Published November 2010
| Version v1
Journal article
U1 approximation to the neutron transport equation and calculation of the asymptotic relaxation length
Creators
- 1. Osmaniye Korkut Ata Univ. (Turkey). Dept. of Physics
Description
The U1 approximation is used to determine the asymptotic relaxation length (diffusion length) for one-speed neutrons in a homogeneous slab. The method is based on the series expansion of the neutron angular flux in terms of the Chebyshev polynomials of second kind and then calculating the diffusion length by applying the first order approximation to transport equation. Analytic and numerical results are obtained for the diffusion length and compared with the ones obtained from the method of separation of variables and simple diffusion theory (P1 approximation). (orig.)
Additional details
Publishing Information
- Journal Title
- Kerntechnik (1987)
- Journal Volume
- 75
- Journal Issue
- 6
- Journal Page Range
- p. 375-376
- ISSN
- 0932-3902
- CODEN
- KERNEU
INIS
- Country of Publication
- Germany
- Country of Input or Organization
- Germany
- INIS RN
- 42006567
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Descriptors DEI
- ANALYTICAL SOLUTION; APPROXIMATIONS; DIFFUSION LENGTH; NEUTRON FLUX; NEUTRON TRANSPORT THEORY; POLYNOMIALS; REACTOR PHYSICS; RELAXATION; SERIES EXPANSION; TIME DEPENDENCE
- Descriptors DEC
- CALCULATION METHODS; DIMENSIONS; FUNCTIONS; LENGTH; MATHEMATICAL SOLUTIONS; PHYSICS; RADIATION FLUX; TRANSPORT THEORY