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

Conceptual design of a laser-diode-pumped Nd:glass slab laser driver for inertial fusion energy

H. Matsui, T. Eguchi, T. Kanabe, M. Yamanaka, S. Nakai1999年Fusion Engineering and DesignIF 1.7出版社

AbstractWe have proposed and designed a laser-diode-pumped laser driver for inertial fusion energy (IFE) which consists of water-cooled zig-zag path Nd:glass slab amplifiers. A driver module was designed under the several operational constraints and has 10 kJ total output energy at 351 nm and operates at 12 Hz with 10.4% overall efficiency. The laser driver producing 4 MJ blue output for IFE will consist of 400 modules.

日本語訳

アブストラクト我々は、慣性核融合エネルギー(IFE)用のレーザーダイオード励起レーザードライバーを提案し、設計した。これは、水冷式ジグザグ経路Nd:ガラススラブ増幅器で構成される。ドライバーモジュールは、いくつかの運転制約の下で設計され、351 nmで総出力エネルギー10 kJ、12 Hzで動作し、総合効率10.4%を有する。IFE用の4 MJの青出力を生成するレーザードライバーは、400個のモジュールで構成される。

wiki

Inertial confinement fusionInertial Fusion Energy
この論文にはまだAI要約がありません。

関連論文

Inertial confinement fusion experiments with OMEGA-A 30-kJ, 60-beam UV laser

1999Fusion Engineering and Design

Inertial fusion program in Japan and ignition experiment facility by laser

1989Fusion Engineering and Design

A concept of an FEL based energy driver for commercial inertial confinement fusion reactor

1999Fusion Engineering and Design

Optimization of laser–target coupling efficiency for direct drive laser fusion

2005Nuclear Fusion

10-Hz laser multi-beam steering and illumination for free-falling targets

2026Nuclear Fusion

High yield polar direct drive fusion neutron sources at the National Ignition Facility

2021Nuclear Fusion

From laser fusion to laser accelerators: basic studies into high power laser plasmas

2009Plasma Physics and Controlled Fusion

Investigation of laser plasma instabilities driven by 527 nm laser pulses relevant for direct drive inertial confinement fusion

2024Physics of Plasmas

An indirect-drive non-cryogenic double-shell path to 1ω Nd-laser hybrid inertial fusion–fission energy

2010Nuclear Fusion

A rep rate KrF system to address issues relevant to inertial fusion energy

1999Fusion Engineering and Design