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Diagnostics Complex of the First Wall and Divertor of Tokamak with Reactor Technologies: Control of Erosion and Temperature and Monitoring of Fusion Fuel Build-up

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Abstract

A project is proposed of the complex of diagnostics of the plasma-facing elements of the first wall and divertor of tokamak with reactor technologies (TRT). The main objectives of the complex are control of the integrity of plasma-facing elements, monitoring of the state of the first wall and the thermal flows onto the first wall and divertor targets as well as studies of the physical processes in the material of the first wall during its interaction with plasma. A review of expected effects of interaction of plasma with the plasma-facing elements is given; in the first place, with the tungsten facing of the divertor. Based on the analysis of the methods that were tested at existing tokamaks and methods that are being developed within the framework of the international ITER project, a complex of complementary diagnostics is proposed, which satisfies the TRT tasks. In the paper, a variant of implementation at TRT is discussed of frequency/amplitude modulated laser radar, two-wavelength digital holography, active (laser) and passive IR thermography, diagnostics of fuel build-up based on laser desorption and ablation, and the placement of witness samples. A variant is proposed of the placement of these diagnostics at TRT and their physical integration.

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Funding

The formulation of the problems for the development of the diagnostics complex of the first wall of TRT (Section 2) was carried out with the support of the Ministry of Science and Higher Education of the Russian Federation (contract no. 0723-2020-0043). The choice and justification of physical methods were also done with the support of the Ministry of Science and Higher Education of the Russian Federation (contract no. 0034-2019-0001). The development of variants of implementation of the diagnostics complex at the tokamak and the analysis of the expected measurement accuracy (Section 4) were supported by the Russian Science Foundation (project no. 22-12-00360).

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Authors and Affiliations

  1. Ioffe Physicotechnical Institute, Russian Academy of Sciences, 194021, St. Petersburg, Russia

    A. G. Razdobarin, D. L. Bogachev, A. M. Dmitriev, D. I. Elets, A. N. Koval, G. S. Kurskiev & E. E. Mukhin

  2. National Research Nuclear University “MEPhI”, 115409, Moscow, Russia

    Yu. M. Gasparyan, A. M. Dmitriev, D. I. Elets, D. G. Bulgadaryan, S. A. Krat & E. D. Marenkov

  3. Immanuel Kant Baltic Federal University, 236016, Kaliningrad, Russia

    I. V. Alekseenko

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  1. A. G. Razdobarin
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Razdobarin, A.G., Gasparyan, Y.M., Bogachev, D.L. et al. Diagnostics Complex of the First Wall and Divertor of Tokamak with Reactor Technologies: Control of Erosion and Temperature and Monitoring of Fusion Fuel Build-up. Plasma Phys. Rep. 48, 1389–1403 (2022). https://doi.org/10.1134/S1063780X22700283

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  • DOI: https://doi.org/10.1134/S1063780X22700283

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