Mathematical formulae for neutron self-shielding properties of media in an isotropic neutron field
Ateia W. Mahmoud, Elsayed K. Elmaghraby, E. Salama, A. Elghazaly, S., A. El-fiki

TL;DR
This paper derives simple, adaptable formulae for neutron self-shielding factors in isotropic neutron fields, based on neutron transport theory, applicable to various geometries and materials, validated against experimental data.
Contribution
It introduces new, simplified formulae for neutron self-shielding factors derived from first principles, accommodating different geometries and energy ranges.
Findings
Formulae accurately predict experimental self-shielding factors.
Applicable to diverse geometries and neutron energies.
Based on integral cross-section parameters and neutron transport theory.
Abstract
The complexity of the neutron transport phenomenon throws its shadows on every physical system wherever neutron is produced or used. In the current study, an ab initio derivation of the neutron self-shielding factor to solve the problem of the decrease of the neutron flux as it penetrates into a material placed in an isotropic neutron field. We have employed the theory of steady-state neutron transport, starting from Stuart's formula. Simple formulae were derived based on the integral cross-section parameters that could be adopted by the user according to various variables, such as the neutron flux distribution and geometry of the simulation at hand. The concluded formulae of the self-shielding factors comprise an inverted sigmoid function normalized with a weight representing the ratio between the macroscopic total and scattering cross-sections of the medium. The general convex volume…
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Taxonomy
TopicsNuclear Physics and Applications · Nuclear reactor physics and engineering · Graphite, nuclear technology, radiation studies
