Divertor Development for a Future Fusion Power Plant

• প্রধান লেখক: Norajitra, Prachai (auth)
• বিন্যাস: বৈদ্যুতিক গ্রন্থের অধ্যায়
• ভাষা: ইংরেজি
• প্রকাশিত: KIT Scientific Publishing 2011
• মালা: Schriftenreihe des Instituts für Angewandte Materialien, Karlsruher Institut für Technologie
• বিষয়গুলি: Technology: general issues; machining and joining tungsten; Fusion power plant; high heat flux tests; helium impingement cooling; helium-cooled divertor
• অনলাইন ব্যবহার করুন: DOAB: download the publication; DOAB: description of the publication

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 feasi...