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

Solid deuterium–tritium surface roughness in a beryllium inertial confinement fusion shell

B.J. Kozioziemski, D.S. Montgomery, J.D. Sater, J.D. Moody, C. Gautier, J.W. Pipes2007年被引用 29Nuclear FusionIF 3出版社

Solid deuterium–tritium (D–T) fuel layers for inertial confinement fusion experiments were formed inside a 2 mm diameter beryllium shell and were characterized using phase-contrast enhanced x-ray imaging. The solid D–T surface roughness is found to be 0.4 µm for modes 7–128 at 1.5 K below the melting temperature. The layer roughness is found to increase with decreasing temperature, in agreement with previous visible light characterization studies. However, phase-contrast enhanced x-ray imaging provides a more robust surface roughness measurement than visible light methods. The new x-ray imaging results demonstrate clearly that the surface roughness decreases with time for solid D–T layers held at 1.5 K below the melting temperature.

日本語訳

慣性核融合実験用の固体重水素–トリチウム(D–T)燃料層を、直径2 mmのベリリウムシェル内に形成し、位相コントラスト強調X線イメージングを用いて特性評価した。固体D–T表面粗さは、融点より1.5 K低い温度で、モード7–128について0.4 µmであることが見出された。層粗さは温度の低下とともに増加することが見出され、これは従来の可視光特性評価研究と一致する。しかし、位相コントラスト強調X線イメージングは、可視光法よりも堅牢な表面粗さ測定を提供する。新しいX線イメージング結果は、融点より1.5 K低い温度に保持された固体D–T層において、表面粗さが時間とともに減少することを明確に示している。

wiki

TritiumInertial confinement fusionDeuteriumDeuterium-tritiumBeryllium
この論文にはまだAI要約がありません。

関連論文

Study on the growth and redistribution of deuterium–deuterium layer driven by temperature gradient

2022Nuclear Fusion

Invited article: X-ray phase contrast imaging in inertial confinement fusion and high energy density research

2023Review of Scientific Instruments

Oxide segregation and melting behavior of transient heat load exposed beryllium

2016Nuclear Fusion

First implosion experiments with cryogenic thermonuclear fuel on the National Ignition Facility

2012Plasma Physics and Controlled Fusion

Effect of thermal fluctuations in the fill tube on deuterium-tritium ice layering in an inertial confinement fusion target

2023Fusion Engineering and Design

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

1997Fusion Engineering and Design

The role of defects, deuterium, and surface morphology on the optical response of beryllium

2022Nuclear Fusion

Refractive index measurement of hydrogen isotopologue mixture and applicability for homogeneity of hydrogen solid at cryogenic temperature in fusion fuel system

2023Nuclear Fusion

In situ observation of tritium interactions with Pd and Zr by β-ray induced X-ray spectrometry

2000Fusion Engineering and Design

Neutron emission profile measurements during the first tritium experiments at JET

1993Nuclear Fusion