Calculating photon buildup factors in determining the γ-ray shielding effectiveness of some materials susceptible to be used for the conception of neutrons and γ-ray shielding
We report γ−ray shielding effectiveness of eight selected shielding materials susceptible to be used for the conception of γ−ray and fast neutrons absorbers has been investigated. Four of the selected materials were polyethylene composites, the first one is doped with 7.5% Lithium (Lithium7.5%-Polye...
Ausführliche Beschreibung
Gespeichert in:
| Autor*in: |
Norah A.M. Alsaif [verfasserIn] Youssef Elmahroug [verfasserIn] B.M. Alotaibi [verfasserIn] Haifa A. Alyousef [verfasserIn] Najeh Rekik [verfasserIn] A. Wahab M.A. Hussein [verfasserIn] Ram Chand [verfasserIn] Umer Farooq [verfasserIn] |
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| Format: |
E-Artikel |
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| Sprache: |
Englisch |
| Erschienen: |
2021 |
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| Schlagwörter: |
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| Übergeordnetes Werk: |
In: Journal of Materials Research and Technology - Elsevier, 2015, 11(2021), Seite 769-784 |
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| Übergeordnetes Werk: |
volume:11 ; year:2021 ; pages:769-784 |
| Links: |
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| DOI / URN: |
10.1016/j.jmrt.2021.01.052 |
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| Katalog-ID: |
DOAJ069080305 |
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| 520 | |a We report γ−ray shielding effectiveness of eight selected shielding materials susceptible to be used for the conception of γ−ray and fast neutrons absorbers has been investigated. Four of the selected materials were polyethylene composites, the first one is doped with 7.5% Lithium (Lithium7.5%-Polyethylene), the second one is doped with 8.97% boron (Borated8.97%-Polyethylene), the third one is doped with 5.45% boron (Borated5.45%-Polyethylene), and the fourth one contains high hydrogen content as well as 0.9% by weight boron namely Self Extinguishing Borated Polythylene. The other four considered materials are FlexiBoron, High Temperature Boron Silicone, Polykast Dry Mix, and Field castable Heat Resistant shielding. These materials have been selected in fact because they contain iron (Fe), zinc (Zn), Strontium (Sr) and Manganese (Mn) which heavy elements and considered as good absorbers of γ−radiation and also because they contain hydrogen which is considered as the furthermost active moderator as well as boron which is an extremely appropriate absorber of thermal neutrons. The study has been conducted by determining the γ−ray energy absorption buildup factors (EABF) as well as the exposure buildup factors (EBF). The evaluation of the buildup factors has been determined by employing the five parameters geometric progression (G-P) fitting approximation and taking into account the reference standard database (1991-ANSI/ANS-6.4.3). This determination has been carried out using a photon energy varying from 0.015 to 15 MeV with a permeation depth until 40 mean free paths. By investigating on the reliance of EABF and EBF on the incident photon energy, chemical arrangement, and permeation depth, a deeply comparison between the obtained values of EABF and EBF has been performed. By inspecting the obtained values of EABF and EBF established for the first time, our numerical simulations allow to conclude that among the selected shielding materials, Field castable Heat Resistant shielding and 5.45% Borated Polyethylene provide the lower buildup factors at lower energies (<1.5 MeV for EABF, <2 MeV for EBF), suggesting thereby their candidacy to serve as potential shielding materials against γ−radiation in this energy range. The results of the present investigation therefore shed light on selectivity of the appropriate shielding material as well as the determination of the optimum thickness of the shielding material subject of having superior neutrons shielding ability. | ||
| 650 | 4 | |a Shielding materials | |
| 650 | 4 | |a G-P fitting approximation | |
| 650 | 4 | |a Energy absorption buildup factor | |
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| 700 | 0 | |a A. Wahab M.A. Hussein |e verfasserin |4 aut | |
| 700 | 0 | |a Ram Chand |e verfasserin |4 aut | |
| 700 | 0 | |a Umer Farooq |e verfasserin |4 aut | |
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10.1016/j.jmrt.2021.01.052 doi (DE-627)DOAJ069080305 (DE-599)DOAJ2a142af04d39441181df141dc76a71fd DE-627 ger DE-627 rakwb eng TN1-997 Norah A.M. Alsaif verfasserin aut Calculating photon buildup factors in determining the γ-ray shielding effectiveness of some materials susceptible to be used for the conception of neutrons and γ-ray shielding 2021 Text txt rdacontent Computermedien c rdamedia Online-Ressource cr rdacarrier We report γ−ray shielding effectiveness of eight selected shielding materials susceptible to be used for the conception of γ−ray and fast neutrons absorbers has been investigated. Four of the selected materials were polyethylene composites, the first one is doped with 7.5% Lithium (Lithium7.5%-Polyethylene), the second one is doped with 8.97% boron (Borated8.97%-Polyethylene), the third one is doped with 5.45% boron (Borated5.45%-Polyethylene), and the fourth one contains high hydrogen content as well as 0.9% by weight boron namely Self Extinguishing Borated Polythylene. The other four considered materials are FlexiBoron, High Temperature Boron Silicone, Polykast Dry Mix, and Field castable Heat Resistant shielding. These materials have been selected in fact because they contain iron (Fe), zinc (Zn), Strontium (Sr) and Manganese (Mn) which heavy elements and considered as good absorbers of γ−radiation and also because they contain hydrogen which is considered as the furthermost active moderator as well as boron which is an extremely appropriate absorber of thermal neutrons. The study has been conducted by determining the γ−ray energy absorption buildup factors (EABF) as well as the exposure buildup factors (EBF). The evaluation of the buildup factors has been determined by employing the five parameters geometric progression (G-P) fitting approximation and taking into account the reference standard database (1991-ANSI/ANS-6.4.3). This determination has been carried out using a photon energy varying from 0.015 to 15 MeV with a permeation depth until 40 mean free paths. By investigating on the reliance of EABF and EBF on the incident photon energy, chemical arrangement, and permeation depth, a deeply comparison between the obtained values of EABF and EBF has been performed. By inspecting the obtained values of EABF and EBF established for the first time, our numerical simulations allow to conclude that among the selected shielding materials, Field castable Heat Resistant shielding and 5.45% Borated Polyethylene provide the lower buildup factors at lower energies (<1.5 MeV for EABF, <2 MeV for EBF), suggesting thereby their candidacy to serve as potential shielding materials against γ−radiation in this energy range. The results of the present investigation therefore shed light on selectivity of the appropriate shielding material as well as the determination of the optimum thickness of the shielding material subject of having superior neutrons shielding ability. Shielding materials G-P fitting approximation Energy absorption buildup factor Exposure buildup factor Mining engineering. Metallurgy Youssef Elmahroug verfasserin aut B.M. Alotaibi verfasserin aut Haifa A. Alyousef verfasserin aut Najeh Rekik verfasserin aut A. Wahab M.A. Hussein verfasserin aut Ram Chand verfasserin aut Umer Farooq verfasserin aut In Journal of Materials Research and Technology Elsevier, 2015 11(2021), Seite 769-784 (DE-627)768093163 (DE-600)2732709-7 22140697 nnns volume:11 year:2021 pages:769-784 https://doi.org/10.1016/j.jmrt.2021.01.052 kostenfrei https://doaj.org/article/2a142af04d39441181df141dc76a71fd kostenfrei http://www.sciencedirect.com/science/article/pii/S2238785421000521 kostenfrei https://doaj.org/toc/2238-7854 Journal toc kostenfrei GBV_USEFLAG_A SYSFLAG_A GBV_DOAJ GBV_ILN_20 GBV_ILN_22 GBV_ILN_23 GBV_ILN_24 GBV_ILN_31 GBV_ILN_39 GBV_ILN_40 GBV_ILN_60 GBV_ILN_62 GBV_ILN_63 GBV_ILN_65 GBV_ILN_69 GBV_ILN_70 GBV_ILN_73 GBV_ILN_95 GBV_ILN_105 GBV_ILN_110 GBV_ILN_151 GBV_ILN_161 GBV_ILN_170 GBV_ILN_213 GBV_ILN_224 GBV_ILN_230 GBV_ILN_285 GBV_ILN_293 GBV_ILN_370 GBV_ILN_602 GBV_ILN_2001 GBV_ILN_2003 GBV_ILN_2005 GBV_ILN_2006 GBV_ILN_2007 GBV_ILN_2008 GBV_ILN_2009 GBV_ILN_2010 GBV_ILN_2011 GBV_ILN_2014 GBV_ILN_2015 GBV_ILN_2020 GBV_ILN_2021 GBV_ILN_2025 GBV_ILN_2026 GBV_ILN_2027 GBV_ILN_2034 GBV_ILN_2038 GBV_ILN_2044 GBV_ILN_2048 GBV_ILN_2049 GBV_ILN_2050 GBV_ILN_2055 GBV_ILN_2056 GBV_ILN_2059 GBV_ILN_2061 GBV_ILN_2064 GBV_ILN_2088 GBV_ILN_2106 GBV_ILN_2110 GBV_ILN_2112 GBV_ILN_2122 GBV_ILN_2129 GBV_ILN_2143 GBV_ILN_2152 GBV_ILN_2153 GBV_ILN_2190 GBV_ILN_2232 GBV_ILN_2336 GBV_ILN_2470 GBV_ILN_2507 GBV_ILN_4012 GBV_ILN_4035 GBV_ILN_4037 GBV_ILN_4112 GBV_ILN_4125 GBV_ILN_4126 GBV_ILN_4242 GBV_ILN_4249 GBV_ILN_4251 GBV_ILN_4305 GBV_ILN_4306 GBV_ILN_4307 GBV_ILN_4313 GBV_ILN_4322 GBV_ILN_4323 GBV_ILN_4324 GBV_ILN_4325 GBV_ILN_4326 GBV_ILN_4333 GBV_ILN_4334 GBV_ILN_4335 GBV_ILN_4338 GBV_ILN_4367 GBV_ILN_4393 GBV_ILN_4700 AR 11 2021 769-784 |
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10.1016/j.jmrt.2021.01.052 doi (DE-627)DOAJ069080305 (DE-599)DOAJ2a142af04d39441181df141dc76a71fd DE-627 ger DE-627 rakwb eng TN1-997 Norah A.M. Alsaif verfasserin aut Calculating photon buildup factors in determining the γ-ray shielding effectiveness of some materials susceptible to be used for the conception of neutrons and γ-ray shielding 2021 Text txt rdacontent Computermedien c rdamedia Online-Ressource cr rdacarrier We report γ−ray shielding effectiveness of eight selected shielding materials susceptible to be used for the conception of γ−ray and fast neutrons absorbers has been investigated. Four of the selected materials were polyethylene composites, the first one is doped with 7.5% Lithium (Lithium7.5%-Polyethylene), the second one is doped with 8.97% boron (Borated8.97%-Polyethylene), the third one is doped with 5.45% boron (Borated5.45%-Polyethylene), and the fourth one contains high hydrogen content as well as 0.9% by weight boron namely Self Extinguishing Borated Polythylene. The other four considered materials are FlexiBoron, High Temperature Boron Silicone, Polykast Dry Mix, and Field castable Heat Resistant shielding. These materials have been selected in fact because they contain iron (Fe), zinc (Zn), Strontium (Sr) and Manganese (Mn) which heavy elements and considered as good absorbers of γ−radiation and also because they contain hydrogen which is considered as the furthermost active moderator as well as boron which is an extremely appropriate absorber of thermal neutrons. The study has been conducted by determining the γ−ray energy absorption buildup factors (EABF) as well as the exposure buildup factors (EBF). The evaluation of the buildup factors has been determined by employing the five parameters geometric progression (G-P) fitting approximation and taking into account the reference standard database (1991-ANSI/ANS-6.4.3). This determination has been carried out using a photon energy varying from 0.015 to 15 MeV with a permeation depth until 40 mean free paths. By investigating on the reliance of EABF and EBF on the incident photon energy, chemical arrangement, and permeation depth, a deeply comparison between the obtained values of EABF and EBF has been performed. By inspecting the obtained values of EABF and EBF established for the first time, our numerical simulations allow to conclude that among the selected shielding materials, Field castable Heat Resistant shielding and 5.45% Borated Polyethylene provide the lower buildup factors at lower energies (<1.5 MeV for EABF, <2 MeV for EBF), suggesting thereby their candidacy to serve as potential shielding materials against γ−radiation in this energy range. The results of the present investigation therefore shed light on selectivity of the appropriate shielding material as well as the determination of the optimum thickness of the shielding material subject of having superior neutrons shielding ability. Shielding materials G-P fitting approximation Energy absorption buildup factor Exposure buildup factor Mining engineering. Metallurgy Youssef Elmahroug verfasserin aut B.M. Alotaibi verfasserin aut Haifa A. Alyousef verfasserin aut Najeh Rekik verfasserin aut A. Wahab M.A. Hussein verfasserin aut Ram Chand verfasserin aut Umer Farooq verfasserin aut In Journal of Materials Research and Technology Elsevier, 2015 11(2021), Seite 769-784 (DE-627)768093163 (DE-600)2732709-7 22140697 nnns volume:11 year:2021 pages:769-784 https://doi.org/10.1016/j.jmrt.2021.01.052 kostenfrei https://doaj.org/article/2a142af04d39441181df141dc76a71fd kostenfrei http://www.sciencedirect.com/science/article/pii/S2238785421000521 kostenfrei https://doaj.org/toc/2238-7854 Journal toc kostenfrei GBV_USEFLAG_A SYSFLAG_A GBV_DOAJ GBV_ILN_20 GBV_ILN_22 GBV_ILN_23 GBV_ILN_24 GBV_ILN_31 GBV_ILN_39 GBV_ILN_40 GBV_ILN_60 GBV_ILN_62 GBV_ILN_63 GBV_ILN_65 GBV_ILN_69 GBV_ILN_70 GBV_ILN_73 GBV_ILN_95 GBV_ILN_105 GBV_ILN_110 GBV_ILN_151 GBV_ILN_161 GBV_ILN_170 GBV_ILN_213 GBV_ILN_224 GBV_ILN_230 GBV_ILN_285 GBV_ILN_293 GBV_ILN_370 GBV_ILN_602 GBV_ILN_2001 GBV_ILN_2003 GBV_ILN_2005 GBV_ILN_2006 GBV_ILN_2007 GBV_ILN_2008 GBV_ILN_2009 GBV_ILN_2010 GBV_ILN_2011 GBV_ILN_2014 GBV_ILN_2015 GBV_ILN_2020 GBV_ILN_2021 GBV_ILN_2025 GBV_ILN_2026 GBV_ILN_2027 GBV_ILN_2034 GBV_ILN_2038 GBV_ILN_2044 GBV_ILN_2048 GBV_ILN_2049 GBV_ILN_2050 GBV_ILN_2055 GBV_ILN_2056 GBV_ILN_2059 GBV_ILN_2061 GBV_ILN_2064 GBV_ILN_2088 GBV_ILN_2106 GBV_ILN_2110 GBV_ILN_2112 GBV_ILN_2122 GBV_ILN_2129 GBV_ILN_2143 GBV_ILN_2152 GBV_ILN_2153 GBV_ILN_2190 GBV_ILN_2232 GBV_ILN_2336 GBV_ILN_2470 GBV_ILN_2507 GBV_ILN_4012 GBV_ILN_4035 GBV_ILN_4037 GBV_ILN_4112 GBV_ILN_4125 GBV_ILN_4126 GBV_ILN_4242 GBV_ILN_4249 GBV_ILN_4251 GBV_ILN_4305 GBV_ILN_4306 GBV_ILN_4307 GBV_ILN_4313 GBV_ILN_4322 GBV_ILN_4323 GBV_ILN_4324 GBV_ILN_4325 GBV_ILN_4326 GBV_ILN_4333 GBV_ILN_4334 GBV_ILN_4335 GBV_ILN_4338 GBV_ILN_4367 GBV_ILN_4393 GBV_ILN_4700 AR 11 2021 769-784 |
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10.1016/j.jmrt.2021.01.052 doi (DE-627)DOAJ069080305 (DE-599)DOAJ2a142af04d39441181df141dc76a71fd DE-627 ger DE-627 rakwb eng TN1-997 Norah A.M. Alsaif verfasserin aut Calculating photon buildup factors in determining the γ-ray shielding effectiveness of some materials susceptible to be used for the conception of neutrons and γ-ray shielding 2021 Text txt rdacontent Computermedien c rdamedia Online-Ressource cr rdacarrier We report γ−ray shielding effectiveness of eight selected shielding materials susceptible to be used for the conception of γ−ray and fast neutrons absorbers has been investigated. Four of the selected materials were polyethylene composites, the first one is doped with 7.5% Lithium (Lithium7.5%-Polyethylene), the second one is doped with 8.97% boron (Borated8.97%-Polyethylene), the third one is doped with 5.45% boron (Borated5.45%-Polyethylene), and the fourth one contains high hydrogen content as well as 0.9% by weight boron namely Self Extinguishing Borated Polythylene. The other four considered materials are FlexiBoron, High Temperature Boron Silicone, Polykast Dry Mix, and Field castable Heat Resistant shielding. These materials have been selected in fact because they contain iron (Fe), zinc (Zn), Strontium (Sr) and Manganese (Mn) which heavy elements and considered as good absorbers of γ−radiation and also because they contain hydrogen which is considered as the furthermost active moderator as well as boron which is an extremely appropriate absorber of thermal neutrons. The study has been conducted by determining the γ−ray energy absorption buildup factors (EABF) as well as the exposure buildup factors (EBF). The evaluation of the buildup factors has been determined by employing the five parameters geometric progression (G-P) fitting approximation and taking into account the reference standard database (1991-ANSI/ANS-6.4.3). This determination has been carried out using a photon energy varying from 0.015 to 15 MeV with a permeation depth until 40 mean free paths. By investigating on the reliance of EABF and EBF on the incident photon energy, chemical arrangement, and permeation depth, a deeply comparison between the obtained values of EABF and EBF has been performed. By inspecting the obtained values of EABF and EBF established for the first time, our numerical simulations allow to conclude that among the selected shielding materials, Field castable Heat Resistant shielding and 5.45% Borated Polyethylene provide the lower buildup factors at lower energies (<1.5 MeV for EABF, <2 MeV for EBF), suggesting thereby their candidacy to serve as potential shielding materials against γ−radiation in this energy range. The results of the present investigation therefore shed light on selectivity of the appropriate shielding material as well as the determination of the optimum thickness of the shielding material subject of having superior neutrons shielding ability. Shielding materials G-P fitting approximation Energy absorption buildup factor Exposure buildup factor Mining engineering. Metallurgy Youssef Elmahroug verfasserin aut B.M. Alotaibi verfasserin aut Haifa A. Alyousef verfasserin aut Najeh Rekik verfasserin aut A. Wahab M.A. Hussein verfasserin aut Ram Chand verfasserin aut Umer Farooq verfasserin aut In Journal of Materials Research and Technology Elsevier, 2015 11(2021), Seite 769-784 (DE-627)768093163 (DE-600)2732709-7 22140697 nnns volume:11 year:2021 pages:769-784 https://doi.org/10.1016/j.jmrt.2021.01.052 kostenfrei https://doaj.org/article/2a142af04d39441181df141dc76a71fd kostenfrei http://www.sciencedirect.com/science/article/pii/S2238785421000521 kostenfrei https://doaj.org/toc/2238-7854 Journal toc kostenfrei GBV_USEFLAG_A SYSFLAG_A GBV_DOAJ GBV_ILN_20 GBV_ILN_22 GBV_ILN_23 GBV_ILN_24 GBV_ILN_31 GBV_ILN_39 GBV_ILN_40 GBV_ILN_60 GBV_ILN_62 GBV_ILN_63 GBV_ILN_65 GBV_ILN_69 GBV_ILN_70 GBV_ILN_73 GBV_ILN_95 GBV_ILN_105 GBV_ILN_110 GBV_ILN_151 GBV_ILN_161 GBV_ILN_170 GBV_ILN_213 GBV_ILN_224 GBV_ILN_230 GBV_ILN_285 GBV_ILN_293 GBV_ILN_370 GBV_ILN_602 GBV_ILN_2001 GBV_ILN_2003 GBV_ILN_2005 GBV_ILN_2006 GBV_ILN_2007 GBV_ILN_2008 GBV_ILN_2009 GBV_ILN_2010 GBV_ILN_2011 GBV_ILN_2014 GBV_ILN_2015 GBV_ILN_2020 GBV_ILN_2021 GBV_ILN_2025 GBV_ILN_2026 GBV_ILN_2027 GBV_ILN_2034 GBV_ILN_2038 GBV_ILN_2044 GBV_ILN_2048 GBV_ILN_2049 GBV_ILN_2050 GBV_ILN_2055 GBV_ILN_2056 GBV_ILN_2059 GBV_ILN_2061 GBV_ILN_2064 GBV_ILN_2088 GBV_ILN_2106 GBV_ILN_2110 GBV_ILN_2112 GBV_ILN_2122 GBV_ILN_2129 GBV_ILN_2143 GBV_ILN_2152 GBV_ILN_2153 GBV_ILN_2190 GBV_ILN_2232 GBV_ILN_2336 GBV_ILN_2470 GBV_ILN_2507 GBV_ILN_4012 GBV_ILN_4035 GBV_ILN_4037 GBV_ILN_4112 GBV_ILN_4125 GBV_ILN_4126 GBV_ILN_4242 GBV_ILN_4249 GBV_ILN_4251 GBV_ILN_4305 GBV_ILN_4306 GBV_ILN_4307 GBV_ILN_4313 GBV_ILN_4322 GBV_ILN_4323 GBV_ILN_4324 GBV_ILN_4325 GBV_ILN_4326 GBV_ILN_4333 GBV_ILN_4334 GBV_ILN_4335 GBV_ILN_4338 GBV_ILN_4367 GBV_ILN_4393 GBV_ILN_4700 AR 11 2021 769-784 |
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10.1016/j.jmrt.2021.01.052 doi (DE-627)DOAJ069080305 (DE-599)DOAJ2a142af04d39441181df141dc76a71fd DE-627 ger DE-627 rakwb eng TN1-997 Norah A.M. Alsaif verfasserin aut Calculating photon buildup factors in determining the γ-ray shielding effectiveness of some materials susceptible to be used for the conception of neutrons and γ-ray shielding 2021 Text txt rdacontent Computermedien c rdamedia Online-Ressource cr rdacarrier We report γ−ray shielding effectiveness of eight selected shielding materials susceptible to be used for the conception of γ−ray and fast neutrons absorbers has been investigated. Four of the selected materials were polyethylene composites, the first one is doped with 7.5% Lithium (Lithium7.5%-Polyethylene), the second one is doped with 8.97% boron (Borated8.97%-Polyethylene), the third one is doped with 5.45% boron (Borated5.45%-Polyethylene), and the fourth one contains high hydrogen content as well as 0.9% by weight boron namely Self Extinguishing Borated Polythylene. The other four considered materials are FlexiBoron, High Temperature Boron Silicone, Polykast Dry Mix, and Field castable Heat Resistant shielding. These materials have been selected in fact because they contain iron (Fe), zinc (Zn), Strontium (Sr) and Manganese (Mn) which heavy elements and considered as good absorbers of γ−radiation and also because they contain hydrogen which is considered as the furthermost active moderator as well as boron which is an extremely appropriate absorber of thermal neutrons. The study has been conducted by determining the γ−ray energy absorption buildup factors (EABF) as well as the exposure buildup factors (EBF). The evaluation of the buildup factors has been determined by employing the five parameters geometric progression (G-P) fitting approximation and taking into account the reference standard database (1991-ANSI/ANS-6.4.3). This determination has been carried out using a photon energy varying from 0.015 to 15 MeV with a permeation depth until 40 mean free paths. By investigating on the reliance of EABF and EBF on the incident photon energy, chemical arrangement, and permeation depth, a deeply comparison between the obtained values of EABF and EBF has been performed. By inspecting the obtained values of EABF and EBF established for the first time, our numerical simulations allow to conclude that among the selected shielding materials, Field castable Heat Resistant shielding and 5.45% Borated Polyethylene provide the lower buildup factors at lower energies (<1.5 MeV for EABF, <2 MeV for EBF), suggesting thereby their candidacy to serve as potential shielding materials against γ−radiation in this energy range. The results of the present investigation therefore shed light on selectivity of the appropriate shielding material as well as the determination of the optimum thickness of the shielding material subject of having superior neutrons shielding ability. Shielding materials G-P fitting approximation Energy absorption buildup factor Exposure buildup factor Mining engineering. Metallurgy Youssef Elmahroug verfasserin aut B.M. Alotaibi verfasserin aut Haifa A. Alyousef verfasserin aut Najeh Rekik verfasserin aut A. Wahab M.A. Hussein verfasserin aut Ram Chand verfasserin aut Umer Farooq verfasserin aut In Journal of Materials Research and Technology Elsevier, 2015 11(2021), Seite 769-784 (DE-627)768093163 (DE-600)2732709-7 22140697 nnns volume:11 year:2021 pages:769-784 https://doi.org/10.1016/j.jmrt.2021.01.052 kostenfrei https://doaj.org/article/2a142af04d39441181df141dc76a71fd kostenfrei http://www.sciencedirect.com/science/article/pii/S2238785421000521 kostenfrei https://doaj.org/toc/2238-7854 Journal toc kostenfrei GBV_USEFLAG_A SYSFLAG_A GBV_DOAJ GBV_ILN_20 GBV_ILN_22 GBV_ILN_23 GBV_ILN_24 GBV_ILN_31 GBV_ILN_39 GBV_ILN_40 GBV_ILN_60 GBV_ILN_62 GBV_ILN_63 GBV_ILN_65 GBV_ILN_69 GBV_ILN_70 GBV_ILN_73 GBV_ILN_95 GBV_ILN_105 GBV_ILN_110 GBV_ILN_151 GBV_ILN_161 GBV_ILN_170 GBV_ILN_213 GBV_ILN_224 GBV_ILN_230 GBV_ILN_285 GBV_ILN_293 GBV_ILN_370 GBV_ILN_602 GBV_ILN_2001 GBV_ILN_2003 GBV_ILN_2005 GBV_ILN_2006 GBV_ILN_2007 GBV_ILN_2008 GBV_ILN_2009 GBV_ILN_2010 GBV_ILN_2011 GBV_ILN_2014 GBV_ILN_2015 GBV_ILN_2020 GBV_ILN_2021 GBV_ILN_2025 GBV_ILN_2026 GBV_ILN_2027 GBV_ILN_2034 GBV_ILN_2038 GBV_ILN_2044 GBV_ILN_2048 GBV_ILN_2049 GBV_ILN_2050 GBV_ILN_2055 GBV_ILN_2056 GBV_ILN_2059 GBV_ILN_2061 GBV_ILN_2064 GBV_ILN_2088 GBV_ILN_2106 GBV_ILN_2110 GBV_ILN_2112 GBV_ILN_2122 GBV_ILN_2129 GBV_ILN_2143 GBV_ILN_2152 GBV_ILN_2153 GBV_ILN_2190 GBV_ILN_2232 GBV_ILN_2336 GBV_ILN_2470 GBV_ILN_2507 GBV_ILN_4012 GBV_ILN_4035 GBV_ILN_4037 GBV_ILN_4112 GBV_ILN_4125 GBV_ILN_4126 GBV_ILN_4242 GBV_ILN_4249 GBV_ILN_4251 GBV_ILN_4305 GBV_ILN_4306 GBV_ILN_4307 GBV_ILN_4313 GBV_ILN_4322 GBV_ILN_4323 GBV_ILN_4324 GBV_ILN_4325 GBV_ILN_4326 GBV_ILN_4333 GBV_ILN_4334 GBV_ILN_4335 GBV_ILN_4338 GBV_ILN_4367 GBV_ILN_4393 GBV_ILN_4700 AR 11 2021 769-784 |
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10.1016/j.jmrt.2021.01.052 doi (DE-627)DOAJ069080305 (DE-599)DOAJ2a142af04d39441181df141dc76a71fd DE-627 ger DE-627 rakwb eng TN1-997 Norah A.M. Alsaif verfasserin aut Calculating photon buildup factors in determining the γ-ray shielding effectiveness of some materials susceptible to be used for the conception of neutrons and γ-ray shielding 2021 Text txt rdacontent Computermedien c rdamedia Online-Ressource cr rdacarrier We report γ−ray shielding effectiveness of eight selected shielding materials susceptible to be used for the conception of γ−ray and fast neutrons absorbers has been investigated. Four of the selected materials were polyethylene composites, the first one is doped with 7.5% Lithium (Lithium7.5%-Polyethylene), the second one is doped with 8.97% boron (Borated8.97%-Polyethylene), the third one is doped with 5.45% boron (Borated5.45%-Polyethylene), and the fourth one contains high hydrogen content as well as 0.9% by weight boron namely Self Extinguishing Borated Polythylene. The other four considered materials are FlexiBoron, High Temperature Boron Silicone, Polykast Dry Mix, and Field castable Heat Resistant shielding. These materials have been selected in fact because they contain iron (Fe), zinc (Zn), Strontium (Sr) and Manganese (Mn) which heavy elements and considered as good absorbers of γ−radiation and also because they contain hydrogen which is considered as the furthermost active moderator as well as boron which is an extremely appropriate absorber of thermal neutrons. The study has been conducted by determining the γ−ray energy absorption buildup factors (EABF) as well as the exposure buildup factors (EBF). The evaluation of the buildup factors has been determined by employing the five parameters geometric progression (G-P) fitting approximation and taking into account the reference standard database (1991-ANSI/ANS-6.4.3). This determination has been carried out using a photon energy varying from 0.015 to 15 MeV with a permeation depth until 40 mean free paths. By investigating on the reliance of EABF and EBF on the incident photon energy, chemical arrangement, and permeation depth, a deeply comparison between the obtained values of EABF and EBF has been performed. By inspecting the obtained values of EABF and EBF established for the first time, our numerical simulations allow to conclude that among the selected shielding materials, Field castable Heat Resistant shielding and 5.45% Borated Polyethylene provide the lower buildup factors at lower energies (<1.5 MeV for EABF, <2 MeV for EBF), suggesting thereby their candidacy to serve as potential shielding materials against γ−radiation in this energy range. The results of the present investigation therefore shed light on selectivity of the appropriate shielding material as well as the determination of the optimum thickness of the shielding material subject of having superior neutrons shielding ability. Shielding materials G-P fitting approximation Energy absorption buildup factor Exposure buildup factor Mining engineering. Metallurgy Youssef Elmahroug verfasserin aut B.M. Alotaibi verfasserin aut Haifa A. Alyousef verfasserin aut Najeh Rekik verfasserin aut A. Wahab M.A. Hussein verfasserin aut Ram Chand verfasserin aut Umer Farooq verfasserin aut In Journal of Materials Research and Technology Elsevier, 2015 11(2021), Seite 769-784 (DE-627)768093163 (DE-600)2732709-7 22140697 nnns volume:11 year:2021 pages:769-784 https://doi.org/10.1016/j.jmrt.2021.01.052 kostenfrei https://doaj.org/article/2a142af04d39441181df141dc76a71fd kostenfrei http://www.sciencedirect.com/science/article/pii/S2238785421000521 kostenfrei https://doaj.org/toc/2238-7854 Journal toc kostenfrei GBV_USEFLAG_A SYSFLAG_A GBV_DOAJ GBV_ILN_20 GBV_ILN_22 GBV_ILN_23 GBV_ILN_24 GBV_ILN_31 GBV_ILN_39 GBV_ILN_40 GBV_ILN_60 GBV_ILN_62 GBV_ILN_63 GBV_ILN_65 GBV_ILN_69 GBV_ILN_70 GBV_ILN_73 GBV_ILN_95 GBV_ILN_105 GBV_ILN_110 GBV_ILN_151 GBV_ILN_161 GBV_ILN_170 GBV_ILN_213 GBV_ILN_224 GBV_ILN_230 GBV_ILN_285 GBV_ILN_293 GBV_ILN_370 GBV_ILN_602 GBV_ILN_2001 GBV_ILN_2003 GBV_ILN_2005 GBV_ILN_2006 GBV_ILN_2007 GBV_ILN_2008 GBV_ILN_2009 GBV_ILN_2010 GBV_ILN_2011 GBV_ILN_2014 GBV_ILN_2015 GBV_ILN_2020 GBV_ILN_2021 GBV_ILN_2025 GBV_ILN_2026 GBV_ILN_2027 GBV_ILN_2034 GBV_ILN_2038 GBV_ILN_2044 GBV_ILN_2048 GBV_ILN_2049 GBV_ILN_2050 GBV_ILN_2055 GBV_ILN_2056 GBV_ILN_2059 GBV_ILN_2061 GBV_ILN_2064 GBV_ILN_2088 GBV_ILN_2106 GBV_ILN_2110 GBV_ILN_2112 GBV_ILN_2122 GBV_ILN_2129 GBV_ILN_2143 GBV_ILN_2152 GBV_ILN_2153 GBV_ILN_2190 GBV_ILN_2232 GBV_ILN_2336 GBV_ILN_2470 GBV_ILN_2507 GBV_ILN_4012 GBV_ILN_4035 GBV_ILN_4037 GBV_ILN_4112 GBV_ILN_4125 GBV_ILN_4126 GBV_ILN_4242 GBV_ILN_4249 GBV_ILN_4251 GBV_ILN_4305 GBV_ILN_4306 GBV_ILN_4307 GBV_ILN_4313 GBV_ILN_4322 GBV_ILN_4323 GBV_ILN_4324 GBV_ILN_4325 GBV_ILN_4326 GBV_ILN_4333 GBV_ILN_4334 GBV_ILN_4335 GBV_ILN_4338 GBV_ILN_4367 GBV_ILN_4393 GBV_ILN_4700 AR 11 2021 769-784 |
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Alsaif</subfield><subfield code="e">verfasserin</subfield><subfield code="4">aut</subfield></datafield><datafield tag="245" ind1="1" ind2="0"><subfield code="a">Calculating photon buildup factors in determining the γ-ray shielding effectiveness of some materials susceptible to be used for the conception of neutrons and γ-ray shielding</subfield></datafield><datafield tag="264" ind1=" " ind2="1"><subfield code="c">2021</subfield></datafield><datafield tag="336" ind1=" " ind2=" "><subfield code="a">Text</subfield><subfield code="b">txt</subfield><subfield code="2">rdacontent</subfield></datafield><datafield tag="337" ind1=" " ind2=" "><subfield code="a">Computermedien</subfield><subfield code="b">c</subfield><subfield code="2">rdamedia</subfield></datafield><datafield tag="338" ind1=" " ind2=" "><subfield code="a">Online-Ressource</subfield><subfield code="b">cr</subfield><subfield code="2">rdacarrier</subfield></datafield><datafield tag="520" ind1=" " ind2=" "><subfield code="a">We report γ−ray shielding effectiveness of eight selected shielding materials susceptible to be used for the conception of γ−ray and fast neutrons absorbers has been investigated. Four of the selected materials were polyethylene composites, the first one is doped with 7.5% Lithium (Lithium7.5%-Polyethylene), the second one is doped with 8.97% boron (Borated8.97%-Polyethylene), the third one is doped with 5.45% boron (Borated5.45%-Polyethylene), and the fourth one contains high hydrogen content as well as 0.9% by weight boron namely Self Extinguishing Borated Polythylene. The other four considered materials are FlexiBoron, High Temperature Boron Silicone, Polykast Dry Mix, and Field castable Heat Resistant shielding. These materials have been selected in fact because they contain iron (Fe), zinc (Zn), Strontium (Sr) and Manganese (Mn) which heavy elements and considered as good absorbers of γ−radiation and also because they contain hydrogen which is considered as the furthermost active moderator as well as boron which is an extremely appropriate absorber of thermal neutrons. The study has been conducted by determining the γ−ray energy absorption buildup factors (EABF) as well as the exposure buildup factors (EBF). The evaluation of the buildup factors has been determined by employing the five parameters geometric progression (G-P) fitting approximation and taking into account the reference standard database (1991-ANSI/ANS-6.4.3). This determination has been carried out using a photon energy varying from 0.015 to 15 MeV with a permeation depth until 40 mean free paths. By investigating on the reliance of EABF and EBF on the incident photon energy, chemical arrangement, and permeation depth, a deeply comparison between the obtained values of EABF and EBF has been performed. By inspecting the obtained values of EABF and EBF established for the first time, our numerical simulations allow to conclude that among the selected shielding materials, Field castable Heat Resistant shielding and 5.45% Borated Polyethylene provide the lower buildup factors at lower energies (<1.5 MeV for EABF, <2 MeV for EBF), suggesting thereby their candidacy to serve as potential shielding materials against γ−radiation in this energy range. 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Norah A.M. Alsaif |
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Norah A.M. Alsaif misc TN1-997 misc Shielding materials misc G-P fitting approximation misc Energy absorption buildup factor misc Exposure buildup factor misc Mining engineering. Metallurgy Calculating photon buildup factors in determining the γ-ray shielding effectiveness of some materials susceptible to be used for the conception of neutrons and γ-ray shielding |
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TN1-997 Calculating photon buildup factors in determining the γ-ray shielding effectiveness of some materials susceptible to be used for the conception of neutrons and γ-ray shielding Shielding materials G-P fitting approximation Energy absorption buildup factor Exposure buildup factor |
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misc TN1-997 misc Shielding materials misc G-P fitting approximation misc Energy absorption buildup factor misc Exposure buildup factor misc Mining engineering. Metallurgy |
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Calculating photon buildup factors in determining the γ-ray shielding effectiveness of some materials susceptible to be used for the conception of neutrons and γ-ray shielding |
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Norah A.M. Alsaif Youssef Elmahroug B.M. Alotaibi Haifa A. Alyousef Najeh Rekik A. Wahab M.A. Hussein Ram Chand Umer Farooq |
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calculating photon buildup factors in determining the γ-ray shielding effectiveness of some materials susceptible to be used for the conception of neutrons and γ-ray shielding |
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Calculating photon buildup factors in determining the γ-ray shielding effectiveness of some materials susceptible to be used for the conception of neutrons and γ-ray shielding |
| abstract |
We report γ−ray shielding effectiveness of eight selected shielding materials susceptible to be used for the conception of γ−ray and fast neutrons absorbers has been investigated. Four of the selected materials were polyethylene composites, the first one is doped with 7.5% Lithium (Lithium7.5%-Polyethylene), the second one is doped with 8.97% boron (Borated8.97%-Polyethylene), the third one is doped with 5.45% boron (Borated5.45%-Polyethylene), and the fourth one contains high hydrogen content as well as 0.9% by weight boron namely Self Extinguishing Borated Polythylene. The other four considered materials are FlexiBoron, High Temperature Boron Silicone, Polykast Dry Mix, and Field castable Heat Resistant shielding. These materials have been selected in fact because they contain iron (Fe), zinc (Zn), Strontium (Sr) and Manganese (Mn) which heavy elements and considered as good absorbers of γ−radiation and also because they contain hydrogen which is considered as the furthermost active moderator as well as boron which is an extremely appropriate absorber of thermal neutrons. The study has been conducted by determining the γ−ray energy absorption buildup factors (EABF) as well as the exposure buildup factors (EBF). The evaluation of the buildup factors has been determined by employing the five parameters geometric progression (G-P) fitting approximation and taking into account the reference standard database (1991-ANSI/ANS-6.4.3). This determination has been carried out using a photon energy varying from 0.015 to 15 MeV with a permeation depth until 40 mean free paths. By investigating on the reliance of EABF and EBF on the incident photon energy, chemical arrangement, and permeation depth, a deeply comparison between the obtained values of EABF and EBF has been performed. By inspecting the obtained values of EABF and EBF established for the first time, our numerical simulations allow to conclude that among the selected shielding materials, Field castable Heat Resistant shielding and 5.45% Borated Polyethylene provide the lower buildup factors at lower energies (<1.5 MeV for EABF, <2 MeV for EBF), suggesting thereby their candidacy to serve as potential shielding materials against γ−radiation in this energy range. The results of the present investigation therefore shed light on selectivity of the appropriate shielding material as well as the determination of the optimum thickness of the shielding material subject of having superior neutrons shielding ability. |
| abstractGer |
We report γ−ray shielding effectiveness of eight selected shielding materials susceptible to be used for the conception of γ−ray and fast neutrons absorbers has been investigated. Four of the selected materials were polyethylene composites, the first one is doped with 7.5% Lithium (Lithium7.5%-Polyethylene), the second one is doped with 8.97% boron (Borated8.97%-Polyethylene), the third one is doped with 5.45% boron (Borated5.45%-Polyethylene), and the fourth one contains high hydrogen content as well as 0.9% by weight boron namely Self Extinguishing Borated Polythylene. The other four considered materials are FlexiBoron, High Temperature Boron Silicone, Polykast Dry Mix, and Field castable Heat Resistant shielding. These materials have been selected in fact because they contain iron (Fe), zinc (Zn), Strontium (Sr) and Manganese (Mn) which heavy elements and considered as good absorbers of γ−radiation and also because they contain hydrogen which is considered as the furthermost active moderator as well as boron which is an extremely appropriate absorber of thermal neutrons. The study has been conducted by determining the γ−ray energy absorption buildup factors (EABF) as well as the exposure buildup factors (EBF). The evaluation of the buildup factors has been determined by employing the five parameters geometric progression (G-P) fitting approximation and taking into account the reference standard database (1991-ANSI/ANS-6.4.3). This determination has been carried out using a photon energy varying from 0.015 to 15 MeV with a permeation depth until 40 mean free paths. By investigating on the reliance of EABF and EBF on the incident photon energy, chemical arrangement, and permeation depth, a deeply comparison between the obtained values of EABF and EBF has been performed. By inspecting the obtained values of EABF and EBF established for the first time, our numerical simulations allow to conclude that among the selected shielding materials, Field castable Heat Resistant shielding and 5.45% Borated Polyethylene provide the lower buildup factors at lower energies (<1.5 MeV for EABF, <2 MeV for EBF), suggesting thereby their candidacy to serve as potential shielding materials against γ−radiation in this energy range. The results of the present investigation therefore shed light on selectivity of the appropriate shielding material as well as the determination of the optimum thickness of the shielding material subject of having superior neutrons shielding ability. |
| abstract_unstemmed |
We report γ−ray shielding effectiveness of eight selected shielding materials susceptible to be used for the conception of γ−ray and fast neutrons absorbers has been investigated. Four of the selected materials were polyethylene composites, the first one is doped with 7.5% Lithium (Lithium7.5%-Polyethylene), the second one is doped with 8.97% boron (Borated8.97%-Polyethylene), the third one is doped with 5.45% boron (Borated5.45%-Polyethylene), and the fourth one contains high hydrogen content as well as 0.9% by weight boron namely Self Extinguishing Borated Polythylene. The other four considered materials are FlexiBoron, High Temperature Boron Silicone, Polykast Dry Mix, and Field castable Heat Resistant shielding. These materials have been selected in fact because they contain iron (Fe), zinc (Zn), Strontium (Sr) and Manganese (Mn) which heavy elements and considered as good absorbers of γ−radiation and also because they contain hydrogen which is considered as the furthermost active moderator as well as boron which is an extremely appropriate absorber of thermal neutrons. The study has been conducted by determining the γ−ray energy absorption buildup factors (EABF) as well as the exposure buildup factors (EBF). The evaluation of the buildup factors has been determined by employing the five parameters geometric progression (G-P) fitting approximation and taking into account the reference standard database (1991-ANSI/ANS-6.4.3). This determination has been carried out using a photon energy varying from 0.015 to 15 MeV with a permeation depth until 40 mean free paths. By investigating on the reliance of EABF and EBF on the incident photon energy, chemical arrangement, and permeation depth, a deeply comparison between the obtained values of EABF and EBF has been performed. By inspecting the obtained values of EABF and EBF established for the first time, our numerical simulations allow to conclude that among the selected shielding materials, Field castable Heat Resistant shielding and 5.45% Borated Polyethylene provide the lower buildup factors at lower energies (<1.5 MeV for EABF, <2 MeV for EBF), suggesting thereby their candidacy to serve as potential shielding materials against γ−radiation in this energy range. The results of the present investigation therefore shed light on selectivity of the appropriate shielding material as well as the determination of the optimum thickness of the shielding material subject of having superior neutrons shielding ability. |
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Calculating photon buildup factors in determining the γ-ray shielding effectiveness of some materials susceptible to be used for the conception of neutrons and γ-ray shielding |
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https://doi.org/10.1016/j.jmrt.2021.01.052 https://doaj.org/article/2a142af04d39441181df141dc76a71fd http://www.sciencedirect.com/science/article/pii/S2238785421000521 https://doaj.org/toc/2238-7854 |
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Youssef Elmahroug B.M. Alotaibi Haifa A. Alyousef Najeh Rekik A. Wahab M.A. Hussein Ram Chand Umer Farooq |
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Youssef Elmahroug B.M. Alotaibi Haifa A. Alyousef Najeh Rekik A. Wahab M.A. Hussein Ram Chand Umer Farooq |
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10.1016/j.jmrt.2021.01.052 |
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