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WFRF:(Weckmann Armin)
 

Sökning: WFRF:(Weckmann Armin) > Doktorsavhandling > Material migration ...

Material migration in tokamaks : Erosion-deposition patterns and transport processes

Weckmann, Armin (författare)
KTH,Fusionsplasmafysik
Rubel, Marek, Prof. Dr (preses)
KTH,Fusionsplasmafysik
Neu, Rudolf, Prof. Dr (opponent)
Max Planck Institute of Plasma Physics, Garching, Germany; Technical University of Munich, Garching, Germany
 (creator_code:org_t)
ISBN 9789177294610
Stockholm : KTH Royal Institute of Technology, 2017
Engelska 109 s.
Serie: TRITA-EE, 1653-5146 ; 2017:060
  • Doktorsavhandling (övrigt vetenskapligt/konstnärligt)
Abstract Ämnesord
Stäng  
  • Controlled thermonuclear fusion may become an attractive future electrical power source. The most promising of all fusion machine concepts is called a tokamak. The fuel, a plasma made of deuterium and tritium, must be confined to enable the fusion process. It is also necessary to protect the wall of tokamaks from erosion by the hot plasma. To increase wall lifetime, the high-Z metal tungsten is foreseen as wall material in future fusion devices due to its very high melting point. This thesis focuses on the following consequences of plasma impact on a high-Z wall: (i) erosion, transport and deposition of high-Z wall materials; (ii) fuel retention in tokamak walls; (iii) long term effects of plasma impact on structural machine parts; (iv) dust production in tokamaks.An extensive study of wall components has been conducted with ion beam analysis after the final shutdown of the TEXTOR tokamak. This unique possibility offered by the shutdown combined with a tracer experiment led to the largest study of high-Z metal migration and fuel retention ever conducted. The most important results are: - transport is greatly affected by drifts and flows in the plasma edge;- stepwise transport along wall surfaces takes place mainly in the toroidal direction;- fuel retention is highest on slightly retracted wall elements;- fuel retention is highly inhomogeneous. A broad study on structural parts of a tokamak has been conducted on the TEXTOR liner. The plasma impact does neither degrade mechanical properties nor lead to fuel diffusion into the bulk after 26 years of duty time. Peeling deposition layers on the liner retain fuel in the order of 1g and represent a dust source. Only small amounts of dust are found in TEXTOR with overall low deuterium content. Security risks in future fusion devices due to dust explosions or fuel retention in dust are hence of lesser concern.

Ämnesord

TEKNIK OCH TEKNOLOGIER  -- Elektroteknik och elektronik -- Annan elektroteknik och elektronik (hsv//swe)
ENGINEERING AND TECHNOLOGY  -- Electrical Engineering, Electronic Engineering, Information Engineering -- Other Electrical Engineering, Electronic Engineering, Information Engineering (hsv//eng)

Nyckelord

TEXTOR
fusion
plasma physics
transport
migration
tracers
tokamak
limiter
divertor
high-Z
ion beam analysis
Rutherford backscattering
Nuclear reaction analysis
Elastic recoil detection analysis
Electrical Engineering
Elektro- och systemteknik

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