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

Effect of impurity content in stainless steel on resolidified surface condition after disruption load

Haruki Madarame, Toshio Sukegawa, Hideharu Yanagi, Kenzo Miya, Tadao Ogawa1989年Fusion Engineering and DesignIF 1.7出版社

Plasma disruptions in tokamaks may cause melting of the surface layer of first walls. If the layer resolidifies without any movement, the same layer repeatedly melts and protects the rest of the wall. A number of stainless steel samples were irradiated by a neutral beam injector. After irradiation tests with the same condition, some had wavy resolidification surfaces with dents, while some had smooth surfaces. In the former samples, the amplitude of the roughness increased by repetitive heat loads. The melt layer moved to the convex areas, which deepened the dents on each occasion. Sulphur was found to be one of the harmful elements which promotes the formation of the wavy surface. It is recommended to be kept below 0.005 wt% for obtaining a uniform resolidification surface. Even if samples have a low sulphur content, a high oxygen content also makes the surface rough. Other impurities have some effects, but they have not been clarified yet.

日本語訳

トカマクにおけるプラズマ disruption は、第一壁の表面層の溶融を引き起こす可能性がある。その層が移動することなく再凝固する場合、同じ層が繰り返し溶融し、壁の残りの部分を保護する。複数のステンレス鋼試料が中性粒子ビーム入射装置によって照射された。同一条件での照射試験後、いくつかの試料は窪みを伴う波状の再凝固表面を示し、一方でいくつかの試料は平滑な表面を示した。前者の試料では、繰り返しの熱負荷によって粗さの振幅が増大した。溶融層は凸部へ移動し、その都度窪みを深くした。硫黄は、波状表面の形成を促進する有害元素の一つであることが判明した。均一な再凝固表面を得るためには、硫黄を0.005 wt%未満に保つことが推奨される。試料の硫黄含有量が低い場合でも、高い酸素含有量は表面を粗くする。他の不純物もいくつかの影響を及ぼすが、それらはまだ明らかにされていない。

wiki

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

関連論文

Surface ripple of resolidified stainless steel after disruption load

1991Fusion Engineering and Design

Numerical simulation of surface tension induced melt-layer movement after disruption load

1992Fusion Engineering and Design

Cracks in the resolidification layer of stainless steel formed by simulated plasma disruption

1992Fusion Engineering and Design

Fatigue strength for stainless steel irradiated by high power laser beam

1989Fusion Engineering and Design

Analysis of tungsten melt-layer motion and splashing under tokamak conditions at TEXTOR

2011Nuclear Fusion

Inhibited cavitation in lanthanum-doped tungsten under multiple melt exposures in GLADIS and ASDEX Upgrade

2025Nuclear Fusion

Effect of surface roughness and substrate material on carbon erosion and deposition in the TEXTOR tokamak

2008Plasma Physics and Controlled Fusion

Growth, characterization and adhesion of thick deposited tungsten layers under transient loading in Magnum-PSI

2026Nuclear Fusion

In-vessel surface layer evolution during plasma–wall interaction in the Globus-M spherical tokamak

2009Nuclear Fusion

Experimental and simulation studies on damage mechanisms of tungsten and molybdenum under compressed plasma flow irradiation

2023Nuclear Fusion