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1دورية أكاديمية
المساهمون: NWO
المصدر: Nuclear Fusion ; ISSN 0029-5515 1741-4326
الوصف: The vapor-box is a liquid metal based design to cope with the demanding conditions of the divertor. This design relies on the recirculation of lithium by evaporation and condensation. An issue to this approach is the safety risks of Li-D/T formation and co-deposition on both the vapor-box walls - leading to possible recirculation impedance- and on the first wall leading to unacceptable tritium retention. Additively manufactured tungsten Capillary Porous Structure (CPS) samples filled with Li were exposed to high heat flux D plasmas in the linear plasma device Magnum-PSI and Li-D co-deposition was measured as a function of substrate temperature, estimated to be in the range 200-428 ${^\circ}$C and distance between 25-85 mm to the plasma beam center. The D:Li ratio was determined via in-situ ion beam diagnostics (NRA and EBS) and the spectra analyzed simultaneously to maximise the precision of the measurement. The experimental results approach close to the theoretical maximum at 40:60 D:Li ratio and the thickness of the deposited films was 0.02 - 3.2 $\mu$m. For witness plate temperatures above 400 ${^\circ}$C Li films under 150 nm in thickness were deposited and show lower D:Li ratios, as low as 5:95 D:Li ratio. At these temperatures the evaporation rate from the WPs is close to the deposition rate, and the decomposition pressure for LiD becomes comparable to the operational pressure in the vessel during the discharge. SOLPS-ITER simulations were also conducted to complement the experimental data. The results were used to narrow the range of CPS surface temperature to between $650-700$^{\circ}$C and determined that the D$^{+}$ plasma is largely replaced by Li$^{+}$ plasma close to the target surface. Further, the redeposition ratio of the lithium on the CPS surface is determined to be around 80$\%$, which matches well with the value determined from a quartz crystal microbalance. Due to limitations in the modeling of neutral interactions with Li coated surfaces, the SOLPS-ITER modeling does not well ...
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2دورية أكاديمية
المؤلفون: de Castro, A., Oyarzábal, E., Alegre, D., Tafalla, D., González, M., McCarthy, K. J., Scholte, J. G.A., Morgan, T. W., Tabarés, F. L.
المصدر: OLMAT team , de Castro , A , Oyarzábal , E , Alegre , D , Tafalla , D , González , M , McCarthy , K J , Scholte , J G A , Morgan , T W & Tabarés , F L 2023 , ' Physics and Technology Research for Liquid-Metal Divertor Development, Focused on a Tin-Capillary Porous System Solution, at the OLMAT High Heat-Flux Facility ' , Journal of Fusion Energy , vol. 42 , no. 2 , 45 . https://doi.org/10.1007/s10894-023-00373-9Test
مصطلحات موضوعية: Capillary Porous System, High heat flux facility, Liquid metal divertor, Plasma-surface interaction, Tin
الوصف: The operation of the Optimization of Liquid Metal Advanced Targets (OLMAT) facility began in April 2021 with the scientific objective of exposing liquid-metal plasma facing components (PFCs) to the particle and power fluxes provided by one of the hydrogen neutral beam injectors of the TJ-II stellarator. The system can deliver heat fluxes from 5 to 58 MW m −2 of high energy hydrogen neutral particles (≤ 33 keV) with fluxes up to 10 22 m 2 s −1 (containing an ion fraction ≤ 33% in some instances), pulsed operation of 30–150 ms duration and repetition rates up to 2 min −1 . These characteristics enable OLMAT as a high heat flux (HHF) facility for PFC evaluation in terms of power exhaust capabilities, thermal fatigue and resilience to material damage. Additionally, the facility is equipped with a wide range of diagnostics that includes tools for analyzing the thermal response of the targets as well as for monitoring atomic/plasma physics phenomena. These include spectroscopy, pyrometry, electrical probing and visualization (fast and IR cameras) units. Such particularities make OLMAT a unique installation that can combine pure technological PFC research with the investigation of physical phenomena such as vapor shielding, thermal sputtering, the formation/characterization of plasma plumes with significant content of evaporated metal and the detection of impurities in front of the studied targets. Additionally, a myriad of surface characterization techniques as SEM/EDX for material characterization of the exposed PFC prototypes are available at CIEMAT. In this article, first we provide an overview of the current facility upgrade in which a high-power CW laser, that can be operated in continuous and pulsed modes (0.2–10 ms), dump and electrical (single Langmuir) probe embedded on the target surface have been installed. This laser operation will allow simulating more relevant heat loading scenarios such as nominal steady-state divertor heat fluxes (10–20 MW m −2 in continuous mode) and transients including ELM loading ...
وصف الملف: application/pdf
الإتاحة: https://doi.org/10.1007/s10894-023-00373-9Test
https://research.tue.nl/en/publications/f8d97551-f1f4-4715-be19-c69ab24a2279Test
https://pure.tue.nl/ws/files/307704772/s10894-023-00373-9.pdfTest
http://www.scopus.com/inward/record.url?scp=85169674527&partnerID=8YFLogxKTest -
3دورية أكاديمية
المؤلفون: Tanke, V. F.B., Al, R. S., Alonso van der Westen, S., Brons, S., Classen, I. G.J., van Dommelen, J. A.W., van Eck, H. J.N., Geers, M. G.D., Lopes Cardozo, N. J., van der Meiden, H. J., Orrico, C. A., van de Pol, M. J., Riepen, M., Rindt, P., de Rooij, T. P., Scholten, J., Timmer, R. H.M., Vernimmen, J. W.M., Vos, E. G.P., Morgan, T. W.
المصدر: Tanke , V F B , Al , R S , Alonso van der Westen , S , Brons , S , Classen , I G J , van Dommelen , J A W , van Eck , H J N , Geers , M G D , Lopes Cardozo , N J , van der Meiden , H J , Orrico , C A , van de Pol , M J , Riepen , M , Rindt , P , de Rooij , T P , Scholten , J , Timmer , R H M , Vernimmen , ....
مصطلحات موضوعية: Fusion technology, Liquid metals, Lithium, Plasma-facing components, Tin
الوصف: The liquid metal shield laboratory (LiMeS-Lab) will provide the infrastructure to develop, test, and compare liquid metal divertor designs for future fusion reactors. The main research topics of LiMeS-lab will be liquid metal interactions with the substrate material of the divertor, the continuous circulation and capillary refilling of the liquid metal during intense plasma heat loading and the retention of plasma particles in the liquid metal. To facilitate the research, four new devices are in development at the Dutch Institute for Fundamental Energy Research and the Eindhoven University of Technology: LiMeS-AM: a custom metal 3D printer based on powder bed fusion; LiMeS-Wetting, a plasma device to study the wetting of liquid metals on various substrates with different surface treatments; LiMeS-PSI, a linear plasma generator specifically adapted to operate continuous liquid metal loops. Special diagnostic protection will also be implemented to perform measurements in long duration shots without being affected by the liquid metal vapor; LiMeS-TDS, a thermal desorption spectroscopy system to characterize deuterium retention in a metal vapor environment. Each of these devices has specific challenges due to the presence and deposition of metal vapors that need to be addressed in order to function. In this paper, an overview of LiMeS-Lab will be given and the conceptual designs of the last three devices will be presented.
وصف الملف: application/pdf
الإتاحة: https://doi.org/10.1007/s10894-023-00379-3Test
https://research.tue.nl/en/publications/d3082c0e-41f5-4ee4-a571-08fd708a4feeTest
https://pure.tue.nl/ws/files/307941618/s10894-023-00379-3.pdfTest
http://www.scopus.com/inward/record.url?scp=85169681912&partnerID=8YFLogxKTest -
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المؤلفون: Ratynskaia, Svetlana V., Tolias, Panagiotis, 1984, De Angeli, M., Ripamonti, D., Riva, G., Aussems, D., Morgan, T. W.
المصدر: Nuclear Materials and Energy. 17:222-227
مصطلحات موضوعية: Transient heat loads, Dust remobilization, Dust survivability, Dust adhesion, Mixed material effects
الوصف: Tungsten (W) substrates with adhered beryllium (Be) proxy dust-copper, chromium, aluminium -have been exposed in the Magnum-PSI linear device. Their interaction with transient and stationary plasmas has been systematically studied under varying heat fluxes and magnetic field topologies. The dust remobilization activities, macro-morphological changes and chemical modifications induced by the plasma incidence are documented. Aluminium is identified to be the most suitable surrogate material due to the similar binary phase diagram and nearly identical evaporation rates. Extrapolation suggests that Be dust cannot survive on hot W surfaces but it can trigger mixed Be/W effects prior to its plasma removal.
وصف الملف: print
الوصول الحر: https://urn.kb.se/resolve?urn=urn:nbn:se:kth:diva-241225Test
https://doi.org/10.1016/j.nme.2018.11.007Test -
5دورية أكاديمية
المؤلفون: Wang, S. C., van Kampen, M., Morgan, T. W.
المساهمون: ASML, European Commission, Research Program of the Materials innovation institute
المصدر: ACS Applied Materials & Interfaces ; volume 16, issue 15, page 19884-19884 ; ISSN 1944-8244 1944-8252
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6دورية أكاديمية
المؤلفون: Wang, S. C., Zoethout, E., van Kampen, M., Morgan, T. W.
المصدر: Journal of Applied Physics; 12/14/2022, Vol. 132 Issue 22, p1-13, 13p
مصطلحات موضوعية: HYDROGEN plasmas, DEUTERIUM, DEUTERIUM ions, FUSION reactors, ION bombardment, DEUTERIUM plasma, NUCLEAR reactor materials
مستخلص: Blister formation has been an emerging research topic for extreme ultraviolet (EUV) mirrors exposed to hydrogen plasmas. Similar to plasma-facing materials in nuclear fusion reactors, it has been reported that blister formation in EUV mirrors is initiated by hydrogen uptake due to hydrogen ion or atom bombardment. However, the research so far has focused on Mo/Si multilayers exposed to only hydrogen ions or atoms, while the EUV mirror typically has a Ru capping layer facing hydrogen plasmas. We present experimental work to measure plasma-induced hydrogen uptake of Ru films. We bombarded our designed Ru-capped target with a low-temperature deuterium plasma and measured the deuterium retention using elastic recoil detection. Contrary to ion-driven deuterium uptake, the deuterium uptake rate of the Ru film had no dependence on the deuterium ion flux or energy after a period of plasma exposure. A reaction–diffusion model has been built to calculate the time evolution of deuterium retention, which well fits the experimental data. Based on this model, we conclude that the surface composition of the Ru film is the limiting factor for the deuterium uptake, which is seriously weakened when the surface is covered by Ru oxide. After the Ru oxide is reduced by the plasma, the uptake rate is predominantly driven by the deuterium surface coverage on metallic Ru. Our model also indicates that at the deuterium-populated Ru surface, deuterium has a low absorption barrier to penetrate the surface, which is supported by previously reported computational work. [ABSTRACT FROM AUTHOR]
: Copyright of Journal of Applied Physics is the property of American Institute of Physics and its content may not be copied or emailed to multiple sites or posted to a listserv without the copyright holder's express written permission. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)
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7مؤتمر
المؤلفون: Brezinsek, Sebastijan, De Temmerman, G., Rodriguez, Nestor, Balden, M., Schwarz-Selinger, T., Loewenhoff, Th., Morgan, T. W., Li, Y., Wirtz, M.
المصدر: 1-5 (2021). ; 28th IAEA Fusion Energy Conference (FEC 2020), virtuell, virtuell, 2021-05-10 - 2021-05-15
جغرافية الموضوع: DE
العلاقة: info:eu-repo/semantics/altIdentifier/hdl/2128/27848; https://juser.fz-juelich.de/record/892772Test; https://juser.fz-juelich.de/search?p=id:%22FZJ-2021-02329%22Test
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8دورية أكاديمية
المؤلفون: Ghidersa, B.-E., Morgan, T. W., Roccella, S., Iafrati, M., Mazzitelli, G., DeLuca, R., Dose, G., Barrett, T., Domptail, F., Fursdon, M., Desai, S., Freemantle, J., Horsley, D., Alegre, D., Oyarzabal, E., Tabares, F., Rindt, P., Dejarnac, R., Horacek, J., Jerab, M., Varoutis, S., Peschany, S., Nallo, G. F., Carpignano, A., Moscheni, M., Pedroni, N., Subba, F., Uggenti, A. C., Zanino, R., Pericoli-Ridolfini, V., Chmielewski, P., Ivanova-Stanik, I., Poradziński, M., Zagorski, R., Makhlai, V., Garkusha, I., Pelekasis, N., Vlachomitrou, M., Dimopoulos, D., Lytra, A.
مصطلحات موضوعية: ddc:600, Technology, info:eu-repo/classification/ddc/600
وصف الملف: application/pdf
العلاقة: https://publikationen.bibliothek.kit.edu/1000124851Test; https://publikationen.bibliothek.kit.edu/1000124851/90220204Test; https://doi.org/10.5445/IR/1000124851Test
الإتاحة: https://doi.org/10.5445/IR/1000124851Test
https://publikationen.bibliothek.kit.edu/1000124851Test
https://publikationen.bibliothek.kit.edu/1000124851/90220204Test -
9دورية أكاديمية
المؤلفون: Wang, S. C., van Kampen, M., Morgan, T. W.
المصدر: ACS Applied Materials & Interfaces; 12/13/2023, Vol. 15 Issue 49, p57769-57782, 14p
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10دورية أكاديمية
المؤلفون: Tanke, V. F. B., Al, R. S., Alonso van der Westen, S., Brons, S., Classen, I. G. J., van Dommelen, J. A. W., van Eck, H. J. N., Geers, M. G. D., Lopes Cardozo, N. J., van der Meiden, H. J., Orrico, C. A., van de Pol, M. J., Riepen, M., Rindt, P., de Rooij, T. P., Scholten, J., Timmer, R. H. M., Vernimmen, J. W. M., Vos, E. G. P., Morgan, T. W.
المصدر: Journal of Fusion Energy; Dec2023, Vol. 42 Issue 2, p1-8, 8p
مستخلص: The liquid metal shield laboratory (LiMeS-Lab) will provide the infrastructure to develop, test, and compare liquid metal divertor designs for future fusion reactors. The main research topics of LiMeS-lab will be liquid metal interactions with the substrate material of the divertor, the continuous circulation and capillary refilling of the liquid metal during intense plasma heat loading and the retention of plasma particles in the liquid metal. To facilitate the research, four new devices are in development at the Dutch Institute for Fundamental Energy Research and the Eindhoven University of Technology: LiMeS-AM: a custom metal 3D printer based on powder bed fusion; LiMeS-Wetting, a plasma device to study the wetting of liquid metals on various substrates with different surface treatments; LiMeS-PSI, a linear plasma generator specifically adapted to operate continuous liquid metal loops. Special diagnostic protection will also be implemented to perform measurements in long duration shots without being affected by the liquid metal vapor; LiMeS-TDS, a thermal desorption spectroscopy system to characterize deuterium retention in a metal vapor environment. Each of these devices has specific challenges due to the presence and deposition of metal vapors that need to be addressed in order to function. In this paper, an overview of LiMeS-Lab will be given and the conceptual designs of the last three devices will be presented. [ABSTRACT FROM AUTHOR]
: Copyright of Journal of Fusion Energy is the property of Springer Nature and its content may not be copied or emailed to multiple sites or posted to a listserv without the copyright holder's express written permission. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)
