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