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

Evaluation of nuclear heating, tritium breeding and shielding efficiency of the DEMO HCLL breeder blanket

J. Jordanova, U. Fischer, P. Pereslavtsev, Y. Poitevin, A. Adamski2005年Fusion Engineering and DesignIF 1.7出版社

wiki

DEMOTritiumShieldingBreeder blanketHelium-cooled lead-lithiumTritium breeding
この論文にはまだAI要約がありません。

関連論文

Tritium transport model at breeder unit level for HCLL breeding blanket

2019Fusion Engineering and Design

ITER breeding blanket design for the enhanced performance phase

1998Fusion Engineering and Design

Nuclear performance analyses of the HCLL breeder blanket for a fusion power reactor

2009Fusion Engineering and Design

Tritium transport model at breeder unit level for WCLL breeding blanket

2019Fusion Engineering and Design

Tritium management and safety issues in ITER and DEMO breeding blankets

2013Fusion Engineering and Design

Tritium modelling in HCPB breeder blanket at a system level

2017Fusion Engineering and Design

Exploratory neutronic evaluation on the enhancement of tritium breeding and energy multiplication capability using (Th,U)O2 in a solid-state tritium breeding blanket of a fusion demonstration reactor

2024Fusion Engineering and Design

Tritium breeding capability of water cooled ceramic breeder blanket with different container designs

2019Fusion Engineering and Design

Tritium transfers and main operating parameters impact for demo lithium lead breeding blanket (HCLL)

2008Fusion Engineering and Design

Nuclear analysis of the HCLL “Advanced-Plus” breeding blanket

2018Fusion Engineering and Design