A method for delivering the required neutron fluence in an accelerator-based boron neutron capture therapy system employing a lithium target.

Autor: Nakamura, Satoshi^1,2,3 (AUTHOR) satonaka@ncc.go.jp, Takemori, Mihiro^2,4 (AUTHOR), Nakaichi, Tetsu^1,2 (AUTHOR), Shuto, Yasunori^1,5,6 (AUTHOR), Kashihara, Tairo^2,4 (AUTHOR), Iijima, Kotaro¹ (AUTHOR), Chiba, Takahito^1,7 (AUTHOR), Nakayama, Hiroki¹ (AUTHOR), Urago, Yuka^1,7 (AUTHOR), Nishina, Shuka^1,8 (AUTHOR), Kobayashi, Yuta¹ (AUTHOR), Kishida, Hironori¹ (AUTHOR), Imamichi, Shoji^2,9,10 (AUTHOR), Takahashi, Kana⁴ (AUTHOR), Masutani, Mitsuko^2,9,10 (AUTHOR), Okamoto, Hiroyuki¹ (AUTHOR), Nishio, Teiji³ (AUTHOR), Itami, Jun¹¹ (AUTHOR), Igaki, Hiroshi^2,4,5 (AUTHOR)

Publikováno v: Scientific Reports. 5/16/2024, Vol. 14 Issue 1, p1-9. 9p.

A method for delivering the required neutron fluence in an accelerator-based boron neutron capture therapy system employing a lithium target

Autor: Satoshi Nakamura, Mihiro Takemori, Tetsu Nakaichi, Yasunori Shuto, Tairo Kashihara, Kotaro Iijima, Takahito Chiba, Hiroki Nakayama, Yuka Urago, Shuka Nishina, Yuta Kobayashi, Hironori Kishida, Shoji Imamichi, Kana Takahashi, Mitsuko Masutani, Hiroyuki Okamoto, Teiji Nishio, Jun Itami, Hiroshi Igaki

Publikováno v: Scientific Reports, Vol 14, Iss 1, Pp 1-9 (2024)

Abstract Accelerator-based boron neutron capture therapy (BNCT) systems employing a solid-state lithium target indicated the reduction of neutron flux over the lifetime of a target, and its reduction could represent the neutron flux model. This study

Externí odkaz: https://doaj.org/article/a11c89c95e2e4a4884733c87071bb098

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A quantified approach to assessing the effectiveness of nuclear reactor pressure vessel neutron fluence monitoring programs.

Autor: Kulesza, Joel¹ jkulesza@lanl.gov, Fischer, Greg² fischega@westinghouse.com

Publikováno v: EPJ Web of Conferences. 10/20/2024, Vol. 308, p1-8. 8p.

Measurement of reactor thermal neutron fluence of NTD-Ge by activation High-Purity Ge itself

Autor: Zhao, Kangkang, Xue, Mingxuan, Peng, Haiping, Zhang, Yunlong, Zhang, Zhiyong, Xu, Zizong, Wang, Xiaolian

In neutron transmutation doped germanium, the thermal neutron fluence of reactor irradiation is as high as 10$^{18}$~n$\cdot$cm$^{-2}$. For radiological safety reasons, general Co or Au neutron flux monitors cannot be easily used. We have experimenta

Externí odkaz: http://arxiv.org/abs/2302.12982