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Objectives and Status of EUROfusion DEMO Blanket Studies This work

Culham Publication Services02.2016

Status on DEMO Helium Cooled Lithium Lead Breeding Blanket Thermo-Mechanical Analyses

Culham Publication Services02.2016

Tritium Extraction Technologies and DEMO Requirements

Culham Publication Services02.2016

Nuclear Analysis of the HCLL Blanket Concept for the European DEMO Using the TRIPOLI-4® Monte Carlo Code

Culham Publication Services02.2016

Development of a Thermal-Hydraulic Model for the Dynamic Simulation of the EU DEMO Breeding Blanket Cooling Loops. Part I: HCPB

Culham Publication Services02.2016

Catalytic Membrane Reactor for Tritium Extraction System from He Purge

Culham Publication Services02.2016

Neutronic Performance Issues of the Breeding Blanket Options for the European DEMO Fusion Power Plant

Culham Publication Services02.2016

Tritium Release from Titanium Beryllide After High-Temperature Loading by Tritium/Protium Gas Mixture

Culham Publication Services02.2016

Neutronic Analyses of the Preliminary Design of a DCLL Blanket for the EUROfusion DEMO Power Plant

Culham Publication Services02.2016

Simulation of Hydrogen Effect on Equilibrium Shape of Gas Bubbles in Beryllium

Culham Publication Services02.2016

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This work has been carried out within the framework of the EUROfusion Consortium and has received funding from the Euratom research and training programme 2014-2018 and 2019-2020 under grant agreement No 633053. The views and opinions expressed herein do not necessarily reflect those of the European Commission.

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