Performance and lifetime assessment of reactor wall and nearby components during plasma instabilities.

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Description

Surface and structural damage to plasma-facing components due to the frequent loss of plasma confinement is a serious problem for the tokamak reactor concept. The plasma energy deposited on these components during loss of confinement causes significant surface erosion, possible structural failure, and frequent plasma contamination. Surface damage consists of vaporization, spallation, and liquid splatter of metallic materials. Comprehensive multidimensional models that include thermodynamics and thermal hydraulics of plasma-facing materials, eroded-debris/vapor atomic physics and magnetohydrodynamics, resulting photon radiation and photon transport, as well as liquid splashing and brittle destruction of materials, are used self-consistently to evaluate and assess our current ... continued below

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29 p.

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Hassanein, A. March 10, 1998.

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Description

Surface and structural damage to plasma-facing components due to the frequent loss of plasma confinement is a serious problem for the tokamak reactor concept. The plasma energy deposited on these components during loss of confinement causes significant surface erosion, possible structural failure, and frequent plasma contamination. Surface damage consists of vaporization, spallation, and liquid splatter of metallic materials. Comprehensive multidimensional models that include thermodynamics and thermal hydraulics of plasma-facing materials, eroded-debris/vapor atomic physics and magnetohydrodynamics, resulting photon radiation and photon transport, as well as liquid splashing and brittle destruction of materials, are used self-consistently to evaluate and assess our current understanding of the lifetime of plasma-facing materials and the various forms of damage they experience. Models are developed to study the stability of the vapor shielding layer, erosion of the melt-layer, brittle destruction/explosive erosion, and the issues involved therein.

Physical Description

29 p.

Notes

INIS; OSTI as DE00010680

Medium: P; Size: 29 pages

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  • 8th International Conference on Fusion Reactor Materials (ICFRM-8), Sendai (JP), 10/26/1997--10/31/1997

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  • Report No.: ANL/TD/CP-95857
  • Grant Number: W-31109-ENG-38
  • Office of Scientific & Technical Information Report Number: 10680
  • Archival Resource Key: ark:/67531/metadc624300

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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.

Office of Scientific and Technical Information (OSTI) is the Department of Energy (DOE) office that collects, preserves, and disseminates DOE-sponsored research and development (R&D) results that are the outcomes of R&D projects or other funded activities at DOE labs and facilities nationwide and grantees at universities and other institutions.

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  • March 10, 1998

Added to The UNT Digital Library

  • June 16, 2015, 7:43 a.m.

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  • April 10, 2017, 7:08 p.m.

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Hassanein, A. Performance and lifetime assessment of reactor wall and nearby components during plasma instabilities., article, March 10, 1998; Illinois. (digital.library.unt.edu/ark:/67531/metadc624300/: accessed October 17, 2017), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.