Accession Number : AD0634563
Title : NEUTRON TRANSPORT CALCULATIONS ON AIR FORCE NUCLEAR ENGINEERING TEST REACTOR.
Descriptive Note : Master's thesis,
Corporate Author : AIR FORCE INST OF TECH WRIGHT-PATTERSON AFB OHIO SCHOOL OF ENGINEERING
Personal Author(s) : Floyd, David R.
Report Date : MAR 1966
Pagination or Media Count : 93
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)
Descriptors : (*TEST REACTORS, NEUTRON TRANSPORT THEORY), (*HETEROGENEOUS REACTORS, NEUTRON TRANSPORT THEORY), NEUTRON FLUX, NUMERICAL ANALYSIS, COMPUTER PROGRAMMING, INTEGRAL EQUATIONS, ITERATIONS, GOLD, NEUTRON REACTIONS
Subject Categories : Fission Reactor Physics
Distribution Statement : APPROVED FOR PUBLIC RELEASE