NEUTRON DOSIMETRY SAMPLING OF THE OMRE PRESSURE VESSEL AND GRID PLATES

Abstract

Upon the shutdown of the organic moderated reactor experiment (OMRE) at the National Reactor Testing Station in Idaho, a program was initiated to determine the total neutron dosage and radiation induced transition temperature increase to the pressure vessel and upper grid plates. Drillings were made across the grid plate and the chips were collected from each position to determine the cross-plate neutron exposure gradient. Drillings were taken and collected from the pressure vessel at the fuel centerline, upper and lower grid plate regions, and mid-way between, to determine the vertical neutron flux gradient. The results of the neutron dose analysis of these components are presented. Based upon the results, recommendations are made for testing of the material to determine the transition temperature increase.

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Document Details

Document Type
Technical Report
Publication Date
Jun 02, 1964
Accession Number
AD0602160

Entities

People

  • Charles Z. Serpan Jr.
  • Lendell E. Steele

Organizations

  • United States Naval Research Laboratory

Tags

Communities of Interest

  • Energy and Power Technologies
  • Ground and Sea Platforms

DTIC Thesaurus Topics

  • Fabrication
  • Fast Neutrons
  • Materials
  • Materials Testing
  • Mechanical Properties
  • Neutron Spectrum
  • Neutrons
  • Nuclear Energy
  • Organic Moderated Reactors
  • Power Levels
  • Pressure Vessels
  • Radiation
  • Shielding
  • Structural Components
  • Test Reactors
  • Tools
  • Transition Temperature

Fields of Study

  • Physics

Readers

  • Electrical Engineering
  • Fluid Dynamics.
  • Solar Physics