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150479

On The Use of Beryllium as Thermal Neutron Filter

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Last updated: 23 Jan 2023

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Abstract

A formula is given which allows to calculate the contribution of the
nuclear capture, thermal diffuse and Bragg scattering cross-section to the
neutron transmission through solid crystalline Beryllium. The formula takes
into account the beryllium crystalline structure and its physical parameters. A
computer program CRYSBE was developed to provide the required calculation.
The calculated values of the total cross-section of polycrystalline beryllium at
different temperatures were compared with the previously measured ones in the
neutron energy range from 0.2 meV to 10 eV . The obtained agreement shows
that the formula fits the experimental data . An agreement was also obtained for
values of beryllium single crystal at both room and liquid nitrogen
temperatures. The feasibility study on using a polycrystalline beryllium as a
cold neutron filter is given. The optimum beryllium single crystal thickness,
mosaic spread, temperature and cutting plane for efficiently transmitting the
thermal reactor neutrons, while rejecting both fast neutrons and gamma ray
accompanying the thermal ones are also given .

DOI

10.21608/ejs.2002.150479

Volume

25

Article Issue

2

Related Issue

22140

Issue Date

2002-12-01

Receive Date

2002-04-22

Publish Date

2002-12-01

Page Start

215

Page End

227

Print ISSN

1012-5566

Online ISSN

2735-5640

Link

https://ejs.journals.ekb.eg/article_150479.html

Detail API

https://ejs.journals.ekb.eg/service?article_code=150479

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6

Publication Type

Journal

Publication Title

Egyptian Journal of Solids

Publication Link

https://ejs.journals.ekb.eg/

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Article

Created At

23 Jan 2023