A5016014046- Fusion materials and technologies
- Nuclear Materials and Properties
- Magnetic confinement fusion research
- Nuclear reactor physics and engineering
- Hydrogen Storage and Materials
- Muon and positron interactions and applications
- Laser Material Processing Techniques
- Laser-induced spectroscopy and plasma
- Laser-Matter Interactions and Applications
- Superconducting Materials and Applications
- Cold Fusion and Nuclear Reactions
- Coordination Chemistry and Organometallics
- Bipolar Disorder and Treatment
- Nuclear and radioactivity studies
- Particle accelerators and beam dynamics
Eindhoven University of Technology
2016-2023
For DEMO and beyond, liquid metal plasma-facing components are considered due to their resilience erosion through flowed replacement, potential for cooling beyond conduction inherent immunity many of the issues neutron loading compared solid materials. The development curve metals is behind that e.g. tungsten however, tokamak-based research currently somewhat limited in scope. Therefore, investigation into linear plasma devices can provide faster progress under controlled well-diagnosed...
Liquid metal (LM) divertors are considered for the European DEMO reactor, because they may offer improved performance compared to tungsten monoblock concept. The goal of this work is provide a concept design, and explore limitations liquid divertors. To end, set design requirements was formulated in close collaboration with EUROfusion Power Plant Physics Technology team (responsible EU-DEMO). Tin chosen as preferred metal, unacceptable Tritium retention issues arise when lithium used DEMO. A...
Liquid metal divertors aim to provide a more robust alternative conventional tungsten divertors.However, they still require solid substrate confine the liquid metal.This work proposes novel design philosophy for divertor targets, which allows two orders of magnitude reduction thermal stresses compared state-of-the-art monoblock designs.The main principle is based on 3D-printed structure, has low connectedness in direction perpendicular gradient, and as result also short length scales.This...
To develop realistic liquid lithium divertors for future fusion reactors, this paper aims to improve the understanding of their power handling capabilities. A divertor target prototype, designed facilitate metal experiments in tokamaks, was tested Magnum-PSI. The has an internal reservoir pre-filled with and passively re-supply textured plasma facing surface during operation. assess capability exposed helium plasmas increasing flux density linear device temperature response targets recorded...
A model is formulated to make a first estimate of the maximum tolerable power liquid lithium (Li) divertor targets, and gain insight into their behaviour in terms Li loss rate surface temperature. The model, as simple analytical expression, states that incoming balanced by heat conduction through target which dissipates energy via evaporation, radiation ion-neutral friction. considered fail when net flux from exceeds available supply. evaluated over range input parameters: supply rate, layer...
Tin (Sn) is an attractive option for a liquid metal wall material future fusion reactors. Control of tritium inventory key the successful operation these reactors, but little data exists up until now on hydrogen isotope retention in Sn. Free surface Sn targets and Sn-based capillary porous structure were exposed to deuterium (D) plasma nano-PSI magnum-PSI respectively. The retained D was determined using methods thermal desorption spectroscopy nuclear reaction analysis. dependence somewhat...
Abstract A fusion reactor divertor must withstand heat flux densities <10 MW m −2 . Additionally, it may have to millisecond pulses on the order of 0.5 30 MJ due (mitigated) edge-localized modes (ELM) occurring with 60 Hz. We investigate if these requirements can be met by capillary porous system (CPS) liquid lithium divertors (LLD). 3D-printed tungsten CPS targets were exposed in linear plasma device Magnum-PSI, deuterium discharges lasting 15 s, generating 1.5 16 , and T e ∼ eV....
In this work, a conceptual design for pre-filled liquid lithium divertor target the National Spherical Torus Experiment Upgrade (NSTX-U) is presented. The aimed at facilitating experiments with high flux from plasma facing components (PFCs) in NSTX-U and investigating potential of capillary based components. design, supplied reservoir PFC to surface via action wicking structure. This working principle also demonstrated experimentally. Next, titanium zirconium molybdenum (TZM) prototype...
Abstract In this work, Li-filled 3D-printed porous tungsten samples were exposed to deuterium (D) plasma in Magnum-PSI with a wide ion flux from 4 × 10 22 1.5 24 m −2 s −1 and corresponding temperature range below Li melting point (180.5 °C) above deuteride (LiD) (∼690 °C). The formation, decomposition of LiD have been directly observed the experiment via infra-red thermometry visually post-mortem while still vacuo, correlated D retained content. formation was characterized by solid...
Abstract The liquid metal shield laboratory (LiMeS-Lab) will provide the infrastructure to develop, test, and compare divertor designs for future fusion reactors. main research topics of LiMeS-lab be interactions with substrate material divertor, continuous circulation capillary refilling during intense plasma heat loading retention particles in metal. To facilitate research, four new devices are development at Dutch Institute Fundamental Energy Research Eindhoven University Technology:...
Abstract The splash created by intense laser pulse impact onto a liquid tin layer is studied experimentally using time-delayed stroboscopic shadowgraphy. An 8-ns infrared (1064 nm) focused deep pool. Various spot sizes (70, 120, and 130 $$\upmu$$ <mml:math xmlns:mml="http://www.w3.org/1998/Math/MathML"> <mml:mi>μ</mml:mi> </mml:math> m in diameter) various energies (ranging 2.5–30 mJ) are used, resulting fluences of $$\sim$$ <mml:mo>∼</mml:mo> 10–1000 J/cm $$^2$$ <mml:msup> <mml:mrow />...
Abstract A liquid Li vapour-box divertor is an attractive heat exhaust solution for future fusion reactors. Previous works have established the ability of vapour shielding to protect wall, but it has not been possible directly determine effects on plasma parameters. Experiments investigate this were carried out in Magnum-PSI, which able generate a with DEMO-divertor relevant conditions. 3D printed tungsten capillary porous structures filled used as targets. reciprocating Langmuir probe was...