| Autor: |
Sergey P. Dzhurik, Sergey I. Kravchuk, N.T. Djigailo, I.E. Lyublinski, Mikhail Yu. Zharkov, Vladislav M. Nesterenko, Anastasiya N. Kostina, Yuri V. Petrov, V.B. Lazarev, S.V. Mirnov, Aleksei V. Vertkov |
| Rok vydání: |
2014 |
| Předmět: |
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| Zdroj: |
Fusion Engineering and Design. 89:2923-2929 |
| ISSN: |
0920-3796 |
| DOI: |
10.1016/j.fusengdes.2014.07.021 |
| Popis: |
T-11M lithium program is focused on a solution of technological issues of a steady-state tokamak with liquid lithium plasma facing components (PFC). Lithium, collected by the chamber wall of such tokamak is able to capture a considerable amount of tritium, which is unacceptable. In order to restrict the level of lithium deposited on the chamber wall and captured tritium it was suggested early to use a cryogenic target technique. Such target placed in the plasma of glow discharge (GDH, He or Ar) during the tokamak conditioning can play the role of collector of lithium and tritium atoms which were sputtered by GD bombardment of the wall. The collected lithium and tritium can be evacuated mechanically together with target from tokamak chamber through vacuum lock without venting. Cryogenic target, cooled by liquid nitrogen (LN), was installed in the T-11M and tested in different modes of wall conditioning and tokamak operations. The maximum speed of the lithium collection during GDH was 3.5 mg/h, that corresponds “to contamination” of wall by lithium during approximately 200 regular shots of T-11M which are equivalent to two-week regular operations. It was established that considerable part of lithium was collected in ionized state. On this basis it can be suggested the creation in tokamak chamber an equivalent ionic pump for extraction both lithium and tritium from chamber without venting during regular tokamak operation. |
| Databáze: |
OpenAIRE |
| Externí odkaz: |
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Full Text from ScienceDirect