Divertor Development for a Future Fusion Power Plant
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...
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| Fformat: | Online |
| Iaith: | Saesneg |
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KIT Scientific Publishing
2021
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| Pynciau: | |
| Mynediad Ar-lein: | 35131 |
| Tagiau: |
Dim Tagiau, Byddwch y cyntaf i dagio'r cofnod hwn!
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| _version_ | 1869526904889933824 |
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| author | Norajitra, Prachai |
| author_browse | Norajitra, Prachai |
| author_facet | Norajitra, Prachai |
| author_sort | Norajitra, Prachai |
| collection | Directory of Open Access Books |
| description | 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. |
| format | Online |
| id | doab-20.500.12854ir-45317 |
| institution | Directory of Open Access Books |
| language | eng |
| publishDate | 2021 |
| publishDateRange | 2021 |
| publishDateSort | 2021 |
| publisher | KIT Scientific Publishing |
| publisherStr | KIT Scientific Publishing |
| record_format | ojs |
| spelling | doab-20.500.12854ir-453172024-04-09T23:15:36Z Divertor Development for a Future Fusion Power Plant Norajitra, Prachai T1-995 machining and joining tungsten Fusion power plant high heat flux tests helium impingement cooling helium-cooled divertor thema EDItEUR::T Technology, Engineering, Agriculture, Industrial processes::TB Technology: general issues 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. 2021-02-11T11:37:09Z 2021-02-11T11:37:09Z 2019-07-30 20:02:00 2011 book 35131 21929963 9783866447387 https://directory.doabooks.org/handle/20.500.12854/45317 eng Schriftenreihe des Instituts für Angewandte Materialien, Karlsruher Institut für Technologie image/jpeg Attribution-NonCommercial-NoDerivatives 4.0 International https://www.ksp.kit.edu/9783866447387 KIT Scientific Publishing 10.5445/KSP/1000024270 10.5445/KSP/1000024270 68fffc18-8f7b-44fa-ac7e-0b7d7d979bd2 9783866447387 VI, 136 p. open access |
| spellingShingle | T1-995 machining and joining tungsten Fusion power plant high heat flux tests helium impingement cooling helium-cooled divertor thema EDItEUR::T Technology, Engineering, Agriculture, Industrial processes::TB Technology: general issues Norajitra, Prachai Divertor Development for a Future Fusion Power Plant |
| title | Divertor Development for a Future Fusion Power Plant |
| title_full | Divertor Development for a Future Fusion Power Plant |
| title_fullStr | Divertor Development for a Future Fusion Power Plant |
| title_full_unstemmed | Divertor Development for a Future Fusion Power Plant |
| title_short | Divertor Development for a Future Fusion Power Plant |
| title_sort | divertor development for a future fusion power plant |
| topic | T1-995 machining and joining tungsten Fusion power plant high heat flux tests helium impingement cooling helium-cooled divertor thema EDItEUR::T Technology, Engineering, Agriculture, Industrial processes::TB Technology: general issues |
| topic_facet | T1-995 machining and joining tungsten Fusion power plant high heat flux tests helium impingement cooling helium-cooled divertor thema EDItEUR::T Technology, Engineering, Agriculture, Industrial processes::TB Technology: general issues |
| url | 35131 |
| work_keys_str_mv | AT norajitraprachai divertordevelopmentforafuturefusionpowerplant |