On the optimization of the first wall of the DEMO water-cooled lithium lead outboard breeding blanket equatorial module-Reference-Cited by-同舟云学术

On the optimization of the first wall of the DEMO water-cooled lithium lead outboard breeding blanket equatorial module

Published:2016-11 Issue: Volume:109-111 Page:335-341
ISSN:0920-3796
Container-title:Fusion Engineering and Design
language:en
Short-container-title:Fusion Engineering and Design

Author:

Di Maio P.A.,Arena P.,Bongiovì G.,Chiovaro P.,Forte R.,Garitta S.

Funder

Euratom research and training programme

Publisher

Elsevier BV

Subject

Mechanical Engineering,General Materials Science,Nuclear Energy and Engineering,Civil and Structural Engineering

Reference11 articles.

1. Final Report on Deliverable CAD, Neutronic, Thermo-hydraulics, Thermo-mechanical analyses Contribution to DDD 2014, Report IDM reference No EFDA_D_2M6Q23, WPBB-DEL-D-321-01.

2. Development of the water cooled lithium lead blanket for DEMO;Aubert;Fusion Eng. Des.,2014

3. J. Aubert, G. Aiello, N. Jonquères, A. Li Puma, A. Morin, G. Rampal, Design development of a DEMO blanket vertical segment—water-cooled LiPb concept, CEA, Report, DEN/DANS/DM2S/SEMT/BCCR/RT/13-003/A.

4. Assessment of the thermo-mechanical performances of a DEMO water-cooled liquid metal blanket module;Chiovaro;J. Fusion Energy,2015

5. Optimization of the first wall for the DEMO water cooled lithium lead blanket;Aubert;Fusion Eng. Des.,2015

Cited by 20 articles. 订阅此论文施引文献订阅此论文施引文献，注册后可以免费订阅5篇论文的施引文献，订阅后可以查看论文全部施引文献

1. SIMMER code two-fluid model well-posedness and stability for simulating liquid metal (lead–lithium eutectic), water vapor, and non-condensable gases multi-component multi-phase flows;Progress in Nuclear Energy;2024-08

2. On the impact of the heat transfer modelling approach on the prediction of EU-DEMO WCLL breeding blanket thermal performances;Fusion Engineering and Design;2020-12

3. Advancements in the HELIAS 5-B breeding blanket structural analysis;Fusion Engineering and Design;2020-12

4. A review of the LIBS analysis for the plasma-facing components diagnostics;Journal of Nuclear Materials;2020-12

5. Progresses in the structural assessment of the central region of a HELIAS 5-B breeding blanket half sector;Fusion Engineering and Design;2020-10