Published April 1988 | Version v1
Journal article

Solution of three dimensional inverse transport problems

Creators

  • 1. Department of Nuclear Engineering, The University of Michigan, Ann Arbor, Michigan 48109

Description

A solution is developed for the problem of determining the cross sections of a physical system by irradiating its outer boundary with a known neutron flux, measuring the exiting flux, and then making suitable use of the known incident and exiting boundary fluxes. Our solution requires the use of delta function (pencil beam) incident boundary fluxes, and detectors that are capable of measuring exiting angular fluxes which are weak delta functions of angle (arising from a line source) over an infinitesimal angular interval comprising the support of the delta function. Our approach, which is significantly different from previously published solutions of this problem, is applicable in general geometries with spatial inhomogeneities

Additional details

Publishing Information

Journal Title
Transp. Theory Stat. Phys.
Journal Volume
17
Journal Issue
2
Series
Transp. Theory Stat. Phys.
Journal Page Range
147-168
ISSN
0041-1450
CODEN
TTSPB

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
19097994
Subject category
S73: NUCLEAR PHYSICS AND RADIATION PHYSICS;
Descriptors DEI
ANALYTICAL SOLUTION; CROSS SECTIONS; NEUTRON BEAMS; NEUTRON FLUX; NEUTRON TRANSPORT THEORY; SLABS; THREE-DIMENSIONAL CALCULATIONS
Descriptors DEC
BEAMS; NUCLEON BEAMS; PARTICLE BEAMS; RADIATION FLUX; TRANSPORT THEORY