HCLL TBM design status and development-Reference-Cited by-同舟云学术

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HCLL TBM design status and development

Published:2011-10 Issue:9-11 Volume:86 Page:2129-2134
ISSN:0920-3796
Container-title:Fusion Engineering and Design
language:en
Short-container-title:Fusion Engineering and Design

Author:

Aiello G.,de Dinechin G.,Forest L.,Gabriel F.,Puma A. Li,Rampal G.,Rigal E.,Salavy J.F.,Simon H.

Publisher

Elsevier BV

Subject

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

Reference18 articles.

1. Consistent integration in preparing the helium cooled lithium lead DEMO-2007 reactor;Li-Puma;Fusion Eng. Des.,2009

2. The EU TBM systems: design and development programme;Boccaccini;Fusion Eng. Des.,2009

3. Strategy for the blanket testing in ITER;Boccaccini;Fusion Eng. Des.,2002

4. ITER TBWG, ITER test blanket working group activities: a summary, recommendations and conclusions;Chuyanov;Fusion Eng. Des.,2002

5. DEMO relevance of the test blanket modules in ITER—application to the European test blanket modules;Magnani;Fusion Eng. Des.,2010

Cited by 39 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. Thermo-Physical Property Database of Fusion Materials and Thermo-Hydraulic Database of Breeder Blankets for CFETR;Springer Proceedings in Physics;2023

2. Tritium Breeding Performance Analysis of HCLL Blanket Fusion Reactor Employing Vanadium Alloy (V-5Cr-5Ti) as First Wall Material;Science and Technology of Nuclear Installations;2022-12-15

3. Numerical Simulations with RELAP5-3D and RELAP5/mod3.3 of the Second Experimental Campaign on In-Box LOCA Transients for HCLL TBS;Energies;2021-07-27

4. Fabrication and testing of small mock-ups for helium cooled ceramic reflector breeding blanket development;Fusion Engineering and Design;2021-06

5. MHD effects of partition plates on thermofluid performance of Indian variant LLCB TBM for ITER;Fusion Engineering and Design;2021-03

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