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

Measuring the difference between gross and net erosion

R.P. Doerner, D. Nishijima, T. Schwarz-Selinger2012年被引用 13Nuclear FusionIF 3出版社

A series of systematic experimental investigations are reported, using a beryllium-containing oven to seed a controlled and adjustable amount of impurities into a steady-state plasma. Beryllium impurity seeding of the plasma is used to simulate redeposition of eroded material to investigate the relationship between gross and net erosion. The measured net erosion rates from beryllium targets do not change when the influx of beryllium ions is increased unless the Be-seeding rate exceeds, by an order of magnitude, the beryllium surface loss rate, which was determined without beryllium seeding of the plasma. Measurements of the penetration distance of eroding beryllium atoms axially into the plasma column reveal that the reflection coefficient of the incident beryllium ions is unchanged, but the sputtering yield of the plasma-deposited surface beryllium is increased with respect to the bulk beryllium material by a factor of ∼10.

日本語訳

一連の系統的な実験的調査について報告する。この調査では、ベリリウムを含むオーブンを用いて、定常状態プラズマ中に制御された量の不純物を導入した。ベリリウム不純物のシーディングは、侵食された材料の再堆積を模擬するために用いられ、総侵食量と正味侵食量の関係を調べた。ベリリウムターゲットから測定された正味侵食速度は、ベリリウムイオンの流入量を増加させても変化しなかった。ただし、そのシーディング速度が、ベリリウムシーディングなしで決定されたベリリウム表面の損失速度を一桁上回る場合を除く。プラズマ中を軸方向に侵食されたベリリウム原子の到達距離の測定により、入射ベリリウムイオンの反射係数は変化しないが、プラズマ堆積表面からのベリリウムのスパッタリング収率は、バルクのベリリウム材料と比較して約10倍増加することが明らかになった。

wiki

Next European Torus
この論文にはまだAI要約がありません。

関連論文

Beryllium as the plasma-facing material in fusion energy systems—experiments, evaluation, and comparison with alternative materials

1997Fusion Engineering and Design

Studies of tritium desorption from beryllium and characterization of erosion products under plasma–beryllium interaction

1998Fusion Engineering and Design

A time resolved study of the mitigation of graphite chemical erosion in deuterium plasmas containing beryllium

2006Nuclear Fusion

Effect of beryllium on plasma performance in JET

1990Plasma Physics and Controlled Fusion

Oxidation of beryllium—a scanning Auger investigation

2005Nuclear Fusion

Distribution of beryllium concentrations and fluxes in the Tokamak UNITOR

1988Plasma Physics and Controlled Fusion

Novel plasma source for safe beryllium spectral line studies in the presence of beryllium dust

2018Review of Scientific Instruments

Beryllium plasma-facing components: JET experience

1997Fusion Engineering and Design

Chemical reactivity and mobilization of beryllium exposed to steam

1997Fusion Engineering and Design

The effect of neutron irradiation on beryllium performance

2000Fusion Engineering and Design