High-heat-flux technologies for the European demo divertor targets: State-of-the-art and a review of the latest testing campaign

JOURNAL OF NUCLEAR MATERIALS

卷:544

Review

You, J. H.¹  Visca, E.²  Barrett, T.³  Boeswirth, B.¹  Crescenzi, F.²  Domptail, F.³  Dose, G.⁴  Fursdon, M.³  Gallay, F.⁵  Greuner, H.¹  Hunger, K.¹  Lukenskas, A.³  Mueller, A. V.¹  Richou, M.⁵  Roccella, S.²  Vorpahl, C.⁶  Zhang, K.¹ 

[1] Max Planck Inst Plasma Phys, Boltzmann Str 2, D-85748 Garching, Germany

[2] ENEA, Dept Fus & Technol Nucl Safety & Secur, Via E Fermi 45, I-00044 Frascati, Italy

[3] CCFE, Culham Sci Ctr, Abingdon OX14 3DB, Oxon, England

[4] Univ Roma Tor Vergata, Dipartimento Ingn Ind, Via Politecn 1, I-00133 Rome, Italy

[5] CEA, IRFM, F-13108 St Paul Les Durance, France

[6] EUROfusion, PMU PPPT, Boltzmann Str 2, D-85748 Garching, Germany

关键词: Fusion reactor;    Demo;    Divertor;    Vertical target;    High heat flux;    Tungsten monoblock;   

DOI  :  10.1016/j.jnucmat.2020.152670

来源: Elsevier

【 摘 要 】

Divertor target is one of the most critical in-vessel components in a fusion power plant being in charge of particle and power exhaust. The targets are exposed to severe thermal loads produced by steady bombardment of impinging plasma flux. Since 2014, integrated R&D efforts have been continued aiming at developing a design concept and high-heat-flux (HHF) technologies for divertor targets of the European DEMO reactor. Recently, the second round (2017-2019) of the R&D program has been concluded. As in the first R&D round, five water-cooled target design concepts were further developed and evaluated. Fabrication technologies were improved reaching a consolidated production quality. Extensive HHF tests were conducted using small-scale mock-ups for extended loading regimes (heat flux: 20-32MW/m(2)). Comparative studies were performed to investigate effects of copper interlayer thickness (0.1-1 mm) and different tungsten armor materials. In the present paper, the final results of the second round HHF testing campaign are reported. The HHF performance of each design variant is discussed based on in-situ diagnostic data (infrared thermography), ultrasonic inspection images and postmortem metallographic micrographs. All monoblock-type design concepts passed the specified qualification criterion (>= 500 pulses at 20 MW/m(2), coolant: 130 degrees C) without any failure or armor cracking. Moreover, two of them (ITER-like and composite pipe) remained fully intact even under 25 MW/m(2) (100 pulses) and 32 MW/m(2) (5 pulses). (C) 2020 The Author(s). Published by Elsevier B.V. All rights reserved.

【 授权许可】

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