Minimum-thickness blanket/shield with optimum tritium breeding and shielding effectiveness Metadata

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Title

  • Main Title Minimum-thickness blanket/shield with optimum tritium breeding and shielding effectiveness

Creator

  • Author: Gerstl, S.A.W.
    Creator Type: Personal

Publisher

  • Name: Los Alamos Scientific Laboratory
    Place of Publication: New Mexico
    Additional Info: Los Alamos Scientific Lab., N.Mex. (USA)

Date

  • Creation: 1978-01-01

Language

  • English

Description

  • Content Description: A blanket/shield assembly for a fusion reactor has been designed through extensive optimization studies. The design was optimized under the following constraints: (a) minimum overall thickness, (b) tritium breeding ratio of 1.10, (c) thermal energy recovery of 90%, (d) acceptably flat temperature distribution, and (e) excluding all ''exotic'' or problematic materials. The optimized blanket/shield has an overall thickness of 36 cm and conforms with all the above requirements. All tritium breeding is accomplished in a 24-cm-thick breeding zone using stagnant enriched lithium-6, and lead as a neutron multiplier. The energy recovery in this breeding zone is 71% which, together with an additional energy extraction of 19% in a 12-cm-thick laminated stainless steel/boron carbide shield zone, results in the desired overall thermal efficiency of 0.90 which is considered adequate if normal-conducting magnets are used for plasma confinement.
  • Physical Description: 11 pages

Subject

  • Keyword: Alloys
  • Keyword: Shielding
  • STI Subject Categories: 70 Plasma Physics And Fusion Technology
  • Keyword: Beta Decay Radioisotopes
  • Keyword: Lithium Isotopes
  • Keyword: Reactor Components
  • Keyword: Beta-Minus Decay Radioisotopes
  • Keyword: Thermonuclear Reactors
  • Keyword: Light Nuclei
  • Keyword: Optimization
  • Keyword: Breeding Ratio
  • Keyword: Chromium Alloys
  • Keyword: Nuclei
  • Keyword: Iron Alloys
  • Keyword: Lithium 6
  • Keyword: Alkali Metal Isotopes
  • Keyword: Hydrogen Isotopes
  • Keyword: Isotopes
  • Keyword: Tritium
  • Keyword: Odd-Even Nuclei
  • Keyword: Years Living Radioisotopes 700201* -- Fusion Power Plant Technology-- Blanket Engineering
  • Keyword: Design
  • Keyword: Steels
  • Keyword: Dimensions
  • Keyword: Odd-Odd Nuclei
  • Keyword: Corrosion Resistant Alloys
  • Keyword: Breeding Blankets
  • Keyword: Thickness
  • Keyword: Stainless Steels
  • Keyword: Radioisotopes
  • Keyword: Iron Base Alloys
  • Keyword: Stable Isotopes
  • Keyword: Conversion Ratio

Source

  • Conference: 3. meeting on the technology of controlled thermonuclear fusion, Santa Fe, NM, USA, 9 May 1978

Collection

  • Name: Office of Scientific & Technical Information Technical Reports
    Code: OSTI

Institution

  • Name: UNT Libraries Government Documents Department
    Code: UNTGD

Resource Type

  • Article

Format

  • Text

Identifier

  • Report No.: LA-UR-78-1198
  • Report No.: CONF-780508-3
  • Grant Number: W-7405-ENG-36
  • Office of Scientific & Technical Information Report Number: 7080183
  • Archival Resource Key: ark:/67531/metadc1192655

Note

  • Display Note: Dep. NTIS, PC A02/MF A01.
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