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

Thermal–mechanical and thermal–hydraulic integrated study of the Helium-Cooled Lithium Lead Test Blanket Module

P. Chiovaro, P.A. Di Maio, R. Giammusso, Q. Lupo, G. Vella2010年Fusion Engineering and DesignIF 1.7出版社

wiki

LithiumHeliumTest blanket moduleLead-lithium eutecticBlanket moduleThermal-hydraulics
この論文にはまだAI要約がありません。

関連論文

Preliminary thermal-hydraulics design of the dual-cooled lithium lead blanket for FDS-II

2005Fusion Engineering and Design

On the nuclear response of the helium-cooled lithium lead test blanket module in ITER

2005Fusion Engineering and Design

Assessment of COMSOL capability to analyze thermal-hydraulic characteristics of Korean helium cooled test blanket

2013Fusion Engineering and Design

Helium-cooled lithium lead: Activation analysis of the test blanket module in ITER

2008Fusion Engineering and Design

Investigation on the “advanced-plus” Helium Cooled Lithium Lead Breeding Blanket design concept for TBR enhancement regarding thermal and mechanical behavior

2018Fusion Engineering and Design

On the influence of the supporting frame on the nuclear response of the Helium-Cooled Lithium Lead Test Blanket Module for ITER

2006Fusion Engineering and Design

Validation study of turbulence models for thermal-hydraulic simulation of helium cooled DONES high flux test module

2020Fusion Engineering and Design

Design approach for the main ITER test blanket modules for the EU helium cooled lithium–lead blankets

2006Fusion Engineering and Design

On the thermal and thermomechanical assessment of the “Optimized Conservative” helium-cooled lithium lead breeding blanket concept for DEMO

2018Fusion Engineering and Design

Development of a thermal-hydraulic model of the EU-DEMO Water Cooled Lithium Lead Breeding Blanket Primary Heat Transport System

2023Fusion Engineering and Design