4.5 Article Proceedings Paper

Calculation and experimental test of the cooling factor of tungsten

期刊

NUCLEAR FUSION
卷 50, 期 2, 页码 -

出版社

IOP PUBLISHING LTD
DOI: 10.1088/0029-5515/50/2/025012

关键词

-

向作者/读者索取更多资源

The cooling factor of W is evaluated using state of the art data for line radiation and an ionization balance which has been benchmarked with experiment. For the calculation of line radiation, level-resolved calculations were performed with the Cowan code to obtain the electronic structure and excitation cross sections ( plane-wave Born approximation). The data were processed by a collisional radiative model to obtain electron density dependent emissions. These data were then combined with the radiative power derived from recombination rates and bremsstrahlung to obtain the total cooling factor. The effect of uncertainties in the recombination rates on the cooling factor was studied and was identified to be of secondary importance. The new cooling factor is benchmarked, by comparisons of the line radiation with spectral measurements as well as with a direct measurement of the cooling factor. Additionally, a less detailed calculation using a configuration averaged model was performed. It was used to benchmark the level-resolved calculations and to improve the prediction on radiation power from line radiation for ionization stages which are computationally challenging. The obtained values for the cooling factor validate older predictions from the literature. Its ingredients and the absolute value are consistent with the existing experimental results regarding the value itself, the spectral distribution of emissions and the ionization equilibrium. A table of the cooling factor versus electron temperature is provided. Finally, the cooling factor is used to investigate the operational window of a fusion reactor with W as intrinsic impurity. The minimum value of nT tau(E), for which a thermonuclear burn is possible, is increased by 20% for a W concentration of 3.0 x 10(-5) compared with a plasma without any impurities, except for the He ash which is considered in both cases.

作者

我是这篇论文的作者
点击您的名字以认领此论文并将其添加到您的个人资料中。

评论

主要评分

4.5
评分不足

次要评分

新颖性
-
重要性
-
科学严谨性
-
评价这篇论文

推荐

Article Materials Science, Multidisciplinary

Charpy impact tests of tungsten fiber-reinforced composite from-150 °C to 1000 °C☆

Hanns Gietl, Johann Riesch, Till Hoeschen, Michael Rieth, Jan W. Coenen, Rudolf Neu

Summary: Research has shown that tungsten fiber-reinforced composites have the potential to overcome the brittleness issue of tungsten at room temperature. Through Charpy impact tests and microscopic investigation, the transition temperature ranges of the fiber and matrix have been identified.

MATERIALS LETTERS (2022)

Article Physics, Fluids & Plasmas

Plasma physics and control studies planned in JT-60SA for ITER and DEMO operations and risk mitigation

M. Yoshida, G. Giruzzi, N. Aiba, J. F. Artaud, J. Ayllon-Guerola, L. Balbinot, O. Beeke, E. Belonohy, P. Bettini, W. Bin, A. Bierwage, T. Bolzonella, M. Bonotto, C. Boulbe, J. Buermans, M. Chernyshova, S. Coda, R. Coelho, S. Davis, C. Day, G. De Tommasi, M. Dibon, A. Ejiri, G. Falchetto, A. Fassina, B. Faugeras, L. Figini, M. Fukumoto, S. Futatani, K. Galazka, J. Garcia, M. Garcia-Munoz, L. Garzotti, L. Giacomelli, L. Giudicotti, S. Hall, N. Hayashi, C. Hoa, M. Honda, K. Hoshino, M. Iafrati, A. Iantchenko, S. Ide, S. Iio, R. Imazawa, S. Inoue, A. Isayama, E. Joffrin, K. Kamiya, Y. Ko, M. Kobayashi, T. Kobayashi, G. Kocsis, A. Kovacsik, T. Kurki-Suonio, B. Lacroix, P. Lang, Ph Lauber, A. Louzguiti, E. de la Luna, G. Marchiori, M. Mattei, A. Matsuyama, S. Mazzi, A. Mele, F. Michel, Y. Miyata, J. Morales, P. Moreau, A. Moro, T. Nakano, M. Nakata, E. Narita, R. Neu, S. Nicollet, M. Nocente, S. Nowak, F. P. Orsitto, V Ostuni, Y. Ohtani, N. Oyama, R. Pasqualotto, B. Pegourie, E. Perelli, L. Pigatto, C. Piccinni, A. Pironti, P. Platania, B. Ploeckl, D. Ricci, P. Roussel, G. Rubino, R. Sano, K. Sarkimaki, K. Shinohara, S. Soare, C. Sozzi, S. Sumida, T. Suzuki, Y. Suzuki, T. Szabolics, T. Szepesi, Y. Takase, M. Takech, N. Tamura, K. Tanaka, H. Tanaka, M. Tardocchi, A. Terakado, H. Tojo, T. Tokuzawa, A. Torre, N. Tsujii, H. Tsutsui, Y. Ueda, H. Urano, M. Valisa, M. Vallar, J. Vega, F. Villone, T. Wakatsuki, T. Wauters, M. Wischmeier, S. Yamoto, L. Zani

Summary: The JT-60SA project focuses on plasma controllability for scenario development and risk mitigation in ITER and investigating DEMO relevant regimes. Recent works on simulation studies have prepared for plasma physics and control experiments, contributing to ITER and DEMO.

PLASMA PHYSICS AND CONTROLLED FUSION (2022)

Article Nuclear Science & Technology

Irradiation effects in tungsten-From surface effects to bulk mechanical properties

J. Riesch, A. Feichtmayer, J. W. Coenen, B. Curzadd, H. Gietl, T. Hoeschen, A. Manhard, T. Schwarz-Selinger, R. Neu

Summary: Advanced materials, such as tungsten fibre-reinforced composites, are used to address issues with baseline materials in fusion reactors. High-energy ions are used to simulate the effects of neutron irradiation on the mechanical properties of these materials. Fine tungsten wire provides a means to study irradiation damage and can be used to predict the properties of bulk composite materials.

NUCLEAR MATERIALS AND ENERGY (2022)

Article Physics, Fluids & Plasmas

Overview of initial negative triangularity plasma studies on the ASDEX Upgrade tokamak

T. Happel, T. Puetterich, D. Told, M. Dunne, R. Fischer, J. Hobirk, R. M. McDermott, U. Plank, A. S. D. E. X. Upgrade Team ASDEX Upgrade Team

Summary: This study provides an overview of the results of negative triangularity (NT) studies conducted on the ASDEX Upgrade tokamak (AUG). The results show moderate values of triangularity and both favorable and unfavorable magnetic configurations. In unfavorable configuration, higher power thresholds are required to enter the high-confinement mode (H-mode). In favorable configuration, H-mode with type-I edge localized modes (ELMs) is observed. The study also investigates the influence of different heating methods on plasma confinement.

NUCLEAR FUSION (2023)

Article Nuclear Science & Technology

Pre-conceptual design of a PFC equipped with a W lattice armour for first wall limiters in the EU-DEMO fusion reactor

R. De Luca, P. Fanelli, D. Paoletti, C. Stefanini, A. von Mueller, A. Feichtmayer, F. Vivio, V. Belardi, G. Dose, G. De Sano, S. Roccella, G. Calabro, J. -H. You, R. Neu

Summary: Amongst the engineering challenges of power exhaust in DEMO and future reactors, an effective wall protection strategy is regarded as crucial. Sacrificial first wall limiters provided with innovative tungsten lattices are preferred as the last protection resource during extreme plasma events. Additive manufacturing was employed to realize samples for material characterization and testing.

FUSION ENGINEERING AND DESIGN (2023)

Article Materials Science, Multidisciplinary

Rate-controlling deformation mechanisms in drawn tungsten wires

Maximilian Fuhr, Till Hoeschen, Johann Riesch, Max Boleininger, Juergen Almanstoetter, Wolfgang Pantleon, Rudolf Neu

Summary: Through studying a series of potassium-doped tungsten wires, it was found that cold-worked tungsten materials can exhibit ductility even at low temperatures. Transient mechanical tests were conducted to determine the effective activation volumes and strain-rate sensitivities of the wires at room temperature. It was concluded that the ductility of drawn tungsten wires at low temperatures is attributed to microstructural and textural changes during the wire drawing process, rather than a change in the rate-controlling deformation mechanisms.

PHILOSOPHICAL MAGAZINE (2023)

Article Nuclear Science & Technology

Surface features of strongly heated bulk tungsten divertor plates at ASDEX Upgrade

V. Rohde, M. Balden, K. Hunger, I. Zammuto, A. Herrmann, R. Neu

Summary: Solid tungsten tiles in the ASDEX Upgrade divertor exhibit cracks parallel to surface and humps at the surface. These horizontal cracks, occurring for the first time, lead to protrusions on approximately 10% of the tiles. The location of these cracks coincides with the highest deposited energy, affecting thermal contact and causing recrystallization and grain growth.

NUCLEAR MATERIALS AND ENERGY (2023)

Article Nuclear Science & Technology

Investigations on cold spray tungsten/tantalum coatings for plasma facing applications

R. Neu, H. Maier, B. Boeswirth, S. Elgeti, H. Greuner, K. Hunger, J. Kondas, A. von Mueller

Summary: Cold gas spraying was investigated for the production of thick tungsten coatings for use in fusion devices. A systematic study using tungsten and tantalum powder mixtures was performed due to the brittle nature of tungsten. Coatings with negligible porosity and good adhesion were achieved using a 90 vol% tungsten mixture, resulting in a 70 vol% tungsten content in the coating. High heat flux experiments showed good performance under low steady-state loads, but cracks appeared during high power transients.

NUCLEAR MATERIALS AND ENERGY (2023)

Article Nuclear Science & Technology

Conceptual design of the next generation of W7-X divertor W-target elements

J. Boscary, G. Ehrke, P. Frosi, P. Junghanns, B. Koncar, B. Mendelevitch, D. Naujoks, R. Neu, M. Richou, L. Selan, J. Tretter, Z. Wang, J. H. You, K. Zhang

Summary: The Wendelstein 7-X stellarator will start operating in 2022 with an actively water cooled divertor using CFC NB31 tiles. Research activities, supported by EUROfusion, are being carried out to develop a metallic water cooled divertor for future installation. The first prototyping phase is being prepared through conceptual design.

FUSION ENGINEERING AND DESIGN (2023)

Article Nuclear Science & Technology

Parametric FE model for the thermal and hydraulic optimization of a Plasma Facing Component equipped with sacrificial lattice armours for First Wall limiter application in EU-DEMO fusion reactor

C. Stefanini, P. Fanelli, R. De Luca, D. Paoletti, F. Vivio, V. Belardi, S. Trupiano, G. Calabro, J. -H. You, R. Neu

Summary: In the EU DEMO reactor, components exposed to burning plasma are subjected to extreme conditions, which affect their lifespan and functionality. Researchers have developed a parametric model to identify the optimal component configurations that maximize the sacrificial limiter's effectiveness.

FUSION ENGINEERING AND DESIGN (2023)

Article Physics, Fluids & Plasmas

Experimental evidence of magnetic flux pumping in ASDEX upgrade

A. Burckhart, A. Bock, R. Fischer, T. Puetterich, J. Stober, S. Guenter, A. Gude, J. Hobirk, M. Hoelzl, V. Igochine, I. Krebs, M. Maraschek, M. Reisner, R. Schramm, H. Zohm, ASDEX Upgrade Team

Summary: In high-beta scenarios, the absence of sawteeth suggests the presence of an additional current redistribution mechanism beyond neoclassical current diffusion. Imaging diagnostics indicate the consistent behavior of q0 around 1 in the presence of a 1/1 mode, highlighting its potential role in current redistribution. Furthermore, it is shown that the mode's ability to modify central current and suppress sawteeth increases with plasma pressure. The advantages of the flux pumping scenario are also emphasized.

NUCLEAR FUSION (2023)

Article Materials Science, Multidisciplinary

Material and component developments for the DEMO divertor using fibre reinforcement and additive manufacturing

R. Neu, J. W. Coenen, B. Curzadd, H. Gietl, H. Greuner, T. Hoeschen, K. Hunger, R. Luerbke, Av Mueller, J. Riesch, G. Schlick, U. Siefken, E. Visca, Jh You

Summary: In the research on the European Fusion Roadmap, water-cooled divertor PFCs are planned to be used in the design of the first fusion demonstration power plant (DEMO) for reliable heat removal capability. The Max Planck Institute for Plasma Physics is focusing on the development and testing of composite materials based on tungsten and copper, with W fibres playing a central role in the investigations.

MATERIALS RESEARCH EXPRESS (2023)

Article Nuclear Science & Technology

Design and GLADIS testing of a liquid tin divertor module prior to exposure in ASDEX Upgrade

J. G. A. Scholte, M. Balden, B. Boeswirth, S. Elgeti, H. Greuner, A. Herrmann, K. Hunger, K. Krieger, P. Leitenstern, A. Manhard, R. Neu, R. C. van Schaik, V. Rohde, I. Zammuto, T. W. Morgan

Summary: Using liquid metals as plasma-facing components can extend the lifespan of the divertor, but the high atomic number of tin limits its use in the main plasma. Therefore, it is crucial to test this concept in a tokamak environment. This paper presents the design of a liquid tin module and its testing in a high heat flux device. The results show that the module is suitable for high heat fluxes.

NUCLEAR MATERIALS AND ENERGY (2023)

Article Nuclear Science & Technology

Tungsten based divertor development for Wendelstein 7-X

Joris Fellinger, M. Richou, G. Ehrke, M. Endler, F. Kunkel, D. Naujoks, Th. Kremeyer, A. Menzel-Barbara, Th. Sieber, J-F. Lobsien, R. Neu, J. Tretter, Z. Wang, J-H. You, H. Greuner, K. Hunger, P. Junghanns, O. Schneider, M. Wirtz, Th. Loewenhoff, A. Houben, A. Litnovsky, P-E. Fraysinnes, P. Emonot, S. Roccella, O. Widlund, B. Koncar, M. Tekavcic

Summary: Wendelstein 7-X, the world's largest superconducting stellarator, has started plasma experiments with a water-cooled plasma-facing wall in 2022, allowing for long pulse operation. Furthermore, a project is planned to develop a W based divertor to demonstrate plasma performance of a stellarator with low tritium retention.

NUCLEAR MATERIALS AND ENERGY (2023)

Article Nuclear Science & Technology

Performance of tungsten plasma facing components in the stellarator experiment W7-X: Recent results from the first OP2 campaign

Dirk Naujoks, Chandra-Prakash Dhard, Yuhe Feng, Yu Gao, Torsten Stange, Birger Buttenschoen, Sergey A. Bozhenkov, Sebastijan Brezinsek, Kai Jakob Brunner, Gabor Cseh, Andreas Dinklage, David Ennis, Joris Fellinger, Eric Flom, Dorothea Gradic, Eduard Grigore, Dirk Hartmann, Frederik Henke, Marcin Jakubowski, Amit Kharwandikar, Mikhail Khokhlov, Jens Knauer, Gabor Kocsis, Petra Kornejew, Maciej Krychowiak, Matej Mayer, Paul McNeely, Daniel Medina, Rudolf Neu, Kian Rahbarnia, Cristian Ruset, Norbert Rust, Peter Scholz, Thomas Sieber, Ivan Stepanov, Naoki Tamura, Erhui Wang, Thomas Wegner, Daihong Zhang

Summary: The transition to reactor-relevant materials for the plasma facing components is a crucial step to demonstrate the feasibility of the stellarator concept for future fusion reactors. Tungsten was used as the plasma-facing material in W7-X stellarator, and design changes were made to improve the overheating issue in the baffle area.

NUCLEAR MATERIALS AND ENERGY (2023)

暂无数据