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A comprehensive study on the charged-uncharged particle shielding features of (70 − x) CRT–30K2O–xBaO glass system

A comprehensive study on the charged-uncharged particle shielding features of (70 − x)... The going study aims to investigate the charged-uncharged particles’ shielding performance of the (70 − x) CRT–30K2O–xBaO glass system for x = 0–20 mol% via the MCNPX simulation, analytical calculations, Phy-X: PSD, and SRIM software. For this purpose, three types of glasses coded as G-C1, G-C2, and G-C3 are irradiated by the 252Cf neutron source. Applying Watt Fission Distribution (WFD) and Doppler Effect (DE), the neutron-gamma photon spectra are extracted and the obtained results are shown graphically. The outcomes reveal that G-C1 can better shield neutrons among the rest of the chosen samples and a strong linear relationship is found between equivalent absorbed dose rate and Fast Neutron removal Cross Section (FNRCS; cm−1) with R2 = 0.99225. In addition, by increasing the density from 2.8232 g.cm−3 for sample coded as G-C1 to 3.2266 g.cm−3 for the sample coded as G-C3 an ascending order of (LAC)G-C1 < (LAC)G-C2 < (LAC)G-C3 is monitored and the best gamma photon-shielding competence is recorded for G-C3. Moreover, the glass samples’ Transmission Factor (TF) and Radiation Protection Efficiency (RPE) are evaluated and discussed in detail. http://www.deepdyve.com/assets/images/DeepDyve-Logo-lg.png Journal of the Australian Ceramic Society Springer Journals

A comprehensive study on the charged-uncharged particle shielding features of (70 − x) CRT–30K2O–xBaO glass system

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References (38)

Publisher
Springer Journals
Copyright
Copyright © The Author(s) under exclusive licence to Australian Ceramic Society 2022
ISSN
2510-1560
eISSN
2510-1579
DOI
10.1007/s41779-022-00733-2
Publisher site
See Article on Publisher Site

Abstract

The going study aims to investigate the charged-uncharged particles’ shielding performance of the (70 − x) CRT–30K2O–xBaO glass system for x = 0–20 mol% via the MCNPX simulation, analytical calculations, Phy-X: PSD, and SRIM software. For this purpose, three types of glasses coded as G-C1, G-C2, and G-C3 are irradiated by the 252Cf neutron source. Applying Watt Fission Distribution (WFD) and Doppler Effect (DE), the neutron-gamma photon spectra are extracted and the obtained results are shown graphically. The outcomes reveal that G-C1 can better shield neutrons among the rest of the chosen samples and a strong linear relationship is found between equivalent absorbed dose rate and Fast Neutron removal Cross Section (FNRCS; cm−1) with R2 = 0.99225. In addition, by increasing the density from 2.8232 g.cm−3 for sample coded as G-C1 to 3.2266 g.cm−3 for the sample coded as G-C3 an ascending order of (LAC)G-C1 < (LAC)G-C2 < (LAC)G-C3 is monitored and the best gamma photon-shielding competence is recorded for G-C3. Moreover, the glass samples’ Transmission Factor (TF) and Radiation Protection Efficiency (RPE) are evaluated and discussed in detail.

Journal

Journal of the Australian Ceramic Society – Springer Journals

Published: Jul 1, 2022

Keywords: CRT waste glass; Doppler Effect; Watt Fission Distribution; Mass stopping power; Transmission Factor; Radiation Protection Efficiency

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