ITER plasma safety interface models and assessments

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Description

Physics models and requirements to be used as a basis for safety analysis studies are developed and physics results motivated by safety considerations are presented for the ITER design. Physics specifications are provided for enveloping plasma dynamic events for Category I (operational event), Category II (likely event), and Category III (unlikely event). A safety analysis code SAFALY has been developed to investigate plasma anomaly events. The plasma response to ex-vessel component failure and machine response to plasma transients are considered.

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4 p.

Creation Information

Uckan, N.A.; Bartels, H-W.; Honda, T.; Putvinski, S.; Amano, T.; Boucher, D. et al. December 31, 1996.

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This article is part of the collection entitled: Office of Scientific & Technical Information Technical Reports and was provided by UNT Libraries Government Documents Department to Digital Library, a digital repository hosted by the UNT Libraries. More information about this article can be viewed below.

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Authors

  • Uckan, N.A. Oak Ridge National Lab., TN (United States)
  • Bartels, H-W. ITER San Diego Joint Work Site, La Jolla, CA (United States)
  • Honda, T. Hitachi Ltd., Ibaraki (Japan). Hitachi Research Lab.
  • Putvinski, S. ITER San Diego Joint Work Site, La Jolla, CA (United States)
  • Amano, T. National Inst. for Fusion Science, Nagoya (Japan)
  • Boucher, D.
  • Post, D.
  • Wesley, J. ITER San Diego Joint Work Site, La Jolla, CA (United States)

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Description

Physics models and requirements to be used as a basis for safety analysis studies are developed and physics results motivated by safety considerations are presented for the ITER design. Physics specifications are provided for enveloping plasma dynamic events for Category I (operational event), Category II (likely event), and Category III (unlikely event). A safety analysis code SAFALY has been developed to investigate plasma anomaly events. The plasma response to ex-vessel component failure and machine response to plasma transients are considered.

Physical Description

4 p.

Notes

INIS; OSTI as DE97001656

Source

  • SOFT `96: 19. symposium on fusion technology, Lisbon (Portugal), 16-20 Sep 1996

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Identifier

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  • Other: DE97001656
  • Report No.: CONF-960944--5
  • Grant Number: AC05-96OR22464
  • Office of Scientific & Technical Information Report Number: 435323
  • Archival Resource Key: ark:/67531/metadc681393

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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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Creation Date

  • December 31, 1996

Added to The UNT Digital Library

  • July 25, 2015, 2:20 a.m.

Description Last Updated

  • Aug. 3, 2016, 9:29 p.m.

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Uckan, N.A.; Bartels, H-W.; Honda, T.; Putvinski, S.; Amano, T.; Boucher, D. et al. ITER plasma safety interface models and assessments, article, December 31, 1996; Tennessee. (digital.library.unt.edu/ark:/67531/metadc681393/: accessed November 24, 2017), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.