# [P9] Estimating anisotropic diffusion of neutrons near the boundary of a pebble bed random system

### Conference paper

Proceedings of International Conference on Mathematics and Computational Methods Applied to Nuclear Science & Engineering, Sun Valley, ID, 2013 May

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### Cite

**APA**

Vasques, R. (2013). [P9] Estimating anisotropic diffusion of neutrons near the boundary of a pebble bed random system. In Proceedings of International Conference on Mathematics and Computational Methods Applied to Nuclear Science & Engineering. Sun Valley, ID.

**Chicago/Turabian**

Vasques, Richard. “[P9] Estimating Anisotropic Diffusion of Neutrons near the Boundary of a Pebble Bed Random System.” In Proceedings of International Conference on Mathematics and Computational Methods Applied to Nuclear Science & Engineering. Sun Valley, ID, 2013.

**MLA**

Vasques, Richard. “[P9] Estimating Anisotropic Diffusion of Neutrons near the Boundary of a Pebble Bed Random System.” Proceedings of International Conference on Mathematics and Computational Methods Applied to Nuclear Science & Engineering, 2013.

**ABSTRACT:**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.