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Estimation of Neutron Duct Streaming with the feeder for the Power Supply System in the Tokamak Fusion Device Facility

https://repo.qst.go.jp/records/72385
https://repo.qst.go.jp/records/72385
58287e4b-1305-4b4a-a51d-065a8347d512
Item type 会議発表用資料 / Presentation(1)
公開日 2017-07-19
タイトル
タイトル Estimation of Neutron Duct Streaming with the feeder for the Power Supply System in the Tokamak Fusion Device Facility
言語
言語 eng
資源タイプ
資源タイプ識別子 http://purl.org/coar/resource_type/c_c94f
資源タイプ conference object
アクセス権
アクセス権 metadata only access
アクセス権URI http://purl.org/coar/access_right/c_14cb
著者 助川篤彦

× 助川篤彦

WEKO 712973

助川篤彦

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奥野功一

× 奥野功一

WEKO 712974

奥野功一

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助川 篤彦

× 助川 篤彦

WEKO 712975

en 助川 篤彦

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抄録
内容記述タイプ Abstract
内容記述 The estimation of neutron duct streaming with a feeder for the power supply system in a Tokamak fusion device facility has been performed via neutoronics analysis using a simplified formula for the cylindrical duct streaming model and a suitable model based on the Monte Carlo technique. However, the safety margin is too large for the evaluation using a simplified formula in order to evaluate the neutron streaming of a duct with three feeders (each feeder of size 0.126 m × 0.357 m × 2 m) inside a cylindrical duct (0.8 × 2 m in size). Further, a detailed evaluation of neutron streaming of a cylindrical duct with three feeders has not been performed in the facility. In the present study, three-dimensional (3D) neutronics analysis using a real-model of the complex structured duct was performed to assess the safety margin of the simplified formula. It was confirmed that the neutron dose attenuation of the penetrating section in the duct using the simplified formula is approximately one order of magnitude larger than the real-model using the 3D calculation code.
会議概要(会議名, 開催地, 会期, 主催者等)
内容記述タイプ Other
内容記述 The Ninth International Symposium On Radiation Safety and Detection Technology (ISORD-9)
発表年月日
日付 2017-07-12
日付タイプ Issued
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