NEUTRON TRANSPORT CALCULATIONS ON AIR FORCE NUCLEAR ENGINEERING TEST REACTOR.

Abstract

Neutron transport flux calculations are performed on the test cells of the Air Force Institute of Technology Nuclear Engineering Test Facility at Wright-Patterson Air Force Base, Ohio. The calculations are performed by a computer code, written by the author, which uses a three energy group, discrete S-4 approximation of the Boltzmann transport equation in XY-geometry. An iterative procedure having the total fission source production as the eigenvalue is used by the computer code to solve the derived discrete SN difference equations numerically. The code is written in Fortran IV language for the IBM 7094 coupled system. The results obtained by the code calculations are compared with the results from gold foil experiments. Theses results are in good agreement. (Author)

Document Details

Document Type
Technical Report
Publication Date
Mar 01, 1966
Accession Number
AD0634563

Entities

People

  • David R. Floyd

Organizations

  • Air Force Institute of Technology

Tags

DTIC Thesaurus Topics

  • Air Force
  • Air Force Facilities
  • Boltzmann Equation
  • Computers
  • Difference Equations
  • Eigenvalues
  • Engineering
  • Equations
  • Nuclear Engineering
  • Test Facilities
  • Test Reactors
  • Transport Ships

Fields of Study

  • Physics

Readers

  • Calculus or Mathematical Analysis
  • Computer Science.
  • Solar Physics