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 window for shield thermal energy storage for pulsed tokamak fusion reactors

Mohammad Z. Hasan, Masanori Monde, Yuichi Mitsutake, M.A. Islam1998年Fusion Engineering and DesignIF 1.7出版社

AbstractNumerical parametric analysis has been carried out to find design window for shield thermal energy storage for pulsed tokamak fusion reactors. A fast, quasi-2-dimensional computer code has been developed for the parametric study. The parameters are coolant tube diameter, cell thickness, shield height, amount of energy stored above the coolant inlet temperature, maximum shield temperature, and coolant exit temperature. Ensuring the basic requirement of the withdrawal of the rated reactor power at the coolant exit temperature during the downtime, the design is optimized by minimizing the shield volume and pumping power for coolant circulation. A single design window is not possible because of the many parameters influencing the design. The effects of the design parameters are discussed and design windows for a PULSAR-I-like pulsed tokamak fusion reactor are presented and discussed.

日本語訳

パルス運転トカマク核融合炉の遮蔽体熱エネルギー貯蔵の設計ウィンドウを見出すために、数値パラメトリック解析を実施した。パラメトリック研究のための高速準2次元コンピュータコードを開発した。パラメータは、冷却管直径、セル厚さ、遮蔽体高さ、冷却材入口温度以上の蓄積エネルギー量、最大遮蔽体温度、および冷却材出口温度である。ダウンタイム中の定格原子炉出力の冷却材出口温度での取出しという基本要件を確保しつつ、遮蔽体体積と冷却材循環ポンプ動力を最小化することにより設計を最適化した。多数のパラメータが影響を及ぼすため、単一の設計ウィンドウは存在しない。設計パラメータの影響について考察し、PULSAR-I類似パルス運転トカマク核融合炉の設計ウィンドウを示し、議論した。

この論文にはまだAI要約がありません。

関連論文

Using the shield for thermal energy storage in pulsar

1995Fusion Engineering and Design

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

1993Fusion Engineering and Design

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

2000Fusion Engineering and Design

Thermal analysis of a tokamak divertor plate after a sudden coolant dry-out

1990Fusion Engineering and Design

Configuration and engineering design of the ARIES-RS tokamak power plant

1997Fusion Engineering and Design

Thermal hydraulic assessment on the full banana model of COOL blanket for CFETR

2024Nuclear Fusion

Synchronized fusion development considering physics, materials and heat transfer

2017Nuclear Fusion

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

1989Fusion Engineering and Design

Nuclear design and assessments of helical-axis advanced stellarator with dual-coolant lithium-lead breeding blanket: adaptation from DEMO tokamak reactor

2021Nuclear Fusion

Temperature transients in reference tokamak reactors following loss of coolant

1991Fusion Engineering and Design