Neutronics Investigation into Lithium/Vanadium Test Blanket Modules
Journal Article
·
· Fusion Science and Technology
OSTI ID:20849919
- Fusion Engineering Research Center, National Institute for Fusion Science (United States)
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.
- OSTI ID:
- 20849919
- Journal Information:
- Fusion Science and Technology, Vol. 47, Issue 3; Other Information: Copyright (c) 2006 American Nuclear Society (ANS), United States, All rights reserved. http://epubs.ans.org/; Country of input: International Atomic Energy Agency (IAEA); ISSN 1536-1055
- Country of Publication:
- United States
- Language:
- English
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