Criticality Studies of Graphite Moderated Production Reactors

Abstract

The objective of the study was to examine the feasibility of using commercially available graphite in small production reactors. Three different- size reactors, each with a different coolant, were investigated, and an assessment was made of the effect of parasitic neutron-absorbing material in the graphite, either as naturally-occurring impurities or as intentionally-added spikants. In addition, a brief survey of methods of manufacturing and of purifying graphite was performed.

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Document Details

Document Type
Technical Report
Publication Date
Jan 01, 1980
Accession Number
ADA084910

Entities

People

  • K. D. Kirby
  • M. K. Gurley
  • R. D. Keller Jr.
  • R. M. Cole
  • S. E. Turner
  • W. Mditchell Iii

Tags

DTIC Thesaurus Topics

  • Bricks
  • Construction
  • Energy
  • Fission
  • Fission Products
  • Gas Cooled Reactors
  • Heat Transfer
  • High Temperature
  • Manufacturing
  • Materials Laboratories
  • Materials Processing
  • Materials Science
  • Neutron Absorbers
  • Nuclear Energy
  • Nuclear Materials
  • Nuclear Reactors
  • Thermal Conductivity

Fields of Study

  • Physics

Readers

  • Combustion and Flow Dynamics.
  • Materials Science and Engineering.