SOVIET BERYLLIUM PHYSICS REACTOR (BRG). REVIEW OF SOVIET LITERATURE

Abstract

the results of this investigation led to the following conclusions: Metallic beryllium has a very small neutron absorption cross-section (6.0 ! 1.2 to the -27th power sq cm). The mass production of high purity beryllium (having total impurities of less than 1 mbarn per beryllium nucleus) presents serious technological difficulties. However, beryllium with total impurities of 2 to 3 mbarn per nucleus can be produced in large quantities. This beryllium has an absorption cross-section of 9.0 ! 1.2 to the -27th power sq cm and can be used in thermal reactors. The problem of the practical use of beryllium in the construction of an actual reactor can only be solved after completion of the study of the physicomechanical and corrosive properties of beryllium under conditions similar to actual reactor operating conditions.

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Document Details

Document Type
Technical Report
Publication Date
Aug 31, 1962
Accession Number
AD0284759

Entities

Organizations

  • Library of Congress

Tags

Communities of Interest

  • Space

DTIC Thesaurus Topics

  • Assembly
  • Construction
  • Construction Materials
  • Critical Assemblies
  • Elements
  • Government Procurement
  • Governments
  • Mass Production
  • Materials
  • Measurement
  • Multiplication Factor
  • Neutrons
  • Nuclear Reactors
  • Resonance Escape Probability
  • Thermal Neutrons
  • Thermal Reactors
  • Thermal Utilization

Fields of Study

  • Physics

Readers

  • Metallurgy
  • Nuclear and Radiation Engineering.