Published November 2008 | Version v1
Miscellaneous Open

Neutron Transport in Finite Random Media with Pure-Triplet Scattering

  • 1. Theoretical Physics Research Group, Physics Department, Faculty of Science, Mansoura University, Mansoura (Egypt)
  • 2. Physics Department, Faculty of Science, King Saud University, Riyadh (Saudi Arabia)

Description

The solution of the one-speed neutron transport equation in a finite slab random medium with pure-triplet anisotropic scattering is studied. The stochastic medium is assumed to consist of two randomly mixed immiscible fluids. The cross section and the scattering kernel are treated as discrete random variables, which obey the same statistics as Markovian processes and exponential chord length statistics. The medium boundaries are considered to have specular reflectivities with angular-dependent externally incident flux. The deterministic solution is obtained by using Pomraning-Eddington approximation. Numerical results are calculated for the average reflectivity and average transmissivity for different values of the single scattering albedo and varying the parameters which characterize the random medium. Compared to the results obtained by Adams et al. in case of isotropic scattering that based on the Monte Carlo technique, it can be seen that we have good comparable data

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Part of:
Proceeding of the Sixth Nuclear and Particle Physics Conference (NUPPAC-2007)

Additional details

Publishing Information

Imprint Title
Proceeding of the Sixth Nuclear and Particle Physics Conference (NUPPAC-2007)
Imprint Pagination
642 p.
Journal Page Range
p. 291-306
Report number
INIS-EG--214

Conference

Title
6. Conference on Nuclear and Particle Physics
Acronym
NUPPAC 07
Dates
17-21 Nov 2007
Place
Luxor (Egypt)

INIS

Country of Publication
Egypt
Country of Input or Organization
Egypt
INIS RN
40081092
Subject category
S73: NUCLEAR PHYSICS AND RADIATION PHYSICS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
ANISOTROPY; BOUNDARY CONDITIONS; CROSS SECTIONS; EDDINGTON THEORY; KERNELS; LEGENDRE POLYNOMIALS; MONTE CARLO METHOD; NEUTRON TRANSPORT; RANDOMNESS; SCATTERING; STATISTICS; TRIPLETS
Descriptors DEC
CALCULATION METHODS; FUNCTIONS; MATHEMATICS; MULTIPLETS; NEUTRAL-PARTICLE TRANSPORT; POLYNOMIALS; RADIATION TRANSPORT

Optional Information