Development of tungsten divertor components for ITER in Japan
The refined design of full-W ITER divertor outer vertical targets (OVT) has the combination of plasma-facing units (PFUs) variants with bevelled W monoblocks to prevent leading edge overheating. Full-length PFU prototypes have withstood against the repetitive heat load of 20MW/m2 and they met the re...
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Veröffentlicht in: | Fusion engineering and design 2018-11, Vol.136, p.683-689 |
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Hauptverfasser: | , , , , , , |
Format: | Artikel |
Sprache: | eng |
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Zusammenfassung: | The refined design of full-W ITER divertor outer vertical targets (OVT) has the combination of plasma-facing units (PFUs) variants with bevelled W monoblocks to prevent leading edge overheating. Full-length PFU prototypes have withstood against the repetitive heat load of 20MW/m2 and they met the requirements for W technologies qualification programed by the IO. Upon the successful results, JADA has launched series of qualification programs toward the mass production of components. Furthermore, JADA successfully verified the water flow design inside the OVT is fulfilling the ITER requirements. The flow test was done using a OVT prototype with dummy cooling tubes. |
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ISSN: | 0920-3796 1873-7196 |
DOI: | 10.1016/j.fusengdes.2018.03.057 |