Blanket neutronics of Li/vanadium-alloy and Flibe/vanadium-alloy systems for FFHR
Author:
Publisher
Elsevier BV
Subject
Mechanical Engineering,General Materials Science,Nuclear Energy and Engineering,Civil and Structural Engineering
Reference13 articles.
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3. Tritium Self-Sufficiency and Neutron Shielding Performance of Self-Cooled Liquid Blanket System for Helical Reactor
4. IPFR, Integrated Pool Fusion Reactor Concept
5. J.F. Briesmeister, “MCNP-A general Monte Carlo n-particle transport code”, Los Alamos National Laboratory report LA-12625-M, March 1997.
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2. Interfacial characterization of dissimilar-metals bonding between vanadium alloy and Hastelloy X alloy by explosive welding;Journal of Nuclear Materials;2020-10
3. Evaluation of lithium glass scintillation detector responses for tritium production rate measurement in blanket neutronics experiments using the PHITS code;Fusion Engineering and Design;2020-02
4. Dissimilar-Metals Bonding Between NIFS-HEAT-2 Vanadium Alloy and Hastelloy X Nickel Alloy by Controlling Intermetallics;Fusion Science and Technology;2017-08-16
5. Design studies on three-dimensional issues for liquid blanket systems in helical reactor FFHR;Fusion Engineering and Design;2012-08
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