rdf-syntax-grammar
mods:
  schema location: http://www.loc.gov/mods/v3 http://www.loc.gov/standards/mods/v3/mods-3-2.xsd
  title info:
    non sort: An
    title: investigation of aqueous slurries as fusion reactor blankets
  name:
    name part: Schuller, Michael John
    name part: 1958-
    role:
      role term: creator
  name:
    name part: Hart, R. R.
    role:
      role term: degree committee member.
  name:
    name part: Narcowich, F. J.
    role:
      role term: degree committee member.
  name:
    name part: Parish, T. A.
    role:
      role term: degree supervisor.
  name:
    name part: Schlapper, G. A.
    role:
      role term: degree committee member.
  name:
    name part: Texas A & M University
    role:
      role term: degree granting institution.
  type of resource: text
  genre: bibliography
  genre: Academic theses
  origin info:
    place:
      place term: xx
    date issued: 1985
    issuance: monographic
  language:
    language term: eng
  physical description:
    form: print
    extent: ix, 153 leaves : illustrations ; 29 cm
  abstract: Numerical and experimental studies were carried out to assess the feasibility of using an aqueous slurry, with lithium in its solid component, to meet the tritium breeding, cooling, and shielding requirements of a controlled thermonuclear reactor (CTR). The numerical studies were designed to demonstrate the theoretical ability of a conceptual slurry blanket to breed adequate tritium to sustain the CTR. The experimental studies were designed to show that the tritium retention characteristics of likely solid components for the slurry were conducive to adequate tritium recovery without the need for isotopic separation. The numerical portion of this work consisted in part of using ANISN, a one-dimensional finite difference neutron transport code, to model the neutronic performance of the slurry blanket concept. The parameters governing tritium production and retention in a slurry were computed and used to modify the results of the ANISN computer runs. The numerical work demonstrated that the slurry blanket was only marginally capable of breeding sufficient tritium without the aid of a neutron multiplying region. The highest theoretical tritium breeding ratio, based on tritium retained in the solid portion of the slurry, achieved without a neutron multiplying region was 1.08 tritons per fusion neutron. A theoretical tritium breeding ratio greater than 1.2 tritons per fusion neutron could be achieved by including a beryllium layer in the first wall of the blanket. The experimental portion of this work consisted of several neutron irradiation experiments, which were designed to determine the retention abilities of LiF particles. The experiments measured tritium recoil losses, tritium retention versus time, and tritium retention versus temperature. The experimental results indicated that the tritium retention properties of LiF were adequate for the purposes of the slurry blanket concept.
  note: "Major subject: Nuclear Engineering."
  note: Typescript (photocopy).
  note: Vita.
  note: Ph. D. Texas A & M University 1985
  note: Includes bibliographical references (leaves 149-152).
  subject:
    topic: Fusion reactors
  subject:
    topic: Major nuclear engineering
  identifier: http://proxy.library.tamu.edu/login
  identifier: https://hdl.handle.net/1969.1/DISSERTATIONS-597426
  identifier: http://gateway.proquest.com/openurl
  related item:
    location:
      url: http://proxy.library.tamu.edu/login
  related item:
    location:
      url: https://hdl.handle.net/1969.1/DISSERTATIONS-597426
  related item:
    location:
      url: http://gateway.proquest.com/openurl
  record info:
    record content source: TXA
    record creation date: 870822
    record change date: 20220103135241.0
    record identifier: in00000585095
    language of cataloging:
      language term: eng