An optimization study for shielding design of D-D and D-T neutron generators
Neutron generators (NG) are being increasingly used in various industrial and research areas such as neutron activation analysis, neutron radiography, and neutron capture therapy. In such applications of neutron generators, compactness is one of the most important issues. Since a neutron source is g...
Ausführliche Beschreibung
Gespeichert in:
| Autor*in: |
Yun, Sunghwan [verfasserIn] |
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| Format: |
E-Artikel |
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| Sprache: |
Englisch |
| Erschienen: |
2019transfer abstract |
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| Umfang: |
4 |
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| Übergeordnetes Werk: |
Enthalten in: CFD modelling of local scour around Tri-USAF in sand with different arrangements under steady current - Yang, Qi ELSEVIER, 2021, an international journal for fusion energy and technology devoted to experiments, theory, methods, and design, New York, NY [u.a.] |
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| Übergeordnetes Werk: |
volume:146 ; year:2019 ; pages:531-534 ; extent:4 |
| Links: |
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| DOI / URN: |
10.1016/j.fusengdes.2019.01.014 |
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| Katalog-ID: |
ELV047636785 |
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| 520 | |a Neutron generators (NG) are being increasingly used in various industrial and research areas such as neutron activation analysis, neutron radiography, and neutron capture therapy. In such applications of neutron generators, compactness is one of the most important issues. Since a neutron source is generated by deuterium-deuterium (D-D) or deuterium-tritium (D-T) fusion reaction, a relatively thick shield for both fast neutrons and related photons is usually required. In this study, optimization of shielding designs for D-D and D-T neutron generators were investigated by adopting appropriate moderator and shielding materials. Based on the optimized moderator and shield thicknesses, the final dimensions of neutron generators were derived for various source strengths of D-D and D-T neutron conditions. Considering conventional condition of a container, we concluded that a 1010 n/sec D-D source and a 108 n/sec D-T source could be a portable NG. | ||
| 520 | |a Neutron generators (NG) are being increasingly used in various industrial and research areas such as neutron activation analysis, neutron radiography, and neutron capture therapy. In such applications of neutron generators, compactness is one of the most important issues. Since a neutron source is generated by deuterium-deuterium (D-D) or deuterium-tritium (D-T) fusion reaction, a relatively thick shield for both fast neutrons and related photons is usually required. In this study, optimization of shielding designs for D-D and D-T neutron generators were investigated by adopting appropriate moderator and shielding materials. Based on the optimized moderator and shield thicknesses, the final dimensions of neutron generators were derived for various source strengths of D-D and D-T neutron conditions. Considering conventional condition of a container, we concluded that a 1010 n/sec D-D source and a 108 n/sec D-T source could be a portable NG. | ||
| 650 | 7 | |a D-D neutron source |2 Elsevier | |
| 650 | 7 | |a Portable neutron source |2 Elsevier | |
| 650 | 7 | |a D-T neutron source |2 Elsevier | |
| 650 | 7 | |a Neutron generator |2 Elsevier | |
| 650 | 7 | |a Neutron shielding analysis |2 Elsevier | |
| 700 | 1 | |a Lee, Cheol Woo |4 oth | |
| 700 | 1 | |a Lee, Dong Won |4 oth | |
| 700 | 1 | |a Kim, Sun-Ho |4 oth | |
| 700 | 1 | |a Jung, Bongki |4 oth | |
| 700 | 1 | |a Chang, Doo-Hee |4 oth | |
| 700 | 1 | |a Jin, Hyung Gon |4 oth | |
| 700 | 1 | |a Shin, Chang Wook |4 oth | |
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10.1016/j.fusengdes.2019.01.014 doi GBV00000000000726.pica (DE-627)ELV047636785 (ELSEVIER)S0920-3796(19)30019-5 DE-627 ger DE-627 rakwb eng 690 VZ 50.92 bkl Yun, Sunghwan verfasserin aut An optimization study for shielding design of D-D and D-T neutron generators 2019transfer abstract 4 nicht spezifiziert zzz rdacontent nicht spezifiziert z rdamedia nicht spezifiziert zu rdacarrier Neutron generators (NG) are being increasingly used in various industrial and research areas such as neutron activation analysis, neutron radiography, and neutron capture therapy. In such applications of neutron generators, compactness is one of the most important issues. Since a neutron source is generated by deuterium-deuterium (D-D) or deuterium-tritium (D-T) fusion reaction, a relatively thick shield for both fast neutrons and related photons is usually required. In this study, optimization of shielding designs for D-D and D-T neutron generators were investigated by adopting appropriate moderator and shielding materials. Based on the optimized moderator and shield thicknesses, the final dimensions of neutron generators were derived for various source strengths of D-D and D-T neutron conditions. Considering conventional condition of a container, we concluded that a 1010 n/sec D-D source and a 108 n/sec D-T source could be a portable NG. Neutron generators (NG) are being increasingly used in various industrial and research areas such as neutron activation analysis, neutron radiography, and neutron capture therapy. In such applications of neutron generators, compactness is one of the most important issues. Since a neutron source is generated by deuterium-deuterium (D-D) or deuterium-tritium (D-T) fusion reaction, a relatively thick shield for both fast neutrons and related photons is usually required. In this study, optimization of shielding designs for D-D and D-T neutron generators were investigated by adopting appropriate moderator and shielding materials. Based on the optimized moderator and shield thicknesses, the final dimensions of neutron generators were derived for various source strengths of D-D and D-T neutron conditions. Considering conventional condition of a container, we concluded that a 1010 n/sec D-D source and a 108 n/sec D-T source could be a portable NG. D-D neutron source Elsevier Portable neutron source Elsevier D-T neutron source Elsevier Neutron generator Elsevier Neutron shielding analysis Elsevier Lee, Cheol Woo oth Lee, Dong Won oth Kim, Sun-Ho oth Jung, Bongki oth Chang, Doo-Hee oth Jin, Hyung Gon oth Shin, Chang Wook oth Enthalten in Elsevier Yang, Qi ELSEVIER CFD modelling of local scour around Tri-USAF in sand with different arrangements under steady current 2021 an international journal for fusion energy and technology devoted to experiments, theory, methods, and design New York, NY [u.a.] (DE-627)ELV006449069 volume:146 year:2019 pages:531-534 extent:4 https://doi.org/10.1016/j.fusengdes.2019.01.014 Volltext GBV_USEFLAG_U GBV_ELV SYSFLAG_U 50.92 Meerestechnik VZ AR 146 2019 531-534 4 |
| spelling |
10.1016/j.fusengdes.2019.01.014 doi GBV00000000000726.pica (DE-627)ELV047636785 (ELSEVIER)S0920-3796(19)30019-5 DE-627 ger DE-627 rakwb eng 690 VZ 50.92 bkl Yun, Sunghwan verfasserin aut An optimization study for shielding design of D-D and D-T neutron generators 2019transfer abstract 4 nicht spezifiziert zzz rdacontent nicht spezifiziert z rdamedia nicht spezifiziert zu rdacarrier Neutron generators (NG) are being increasingly used in various industrial and research areas such as neutron activation analysis, neutron radiography, and neutron capture therapy. In such applications of neutron generators, compactness is one of the most important issues. Since a neutron source is generated by deuterium-deuterium (D-D) or deuterium-tritium (D-T) fusion reaction, a relatively thick shield for both fast neutrons and related photons is usually required. In this study, optimization of shielding designs for D-D and D-T neutron generators were investigated by adopting appropriate moderator and shielding materials. Based on the optimized moderator and shield thicknesses, the final dimensions of neutron generators were derived for various source strengths of D-D and D-T neutron conditions. Considering conventional condition of a container, we concluded that a 1010 n/sec D-D source and a 108 n/sec D-T source could be a portable NG. Neutron generators (NG) are being increasingly used in various industrial and research areas such as neutron activation analysis, neutron radiography, and neutron capture therapy. In such applications of neutron generators, compactness is one of the most important issues. Since a neutron source is generated by deuterium-deuterium (D-D) or deuterium-tritium (D-T) fusion reaction, a relatively thick shield for both fast neutrons and related photons is usually required. In this study, optimization of shielding designs for D-D and D-T neutron generators were investigated by adopting appropriate moderator and shielding materials. Based on the optimized moderator and shield thicknesses, the final dimensions of neutron generators were derived for various source strengths of D-D and D-T neutron conditions. Considering conventional condition of a container, we concluded that a 1010 n/sec D-D source and a 108 n/sec D-T source could be a portable NG. D-D neutron source Elsevier Portable neutron source Elsevier D-T neutron source Elsevier Neutron generator Elsevier Neutron shielding analysis Elsevier Lee, Cheol Woo oth Lee, Dong Won oth Kim, Sun-Ho oth Jung, Bongki oth Chang, Doo-Hee oth Jin, Hyung Gon oth Shin, Chang Wook oth Enthalten in Elsevier Yang, Qi ELSEVIER CFD modelling of local scour around Tri-USAF in sand with different arrangements under steady current 2021 an international journal for fusion energy and technology devoted to experiments, theory, methods, and design New York, NY [u.a.] (DE-627)ELV006449069 volume:146 year:2019 pages:531-534 extent:4 https://doi.org/10.1016/j.fusengdes.2019.01.014 Volltext GBV_USEFLAG_U GBV_ELV SYSFLAG_U 50.92 Meerestechnik VZ AR 146 2019 531-534 4 |
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10.1016/j.fusengdes.2019.01.014 doi GBV00000000000726.pica (DE-627)ELV047636785 (ELSEVIER)S0920-3796(19)30019-5 DE-627 ger DE-627 rakwb eng 690 VZ 50.92 bkl Yun, Sunghwan verfasserin aut An optimization study for shielding design of D-D and D-T neutron generators 2019transfer abstract 4 nicht spezifiziert zzz rdacontent nicht spezifiziert z rdamedia nicht spezifiziert zu rdacarrier Neutron generators (NG) are being increasingly used in various industrial and research areas such as neutron activation analysis, neutron radiography, and neutron capture therapy. In such applications of neutron generators, compactness is one of the most important issues. Since a neutron source is generated by deuterium-deuterium (D-D) or deuterium-tritium (D-T) fusion reaction, a relatively thick shield for both fast neutrons and related photons is usually required. In this study, optimization of shielding designs for D-D and D-T neutron generators were investigated by adopting appropriate moderator and shielding materials. Based on the optimized moderator and shield thicknesses, the final dimensions of neutron generators were derived for various source strengths of D-D and D-T neutron conditions. Considering conventional condition of a container, we concluded that a 1010 n/sec D-D source and a 108 n/sec D-T source could be a portable NG. Neutron generators (NG) are being increasingly used in various industrial and research areas such as neutron activation analysis, neutron radiography, and neutron capture therapy. In such applications of neutron generators, compactness is one of the most important issues. Since a neutron source is generated by deuterium-deuterium (D-D) or deuterium-tritium (D-T) fusion reaction, a relatively thick shield for both fast neutrons and related photons is usually required. In this study, optimization of shielding designs for D-D and D-T neutron generators were investigated by adopting appropriate moderator and shielding materials. Based on the optimized moderator and shield thicknesses, the final dimensions of neutron generators were derived for various source strengths of D-D and D-T neutron conditions. Considering conventional condition of a container, we concluded that a 1010 n/sec D-D source and a 108 n/sec D-T source could be a portable NG. D-D neutron source Elsevier Portable neutron source Elsevier D-T neutron source Elsevier Neutron generator Elsevier Neutron shielding analysis Elsevier Lee, Cheol Woo oth Lee, Dong Won oth Kim, Sun-Ho oth Jung, Bongki oth Chang, Doo-Hee oth Jin, Hyung Gon oth Shin, Chang Wook oth Enthalten in Elsevier Yang, Qi ELSEVIER CFD modelling of local scour around Tri-USAF in sand with different arrangements under steady current 2021 an international journal for fusion energy and technology devoted to experiments, theory, methods, and design New York, NY [u.a.] (DE-627)ELV006449069 volume:146 year:2019 pages:531-534 extent:4 https://doi.org/10.1016/j.fusengdes.2019.01.014 Volltext GBV_USEFLAG_U GBV_ELV SYSFLAG_U 50.92 Meerestechnik VZ AR 146 2019 531-534 4 |
| allfieldsGer |
10.1016/j.fusengdes.2019.01.014 doi GBV00000000000726.pica (DE-627)ELV047636785 (ELSEVIER)S0920-3796(19)30019-5 DE-627 ger DE-627 rakwb eng 690 VZ 50.92 bkl Yun, Sunghwan verfasserin aut An optimization study for shielding design of D-D and D-T neutron generators 2019transfer abstract 4 nicht spezifiziert zzz rdacontent nicht spezifiziert z rdamedia nicht spezifiziert zu rdacarrier Neutron generators (NG) are being increasingly used in various industrial and research areas such as neutron activation analysis, neutron radiography, and neutron capture therapy. In such applications of neutron generators, compactness is one of the most important issues. Since a neutron source is generated by deuterium-deuterium (D-D) or deuterium-tritium (D-T) fusion reaction, a relatively thick shield for both fast neutrons and related photons is usually required. In this study, optimization of shielding designs for D-D and D-T neutron generators were investigated by adopting appropriate moderator and shielding materials. Based on the optimized moderator and shield thicknesses, the final dimensions of neutron generators were derived for various source strengths of D-D and D-T neutron conditions. Considering conventional condition of a container, we concluded that a 1010 n/sec D-D source and a 108 n/sec D-T source could be a portable NG. Neutron generators (NG) are being increasingly used in various industrial and research areas such as neutron activation analysis, neutron radiography, and neutron capture therapy. In such applications of neutron generators, compactness is one of the most important issues. Since a neutron source is generated by deuterium-deuterium (D-D) or deuterium-tritium (D-T) fusion reaction, a relatively thick shield for both fast neutrons and related photons is usually required. In this study, optimization of shielding designs for D-D and D-T neutron generators were investigated by adopting appropriate moderator and shielding materials. Based on the optimized moderator and shield thicknesses, the final dimensions of neutron generators were derived for various source strengths of D-D and D-T neutron conditions. Considering conventional condition of a container, we concluded that a 1010 n/sec D-D source and a 108 n/sec D-T source could be a portable NG. D-D neutron source Elsevier Portable neutron source Elsevier D-T neutron source Elsevier Neutron generator Elsevier Neutron shielding analysis Elsevier Lee, Cheol Woo oth Lee, Dong Won oth Kim, Sun-Ho oth Jung, Bongki oth Chang, Doo-Hee oth Jin, Hyung Gon oth Shin, Chang Wook oth Enthalten in Elsevier Yang, Qi ELSEVIER CFD modelling of local scour around Tri-USAF in sand with different arrangements under steady current 2021 an international journal for fusion energy and technology devoted to experiments, theory, methods, and design New York, NY [u.a.] (DE-627)ELV006449069 volume:146 year:2019 pages:531-534 extent:4 https://doi.org/10.1016/j.fusengdes.2019.01.014 Volltext GBV_USEFLAG_U GBV_ELV SYSFLAG_U 50.92 Meerestechnik VZ AR 146 2019 531-534 4 |
| allfieldsSound |
10.1016/j.fusengdes.2019.01.014 doi GBV00000000000726.pica (DE-627)ELV047636785 (ELSEVIER)S0920-3796(19)30019-5 DE-627 ger DE-627 rakwb eng 690 VZ 50.92 bkl Yun, Sunghwan verfasserin aut An optimization study for shielding design of D-D and D-T neutron generators 2019transfer abstract 4 nicht spezifiziert zzz rdacontent nicht spezifiziert z rdamedia nicht spezifiziert zu rdacarrier Neutron generators (NG) are being increasingly used in various industrial and research areas such as neutron activation analysis, neutron radiography, and neutron capture therapy. In such applications of neutron generators, compactness is one of the most important issues. Since a neutron source is generated by deuterium-deuterium (D-D) or deuterium-tritium (D-T) fusion reaction, a relatively thick shield for both fast neutrons and related photons is usually required. In this study, optimization of shielding designs for D-D and D-T neutron generators were investigated by adopting appropriate moderator and shielding materials. Based on the optimized moderator and shield thicknesses, the final dimensions of neutron generators were derived for various source strengths of D-D and D-T neutron conditions. Considering conventional condition of a container, we concluded that a 1010 n/sec D-D source and a 108 n/sec D-T source could be a portable NG. Neutron generators (NG) are being increasingly used in various industrial and research areas such as neutron activation analysis, neutron radiography, and neutron capture therapy. In such applications of neutron generators, compactness is one of the most important issues. Since a neutron source is generated by deuterium-deuterium (D-D) or deuterium-tritium (D-T) fusion reaction, a relatively thick shield for both fast neutrons and related photons is usually required. In this study, optimization of shielding designs for D-D and D-T neutron generators were investigated by adopting appropriate moderator and shielding materials. Based on the optimized moderator and shield thicknesses, the final dimensions of neutron generators were derived for various source strengths of D-D and D-T neutron conditions. Considering conventional condition of a container, we concluded that a 1010 n/sec D-D source and a 108 n/sec D-T source could be a portable NG. D-D neutron source Elsevier Portable neutron source Elsevier D-T neutron source Elsevier Neutron generator Elsevier Neutron shielding analysis Elsevier Lee, Cheol Woo oth Lee, Dong Won oth Kim, Sun-Ho oth Jung, Bongki oth Chang, Doo-Hee oth Jin, Hyung Gon oth Shin, Chang Wook oth Enthalten in Elsevier Yang, Qi ELSEVIER CFD modelling of local scour around Tri-USAF in sand with different arrangements under steady current 2021 an international journal for fusion energy and technology devoted to experiments, theory, methods, and design New York, NY [u.a.] (DE-627)ELV006449069 volume:146 year:2019 pages:531-534 extent:4 https://doi.org/10.1016/j.fusengdes.2019.01.014 Volltext GBV_USEFLAG_U GBV_ELV SYSFLAG_U 50.92 Meerestechnik VZ AR 146 2019 531-534 4 |
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Enthalten in CFD modelling of local scour around Tri-USAF in sand with different arrangements under steady current New York, NY [u.a.] volume:146 year:2019 pages:531-534 extent:4 |
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Enthalten in CFD modelling of local scour around Tri-USAF in sand with different arrangements under steady current New York, NY [u.a.] volume:146 year:2019 pages:531-534 extent:4 |
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CFD modelling of local scour around Tri-USAF in sand with different arrangements under steady current |
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In such applications of neutron generators, compactness is one of the most important issues. Since a neutron source is generated by deuterium-deuterium (D-D) or deuterium-tritium (D-T) fusion reaction, a relatively thick shield for both fast neutrons and related photons is usually required. In this study, optimization of shielding designs for D-D and D-T neutron generators were investigated by adopting appropriate moderator and shielding materials. Based on the optimized moderator and shield thicknesses, the final dimensions of neutron generators were derived for various source strengths of D-D and D-T neutron conditions. 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An optimization study for shielding design of D-D and D-T neutron generators |
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Neutron generators (NG) are being increasingly used in various industrial and research areas such as neutron activation analysis, neutron radiography, and neutron capture therapy. In such applications of neutron generators, compactness is one of the most important issues. Since a neutron source is generated by deuterium-deuterium (D-D) or deuterium-tritium (D-T) fusion reaction, a relatively thick shield for both fast neutrons and related photons is usually required. In this study, optimization of shielding designs for D-D and D-T neutron generators were investigated by adopting appropriate moderator and shielding materials. Based on the optimized moderator and shield thicknesses, the final dimensions of neutron generators were derived for various source strengths of D-D and D-T neutron conditions. Considering conventional condition of a container, we concluded that a 1010 n/sec D-D source and a 108 n/sec D-T source could be a portable NG. |
| abstractGer |
Neutron generators (NG) are being increasingly used in various industrial and research areas such as neutron activation analysis, neutron radiography, and neutron capture therapy. In such applications of neutron generators, compactness is one of the most important issues. Since a neutron source is generated by deuterium-deuterium (D-D) or deuterium-tritium (D-T) fusion reaction, a relatively thick shield for both fast neutrons and related photons is usually required. In this study, optimization of shielding designs for D-D and D-T neutron generators were investigated by adopting appropriate moderator and shielding materials. Based on the optimized moderator and shield thicknesses, the final dimensions of neutron generators were derived for various source strengths of D-D and D-T neutron conditions. Considering conventional condition of a container, we concluded that a 1010 n/sec D-D source and a 108 n/sec D-T source could be a portable NG. |
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Neutron generators (NG) are being increasingly used in various industrial and research areas such as neutron activation analysis, neutron radiography, and neutron capture therapy. In such applications of neutron generators, compactness is one of the most important issues. Since a neutron source is generated by deuterium-deuterium (D-D) or deuterium-tritium (D-T) fusion reaction, a relatively thick shield for both fast neutrons and related photons is usually required. In this study, optimization of shielding designs for D-D and D-T neutron generators were investigated by adopting appropriate moderator and shielding materials. Based on the optimized moderator and shield thicknesses, the final dimensions of neutron generators were derived for various source strengths of D-D and D-T neutron conditions. Considering conventional condition of a container, we concluded that a 1010 n/sec D-D source and a 108 n/sec D-T source could be a portable NG. |
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