The HGCR-1, a Design Study of a Nuclear Power Station Employing a High-Temperature Gas-Cooled Reactor with Graphite-UO₂ Fuel Elements Metadata

Metadata describes a digital item, providing (if known) such information as creator, publisher, contents, size, relationship to other resources, and more. Metadata may also contain "preservation" components that help us to maintain the integrity of digital files over time.

Title

  • Main Title The HGCR-1, a Design Study of a Nuclear Power Station Employing a High-Temperature Gas-Cooled Reactor with Graphite-UO₂ Fuel Elements
  • Series Title Oak Ridge National Laboratory Reports
  • Series Title TID
  • Added Title Oak Ridge National Laboratory Report ORNL-2653
  • Series Title AEC research and development report
  • Series Title Atomic Energy Commission Reports

Creator

  • Author: Cottrell, William B.
    Creator Type: Personal
  • Author: Copenhaver, C. M.
    Creator Type: Personal
  • Author: Culver, H. N.
    Creator Type: Personal
  • Author: Fontana, M. H.
    Creator Type: Personal
  • Author: Kelleghan, V. J.
    Creator Type: Personal
  • Author: Samuels, G.
    Creator Type: Personal

Contributor

  • Distributor: United States. Department of Commerce. Office of Technical Services.
    Contributor Type: Organization
  • Originator: Oak Ridge National Laboratory
    Contributor Type: Organization
  • Originator: U.S. Atomic Energy Commission
    Contributor Type: Organization

Publisher

  • Name: Oak Ridge National Laboratory
    Place of Publication: Oak Ridge, Tennessee

Date

  • Creation: 1959

Language

  • English

Description

  • Content Description: "The preliminary design of a 3095-Mw(thermal), helium-cooled, graphite- moderated reactor employing sign conditions, 1500 deg F reactor outlet gas would be circulated to eight steam generators to produce 1050 deg F, 1450-psi steam which would be converted to electrical power in eight 157-Mw(electrical) turbine- generators. The over-all efficiency of this nuclear power station is 36.5%. The significant activities released from the unclad graphite-UO₂ fuel appear to be less than 0.2% of those produced and would be equivalent to 0.002 curie/ cm/ sup 3/ in the primary helium circuit. The maintenance problems associated with this contamination level are discussed. A cost analysis indicates that the capital cost of this nuclear station per electrical kilowatt would be around 0, and that the production cost of electrical power would be 7.8 mills/kwhr" (p. iii).
  • Physical Description: vii, 192 p. : ill. ; 28 cm.

Subject

  • Library of Congress Subject Headings: Gas cooled reactors -- Fuel.
  • Library of Congress Subject Headings: Nuclear fuels.

Primary Source

  • Item is a Primary Source

Collection

  • Name: Technical Report Archive and Image Library
    Code: TRAIL

Institution

  • Name: UNT Libraries Government Documents Department
    Code: UNTGD

Resource Type

  • Report

Format

  • Text

Identifier

  • OCLC: 36133637
  • SuDoc Number: Y 3.At 7:22/ORNL-2653
  • Report No.: ORNL-2653
  • Grant Number: Contract No. W-7405-eng-26
  • Archival Resource Key: ark:/67531/metadc100279

Note

  • Display Note: "ORNL-2653, Reactors - Power, TID-4500 (14th ed.)."