Accession Number:

AD0857979

Title:

Neutron Transport in a Spherical Subcritical Assembly with an External Neutron Source.

Descriptive Note:

Master's thesis,

Corporate Author:

AIR FORCE INST OF TECH WRIGHT-PATTERSON AFB OH SCHOOL OF ENGINEERING

Personal Author(s):

Report Date:

1969-06-01

Pagination or Media Count:

103.0

Abstract:

Neutron transport theory was used to predict resulting neutron distributions from an external neutron source in a spherical subcritical fissile assembly. A plane wave-delta function neutron source in time was assumed incident on the sphere containing fissionable material. Two methods of three-group calculations in r, theta spherical geometry were used. A time-space integrated diffusion equation was solved for fluence nvt as a function of energy and position. Secondly, the Boltzmann equation was solved by the discrete ordinates S sub n method. Computer codes for both methods were written in Fortran IV for the IBM 7094 computer. In a sphere 14 cm in diameter, composed of U-235 and aluminum, fission buildup from a fission spectrum source resulted in a total increase in neutron population of three times the source strength. A comparison of the results of the two methods is presented. Author

Subject Categories:

  • Nuclear Radiation Shielding, Protection and Safety
  • Radioactivity, Radioactive Wastes and Fission Products
  • Fission Reactor Physics

Distribution Statement:

APPROVED FOR PUBLIC RELEASE