Item type |
学術雑誌論文 / Journal Article(1) |
公開日 |
2024-07-16 |
タイトル |
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言語 |
en |
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タイトル |
Baseline design of laser fusion research reactor with MW class laser facility |
言語 |
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言語 |
eng |
キーワード |
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言語 |
en |
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主題Scheme |
Other |
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主題 |
laser fusion |
キーワード |
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言語 |
en |
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主題Scheme |
Other |
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主題 |
research reactor |
キーワード |
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言語 |
en |
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主題Scheme |
Other |
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主題 |
baseline design |
キーワード |
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言語 |
en |
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主題Scheme |
Other |
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主題 |
replaceable core |
キーワード |
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言語 |
en |
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主題Scheme |
Other |
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主題 |
EDS |
キーワード |
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言語 |
en |
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主題Scheme |
Other |
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主題 |
neutron shielding |
キーワード |
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言語 |
en |
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主題Scheme |
Other |
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主題 |
J-EPoCH |
資源タイプ |
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資源タイプ識別子 |
http://purl.org/coar/resource_type/c_6501 |
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資源タイプ |
journal article |
著者 |
IWAMOTO, Akifumi
TANAKA, Masahiro
SHIGEMORI, Keisuke
KODAMA, Ryosuke
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抄録 |
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内容記述タイプ |
Abstract |
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内容記述 |
We propose a sub-ignition/burning reactor which is named the Laser-fusion Subcritical Power Reactor Engineering Method (L-Supreme). The reliabilities of L-Supreme in a MW class laser facility are assessed with respect to the following points: a reactor core, a target chamber, a target delivery system, an Exhaust Detritiation System (EDS), and neutron shielding. The Japan Establishment for Power-laser Community Harvest (J-EPoCH) would be applied as a MW class laser facility. A non-cryogenic glass balloon target filled with gaseous deuterium-tritium (DT) is contained in a target capsule. A chain-type magazine system might be used for a mass supply of the target capsules. Each target capsule is delivered to the center of a reactor core at 1 Hz. A batch of 10 000 laser shots would realize 0.22 MJ fusion power. The amount of tritium per batch is 1.51 × 1012 Bq. During laser experiments, unburned tritium is evacuated and transferred into an Exhaust Detritiation System (EDS). An evacuation rate of more than 0.1 m3 s−1 is required in order to recover less than 5000 Bq m−3 of the threshold of tritium concentration within 1 h. For safety, emergency situations such as tritium leakage in facilities are examined. The EDS works by internal circulation processes. Assuming leakage of tritium for a batch, an air circulation flow rate of 4100 Nm3 h−1 is required in an experimental hall for recovering less than 5000 Bq m−3 within 48 h. A primary and secondary neutron shield concept are proposed and would provide full neutron shielding. We conclude that it is possible to construct the L-Supreme system by marshalling current technologies. |
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言語 |
en |
書誌情報 |
en : Nuclear Fusion
巻 64,
号 8,
p. 086068,
発行日 2024-07-15
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出版者 |
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言語 |
en |
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出版者 |
IOP Publishing |
ISSN |
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収録物識別子タイプ |
ISSN |
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収録物識別子 |
1741-4326 |
DOI |
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関連タイプ |
isIdenticalTo |
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識別子タイプ |
DOI |
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関連識別子 |
10.1088/1741-4326/ad573d |
権利 |
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言語 |
en |
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権利情報 |
© 2024 The Author(s). 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. |
情報源 |
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言語 |
en |
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関連名称 |
Akifumi Iwamoto et al 2024 Nucl. Fusion 64 086068 |
関連サイト |
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識別子タイプ |
DOI |
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関連識別子 |
http://doi.org/10.1088/1741-4326/ad573d |
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関連名称 |
Publisher version |
著者版フラグ |
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出版タイプ |
VoR |
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出版タイプResource |
http://purl.org/coar/version/c_970fb48d4fbd8a85 |
NAIS |
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13975 |