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

Simulation of loss-of-flow transient in water cooled fission blanket of Fusion-fission Hybrid Energy Reactor (FFHER)

Heng Xie, Ming-gang Lang, Zhang-cheng Yu2018年Fusion Engineering and DesignIF 1.7出版社
この論文にはまだAI要約がありません。

関連論文

Neutronics analysis of water-cooled energy production blanket for a fusion–fission hybrid reactor

2010Fusion Engineering and Design

Study on fission blanket fuel cycling of a fusion–fission hybrid energy generation system

2011Nuclear Fusion

Neutronics performance evaluation of fast-fission fuel breeding blankets for a fusion–fission hybrid reactor

2010Fusion Engineering and Design

Burnup calculations of light water-cooled pressure tube blanket for a fusion-fission hybrid reactor

2014Fusion Engineering and Design

The neutronics studies of a fusion fission hybrid reactor using pressure tube blankets

2012Fusion Engineering and Design

Thermal-hydraulics design and analysis on a helium-cooled high power density blanket for a fusion–fission hybrid reactor

2010Fusion Engineering and Design

RFP based Fusion-Fission Hybrid reactor model for nuclear applications

2019Fusion Engineering and Design

Neutronic calculations of a thorium-based fusion–fission hybrid reactor blanket

2010Fusion Engineering and Design

Neutronic performance of new coolants in a fusion–fission (hybrid) reactor

2004Fusion Engineering and Design

Fission-fusion systems: hybrid, symbiotic and augean

1975Nuclear Fusion