Plasma and Fusion Research

Volume 16, 2405080 (2021)

Regular Articles

Conceptual Design of the Beamline for the DTT Neutral Beam Injector following a Double Beam Source Design Approach

Piero AGOSTINETTI¹⁾, Eugenio BENEDETTI²⁾, Tommaso BOLZONELLA¹⁾, Massimiliano BONESSO^3,4), Irene CASIRAGHI^5,6), Razvan DIMA³⁾, Giacomo FAVERO³⁾, Alberto FERRO¹⁾, Marco GOBBIN¹⁾, Gustavo GRANUCCI⁵⁾, Chundong HU⁷⁾, Paola MANTICA⁵⁾, Francesco LUCCHINI^1,8), Adriano PEPATO³⁾, Nicola PILAN¹⁾, Fabrizio RAFFAELLI²⁾, Pietro REBESAN^3,9), Afra ROMANO^10,11), Gianluca SPIZZO¹⁾, Fabio VERONESE^1,8), Pietro VINCENZI¹⁾, Yahong XIE⁷⁾ and Yuanlai XIE⁷⁾

1): Consorzio RFX (CNR, ENEA, INFN, Università di Padova, Acciaierie Venete SpA), C.so Stati Uniti 4, 35127 Padova, Italy
2): INFN-Section of Pisa - Polo Fibonacci, Largo B. Pontecorvo 3, 56127 Pisa, Italy
3): INFN-Section of Padova, Via Marzolo 8, 35131 Padova, Italy
4): Dept. of Industrial Engineering, University of Padova, Via Marzolo 9, 35131 Padova, Italy
5): Institute for Plasma Science and Tecnology, Via R. Cozzi 53, 20125 Milano, Italy
6): Dept. of Physics G. Occhialini, Milano-Bicocca University, Piazza della Scienza 3, 20126 Milano, Italy
7): Institute of Plasma physics CAS, Hefei, Anhui 230031, China
8): Dept. of Electrical Engineering, University of Padova, Via Gradenigo, 6/A, Italy
9): Dept. of Mechanical Engineering, Politecnico di Milano, via La Masa 1, 20156 Milano, Italy
10): DTT S.c.a.r.l., Consorzio per l'attuazione del Progetto Divertor Tokamak Test, v. E. Fermi, 45 00044 Frascati, Italy
11): ENEA, Fusion and Technologies for Nuclear Safety Dept, C.R. Frascati, C.P. 65 00044 Frascati, Italy

(Received 19 November 2020 / Accepted 13 April 2021 / Published 18 June 2021)

Abstract

The main purpose of the Divertor Tokamak Test facility (DTT) [1], whose construction is starting in Frascati, Italy, is to study solutions to mitigate the issue of power exhaust in conditions relevant for ITER and DEMO. DTT will be equipped with a significant amount of auxiliary heating power (45 MW) to reach P_SEP/R = 15 MW m⁻¹ required to be DEMO-relevant [2]. DDT is characterized by high flexibility for the assembling and testing of divertor components and for the different magnetic configurations to address the integrated physics and technology problems. The current conceptual design of the beamline for the DTT Neutral Beam Heating system is here presented, with a particular focus on the effect on the DTT plasma and on the technical solutions adopted to maximize the RAMI indexes (Reliability, Availability, Maintainability and Inspectability) and minimize complexity and costs. Various design options were considered, and a comprehensive set of simulations was carried out using several physics and engineering codes to drive the choice of the most suitable design options and optimize them, aiming at finding a good compromise among different requirements. This paper describes the design of the main components of the DTT NBI beamline, explaining the motivations for the main design choices.

Keywords

DTT neutral, beam, injector, conceptual, design

DOI: 10.1585/pfr.16.2405080

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References

[1] DTT Divertor Tokamak Test facility Interim Design Report, ENEA (ISBN 978-88-8286-378-4), April 2019 (“Green Book”), https://www.dtt-dms.enea.it/share/s/avvglhVQT2aSkSgV9vuEtw
[2] R. Albanese et al., DTT: a divertor tokamak test facility for the study of the power exhaust issues in view of DEMO, Nucl. Fusion 57, 016010 (2017).
[3] R. Albanese et al., Design review for the Italian Divertor Tokamak Test facility, Fusion Eng. Des. 146, 194 (2019).
[4] G. Mazzitelli et al., Role of Italian DTT in the power exhaust implementation strategy, Fusion Eng. Des. 146, 932 (2019).
[5] G. Federici et al., Overview of the DEMO staged design approach in Europe, Nucl. Fusion 59, 066013 (2019).
[6] G. Granucci et al., The DTT device: System for heating, Fusion Eng. Des. 122, 349 (2017).
[7] P. Agostinetti et al., Conceptual design of a neutral beam heating & current drive system for DTT, Fusion Eng. Des. 146, 441 (2019).
[8] J.F. Artaud et al., Metis: a fast integrated tokamak modelling tool for scenario design, Nucl. Fusion 58, 105001 (2018).
[9] R.B. White and M.S. Chance, Hamiltonian guiding center drift orbit calculation for plasmas of arbitrary cross section, Phys. Fluids 27, no. 10, 2455 (1984).
[10] TRANSP home page, https://transp.pppl.gov/index.html
[11] R.B. White, Chaos in trapped particle orbits, Phys. Rev. E 58, 1774 (1998).
[12] M. Gobbin et al., Numerical simulations of fast ion loss measurements induced by magnetic islands in the ASDEX Upgrade tokamak, Nucl. Fusion 49, 095021 (2009).
[13] A. Kojima et al., Progress in long-pulse production of powerful negative ion beams for JT-60SA and ITER, Nucl. Fusion 55, 063006 (2015).
[14] Y. Takeiri et al., High Performance of Neutral Beam Injectors for extension of LHD operational regime, Fusion Sci. Technol. 58, 482 (2010).
[15] B. Heinemann et al., Latest achievements of the negative ion beam test facility ELISE, Fusion Eng. Des. 136, 569 (2018).
[16] F. Siviero et al., Characterization of ZAO^® sintered getter material for use in fusion applications, Fusion Eng. Des. 146, 1729 (2019).
[17] P. Agostinetti et al., Physics and engineering design of the Accelerator and Electron Dump for SPIDER, Nucl. Fusion 51, 063004 (2011).
[18] P. Agostinetti et al., Detailed design optimization of the MITICA negative ion accelerator in view of the ITER NBI, Nucl. Fusion 56, 016015 (2016).
[19] P. Agostinetti et al., Manufacturing and Testing of Grid Prototypes for the ITER Neutral Beam Injectors, IEEE Trans. Plasma Sci. 42, 628 (2014).
[20] M. Bonesso et al., Effect of particle size distribution on laser powder bed fusion manufacturability of copper, Proceedings of the 5th Metal Additive Manufacturing Conference 2020, pp. 173-182.