Report of a technical evaluation panel on the use of beryllium for ITER plasma facing material and blanket breeder material

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Description

Beryllium because of its low atomic number and high thermal conductivity, is a candidate for both ITER first wall and divertor surfaces. This study addresses the following: why beryllium; design requirements for the ITER divertor; beryllium supply and unirradiated physical/mechanical property database; effects of irradiation on beryllium properties; tritium issues; beryllium health and safety; beryllium-coolant interactions and safety; thermal and mechanical tests; plasma erosion of beryllium; recommended beryllium grades for ITER plasma facing components; proposed manufacturing methods to produce beryllium parts for ITER; emerging beryllium materials; proposed inspection and maintenance techniques for beryllium components and coatings; time table and costs; ... continued below

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150 p.

Creation Information

Ulrickson, M.A.; Manly, W.D. & Dombrowski, D.E. August 1, 1995.

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  • Sandia National Laboratories
    Publisher Info: Sandia National Labs., Albuquerque, NM (United States)
    Place of Publication: Albuquerque, New Mexico

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Description

Beryllium because of its low atomic number and high thermal conductivity, is a candidate for both ITER first wall and divertor surfaces. This study addresses the following: why beryllium; design requirements for the ITER divertor; beryllium supply and unirradiated physical/mechanical property database; effects of irradiation on beryllium properties; tritium issues; beryllium health and safety; beryllium-coolant interactions and safety; thermal and mechanical tests; plasma erosion of beryllium; recommended beryllium grades for ITER plasma facing components; proposed manufacturing methods to produce beryllium parts for ITER; emerging beryllium materials; proposed inspection and maintenance techniques for beryllium components and coatings; time table and costs; and the importance of integrating materials and manufacturing personnel with designers.

Physical Description

150 p.

Notes

INIS; OSTI as DE96000055

Source

  • Other Information: PBD: Aug 1995

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  • Other: DE96000055
  • Report No.: SAND--95-1693
  • Grant Number: AC04-94AL85000
  • DOI: 10.2172/106616 | External Link
  • Office of Scientific & Technical Information Report Number: 106616
  • Archival Resource Key: ark:/67531/metadc618724

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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

  • August 1, 1995

Added to The UNT Digital Library

  • June 16, 2015, 7:43 a.m.

Description Last Updated

  • April 13, 2016, 6:49 p.m.

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Ulrickson, M.A.; Manly, W.D. & Dombrowski, D.E. Report of a technical evaluation panel on the use of beryllium for ITER plasma facing material and blanket breeder material, report, August 1, 1995; Albuquerque, New Mexico. (digital.library.unt.edu/ark:/67531/metadc618724/: accessed January 22, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.