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

Analysis of thermal-hydraulic transients of the water-cooled eutectic LiPb blanket of NET

H.Th. Klippel1988年Fusion Engineering and DesignIF 1.7出版社

For the liquid LiPb blanket concept of NET the response of the first wall and the water-cooled blanket to coolant tube blockage, loss of pumping power and loss of heat sink events has been evaluated. Thermal-hydraulic calculations were carried out with the code RELAP followed by two-dimensional transient non-linear heat transfer calculations with the code MARC. The main conclusion is that the concept of two parallel coolant loops provides a good safety measure since a flow coastdown in one coolant loop with the plasma is still burning does not lead to any significant temperature increase of the structures. Also passive shut-down cooling by natural convection flow or by thermal radiation is sufficiently adequate to remove the decay heat in first wall and blanket.

日本語訳

液体LiPbブランケット概念について、冷却管閉塞、ポンプ動力喪失、および熱シンク喪失事象に対する第一壁と水冷ブランケットの応答を評価した。熱流動計算はコードRELAPを用いて実施し、続いてコードMARCによる二次元過渡非線形伝熱計算を行った。主な結論として、二重並列冷却ループの概念は優れた安全対策を提供し、プラズマが依然として燃焼している状態で一方のループの流量が減衰しても、構造物の有意な温度上昇は生じない。さらに、自然対流による受動的な崩壊熱除去、または熱放射のみによっても、第一壁およびブランケットの崩壊熱を十分に除去できることが示された。

wiki

Lead-lithium eutecticThermal-hydraulicsNext European Torus
この論文にはまだAI要約がありません。

関連論文

Thermal hydraulic analysis of water cooled blanket under transient condition

2018Fusion Engineering and Design

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

2024Nuclear Fusion

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

1989Fusion Engineering and Design

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

1993Fusion Engineering and Design

The flow instability phenomenon in the loss of coolant accident of the water cooled blanket

2020Fusion Engineering and Design

Thermal hydraulic analysis on the heat transfer enhancement of the COOL blanket first wall for CFETR

2025Fusion Engineering and Design

Decay heat removal in the ITER outline design

1996Fusion Engineering and Design

Thermal-hydraulic design of water-cooled pressure tube blanket for a fusion driven subcritical reactor

2013Fusion Engineering and Design

Analyses of temperature transients in ITER design concepts following hypothetical loss of cooling accidents

2001Fusion Engineering and Design

A self-cooled liquid metal blanket for a tokamak reactor

1992Fusion Engineering and Design