach validation to model passive heat removal due to inter-wrapper flow
2019 · Akshat Mathur, Heleen Uitslag-Doolaard, et al. · Nuclear Engineering and Design · 11
CFD Benchmark for a heavy liquid metal fuel assembly
2015 · H. Doolaard, Afaque Shams, et al. · Ghent University Academic Bibliography (Ghent University) · 11
Core thermal hydraulic CFD support for liquid metal reactors
2019 · F. Roelofs, D. Dovizio, et al. · Nuclear Engineering and Design · 10
Synthesis, Purification, and Characterization of Molten Salt Fuel for the SALIENT-03 Irradiation Experiment
2024 · Pavel Souček, Ondřej Beneš, et al. · Materials · 7
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An overview of molten salt reactor research experiments at NRG PALLAS
2025 · Eva de Visser – Týnová, Ralph Hania, et al. · Nuclear Engineering and Design · 5
Fast reactor multi-scale and multi-physics modelling at NRG
2023 · Kevin Zwijsen, Heleen Uitslag-Doolaard, et al. · Nuclear Engineering and Design · 5
Development and First Applications of the Multi-Scale Multi-Physics Platform myMUSCLE -- MUSCLE-Foam
2023 · F. Roelofs, K. Zwijsen, et al. · International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH) · 5
Thermal-Hydraulic Design Support and Safety Analyses of Sealer UK Demo
2021 · Kevin Zwijsen, Heleen Uitslag-Doolaard, et al. · 5
Natural and hybrid ventilation principles based on buoyancy, sun and wind
2012 · P Engel, R.A.M. Kemperman, et al. · 4
Experiments and CFD for Wire-Wrapped Fuel Assembly Blockages
2025 · Ferry Roelofs, Akshat Mathur, et al. · Nuclear Technology · 3
Fast reactor thermal hydraulics in the Dutch PIONEER program
2023 · F. Roelofs, H. Uitslag-Doolaard, et al. · Nuclear Engineering and Design · 3
CFD analyses of the internal blockage in the nacie-up fuel Pin Bundle simulator
2017 · I. Di Piazza, Ranieri Marinari, et al. · CINECA IRIS Institutial research information system (University of Pisa) · 3
Comprehensive Modelling of Pressurized Thermal Shock With a Probabilistic Approach
2023 · Fabio Pasti, Sina Tajfirooz, et al. · ASME Pressure Vessels and Piping Conference (PVP) · 2
Thermal Hydraulic Design Support and Safety Analyses of SEALER UK Demo: Nominal Operations and Various Accident Scenarios
2022 · K. Zwijsen, H.J. Uitslag-Doolaard, et al. · Advances in Thermal Hydraulics (ATH) · 2
Works count: 42
Citation count: 456
H-index: 11
I10-index: 14
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