Experimental Evaluation of the Combustion Hazard to the Experimental Gas- Cooled Reactor-Preliminary Burning Rig Experiments Metadata

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Title

  • Main Title Experimental Evaluation of the Combustion Hazard to the Experimental Gas- Cooled Reactor-Preliminary Burning Rig Experiments

Creator

  • Author: Dahl, R.E.
    Creator Type: Personal

Contributor

  • Sponsor: United States. Department of Energy.
    Contributor Type: Organization
    Contributor Info: USDOE

Publisher

  • Name: General Electric Co. Hanford Atomic Products Operation, Richland, Wash.
    Place of Publication: United States

Date

  • Creation: 1961-11-01

Language

  • English

Description

  • Content Description: >An assembly was constructed which simulated the moderator coolant annulus in the Experimental Gas-Cooled Reactor. This assembly was preheated to various temperatures and air was passed through the coolant annulus. Under certain conditions it was demonstrated that self-sustained combustion of the graphite could occur. Rates of temperature rise were generally less than 1 deg C/ min until the graphite temperature exceeded 700 deg C and then rise rates became very high. In these cxperimcnts, the assembly was not operated in such a manner as to give ignition temperatures eharaeteristic of the EGCR. These tests were designed only to investigate the effects of changing such parameters as the rate of coolant flow, air humidity, prior oxidation on the graphite, and air inlet temperature. A later series of experiments to more closely duplicate the EGCR operating conditions was completed and will be reported in a second report, HW- 71182. (auth)
  • Physical Description: 45 pages

Subject

  • Keyword: Heat Transfer
  • Keyword: Chemical Reactions
  • Keyword: Egcr
  • Keyword: Oxidation
  • Keyword: Pressure
  • Keyword: Configuration
  • Keyword: Power Plants
  • Keyword: Corrosion
  • Keyword: Heating
  • Keyword: Gas Coolant
  • Keyword: Air
  • Keyword: Coolant Loops
  • Keyword: High Temperature
  • Keyword: Variations
  • Keyword: Humidity
  • Keyword: Materials Testing
  • Keyword: Graphite
  • Keyword: Transients
  • Keyword: Failures
  • Keyword: Testing
  • Keyword: Reactor Safety
  • Keyword: Temperature
  • Keyword: Combustion
  • Keyword: Accidents
  • Keyword: Reactor Technology
  • Keyword: Mockup
  • Keyword: Graphite Moderator
  • Keyword: Gas Flow
  • Keyword: Reactor Core
  • Keyword: Measured Values

Source

  • Other Information: Orig. Receipt Date: 31-DEC-62

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.: HW-67792
  • Grant Number: AT(45-1)-1350
  • DOI: 10.2172/4791773
  • Office of Scientific & Technical Information Report Number: 4791773
  • Archival Resource Key: ark:/67531/metadc1059538
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