The helium-cooled lithium lead blanket test proposal in ITER and requirements on test blanket modules instrumentation-Reference-Cited by-同舟云学术

The helium-cooled lithium lead blanket test proposal in ITER and requirements on test blanket modules instrumentation

Published:2005-11 Issue: Volume:75-79 Page:951-955
ISSN:0920-3796
Container-title:Fusion Engineering and Design
language:en
Short-container-title:Fusion Engineering and Design

Author:

Puma A. Li,Poitevin Y.,Giancarli L.,Rampal G.,Farabolini W.

Publisher

Elsevier BV

Subject

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

Reference8 articles.

1. Materials and design of the European DEMO blankets;Boccaccini;J. Nucl. Mater.,2004

2. Strategy for the blanket testing in ITER;Boccaccini;Fus. Eng. Des.,2002

3. The European breeding blankets development and the test strategy in ITER;Poitevin;Fus. Eng. Des.,2005

4. HCLL-TBM for ITER, Design Studies;Rampal;Fus. Eng. Des.,2005

5. M.A. Fütterer, B. Bielak, J. Szczepanski, L. Giancarli, Drain system and instrumentation of a water-cooled Pb–17Li test blanket module, CEA Report, SERMA/LCA/98-2460/A, December 1998.

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1. Instrumentation for Neutron Flux and Tritium Production Rate Monitoring in the European TBM in ITER;IEEE Transactions on Plasma Science;2014-10

2. DEMO relevance of the test blanket modules in ITER—Application to the European test blanket modules;Fusion Engineering and Design;2010-12

3. MHD Mock-Up Experiments for Studying Pressure Distribution in a Helium-Cooled Liquid-Metal Blanket;IEEE Transactions on Plasma Science;2010-03

4. Nuclear Data Benchmarking for Lead by LiAl/Pb Fusion Blanket Mock-Up Experiment;Nuclear Technology;2009-12

5. Experimental analysis of MHD pressure drop in a HCLL blanket mock-up;2009 23rd IEEE/NPSS Symposium on Fusion Engineering;2009-06