Estimating anisotropic diffusion of neutrons near the boundary of a pebble bed random system
Creators
- 1. Department of Mathematics, Center for Computational Engineering Science, RWTH Aachen University, Schinkel Strasse 2, D-52062 Aachen (Germany)
Description
Due to the arrangement of the pebbles in a Pebble Bed Reactor (PBR) core, if a neutron is located close to a boundary wall, its path length probability distribution function in directions of flight parallel to the wall is significantly different than in other directions. Hence, anisotropic diffusion of neutrons near the boundaries arises. We describe an analysis of neutron transport in a simplified 3-D pebble bed random system, in which we investigate the anisotropic diffusion of neutrons born near one of the system's boundary walls. While this simplified system does not model the actual physical process that takes place near the boundaries of a PBR core, the present work paves the road to a formulation that may enable more accurate diffusion simulations of such problems to be performed in the future. Monte Carlo codes have been developed for (i) deriving realizations of the 3-D random system, and (ii) performing 3-D neutron transport inside the heterogeneous model; numerical results are presented for three different choices of parameters. These numerical results are used to assess the accuracy of estimates for the mean-squared displacement of neutrons obtained with the diffusion approximations of the Atomic Mix Model and of the recently introduced [1] Non-Classical Theory with angular-dependent path length distribution. The Non-Classical Theory makes use of a Generalized Linear Boltzmann Equation in which the locations of the scattering centers in the system are correlated and the distance to collision is not exponentially distributed. We show that the results predicted using the Non-Classical Theory successfully model the anisotropic behavior of the neutrons in the random system, and more closely agree with experiment than the results predicted by the Atomic Mix Model. (authors)
Additional details
Publishing Information
- Publisher
- American Nuclear Society - ANS
- Imprint Place
- La Grange Park (United States)
- ISBN
- 978-0-89448-700-2
- Imprint Title
- Proceedings of the 2013 International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering - M and C 2013
- Imprint Pagination
- 3016 p.
- Journal Page Range
- p. 1736-1747
Conference
- Title
- 2013 International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering
- Acronym
- M and C 2013
- Dates
- 5-9 May 2013
- Place
- Sun Valley, ID (United States)
INIS
- Country of Publication
- United States
- Country of Input or Organization
- France
- INIS RN
- 45033789
- Subject category
- S97: MATHEMATICAL METHODS AND COMPUTING; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ANGULAR DISTRIBUTION; ANISOTROPY; APPROXIMATIONS; BOLTZMANN EQUATION; COMPUTERIZED SIMULATION; DISTRIBUTION FUNCTIONS; MONTE CARLO METHOD; NEUTRON DIFFUSION EQUATION; NEUTRON FLUX; NEUTRON TRANSPORT; NEUTRONS; PEBBLE BED REACTORS; SCATTERING
- Descriptors DEC
- BARYONS; CALCULATION METHODS; DIFFERENTIAL EQUATIONS; DIFFUSION EQUATIONS; DISTRIBUTION; ELEMENTARY PARTICLES; EQUATIONS; FERMIONS; FUNCTIONS; GAS COOLED REACTORS; HADRONS; HOMOGENEOUS REACTORS; INTEGRO-DIFFERENTIAL EQUATIONS; KINETIC EQUATIONS; NEUTRAL-PARTICLE TRANSPORT; NUCLEONS; PARTIAL DIFFERENTIAL EQUATIONS; RADIATION FLUX; RADIATION TRANSPORT; REACTORS; SIMULATION; SOLID HOMOGENEOUS REACTORS
Optional Information
- Notes
- 8 refs.