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Neutronics Investigation into Lithium/Vanadium Test Blanket Modules

T. Muroga, T. Tanaka

Fusion Science and Technology / Volume 47 / Number 3 / April 2005 / Pages 540-543

Technical Paper / Fusion Energy - First Wall, Blanket, and Shield

A neutronics-based investigation was carried out for self-cooled Blanket Test Modules in ITER with coolant of liquid lithium and structural materials of V-4Cr-4Ti. The design feasibility was demonstrated for the test module having the purpose to validate the tritium self sufficiency for DEMO Li/V blanket without neutron multiplier Be.

 
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