Home / Store / Journals / Electronic Articles / Fusion Science and Technology / Volume 47 / Number 3 / Pages 540-543
T. Muroga, T. Tanaka
Fusion Science and Technology / Volume 47 / Number 3 / Pages 540-543
Format:electronic copy (download)
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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