Lifetime evaluation of plasma-facing materials during a tokamak disruption

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Erosion losses of plasma-facing materials in a tokamak reactor during major disruptions, giant ELMS, and large power excursions are serious concerns that influence component survivability and overall lifetime. Two different mechanisms lead to material erosion during these events: surface vaporization and loss of the melt layer. Hydrodynamics and radiation transport in the rapidly developed vapor-cloud region above the exposed area are found to control and determine the net erosion thickness from surface vaporization. A comprehensive self-consistent kinetic model has been developed in which the time-dependent optical properties and the radiation field of the vapor cloud are calculated in order to ... continued below

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24 p.

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Hassanein, A. & Konkashbaev, I. September 1, 1995.

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  • Hassanein, A. Argonne National Lab., Argonne, IL (United States)
  • Konkashbaev, I. Troitsk Inst. for Innovation, Troitsk (Russian Federation)

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Description

Erosion losses of plasma-facing materials in a tokamak reactor during major disruptions, giant ELMS, and large power excursions are serious concerns that influence component survivability and overall lifetime. Two different mechanisms lead to material erosion during these events: surface vaporization and loss of the melt layer. Hydrodynamics and radiation transport in the rapidly developed vapor-cloud region above the exposed area are found to control and determine the net erosion thickness from surface vaporization. A comprehensive self-consistent kinetic model has been developed in which the time-dependent optical properties and the radiation field of the vapor cloud are calculated in order to correctly estimate the radiation flux at the divertor surface. The developed melt layer of metallic divertor materials will, however, be free to move and can be eroded away due to various forces. , Physical mechanisms that affect surface vaporization and cause melt layer erosion are integrated in a comprehensive model. It is found that for metallic components such as beryllium and tungsten, lifetime due to these abnormal events will be controlled and dominated by the evolution and hydrodynamics of the melt layer during the disruption. The dependence of divertor plate lifetime on various aspects of plasma/material interaction physics is discussed.

Physical Description

24 p.

Notes

INIS; OSTI as DE96007246

Source

  • ICFRM-7: international conference on fusion reactor materials, Obninsk (Russian Federation), 25-29 Sep 1995

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  • Other: DE96007246
  • Report No.: ANL/TD/CP--86326
  • Report No.: CONF-950961--11
  • Grant Number: W-31109-ENG-38
  • Office of Scientific & Technical Information Report Number: 211619
  • Archival Resource Key: ark:/67531/metadc670916

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Office of Scientific & Technical Information Technical Reports

Reports, articles and other documents harvested from the Office of Scientific and Technical Information.

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  • September 1, 1995

Added to The UNT Digital Library

  • June 29, 2015, 9:42 p.m.

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  • Dec. 16, 2015, 12:52 p.m.

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Hassanein, A. & Konkashbaev, I. Lifetime evaluation of plasma-facing materials during a tokamak disruption, article, September 1, 1995; Illinois. (digital.library.unt.edu/ark:/67531/metadc670916/: accessed October 17, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.