Army Gas-Cooled Reactor Systems Program Semiannual Progress Report: January 1 - June 30, 1960 Metadata

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Title

  • Added Title ARMY GAS-COOLED REACTOR SYSTEMS PROGRAM SEMIANNUAL PROGRESS REPORT FOR JANUARY 1-JUNE 30, 1960
  • Main Title Army Gas-Cooled Reactor Systems Program Semiannual Progress Report: January 1 - June 30, 1960
  • Serial Title Army Gas-Cooled Reactor Systems Program Progress Report
  • Sort Title Army Gas-Cooled Reactor Systems Program Progress Report: 1960-01
  • Added Title U.S. Atomic Energy Commission Idaho Operations Office Report IDO-28558

Creator

  • Author: Aerojet-General Corporation
    Creator Type: Organization

Contributor

  • Originator: National Reactor Testing Station, Idaho (U.S.)
    Contributor Type: Organization
  • Distributor: United States. Department of Commerce. Office of Technical Services.
    Contributor Type: Organization

Publisher

  • Name: Aerojet-General Nucleonics
    Place of Publication: San Ramon, California

Date

  • Creation: 1960-07-31

Language

  • English

Description

  • Content Description: Report documenting the progress of the Army Gas-Cooled Reactor Systems Program to develop a mobile nuclear power plant for military field operation.
  • Physical Description: xiv, 211 p. : ill. ; 28 cm.

Subject

  • Library of Congress Subject Headings: Gas cooled reactors.
  • Library of Congress Subject Headings: Nuclear reactors. -- Research.
  • Keyword: semiannual reports
  • Keyword: progress reports
  • Keyword: reactor technology
  • Keyword: reactor technologies
  • Keyword: control elements
  • Keyword: criticality
  • Keyword: fuel elements
  • Keyword: gas coolants
  • Keyword: GCRE-1
  • Keyword: power plants
  • Keyword: reactors
  • Keyword: fuels
  • Keyword: GCRE-2
  • Keyword: graphite moderators
  • Keyword: homogeneous reactors

Coverage

  • Coverage Date: 1960-01-01/1960-06-30

Relation

  • Is Version Of: Army Gas-Cooled Reactor Systems Program Semiannual Progress Report: January 1 - June 30, 1960, ark:/67531/metadc67300/

Collection

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

Institution

  • Name: UNT Libraries Government Documents Department
    Code: UNTGD

Resource Type

  • Report

Format

  • Text

Identifier

  • Report No.: IDO-28558
  • Grant Number: AT(10-1)-880
  • DOI: 10.2172/4135055
  • Office of Scientific & Technical Information Report Number: 4135055
  • OCLC: 727224963
  • SuDoc Number: Y 3.At 7:22/IDO-28558
  • Archival Resource Key: ark:/67531/metadc863304

Note

  • Display Note: NTIS
  • Display Note: Gas Cooled Reactor Experiment I. Expedient modifications to the tube bundle and control rods made possible the attainment of initial critical of the GCRE-I reactor early in February. The scheduled series of low-power experiments was completed and the facility shut down in midApril to permit the permanent modification to the tube bundle, control rods, and instrumentation. Gas Cooled Reactor Experiment II. Work on the GCRE-II was limited to materials development and systems studies. These studies included mobile and portable power systems using homogeneous graphite reactors as well as modifications and improvements to the ML-1 system. The materials development effort was devoted to homogeneous graphite fuel materials. The ML-1. Activation measurements were made in the Lid Tank Facility. Reanalysis of stresses in the tube sheet indicated high stresses in certain regions. Design of most of the reactor package was completed and fabrication initiated. An alloy (80% Ag--15% In--5% Cd) was selected for the ML- 1 control blades on the basis of ductility tests, corrosion tests, and neutronic calculations. A critical experiment was performed on the ML-1 configuration with pin type fuel elements. The recuperator design selected is a four-pas-s shell and tube heat exchanger. Fuel-element Development. A preliminary design study indicated that the seven-pin fuel element does not significantly improve performance over that obtainable with the 19-pin design. A corrosion test specimen of Hastelloy X exposed for 5000 hr in air at 1750 deg F showed 0.0016- in. penetration. Beryllium oxide-- uranium oxide capsule irradiation was completed with about 2 at.% U/sup 235/ burn-up at maximum surface temperature of 1740 deg F. The IB-2T-Z irradiation test was completed after about 800 hr of operation, including 1147 thermal cycles between 1000 and 1600 deg F without any evidence of malfunction. The irradiation of the GCRE-1 plate type element (1-3P) was completed after 429 hr of operation. (For preceding period see IDO-28549.) (W.L.H.)
  • Display Note: Other Information: Orig. Receipt Date: 31-DEC-60