ダウンロード数: 61

このアイテムのファイル:
ファイル 記述 サイズフォーマット 
2057-1976_acc33c.pdf1.98 MBAdobe PDF見る/開く
タイトル: Development and evaluation of dose calculation algorithm with a combination of Monte Carlo and point-kernel methods for boron neutron capture therapy
著者: Nojiri, Mai
Takata, Takushi  kyouindb  KAKEN_id
Hu, Naonori
Sakurai, Yoshinori  kyouindb  KAKEN_id  orcid https://orcid.org/0000-0001-9404-4255 (unconfirmed)
Suzuki, Minoru  kyouindb  KAKEN_id  orcid https://orcid.org/0000-0002-5421-9417 (unconfirmed)
Tanaka, Hiroki  kyouindb  KAKEN_id
著者名の別形: 野尻, 摩依
高田, 卓志
呼, 尚徳
櫻井, 良憲
鈴木, 実
田中, 浩基
キーワード: boron neutron capture therapy
treatment planning
dose calculation algorithm
Monte Carlo method
point-kernel
発行日: May-2023
出版者: IOP Publishing
誌名: Biomedical Physics & Engineering Express
巻: 9
号: 3
論文番号: 035025
抄録: We developed a 'hybrid algorithm' that combines the Monte Carlo (MC) and point-kernel methods for fast dose calculation in boron neutron capture therapy. The objectives of this study were to experimentally verify the hybrid algorithm and to verify the calculation accuracy and time of a 'complementary approach' adopting both the hybrid algorithm and the full-energy MC method. In the latter verification, the results were compared with those obtained using the full-energy MC method alone. In the hybrid algorithm, the moderation process of neutrons is simulated using only the MC method, and the thermalization process is modeled as a kernel. The thermal neutron fluxes calculated using only this algorithm were compared with those measured in a cubic phantom. In addition, a complementary approach was used for dose calculation in a geometry simulating the head region, and its computation time and accuracy were verified. The experimental verification indicated that the thermal neutron fluxes calculated using only the hybrid algorithm reproduced the measured values at depths exceeding a few centimeters, whereas they overestimated those at shallower depths. Compared with the calculation using only the full-energy MC method, the complementary approach reduced the computation time by approximately half, maintaining nearly same accuracy. When focusing on the calculation only using the hybrid algorithm only for the boron dose attributed to the reaction of thermal neutrons, the computation time was expected to reduce by 95% compared with the calculation using only the full-energy MC method. In conclusion, modeling the thermalization process as a kernel was effective for reducing the computation time.
著作権等: © 2023 The Author(s). Published by IOP Publishing Ltd
Original content from this work may be used under the terms of the Creative Commons Attribution 4.0 licence. Any further distribution of this work must maintain attribution to the author(s) and the title of the work, journal citation and DOI.
URI: http://hdl.handle.net/2433/283978
DOI(出版社版): 10.1088/2057-1976/acc33c
PubMed ID: 37021631
出現コレクション:学術雑誌掲載論文等

アイテムの詳細レコードを表示する

Export to RefWorks


出力フォーマット 


このアイテムは次のライセンスが設定されています: クリエイティブ・コモンズ・ライセンス Creative Commons