Revisiting Carbon Materials as Plasma-Facing Materials of a Fusion Reactor

Carbon materials (C) are revisited to use as a plasma-facing material (PFM) of a fusion reactor. Characteristics of C concerned, such as erosion, redeposition, H retention, and neutron damages, are reinvestigated considering recent observations in laboratories and plasma machines, in particular, JET...

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Bibliographic Details
Published inPlasma physics reports Vol. 45; no. 4; pp. 300 - 314
Main Author Tanabe, T.
Format Journal Article
LanguageEnglish
Published Moscow Pleiades Publishing 01.04.2019
Springer Nature B.V
Subjects
Armor
Atomic
Carbon
Erosion
Fusion reactors
Heat exchange
Molecular
Neutron irradiation
Neutrons
Optical and Plasma Physics
Physics
Physics and Astronomy
Remote handling
Tiles
Tokamaks
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Summary:Carbon materials (C) are revisited to use as a plasma-facing material (PFM) of a fusion reactor. Characteristics of C concerned, such as erosion, redeposition, H retention, and neutron damages, are reinvestigated considering recent observations in laboratories and plasma machines, in particular, JET and JT-60U. It is concluded that C can be a good PFM of a fusion reactor if they are used as armor tiles mechanically fixed to heat sink allowing possible temperature escalation of tile surfaces, which mitigate T retention and neutron irradiation effect. The mechanical fixing ensures easy replacement of the carbon armor tiles by remote handling and periodic break for reactor maintenance gives opportunity for routine replacements of the armor tiles. In addition, routine T removal by isotopic exchange with D discharges and installation of replaceable cooled plates at divertor area to take up redeposited C incorporating with T would significantly reduce T inventory in a rector.
ISSN:1063-780X
1562-6938
DOI:10.1134/S1063780X1904007X