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

Tritium extraction and recovery system (TER) for the helium cooled pebble beds with steam in the helium purge gas

Mirela Draghia, I. Cristescu, G. Pasca2023年Fusion Engineering and DesignIF 1.7出版社

wiki

TritiumHeliumPebble bedHelium-cooled pebble bedTritium extraction
この論文にはまだAI要約がありません。

関連論文

Tritium transport in the vacuum vessel pressure suppression system for helium cooled pebble bed

2023Fusion Engineering and Design

Tritium processing systems for the helium cooled pebble bed test blanket module

2008Fusion Engineering and Design

Experimental study on the pressure drop of helium purge gas in particle crushing pebble beds

2024Fusion Engineering and Design

Observation of tritium and helium core transport barriers in reversed shear plasmas on TFTR

1998Plasma Physics and Controlled Fusion

Inpile tritium release from ceramic breeder materials in TRIDEX experiments 1–6

1991Fusion Engineering and Design

Cold trapping of traces of tritiated water from the helium loops of a fusion breeder blanket

2001Fusion Engineering and Design

Transport properties of a deuterium, tritium, helium plasma/gas mixture

1985Nuclear Fusion

Helium-3 blankets for tritium breeding in near-term fusion devices

1989Fusion Engineering and Design

Evaluation of tritium production rate in a gas-cooled reactor with continuous tritium recovery system for fusion reactors

2013Fusion Engineering and Design

Helium behaviour in expanded boundary divertor discharges

1982Nuclear Fusion