A 2-D Numerical Simulation of ITER-FEAT Disruptive Hot Plasma-Wall Interaction and Model Validation against Disruption Simulation Experiments-Reference-Cited by-同舟云学术

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A 2-D Numerical Simulation of ITER-FEAT Disruptive Hot Plasma-Wall Interaction and Model Validation against Disruption Simulation Experiments

Published:2001-11 Issue:3 Volume:40 Page:191-246
ISSN:1536-1055
Container-title:Fusion Science and Technology
language:en
Short-container-title:Fusion Science and Technology

Author:

Würz H.¹,Pestchanyi S.²,Landman I.²,Bazylev B.³,Tolkach V.³,Kappler F.⁴

Affiliation:

1. Forschungszentrum Karlsruhe IHM, P.O. Box 3640, D-76021 Karlsruhe, Germany

2. Troitsk Institute for Innovation and Fusion Research, (TRINITI), 142190 Troitsk, Russia

3. Luikov Institute of Heat and Mass Transfer 220072 Minsk, Belarus

4. IHM, P.O. Box 3640, D-76021 Karlsruhe, Germany

Publisher

Informa UK Limited

Subject

Mechanical Engineering,General Materials Science,Nuclear Energy and Engineering,Nuclear and High Energy Physics,Civil and Structural Engineering

Link

https://www.tandfonline.com/doi/pdf/10.13182/FST01-A191

Reference38 articles.

1. Formation and evolution of a wall protective plasma shield in a hard disruption

2. Plasma shield formation and divertor plate erosion for ITER tokamak plasma disruptions

3. Plasma/Surface Interaction in ITER Tokamak Disruption Simulation Experiments

4. Plasma-material interaction under simulated disruption conditions

5. The plasma shield in ITER plasma wall interactions

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1. Numerical simulation of the initial stage of unipolar arcing in fusion-relevant conditions;Plasma Physics and Controlled Fusion;2019-07-23

2. Estimation of suppressed erosion by vapor shielding at Be and W walls under transient loads;Nuclear Fusion;2019-05-22

3. Numerical simulations of tungsten melt layer erosion caused by J×B force at TEXTOR;Physica Scripta;2011-12-01

4. Chapter 4: Power and particle control;Nuclear Fusion;2007-06

5. Simulation of tokamak armour erosion and plasma contamination at intense transient heat fluxes in ITER;Journal of Nuclear Materials;2005-03

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