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1. Disruption avoidance strategies for DEMO

Author

Biel W., Alessi E., Ambrosino R., Ariola M., Bolshakova I., Brunner K.J., Cecconello M., Conroy S., Dezman D., Duran I., Entler S., Fable E., Farina D., Franke T., Giacomelli L., Giannone L., Gomes R., Gonçalves B., Heuraux S., Hjalmarsson A., Hron M., Janky F., Jesenko A., Krimmer A., Kudlacek O., Luís R., Marchuk O., Marchiori G., Mattei M., Maviglia F., De Masi G., Mazon D., Muscente P., Nietiadi Y., Nowak S., Pironti A., Quercia A., Ricardo E., Rispoli N., Sergienko G., Schramm R., El Shawish S., Siccinio M., Silva A., da Silva F., Sozzi C., Tardocchi M., Testa D., Treutterer W., Vale A., Vasyliev O., Wiesen S., Zohm H., Forschungszentrum Jülich GmbH | Centre de recherche de Juliers, Helmholtz-Gemeinschaft = Helmholtz Association, Universiteit Gent = Ghent University [Belgium] (UGENT), Istituto di Scienza e Tecnologia dei Plasmi, Università degli studi di Napoli Federico II, Universita degli studi di Napoli 'Parthenope' [Napoli], Magnetic Sensor laboratory [Lviv] (MSL), National Polytechnic University of Lviv (LPNU), Max-Planck-Institut für Plasmaphysik [Garching] (IPP), Uppsala University, Cosylab, Institute of Plasma Physics [Praha], Czech Academy of Sciences [Prague] (CAS), Instituto de Plasmas e Fusão Nuclear [Lisboa] (IPFN), Instituto Superior Técnico, Universidade Técnica de Lisboa (IST), Institut Jean Lamour (IJL), Université de Lorraine (UL)-Institut de Chimie du CNRS (INC)-Centre National de la Recherche Scientifique (CNRS), Consorzio RFX, Università degli studi della Campania 'Luigi Vanvitelli', Associazione Euratom-ENEA sulla Fusione, Institut de Recherche sur la Fusion par confinement Magnétique (IRFM), Commissariat à l'énergie atomique et aux énergies alternatives (CEA), Jozef Stefan Institute [Ljubljana] (IJS), Ecole Polytechnique Fédérale de Lausanne (EPFL), Universiteit Gent = Ghent University (UGENT), University of Naples Federico II = Università degli studi di Napoli Federico II, Università degli Studi di Napoli 'Parthenope' = University of Naples (PARTHENOPE), Institut de Chimie du CNRS (INC)-Université de Lorraine (UL)-Centre National de la Recherche Scientifique (CNRS), and Università degli studi della Campania 'Luigi Vanvitelli' = University of the Study of Campania Luigi Vanvitelli

Subjects
ComputingMilieux_GENERAL, plasma diagnostic and control, plasma fusion, [PHYS.PHYS.PHYS-PLASM-PH]Physics [physics]/Physics [physics]/Plasma Physics [physics.plasm-ph], ComputerApplications_GENERAL, DEMO diagnostic and control system, D&C, DEMO, GeneralLiterature_MISCELLANEOUS, ComputingMilieux_MISCELLANEOUS
Abstract

Disruption avoidance strategies for DEMO.

Published
2020

2. Power Handling and Plasma Protection Aspects that affect the Design of the DEMO Divertor and First Wall

Author

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

3. The science program of the TCV tokamak: exploring fusion reactor and power plant concepts

Author

Coda, S., Albanese, R., Alberti, S., Ambrosino, R., Anand, H., Andrebe, Y., Ariola, M., Barton, J. E., Behn, R., Blanchard, P., Boedo, J. A., Bortolon, A., Braunmüller, F. H., Brémond, S., Brunner, S., Camenen, Y., Canal, G. P., Cooper, W. A., Cruz, N., De Baar, M., Decker, J., De Meijere, C. A., Duval, B. P., Fasoli, A., Federspiel, L., Felici, F., Fontana, M., Furno, I., Galperti, C., Garrido, I., Genoud, J., Goodman, T. P., Graves, J. P., Hennequin, P., Hogge, J. -Ph., Hommen, G., Huang, Z., Joye, B., Kamleitner, J., Karpushov, A., Kim, D., Kirneva, N., Krämer-Flecken, A., Labit, B., Lazzaro, E., Le, H. B., Lefevre, L., Li, F., Lipschultz, B., Lister, J. B., Llobet, X., Lunt, T., Malygin, A., Maljaars, E., Marini, C., Martin, Y., Mattei, M., Merle, A., Molina Cabrera, P. A., Moreau, D., Moret, J. -M., Morgan, T., Mustafin, N. A., Nespoli, F., Nouailletas, R., Nowak, S., Peysson, Y., Pironti, A., Pochelon, A., Porte, L., Reimerdes, H., Sauter, O., Schlatter, Ch., Schuster, E., Silva, M., Sinha, J., Stoltzfus-Dueck, T., Tál, B., Teplukhina, A. A., Testa, D., Theiler, C., Tonetti, G., Tran, M. Q., Tsui, C., Vermare, L., Vernay, T., Vijvers, W. A. J., Vu, N. M. T., Vuille, V., Weisen, H., Wenninger, R., Witrant, E., Laboratoire de Physique des Plasmas (LPP), Université Paris-Sud - Paris 11 (UP11)-Université Pierre et Marie Curie - Paris 6 (UPMC)-Observatoire de Paris, Université Paris sciences et lettres (PSL)-Université Paris sciences et lettres (PSL)-École polytechnique (X)-Sorbonne Université (SU)-Université Paris-Saclay-Centre National de la Recherche Scientifique (CNRS), Coda, S., Albanese, R., Alberti, S., Ambrosino, R., Anand, H., Andrebe, Y., Ariola, M., Barton, J. E., Behn, R., Blanchard, P., Boedo, J. A., Bortolon, A., Braunmüller, F. H., Brémond, S., Brunner, S., Camenen, Y., Canal, G. P., Cooper, W. A., Cruz, N., De Baar, M., Decker, J., De Meijere, C. A., Duval, B. P., Fasoli, A., Federspiel, L., Felici, F., Fontana, M., Furno, I., Galperti, C., Garrido, I., Genoud, J., Goodman, T. P., Graves, J. P., Hennequin, P., Hogge, J. -Ph., Hommen, G., Huang, Z., Joye, B., Kamleitner, J., Karpushov, A., Kim, D., Kirneva, N., Krämer-Flecken, A., Labit, B., Lazzaro, E., Le, H. B., Lefevre, L., Li, F., Lipschultz, B., Lister, J. B., Llobet, X., Lunt, T., Malygin, A., Maljaars, E., Marini, C., Martin, Y., Mattei, M., Merle, A., Molina Cabrera, P. A., Moreau, D., Moret, J. -M., Morgan, T., Mustafin, N. A., Nespoli, F., Nouailletas, R., Nowak, S., Peysson, Y., Pironti, A., Pochelon, A., Porte, L., Reimerdes, H., Sauter, O., Schlatter, Ch., Schuster, E., Silva, M., Sinha, J., Stoltzfus-Dueck, T., Tál, B., Teplukhina, A. A., Testa, D., Theiler, C., Tonetti, G., Tran, M. Q., Tsui, C., Vermare, L., Vernay, T., Vijvers, W. A. J., Vu, N. M. T., Vuille, V., Weisen, H., Wenninger, R., Witrant, E., Hogge, J. P. h., Krämer Flecken, A., Mattei, Massimiliano, Moret, J. M., Schlatter, C. h., Stoltzfus Dueck, T., and Université Paris sciences et lettres (PSL)-Université Paris sciences et lettres (PSL)-École polytechnique (X)-Université Paris-Saclay-Centre National de la Recherche Scientifique (CNRS)

Subjects
Nuclear and High Energy Physics, Tokamak, DEMO, ITER, nuclear fusion, plasma, TCV, tokamak, Condensed Matter Physics, Cyclotron, Condensed Matter Physic, 7. Clean energy, Electron cyclotron resonance, law.invention, [PHYS.PHYS.PHYS-PLASM-PH]Physics [physics]/Physics [physics]/Plasma Physics [physics.plasm-ph], Physics::Plasma Physics, law, Physics, Toroid, Divertor, Plasma, Fusion power, Computational physics, Heat flux, Atomic physics
Abstract

International audience; TCV is acquiring a new 1 MW neutral beam and 2 MW additional third-harmonic electron cyclotron resonance heating (ECRH) to expand its operational range. Its existing shaping and ECRH launching versatility was amply exploited in an eclectic 2013 campaign. A new sub-ms real-time equilibrium reconstruction code was used in ECRH control of NTMs and in a prototype shape controller. The detection of visible light from the plasma boundary was also successfully used in a position-control algorithm. A new bang-bang controller improved stability against vertical displacements. The RAPTOR real-time transport simulator was employed to control the current density profile using electron cyclotron current drive. Shot-by-shot internal inductance optimization was demonstrated by iterative learning control of the current reference trace. Systematic studies of suprathermal electrons and ions in the presence of ECRH were performed. The L?H threshold power was measured to be ?50?75% higher in both H and He than D, to increase with the length of the outer separatrix, and to be independent of the current ramp rate. Core turbulence was found to decrease from positive to negative edge triangularity deep into the core. The geodesic acoustic mode was studied with multiple diagnostics, and its axisymmetry was confirmed by a full toroidal mapping of its magnetic component. A new theory predicting a toroidal rotation component at the plasma edge, driven by inhomogeneous transport and geodesic curvature, was tested successfully. A new high-confinement mode (IN-mode) was found with an edge barrier in density but not in temperature. The edge gradients were found to govern the scaling of confinement with current, power, density and triangularity. The dynamical interplay of confinement and magnetohydrodynamic modes leading to the density limit in TCV was documented. The heat flux profile decay lengths and heat load profile on the wall were documented in limited plasmas. In the snowflake (SF) divertor configuration the heat flux profiles were documented on all four strike points. SF simulations with the EMC3-EIRENE code, including the physics of the secondary separatrix, underestimate the flux to the secondary strike points, possibly resulting from steady-state E × B drifts. With neon injection, radiation in a SF was 15% higher than in a conventional divertor. The novel triple-null and X-divertor configurations were also achieved in TCV.

Published
2015

4. Wall protection strategies for DEMO plasma transients.

Author

Maviglia, F., Albanese, R., Ambrosino, R., Arter, W., Bachmann, C., Barrett, T., Federici, G., Firdaous, M., Gerardin, J., Kovari, M., Loschiavo, V., Mattei, M., Villone, F., and Wenninger, R.

Subjects
*PLASMA gases, *HEAT flux, *ENERGY conversion, *COOLANTS, *NEUTRON irradiation
Abstract

Highlights • Preliminary design of DEMO first wall 3D surface is presented. • Steady state and controllable perturbations are preented,evaluating the radiated HF density on the wall and the charged particle power. • Different plasma-wall contact phases have been analysed for a list of foresseable and unforeseeable transients. • 3D field line tracing codes were employed to analyse and design discrete high heat flux components surfaces. Abstract The present DEMO breeding blanked design heat load capability is limited to ≈1 MW/m2 for steady state plasma loading, due to the specific requirements on high neutron irradiation capable materials, and high coolant temperature for efficient energy conversion. While this limit is achievable in nominal conditions in the present DEMO blanket concept designs, the greatest challenges arise from the occurrence of plasma transients. The results of simulations of a number of plasma transients are presented in this paper. 3D field-line tracing codes have been used to analyses the maximum heat flux and energy density for a specific first wall shape design, and optimize it. A scoping study has been performed with the thermal analysis code RACLETTE, using a broad range of transient input heat fluxes, on a series of high heat flux (HF) components concepts with tungsten armor, Eurofer steel or copper alloy as heat sink materials, and helium or water as coolant. The results permit the identification of the operational space of the peak HF density that can be tolerated by different plasma facing components, for the different transient models. [ABSTRACT FROM AUTHOR]

Published
2018
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5. EU DEMO transient phases: Main constraints and heating mix studies for ramp-up and ramp-down.

Author

Vincenzi, P., Ambrosino, R., Artaud, J.F., Bolzonella, T., Garzotti, L., Giruzzi, G., Granucci, G., Köchl, F., Mattei, M., Tran, M.Q., and Wenninger, R.

Subjects
*FUSION reactors, *NUCLEAR reactor design & construction, *TRAJECTORIES (Mechanics), *SIMULATION methods & models, *TRANSIENT analyzers, *PLASMA simulation, *MATHEMATICAL models
Abstract

The pre-conceptual design for a European pulsed fusion reactor (DEMO1) is ongoing and one of the most challenging activities within scenario modeling studies deals with numerical investigations of DEMO1 transient phases. This paper presents an investigation on both ramp-up and ramp-down phases by selected plasma trajectories. Plasma evolution has a clear impact on the engineering design of the reactor, e.g. on auxiliary power systems, current ramp-rates and requirements on the coil system. Studies on ramp-up have been carried out with the fast tokamak simulator METIS to highlight the effects of different ramp-up options in terms of robustness of access to the desired flat-top scenario. Particular attention has been paid to requirements on heating systems and plasma position controllability. A dedicated heating power during ramp-up, in addition to the one required during flat-top, appears to be necessary for reliable access to H-mode. The ramp-down phase poses specific issues on vertical stability due to the complex plasma evolution. Ramp-down trajectories with controllable plasma boundaries generated by the CREATE NL code have been coupled to 1.5D transport simulations by means of the JINTRAC transport suite of codes. The results show the necessity of additional ramp-down heating power to avoid a radiative plasma collapse and to control the current density profile. Reducing the current ramp-rate in the ramp-down phase can help the controllability of the plasma. [ABSTRACT FROM AUTHOR]

Published
2017
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6. Integrated design strategy for EU-DEMO first wall protection from plasma transients

Author

Francesco Maviglia, Christian Bachmann, Gianfranco Federici, Thomas Franke, Mattia Siccinio, Raffaele Albanese, Roberto Ambrosino, Wayne Arter, Roberto Bonifetto, Giuseppe Calabrò, Riccardo De Luca, Luigi E. Di Grazia, Emiliano Fable, Pierluigi Fanelli, Alessandra Fanni, Mehdi Firdaouss, Jonathan Gerardin, Riccardo Lombroni, Massimiliano Mattei, Matteo Moscheni, William Morris, Gabriella Pautasso, Sergey Pestchanyi, Giuseppe Ramogida, Maria Lorena Richiusa, Giuliana Sias, Fabio Subba, Fabio Villone, Jeong-Ha You, Zsolt Vizvary, Maviglia, F., Bachmann, C., Federici, G., Franke, T., Siccinio, M., Albanese, R., Ambrosino, R., Arter, W., Bonifetto, R., Calabro, G., De Luca, R., Grazia, L. E. D., Fable, E., Fanelli, P., Fanni, A., Firdaouss, M., Gerardin, J., Lombroni, R., Mattei, M., Moscheni, M., Morris, W., Pautasso, G., Pestchanyi, S., Ramogida, G., Richiusa, M. L., Sias, G., Subba, F., Villone, F., You, J. -H., and Vizvary, Z.

Subjects
Discrete limiters, Nuclear Energy and Engineering, Electromagnetic simulation, Mechanical Engineering, Electromagnetic simulations, Discrete limiter, General Materials Science, Plasma transients, DEMO, First wall load, Plasma scenario optimization, Civil and Structural Engineering
Abstract

This work presents an overview of the integrated strategy developed, as part of the DEMO Key Design Integration Issue 1 (KDII1), to protect the EU-DEMO first wall (FW) from planned and unplanned plasma transients by employing discrete limiters. The present Breeding Blanket (BB) FW design, which aims at minimizing the loss of neutrons while travelling to the breeding zone, is able to withstand steady state heat fluxes up to ≈1-1.5 MW/m2 [1], which is not sufficient to guarantee its integrity for most plasma-FW direct contact. This is different from ITER, which has a FW designed for peak heat loads up to 4.6 MW/m2 [2], and it does not have the DEMO BB breeding related requirement. A series of documents was compiled in the DEMO Pre-Conceptual Design Phase, in support of the KDII1. The work presented here was presented at the 2020 DEMO Gate 1 (G1) review, and collects also the comments of the panel and the relative additional studies triggered by them. The design process, presented in this paper was adopted to systematically evaluate the impact of design changes, or new physics inputs, on the FW protection strategy and integration issues. It includes compiling the list of transients, and performing the relative plasma simulations, the design of discrete limiters and the evaluation of their capability to reduce the heat flux density on the FW, and finally a preliminary analysis of the heat loads effects on the Plasma Facing Components (PFC). All these aspects, together with preliminary limiter design, where considered since the beginning, in an integrated way.

Published
2022

7. Initial DEMO tokamak design configuration studies.

Author

Bachmann, Christian, Aiello, G., Albanese, R., Ambrosino, R., Arbeiter, F., Aubert, J., Boccaccini, L., Carloni, D., Federici, G., Fischer, U., Kovari, M., Li Puma, A., Loving, A., Maione, I., Mattei, M., Mazzone, G., Meszaros, B., Palermo, I., Pereslavtsev, P., and Riccardo, V.

Subjects
*TOKAMAKS, *CONCEPTUAL design, *ELECTRIC blankets, *ENERGY conversion
Abstract

To prepare the DEMO conceptual design phase a number of physics and engineering assessments were carried out in recent years in the frame of EFDA concluding in an initial design configuration of a DEMO tokamak. This paper gives an insight into the identified engineering requirements and constraints and describes their impact on the selection of the technologies and design principles of the main tokamak components. The EU DEMO program aims at making best use of the technologies developed for ITER (e.g., magnets, vessel, cryostat, and to some degree also the divertor). However, other systems in particular the breeding blanket require design solutions and advanced technologies that will only partially be tested in ITER. The main differences from ITER include the requirement to breed, to extract, to process and to recycle the tritium needed for plasma operation, the two orders of magnitude larger lifetime neutron fluence, the consequent radiation dose levels, which limit remote maintenance options, and the requirement to use low-activation steel for in-vessel components that also must operate at high temperature for efficient energy conversion. [ABSTRACT FROM AUTHOR]

Published
2015
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8. Electromagnetic analyses of single and double null configurations in DEMO device

Author

Christian Bachmann, Francesco Maviglia, Raffaele Albanese, V. P. Loschiavo, Fabio Villone, A. Castaldo, Massimiliano Mattei, R. Ambrosino, Gianfranco Federici, Albanese, R., Ambrosino, R., Bachmann, C., Castaldo, A., Federici, G., Loschiavo, V. P., Mattei, M., Maviglia, F., Villone, F., Albanese, Raffaele, Ambrosino, Roberto, Bachmann, Christian, Castaldo, Antonio, Federici, Gianfranco, Loschiavo, Vincenzo Paolo, Mattei, Massimiliano, Maviglia, Francesco, and Villone, Fabio

Subjects
Physics, MHD, Tokamak, Vertical stability, Power load, Mechanical Engineering, Divertor, Null (mathematics), Rotational symmetry, Vertical stability analysis, Mechanics, Plasma, 01 natural sciences, 010305 fluids & plasmas, Nuclear Energy and Engineering, Face (geometry), 0103 physical sciences, General Materials Science, DEMO, 010306 general physics, Civil and Structural Engineering
Abstract

The DEMO design has to face a number of challenges. According to the DEMO device limitations, the power load impinging on the Plasma Facing Components (PFCs) in the plasma Single Null (SN) magnetic configuration (which is for DEMO as in ITER the baseline configuration) clearly underlines the need to explore alternative divertor concepts. In this paper, a comparison between the Single and Double Null (DN) configurations is proposed. In particular, a comparative electromagnetic analysis of the magnetic configurations is performed in terms of vertical stability (VS) and disruptions in the 2D axisymmetric case.

Published
2019

9. Optimization-oriented modelling of neutral beam injection for EU pulsed DEMO

Author

Jari Varje, M. Vallar, P. Vincenzi, Massimiliano Mattei, Piero Agostinetti, Tommaso Bolzonella, Taina Kurki-Suonio, J.F. Artaud, Vincenzi, P., Agostinetti, P., Artaud, J. F., Bolzonella, T., Kurki-Suonio, T., Mattei, M., Vallar, M., Varje, J., National Research Council of Italy, CEA, Fusion and Plasma Physics, University of Naples Federico II, Department of Applied Physics, Aalto-yliopisto, and Aalto University

Subjects
Materials science, ASCOT, NBI, Plasma, Condensed Matter Physics, plasmas, 7. Clean energy, 01 natural sciences, Neutral beam injection, 010305 fluids & plasmas, Nuclear Energy and Engineering, Deuterium, 0103 physical sciences, fast ion, fast ions, Atomic physics, 010306 general physics, DEMO, deuterium, ramp-up
Abstract

openaire: EC/H2020/633053/EU//EUROfusion Neutral beam injection (NBI) is one of the auxiliary power systems considered for the EU DEMO pulsed plasma ('DEMO1'). In this paper, we discuss the characteristics of optimized NBI in terms of the DEMO1 requirements, relating physics and engineering contexts in a novel parameter range compared to current NBI systems and in a larger plasma volume than ITER. Different injection options are investigated to account for various concepts discussed in the literature. The investigation is carried out using a wide range of sensitivity studies by means of the METIS 0.5D transport code and ASCOT Monte Carlo simulations of injected neutral-beam particles. This investigation has generated a series of recommendations for the NBI design, contributing to the system optimization process. We show how tangential injection aimed at the plasma core, with an energy greater than or similar to 800 keV, is recommended to maintain high fusion power performance and fulfill the requirements for bulk heating. Compliance with engineeringconstraints on the NBI design, e.g., the least interference with breeding blanket modules or compatibility with solutions for the beamline components, imposes some restrictions when discussing the beam geometry. The minimum density at which an NBI can be safely operated without harmful shine-through losses is investigated for different injection energies and compared to the ITER case. The NBI operational window for DEMO is shown to be significantly extended to transient, low-density phases, also highlighting the importance of NBI systems designed for modular energy and power output. NBI can therefore sustain the plasma during a considerable portion of the transient phases, i.e., the current ramp-up and ramp-down phases. The final decision on the DEMO heating mix will be made on the basis of system operability and performance: the optimized NBI is shown to be a suitable and effective option for the EU DEMO inductive scenario.

Published
2021

10. Diagnostics for plasma control : from ITER to DEMO

Author

Sean Conroy, Slavomir Entler, F. Janky, Carlo Sozzi, Martin Hron, F. da Silva, W. Treutterer, M. Tardocchi, Alfredo Pironti, Kai Jakob Brunner, H. Meister, Giuseppe Marchiori, I. Duran, J. Kogoj, Lorenzo Figini, F. Maviglia, Wolfgang Biel, C. Finotti, Th. Franke, T. Eade, Marco Cecconello, E. Fable, V. Rohde, Marco Ariola, C. Piron, Inessa Bolshakova, H. Zohm, O. Marchuk, Didier Mazon, M. v. Berkel, N. Rispoli, R. Luis, R. Dux, K. Meyer, M. Z. Tokar, Raffaele Albanese, Massimiliano Mattei, O. Kudlacek, D. Micheletti, A. Malaquias, W. Gonzalez, Göran Ericsson, L. Giacomelli, Andreas Dinklage, Gennady Sergienko, D. Farina, L. Giannone, S. Nowak, R. Cavazzana, A. Kallenbach, S. El Shawish, Anders Hjalmarsson, R. König, Roberto Ambrosino, Analiza M. Silva, Mattia Siccinio, G. De Masi, Biel, W., Albanese, R., Ambrosino, R., Ariola, M., Berkel, M. V., Bolshakova, I., Brunner, K. J., Cavazzana, R., Cecconello, M., Conroy, S., Dinklage, A., Duran, I., Dux, R., Eade, T., Entler, S., Ericsson, G., Fable, E., Farina, D., Figini, L., Finotti, C., Franke, T., Giacomelli, L., Giannone, L., Gonzalez, W., Hjalmarsson, A., Hron, M., Janky, F., Kallenbach, A., Kogoj, J., Konig, R., Kudlacek, O., Luis, R., Malaquias, A., Marchuk, O., Marchiori, G., Mattei, M., Maviglia, F., De Masi, G., Mazon, D., Meister, H., Meyer, K., Micheletti, D., Nowak, S., Piron, C., Pironti, A., Rispoli, N., Rohde, V., Sergienko, G., El Shawish, S., Siccinio, M., Silva, A., da Silva, F., Sozzi, C., Tardocchi, M., Tokar, M., Treutterer, W., and Zohm, H.

Subjects
Tokamak, Materials science, Plasma diagnostic, ComputingMethodologies_SIMULATIONANDMODELING, Nuclear engineering, ComputerApplications_COMPUTERSINOTHERSYSTEMS, 01 natural sciences, 010305 fluids & plasmas, law.invention, Plasma diagnostics, HALL SENSORS, Fusion, plasma och rymdfysik, DESIGN, law, ITER, 0103 physical sciences, Medicine and Health Sciences, ddc:530, General Materials Science, 010306 general physics, DEMO, Civil and Structural Engineering, ISSUES, Mechanical Engineering, RESEARCH-AND-DEVELOPMENT, DENSITY-MEASUREMENTS, Plasma, Fusion power, Plasma control, Fusion, Plasma and Space Physics, Nuclear Energy and Engineering, EDGE, Hall effect sensor, ELECTRON, INTEGRATION, SYSTEM
Abstract

The plasma diagnostic and control (D&C) system for a future tokamak demonstration fusion reactor (DEMO) will have to provide reliable operation near technical and physics limits, while its front-end components will be subject to strong adverse effects within the nuclear and high temperature plasma environment. The ongoing developments for the ITER D&C system represent an important starting point for progressing towards DEMO. Requirements for detailed exploration of physics are however pushing the ITER diagnostic design towards using sophisticated methods and aiming for large spatial coverage and high signal intensities, so that many front-end components have to be mounted in forward positions. In many cases this results in a rapid aging of diagnostic components, so that additional measures like protection shutters, plasma based mirror cleaning or modular approaches for frequent maintenance and exchange are being developed. Under the even stronger fluences of plasma particles, neutron/gamma and radiation loads on DEMO, durable and reliable signals for plasma control can only be obtained by selecting diagnostic methods with regard to their robustness, and retracting vulnerable front-end components into protected locations. Based on this approach, an initial DEMO D&C concept is presented, which covers all major control issues by signals to be derived from at least two different diagnostic methods (risk mitigation).

Published
2019

11. Initial DEMO tokamak design configuration studies

Author

Pavel Pereslavtsev, M. Kovari, Giuseppe Mazzone, Christian Bachmann, V. Riccardo, Z. Vizvary, A. Loving, Giacomo Aiello, G. Federici, A. Li Puma, Lorenzo Virgilio Boccaccini, Raffaele Albanese, I. Palermo, Ronald Wenninger, Frederik Arbeiter, Massimiliano Mattei, Ulrich Fischer, D. Carloni, Ivan Alessio Maione, Eliseo Visca, Alessandro Vaccaro, R. Ambrosino, N. Taylor, P. Sardain, S. Villari, B. Meszaros, J. Aubert, Bachmann, Christian, Aiello, G., Albanese, R., Ambrosino, R., Arbeiter, F., Aubert, J., Boccaccini, L., Carloni, D., Federici, G., Fischer, U., Kovari, M., Li Puma, A., Loving, A., Maione, I., Mattei, M., Mazzone, G., Meszaros, B., Palermo, I., Pereslavtsev, P., Riccardo, V., Sardain, P., Taylor, N., Villari, S., Vizvary, Z., Vaccaro, A., Visca, E., Wenninger, R., Mattei, Massimiliano, Bureau de Conception Calculs et Réalisations (BCCR), Service d'Etudes Mécaniques et Thermiques (SEMT), Département de Modélisation des Systèmes et Structures (DM2S), CEA-Direction des Energies (ex-Direction de l'Energie Nucléaire) (CEA-DES (ex-DEN)), Commissariat à l'énergie atomique et aux énergies alternatives (CEA)-Commissariat à l'énergie atomique et aux énergies alternatives (CEA)-Université Paris-Saclay-CEA-Direction des Energies (ex-Direction de l'Energie Nucléaire) (CEA-DES (ex-DEN)), Commissariat à l'énergie atomique et aux énergies alternatives (CEA)-Commissariat à l'énergie atomique et aux énergies alternatives (CEA)-Université Paris-Saclay-Département de Modélisation des Systèmes et Structures (DM2S), Commissariat à l'énergie atomique et aux énergies alternatives (CEA)-Commissariat à l'énergie atomique et aux énergies alternatives (CEA)-Université Paris-Saclay, and Laboratoire Technologie d'Assemblage (LTA)

Subjects
Cryostat, Tokamak, DEMO, Power plant, Nuclear Energy and Engineering, Materials Science (all), Civil and Structural Engineering, Mechanical Engineering, Requirements engineering, Power station, Divertor, Nuclear engineering, Blanket, 7. Clean energy, law.invention, [SPI]Engineering Sciences [physics], Conceptual design, law, General Materials Science, Efficient energy use
Abstract

To prepare the DEMO conceptual design phase a number of physics and engineering assessments were carried out in recent years in the frame of EFDA concluding in an initial design configuration of a DEMO tokamak. This paper gives an insight into the identified engineering requirements and constraints and describes their impact on the selection of the technologies and design principles of the main tokamak components. The EU DEMO program aims at making best use of the technologies developed for ITER (e.g., magnets, vessel, cryostat, and to some degree also the divertor). However, other systems in particular the breeding blanket require design solutions and advanced technologies that will only partially be tested in ITER. The main differences from ITER include the requirement to breed, to extract, to process and to recycle the tritium needed for plasma operation, the two orders of magnitude larger lifetime neutron fluence, the consequent radiation dose levels, which limit remote maintenance options, and the requirement to use low-activation steel for in-vessel components that also must operate at high temperature for efficient energy conversion. © 2015 Elsevier B.V. All rights reserved.

Published
2015

12. Wall protection strategies for DEMO plasma transients

Author

J. Gerardin, Fabio Villone, T.R. Barrett, Massimiliano Mattei, Roberto Ambrosino, Ronald Wenninger, C. Bachmann, V. P. Loschiavo, F. Maviglia, M. Kovari, M. Firdaous, G. Federici, Wayne Arter, Raffaele Albanese, Maviglia, F., Albanese, R., Ambrosino, R., Arter, W., Bachmann, C., Barrett, T., Federici, G., Firdaous, M., Gerardin, J., Kovari, M., Loschiavo, V., Mattei, M., Villone, F., and Wenninger, R.

Subjects
Steady state (electronics), Materials science, Nuclear engineering, chemistry.chemical_element, Blanket, Heat sink, 01 natural sciences, 7. Clean energy, 010305 fluids & plasmas, 0103 physical sciences, General Materials Science, 010306 general physics, DEMO, Helium, Civil and Structural Engineering, Transient load, Mechanical Engineering, Plasma, Plasma facing component, Coolant, Nuclear Energy and Engineering, chemistry, Heat flux, Heat wall load, Transient loads, Materials Science (all), Transient (oscillation)
Abstract

The present DEMO breeding blanked design heat load capability is limited to ≈1 MW/m2 for steady state plasma loading, due to the specific requirements on high neutron irradiation capable materials, and high coolant temperature for efficient energy conversion. While this limit is achievable in nominal conditions in the present DEMO blanket concept designs, the greatest challenges arise from the occurrence of plasma transients. The results of simulations of a number of plasma transients are presented in this paper. 3D field-line tracing codes have been used to analyses the maximum heat flux and energy density for a specific first wall shape design, and optimize it. A scoping study has been performed with the thermal analysis code RACLETTE, using a broad range of transient input heat fluxes, on a series of high heat flux (HF) components concepts with tungsten armor, Eurofer steel or copper alloy as heat sink materials, and helium or water as coolant. The results permit the identification of the operational space of the peak HF density that can be tolerated by different plasma facing components, for the different transient models.

Published
2018
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13. EU DEMO transient phases: Main constraints and heating mix studies for ramp-up and ramp-down

Author

G. Giruzzi, L. Garzotti, F. Köchl, J.F. Artaud, Ronald Wenninger, R. Ambrosino, P. Vincenzi, Tommaso Bolzonella, Massimiliano Mattei, Minh Quang Tran, Gustavo Granucci, Vincenzi, P., Ambrosino, R., Artaud, J. F., Bolzonella, T., Garzotti, L., Giruzzi, G., Granucci, G., Kochl, F., Mattei, M., Tran, M. Q., Wenninger, R., Vincenzi, P, Köchl, F., and Mattei, Massimiliano

Subjects
Tokamak, Computer science, Nuclear engineering, 01 natural sciences, 7. Clean energy, 010305 fluids & plasmas, law.invention, Heating and current drive, Materials Science(all), Physics::Plasma Physics, law, 0103 physical sciences, General Materials Science, 010306 general physics, DEMO, Civil and Structural Engineering, Radiation, Mechanical Engineering, Ramp-up, Plasma, Fusion power, Plasma control, Ramp-down, Controllability, Nuclear Energy and Engineering, 13. Climate action, Auxiliary power unit, Electromagnetic coil, ____, Physics::Accelerator Physics, Transient (oscillation), Materials Science (all), Engineering design process
Abstract

Content: EU DEMO studies for pulsed (DEMO1) and steady-state (DEMO2) concepts are currently in the pre-conceptual phase [1]. DEMO1 aims at producing about 2GW of fusion power with a burn time of approximately 2 hours. Within EUROfusion Power Plant Physics and Technology department, DEMO scenario modelling is carried out as part of the validation of feasibility and performance of DEMO designs. One of the most challenging activities deals with numerical investigations of DEMO1 transient phases including ramp-up and ramp-down, which exhibit peculiar issues with respect to existing devices. Studies on ramp-up have been carried out to highlight the effects of different ramp-up options in terms of robustness of the access to the desired flattop scenario. A heating power during ramp-up, additional to the one required during flattop, appears to be necessary for plasma burn initiation and access to H-mode, with Paux,RU50MW depending on the uncertainties on L-H transition scaling. Current ramp-rate and heating power influence also plasma position controllability, and results are presented in terms of the achieved li(3) and bp. Additional power requirements and integration of different systems which are relevant for DEMO heating mix assessment are here discussed. Ramp-down phase in DEMO poses specific issues on vertical stability given the distance of control actuators from the plasma. Ramp-down trajectories with controllable plasma boundaries have been coupled to transport studies showing the necessity of additional ramp-down heating power to avoid radiative plasma collapses. Off-axis power deposition helps plasma controllability, together with a current ramp-rate100kA/s. Plasma radiation also dominates the H-L transition, which is investigated and appears to be a critical step in terms of plasma control. DEMO performance is strongly linked to the maximum plasma elongation, which has to be assessed comparing different ramp-down trajectories. [1] G. Federici et. al, Fus. Eng. Des. 89, 882-889 (2014)

Published
2017
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14. Advances in the physics basis for the European DEMO design

Author

Patrick Maget, E. Fable, Emanuele Poli, Massimiliano Mattei, H. Zohm, Raffaele Albanese, C. Reux, C. Angioni, G. Ramogida, Ambrogio Fasoli, M. Bernert, G. Federici, J.F. Artaud, G. Giruzzi, J. Aubert, Fabio Villone, Roberto Ambrosino, Leena Aho-Mantila, M. Wischmeier, Ronald Wenninger, J. Garcia, Frederik Arbeiter, M. Schneider, B. Sieglin, Frank Jenko, F. Maviglia, CEA-Direction des Energies (ex-Direction de l'Energie Nucléaire) (CEA-DES (ex-DEN)), Commissariat à l'énergie atomique et aux énergies alternatives (CEA), VTT Technical Research Centre of Finland (VTT), Assoc. Euratom-ENEA-CREATE, Universita Mediterranea of Reggio Calabria [Reggio Calabria], Max-Planck-Institut für Plasmaphysik [Garching] (IPP), Association EURATOM-CEA (CEA/DSM/DRFC), Università degli studi di Napoli Federico II, Laboratoire de Physique des Plasmas (LPP), Université Paris-Sud - Paris 11 (UP11)-Université Pierre et Marie Curie - Paris 6 (UPMC)-Observatoire de Paris, Université Paris sciences et lettres (PSL)-Université Paris sciences et lettres (PSL)-École polytechnique (X)-Sorbonne Université-Université Paris-Saclay-Centre National de la Recherche Scientifique (CNRS), European Project: 633053,H2020,EURATOM-Adhoc-2014-20,EUROfusion(2014), EUROfusion, Karlsruher Institut für Technologie (KIT), Institut de Physique du Globe de Paris (IPGP), Université Pierre et Marie Curie - Paris 6 (UPMC)-Institut national des sciences de l'Univers (INSU - CNRS)-IPG PARIS-Université Paris Diderot - Paris 7 (UPD7)-Université de La Réunion (UR)-Centre National de la Recherche Scientifique (CNRS), Universita degli studi di Napoli 'Parthenope' [Napoli], Centre de Recherches en Physique des Plasmas (CRPP), Ecole Polytechnique Fédérale de Lausanne (EPFL), Institut de Recherche sur la Fusion par confinement Magnétique (IRFM), Institut de Génétique Moléculaire de Montpellier (IGMM), Centre National de la Recherche Scientifique (CNRS)-Université de Montpellier (UM), Italian National agency for new technologies, Energy and sustainable economic development [Frascati] (ENEA), Università degli studi di Cassino e del Lazio Meridionale (UNICAS), Wenninger, R., Arbeiter, F., Aubert, J., Aho Mantila, L., Albanese, R., Ambrosino, R., Angioni, C., Artaud, J. F., Bernert, M., Fable, E., Fasoli, A., Federici, G., Garcia, J., Giruzzi, G., Jenko, F., Maget, P., Mattei, Massimiliano, Maviglia, F., Poli, E., Ramogida, G., Reux, C., Schneider, M., Sieglin, B., Villone, F., Wischmeier, M., Zohm, H., Laboratoire Technologie d'Assemblage (LTA), Service d'Etudes Mécaniques et Thermiques (SEMT), Département de Modélisation des Systèmes et Structures (DM2S), Commissariat à l'énergie atomique et aux énergies alternatives (CEA)-Commissariat à l'énergie atomique et aux énergies alternatives (CEA)-Université Paris-Saclay-CEA-Direction des Energies (ex-Direction de l'Energie Nucléaire) (CEA-DES (ex-DEN)), Commissariat à l'énergie atomique et aux énergies alternatives (CEA)-Commissariat à l'énergie atomique et aux énergies alternatives (CEA)-Université Paris-Saclay-Département de Modélisation des Systèmes et Structures (DM2S), Commissariat à l'énergie atomique et aux énergies alternatives (CEA)-Commissariat à l'énergie atomique et aux énergies alternatives (CEA)-Université Paris-Saclay, University of Naples Federico II = Università degli studi di Napoli Federico II, Università degli Studi di Napoli 'Parthenope' = University of Naples (PARTHENOPE), Université de Montpellier (UM)-Centre National de la Recherche Scientifique (CNRS), Aho-Mantila, L., Artaud, J. -F., and Mattei, M.

Subjects
Nuclear and High Energy Physics, [PHYS.NUCL]Physics [physics]/Nuclear Theory [nucl-th], Basis (linear algebra), MHD, Condensed Matter Physic, [PHYS.NEXP]Physics [physics]/Nuclear Experiment [nucl-ex], Fusion power, Condensed Matter Physics, 7. Clean energy, disruption, scenario, fast particle, fast particles, Conceptual design, [SDU]Sciences of the Universe [physics], Iter, transport, Systems engineering, ddc:620, Current (fluid), DEMO, PWI, Engineering & allied operations
Abstract

International audience; in the European fusion roadmap, ITER is followed by a demonstration fusion power reactor (DEMO), for which a conceptual design is under development. This paper reports the first results of a coherent effort to develop the relevant physics knowledge for that (DEMO Physics Basis), carried out by European experts. The program currently includes investigations in the areas of scenario modeling, transport, MHD, heating & current drive, fast particles, plasma wall interaction and disruptions.

Published
2015

15. Impact of plasma thermal transients on the design of the EU DEMO first wall protection

Author

F. Palermo, M. Firdaouss, C. Vorpahl, Thomas Franke, V. P. Loschiavo, Fabio Villone, M. L. Richiusa, J. Gerardin, Roberto Ambrosino, Christian Bachmann, E. Fable, Z. Vizvary, Gianfranco Federici, Francesco Maviglia, Raffaele Albanese, Massimiliano Mattei, Mattia Siccinio, Maviglia, F., Bachmann, C., Federici, G., Franke, T., Siccinio, M., Vorpahl, C., Albanese, R., Ambrosino, R., Fable, E., Firdaouss, M., Gerardin, J., Loschiavo, V. P., Mattei, M., Palermo, F., Richiusa, M. L., Villone, F., and Vizvary, Z.

Subjects
Materials science, Steady state (electronics), Nuclear engineering, Discrete limiter, Plasma transients, 01 natural sciences, 010305 fluids & plasmas, Electromagnetic simulation, 0103 physical sciences, Thermal, Limit (music), Limiter, Water cooling, General Materials Science, 010306 general physics, First wall load, DEMO, Civil and Structural Engineering, Mechanical Engineering, Plasma, Discrete limiters, Nuclear Energy and Engineering, 13. Climate action, Thermal radiation, Electromagnetic simulations, Transient (oscillation), Plasma scenario optimization
Abstract

The protection of the EU-DEMO first wall (FW) during plasma transients represents one of the main challenges of the current pre-concept design phase. While the present DEMO FW design heat load capability is of the order of ≈1−2 MW/m2 in steady state, this limit is overcome during plasma transients for both normal and off-normal events leading to a plasma-wall contact. A strategy to protect the FW is being developed, considering the inclusion of discrete limiters, designed also to maintain the integrity of their cooling system during transients. The present investigations include electromagnetic modelling and plasma simulations on a list of critical transient events. The plasma equilibria are designed to ensure that the plasma impact, in case of loss of plasma control, is located, when possible, close to maintenance ports, to allow for replacement of the limiters. Charged particles and radiation heat load calculations are performed to evaluate the surface design and the required number of limiters. Finally, simplified thermal analyses are run to verify the integrity of the limiter plasma-facing components, and propose their design.

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