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First wall energy d...
First wall energy deposition during vertical displacement events on ITER
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- Coburn, J. (författare)
- ITER Org, Route Vinon Sur Verdon,CS 90 046, F-13067 St Paul Les Durance, France.
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- Thorén, Emil (författare)
- KTH,Rymd- och plasmafysik
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- Pitts, R. A. (författare)
- ITER Org, Route Vinon Sur Verdon,CS 90 046, F-13067 St Paul Les Durance, France.
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- Anand, H. (författare)
- ITER Org, Route Vinon Sur Verdon,CS 90 046, F-13067 St Paul Les Durance, France.
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- Lehnen, M. (författare)
- ITER Org, Route Vinon Sur Verdon,CS 90 046, F-13067 St Paul Les Durance, France.
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- Kos, L. (författare)
- Univ Ljubljana, LECAD Lab, Mech Engn, Ljubljana, Slovenia.
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- Brank, M. (författare)
- Univ Ljubljana, LECAD Lab, Mech Engn, Ljubljana, Slovenia.
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- Ratynskaia, Svetlana V. (författare)
- KTH,Rymd- och plasmafysik
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- Tolias, Panagiotis, 1984- (författare)
- KTH,Rymd- och plasmafysik
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ITER Org, Route Vinon Sur Verdon,CS 90 046, F-13067 St Paul Les Durance, France Rymd- och plasmafysik (creator_code:org_t)
- 2020-06-30
- 2020
- Engelska.
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Ingår i: Physica Scripta. - : IOP Publishing. - 0031-8949 .- 1402-4896. ; T171:1
- Relaterad länk:
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https://urn.kb.se/re...
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https://doi.org/10.1...
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Abstract
Ämnesord
Stäng
- The beryllium (Be) first wall energy deposition and melt damage profiles resulting from the current quench phase of an unmitigated, 5 MA/1.8 T upward vertical displacement event for ITER are investigated. Time dependent 2D magnetic flux profiles are calculated with the DINA code and used as input for the SMITER 3D field line tracing software. 3D maps of the wetted area and perpendicular heat flux q(perpendicular to) show that the majority of the energy deposition occurs on the upper first wall panels #8 and #9 SMITER simulations predict q(perpendicular to,peak) approximate to 190 MW m(-2) on the surfaces of upper FWPs #8 and #9 at the end of the similar to 450 ms current quench. The surface heat flux maps generated by SMITER are used as input in the MEMOS-U code, which models Be melt formation and dynamics. Simulations reveal peak surface temperatures of similar to 2200 K, inward surface damage of similar to 0.5 mm in depth, and average melt velocities of similar to 2 m s(-1). Although VDEs are in principle the easiest disruptive instability to avoid, the analysis demonstrates that any non-mitigated events or intentional VDEs taking place during low I-p, early operational phases of ITER for the purposes of estimating disruption forces, must be kept to a low number.
Ämnesord
- NATURVETENSKAP -- Fysik -- Fusion, plasma och rymdfysik (hsv//swe)
- NATURAL SCIENCES -- Physical Sciences -- Fusion, Plasma and Space Physics (hsv//eng)
Nyckelord
- current quench
- melt motion
- first wall
- heat load
- MEMOS-U
- SMITER
Publikations- och innehållstyp
- ref (ämneskategori)
- art (ämneskategori)
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