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

Beryllium erosion and redeposition in ITER H, He and D–T discharges

J. Romazanov, A. Kirschner, S. Brezinsek, R.A. Pitts, D. Borodin, S. Rode, M.X. Navarro, K. Schmid, E. Veshchev, V.S. Neverov2022年被引用 14Nuclear FusionIF 3出版社

The Monte-Carlo code ERO2.0 was used to simulate steady-state erosion and transport of beryllium (Be) in the ITER main chamber. Various plasma scenarios were tested, including a variation of the main species (hydrogen, deuterium, helium), plasma conditions (density, temperature, flow velocity) and magnetic configurations. The study provides valuable predictions for the Be transport to the divertor, where it is expected to be an important contributor to dust formation and fuel retention due to build-up of co-deposited layers. The Be gross and net erosion rates provided by this study can help identifying first wall regions with potentially critical armour lifetime.

日本語訳

モンテカルロコードERO2.0を用いて、ITER主容器内におけるベリリウム(Be)の定常状態での損耗と輸送をシミュレーションした。主成分種(水素、重水素、ヘリウム)、プラズマ条件(密度、温度、流れ速度)、および磁場配位の変化を含む、様々なプラズマシナリオを試験した。本研究は、ダイバータへのBe輸送に関する貴重な予測を提供するものであり、そこでは共堆積層の形成によるダスト生成と燃料保持への重要な寄与因子となることが予想される。本研究によって提供されるBeのグロスおよびネット損耗率は、アーマー寿命が臨界的に短くなる可能性のある第一壁領域の特定に役立ち得る。

装置

iter高精度(タイトル一致)

wiki

ITERBeryllium
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

Sputtering erosion of beryllium coated plasma facing components—general considerations and analysis for ITER detached plasma regime

1997Fusion Engineering and Design

Influence of beryllium plasma impurities on the erosion of graphite

2004Nuclear Fusion

Impact of divertor configuration on recycling neutral fluxes for ITER-like wall in JET H-mode plasmas

2020Plasma Physics and Controlled Fusion

Measuring the difference between gross and net erosion

2012Nuclear Fusion

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

1998Fusion Engineering and Design

Effect of beryllium on plasma performance in JET

1990Plasma Physics and Controlled Fusion

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

2006Nuclear Fusion

Material migration studies with an ITER first wall panel proxy on EAST

2015Nuclear Fusion

Gross and net erosion balance of plasma-facing materials in full-W tokamaks

2021Nuclear Fusion