Evaluation of neutron attenuation properties using helium-4 scintillation detector for dry cask inspection
In this paper, we demonstrate the neutron attenuation of dry cask shielding materials using the S670e helium-4 detector manufactured by Arktis Radiation Ltd. In particular, two materials expected to be applied to the TN-32 dry cask manufactured by ORANO Korea and KORAD-21 by the Korea Radioactive Wa...
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| Format: | Article |
| Language: | English |
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Elsevier
2023-09-01
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| Series: | Nuclear Engineering and Technology |
| Subjects: | |
| Online Access: | http://www.sciencedirect.com/science/article/pii/S1738573323003030 |
| _version_ | 1797737354536943616 |
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| author | Jihun Moon Jisu Kim Heejun Chung Sung-Woo Kwak Kyung Taek Lim |
| author_facet | Jihun Moon Jisu Kim Heejun Chung Sung-Woo Kwak Kyung Taek Lim |
| author_sort | Jihun Moon |
| collection | DOAJ |
| description | In this paper, we demonstrate the neutron attenuation of dry cask shielding materials using the S670e helium-4 detector manufactured by Arktis Radiation Ltd. In particular, two materials expected to be applied to the TN-32 dry cask manufactured by ORANO Korea and KORAD-21 by the Korea Radioactive Waste Agency (KORAD) were utilized. The measured neutron attenuation was compared with our Monte Carlo N-Particle Transport simulation results, and the difference is given as the root mean square (RMS). For the fast neutron case, a rapid decline in neutron counts was observed as a function of increasing material thickness, exhibiting an exponential relationship. The discrepancy between the experimentally acquired data and simulation results for the fast neutron was maintained within a 2.3% RMS. In contrast, the observed thermal neutron count demonstrated an initial rise, attained a maximum value, and exhibited an exponential decline as a function of increasing thickness. In particular, the discrepancy between the measured and simulated peak locations for thermal neutrons displayed an RMS deviation of approximately 17.3–22.4%. Finally, the results suggest that a minimum thickness of 5 cm for Li-6 is necessary to achieve a sufficiently significant cross-section, effectively capturing incoming thermal neutrons within the dry cask. |
| first_indexed | 2024-03-12T13:27:28Z |
| format | Article |
| id | doaj.art-6fb5f4b80231485aac90e7540abf68d4 |
| institution | Directory Open Access Journal |
| issn | 1738-5733 |
| language | English |
| last_indexed | 2024-03-12T13:27:28Z |
| publishDate | 2023-09-01 |
| publisher | Elsevier |
| record_format | Article |
| series | Nuclear Engineering and Technology |
| spelling | doaj.art-6fb5f4b80231485aac90e7540abf68d42023-08-25T04:24:07ZengElsevierNuclear Engineering and Technology1738-57332023-09-0155935063513Evaluation of neutron attenuation properties using helium-4 scintillation detector for dry cask inspectionJihun Moon0Jisu Kim1Heejun Chung2Sung-Woo Kwak3Kyung Taek Lim4The Nuclear Safety and Security Commission, Seoul, Republic of KoreaKorea Institute of Nuclear Non-proliferation and Control, Daejeon, Republic of KoreaKorea Institute of Nuclear Non-proliferation and Control, Daejeon, Republic of KoreaKorea Institute of Nuclear Non-proliferation and Control, Daejeon, Republic of KoreaQuantum and Nuclear Engineering, Sejong University, Seoul, Republic of Korea; Corresponding author. Quantum and Nuclear Engineering, Sejong University, 209 Neungdong-ro, Gwangjin-gu, Seoul, 05006, Republic of Korea.In this paper, we demonstrate the neutron attenuation of dry cask shielding materials using the S670e helium-4 detector manufactured by Arktis Radiation Ltd. In particular, two materials expected to be applied to the TN-32 dry cask manufactured by ORANO Korea and KORAD-21 by the Korea Radioactive Waste Agency (KORAD) were utilized. The measured neutron attenuation was compared with our Monte Carlo N-Particle Transport simulation results, and the difference is given as the root mean square (RMS). For the fast neutron case, a rapid decline in neutron counts was observed as a function of increasing material thickness, exhibiting an exponential relationship. The discrepancy between the experimentally acquired data and simulation results for the fast neutron was maintained within a 2.3% RMS. In contrast, the observed thermal neutron count demonstrated an initial rise, attained a maximum value, and exhibited an exponential decline as a function of increasing thickness. In particular, the discrepancy between the measured and simulated peak locations for thermal neutrons displayed an RMS deviation of approximately 17.3–22.4%. Finally, the results suggest that a minimum thickness of 5 cm for Li-6 is necessary to achieve a sufficiently significant cross-section, effectively capturing incoming thermal neutrons within the dry cask.http://www.sciencedirect.com/science/article/pii/S1738573323003030S670eHelium-4 detectordry caskNeutron shieldingNeutron detection |
| spellingShingle | Jihun Moon Jisu Kim Heejun Chung Sung-Woo Kwak Kyung Taek Lim Evaluation of neutron attenuation properties using helium-4 scintillation detector for dry cask inspection Nuclear Engineering and Technology S670e Helium-4 detector dry cask Neutron shielding Neutron detection |
| title | Evaluation of neutron attenuation properties using helium-4 scintillation detector for dry cask inspection |
| title_full | Evaluation of neutron attenuation properties using helium-4 scintillation detector for dry cask inspection |
| title_fullStr | Evaluation of neutron attenuation properties using helium-4 scintillation detector for dry cask inspection |
| title_full_unstemmed | Evaluation of neutron attenuation properties using helium-4 scintillation detector for dry cask inspection |
| title_short | Evaluation of neutron attenuation properties using helium-4 scintillation detector for dry cask inspection |
| title_sort | evaluation of neutron attenuation properties using helium 4 scintillation detector for dry cask inspection |
| topic | S670e Helium-4 detector dry cask Neutron shielding Neutron detection |
| url | http://www.sciencedirect.com/science/article/pii/S1738573323003030 |
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