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TRITIUM BREEDING SELF-SUFFICIENCY OF DEMO REACTORS WITH A WATER-COOLED PB17LI BLANKET

1993
In the frame of the studies developed for DEMO breeding blankets, a type of blanket with Pb17Li as breeder and water as coolant has been developed at the JRC-Ispra. It deals with breeder circular modules, internally cooled by water in U-type tubes and arranged poloidally according to rows inside boxes, named segments.
Casini, G.   +3 more
openaire   +2 more sources

Conceptual Design for a Blanket Tritium Extraction Test Stand

Fusion Science and Technology, 2021
Chase N Taylor   +2 more
exaly  

Integration issues on tritium management of the European DEMO Breeding Blanket and ancillary systems

Fusion Engineering and Design, 2021
Gandolfo Alessandro Spagnuolo   +2 more
exaly  

3D tritium transport analysis for WCCB blanket based on COMSOL

Fusion Engineering and Design, 2020
Baojie Nie, Lei Chen, Kai Huang
exaly  

Progress of the conceptual design of the European DEMO breeding blanket, tritium extraction and coolant purification systems

Fusion Engineering and Design, 2020
Gandolfo Alessandro Spagnuolo   +2 more
exaly  

Tritium transport analysis in HCPB DEMO blanket with the FUS-TPC code

Fusion Engineering and Design, 2013
Massimo Zucchetti
exaly  

Tritium transport analysis for CFETR WCSB blanket

Fusion Engineering and Design, 2017
Pinghui Zhao
exaly  

Tritium transport analysis of HCPB blanket for CFETR

Fusion Engineering and Design, 2016
Lei Pan, Hong-Li Chen
exaly  

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