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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ftdoajarticles:oai:doaj.org/article:6fb5f4b80231485aac90e7540abf68d4 2023-09-26T15:15:36+02:00 Evaluation of neutron attenuation properties using helium-4 scintillation detector for dry cask inspection Jihun Moon Jisu Kim Heejun Chung Sung-Woo Kwak Kyung Taek Lim 2023-09-01T00:00:00Z https://doi.org/10.1016/j.net.2023.06.039 https://doaj.org/article/6fb5f4b80231485aac90e7540abf68d4 EN eng Elsevier http://www.sciencedirect.com/science/article/pii/S1738573323003030 https://doaj.org/toc/1738-5733 1738-5733 doi:10.1016/j.net.2023.06.039 https://doaj.org/article/6fb5f4b80231485aac90e7540abf68d4 Nuclear Engineering and Technology, Vol 55, Iss 9, Pp 3506-3513 (2023) S670e Helium-4 detector dry cask Neutron shielding Neutron detection Nuclear engineering. Atomic power TK9001-9401 article 2023 ftdoajarticles https://doi.org/10.1016/j.net.2023.06.039 2023-08-27T00:36:35Z 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. Article in Journal/Newspaper Arktis Arktis* Directory of Open Access Journals: DOAJ Articles Nuclear Engineering and Technology 55 9 3506 3513 |
institution |
Open Polar |
collection |
Directory of Open Access Journals: DOAJ Articles |
op_collection_id |
ftdoajarticles |
language |
English |
topic |
S670e Helium-4 detector dry cask Neutron shielding Neutron detection Nuclear engineering. Atomic power TK9001-9401 |
spellingShingle |
S670e Helium-4 detector dry cask Neutron shielding Neutron detection Nuclear engineering. Atomic power TK9001-9401 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 |
topic_facet |
S670e Helium-4 detector dry cask Neutron shielding Neutron detection Nuclear engineering. Atomic power TK9001-9401 |
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. |
format |
Article in Journal/Newspaper |
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 |
title |
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_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_sort |
evaluation of neutron attenuation properties using helium-4 scintillation detector for dry cask inspection |
publisher |
Elsevier |
publishDate |
2023 |
url |
https://doi.org/10.1016/j.net.2023.06.039 https://doaj.org/article/6fb5f4b80231485aac90e7540abf68d4 |
genre |
Arktis Arktis* |
genre_facet |
Arktis Arktis* |
op_source |
Nuclear Engineering and Technology, Vol 55, Iss 9, Pp 3506-3513 (2023) |
op_relation |
http://www.sciencedirect.com/science/article/pii/S1738573323003030 https://doaj.org/toc/1738-5733 1738-5733 doi:10.1016/j.net.2023.06.039 https://doaj.org/article/6fb5f4b80231485aac90e7540abf68d4 |
op_doi |
https://doi.org/10.1016/j.net.2023.06.039 |
container_title |
Nuclear Engineering and Technology |
container_volume |
55 |
container_issue |
9 |
container_start_page |
3506 |
op_container_end_page |
3513 |
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1778136572203368448 |