Thermonuclear Fusion Reactor Plasma-Facing Materials under Conditions of Ion Irradiation and Plasma Flux

A review of experimental studies carried out at the NRC “Kurchatov Institute” on plasma-facing thermonuclear fusion reactor materials is presented in the paper. An experimental method was developed to produce high-level radiation damage in materials simulating the neutron effect by surrogate irradia...

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Autores principales:	Boris I. Khripunov, Vasily S. Koidan, Evgeny V. Semenov
Formato:	article
Lenguaje:	EN
Publicado:	MDPI AG 2021
Materias:	fusion reactor plasma ions high energy microstructure Mathematics QA1-939
Acceso en línea:	https://doaj.org/article/72c311e82e5749eb9193e24b9a916f0a
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spelling	oai:doaj.org-article:72c311e82e5749eb9193e24b9a916f0a2021-11-25T19:06:34ZThermonuclear Fusion Reactor Plasma-Facing Materials under Conditions of Ion Irradiation and Plasma Flux10.3390/sym131120812073-8994https://doaj.org/article/72c311e82e5749eb9193e24b9a916f0a2021-11-01T00:00:00Zhttps://www.mdpi.com/2073-8994/13/11/2081https://doaj.org/toc/2073-8994A review of experimental studies carried out at the NRC “Kurchatov Institute” on plasma-facing thermonuclear fusion reactor materials is presented in the paper. An experimental method was developed to produce high-level radiation damage in materials simulating the neutron effect by surrogate irradiation with high-energy ions. Plasma-surface interaction is investigated on materials irradiated to high levels of radiation damage in high-flux deuterium plasma. The total fluence of accelerated ions (3–30 MeV, <sup>4</sup>He<sup>2+</sup>, <sup>12</sup>C<sup>3+</sup>, <sup>14</sup>N<sup>3+</sup>, protons) on the samples was 10<sup>21</sup>–10<sup>23</sup> m<sup>−2</sup>. Experiments were carried out on graphite materials, tungsten, and silicon carbide. Samples have been obtained with a primary defect concentration from 0.1 to 100 displacements per atom, which covers the predicted damage for the ITER and DEMO projects. Erosion dynamics of the irradiated materials in steady-state deuterium plasma, changes of the surface microstructure, and deuterium retention were studied using SEM, TEM, ERDA, TDS, and nuclear backscattering techniques. The surface layer of the materials (3 to hundreds µm) was investigated, and it was shown that the changes in the crystal structure, the loss of their symmetry, and diffusion of defects to grain boundaries play an important role. The most significant results are presented in the paper as an overview of our previous work for many years (carbon and tungsten materials) as well as the relatively recent results (silicon carbide).Boris I. KhripunovVasily S. KoidanEvgeny V. SemenovMDPI AGarticlefusionreactorplasmaionshigh energymicrostructureMathematicsQA1-939ENSymmetry, Vol 13, Iss 2081, p 2081 (2021)
institution	DOAJ
collection	DOAJ
language	EN
topic	fusion reactor plasma ions high energy microstructure Mathematics QA1-939
spellingShingle	fusion reactor plasma ions high energy microstructure Mathematics QA1-939 Boris I. Khripunov Vasily S. Koidan Evgeny V. Semenov Thermonuclear Fusion Reactor Plasma-Facing Materials under Conditions of Ion Irradiation and Plasma Flux
description	A review of experimental studies carried out at the NRC “Kurchatov Institute” on plasma-facing thermonuclear fusion reactor materials is presented in the paper. An experimental method was developed to produce high-level radiation damage in materials simulating the neutron effect by surrogate irradiation with high-energy ions. Plasma-surface interaction is investigated on materials irradiated to high levels of radiation damage in high-flux deuterium plasma. The total fluence of accelerated ions (3–30 MeV, <sup>4</sup>He<sup>2+</sup>, <sup>12</sup>C<sup>3+</sup>, <sup>14</sup>N<sup>3+</sup>, protons) on the samples was 10<sup>21</sup>–10<sup>23</sup> m<sup>−2</sup>. Experiments were carried out on graphite materials, tungsten, and silicon carbide. Samples have been obtained with a primary defect concentration from 0.1 to 100 displacements per atom, which covers the predicted damage for the ITER and DEMO projects. Erosion dynamics of the irradiated materials in steady-state deuterium plasma, changes of the surface microstructure, and deuterium retention were studied using SEM, TEM, ERDA, TDS, and nuclear backscattering techniques. The surface layer of the materials (3 to hundreds µm) was investigated, and it was shown that the changes in the crystal structure, the loss of their symmetry, and diffusion of defects to grain boundaries play an important role. The most significant results are presented in the paper as an overview of our previous work for many years (carbon and tungsten materials) as well as the relatively recent results (silicon carbide).
format	article
author	Boris I. Khripunov Vasily S. Koidan Evgeny V. Semenov
author_facet	Boris I. Khripunov Vasily S. Koidan Evgeny V. Semenov
author_sort	Boris I. Khripunov
title	Thermonuclear Fusion Reactor Plasma-Facing Materials under Conditions of Ion Irradiation and Plasma Flux
title_short	Thermonuclear Fusion Reactor Plasma-Facing Materials under Conditions of Ion Irradiation and Plasma Flux
title_full	Thermonuclear Fusion Reactor Plasma-Facing Materials under Conditions of Ion Irradiation and Plasma Flux
title_fullStr	Thermonuclear Fusion Reactor Plasma-Facing Materials under Conditions of Ion Irradiation and Plasma Flux
title_full_unstemmed	Thermonuclear Fusion Reactor Plasma-Facing Materials under Conditions of Ion Irradiation and Plasma Flux
title_sort	thermonuclear fusion reactor plasma-facing materials under conditions of ion irradiation and plasma flux
publisher	MDPI AG
publishDate	2021
url	https://doaj.org/article/72c311e82e5749eb9193e24b9a916f0a
work_keys_str_mv	AT borisikhripunov thermonuclearfusionreactorplasmafacingmaterialsunderconditionsofionirradiationandplasmaflux AT vasilyskoidan thermonuclearfusionreactorplasmafacingmaterialsunderconditionsofionirradiationandplasmaflux AT evgenyvsemenov thermonuclearfusionreactorplasmafacingmaterialsunderconditionsofionirradiationandplasmaflux
_version_	1718410284184371200

Thermonuclear Fusion Reactor Plasma-Facing Materials under Conditions of Ion Irradiation and Plasma Flux

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