CALCULATION OF RADIATION DOSE LEVELS FOR THE ARMY PULSE EXPERIMENTAL REACTOR ASSEMBLY

Abstract

Calculations are side to estimate, as a function of distance, the radiation dose levels which would occur during full capacity operation of the Army Pulse Reactor Assembly (APRA) scheduled for construction at Aberdeen Proving Ground, Maryland. Calculations of the neutron dose are made by two methods. The first calculation (Method A) is made by utilizing an experimentally determined effective dose mean free path, which probably includes the effect of ground scattering. The second calculation (Method B) is made by utilizing the result of a Monte Carlo calculation of neutron transmission in air. The results of this calculation indicate considerably higher dose levels than indicated by Method A. Experimental data are available which substantiate the result of Method A. The gamma dose at distances of interest is found to be unimportant when considered in light of the uncertainty in the neutron dose.

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Document Details

Document Type
Technical Report
Publication Date
Nov 01, 1962
Accession Number
AD0402147

Entities

People

  • Frederick H. Gregory

Organizations

  • Ballistic Research Laboratory

Tags

Communities of Interest

  • Air Platforms
  • Biomedical
  • Energy and Power Technologies

DTIC Thesaurus Topics

  • Absorption Coefficients
  • Air Force
  • Air Force Facilities
  • Assembly
  • Composite Materials
  • Engineering
  • Experimental Data
  • Gamma Rays
  • Maryland
  • Mean Free Path
  • Military Research
  • Navy
  • Nitrogen
  • Nuclear Energy
  • Nuclear Reactors
  • Radiation
  • Scattering

Fields of Study

  • Medicine
  • Physics

Readers

  • Software Engineering
  • Solar Physics