Simulation study of uranium content in uranium yellow cake using the active multiplicity method
BackgroundAccurately quantifying the uranium in uranium yellow cake material is the key to selecting the subsequent processing technology. As an essential nondestructive testing method for uranium-containing materials, the active multiplicity method is proposed to quantify uranium by recording and a...
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| Autor*in: |
ZHANG Haoran [verfasserIn] ZHANG Yan [verfasserIn] HU Wenxing [verfasserIn] QU Jinhui [verfasserIn] LIU Shiliang [verfasserIn] WANG Renbo [verfasserIn] |
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| Format: |
E-Artikel |
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| Sprache: |
Chinesisch |
| Erschienen: |
2024 |
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| Übergeordnetes Werk: |
In: He jishu - Science Press, 2022, 47(2024), 2, Seite 49-57 |
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| Übergeordnetes Werk: |
volume:47 ; year:2024 ; number:2 ; pages:49-57 |
| Links: |
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| DOI / URN: |
10.11889/j.0253-3219.2024.hjs.47.020202 |
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| Katalog-ID: |
DOAJ091681995 |
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| 520 | |a BackgroundAccurately quantifying the uranium in uranium yellow cake material is the key to selecting the subsequent processing technology. As an essential nondestructive testing method for uranium-containing materials, the active multiplicity method is proposed to quantify uranium by recording and analyzing 238U fission information induced by neutron sources. However, the quantitative results are biased owing to the neutron self-shielding of the uranium yellow cake material itself and differences in water content between samples.PurposeThis study aims to rapidly measure the uranium content of uranium yellow cake material using active multiplicity method and further improve of measurement accuracy.MethodsFirst of all, following the comparison of the excitation effects of different neutron sources on a sample using the MCNP (Monte Carlo N-Particle Transport) program, a 241Am-Be source was selected to simulate the sample measurement process and optimized using MATLAB programming combined with MCNP. Then, the curve of multiplication factor M versus the uranium mass was obtained by simulation, and an appropriate M was selected according to the net content of the sample. Finally, the quantitative error caused by the difference between neutron absorption and water content in the process was investigated, and the double rate was corrected using the relationship between S0/Si and D0/Di and then calculated.ResultsThe simulation results of a series of samples with different masses and water contents show that a large gap is found between M and the leakage multiplication factor ML caused by neutron self-shielding. The error in uranium quantification is less than 5%; neutron self-shielding due to the change in water content affects the single, double, and triple counting rates (S/D/T). The relative error of uranium quantification can be controlled at around 10%.ConclusionsThis study has significance and important reference value for further research on the application of the active multiplicity method in the production and measurement of uranium yellow cake. | ||
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10.11889/j.0253-3219.2024.hjs.47.020202 doi (DE-627)DOAJ091681995 (DE-599)DOAJ8ed5e73864fb4f9baa720276c8834f65 DE-627 ger DE-627 rakwb chi TK9001-9401 ZHANG Haoran verfasserin aut Simulation study of uranium content in uranium yellow cake using the active multiplicity method 2024 Text txt rdacontent Computermedien c rdamedia Online-Ressource cr rdacarrier BackgroundAccurately quantifying the uranium in uranium yellow cake material is the key to selecting the subsequent processing technology. As an essential nondestructive testing method for uranium-containing materials, the active multiplicity method is proposed to quantify uranium by recording and analyzing 238U fission information induced by neutron sources. However, the quantitative results are biased owing to the neutron self-shielding of the uranium yellow cake material itself and differences in water content between samples.PurposeThis study aims to rapidly measure the uranium content of uranium yellow cake material using active multiplicity method and further improve of measurement accuracy.MethodsFirst of all, following the comparison of the excitation effects of different neutron sources on a sample using the MCNP (Monte Carlo N-Particle Transport) program, a 241Am-Be source was selected to simulate the sample measurement process and optimized using MATLAB programming combined with MCNP. Then, the curve of multiplication factor M versus the uranium mass was obtained by simulation, and an appropriate M was selected according to the net content of the sample. Finally, the quantitative error caused by the difference between neutron absorption and water content in the process was investigated, and the double rate was corrected using the relationship between S0/Si and D0/Di and then calculated.ResultsThe simulation results of a series of samples with different masses and water contents show that a large gap is found between M and the leakage multiplication factor ML caused by neutron self-shielding. The error in uranium quantification is less than 5%; neutron self-shielding due to the change in water content affects the single, double, and triple counting rates (S/D/T). The relative error of uranium quantification can be controlled at around 10%.ConclusionsThis study has significance and important reference value for further research on the application of the active multiplicity method in the production and measurement of uranium yellow cake. neutron multiplicity uranium yellow cake 238u neutron self-shielding simulation Nuclear engineering. Atomic power ZHANG Yan verfasserin aut HU Wenxing verfasserin aut QU Jinhui verfasserin aut LIU Shiliang verfasserin aut WANG Renbo verfasserin aut In He jishu Science Press, 2022 47(2024), 2, Seite 49-57 (DE-627)DOAJ078593506 02533219 nnns volume:47 year:2024 number:2 pages:49-57 https://doi.org/10.11889/j.0253-3219.2024.hjs.47.020202 kostenfrei https://doaj.org/article/8ed5e73864fb4f9baa720276c8834f65 kostenfrei http://www.hjs.sinap.ac.cn/thesisDetails#10.11889/j.0253-3219.2024.hjs.47.020202&lang=zh kostenfrei https://doaj.org/toc/0253-3219 Journal toc kostenfrei GBV_USEFLAG_A SYSFLAG_A GBV_DOAJ AR 47 2024 2 49-57 |
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10.11889/j.0253-3219.2024.hjs.47.020202 doi (DE-627)DOAJ091681995 (DE-599)DOAJ8ed5e73864fb4f9baa720276c8834f65 DE-627 ger DE-627 rakwb chi TK9001-9401 ZHANG Haoran verfasserin aut Simulation study of uranium content in uranium yellow cake using the active multiplicity method 2024 Text txt rdacontent Computermedien c rdamedia Online-Ressource cr rdacarrier BackgroundAccurately quantifying the uranium in uranium yellow cake material is the key to selecting the subsequent processing technology. As an essential nondestructive testing method for uranium-containing materials, the active multiplicity method is proposed to quantify uranium by recording and analyzing 238U fission information induced by neutron sources. However, the quantitative results are biased owing to the neutron self-shielding of the uranium yellow cake material itself and differences in water content between samples.PurposeThis study aims to rapidly measure the uranium content of uranium yellow cake material using active multiplicity method and further improve of measurement accuracy.MethodsFirst of all, following the comparison of the excitation effects of different neutron sources on a sample using the MCNP (Monte Carlo N-Particle Transport) program, a 241Am-Be source was selected to simulate the sample measurement process and optimized using MATLAB programming combined with MCNP. Then, the curve of multiplication factor M versus the uranium mass was obtained by simulation, and an appropriate M was selected according to the net content of the sample. Finally, the quantitative error caused by the difference between neutron absorption and water content in the process was investigated, and the double rate was corrected using the relationship between S0/Si and D0/Di and then calculated.ResultsThe simulation results of a series of samples with different masses and water contents show that a large gap is found between M and the leakage multiplication factor ML caused by neutron self-shielding. The error in uranium quantification is less than 5%; neutron self-shielding due to the change in water content affects the single, double, and triple counting rates (S/D/T). The relative error of uranium quantification can be controlled at around 10%.ConclusionsThis study has significance and important reference value for further research on the application of the active multiplicity method in the production and measurement of uranium yellow cake. neutron multiplicity uranium yellow cake 238u neutron self-shielding simulation Nuclear engineering. Atomic power ZHANG Yan verfasserin aut HU Wenxing verfasserin aut QU Jinhui verfasserin aut LIU Shiliang verfasserin aut WANG Renbo verfasserin aut In He jishu Science Press, 2022 47(2024), 2, Seite 49-57 (DE-627)DOAJ078593506 02533219 nnns volume:47 year:2024 number:2 pages:49-57 https://doi.org/10.11889/j.0253-3219.2024.hjs.47.020202 kostenfrei https://doaj.org/article/8ed5e73864fb4f9baa720276c8834f65 kostenfrei http://www.hjs.sinap.ac.cn/thesisDetails#10.11889/j.0253-3219.2024.hjs.47.020202&lang=zh kostenfrei https://doaj.org/toc/0253-3219 Journal toc kostenfrei GBV_USEFLAG_A SYSFLAG_A GBV_DOAJ AR 47 2024 2 49-57 |
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10.11889/j.0253-3219.2024.hjs.47.020202 doi (DE-627)DOAJ091681995 (DE-599)DOAJ8ed5e73864fb4f9baa720276c8834f65 DE-627 ger DE-627 rakwb chi TK9001-9401 ZHANG Haoran verfasserin aut Simulation study of uranium content in uranium yellow cake using the active multiplicity method 2024 Text txt rdacontent Computermedien c rdamedia Online-Ressource cr rdacarrier BackgroundAccurately quantifying the uranium in uranium yellow cake material is the key to selecting the subsequent processing technology. As an essential nondestructive testing method for uranium-containing materials, the active multiplicity method is proposed to quantify uranium by recording and analyzing 238U fission information induced by neutron sources. However, the quantitative results are biased owing to the neutron self-shielding of the uranium yellow cake material itself and differences in water content between samples.PurposeThis study aims to rapidly measure the uranium content of uranium yellow cake material using active multiplicity method and further improve of measurement accuracy.MethodsFirst of all, following the comparison of the excitation effects of different neutron sources on a sample using the MCNP (Monte Carlo N-Particle Transport) program, a 241Am-Be source was selected to simulate the sample measurement process and optimized using MATLAB programming combined with MCNP. Then, the curve of multiplication factor M versus the uranium mass was obtained by simulation, and an appropriate M was selected according to the net content of the sample. Finally, the quantitative error caused by the difference between neutron absorption and water content in the process was investigated, and the double rate was corrected using the relationship between S0/Si and D0/Di and then calculated.ResultsThe simulation results of a series of samples with different masses and water contents show that a large gap is found between M and the leakage multiplication factor ML caused by neutron self-shielding. The error in uranium quantification is less than 5%; neutron self-shielding due to the change in water content affects the single, double, and triple counting rates (S/D/T). The relative error of uranium quantification can be controlled at around 10%.ConclusionsThis study has significance and important reference value for further research on the application of the active multiplicity method in the production and measurement of uranium yellow cake. neutron multiplicity uranium yellow cake 238u neutron self-shielding simulation Nuclear engineering. Atomic power ZHANG Yan verfasserin aut HU Wenxing verfasserin aut QU Jinhui verfasserin aut LIU Shiliang verfasserin aut WANG Renbo verfasserin aut In He jishu Science Press, 2022 47(2024), 2, Seite 49-57 (DE-627)DOAJ078593506 02533219 nnns volume:47 year:2024 number:2 pages:49-57 https://doi.org/10.11889/j.0253-3219.2024.hjs.47.020202 kostenfrei https://doaj.org/article/8ed5e73864fb4f9baa720276c8834f65 kostenfrei http://www.hjs.sinap.ac.cn/thesisDetails#10.11889/j.0253-3219.2024.hjs.47.020202&lang=zh kostenfrei https://doaj.org/toc/0253-3219 Journal toc kostenfrei GBV_USEFLAG_A SYSFLAG_A GBV_DOAJ AR 47 2024 2 49-57 |
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10.11889/j.0253-3219.2024.hjs.47.020202 doi (DE-627)DOAJ091681995 (DE-599)DOAJ8ed5e73864fb4f9baa720276c8834f65 DE-627 ger DE-627 rakwb chi TK9001-9401 ZHANG Haoran verfasserin aut Simulation study of uranium content in uranium yellow cake using the active multiplicity method 2024 Text txt rdacontent Computermedien c rdamedia Online-Ressource cr rdacarrier BackgroundAccurately quantifying the uranium in uranium yellow cake material is the key to selecting the subsequent processing technology. As an essential nondestructive testing method for uranium-containing materials, the active multiplicity method is proposed to quantify uranium by recording and analyzing 238U fission information induced by neutron sources. However, the quantitative results are biased owing to the neutron self-shielding of the uranium yellow cake material itself and differences in water content between samples.PurposeThis study aims to rapidly measure the uranium content of uranium yellow cake material using active multiplicity method and further improve of measurement accuracy.MethodsFirst of all, following the comparison of the excitation effects of different neutron sources on a sample using the MCNP (Monte Carlo N-Particle Transport) program, a 241Am-Be source was selected to simulate the sample measurement process and optimized using MATLAB programming combined with MCNP. Then, the curve of multiplication factor M versus the uranium mass was obtained by simulation, and an appropriate M was selected according to the net content of the sample. Finally, the quantitative error caused by the difference between neutron absorption and water content in the process was investigated, and the double rate was corrected using the relationship between S0/Si and D0/Di and then calculated.ResultsThe simulation results of a series of samples with different masses and water contents show that a large gap is found between M and the leakage multiplication factor ML caused by neutron self-shielding. The error in uranium quantification is less than 5%; neutron self-shielding due to the change in water content affects the single, double, and triple counting rates (S/D/T). The relative error of uranium quantification can be controlled at around 10%.ConclusionsThis study has significance and important reference value for further research on the application of the active multiplicity method in the production and measurement of uranium yellow cake. neutron multiplicity uranium yellow cake 238u neutron self-shielding simulation Nuclear engineering. Atomic power ZHANG Yan verfasserin aut HU Wenxing verfasserin aut QU Jinhui verfasserin aut LIU Shiliang verfasserin aut WANG Renbo verfasserin aut In He jishu Science Press, 2022 47(2024), 2, Seite 49-57 (DE-627)DOAJ078593506 02533219 nnns volume:47 year:2024 number:2 pages:49-57 https://doi.org/10.11889/j.0253-3219.2024.hjs.47.020202 kostenfrei https://doaj.org/article/8ed5e73864fb4f9baa720276c8834f65 kostenfrei http://www.hjs.sinap.ac.cn/thesisDetails#10.11889/j.0253-3219.2024.hjs.47.020202&lang=zh kostenfrei https://doaj.org/toc/0253-3219 Journal toc kostenfrei GBV_USEFLAG_A SYSFLAG_A GBV_DOAJ AR 47 2024 2 49-57 |
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10.11889/j.0253-3219.2024.hjs.47.020202 doi (DE-627)DOAJ091681995 (DE-599)DOAJ8ed5e73864fb4f9baa720276c8834f65 DE-627 ger DE-627 rakwb chi TK9001-9401 ZHANG Haoran verfasserin aut Simulation study of uranium content in uranium yellow cake using the active multiplicity method 2024 Text txt rdacontent Computermedien c rdamedia Online-Ressource cr rdacarrier BackgroundAccurately quantifying the uranium in uranium yellow cake material is the key to selecting the subsequent processing technology. As an essential nondestructive testing method for uranium-containing materials, the active multiplicity method is proposed to quantify uranium by recording and analyzing 238U fission information induced by neutron sources. However, the quantitative results are biased owing to the neutron self-shielding of the uranium yellow cake material itself and differences in water content between samples.PurposeThis study aims to rapidly measure the uranium content of uranium yellow cake material using active multiplicity method and further improve of measurement accuracy.MethodsFirst of all, following the comparison of the excitation effects of different neutron sources on a sample using the MCNP (Monte Carlo N-Particle Transport) program, a 241Am-Be source was selected to simulate the sample measurement process and optimized using MATLAB programming combined with MCNP. Then, the curve of multiplication factor M versus the uranium mass was obtained by simulation, and an appropriate M was selected according to the net content of the sample. Finally, the quantitative error caused by the difference between neutron absorption and water content in the process was investigated, and the double rate was corrected using the relationship between S0/Si and D0/Di and then calculated.ResultsThe simulation results of a series of samples with different masses and water contents show that a large gap is found between M and the leakage multiplication factor ML caused by neutron self-shielding. The error in uranium quantification is less than 5%; neutron self-shielding due to the change in water content affects the single, double, and triple counting rates (S/D/T). The relative error of uranium quantification can be controlled at around 10%.ConclusionsThis study has significance and important reference value for further research on the application of the active multiplicity method in the production and measurement of uranium yellow cake. neutron multiplicity uranium yellow cake 238u neutron self-shielding simulation Nuclear engineering. Atomic power ZHANG Yan verfasserin aut HU Wenxing verfasserin aut QU Jinhui verfasserin aut LIU Shiliang verfasserin aut WANG Renbo verfasserin aut In He jishu Science Press, 2022 47(2024), 2, Seite 49-57 (DE-627)DOAJ078593506 02533219 nnns volume:47 year:2024 number:2 pages:49-57 https://doi.org/10.11889/j.0253-3219.2024.hjs.47.020202 kostenfrei https://doaj.org/article/8ed5e73864fb4f9baa720276c8834f65 kostenfrei http://www.hjs.sinap.ac.cn/thesisDetails#10.11889/j.0253-3219.2024.hjs.47.020202&lang=zh kostenfrei https://doaj.org/toc/0253-3219 Journal toc kostenfrei GBV_USEFLAG_A SYSFLAG_A GBV_DOAJ AR 47 2024 2 49-57 |
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As an essential nondestructive testing method for uranium-containing materials, the active multiplicity method is proposed to quantify uranium by recording and analyzing 238U fission information induced by neutron sources. However, the quantitative results are biased owing to the neutron self-shielding of the uranium yellow cake material itself and differences in water content between samples.PurposeThis study aims to rapidly measure the uranium content of uranium yellow cake material using active multiplicity method and further improve of measurement accuracy.MethodsFirst of all, following the comparison of the excitation effects of different neutron sources on a sample using the MCNP (Monte Carlo N-Particle Transport) program, a 241Am-Be source was selected to simulate the sample measurement process and optimized using MATLAB programming combined with MCNP. Then, the curve of multiplication factor M versus the uranium mass was obtained by simulation, and an appropriate M was selected according to the net content of the sample. Finally, the quantitative error caused by the difference between neutron absorption and water content in the process was investigated, and the double rate was corrected using the relationship between S0/Si and D0/Di and then calculated.ResultsThe simulation results of a series of samples with different masses and water contents show that a large gap is found between M and the leakage multiplication factor ML caused by neutron self-shielding. The error in uranium quantification is less than 5%; neutron self-shielding due to the change in water content affects the single, double, and triple counting rates (S/D/T). 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Simulation study of uranium content in uranium yellow cake using the active multiplicity method |
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BackgroundAccurately quantifying the uranium in uranium yellow cake material is the key to selecting the subsequent processing technology. As an essential nondestructive testing method for uranium-containing materials, the active multiplicity method is proposed to quantify uranium by recording and analyzing 238U fission information induced by neutron sources. However, the quantitative results are biased owing to the neutron self-shielding of the uranium yellow cake material itself and differences in water content between samples.PurposeThis study aims to rapidly measure the uranium content of uranium yellow cake material using active multiplicity method and further improve of measurement accuracy.MethodsFirst of all, following the comparison of the excitation effects of different neutron sources on a sample using the MCNP (Monte Carlo N-Particle Transport) program, a 241Am-Be source was selected to simulate the sample measurement process and optimized using MATLAB programming combined with MCNP. Then, the curve of multiplication factor M versus the uranium mass was obtained by simulation, and an appropriate M was selected according to the net content of the sample. Finally, the quantitative error caused by the difference between neutron absorption and water content in the process was investigated, and the double rate was corrected using the relationship between S0/Si and D0/Di and then calculated.ResultsThe simulation results of a series of samples with different masses and water contents show that a large gap is found between M and the leakage multiplication factor ML caused by neutron self-shielding. The error in uranium quantification is less than 5%; neutron self-shielding due to the change in water content affects the single, double, and triple counting rates (S/D/T). The relative error of uranium quantification can be controlled at around 10%.ConclusionsThis study has significance and important reference value for further research on the application of the active multiplicity method in the production and measurement of uranium yellow cake. |
| abstractGer |
BackgroundAccurately quantifying the uranium in uranium yellow cake material is the key to selecting the subsequent processing technology. As an essential nondestructive testing method for uranium-containing materials, the active multiplicity method is proposed to quantify uranium by recording and analyzing 238U fission information induced by neutron sources. However, the quantitative results are biased owing to the neutron self-shielding of the uranium yellow cake material itself and differences in water content between samples.PurposeThis study aims to rapidly measure the uranium content of uranium yellow cake material using active multiplicity method and further improve of measurement accuracy.MethodsFirst of all, following the comparison of the excitation effects of different neutron sources on a sample using the MCNP (Monte Carlo N-Particle Transport) program, a 241Am-Be source was selected to simulate the sample measurement process and optimized using MATLAB programming combined with MCNP. Then, the curve of multiplication factor M versus the uranium mass was obtained by simulation, and an appropriate M was selected according to the net content of the sample. Finally, the quantitative error caused by the difference between neutron absorption and water content in the process was investigated, and the double rate was corrected using the relationship between S0/Si and D0/Di and then calculated.ResultsThe simulation results of a series of samples with different masses and water contents show that a large gap is found between M and the leakage multiplication factor ML caused by neutron self-shielding. The error in uranium quantification is less than 5%; neutron self-shielding due to the change in water content affects the single, double, and triple counting rates (S/D/T). The relative error of uranium quantification can be controlled at around 10%.ConclusionsThis study has significance and important reference value for further research on the application of the active multiplicity method in the production and measurement of uranium yellow cake. |
| abstract_unstemmed |
BackgroundAccurately quantifying the uranium in uranium yellow cake material is the key to selecting the subsequent processing technology. As an essential nondestructive testing method for uranium-containing materials, the active multiplicity method is proposed to quantify uranium by recording and analyzing 238U fission information induced by neutron sources. However, the quantitative results are biased owing to the neutron self-shielding of the uranium yellow cake material itself and differences in water content between samples.PurposeThis study aims to rapidly measure the uranium content of uranium yellow cake material using active multiplicity method and further improve of measurement accuracy.MethodsFirst of all, following the comparison of the excitation effects of different neutron sources on a sample using the MCNP (Monte Carlo N-Particle Transport) program, a 241Am-Be source was selected to simulate the sample measurement process and optimized using MATLAB programming combined with MCNP. Then, the curve of multiplication factor M versus the uranium mass was obtained by simulation, and an appropriate M was selected according to the net content of the sample. Finally, the quantitative error caused by the difference between neutron absorption and water content in the process was investigated, and the double rate was corrected using the relationship between S0/Si and D0/Di and then calculated.ResultsThe simulation results of a series of samples with different masses and water contents show that a large gap is found between M and the leakage multiplication factor ML caused by neutron self-shielding. The error in uranium quantification is less than 5%; neutron self-shielding due to the change in water content affects the single, double, and triple counting rates (S/D/T). The relative error of uranium quantification can be controlled at around 10%.ConclusionsThis study has significance and important reference value for further research on the application of the active multiplicity method in the production and measurement of uranium yellow cake. |
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