Tritium in plasma facing components

Recent results on measurements of tritium and other hydrogen isotopes in first wall materials of large tokamaks are discussed and evaluated. Data on the in situ and ex situ release of tritium from plasma facing components under different conditions are assessed.

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Bibliographische Detailangaben
Veröffentlicht in:	Fusion engineering and design 2001-10, Vol.56, p.105-116
Hauptverfasser:	Penzhorn, R.-D, Coad, J.P, Bekris, N, Doerr, L, Friedrich, M, Pilz, W
Format:	Artikel
Sprache:	eng
Schlagworte:	Applied sciences Carbon fibers Chemical vapor deposition Composite materials Controled nuclear fusion plants Energy Energy. Thermal use of fuels Exact sciences and technology Fusion reactors Installations for energy generation and conversion: thermal and electrical energy Plasma theory Thermal conductivity Tokamak devices
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Beschreibung
Zusammenfassung:	Recent results on measurements of tritium and other hydrogen isotopes in first wall materials of large tokamaks are discussed and evaluated. Data on the in situ and ex situ release of tritium from plasma facing components under different conditions are assessed.
ISSN:	0920-3796 1873-7196
DOI:	10.1016/S0920-3796(01)00576-2