FusionPapers
図版検索トレンドwiki日本の研究
© 2026 FUSIONPAPERS
About法務情報
トップに戻る

Design of separated first wall for fusion experimental reactor

K Koizumi, M Shibui, M Nakahira, H Takatsu, T Tsunematsu1995年Fusion Engineering and DesignIF 1.7出版社

AbstractDesign studies and R&D activities on the separate first wall for tokamak fusion experimental reactors have been progressed at JAERI. The first wall has a high probability of unexpected damage because of the uncertainties in local heat and particle loads and it requires easy replacement in case of failure. In order to satisfy the requirement of assembly and maintenance, the first wall mechanically separated and separately cooled from a massive blanket module has been proposed as a promising concept with a number of advantageous features, such as easy handling during assembly/disassembly due to light weight ( ∼350 kg), short down-time for maintenance operation, minimized amount of radwaste and so on. A fail-safe structure, which is consistent with in-service-inspection requirements, has been realized by employing a reliable double-walled thin shell structure sandwiching metal mesh. A quilting structure of austenitic stainless steel (SS316) cooled by low pressure (2 MPa), low temperature (100–150°C) water is employed to accommodate high surface heat flux of more than 0.3 MW m−2 and nuclear heating together with large electromagnetic loads up to 2 MPa. This paper describes the outlines of the structural design of the separated first wall, cooling and manifolds, mechanical connection to blanket structure, fabrication procedure, results of thermo-mechanical analyses and related R&D activities performed at JAERI.

日本語訳

抄録 トカマク核融合実験炉用の分離型第一壁に関する設計研究およびR&D活動は、JAERIにおいて進められてきた。第一壁は、局所的な熱負荷および粒子負荷に関する不確実性のため、予期せぬ損傷を受ける可能性が高く、故障時には容易な交換が要求される。組立および保守の要件を満たすため、大型ブランケットモジュールから機械的に分離され、独立して冷却される第一壁が有望な概念として提案されてきた。この概念は、軽量(約350 kg)による組立・分解時の取り扱い容易性、保守作業の短縮化、放射性廃棄物量の最小化など、数多くの有利な特徴を有する。供用期間中検査の要件に適合するフェイルセーフ構造は、金属メッシュを挟持した信頼性の高い二重壁薄肉シェル構造を採用することにより実現された。オーステナイト系ステンレス鋼(SS316)製のキルティング構造は、低圧(2 MPa)、低温(100〜150°C)の水で冷却され、0.3 MW m−2を超える高い表面熱流束および核発熱と、最大2 MPaの大きな電磁力を収容するために採用されている。本論文は、分離型第一壁の構造設計、冷却およびマニホールド、ブランケット構造への機械的接続、製作手順、熱機械解析の結果、ならびにJAERIにおいて実施された関連R&D活動の概要について述べるものである。

wiki

First wall
この論文にはまだAI要約がありません。

関連論文

Thermal-mechanical analyses of the ITER shielding blanket designs

1995Fusion Engineering and Design

Thermal-hydraulic and structural design for the lithium-cooled TITAN-I reversed-feeld-pinch reactor

1989Fusion Engineering and Design

Structural design criteria for high heat flux components

2000Fusion Engineering and Design

A helium-cooled blanket design of the low aspect ratio reactor

2000Fusion Engineering and Design

Development of advanced high heat flux and plasma-facing materials

2017Nuclear Fusion

Thermal-hydraulic and structural design of the TITAN-I reversed-field-pinch fusion power core

1993Fusion Engineering and Design

ITER blanket designs

1995Fusion Engineering and Design

Design and technology development of solid breeder blanket cooled by supercritical water in Japan

2003Nuclear Fusion

EVOLVE—an advanced first wall/blanket system

2000Fusion Engineering and Design

Research and development of liquid metal systems for a tokamak reactor

1989Fusion Engineering and Design