Review of the Innovative H&CD Designs and the Impact of Their Configurations on the Performance of the EU DEMO Fusion Power Plant Reactor

Heating and current drive (H&CD) systems are being investigated for a demonstration fusion power plant DEMO to deliver net electricity for the grid around 2050. Compared to ITER, which has to show the generation of 500-MW thermal power, the target of DEMO is the successful production of 300 to 500 MW electrical power to the grid and to aim for a self-sufficient tritium fuel cycle. Three H&CD systems are under development for DEMO in Europe, the electron cyclotron (EC) system, the neutral beam injection (NBI) system, and the ion cyclotron system. Based on present studies for plasma ramp-up, ramp-down, and flat top phases, to be further validated in more detailed simulations, the assumed total launched power needed from the H&CD system in DEMO is in the range of 50–100 MW, to be provided for plasma heating and control. This paper describes the design and Research and Development status of selected H&CD systems, considered for their deployment in the EU DEMO. It was always considered that different H&CD configurations and design variants will have an impact on the performances for the whole fusion plant. It shall be noted that the basis for the H&CD integrated design and system development is the actual version of the European fusion electricity roadmap. The project also elaborates on H&CD efficiency improvements which will reduce the recirculating power fraction in the future fusion power plants. Different studies under investigation will be discussed such as for NBI the photoneutralization and for EC novel concepts for gyrotron multistage-depressed collector.

[1]  John Jelonnek,et al.  EU DEMO Heating and Current Drive: Physics and Technology , 2017 .

[2]  P. Vincenzi,et al.  The physics and technology basis entering European system code studies for DEMO , 2016 .

[3]  John Jelonnek,et al.  Preliminary conceptual design of DEMO EC system , 2015 .

[4]  Ivo Furno,et al.  Conceptual design of the beam source for the DEMO Neutral Beam Injectors , 2016 .

[5]  G. Granucci,et al.  DEMO port plug design and integration studies , 2017 .

[6]  John Jelonnek,et al.  Conceptual design of the EU DEMO EC-system: main developments and R&D achievements , 2017 .

[7]  Timothy Goodman,et al.  Overview of the ITER EC H&CD system and its capabilities , 2011 .

[8]  P. Vincenzi,et al.  Conceptual design of the DEMO neutral beam injectors: main developments and R&D achievements , 2017 .

[9]  M. Gadomska,et al.  Overview of EU DEMO design and R&D activities , 2014 .

[10]  David Ward,et al.  “PROCESS”: A systems code for fusion power plants—Part 1: Physics , 2014 .

[11]  G. Granucci,et al.  On the present status of the EU demo H&CD systems, technology, functions and mix , 2015, 2015 IEEE 26th Symposium on Fusion Engineering (SOFE).

[12]  Stefan Illy,et al.  Influence of emitter ring manufacturing tolerances on electron beam quality of high power gyrotrons , 2016 .

[13]  R. Ragona,et al.  Study of a distributed ICRF antenna system in DEMO , 2017 .

[14]  G. Granucci,et al.  EU DEMO transient phases: Main constraints and heating mix studies for ramp-up and ramp-down , 2017 .

[15]  Tony Donné.  Challenges on the road towards fusion electricity , 2016 .

[16]  Ivo Furno,et al.  Helicon wave-generated plasmas for negative ion beams for fusion , 2017 .

[17]  John Jelonnek,et al.  Design of E × B multistage depressed collector concepts for high-power fusion gyrotrons , 2017, 2017 42nd International Conference on Infrared, Millimeter, and Terahertz Waves (IRMMW-THz).

[18]  John Jelonnek,et al.  EU DEMO EC system preliminary conceptual design , 2018, Fusion Engineering and Design.

[19]  John Jelonnek,et al.  Design considerations for future DEMO gyrotrons: A review on related gyrotron activities within EUROfusion , 2017 .

[20]  John Jelonnek,et al.  Multistage depressed collector conceptual design for thin magnetically confined electron beams , 2016 .

[21]  John Jelonnek,et al.  Study of the Influence of Stray Magnetic Fields on the Operation of the European Gyrotron for ITER , 2017, IEEE Transactions on Electron Devices.

[22]  P. Vincenzi,et al.  Comparison of Neutral Beam Injection options for EU DEMO pulsed scenario , 2017 .

[23]  Th. Franke,et al.  Integrating a distributed antenna in DEMO: Requirements and challenges , 2017 .

[24]  B. P. Duval,et al.  Spectroscopic characterization of H 2 and D 2 helicon plasmas generated by a resonant antenna for neutral beam applications in fusion , 2017 .

[25]  R. S. Hemsworth,et al.  Overview of the design of the ITER heating neutral beam injectors , 2017 .

[26]  S. Alberti,et al.  A New Concept for the Collection of an Electron Beam Configured by an Externally Applied Axial Magnetic Field , 2008, IEEE Transactions on Plasma Science.

[27]  S. Alberti,et al.  Study of the ITER Stray Magnetic Field Effect on the EU 170-GHz 2-MW Coaxial Cavity Gyrotron , 2012, IEEE Transactions on Plasma Science.

[28]  J. B. Lister,et al.  The CRONOS suite of codes for integrated tokamak modeling (topical review) , 2010 .

[29]  John Jelonnek,et al.  Novel multistage depressed collector for high power fusion gyrotrons based on an E×B drift concept , 2017, 2017 Eighteenth International Vacuum Electronics Conference (IVEC).

[30]  John Jelonnek,et al.  Multi-frequency design of a 2 MW coaxial-cavity gyrotron for DEMO , 2015, 2015 40th International Conference on Infrared, Millimeter, and Terahertz waves (IRMMW-THz).

[31]  J. Jelonnek,et al.  Cooling concepts for the CVD diamond brewster-angle window , 2017, 2017 42nd International Conference on Infrared, Millimeter, and Terahertz Waves (IRMMW-THz).

[32]  John Jelonnek,et al.  Gyrotron multistage depressed collector based on E × B drift concept using azimuthal electric field. I. Basic design , 2018 .

[33]  B. Duval,et al.  Negative ion source development for a photoneutralization based neutral beam system for future fusion reactors , 2016 .

[34]  John Jelonnek,et al.  Electron trapping mechanisms in magnetron injection guns , 2016 .

[35]  P. Barabaschi,et al.  Fusion electricity: a roadmap to the realization of fusion energy , 2012 .

[36]  R. Mitteau,et al.  Heating neutral beams for ITER: negative ion sources to tune fusion plasmas , 2017 .

[37]  B. Heinemann,et al.  Towards powerful negative ion beams at the test facility ELISE for the ITER and DEMO NBI systems , 2017 .