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7116983 
Journal Article 
Status on DEMO Helium Cooled Lithium Lead breeding blanket thermo-mechanical analyses 
Aubert, J; Aiello, G; Jaboulay, JC; Kiss, B; Morin, A; , 
2016 
Yes 
Fusion Engineering and Design
ISSN: 0920-3796 
ELSEVIER SCIENCE SA 
LAUSANNE 
109 
991-995 
WOS:000382421900171 
The EUROfusion Consortium develops a design of a fusion power demonstrator (DEMO) in the framework of the European "Horizon 2020" innovation and research program. One of the key components in the fusion reactor is the breeding blanket surrounding the plasma, ensuring tritium self-sufficiency, heat removal for conversion into electricity, and neutron shielding. The Helium Cooled Lithium Lead (HCLL) blanket is one of the concepts which is investigated for DEMO. It is made of a Eurofer structure and uses the eutectic liquid lithium-lead as tritium breeder and neutron multiplier, and helium gas as coolant. Within the EUROfusion organization, CEA with the support of Wigner-RCP and IPP-CR, is in charge of the design of the HCLL blanket for DEMO.This paper presents the status of the thermal and mechanical analyses carried out on the HCLL breeding blanket in order to justify the design. CFD thermal analyses on generic breeding unit including stiffening plates and cooling plates have been performed with ANSYS in order to consolidate results obtained with previous FEM design analyses. Moreover in order to expand the justification of the HCLL Breeding blanket design, the most loaded area of the equatorial outboard module has been analyzed with CAST3M in case of accident, according to RCC-MRx, resulting in relatively good behavior of the box. Additionally analyses have been performed in order to check the good behavior of the tie rods modules' attachments system in normal condition showing promising results. (C) 2016 Elsevier B.V. All rights reserved. 
DEMO; Breeding Blanket; HCLL; Design; Cast3M; RCC-MRx 
12th International Symposium on Fusion Nuclear Technology (ISFNT) 
Jeju, SOUTH KOREA