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

ITER divertor heat transfer system and loss of vacuum accident sequence analyses overview

G. Cambi, M.T. Porfiri, H. Jahn, D.G. Cepraga, H.-W. Bartels1998年Fusion Engineering and DesignIF 1.7出版社

AbstractThe paper presents the analyses performed by the European Union ITER Home Team for five ITER reference accident sequences: two loss of flow and two loss of coolant accidents on the divertor primary heat transfer system, and one loss of vacuum accident. Tritium and activated materials ground and stack environmental releases have been evaluated for each one of the accident sequences, up to 7 days from the accident start. The ATHENA and the INTRA codes are used for the accident transient thermal–hydraulic analysis and for the containment response to coolant leaks, respectively. The NAUA Mod 5M code has been used to assess the radioactive material transport, deposition and leakage inside and through the containment.

日本語訳

本論文は、欧州連合ITER国内機関チームが実施した、5つのITER参照事故シーケンスに関する解析を提示するものである。すなわち、ダイバータ一次熱輸送系における2つの流量喪失事故、2つの冷却材喪失事故、および1つの真空喪失事故である。各事故シーケンスについて、事故開始から7日間までのトリチウムおよび放射性物質の環境放出量(地表およびスタック経由)が評価された。ATHENAコードは事故時の熱流動過渡解析に、INTRAコードは冷却材漏洩に対する格納容器応答解析に、それぞれ使用された。NAUA Mod 5Mコードは、格納容器内および格納容器を通じた放射性物質の輸送、沈着、漏洩の評価に用いられた。

装置

iter高精度(タイトル一致)

wiki

ITERDivertor
この論文にはまだAI要約がありません。

関連論文

Analysis of loss-of-coolant and loss-of-flow accidents in the divertor cooling system of NET/ITER

1991Fusion Engineering and Design

Thermal hydraulic analysis of in-vessel loss of coolant accident for the EAST lower divertor primary heat transfer system

2024Fusion Engineering and Design

Preliminary examination of accident scenarios for the aqueous salt blanket

1990Fusion Engineering and Design

Influence of the break location in the loss of coolant accident analyses for the ITER divertor cooling loop

2002Fusion Engineering and Design

Afterheat transient in ITER after a total loss of coolant accident

1991Fusion Engineering and Design

Loss of flow accident and loss of heat sink accident analyses of the WCCB primary heat transfer system for CFETR

2019Fusion Engineering and Design

Source terms due to the activated corrosion products in primary cooling loops of ITER

1995Fusion Engineering and Design

ITER reference accidents

1998Fusion Engineering and Design

Liquid-metal-cooled divertor for ARIES

1995Fusion Engineering and Design

Safety assessment for ITER-FEAT tritium systems

2002Fusion Engineering and Design