43 results on '"Kembleton, R."'
Search Results
2. Overview of European efforts and advances in Stellarator power plant studies
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Warmer, Felix, Alguacil, J., Biek, D., Bogaarts, T., Bongiovì, G., Bykov, V., Catalán, J.P., Duligal, R.K., Fernández-Berceruelo, I., Giambrone, S., Hume, C., Hrecinuc, M., Kembleton, R., Lion, J., Lyytinen, T., Noguerón Valiente, J.A., Palermo, I., Queral, V., Rapisarda, D., Rutten, W.J., Sanchis, L., Sarasola, X., Sedlak, K., Snicker, A., Sosa, D., and Urgorri, F.R.
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- 2024
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3. Technological features of a commercial fusion power plant, and the gap from DEMO
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Kembleton, R.
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- 2023
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4. Benefits and Challenges of Advanced Divertor Configurations in DEMO
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Kembleton, R., Siccinio, M., Maviglia, F., and Militello, F.
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- 2022
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5. EU-DEMO design space exploration and design drivers
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Kembleton, R., Morris, J., Siccinio, M., and Maviglia, F.
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- 2022
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6. Prospective research and development for fusion commercialisation
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Kembleton, R. and Bustreo, C.
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- 2022
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7. Development of the plasma scenario for EU-DEMO: Status and plans
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Siccinio, M., Graves, J.P., Kembleton, R., Lux, H., Maviglia, F., Morris, A.W., Morris, J., and Zohm, H.
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- 2022
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- View/download PDF
8. Design and feasibility of breeding blanket vertical segment-based architecture
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Chauvin, D., Berry, T., Chuilon, B., Budden, S., Colling, B., Crofts, O., Federici, G., Flynn, E., Gliss, C., Ha, S., Jackson, C., Keech, G., Keep, J., Kembleton, R., Leong, W., Loving, A., Maisonnier, D., Mathew, G., Organ, E., Shaw, C., Spagnuolo, A, Waldon, C., and Wilde, A.
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- 2021
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9. 'PROCESS': a systems code for fusion power plants - Part 2:Engineering
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Kovari, M, Fox, F., Harrington, C., Kembleton, R., Knight, P., Lux, H., and Morris, J.
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Physics - Instrumentation and Detectors ,Physics - Plasma Physics - Abstract
PROCESS is a reactor systems code - it assesses the engineering and economic viability of a hypothetical fusion power station using simple models of all parts of a reactor system. PROCESS allows the user to choose which constraints to impose and which to ignore, so when evaluating the results it is vital to study the list of constraints used. New algorithms submitted by collaborators can be incorporated - for example safety, first wall erosion, and fatigue life will be crucial and are not yet taken into account. This paper describes algorithms relating to the engineering aspects of the plant. The toroidal field (TF) coils and the central solenoid are assumed by default to be wound from niobium-tin superconductor with the same properties as the ITER conductors. The winding temperature and induced voltage during a quench provide a limit on the current density in the TF coils. Upper limits are placed on the stresses in the structural materials of the TF coil, using a simple two-layer model of the inboard leg of the coil. The thermal efficiency of the plant can be estimated using the maximum coolant temperature, and the capacity factor is derived from estimates of the planned and unplanned downtime, and the duty cycle if the reactor is pulsed. An example of a pulsed power plant is given., Comment: 22 pages, 13 figures
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- 2016
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10. Key design integration issues addressed in the EU DEMO pre-concept design phase
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Bachmann, C., Ciattaglia, S., Cismondi, F., Federici, G., Franke, T., Gliss, C., Härtl, T., Keech, G., Kembleton, R., Maviglia, F., and Siccinio, M.
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- 2020
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11. Engineering and integration risks arising from advanced magnetic divertor configurations
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Kembleton, R., Federici, G., Ambrosino, R., Maviglia, F., Siccinio, M., Reimerdes, H., Ha, S., Merriman, S., Bachmann, C., and Suiko, M.
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- 2019
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12. Issues of the vertical blanket segment architecture in DEMO: Current progress and resolution strategies
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Keech, G., Bachmann, C., Vorpahl, C., Gliss, C., Franke, T., Cismondi, F., Ciattaglia, S., Maviglia, F., Kembleton, R., Loving, A., and Keep, J.
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- 2019
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13. DEMO design activity in Europe: Progress and updates
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Federici, G., Bachmann, C., Barucca, L., Biel, W., Boccaccini, L., Brown, R., Bustreo, C., Ciattaglia, S., Cismondi, F., Coleman, M., Corato, V., Day, C., Diegele, E., Fischer, U., Franke, T., Gliss, C., Ibarra, A., Kembleton, R., Loving, A., Maviglia, F., Meszaros, B., Pintsuk, G., Taylor, N., Tran, M.Q., Vorpahl, C., Wenninger, R., and You, J.H.
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- 2018
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14. Heating & current drive efficiencies, TBR and RAMI considerations for DEMO
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Franke, T., Agostinetti, P., Avramidis, K., Bader, A., Bachmann, Ch., Biel, W., Bolzonella, T., Ciattaglia, S., Coleman, M., Cismondi, F., Granucci, G., Grossetti, G., Jelonnek, J., Jenkins, I., Kalsey, M., Kembleton, R., Mantel, N., Noterdaeme, J.-M., Rispoli, N., Simonin, A., Sonato, P., Tran, M.Q., Vincenzi, P., and Wenninger, R.
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- 2017
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15. Impact of plasma-wall interaction and exhaust on the EU-DEMO design
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Maviglia, F, Siccinio, M, Bachmann, C, Biel, W, Cavedon, M, Fable, E, Federici, G, Firdaouss, M, Gerardin, J, Hauer, V, Ivanova-Stanik, I, Janky, F, Kembleton, R, Militello, F, Subba, F, Varoutis, S, Vorpahl, C, Maviglia F., Siccinio M., Bachmann C., Biel W., Cavedon M., Fable E., Federici G., Firdaouss M., Gerardin J., Hauer V., Ivanova-Stanik I., Janky F., Kembleton R., Militello F., Subba F., Varoutis S., Vorpahl C., Maviglia, F, Siccinio, M, Bachmann, C, Biel, W, Cavedon, M, Fable, E, Federici, G, Firdaouss, M, Gerardin, J, Hauer, V, Ivanova-Stanik, I, Janky, F, Kembleton, R, Militello, F, Subba, F, Varoutis, S, Vorpahl, C, Maviglia F., Siccinio M., Bachmann C., Biel W., Cavedon M., Fable E., Federici G., Firdaouss M., Gerardin J., Hauer V., Ivanova-Stanik I., Janky F., Kembleton R., Militello F., Subba F., Varoutis S., and Vorpahl C.
- Abstract
In the present work, the role of plasma facing components protection in driving the EU-DEMO design will be reviewed, focusing on steady-state and, especially, on transients. This work encompasses both the first wall (FW) as well as the divertor. In fact, while the ITER divertor heat removal technology has been adopted, the ITER FW concept has been shown in the past years to be inadequate for EU-DEMO. This is due to the higher foreseen irradiation damage level, which requires structural materials (like Eurofer) able to withstand more than 5 dpa of neutron damage. This solution, however, limits the tolerable steady-state heat flux to ~1 MW/m2, i.e. a factor 3–4 below the ITER specifications. For this reason, poloidally and toroidally discontinuous protection limiters are implemented in EU-DEMO. Their role consists in reducing the heat load on the FW due to charged particles, during steady state and, more importantly, during planned and off-normal plasma transients. Concerning the divertor configuration, EU-DEMO currently assumes an ITER-like, lower single null (LSN) divertor, with seeded impurities for the dissipation of the power. However, this concept has been shown by numerous simulations in the past years to be marginal during steady-state (where a detached divertor is necessary to maintain the heat flux below the technological limit and to avoid excessive erosion) and unable to withstand some relevant transients, such as large ELMs and accidental loss of detachment. Various concepts, deviating from the ITER design, are currently under investigation to mitigate such risks, for example in-vessel coils for strike point sweeping in case of reattachment, as well as alternative divertor configurations. Finally, a broader discussion on the impact of divertor protection on the overall machine design is presented.
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- 2021
16. An Assessment of Alternative Divertors for the European DEMO
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Militello F., Aho-Mantila L., Body T., Bufferand H., Ciraolo G., Calabro G., Coster D., Di Gironimo G., Fanelli P., Fedorczak N., Hermann A., Innocente P., Ambrosino R., Kembleton R., Lunt T., Marzullo D., Merriman S., Moulton D., Nielsen A.H., Omatani J., Ramogida G., Reimerdes H., Reinhart M., Ricci P., Riva P., Stegmeir A., Subbba F., Suttrop W., Tamain P., Teschke M., Thrysoe A., Treutterer W., Varoutis S., Wensing M., Wischmeier M., and Xiang L.
- Subjects
European DEMO ,Alternative Divertors - Abstract
The uncertainties surrounding the physics of plasma exhaust and its centrality in reactor design require a thorough evaluation of promising alternatives as a precautionary measure to avoid delays in DEMO, if the ITER solution for the divertor could not extrapolate to reactor relevant machines. In this contribution, we review the physics and engineering work carried out within EUROfusion's work package DTT1/ADC on the subject (see Fig.1), showing with a quantitative assessment that alternative configurations provide a larger operating space than the single null according to multifluid simulations (in particular, lower Argon seeding levels and core concentration; lower separatrix density for comparable divertor protection; greater resilience to high power operations), but also highlighting the many engineering challenges that these configurations entail. The 3D engineering analysis of the alternative designs shows that the balance between port space for remote maintenance and the reinforcement of the supporting intercoil structures, stiffening the structure with respect to out of plane forces, is crucial to achieve acceptable solutions. In addition, active and passive magnetic control, pumping, neutronics and turbulence in alternative configurations will be discussed with quantitative analyses.
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- 2021
17. Impact of plasma-wall interaction and exhaust on the EU-DEMO design
- Author
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Siccinio, M., Bachmann, C., Maviglia, F., Militello, F., Subba, F., Vorpahl, C., Varoutis, S., Biel, W., Cavedon, M., Fable, E., Federici, G., Hauer, V., Ivanova-Stanik, I., Janky, F., and Kembleton, R.
- Published
- 2021
18. Preliminary analysis of alternative divertors for DEMO
- Author
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Militello, F., Aho-Mantila, L., Ambrosino, R., Body, T., Bufferand, H., Calabro, G., Ciraolo, G., Coster, D., Di Gironimo, G., Fanelli, P., Fedorczak, N., Herrmann, A., Innocente, P., Kembleton, R., Lilburne, J., Lunt, T., Marzullo, D., Merriman, S., Moulton, D., Nielsen, A. H., Omotani, J. T., Ramogida, G., Reimerdes, H., Reinhart, M., Ricci, P., Riva, F., Stegmeir, A., Subba, F., Suttrop, W., Tamain, P., Teschke, M., Thrysoe, A., Treutterer, W., Varoutis, S., Wensing, M., Wilde, A., Wischmeier, M., Xiang, L. Y., Militello, F., Aho-Mantila, L., Ambrosino, R., Body, T., Bufferand, H., Calabro, G., Ciraolo, G., Coster, D., Di Gironimo, G., Fanelli, P., Fedorczak, N., Herrmann, A., Innocente, P., Kembleton, R., Lilburne, J., Lunt, T., Marzullo, D., Merriman, S., Moulton, D., Nielsen, A. H., Omotani, J. T., Ramogida, G., Reimerdes, H., Reinhart, M., Ricci, P., Riva, F., Stegmeir, A., Subba, F., Suttrop, W., Tamain, P., Teschke, M., Thrysoe, A., Treutterer, W., Varoutis, S., Wensing, M., Wilde, A., Wischmeier, M., and Xiang, L. Y.
- Abstract
A physics and engineering analysis of alternative divertor configurations is carried out by examining benefits and problems by comparing the baseline single null solution with a Snowflake, an X- and a Super-X divertor. It is observed that alternative configurations can provide margin and resilience against large power fluctuations, but their engineering has intrinsic difficulties, especially in the balance between structural solidity and accessibility of the components and when the specific poloidal field coil positioning poses further constraints. A hybrid between the X- and Super-X divertor is proposed as a possible solution to the integration challenge.
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- 2021
19. Impact of plasma-wall interaction and exhaust on the EU-DEMO design
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Maviglia, F., primary, Siccinio, M., additional, Bachmann, C., additional, Biel, W., additional, Cavedon, M., additional, Fable, E., additional, Federici, G., additional, Firdaouss, M., additional, Gerardin, J., additional, Hauer, V., additional, Ivanova-Stanik, I., additional, Janky, F., additional, Kembleton, R., additional, Militello, F., additional, Subba, F., additional, Varoutis, S., additional, and Vorpahl, C., additional
- Published
- 2021
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20. Preliminary analysis of alternative divertors for DEMO
- Author
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Militello, F., primary, Aho-Mantila, L., additional, Ambrosino, R., additional, Body, T., additional, Bufferand, H., additional, Calabro, G., additional, Ciraolo, G., additional, Coster, D., additional, Di Gironimo, G., additional, Fanelli, P., additional, Fedorczak, N., additional, Herrmann, A., additional, Innocente, P., additional, Kembleton, R., additional, Lilburne, J., additional, Lunt, T., additional, Marzullo, D., additional, Merriman, S., additional, Moulton, D., additional, Nielsen, A.H., additional, Omotani, J., additional, Ramogida, G., additional, Reimerdes, H., additional, Reinhart, M., additional, Ricci, P., additional, Riva, F., additional, Stegmeir, A., additional, Subba, F., additional, Suttrop, W., additional, Tamain, P., additional, Teschke, M., additional, Thrysoe, A., additional, Treutterer, W., additional, Varoutis, S., additional, Wensing, M., additional, Wilde, A., additional, Wischmeier, M., additional, and Xiang, L.Y., additional
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- 2021
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21. Design Issues for Fusion Commercialization
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Kembleton, R., primary, Morris, A. W., additional, Federici, G., additional, and Donne, A. J. H., additional
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- 2020
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22. Assessment of alternative divertor configurations as an exhaust solution for DEMO
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Reimerdes, H., primary, Ambrosino, R., additional, Innocente, P., additional, Castaldo, A., additional, Chmielewski, P., additional, Di Gironimo, G., additional, Merriman, S., additional, Pericoli-Ridolfini, V., additional, Aho-Mantilla, L., additional, Albanese, R., additional, Bufferand, H., additional, Calabro, G., additional, Ciraolo, G., additional, Coster, D., additional, Fedorczak, N., additional, Ha, S., additional, Kembleton, R., additional, Lackner, K., additional, Loschiavo, V.P., additional, Lunt, T., additional, Marzullo, D., additional, Maurizio, R., additional, Militello, F., additional, Ramogida, G., additional, Subba, F., additional, Varoutis, S., additional, Zagórski, R., additional, and Zohm, H., additional
- Published
- 2020
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23. Advance in the conceptual design of the European DEMO magnet system
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Sedlak, K, primary, Anvar, V A, additional, Bagrets, N, additional, Biancolini, M E, additional, Bonifetto, R, additional, Bonne, F, additional, Boso, D, additional, Brighenti, A, additional, Bruzzone, P, additional, Celentano, G, additional, Chiappa, A, additional, D’Auria, V, additional, Dan, M, additional, Decool, P, additional, della Corte, A, additional, Dembkowska, A, additional, Dicuonzo, O, additional, Duran, I, additional, Eisterer, M, additional, Ferro, A, additional, Fiamozzi Zignani, C, additional, Fietz, W H, additional, Frittitta, C, additional, Gaio, E, additional, Giannini, L, additional, Giorgetti, F, additional, Gömöry, F, additional, Granados, X, additional, Guarino, R, additional, Heller, R, additional, Hoa, C, additional, Ivashov, I, additional, Jiolat, G, additional, Jirsa, M, additional, Jose, B, additional, Kembleton, R, additional, Kumar, M, additional, Lacroix, B, additional, Le Coz, Q, additional, Lewandowska, M, additional, Maistrello, A, additional, Misiara, N, additional, Morici, L, additional, Muzzi, L, additional, Nicollet, S, additional, Nijhuis, A, additional, Nunio, F, additional, Portafaix, C, additional, Romanelli, G, additional, Sarasola, X, additional, Savoldi, L, additional, Stepanov, B, additional, Tiseanu, I, additional, Tomassetti, G, additional, Torre, A, additional, Turtù, S, additional, Uglietti, D, additional, Vallcorba, R, additional, Viererbl, L, additional, Vojenciak, M, additional, Vorpahl, C, additional, Weiss, K-P, additional, Wesche, R, additional, Wolf, M J, additional, Zani, L, additional, Zanino, R, additional, Zappatore, A, additional, and Corato, V, additional
- Published
- 2020
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24. Power Handling and Plasma Protection Aspects that affect the Design of the DEMO Divertor and First Wall
- Author
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Wenninger, R., Federici, G., Albanese, R., Ambrosino, R., Bachmann, C., Barbato, L., Barrett, T., Biel, W., Cavedon, M., Coster, D., Eich, T., Firdaouss, M., Harrison, J., Kembleton, R., Lackner, K., Loschiavo, V., Lowry, C., Mattei, M., Maviglia, F., Murari, A., Neu, R., Pereslavtsev, P., Saarelma, S., Siccinio, M., Sieglin, B., Turnyanskiy, M., and Zohm, H.
- Subjects
DEMO - Abstract
The publication introduces power handling and plasma protection challenges associated with the recent EU DEMO baseline design. Based on this design possible modifications diverging fundamentally from ITER design choices are discussed: A double-null magnetic configuration and the integration of high heat flux limiters at the first wall.
- Published
- 2019
25. Development of a Plasma Scenario for the EU-DEMO: Current Activities and Perspectives
- Author
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Siccinio, M., Fable, E., Janky, F., Ambrosino, R., Biel, W., Cavedon, M., Franke, T., Görler, T., Härtl, T., Kembleton, R., Liu, Y., Mattei, M., Maviglia, F., Morris, J., Pautasso, G., Pigatto, L., Poli, E., Saarelma, S., Sauter, O., Subba, F., Tran, M., Viezzer, E., Vorpahl, C., and Zohm, H.
- Published
- 2019
26. Overview of the DEMO staged design approach in Europe
- Author
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Federici, G., Bachmann, C., Barucca, L., Baylard, C., Biel, W., Boccaccini, L.V., Bustreo, C., Ciattaglia, S., Cismondi, F., Corato, V., Day, C., Diegele, E., Franke, T., Gaio, E., Gliss, C., Haertl, T., Ibarra, A., Holden, J., Keech, G., Kembleton, R., Loving, A., Maviglia, F., Morris, J., Meszaros, B., Moscato, I., Pintsuk, G., Siccinio, M., Taylor, N., Tran, M.Q., Vorpahl, C., Walden, H., You, J.H., Federici, G., Bachmann, C., Barucca, L., Baylard, C., Biel, W., Boccaccini, L.V., Bustreo, C., Ciattaglia, S., Cismondi, F., Corato, V., Day, C., Diegele, E., Franke, T., Gaio, E., Gliss, C., Haertl, T., Ibarra, A., Holden, J., Keech, G., Kembleton, R., Loving, A., Maviglia, F., Morris, J., Meszaros, B., Moscato, I., Pintsuk, G., Siccinio, M., Taylor, N., Tran, M.Q., Vorpahl, C., Walden, H., and You, J.H.
- Abstract
This paper describes the status of the pre-conceptual design activities in Europe to advance the technical basis of the design of a DEMOnstration Fusion Power Plant (DEMO) to come in operation around the middle of this century with the main aims of demonstrating the production of few hundred MWs of net electricity, the feasibility of operation with a closedtritium fuel cycle, and maintenance systems capable of achieving adequate plant availability. This is expected to benefit as much as possible from the ITER experience, in terms of design, licensing, and construction. Emphasis is on an integrated design approach, based on system engineering, which provides a clear path for urgent R&D and addresses the main design integration issues by taking account critical systems interdependencies and inherent uncertainties of important design assumptions (physics and technology). A design readiness evaluation, together with a technology maturation and down selection strategy are planned through structured and transparent Gate Reviews. By embedding industry experience in the design from the beginning it will ensure that early attention is given to technology readiness and industrial feasibility, costs, maintenance, power conversion, nuclear safety and licensing aspects.
- Published
- 2019
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27. The next step in systems modelling: The integration of a simple 1D transport and equilibrium solver
- Author
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Ellis, K., Lux, H., Fable, E., Kembleton, R., and Siccinio, M.
- Published
- 2018
28. Assessment of Alternative Divertor Configurations as an Exhaust Solution for DEMO
- Author
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Reimerdes, H., Ambrosino, R., Innocente, P., Albanese, R., Bufferand, H., Castaldo, A., Chmielewski, P., Ciraolo, G., Coster, D., Ha, S., Kembleton, R., Loschiavo, V., Lunt, T., Merriman, S., Pericoli-Ridolfini, V., Siccinio, M., Subba, F., and Zagorski, R.
- Subjects
Alternative Divertor Configurations ,ITER ,DEMO - Abstract
The European roadmap for fusion energy has identified plasma exhaust as a major challenge towards the realization of magnetic confinement fusion. To mitigate the risk that the baseline scenario with a single null divertor (SND) and a high radiation fraction adopted for ITER will not extrapolate to a DEMO reactor, the EUROfusion consortium is assessing potential benefits and engineering challenges of alternative divertor configurations. A range of alternative configurations that could be readily adopted in a DEMO design have been identified. They include the X divertor (XD), the Super-X divertor (SXD) and the Snowflake divertor (SFD). The flux flaring towards the divertor target of the XD is found to be limited by the minimum grazing angle at the target. The characteristic increase of the target radius in the SXD is a trade-off with the increased TF coil volume, but ultimately limited by forces onto coils. Engineering constraints also limit XD and SXD characteristics to the outer divertor leg with a solution for the inner leg requiring up-down symmetric configurations. Boundary models with varying degrees of complexity have been used to predict the beneficial effect of the alternative configurations on exhaust performance. Desired effects are an easier access to detachment, reluctance of the detachment front to move along the divertor leg and an increase of the divertor radiation without excessive core confinement degradation. Based on the extended 2-point model and achievable geometric variations the SOL radiation required for the onset of detachment decreases in the SXD and SFD with the tolerable residual power 9p1 ´ fradq being 30-40% larger than in the SND. Additional improvements are expected from the ability to increase frad without adverse effects on the core performance and through SOL broadening as postulated for the SFD. A systematic study of the alternative configurations and the SND reference using the divertor transport code TECXY confirms that the SFD detaches at a lower frad, but also shows that the potential gain is modest. The main expected advantage of the XD and similarly of the SXD is an increased reluctance of the detachment front to move towards the X-point. To that end the detachment dynamics are assessed with the SOLPS and SOLEDGE2D-EIRENE codes, which use more sophisticated models of the target geometry and neutral particles.
- Published
- 2018
29. Figure of merit for divertor protection in the preliminary design of the EU-DEMO reactor
- Author
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Siccinio, M., primary, Federici, G., additional, Kembleton, R., additional, Lux, H., additional, Maviglia, F., additional, and Morris, J., additional
- Published
- 2019
- Full Text
- View/download PDF
30. Overview of the DEMO staged design approach in Europe
- Author
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Federici, G., primary, Bachmann, C., additional, Barucca, L., additional, Baylard, C., additional, Biel, W., additional, Boccaccini, L.V., additional, Bustreo, C., additional, Ciattaglia, S., additional, Cismondi, F., additional, Corato, V., additional, Day, C., additional, Diegele, E., additional, Franke, T., additional, Gaio, E., additional, Gliss, C., additional, Haertl, T., additional, Ibarra, A., additional, Holden, J., additional, Keech, G., additional, Kembleton, R., additional, Loving, A., additional, Maviglia, F., additional, Morris, J., additional, Meszaros, B., additional, Moscato, I., additional, Pintsuk, G., additional, Siccinio, M., additional, Taylor, N., additional, Tran, M.Q., additional, Vorpahl, C., additional, Walden, H., additional, and You, J.H., additional
- Published
- 2019
- Full Text
- View/download PDF
31. Implications of uncertainties on European DEMO design
- Author
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Lux, H., primary, Siccinio, M., additional, Biel, W., additional, Federici, G., additional, Kembleton, R., additional, Morris, A.W., additional, Patelli, E., additional, and Zohm, H., additional
- Published
- 2019
- Full Text
- View/download PDF
32. The physics and technology basis entering European system code studies for DEMO
- Author
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Wenninger, R., primary, Kembleton, R., additional, Bachmann, C., additional, Biel, W., additional, Bolzonella, T., additional, Ciattaglia, S., additional, Cismondi, F., additional, Coleman, M., additional, Donné, A.J.H., additional, Eich, T., additional, Fable, E., additional, Federici, G., additional, Franke, T., additional, Lux, H., additional, Maviglia, F., additional, Meszaros, B., additional, Pütterich, T., additional, Saarelma, S., additional, Snickers, A., additional, Villone, F., additional, Vincenzi, P., additional, Wolff, D., additional, and Zohm, H., additional
- Published
- 2016
- Full Text
- View/download PDF
33. “PROCESS”: A systems code for fusion power plants – Part 2: Engineering
- Author
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Kovari, M., primary, Fox, F., additional, Harrington, C., additional, Kembleton, R., additional, Knight, P., additional, Lux, H., additional, and Morris, J., additional
- Published
- 2016
- Full Text
- View/download PDF
34. Preliminary analysis of alternative divertors for DEMO
- Author
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Militello, F., Aho-Mantila, L., Ambrosino, R., Body, T., Bufferand, H., Calabro, G., Ciraolo, G., Coster, D., Di Gironimo, G., Fanelli, P., Fedorczak, N., Herrmann, A., Innocente, P., Kembleton, R., Lilburne, J., Lunt, T., Marzullo, D., Merriman, S., Moulton, D., Nielsen, A. H., Omotani, J., Ramogida, G., Reimerdes, H., Reinhart, M., Ricci, P., Riva, F., Stegmeir, A., Subba, F., Suttrop, W., Tamain, P., Teschke, M., Thrysoe, A., Treutterer, W., Varoutis, Stylianos, Wensing, M., Wilde, A., Wischmeier, M., and Xiang, L. Y.
- Subjects
Alternative divertor configurations ,Divertor design ,7. Clean energy ,DEMO - Abstract
A physics and engineering analysis of alternative divertor configurations is carried out by examining benefits and problems by comparing the baseline single null solution with a Snowflake, an X- and a Super-X divertor. It is observed that alternative configurations can provide margin and resilience against large power fluctuations, but their engineering has intrinsic difficulties, especially in the balance between structural solidity and accessibility of the components and when the specific poloidal field coil positioning poses further constraints. A hybrid between the X- and Super-X divertor is proposed as a possible solution to the integration challenge.
35. Heating & current drive efficiencies, TBR and RAMI considerations for DEMO
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Franke, T., Agostinetti, P., Avramidis, K., Bader, A., Bachmann, C., Biel, W., Bolzonella, T., Ciattaglia, S., Coleman, M., Cismondi, F., Granucci, G., Grossetti, G., Jelonnek, J., Jenkins, I., Kalsey, M., Kembleton, R., Mantel, N., Noterdaeme, J.-M., Rispoli, N., Simonin, A., Sonato, P., Tran, M.Q., Vincenzi, P., and Wenninger, R.
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7. Clean energy
36. Engineering and integration risks arising from advanced magnetic divertor configurations
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Mattia Siccinio, M. Suiko, H. Reimerdes, S. Merriman, Roberto Ambrosino, R. Kembleton, C. Bachmann, Francesco Maviglia, S. Ha, Giulia Federici, Kembleton, R., Federici, G., Ambrosino, R., Maviglia, F., Siccinio, M., Reimerdes, H., Ha, S., Merriman, S., Bachmann, C., and Suiko, M.
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Tokamak ,Computer science ,Systems studies ,Systems studie ,Port (circuit theory) ,7. Clean energy ,01 natural sciences ,Automotive engineering ,010305 fluids & plasmas ,law.invention ,law ,0103 physical sciences ,General Materials Science ,010306 general physics ,Baseline (configuration management) ,DEMO ,Civil and Structural Engineering ,Fusion power plant ,Mechanical Engineering ,Divertor ,Fusion power ,Power (physics) ,Nuclear Energy and Engineering ,Electromagnetic coil ,Key (cryptography) ,System modelling ,Technology choices - Abstract
The divertor configuration defines the power exhaust capabilities of DEMO as one of the major key design parameters and sets a number of requirements on the tokamak layout, including port sizes, poloidal field coil positions, and size of toroidal field coils. It also requires a corresponding configuration of plasma-facing components (PFCs) and a remote handling scheme to be able to handle the cassettes and associated in-vessel components (IVC) the configuration requires., There is a risk that the baseline ITER-like single-null (SN) divertor configuration cannot meet the PFC technology limits regarding power exhaust and first wall protection while achieving the target plasma performance requirements of DEMO or a future fusion power plant. Alternative magnetic configurations - double-null, snowflake, X-, and super-X - exist and potentially offer solutions to these risks and a route to achievable power handling in DEMO. But these options impose significant changes on machine architecture, increase the machine complexity and affect remote handling and plasma physics and so an integrated approach must be taken to assessing the feasibility of these options., In this paper we describe the work programme to assess the requirements for incorporating these configurations into DEMO.
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- 2019
37. Impact of plasma-wall interaction and exhaust on the EU-DEMO design
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C. Vorpahl, J. Gerardin, Irena Ivanova-Stanik, Wolfgang Biel, M. Cavedon, Stylianos Varoutis, Mattia Siccinio, M. Firdaouss, C. Bachmann, Volker Hauer, Francesco Maviglia, Fulvio Militello, R. Kembleton, E. Fable, Fabio Subba, G. Federici, F. Janky, Maviglia, F, Siccinio, M, Bachmann, C, Biel, W, Cavedon, M, Fable, E, Federici, G, Firdaouss, M, Gerardin, J, Hauer, V, Ivanova-Stanik, I, Janky, F, Kembleton, R, Militello, F, Subba, F, Varoutis, S, and Vorpahl, C
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Disruptions ,Divertor reattachment ,ELMs ,EU-DEMO ,Limiters ,Transients ,Nuclear and High Energy Physics ,Work (thermodynamics) ,Materials science ,Steady state (electronics) ,Materials Science (miscellaneous) ,Nuclear engineering ,01 natural sciences ,010305 fluids & plasmas ,Limiter ,0103 physical sciences ,ddc:530 ,010302 applied physics ,Transient ,Physics ,Divertor ,Plasma ,Dissipation ,lcsh:TK9001-9401 ,Power (physics) ,Nuclear Energy and Engineering ,Heat flux ,lcsh:Nuclear engineering. Atomic power ,Disruption ,ELM ,ddc:624 - Abstract
In the present work, the role of plasma facing components protection in driving the EU-DEMO design will be reviewed, focusing on steady-state and, especially, on transients. This work encompasses both the first wall (FW) as well as the divertor. In fact, while the ITER divertor heat removal technology has been adopted, the ITER FW concept has been shown in the past years to be inadequate for EU-DEMO. This is due to the higher foreseen irradiation damage level, which requires structural materials (like Eurofer) able to withstand more than 5 dpa of neutron damage. This solution, however, limits the tolerable steady-state heat flux to ~1 MW/m2, i.e. a factor 3–4 below the ITER specifications. For this reason, poloidally and toroidally discontinuous protection limiters are implemented in EU-DEMO. Their role consists in reducing the heat load on the FW due to charged particles, during steady state and, more importantly, during planned and off-normal plasma transients. Concerning the divertor configuration, EU-DEMO currently assumes an ITER-like, lower single null (LSN) divertor, with seeded impurities for the dissipation of the power. However, this concept has been shown by numerous simulations in the past years to be marginal during steady-state (where a detached divertor is necessary to maintain the heat flux below the technological limit and to avoid excessive erosion) and unable to withstand some relevant transients, such as large ELMs and accidental loss of detachment. Various concepts, deviating from the ITER design, are currently under investigation to mitigate such risks, for example in-vessel coils for strike point sweeping in case of reattachment, as well as alternative divertor configurations. Finally, a broader discussion on the impact of divertor protection on the overall machine design is presented.
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- 2021
38. Preliminary analysis of alternative divertors for DEMO
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M. Reinhart, Paolo Ricci, G. Ramogida, A. Herrmann, R. Kembleton, Pierluigi Fanelli, A. Wilde, G. Di Gironimo, Paolo Innocente, Leena Aho-Mantila, Fabio Riva, Anders Nielsen, Stylianos Varoutis, N. Fedorczak, H. Reimerdes, G. Ciraolo, D. Marzullo, L. Xiang, A. Stegmeir, T. Body, W. Treutterer, D. P. Coster, M. Wischmeier, John Omotani, Fulvio Militello, A. S. Thrysøe, G. Calabrò, S. Merriman, J. Lilburne, Fabio Subba, David Moulton, H. Bufferand, Roberto Ambrosino, T. Lunt, P. Tamain, W. Suttrop, M. Teschke, M. Wensing, Militello, F., Aho-Mantila, L., Ambrosino, R., Body, T., Bufferand, H., Calabro, G., Ciraolo, G., Coster, D., Di Gironimo, G., Fanelli, P., Fedorczak, N., Herrmann, A., Innocente, P., Kembleton, R., Lilburne, J., Lunt, T., Marzullo, D., Merriman, S., Moulton, D., Nielsen, A. H., Omotani, J., Ramogida, G., Reimerdes, H., Reinhart, M., Ricci, P., Riva, F., Stegmeir, A., Subba, F., Suttrop, W., Tamain, P., Teschke, M., Thrysoe, A., Treutterer, W., Varoutis, S., Wensing, M., Wilde, A., Wischmeier, M., and Xiang, L. Y.
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Nuclear and High Energy Physics ,Computer science ,Materials Science (miscellaneous) ,Nuclear engineering ,7. Clean energy ,01 natural sciences ,010305 fluids & plasmas ,Alternative divertor configurations ,DEMO ,Divertor design ,Margin (machine learning) ,0103 physical sciences ,ddc:530 ,Baseline (configuration management) ,Resilience (network) ,Engineering analysis ,010302 applied physics ,Divertor ,Physics ,lcsh:TK9001-9401 ,Power (physics) ,Nuclear Energy and Engineering ,Electromagnetic coil ,Solidity ,lcsh:Nuclear engineering. Atomic power ,Alternative divertor configuration - Abstract
A physics and engineering analysis of alternative divertor configurations is carried out by examining benefits and problems by comparing the baseline single null solution with a Snowflake, an X- and a Super-X divertor. It is observed that alternative configurations can provide margin and resilience against large power fluctuations, but their engineering has intrinsic difficulties, especially in the balance between structural solidity and accessibility of the components and when the specific poloidal field coil positioning poses further constraints. A hybrid between the X- and Super-X divertor is proposed as a possible solution to the integration challenge.
- Published
- 2021
39. Assessment of alternative divertor configurations as an exhaust solution for DEMO
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R. Zagórski, V. P. Loschiavo, Fabio Subba, F. Militello, H. Bufferand, Paolo Innocente, S. Merriman, R. Kembleton, H. Reimerdes, L. Aho-Mantilla, T. Lunt, G. Ramogida, Roberto Maurizio, G. Di Gironimo, V. Pericoli-Ridolfini, D. P. Coster, Raffaele Albanese, D. Marzullo, P. Chmielewski, Nicolas Fedorczak, K. Lackner, G. Ciraolo, Anna Castaldo, Stylianos Varoutis, G. Calabrò, R. Ambrosino, S. Ha, H. Zohm, Reimerdes, H., Ambrosino, R., Innocente, P., Castaldo, A., Chmielewski, P., Di Gironimo, G., Merriman, S., Pericoli-Ridolfini, V., Aho-Mantilla, L., Albanese, R., Bufferand, H., Calabro, G., Ciraolo, G., Coster, D., Fedorczak, N., Ha, S., Kembleton, R., Lackner, K., Loschiavo, V. P., Lunt, T., Marzullo, D., Maurizio, R., Militello, F., Ramogida, G., Subba, F., Varoutis, S., Zagorski, R., and Zohm, H.
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Physics ,Nuclear and High Energy Physics ,DEMO ,divertor ,fusion reactor ,plasma exhaust ,Divertor ,Nuclear engineering ,Fusion power ,Condensed Matter Physics ,01 natural sciences ,7. Clean energy ,010305 fluids & plasmas ,13. Climate action ,0103 physical sciences ,010306 general physics - Abstract
Plasma exhaust has been identified as a major challenge towards the realisation of magnetic confinement fusion. To mitigate the risk that the single null divertor (SND) with a high radiation fraction in the scrape-of-layer (SOL) adopted for ITER will not extrapolate to a DEMO reactor, the EUROfusion consortium is assessing potential benefits and engineering challenges of alternative divertor configurations. Alternative configurations that could be readily adopted in a DEMO design include the X divertor (XD), the Super-X divertor (SXD), the Snowflake divertor (SFD) and the double null divertor (DND). The flux flaring towards the divertor target of the XD is limited by the minimum grazing angle at the target set by gaps and misalignments. The characteristic increase of the target radius in the SXD is a trade-off with the increased TF coil volume, but, ultimately, also limited by forces onto coils. Engineering constraints also limit XD and SXD characteristics to the outer divertor leg with a solution for the inner leg requiring up-down symmetric configurations. Capital cost increases with respect to a SND configuration are largest for SXD and SFD, which require both significantly more poloidal field coil conductors and in the case of the SXD also more toroidal field coil conductors. Boundary models with increasing degrees of complexity have been used to predict the beneficial effect of the alternative configurations on exhaust performance. While all alternative configurations should decrease the power that must be radiated in the outer divertor, only the DND and possibly the SFD also ease the radiation requirements in the inner divertor. These decreases of the radiation requirements are however expected to be small making the ability of alternative divertors to increase divertor radiation without excessive core performance degradation their main advantage. Initial 2D fluid modeling of argon seeding in XD and SFD configurations indicate such advantages over the SND, while results for SXD and DND are still pending. Additional improvements, expected from increased turbulence in the low poloidal field region of the SFD also remain to be verified. A more precise comparison with the SND as well as absolute quantitative predictions for all configurations requires more complete physics models that are currently only being developed.
- Published
- 2020
40. Advance in the conceptual design of the European DEMO magnet system
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Ilia Ivashov, B. Jose, G. Jiolat, Andrea Chiappa, S. Nicollet, Lorenzo Giannini, Roberto Bonifetto, F. Giorgetti, Pierluigi Bruzzone, A. della Corte, R. Kembleton, P. Decool, C. Portafaix, Michael Eisterer, M. Dan, Rainer Wesche, L. Morici, Louis Zani, Giordano Tomassetti, B. Lacroix, V A Anvar, N. Misiara, Christian Vorpahl, Ortensia Dicuonzo, Boris Stepanov, Luigi Muzzi, Alberto Brighenti, Vincenzo D'Auria, Michael J. Wolf, Elena Gaio, Davide Uglietti, Francois Nunio, A. Maistrello, Xabier Sarasola, Alexandre Torre, F. Bonne, Ladislav Viererbl, Arend Nijhuis, Marco Evangelos Biancolini, Reinhard Heller, C. Fiamozzi Zignani, Milos Jirsa, C. Hoa, Aleksandra Dembkowska, Fedor Gömöry, I. Duran, Andrea Zappatore, A. Ferro, Monika Lewandowska, Ion Tiseanu, Q. Le Coz, Xavier Granados, R. Vallcorba, Simonetta Turtu, Roberto Zanino, Roberto Guarino, Gherardo Romanelli, V. Corato, Kamil Sedlak, Walter H. Fietz, Michal Vojenciak, G. Celentano, Daniela P. Boso, Nadezda Bagrets, Laura Savoldi, Maneesh Kumar, C. Frittitta, K.P. Weiss, Energy, Materials and Systems, European Commission, Swiss National Science Foundation, Sedlak, K., Anvar, V. A., Bagrets, N., Biancolini, M. E., Bonifetto, R., Bonne, F., Boso, D., Brighenti, A., Bruzzone, P., Celentano, G., Chiappa, A., D'Auria, V., Dan, M., Decool, P., Della Corte, A., Dembkowska, A., Dicuonzo, O., Duran, I., Eisterer, M., Ferro, A., Fiamozzi Zignani, C., Fietz, W. H., Frittitta, C., Gaio, E., Giannini, L., Giorgetti, F., Gomory, F., Granados, X., Guarino, R., Heller, R., Hoa, C., Ivashov, I., Jiolat, G., Jirsa, M., Jose, B., Kembleton, R., Kumar, M., Lacroix, B., Le Coz, Q., Lewandowska, M., Maistrello, A., Misiara, N., Morici, L., Muzzi, L., Nicollet, S., Nijhuis, A., Nunio, F., Portafaix, C., Romanelli, G., Sarasola, X., Savoldi, L., Stepanov, B., Tiseanu, I., Tomassetti, G., Torre, A., Turtu, S., Uglietti, D., Vallcorba, R., Viererbl, L., Vojenciak, M., Vorpahl, C., Weiss, K. -P., Wesche, R., Wolf, M. J., Zani, L., Zanino, R., Zappatore, A., and Corato, V.
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conductor ,Materials science ,Hybrid coil ,Nuclear engineering ,Superconducting magnet ,7. Clean energy ,01 natural sciences ,Conceptual design ,Superconducting magnets ,0103 physical sciences ,Materials Chemistry ,Nuclear fusion ,cable ,Electrical and Electronic Engineering ,010306 general physics ,DEMO ,nuclear fusion ,010302 applied physics ,Settore ING-IND/14 ,Metals and Alloys ,22/2 OA procedure ,Fusion power ,Condensed Matter Physics ,CICC ,superconducting magnets, CICC ,Magnetic flux ,progress ,Electromagnetic coil ,Magnet ,Ceramics and Composites ,superconducting magnets - Abstract
Sedlak, K. et al., The European DEMO, i.e. the demonstration fusion power plant designed in the framework of the Roadmap to Fusion Electricity by the EUROfusion Consortium, is approaching the end of the pre-conceptual design phase, to be accomplished with a Gate Review in 2020, in which all DEMO subsystems will be reviewed by panels of independent experts. The latest 2018 DEMO baseline has major and minor radius of 9.1 m and 2.9 m, plasma current 17.9 MA, toroidal field on the plasma axis 5.2 T, and the peak field in the toroidal-field (TF) conductor 12.0 T. The 900 ton heavy TF coil is prepared in four low-temperature-superconductor (LTS) variants, some of them differing slightly, other significantly, from the ITER TF coil design. Two variants of the CS coils are investigated—a purely LTS one resembling the ITER CS, and a hybrid coil, in which the innermost layers made of HTS allow the designers either to increase the magnetic flux, and thus the duration of the fusion pulse, or to reduce the outer radius of the CS coil. An issue presently investigated by mechanical analyzes is the fatigue load. Two variants of the poloidal field coils are being investigated. The magnet and conductor design studies are accompanied by the experimental tests on both LTS and HTS prototype samples, covering a broad range of DC and AC tests. Testing of quench behavior of the 15 kA HTS cables, with size and layout relevant for the fusion magnets and cooled by forced flow helium, is in preparation., This work has been carried out within the framework of the EUROfusion Consortium and has received funding from the Euratom research and training programme 2014–2018 and 2019–2020 under grant agreement No 633053. The views and opinions expressed herein do not necessarily reflect those of the European Commission. This work was supported in part by the Swiss National Science Foundation (SNF) under contract number 200021_179134.
- Published
- 2020
41. Figure of merit for divertor protection in the preliminary design of the EU-DEMO reactor
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H. Lux, R. Kembleton, G. Federici, Francesco Maviglia, J. Morris, Mattia Siccinio, Siccinio, M., Federici, G., Kembleton, R., Lux, H., Maviglia, F., and Morris, J.
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Nuclear and High Energy Physics ,Toroid ,Nuclear engineering ,Divertor ,major radiu ,Plasma ,Fusion power ,Dissipation ,major radius ,Condensed Matter Physics ,7. Clean energy ,01 natural sciences ,010305 fluids & plasmas ,divertor ,EU-DEMO ,toroidal field ,Heat flux ,0103 physical sciences ,Figure of merit ,010306 general physics ,Plasma stability - Abstract
This paper discusses the criteria to be used in the preliminary design phases of the EU-DEMO reactor to ensure the performance of the divertor without compromising the stability of core plasma or the fusion power generation. This work refers to a lower single null conventional divertor using actively cooled solid metal plasma-facing components and with extrinsic seeding for heat flux dissipation, which is the solution currently being adopted for EU-DEMO. The analysis does not consider the role of edge localised modes, and also neglects major off-normal events like disruptions. It is shown that it is necessary to fulfil two high-level requirements, namely: (i) the concentration of seeded impurities has to be lower than some critical value in order to not compromise the fusion plasma performance or stability and (ii) damage to the divertor plate in the case of accidental plasma reattachment must be avoided for a sufficiently long time in order to ensure safe, controlled termination of the plasma discharge. These requirements are needed because in a device like EU-DEMO, other strategies relying on mass injection are considered more likely to cause a loss of plasma stability at full current, with dramatic consequences for the integrity of plasma facing components. Two figures of merit, corresponding to these criteria, have been identified in the existing literature and discussed. The dependence of such figures of merit on the relevant machine parameters (major radius and toroidal magnetic field) is analysed. Initially, the analysis is carried out using a simple 0D physics approach and subsequently by means of the systems code PROCESS, which allows for consideration of further parameters, such as aspect ratio and elongation. The main conclusion of the present work is that the simultaneous fulfilment of both requirements limits the viable EU-DEMO size both in terms of major radius R and in terms of toroidal magnetic field BT. Finally, an attempt to extend the EU-DEMO related conclusions to a more general level is made.
- Published
- 2019
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42. The physics and technology basis entering European system code studies for DEMO
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Fabio Cismondi, M. Coleman, R. Kembleton, E. Fable, Ajh Tony Donné, Ronald Wenninger, Sergio Ciattaglia, C. Bachmann, Wolfgang Biel, P. Vincenzi, T. Bolzonella, H. Lux, Th. Franke, Fabio Villone, Th. Pütterich, T. Eich, A Snickers, G. Federici, H. Zohm, F. Maviglia, D Wolff, S. Saarelma, B. Meszaros, Wenninger, R., Kembleton, R., Bachmann, C., Biel, W., Bolzonella, T., Ciattaglia, S., Cismondi, F., Coleman, M., Donné, A. J. H., Eich, T., Fable, E., Federici, G., Franke, T., Lux, H., Maviglia, F., Meszaros, B., Pütterich, T., Saarelma, S., Snickers, A., Villone, F., Vincenzi, P., Wolff, D., Zohm, H., and Science and Technology of Nuclear Fusion
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Nuclear and High Energy Physics ,system code ,FUSION POWER-PLANTS ,Context (language use) ,Fusion power ,Condensed Matter Physics ,physics basi ,7. Clean energy ,01 natural sciences ,010305 fluids & plasmas ,physics basis ,Conceptual design ,DESIGN ,0103 physical sciences ,Credibility ,Key (cryptography) ,Systems engineering ,COLLISIONALITY ,Electric power ,Sensitivity (control systems) ,010306 general physics ,Baseline (configuration management) ,DEMO ,Nuclear and High Energy Physic - Abstract
A large scale program to develop a conceptual design for a demonstration fusion power plant (DEMO) has been initiated in Europe. Central elements are the baseline design points, which are developed by system codes. The assessment of the credibility of these design points is often hampered by missing information. The main physics and technology content of the central European system codes have been published (Kovari et al 2014 Fusion Eng. Des. 89 3054–69, 2016 Fusion Eng. Des. 104 9–20, Reux et al 2015 Nucl. Fusion 55 073011). In addition, this publication discusses key input parameters for the pulsed and conservative design option EU DEMO1 2015 and provides justifications for the parameter choices. In this context several DEMO physics gaps are identified, which need to be addressed in the future to reduce the uncertainty in predicting the performance of the device. Also the sensitivities of net electric power and pulse duration to variations of the input parameters are investigated. The most extreme sensitivity is found for the elongation ( Δ κ 95 = 10 % corresponds to Δ P e l , n e t = 125 % ).
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- 2017
43. Overview of the DEMO staged design approach in Europe
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F. Maviglia, E. Diegele, A. Loving, Gerald Pintsuk, Valentina Corato, C. Bachmann, G. Keech, Wolfgang Biel, I. Moscato, Minh Quang Tran, Th. Franke, Mattia Siccinio, Joanne M. Holden, Lorenzo V. Boccaccini, C. Gliss, Sergio Ciattaglia, H. Walden, Elena Gaio, Jeong-Ha You, C. Bustreo, L. Barucca, G. Federici, C. Vorpahl, N. Taylor, J. Morris, B. Meszaros, Fabio Cismondi, Angel Ibarra, Christian Day, R. Kembleton, T. Haertl, Ch. Baylard, Federici, G., Bachmann, C., Barucca, L., Baylard, C., Biel, W., Boccaccini, L. V., Bustreo, C., Ciattaglia, S., Cismondi, F., Corato, V., Day, C., Diegele, E., Franke, T., Gaio, E., Gliss, C., Haertl, T., Ibarra, A., Holden, J., Keech, G., Kembleton, R., Loving, A., Maviglia, F., Morris, J., Meszaros, B., Moscato, I., Pintsuk, G., Siccinio, M., Taylor, N., Tran, M. Q., Vorpahl, C., Walden, H., and You, J. H.
- Subjects
Nuclear and High Energy Physics ,breeding blanket ,DEMO ,design integration ,divertor ,fusion reactor ,systems code ,Design activities ,Fuel cycle ,media_common.quotation_subject ,Thermal power station ,Design integration ,7. Clean energy ,01 natural sciences ,010305 fluids & plasmas ,0103 physical sciences ,Production (economics) ,010306 general physics ,media_common ,Integrated design ,business.industry ,Condensed Matter Physics ,Interdependence ,Systems engineering ,Electricity ,ddc:620 ,business - Abstract
This paper describes the status of the pre-conceptual design activities in Europe to advance the technical basis of the design of a DEMOnstration Fusion Power Plant (DEMO) to come in operation around the middle of this century with the main aims of demonstrating the production of few hundred MWs of net electricity, the feasibility of operation with a closed-tritium fuel cycle, and maintenance systems capable of achieving adequate plant availability. This is expected to benefit as much as possible from the ITER experience, in terms of design, licensing, and construction. Emphasis is on an integrated design approach, based on system engineering, which provides a clear path for urgent R&D and addresses the main design integration issues by taking account critical systems interdependencies and inherent uncertainties of important design assumptions (physics and technology). A design readiness evaluation, together with a technology maturation and down selection strategy are planned through structured and transparent Gate Reviews. By embedding industry experience in the design from the beginning it will ensure that early attention is given to technology readiness and industrial feasibility, costs, maintenance, power conversion, nuclear safety and licensing aspects.
- Full Text
- View/download PDF
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