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

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

Minghuang Wang, Jieqiong Jiang, Jinchao Liu, Yunqing Bai, Yanglin Hu2010年Fusion Engineering and DesignIF 1.7出版社

wiki

Fusion Advanced Studies TorusNeutronicsHybrid reactor
この論文にはまだAI要約がありません。

関連論文

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

2012Fusion Engineering and Design

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

2011Nuclear Fusion

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

2010Fusion 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

Fusion-fission fuel factory conceptual design for China

1989Fusion Engineering and Design

Fission-fusion systems: hybrid, symbiotic and augean

1975Nuclear Fusion

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

2018Fusion Engineering and Design

NAPTH: Neutronics analysis code system for the fusion–fission hybrid reactor with pressure tube type blanket

2013Fusion Engineering and Design

A scoping neutronics study for a tokamak engineering test fusion breeder (ETFB)

1989Fusion Engineering and Design