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Disruption Scenarios, their Mitigation and Operation Window in ITER

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TLDR
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.

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Citations
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Fusion 如果,爱

小倩, +1 more
TL;DR: Fusion,四个来自上海的大男孩 as discussed by the authors,2008年第一周,他们发行属于
Journal ArticleDOI

Physics basis and design of the ITER plasma-facing components

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

Disruption mitigation by massive gas injection in JET

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

David Campbell
- 01 Dec 1999 - 
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.

Fusion 如果,爱

小倩, +1 more
TL;DR: Fusion,四个来自上海的大男孩 as discussed by the authors,2008年第一周,他们发行属于
Journal ArticleDOI

Theory for avalanche of runaway electrons in tokamaks

M.N. Rosenbluth, +1 more
- 01 Oct 1997 - 
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

Studies of plasma equilibrium and transport in a Tokamak fusion device with the inverse-variable technique

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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