Development of thermal-hydraulic analysis methodology for multiple modules of water-cooled breeder blanket in fusion DEMO reactor
Author:
Funder
National Fusion Research Institute of Korea
Publisher
Elsevier BV
Subject
Mechanical Engineering,General Materials Science,Nuclear Energy and Engineering,Civil and Structural Engineering
Reference7 articles.
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2. A preliminary conceptual design study for Korean fusion DEMO reactor;Kim;Fusion Eng. Des.,2012
3. Pre-conceptual design study on K-DEMO ceramic breeder blanket;Park;Fusion Eng. Des.,2015
4. Development of a multi-dimensional thermal-hydraulic system code, MARS 1.3.1;Jeong;Ann. Nucl. Energy,1999
5. Thermal-hydraulic analysis of water cooled breeding blanket of K-DEMO using MARS-KS code;Lee;Fusion Eng. Des.,2015
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1. Study of the EU-DEMO WCLL Breeding Blanket Primary Cooling Circuits Thermal-Hydraulic Performances during Transients Belonging to LOFA Category;Energies;2021-03-11
2. A Two-Way Neutronics/Thermal-Hydraulics Coupling Analysis Method for Fusion Blankets and Its Application to CFETR;Energies;2020-08-06
3. Conceptual design and analysis of the HCCR breeder blanket for the K-DEMO;Fusion Engineering and Design;2020-04
4. Analysis of the Flow Distribution in the Back Supporting Structure Manifolds of the HCPB Breeding Blanket for the EU DEMO Fusion Reactor;Fusion Science and Technology;2019-05-03
5. Investigation of technical gaps between DEMO blanket and HCCR TBM;Fusion Engineering and Design;2018-11
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