Journal ArticleDOI
Disruption Scenarios, their Mitigation and Operation Window in ITER
Masayoshi Sugihara,Michiya Shimada,H. Fujieda,Yu. Gribov,K. Ioki,Yasunori Kawano,R.R. Khayrutdinov,V.E. Lukash,J. Ohmori +8 more
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In this paper, the impacts of plasma disruptions on ITER have been investigated in detail to confirm the robustness of the design of the machine to the potential consequential loads, including both electro-magnetic (EM) and heat loads on the in-vessel components and the vacuum vessel.Abstract:
The impacts of plasma disruptions on ITER have been investigated in detail to confirm the robustness of the design of the machine to the potential consequential loads. The loads include both electro-magnetic (EM) and heat loads on the in-vessel components and the vacuum vessel. Several representative disruption scenarios are specified based on newly derived physics guidelines for the shortest current quench time as well as the maximum product of halo current fraction and toroidal peaking factor arising from disruptions in ITER. Disruption simulations with the DINA code and EM load analyses with a 3D finite element method code are performed for these scenarios. Some margins are confirmed in the EM load on in-vessel components due to induced eddy and halo currents for these representative scenarios. However, the margins are not very large. The heat load on various parts of the first wall due to the vertical movement and the thermal quench (TQ) is calculated with a 2D heat conduction code based on the database of heat deposition during disruptions and simulation results with the DINA code. For vertical displacement event, it is found that the beryllium (Be) wall does not melt during the vertical movement, prior to the TQ. Significant melting is anticipated for the upper Be wall and the tungsten divertor baffle due to TQ after the vertical movement. However, its impact could be substantially mitigated by implementing a reliable detection system of the vertical movement and a mitigation system, e.g. massive noble gas injection. Some melting of the upper Be wall is anticipated at major disruptions. At least several tens of unmitigated disruptions must be considered even if an advanced prediction/mitigation system is implemented. With these unmitigated disruptions, the loss of the Be layer is expected to be within ?30?100??m/event out of a 10?mm thick Be first wall.read more
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Journal ArticleDOI
Physics basis and design of the ITER plasma-facing components
R.A. Pitts,S. Carpentier,Frederic Escourbiac,T. Hirai,V. Komarov,A.S. Kukushkin,S.W. Lisgo,A. Loarte,Mario Merola,R. Mitteau,A.R. Raffray,Michiya Shimada,P.C. Stangeby +12 more
TL;DR: The ITER PFC design has now reached a rather mature stage following the 2007 ITER Design Review as discussed by the authors, and the key elements of the design, reviews the physics drivers, essentially thermal load specifications, which have defined the concept and discusses a selection of material and design issues.
Journal ArticleDOI
Disruptions in ITER and strategies for their control and mitigation
Michael Lehnen,K. Aleynikova,P. Aleynikov,David Campbell,P. Drewelow,N.W. Eidietis,Yu. Gasparyan,Robert Granetz,Y. Gribov,N. Hartmann,E. M. Hollmann,V.A. Izzo,S. Jachmich,S.H. Kim,M. Kocan,H. R. Koslowski,D. V. Kovalenko,U. Kruezi,A. Loarte,S. Maruyama,G. F. Matthews,P. B. Parks,G. Pautasso,R.A. Pitts,C. Reux,V. Riccardo,R. Roccella,J. A. Snipes,A.J. Thornton,P. de Vries,Efda Jet Contributors +30 more
TL;DR: In this paper, a brief overview on the disruption loads and mitigation strategies for ITER and the physics basis which is continuously refined through the current disruption R&D programs is discussed.
Journal ArticleDOI
Disruption mitigation by massive gas injection in JET
Michael Lehnen,A. Alonso,G. Arnoux,N. Baumgarten,S. A. Bozhenkov,S. Brezinsek,M. Brix,T. Eich,Sergei Gerasimov,A. Huber,S. Jachmich,U. Kruezi,P. D. Morgan,V. V. Plyusnin,C. Reux,V. Riccardo,Gennady Sergienko,M. F. Stamp,Jet-Efda Contributors +18 more
TL;DR: In this article, a fast disruption mitigation valve has been installed at JET to study mitigation by massive gas injection and different gas species and amounts have been investigated with respect to timescales and mitigation efficiency.
References
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Journal ArticleDOI
Chapter 1: Overview and summary
TL;DR: The ITER Physics Basis as mentioned in this paper presents and evaluates the physics rules and methodologies for plasma performance projections, which provide the basis for the design of a tokamak burning plasma device whose goal is to demonstrate the scientific and technological feasibility of fusion energy for peaceful purposes.
Journal ArticleDOI
Theory for avalanche of runaway electrons in tokamaks
M.N. Rosenbluth,S.V. Putvinski +1 more
TL;DR: In this paper, an analysis of runaway electron formation and its evolution during disruptions in large tokamaks, where avalanche phenomena play a crucial role, is presented, but sufficiently accurate, analytical model suitable for one dimensional (1-D) transport codes is proposed.
Journal ArticleDOI
Plasma confinement in JET H?mode plasmas with H, D, DT and T isotopes
J.G. Cordey,B. Balet,D.V. Bartlett,Robert Budny,J.P. Christiansen,G. D. Conway,L.-G. Eriksson,G.M. Fishpool,C. Gowers,J.C.M. de Haas,P.J. Harbour,L. D. Horton,A. Howman,J. Jacquinot,Wolfgang Kerner,C.G. Lowry,R.D. Monk,P. Nielsen,E. Righi,F.G. Rimini,G. Saibene,R. Sartori,B. Schunke,A. C. C. Sips,Richard J.H. Smith,M.F. Stamp,D.F.H. Start,K. Thomsen,B.J.D. Tubbing,M. von Hellermann +29 more
TL;DR: In this article, the scaling of the energy confinement in H mode plasmas with different hydrogenic isotopes (hydrogen, deuterium, DT and tritium) is investigated in JET.
Journal ArticleDOI
Studies of plasma equilibrium and transport in a Tokamak fusion device with the inverse-variable technique
R. R. Khayrutdinov,V.E. Lukash +1 more
TL;DR: In this paper, an accurate and efficient model for studying the evolution of tokamak plasmas is described, where the equilibrium problem for a plasma with a free boundary is solved using the "inverse variable" technique.
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