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Journal articles on the topic 'Flux de chaleur au divertor'

Author: Grafiati

Published: 4 June 2021

Last updated: 8 June 2024

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1

Bougriou, Cherif. "Etude du Récupérateur de Chaleur Croisé à Tubes à Ailette." Journal of Renewable Energies 5, no. 1 (June 30, 2002): 59–74. http://dx.doi.org/10.54966/jreen.v5i1.887.

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Nous présentons une méthode de simulation et de calcul des récupérateurs de chaleur croisé (Air-Eau) à tubes ailetés. Ce modèle de calcul est validé par une approche expérimentale, en utilisant trois faisceaux de tubes (échangeurs industriels) en arrangement aligné et quinconcé. Le logiciel prédit les flux de chaleur échangés dans une fourchette de 10%. L'échangeur croisé contre-courant est le plus performant des échangeurs croisés. La configuration croisée simple est non rentable. Dans la plupart des cas, le flux de chaleur total échangé par un échangeur croisé contre-courant est environ de 10% supérieur au flux échangé dans un échangeur croisé cocourant. Un échangeur croisé à ailettes peut échanger cinq fois plus de chaleur qu'un échangeur à tubes lisses.

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2

Bougriou, Cherif. "Etude d’un Récupérateur de Chaleur Croisé à Tubes Lisses." Journal of Renewable Energies 2, no. 2 (December 31, 1999): 109–22. http://dx.doi.org/10.54966/jreen.v2i2.934.

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Nous présentons une méthode de simulation et de calcul des récupérateurs de chaleur croisé (Air-Eau) à tubes lisses. Ce modèle de calcul est validé par une approche expérimentale, en utilisant un faisceau de tubes (échangeur industriel) en arrangement quinconcé. Le logiciel prédit les flux de chaleur échangés dans une fourchette de 10%. L'échangeur croisé contre-courant est le plus performant des échangeurs croisés. La configuration croisé simple est non rentable. Dans la plupart des cas, le flux de chaleur total échangé par un échangeur croisé contre-courant est environ de 10% supérieur au flux échangé dans un échangeur croisé co-courant.

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3

Anthore, Anne, Sébastien Jézouin, François Parmentier, Ulf Gennser, and Frédéric Pierre. "Limite quantique du flux de chaleur." Reflets de la physique, no. 42 (December 2014): 16–19. http://dx.doi.org/10.1051/refdp/201442016.

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4

Aboubacry Mbodji, Oumou, Alassane Diene, Seydou Faye, Youssou Traore, Mamadou Babacar Ndiaye, Issa Diagne, and Gregoire Sissoko. "ETUDE DU TRANSFERT THERMIQUE EN REGIME DE MODULATION DE FREQUENCE A TRAVERS UN PANNEAU A BASE DE FIBRE DE BOIS: INFLUENCE DES PARAMETRES EXTERIEURS." International Journal of Advanced Research 9, no. 10 (October 31, 2021): 805–20. http://dx.doi.org/10.21474/ijar01/13613.

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Cette etude, propose levaluation du comportement thermique en regime dynamique frequentiel dun panneau a base fibre de bois. La resolution de lequation de continuite de la chaleur a produit les expressions theriques de la temperature et de la densite de flux de chaleur dans le panneau. Linfluence des parametres exterieurs a travers les coefficients dechanges thermiques sur les surfaces avant et arriere du panneau, ainsi que de la pulsation excitatrice sur la diffusion de chaleur est analysee.

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5

Ren, J., D. C. Donovan, J. G. Watkins, H. Q. Wang, C. Lasnier, T. Looby, J. Canik, et al. "Measurements of multiple heat flux components at the divertor target by using surface eroding thermocouples (invited)." Review of Scientific Instruments 93, no. 10 (October 1, 2022): 103541. http://dx.doi.org/10.1063/5.0101719.

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The Surface Eroding Thermocouple (SETC) is a robust diagnostic utilized in DIII-D to provide fast, edge-localized modes (ELMs) resolved heat flux measurements, in particular in geometric regions that are too shadowed for traditional infrared thermography. In order to further investigate the power dissipation in the divertor region, a combination of flush-mounted and recessed SETCs was developed to assess the effect on surface heating from non-charged particles at the divertor target. Utilizing the Divertor Materials Evaluation System sample exposure platform, the first demonstration of the feasibility of using this new method to distinguish between the heat flux from charged particles and that from neutrals and radiative heating was achieved. This paper details the process of using the combination of flush SETCs and recessed SETCs to measure the multiple heat flux components at the divertor target and further discusses how to determine two important ratios, α (ratio of heat flux from charged particles deposit on recessed SETC to that deposit on flush SETC) and β (ratio of heat flux from non-charged particles deposit on recessed SETC to that deposit on flush SETC), in the estimation of the heat flux from non-charged particle sources. Using a time dependent ratio α, it was found that ∼50% of the total incident heat flux is attributable to the non-charged particles in the fully detached open divertor in DIII-D. Finally, the new application of similar SETC diagnostics in the Small Angle Slot divertor with a V-like configuration and partial tungsten coated surface (SAS-VW) is also introduced.

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6

Tamene, Youcef, Said Abboudi, and Cherif Bougriou. "Simulation des transferts thermiques transitoires à travers un mur multicouche soumis à des conditions de flux solaire et de convection." Journal of Renewable Energies 12, no. 1 (October 26, 2023): 117–24. http://dx.doi.org/10.54966/jreen.v12i1.125.

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On propose une étude numérique, par différences finies, du transfert de chaleur dans un mur multicouche (à deux ou trois couches) soumis à une condition de rayonnement solaire sur le côté extérieur et prenant en compte les échanges de chaleur par convection sur ses deux faces. L’exploitation du code numérique est développée sur des cas relatifs au problème posé dans l’habitat. Les résultats numériques sont présentés sur des exemples de matériaux utilisés dans le domaine du bâtiment dans des conditions réelles de fonctionnement (flux solaire, pertes convectives, etc…). On analyse également, l’influence, sur le transfert de chaleur, de quelques paramètres clés du système comme le choix des matériaux, l’optimisation de leur épaisseur et également la nature variable du flux solaire. Une proposition optimale sera dégagée de cette étude en fonction des objectifs recherchés.

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7

Kolemen, E., S. L. Allen, B. D. Bray, M. E. Fenstermacher, D. A. Humphreys, A. W. Hyatt, C. J. Lasnier, et al. "Heat flux management via advanced magnetic divertor configurations and divertor detachment." Journal of Nuclear Materials 463 (August 2015): 1186–90. http://dx.doi.org/10.1016/j.jnucmat.2014.11.099.

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8

Wu, N., J. Cheng, H. L. Du, Z. H. Huang, L. W. Yan, W. C. Wang, K. Y. Yi, et al. "Effect of the E × B drift on the redistribution of the divertor particle flux in the HL-2A ECRH plasmas." Physics of Plasmas 30, no. 1 (January 2023): 012501. http://dx.doi.org/10.1063/5.0126491.

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Double-peaked distribution (DPD) of particle flux has only been observed on the outer divertor target in electron cyclotron resonance heating deuterium plasmas with [Formula: see text] toward the X-point in the HL-2A tokamak using high spatiotemporal Langmuir probe arrays. The experimental results demonstrate that the formation of the DPD is mainly due to the enhanced poloidal [Formula: see text] drift flow stimulated in the divertor region, which is dependent on the plasma density, heating power, and divertor structure. The experimental results are qualitatively consistent with the SOLPS simulation. The experiment also shows that the formation of the DPD might be related to the enhanced cross field transport in the far scrape-off layer. This experimental findings presented here reveal the crucial role played by the synergistic effect of poloidal E × B drift flow and the closed divertor structure in the redistribution of the particle flux, which provides a potential way for the control of high heat flux in future fusion devices.

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9

Kumpilov, D., R. Rodionov, A. Kovalev, Y. Kashchuk, D. Portnov, and S. Obudovsky. "Activation of ITER Divertor Neutron Flux Monitor." Journal of Instrumentation 14, no. 11 (November 20, 2019): C11019. http://dx.doi.org/10.1088/1748-0221/14/11/c11019.

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10

Castejón, F., J. L. Velasco, A. López-Fraguas, A. Tarancón, J. Guasp, F. Tabarés, M. A. Pedrosa, E. de la Cal, and M. A. Ochando. "Flux-expansion divertor studies in TJ-II." Nuclear Fusion 49, no. 8 (July 17, 2009): 085019. http://dx.doi.org/10.1088/0029-5515/49/8/085019.

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11

Soukhanovskii, V. A., R. E. Bell, A. Diallo, S. Gerhardt, S. Kaye, E. Kolemen, B. P. LeBlanc, et al. "Advanced divertor configurations with large flux expansion." Journal of Nuclear Materials 438 (July 2013): S96—S101. http://dx.doi.org/10.1016/j.jnucmat.2013.01.015.

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12

Fussmann, G., J. V. Hofmann, G. Janeschitz, and H. R. Yang. "Sputtering flux measurements in the ASDEX divertor." Nuclear Fusion 30, no. 11 (November 1, 1990): 2319–28. http://dx.doi.org/10.1088/0029-5515/30/11/009.

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13

Loiseau, Jean-Jacques, and Hugues Mounier. "Stabilisation de l'équation de la chaleur commandée en flux." ESAIM: Proceedings 5 (1998): 131–44. http://dx.doi.org/10.1051/proc:1998003.

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14

Nameche, T., and J. L. Vassel. "Bilan thermique sous climat tempéré des lagunes aérées et naturelles." Revue des sciences de l'eau 12, no. 1 (April 12, 2005): 65–91. http://dx.doi.org/10.7202/705344ar.

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Un modèle décrivant la température d'équilibre des lagunes a été développé, tenant compte des différents flux de chaleur que celles-ci échangent avec l'air et le sol environnant. Six composantes différentes ont été inclues dans le calcul de ce bilan thermique: radiation solaire, évaporation, convection, rayonnement atmosphérique, rayonnement de la surface du plan d'eau, échange via les parois en contact avec le sol. Le modèle ainsi obtenu a été testé avec efficacité sur deux lagunes aérées et une lagune naturelle situées sous climat tempéré ; sa précision sur l'estimation des températures d'équilibre étant de l'ordre de 0.7 °C. Des simulations en continu ont également pu être effectuées au moyen d'une variante dynamique, tenant compte de l'inertie thermique qu'entraîne le volume des bassins. Quelle que soit la saison envisagée, la principale forme d'apport de chaleur est représentée par la radiation solaire tandis que la dissipation d'énergie se partage entre les flux d'évaporation et la balance des deux flux de rayonnement. Les bassins échangeraient en moyenne plus de 250 W/m2 ; le maximum de transfert de chaleur correspondant au printemps et à la période estivale. Enfin, l'analyse de sensibilité du modèle nous a permis de mettre en évidence la contribution de chacun des termes intervenant dans le calcul de ce bilan thermique et de révéler sa dépendance vis-à-vis principalement de la température d'entrée, du rayonnement solaire et de la température de l'air.

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15

JIANG, Xinhao, and Youwen SUN. "FEQ: a new flux coordinates based equilibrium solver including both magnetic axis and separatrix." Plasma Science and Technology 24, no. 1 (December 8, 2021): 015105. http://dx.doi.org/10.1088/2058-6272/ac363e.

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Abstract Accurate tokamak plasma equilibrium solution in flux coordinates is crucial for many stability and transport studies. Different approaches for dealing with singularities in solving the nonlinear Grad–Shafranov (GS) equation in flux coordinates or also known as straight field line coordinates are proposed in this paper. The GS equation is solved by iterating the position of grids directly in flux coordinates, and hence, no additional errors are introduced due to mapping process for a convergent solution. The singularity at magnetic axis in flux coordinates is removed by using a novel coordinate transform technique. Different from other techniques previously developed, no assumption in boundary condition at magnetic axis is used. This is consistent with the fact that there is no physical boundary at the magnetic axis. A flux coordinate system with poloidal coordinate chosen as the geometric poloidal angle is proposed. It conquers the difficulty in no definition of poloidal coordinate in flux coordinates at separatrix because of the singularity at x-point(s) in a divertor configuration. It also simplifies the process for computing poloidal flux coordinate during the iteration for solving the nonlinear GS equation. Non-uniform grids can be applied in both radial and poloidal coordinates, which allows it to increase the spacial resolution near x-point(s) in a divertor configuration. Based on the model proposed in this paper, a new Flux coordinates based EQuilibrium solver (FEQ) in tokamaks is developed. The numerical solutions from this code agree well with both the analytic Solov’ev solution and the numerical one from the EFIT code for a divertor configuration in the EAST tokamak. This code can be applied for simulating different equilibria with prescribed shape, pressure and current profiles, i.e. including both limiter and divertor configurations, positive triangularity and negative triangularity, different β, arbitrary magnetic shear profile etc. It provides a powerful and convenient fixed-boundary inverse equilibrium solver including both magnetic axis and separatrix in the solution for tokamak researches.

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16

Dai, S. Y., D. F. Kong, V. S. Chan, L. Wang, Y. Feng, and D. Z. Wang. "EMC3–EIRENE simulations of neon impurity seeding effects on heat flux distribution on CFETR." Nuclear Fusion 62, no. 3 (March 1, 2022): 036019. http://dx.doi.org/10.1088/1741-4326/ac47b5.

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Abstract The numerical modelling of the heat flux distribution with neon impurity seeding on China fusion engineering test reactor has been performed by the three-dimensional (3D) edge transport code EMC3–EIRENE. The maximum heat flux on divertor targets is about 18 MW m−2 without impurity seeding under the input power of 200 MW entering into the scrape-off layer. In order to mitigate the heat loads below 10 MW m−2, neon impurity seeded at different poloidal positions has been investigated to understand the properties of impurity concentration and heat load distributions for a single toroidal injection location. The majority of the studied neon injections gives rise to a toroidally asymmetric profile of heat load deposition on the in- or out-board divertor targets. The heat loads cannot be reduced below 10 MW m−2 along the whole torus for a single toroidal injection location. In order to achieve the heat load mitigation (<10 MW m−2) along the entire torus, modelling of sole and simultaneous multi-toroidal neon injections near the in- and out-board strike points has been stimulated, which indicates that the simultaneous multi-toroidal neon injections show a better heat flux mitigation on both in- and out-board divertor targets. The maximum heat flux can be reduced below 7 MW m−2 on divertor targets for the studied scenarios of the simultaneous multi-toroidal neon injections.

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17

Punjabi, Alkesh. "A catastrophe-theory study of a two-chamber model for a tokamak scrape-off and divertor." Journal of Plasma Physics 42, no. 1 (August 1989): 59–74. http://dx.doi.org/10.1017/s0022377800014185.

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The two-chamber model (TCM) of Singer and Langer is employed to study the plasma transport in the scrape-off and divertor regions of a tokamak. Collisiondominated transport along the field lines is considered, with a. geometric-mean flux-limited expression for parallel electron heat conduction. An analytic method for the catastrophe-theory study of the TCM is developed. Maxwell convention for the catastrophes is adopted. Catastrophes occur when the energy flux entering the divertor chamber from the main plasma scrape-off, the recycling coefficient and the ratio of electron temperatures in the scape-off to that in the divertor exceed some threshold values. It is seen that the behaviour of the plasma during these catastrophes is in qualitative agreement with the experimentally observed features of the plasma during the H-mode transition.

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18

Leonard, A. W. "Divertor Heat Flux Control Research on DIII-D." Fusion Science and Technology 48, no. 2 (October 2005): 1083–95. http://dx.doi.org/10.13182/fst05-a1062.

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19

Rensink, M. E., and T. D. Rognlien. "Plasma Heat-Flux Dispersal for ACT1 Divertor Configurations." Fusion Science and Technology 67, no. 1 (January 2015): 125–41. http://dx.doi.org/10.13182/fst14-800.

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20

Olekhnovitch, Andrei, Alberto Teyssedou, and Peter Tye. "Nouvelle représentation du flux de chaleur critique de type assèchement." International Journal of Thermal Sciences 39, no. 1 (January 2000): 63–73. http://dx.doi.org/10.1016/s1290-0729(00)00191-4.

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21

Łopata, Stanisław. "Détermination du flux de chaleur instationnaire sur les surfaces cylindriques." International Journal of Heat and Mass Transfer 33, no. 2 (February 1990): 349–57. http://dx.doi.org/10.1016/0017-9310(90)90104-3.

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22

Battaglia, Jean-Luc, Ludivine Puigsegur, Haj El Moussami, Jean-Pierre Nadeau, and Jean-Christophe Batsale. "Méthode d'estimation du flux de chaleur dans les outils d'usinage." Mécanique & Industries 5, no. 1 (January 2004): 49–60. http://dx.doi.org/10.1051/meca:2004006.

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23

Boukrouche, Abdelhani. "Estimation du Flux de Production de Chaleur d’une Réaction Chimique." Journal of Renewable Energies 2, no. 1 (June 30, 1999): 27–37. http://dx.doi.org/10.54966/jreen.v2i1.921.

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Le but de la calorimétrie est mesuré l’énergie dégagée par une réaction chimique. De manière générale, la puissance dégagée par une réaction est calculable à partir de la modélisation dynamique du bilan thermique de l’installation. A partir de la connaissance de cette puissance, on remonte à l’énergie par intégration de la puissance calorifique par rapport au temps. Afin de déterminer cette puissance, l’approche couramment utilisée est le calcul numérique (lissage) permettant une bonne approximation. Dans le travail présenté ici, une approche différente pour la détermination de cette quantité est proposée. En effet, à partir de la modélisation dynamique de l’installation, cette estimation peut être considérée comme une reconstruction du flux de la production de chaleur par la réaction, ce signal étant la puissance dégagée par la réaction. Cette technique est plus connue sous le nom de déconvolution.

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24

In, Yongkyoon, H. H. Lee, G. Y. Park, Y. M. Jeon, M. Kim, K. Kim, J. K. Park, et al. "Toward holistic understanding of the ITER-like resonant magnetic perturbation (RMP) ELM control on KSTAR." Nuclear Fusion 62, no. 6 (April 5, 2022): 066014. http://dx.doi.org/10.1088/1741-4326/ac5ad1.

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Abstract KSTAR has clarified a set of unresolved 3D physics issues utilizing the ITER-like in-vessel, three-row, resonant magnetic perturbation (RMP) configurations. Since RMP-driven, edge-localized-modes (ELMs)-crash control elevates the divertor heat flux peak through its impact on edge plasma parameters and transport, a series of intentionally misaligned RMP configurations (IMCs) have been explored to investigate the relationship between RMP ELM control and divertor heat fluxes, while searching for an ideal IMC that could be favorable in both aspects. First of all, the contrasting influence of kink vs anti-kink phasing on the ELM-crash suppression has been articulated, demonstrating the synergistic benefit of ‘kink’ phasing on ELM-crash-suppression. On the other hand, the three-row IMC in the anti-kink phasing becomes more insensitive to the ELM-crashes at the sub-marginal level of RMP, consistent with theory. Meanwhile, the divertor ‘wetted’ area of ELM-crash-suppression gets narrower than that of ELM-crash-mitigation, suggesting that ELM-crash-mitigation remains advantageous over ELM-crash-suppression in terms of time-averaged divertor thermal loading. In comparison, based on a set of two-row IMCs, no evidence of divertor heat flux broadening was found during ELM-crash-suppression, supporting a hypothesis that the dispersal of the divertor heat flux in three-row IMCs cannot be driven by helically structured two-row RMPs alone. Among ITER-like three-rows, lower two-row RMPs have been found to be much more effective in suppressing the ELM-crashes than upper two-row RMPs. Although it is quite preliminary, the up/down asymmetric dependence of RMP coupling may be generically attributed to lower-single-null plasmas. Such a holistic understanding of RMP-driven, ELM-crash-control in KSTAR is expected not only to elucidate various subtle points in the vicinity of ELM-crash-suppression, but also to clarify the relevant divertor thermal loading issues for ITER and beyond.

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25

Addab, Y., M. Richou, M. Ramaniraka, N. Vignal, E. Visca, G. Dose, S. Roccella, H. Greuner, M. Missirlian, and J. H. You. "Typology of defects in DEMO divertor target mockups." Physica Scripta 96, no. 12 (November 24, 2021): 124065. http://dx.doi.org/10.1088/1402-4896/ac3875.

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Abstract We analyzed data from ultrasonic testing and infrared thermography non-destructive examinations performed on a subset of 25 small scale water-cooled target mockups of four target designs developed in the 2nd R&D phase of WPDIV. Examinations were performed before high heat flux tests for the 25 mockups and after high heat flux tests for 18 of them. The detected manufacturing defects are various in size and location. Widths of defects range from 0.2 to 12 mm, which is the entire block width. Angular sizes of defects range from few degrees to 360°. Defects having an angular size less than 50° or a width less than 4 mm are likely to be missed by infrared thermography examinations. After high heat flux tests at 20 MW m−2 up to 500 cycles, we noticed no significant evolution of pre-existing defects.

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26

Lee, Kim, Moon, Lim, and Cho. "Heat-Absorbing Capacity of High-Heat-Flux Components in Nuclear Fusion Reactors." Energies 12, no. 19 (October 3, 2019): 3771. http://dx.doi.org/10.3390/en12193771.

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Nuclear fusion energy is a solution to the substitution of fossil fuels and the global energy deficit. However, among the several problems encountered for realizing a nuclear fusion reactor, the divertor presents difficulties due to the tremendous heat flux (~10 MW/m2) from high-temperature plasma. Also, neutrons produce additional heat (~17.5 MW/m3) from collisions with the materials’ atoms. This may lead to unexpected effects such as thermal failure. Thus, a comprehensive investigation on the divertor module is needed to determine the heat-absorbing capacity of the divertor module so to maintain the effect of incident heat flux. In this study, using an analytical approach and a simulation, the quantitative effect of heat generation on the thermophysical behavior, such as temperature and thermal stress, was analyzed while maintaining the incident heat flux. Then, a correlated equation was derived from the thermal design criteria, namely, the maximum thimble temperature and the safety factor at the vulnerable point. Finally, on the basis of the thermal design criteria, the heat-absorbing capacity of a nuclear fusion reactor in operating conditions was determined. This study contributes to the understanding of the divertor’s effects in nuclear fusion reactors for high-heat-flux and high-temperature applications.

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27

Xu, G. S., L. Wang, D. M. Yao, G. Z. Jia, C. F. Sang, X. J. Liu, Y. P. Chen, et al. "Physics design of new lower tungsten divertor for long-pulse high-power operations in EAST." Nuclear Fusion 61, no. 12 (November 24, 2021): 126070. http://dx.doi.org/10.1088/1741-4326/ac3297.

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Abstract A new lower tungsten divertor has been developed and installed in the EAST superconducting tokamak to replace the previous graphite divertor with power handling capability increasing from <2 MW m−2 to ∼10 MW m−2, aiming at achieving long-pulse H-mode operations in a full metal wall environment with the steady-state divertor heat flux of ∼10 MW m−2. A new divertor concept, ‘corner slot’ (CS) divertor, has been employed. By using the ‘corner effect’, a strongly dissipative divertor with the local buildup of high neutral pressure near the corner can be achieved, so that stable detachment can be maintained across the entire outer target plate with a relatively lower impurity seeding rate, at a separatrix density compatible with advanced steady-state core scenarios. These are essential for achieving efficient current drive with low-hybrid waves, a low core impurity concentration and thus a low loop voltage for fully non-inductive long-pulse operations. Compared with the highly closed small-angle-slot divertor in DIII-D, the new divertor in EAST exhibits the following merits: (1) a much simpler geometry with integral cassette body structure, combining vertical and horizontal target plates, which are more suitable for actively water-cooled W/Cu plasma facing components, facilitating installation precision control for minimizing surface misalignment, achieving high engineering reliability and lowering the capital cost as well; (2) it has much greater flexibility in magnetic configurations, allowing for the position of the outer strike point on either vertical or horizontal target plates to accommodate a relatively wide triangularity range, δ l = 0.4–0.6, thus enabling to explore various advanced scenarios. A water-cooled copper in-vessel coil has been installed under the dome. Five supersonic molecular beam injection systems have been mounted in the divertor to achieve faster and more precise feedback control of the gas injection rate. Furthermore, this new divertor allows for double null divertor operation and slowly sweeping the outer strike point across the horizontal and vertical target plates to spread the heat flux for long-pulse operations. Preliminary experimental results demonstrate the ‘corner effect’ and are in good agreement with simulations using SOLPS-ITER code including drifts. The EAST new divertor provides a test-bed for the closed divertor concept to achieve steady-state detachment operation at high power. Next step, a more closed divertor, ‘sharp-cornered slot’ divertor, building upon the current CS divertor concept, has been proposed as a candidate for the EAST upper divertor upgrade.

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28

Lukes, S., J. Horacek, V. Veselovsky, P. Vondracek, D. Sestak, J. Adamek, V. Weinzettl, and I. Duran. "Conceptual design of reciprocating probes and material-testing manipulator for tokamak COMPASS Upgrade." Journal of Instrumentation 17, no. 02 (February 1, 2022): C02007. http://dx.doi.org/10.1088/1748-0221/17/02/c02007.

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Abstract Three new in-vessel manipulators are designed and built for the new COMPASS Upgrade tokamak with uniquely high vessel temperature (250–500 °C) and heat flux density (perpendicular to divertor surface q ⊥ ∼ 80 MW/m2 and q ∥ ∼ GW/m2 at separatrix), which challenges the edge plasma diagnostics. Here we show their detailed engineering designs supported by heat conduction and mechanical models. Deep reciprocation of electrostatic probes near the separatrix should be possible by optimizing older concepts in (a) the head and probe geometry, (b) strongly increasing the deceleration up to 100× gravity by springs and strengthening the manipulator mechanical structure. One reciprocates close to the region of edge plasma influx (the outer midplane), the other at the plasma sink (between the outer divertor strike point and X-point), for studying the plasma divertor (impurity-seeded) detachment and liquid metal vapor transport. Both probe heads are equipped with a set of ball-pen and Langmuir probes, measuring reliably and extremely fast (10−6 s) local (1 mm resolution) plasma potential, density, electron temperature and heat flux and even ion temperature with 10−5 s resolution. The divertor manipulator (without reciprocation) will place various material test targets at the outer divertor. Unique will be its capability to increase 15× the surface heat flux with respect to the surrounding tungsten tiles just by controllable surface inclination of the test targets. We plan to test liquid metal targets where such inclined surface was found critical to achieve the desired mode with lithium vapor shielding. Even in the conservative expected performance of COMPASS Upgrade, we predict to reach and survive the EU DEMO relevant heat fluxes.

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29

Punjabi, Alkes, Arun Verma, and Allen Boozer. "The simple map for a single-null divertor tokamak." Journal of Plasma Physics 56, no. 3 (December 1996): 569–603. http://dx.doi.org/10.1017/s0022377800019474.

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We present the simple map for a single-null divertor tokamak. The simple map is an area-preserving map based on the idea that magnetic field lines are a single-degree- of-freedom time-dependent Hamiltonian system, and that the basic features of such systems near the X-point are generic. We obtain the properties of this map and the resulting footprints of field lines on the divertor plate. These include the width of the stochastic layer, the edge safety factor, the area of the footprint and the amount of magnetic flux diverted. We give the safety factor profile, the average and median values of strike angles, lengths and the Liapunov exponents. We describe how the effects of magnetic perturbations can be included in the simple map. We show how the map can be applied to the problem of the determination of heat flux on the divertor plate in tokamaks.

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WANG, Min, Qingmei XIAO, Xiaogang WANG, and Daoyuan LIU. "Numerical studies of the influence of seeding locations on D-SOL plasmas in EAST." Plasma Science and Technology 24, no. 1 (November 22, 2021): 015101. http://dx.doi.org/10.1088/2058-6272/ac320f.

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Abstract Impurity seeding has been found effective for divertor detachment operations and the seeding location plays a key role in this process. In this work, we use the fluid code SOLPS-ITER to study the influence of seeding locations on divertor and scrape-off layer (D-SOL) plasmas in Experimental Advanced Superconducting Tokamak (EAST) with neon seeding. Simulation results indicate that the neon is a highly effective impurity in mitigating the heat flux and electron temperature peaks on the target of the divertor and achieving the partial detachment on both inner and outer targets. Further, by comparing results of the seeding at the private-flux region (PFR) plate (called ‘TP’ location) and the outer target (called ‘XP’ location), we find that the impurity density and power radiation for TP case are higher in core and upstream regions and lower in the divertor region than that for seeding at the XP, and the difference becomes more and more obvious as the seeding rate increases. It clearly demonstrates that the seeding at the XP location is more appropriate than at the TP location, especially in high seeding rate conditions.

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31

Si, Hang, Rui Ding, Ilya Senichenkov, Vladimir Rozhansky, Pavel Molchanov, Xiaoju Liu, Guozhang Jia, et al. "SOLPS-ITER simulations of high power exhaust for CFETR divertor with full drifts." Nuclear Fusion 62, no. 2 (February 1, 2022): 026031. http://dx.doi.org/10.1088/1741-4326/ac3f4b.

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Abstract One of the major challenges for the Gigawatt-class Chinese Fusion Engineering Testing Reactor (CFETR) is to efficiently handle huge power fluxes on plasma-facing components , especially the divertor targets. This work investigates the effects of two candidate radiation impurity species, argon (Ar) and neon (Ne), with two different divertor geometries (baseline and long leg divertor geometry) on the reduction of steady-state power load to divertor targets in CFETR by using the SOLPS-ITER code package with full drifts and kinetic description of neutrals. The modeling results show clearly that increasing the seeding rate of Ar or Ne with fixed fueling gas D2 injection rate reduces the target electron temperature and heat flux density for the baseline divertor geometry, which can be reduced further by higher D2 injection rate. With a high impurity seeding rate, partial detachment with steady-state power load at the divertor target below the engineering limit of 10 MW m−2 is demonstrated. In addition, the radiation efficiency for Ar is better than that for Ne. Increasing the divertor leg length reduces the electron temperature and heat load at the targets. This modeling, therefore, suggests that a long leg divertor design with Ar seeding impurity is appropriate to meet the CFETR divertor requirements.

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32

EZATO, Koichiro, Masaki TANIGUCHI, Kazuyoshi SATO, Satoshi SUZUKI, and Masato AKIBA. "Development of high heat flux component for ITER divertor." Proceedings of the National Symposium on Power and Energy Systems 2002.8 (2002): 175–80. http://dx.doi.org/10.1299/jsmepes.2002.8.175.

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33

Gaspar, J., Y. Corre, M. Firdaouss, J.-L. Gardarein, D. Guilhem, M. Houry, C. Le Niliot, M. Missirlian, C. Pocheau, and F. Rigollet. "Heat Flux estimation in WEST divertor with embedded thermocouples." Journal of Physics: Conference Series 745 (September 2016): 032091. http://dx.doi.org/10.1088/1742-6596/745/3/032091.

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34

Suzuki, Satoshi, Masato Akiba, Masanori Araki, Kazuyoshi Satoh, Kenji Yokoyama, and Masayuki Dairaku. "High heat flux experiments of saddle type divertor module." Journal of Nuclear Materials 212-215 (September 1994): 1365–69. http://dx.doi.org/10.1016/0022-3115(94)91052-9.

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35

Soukhanovskii, V. A., R. Maingi, C. E. Bush, R. Raman, R. E. Bell, R. Kaita, H. W. Kugel, et al. "Divertor heat flux reduction and detachment experiments in NSTX." Journal of Nuclear Materials 363-365 (June 2007): 432–36. http://dx.doi.org/10.1016/j.jnucmat.2007.01.075.

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36

Li, Xiangyu, Guanghuai Wang, Yun Guo, and Songwei Li. "Critical heat flux analysis of divertor cooling flow channel in fusion reactor with CFD method." Thermal Science, no. 00 (2021): 203. http://dx.doi.org/10.2298/tsci210216203l.

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Situated at the bottom of the vacuum vessel, the divertor extracts heat and ash produced by the fusion reaction, minimizes plasma contamination, and protects the surrounding walls from thermal and neutronic loads. The vertical targets of divertor are designed to be able for up to 20 MW/m2 high heat flux. It is a great ordeal for both the material performance and the cooling ability. Critical heat flux (CHF) margin is very crucial during the design of divertor. ANSYS FLUENT is used in this paper to predict the CHF on a monoblock structure with a twisted tape inside the tube. Numerical results are validated with the corresponding sets of experimental results. In this paper, CFD method used to predict CHF of divertor cooling channel was first introduced. On the other hand, influence of inlet subcooling on CHF is studied in detail. The inlet subcooling affect the CHF much complicated for the single- side heated and swirl flow channel. Whether the influencing trend or the locations of CHF occurrence are different under different inlet subcooling. The derivations between the simulation and experimental results were no more than 32%. This study proves the CFD tools can provide efficient help on the understanding of the CHF phenomenon of complex construction.

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37

Messager, Roselyne. "III. Allemagne - "Des communes chefs d'entreprises. Les réseaux de chaleur en Allemagne"." Cahier / Groupe Réseaux 2, no. 6 (1986): 62–63. http://dx.doi.org/10.3406/flux.1986.1092.

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38

Ermakov, N. V., N. S. Zhiltsov, G. S. Kurskiev, E. E. Mukhin, S. Yu Tolstyakov, E. E. Tkachenko, V. A. Solovey, et al. "Divertor Thomson Scattering on Globus-M2." Физика плазмы 49, no. 12 (December 1, 2023): 1271–81. http://dx.doi.org/10.31857/s036729212360098x.

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We present the first Thomson scattering (TS) measurements of electron temperature and densityin the lower divertor of the Globus-M2 tokamak. The divertor TS diagnostics is designed for local measurementsof the Te(z, t) in the range of 1–100 eV and ne(z, t) in the range of m–3. Parameters of theprobing Nd:YAG laser are as follows 1064 nm/2 J/100 Hz/3 ns. The probing chord is launched vertically atR = 24 cm and covers areas of the inner leg, vicinity of separatrix and private flux region. Along probing chordof 110 mm, 9 spatial points were realized. Advanced filter polychromators were used to analyze Thomsonscattering spectra.

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39

Takherist, D., and A. Lesquer. "Mise en évidence d'importantes variations régionales du flux de chaleur en Algérie." Canadian Journal of Earth Sciences 26, no. 4 (April 1, 1989): 615–26. http://dx.doi.org/10.1139/e89-053.

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Evaluation of heat flow in 230 oil wells, using temperature measurements (bottom-hole temperature and temperature of fluids in drill stem test) and various rock-porosity data, reveals a high heat-flow average (82 ± 19 mW∙m−2) associated with the Algerian Sahara basins.The isopleth map exhibits significant regional variations overprinted by short-wavelength anomalies that, in general, are related to the local geological structure.On a regional scale, we observe an essentially north–south zonation that is not directly related to the major structural units, except for the northern alpine domain. The southern area, at the border of the Hoggar Precambrian basement, is characterized by very high heat-flow values (90–130 mW∙m−2). The anomalies define a major axis, generally east–west, which seems to affect the northern part of the African plate, from the Canaries to Libya. Locally, some relationships with extensional Miocene–Pliocene–Quaternary volcanism suggest an association with recent mantle thermal events. [Journal Translation]

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40

Ren, J., D. C. Donovan, J. G. Watkins, H. Q. Wang, D. M. Thomas, and R. Boivin. "Experimental observation of heat flux mitigation during divertor detachment in the DIII-D small angle slot divertor." Nuclear Materials and Energy 26 (March 2021): 100887. http://dx.doi.org/10.1016/j.nme.2020.100887.

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41

OIKAWA, Dai, Noriyasu OHNO, Shin KAJITA, Makoto TAKAGI, Suguru MASUZAKI, Masayuki TOKITANI, and Kazuhito ASANO. "Thermionic Energy Converter System Using Heat Flux in Divertor Region." Plasma and Fusion Research 7 (2012): 1405050. http://dx.doi.org/10.1585/pfr.7.1405050.

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42

Soukhanovskii, V. A., R. Maingi, D. A. Gates, J. E. Menard, S. F. Paul, R. Raman, A. L. Roquemore, et al. "Divertor heat flux mitigation in the National Spherical Torus Experiment." Physics of Plasmas 16, no. 2 (February 2009): 022501. http://dx.doi.org/10.1063/1.3068170.

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43

Schmid, K. "Beryllium flux distribution and layer deposition in the ITER divertor." Nuclear Fusion 48, no. 10 (September 10, 2008): 105004. http://dx.doi.org/10.1088/0029-5515/48/10/105004.

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44

Herrmann, A., C. J. Fuchs, V. Rohde, and M. Weinlich. "Heat flux distribution in the divertor-II of ASDEX Upgrade." Journal of Nuclear Materials 266-269 (March 1999): 291–95. http://dx.doi.org/10.1016/s0022-3115(98)00531-5.

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45

Deschka, S., A. Cardella, J. Linke, M. Lochter, and H. Nickel. "High heat flux performance of actively cooled divertor mock-ups." Journal of Nuclear Materials 203, no. 1 (July 1993): 67–72. http://dx.doi.org/10.1016/0022-3115(93)90431-w.

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46

Yan, Longwen, Jinming Gao, Xianggan Miao, Zhihui Huang, Na Wu, Wenjin Chen, Ting Wu, et al. "Scaling Laws of Heat Flux Width in HL-2A Closed Divertor Tokamak." Chinese Physics Letters, October 13, 2022. http://dx.doi.org/10.1088/0256-307x/39/11/115202.

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Abstract The scaling law of the divertor heat flux width is one of the key topics of magnetic confinement fusion, which is almost inversely proportional to the poloidal magnetic field on some opened divertor tokamaks. This paper focuses on the scaling laws of the closed divertor heat flux width in the HL-2A tokamak under different discharge conditions, such as the Ohmic, L- and H-modes. The results indicate that there are basic similarities of the scaling laws of the heat flux width between the opened and closed divertors. However, a larger spreading width in the private flux region was found, which is relevant to a small expansion factor of the magnetic flux in the closed divertor.

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47

De Oliveira, Hugo, Christian Theiler, Olivier Février, Holger Reimerdes, Basil P. Duval, Cedric Kar-Wai Tsui, Sophie Gorno, Diego Sales de Oliveira, and Artur Perek. "New insights on divertor parallel flows, ExB drifts, and fluctuations from in situ, two-dimensional probe measurement in the Tokamak à Configuration Variable." Nuclear Fusion, July 21, 2022. http://dx.doi.org/10.1088/1741-4326/ac82fd.

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Abstract In-situ, two-dimensional (2D) Langmuir probe measurements across a large part of the TCV outer divertor are reported in L-mode discharges with and without divertor baffles. This provides detailed insights into time averaged profiles, particle fluxes, and fluctuation behavior in different divertor regimes. The presence of the baffles is shown to substantially increase the divertor neutral pressure for a given upstream density and to facilitate the access to detachment, an effect that increases with plasma current. The detailed, 2D probe measurements allow for a divertor particle balance, including ion flux contributions from parallel flows and ExB drifts. The poloidal flux contribution from the latter is often comparable or even larger than the former, and the divertor parallel flow direction reverses in some conditions, pointing away from the target. In most conditions, the integrated particle flux at the outer target can be predominantly ascribed to ionization along the outer divertor leg, consistent with a closed-box approximation of the divertor. The exception is a strongly detached divertor, achieved here only with baffles, where the total poloidal ion flux even decreases towards the outer target, indicative of significant plasma recombination. The most striking observation from relative density fluctuation measurements along the outer divertor leg is the transition from poloidally uniform fluctuation levels in attached conditions to fluctuations strongly peaking near the X-point when approaching detachment.

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48

Alam, Ayesha, Shahab Ud-Din Khan, Muhammad Abdullah, Riaz Khan, Muhammad Ilyas, Khurram Saleem Chaudri, Ahmad Ali, et al. "Optimization of divertor design for Pakistan spherical tokamak." Kerntechnik, June 7, 2023. http://dx.doi.org/10.1515/kern-2022-0105.

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Abstract Handling the power deposition, reducing erosion effects, and plasma configuration are the key factors in the design of a divertor. The design of Pakistan Spherical Tokamak (PST) is based on double-null divertor configuration with actively cooled graphite targets at outer/inner strike point and peak heat flux range capacity of 0.1–0.3 MW/m2. The configuration of PST divertor module is designed with mock-up (used flat type tiles on baffles and dome) and cassette (support PFC and cooling channels) technology. Helium-cooled stage and water-cooled stage are two options for divertor. Therefore, one part of this research is focused on water-cooling system for the divertor. This paper presents the divertor design for PST with cooling channel and material analysis of the divertor, which is carried out in three phases. In the first phase, the plasma edge temperature, density, particle velocity, input power, heat flux, and surface temperature are estimated. In second phase, physics and engineering design of divertor system has been performed. In the third phase, COMSOL simulation has been performed to analyses the material properties, surface temperature rise (∆T °C) at stable heat flux, and thermal hydraulic system for the divertor. It is found from the analysis that the specific heat flux of 0.3 MW/m2 up to 3 s is the safe zone limit. The R & D work ratifies that manufacturing and installation processes are plausible for the proposed divertor design. This design is able to meet the requirement of PST. However, increasing time or specific heat flux beyond these limits would require redesigning of the cooling channel.

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49

Kuang, A. Q., S. Ballinger, D. Brunner, J. Canik, A. J. Creely, T. Gray, M. Greenwald, et al. "Divertor heat flux challenge and mitigation in SPARC." Journal of Plasma Physics 86, no. 5 (September 29, 2020). http://dx.doi.org/10.1017/s0022377820001117.

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Owing to its high magnetic field, high power, and compact size, the SPARC experiment will operate with divertor conditions at or above those expected in reactor-class tokamaks. Power exhaust at this scale remains one of the key challenges for practical fusion energy. Based on empirical scalings, the peak unmitigated divertor parallel heat flux is projected to be greater than 10 GW m−2. This is nearly an order of magnitude higher than has been demonstrated to date. Furthermore, the divertor parallel Edge-Localized Mode (ELM) energy fluence projections (~11–34 MJ m−2) are comparable with those for ITER. However, the relatively short pulse length (~25 s pulse, with a ~10 s flat top) provides the opportunity to consider mitigation schemes unsuited to long-pulse devices including ITER and reactors. The baseline scenario for SPARC employs a ~1 Hz strike point sweep to spread the heat flux over a large divertor target surface area to keep tile surface temperatures within tolerable levels without the use of active divertor cooling systems. In addition, SPARC operation presents a unique opportunity to study divertor heat exhaust mitigation at reactor-level plasma densities and power fluxes. Not only will SPARC test the limits of current experimental scalings and serve for benchmarking theoretical models in reactor regimes, it is also being designed to enable the assessment of long-legged and X-point target advanced divertor magnetic configurations. Experimental results from SPARC will be crucial to reducing risk for a fusion pilot plant divertor design.

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Long, Fei Fei, Tao Zhang, Tingfeng Ming, Xiaoju Liu, Lingyi Meng, MingFu Wu, Bang Li, et al. "Impact of coherent mode on divertor particle and heat flux in a type I ELMy H mode plasma on EAST tokamak." Nuclear Fusion, July 5, 2022. http://dx.doi.org/10.1088/1741-4326/ac7e5c.

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Abstract The paper investigates the effect of pedestal turbulence, i.e., coherent mode (CM), on the divertor total particle flux, the particle flux distribution and heat flux distribution, and their decay lengths in the SOL region on EAST tokamak. The experimental evidence indicates a strong coherence between the pedestal CM and the divertor particle flux fluctuation, which implies that the pedestal CM can affect the divertor plasma behavior. The increase of the particle flux decay length(λjs) correlates with the density radial decay length (λn,SOL) in the SOL region where the λn,SOL is largely affected by the change of pedestal CM amplitude. A quantitative statistical analysis shows that the divertor total particle flux and λjs in the SOL region increase with increasing amplitude of the electron density fluctuation and the electron temperature fluctuation induced by the pedestal CM. The temporal decay process of the total particle flux is interrupted by the appearance of CM at the pedestal. Meanwhile, the spatial distributions of both the particle and heat flux are enhanced when the pedestal CM appears, which are observed in both the upper single null (USN) and lower single null (LSN) configurations.

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