2002年
Real-time estimation of neutron flux during BNCT treatment using plastic scintillation detector with optical fiber
RESEARCH AND DEVELOPMENT IN NEUTRON CAPTURE THERAPY
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- 開始ページ
- 443
- 終了ページ
- 447
- 記述言語
- 英語
- 掲載種別
- 研究論文(国際会議プロシーディングス)
- 出版者・発行元
- MEDIMOND S R L
We developed a new thermal neutron fluence detector for Boron Neutron Capture Therapy using plastic optical fiber with plastic scintillator containing Boron-10. The presented detector has quite low sensitivity for gammarays, and we succeeded measuring thermal neutrons accurately.
- リンク情報
- ID情報
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- Web of Science ID : WOS:000178661500077