Accession Number : AD0621269

Title :   NEUTRON TRANSPORT CALCULATIONS OF THE AIR FORCE NUCLEAR ENGINEERING TEST FACILITY CORE.

Descriptive Note : Master's thesis,

Corporate Author : AIR FORCE INST OF TECH WRIGHT-PATTERSON AFB OHIO SCHOOL OF ENGINEERING

Personal Author(s) : Norman,Donald Lloyd

Report Date : AUG 1965

Pagination or Media Count : 61

Abstract : The neutron flux in segments of the core of the Air Force Nuclear Engineering Test Reactor was investigated using transport theory. Two portions of the core were treated; the fuel plates and the control rods. These regions were represented as a one-dimensional array of thin slabs. A matrix collapsing technique for the solution of many-region, slab-geometry problems using the P-3 approximation was developed and a computer code to make the calculations was written. It was determined that no flux weighting was necessary in calculating homogeneous cross sections for the fuel regions. A technique was developed to compute a simplified control rod model, but computing difficulty prevented its being tested. (Author)

Descriptors :   (*NEUTRON TRANSPORT THEORY, TEST REACTORS), (*TEST REACTORS, AIR FORCE), (*REACTOR CORES, TEST REACTORS), NUCLEAR ENGINEERING, THERMAL REACTORS, NEUTRON FLUX, REACTOR THEORY, COMPUTER PROGRAMMING

Distribution Statement : APPROVED FOR PUBLIC RELEASE