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

Tritium barrier development for austenitic stainless steel by its aluminizing in a lithium melt

B.A Kalin, V.L Yakushin, E.P Fomina1998年Fusion Engineering and DesignIF 1.7出版社

AbstractA technique for obtaining coatings on a 0.12%C/18%Cr/10%Ni/Ti austenitic stainless steel by its aluminizing in melts of the following composition x%Al+(100%−x)%Li(x=3, 10) at the temperature range 870–1070 K for 5–100 h has been developed. An investigation in to the decrease in the tritium penetration through the steel has been carried out. It has been shown that two-side aluminizing of the steel in the 10%Al/90%Li melt at 870 and 970 K for 5 h decreases its tritium permeability by more than three orders of magnitude. Furthermore, aluminizing the steel under these regimes reduces its erosion coefficient by one order of magnitude on average due to radiation blistering, decreases its coefficient of physical sputtering by more than 2.5 times and protects the steel from failure under the action of hydrogen pulsed plasma fluxes with the incident flux specific power up to 4–5·1010 W m−2 and a pulse duration of 10–50 μs. The mechanisms of decreasing the tritium permeation with regard to the surface relief forming under the treatment have been discussed.

日本語訳

0.12%C/18%Cr/10%Ni/Tiオーステナイト系ステンレス鋼上に、x%Al+(100−x)%Li(x=10、3)組成の溶融金属中で870〜1070 Kの温度範囲において5〜100時間のアルミナイジング処理によりコーティングを形成する手法が開発された。当該鋼材を通じたトリチウム透過の低減について調査が行われた。870 Kおよび970 Kにおいて5時間、10%Al/90%Li溶融金属中での両面アルミナイジング処理により、トリチウム透過率が3桁以上低減することが示された。さらに、これらの条件下でのアルミナイジング処理は、放射線ブリスターリングによる侵食係数を平均で1桁低減し、物理スパッタリング係数を2.5倍以上低減し、入射フラックス比出力が4〜5・10¹⁰ W m⁻²、パルス持続時間が10〜50 μsの水素パルスプラズマフラックス作用下での鋼材の破壊を防ぐことが明らかとなった。処理中に形成される表面形状を考慮したトリチウム透過低減のメカニズムについて考察が行われた。

wiki

TritiumLithiumStainless steel
この論文にはまだAI要約がありません。

関連論文

Efficient hydrogen and deuterium permeation reduction in Al2O3 coatings with enhanced radiation tolerance and corrosion resistance

2018Nuclear Fusion

In-situ oxidation of aluminized stainless-steel to form alumina as tritium permeation barrier coating

2021Fusion Engineering and Design

A high performance and dense Fe–Al/Al2O3 tritium permeation barrier coating prepared on 316LSS at low temperature

2025Nuclear Fusion

Development of a direct insulation layer for a self-cooled liquid metal fusion reactor blanket

1995Fusion Engineering and Design

Preparing Al2O3/TiO2 nano-multilayers on the surface of FeAl/Al2O3 coating as tritium permeation barrier

2025Nuclear Fusion

An effect of gamma-neutron irradiation and oxygen admixtures on interaction of hydrogen with austenitic 18Cr–10Ni–Ti steel

1998Fusion Engineering and Design

IN-situ tritium release experiments from solid breeding materials (TTTEx) — tritium diffusion coefficients and surface reaction on lithium aluminate

1989Fusion Engineering and Design

Scale structure of aluminised F82H-mod. steel after HIP treatment

2000Fusion Engineering and Design

Performance of liquid-lithium-filled 3D-printed tungsten divertor targets under deuterium loading with ELM-like pulses in Magnum-PSI

2021Nuclear Fusion

Mass transfer coefficient of tritium from molten lithium-lead alloy (Li17Pb83) to environmental gas under neutron irradiation

1991Fusion Engineering and Design