Norajitra, Prachai <br/><br/>
Divertor Development for a Future Fusion Power Plant 

 -  KIT Scientific Publishing  2011 
 - 1 electronic resource (VI, 136 p. p.) 
<br/><br/> Open Access 
<br/><br/> Nuclear fusion is considered as a future source of sustainable energy supply. Since the H-mode discovery in ASDEX experiment ""Divertor I"" in 1982, the divertor has been an integral part of all modern tokamaks and stellarators. The major goal of this thesis is to develop a feasible divertor design for a fusion power plant to be built after ITER. The thesis describes the approach in the conceptual development of a helium-cooled divertor and the methods of verification and validation of the design. 
<br/><br/><br/>Creative Commons 
<br/><br/><br/>English 
<br/><br/><label>ISBN: </label>KSP/1000024270 9783866447387 
<br/><br/><label>Standard No.: </label>10.5445/KSP/1000024270  doi 
<br/><br/><label>Subjects--Index Terms: </label>machining and joining tungsten Fusion power plant high heat flux tests helium impingement cooling helium-cooled divertor