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

Calculation and classification of the radioactive waste inventory in the structural components of a compact ignition fusion machine

D.G. Cepraga, G. Cambi, S.A.M.M. Siddiqui1995年Fusion Engineering and DesignIF 1.7出版社

AbstractThe radioactive inventory, decay heat and contact dose rate of certain materials (graphite in the first wall, INCONEL 625 in the vacuum vessel and copper in the magnet) of the IGNITOR-ULT fusion machine are evaluated. The xsdrnpm-s code is used to perform the neutron transport fixed source analysis. The anita-2 code, using updated cross-sections and decay data libraries based on EAF-3 and IRDF90 evaluation files, is used for activation calculations. The fusion neutron source has been normalized to a neutron wall load of 2 MW m −2. The results show that, although the first wall graphite proves to be a relatively benign material, INCONEL 625 in the vacuum vessel and copper in the magnet can become highly radioactive and may need long waiting times before they can be transported to deep geological repositories or recycled. The impact of the variation in the composition of INCONEL 625 on the contact dose has been assessed as a function of the cooling time and its implications for the choice of structural materials in fusion plants are discussed.

日本語訳

抄録IGNITOR-ULT核融合装置の特定材料(第一壁の黒鉛、真空容器のINCONEL 625、および磁石の銅)における放射能インベントリ、崩壊熱、および接触線量率を評価した。中性子輸送固定源解析にはxsdrnpm-sコードを用いた。放射化計算には、EAF-3およびIRDF90評価ファイルに基づく更新された断面積および崩壊データライブラリを使用するanita-2コードを用いた。核融合中性子源は、2 MW m⁻²の中性子壁負荷に規格化した。結果は、第一壁の黒鉛が比較的無害な材料である一方、真空容器のINCONEL 625および磁石の銅は高い放射能を帯びる可能性があり、深地層処分施設への輸送または再処理の前に長い冷却時間を要する可能性があることを示している。INCONEL 625の組成変動が接触線量率に及ぼす影響を冷却時間の関数として評価し、核融合炉における構造材料の選択への影響について考察した。

wiki

Ignition
この論文にはまだAI要約がありません。

関連論文

Materials testing facilities and programmes for fission and ion implantation damage

2017Nuclear Fusion

Assessment of radiation damage of the first wall of a fusion neutron source DEMO-FNS with a blanket for the transmutation of minor actinides

2021Nuclear Fusion

An integrated model for materials in a fusion power plant: transmutation, gas production, and helium embrittlement under neutron irradiation

2012Nuclear Fusion

An intense DT neutron source and test conditions for fusion nuclear technology research

1989Fusion Engineering and Design

Assessment of the gas dynamic trap mirror facility as intense neutron source for fusion material test irradiations

2000Fusion Engineering and Design

DONES performance, experimental capabilities and perspectives

2025Nuclear Fusion

Towards a programme of testing and qualification for structural and plasma-facing materials in 'fusion neutron' environments

2017Nuclear Fusion

Nuclear data libraries for IFMIF-DONES neutronic calculations

2022Nuclear Fusion

Conceptual design of a fusion engineering test facility based on mirror confinement (FEF)

1989Fusion Engineering and Design

An investigation of the activation of water by D-T fusion neutrons and some implications for fusion reactor technology

1997Fusion Engineering and Design