Focus on plasma-facing materials in nuclear fusion reactors

Autor: Dwaipayan Dasgupta, Elodie Bernard, Haishan Zhou, Robert D Kolasinski, Brian D Wirth, Dimitrios Maroudas
Jazyk: angličtina
Rok vydání: 2024
Předmět:
Zdroj: Materials Research Express, Vol 11, Iss 4, p 040201 (2024)
Druh dokumentu: article
ISSN: 2053-1591
DOI: 10.1088/2053-1591/ad36b5
Popis: Fusion energy is a promising, safe, and reliable green energy solution to the increasing energy demand. However, there are several materials challenges that need to be overcome to increase the technical readiness to a level that enables a fusion pilot plant on the grid. This focus issue aims to identify and address a set of such key impediments for realizing deuterium-tritium (D–T) fusion power in a tokamak reactor and highlight the most recent progress on those research frontiers. The main emphasis of this collection is on materials development challenges resulting from helium irradiation, neutron-induced degradation, thermomechanical loading, and the corrosive environment faced by the divertor and first-wall materials, commonly known as plasma-facing components, and blanket systems for tokamak fusion reactors.
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