Single crystal to polycrystal neutron transmission simulation

L. L. Dessieux; A. D. Stoica; P. R. Bingham

doi:10.1063/1.5002102

Single crystal to polycrystal neutron transmission simulation

L. L. Dessieux, A. D. Stoica, P. R. Bingham

Research output: Contribution to journal › Article › peer-review

13 Scopus citations

Abstract

A collection of routines for calculation of the total cross section that determines the attenuation of neutrons by crystalline solids is presented. The total cross section is calculated semi-empirically as a function of crystal structure, neutron energy, temperature, and crystal orientation. The semi-empirical formula includes the contribution of parasitic Bragg scattering to the total cross section using both the crystal's mosaic spread value and its orientation with respect to the neutron beam direction as parameters. These routines allow users to enter a distribution of crystal orientations for calculation of total cross sections of user defined powder or pseudo powder distributions, which enables simulation of non-uniformities such as texture and strain. The spectra for neutron transmission simulations in the neutron thermal energy range (2 meV-100 meV) are presented for single crystal and polycrystal samples and compared to measurements.

Original language	English
Article number	025103
Journal	Review of Scientific Instruments
Volume	89
Issue number	2
DOIs	https://doi.org/10.1063/1.5002102
State	Published - Feb 1 2018

Funding

The research was supported by the Geothermal Technologies Office, Office of Energy Efficiency and Renewable Energy, U.S. Department of Energy under Contract No. DEAC05-00OR22725, Oak Ridge National Laboratory, managed and operated by UT-Battelle, LLC.

Funders	Funder number
UT-Battelle
U.S. Department of Energy	DEAC05-00OR22725
Office of Energy Efficiency and Renewable Energy
Oak Ridge National Laboratory
Geothermal Technologies Office

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Single crystal to polycrystal neutron transmission simulation

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