Neutronics investigation of advanced self-cooled liquid blanket systems in the helical reactor
Author:
Publisher
IOP Publishing
Subject
Condensed Matter Physics,Nuclear and High Energy Physics
Reference18 articles.
1. Blanket and divertor design for force free helical reactor (FFHR)
2. Design studies on nuclear properties on the Flibe blanket for helical-type fusion reactor FFHR
3. Tritium Self-Sufficiency and Neutron Shielding Performance of Self-Cooled Liquid Blanket System for Helical Reactor
4. Blanket neutronics of Li/vanadium-alloy and Flibe/vanadium-alloy systems for FFHR
5. Development of CAD/MCNP interface program prototype for fusion reactor nuclear analysis
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1. Examination of Transmutation Effect on Responses of K-Type and N-Type Thermocouples at Fusion Blanket;Fusion Science and Technology;2019-09-16
2. Dissimilar-Metals Bonding Between NIFS-HEAT-2 Vanadium Alloy and Hastelloy X Nickel Alloy by Controlling Intermetallics;Fusion Science and Technology;2017-08-16
3. Analysis of radiation environment at divertor in helical reactor FFHR-d1;Fusion Engineering and Design;2014-10
4. Design activities on helical DEMO reactor FFHR-d1;Fusion Engineering and Design;2012-08
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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