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Investigation of Mo-99 Radioisotope Production by d-Li Neutron Source

https://repo.qst.go.jp/records/72526
https://repo.qst.go.jp/records/72526
f054b491-07df-4005-adf6-3c6d22a75f87
Item type 会議発表用資料 / Presentation(1)
公開日 2017-11-14
タイトル
タイトル Investigation of Mo-99 Radioisotope Production by d-Li Neutron Source
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 太田, 雅之

× 太田, 雅之

WEKO 714269

太田, 雅之

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権, セロム

× 権, セロム

WEKO 714270

権, セロム

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佐藤, 聡

× 佐藤, 聡

WEKO 714271

佐藤, 聡

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落合, 謙太郎

× 落合, 謙太郎

WEKO 714272

落合, 謙太郎

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鈴木, 寛光

× 鈴木, 寛光

WEKO 714273

鈴木, 寛光

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太田 雅之

× 太田 雅之

WEKO 714274

en 太田 雅之

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権 セロム

× 権 セロム

WEKO 714275

en 権 セロム

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佐藤 聡

× 佐藤 聡

WEKO 714276

en 佐藤 聡

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落合 謙太郎

× 落合 謙太郎

WEKO 714277

en 落合 謙太郎

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鈴木 寛光

× 鈴木 寛光

WEKO 714278

en 鈴木 寛光

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抄録
内容記述タイプ Abstract
内容記述 An advanced fusion neutron source (A-FNS) is under planning at Rokkasyo in Japan. The A-FNS has an accelerator providing a 40 MeV deuteron beam of 125 mA and the Li target. It produces a large amount of neutrons due to Li(d,n) reaction, and has the neutron flux of about 6*10^14 n/cm^2/s at the back plate of the Li target with a broad energy peak around 14 MeV. The main purpose of the A-FNS is the fusion material irradiation. In addition, we propose a production of radioisotopes for medical application. We examine a production of Mo-99. It is the parent nucleus of Tc-99m, which is the used in the nuclear medicine diagnosis. The Mo-99 used in Japan are supplied only from nuclear reactors in foreign countries. The domestic production of Mo-99 is required because of the avoidance of the risk of the supply disruption. A new production method has been proposed for Mo-99, and it applies the Mo-100(n,2n)Mo-99 reaction with accelerator. We have estimated that the A-FNS has an enough potential to produce Mo-99 over its demand in Japan from the Mo-100(n,2n)Mo-99 reaction. In addition, we show the usefulness of the Mo-98(n,g)Mo-99 reaction by the usage of the natural molybdenum from the viewpoint of economic efficiency. In this study, we conduct the conceptual design study of the radioisotope production module at A-FNS which has spectrum shifters and neutron reflectors composed of graphite and beryllium through analyses of the production of Mo-99. The spectrum shifter moderates fast neutrons to lower energy neutrons. It increases the production of Mo-99 due to the Mo-98(n,g)Mo-99 reaction, while it decreases that due to the Mo-100(n,2n)Mo-99 reaction. The neutron reflector increases both of fast and low energy neutrons at the samples. We design the spectrum shifters and reflectors in order to achieve the maximum of the amount of the production of Mo-99. We apply the Monte Carlo transport code MCNP5 and D-Li neutron source code McDeLicious-11 in the calculation. We establish the conceptual design of the radioisotope production module. We compare the amount of the production of Mo-99 with this module at A-FNS with the demand in Japan, and show the usefulness of this module.
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 18th International Conference on Fusion Reactor Materials
発表年月日
日付 2017-11-08
日付タイプ Issued
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