The preliminary thermal–hydraulic analysis of a water cooled blanket concept design based on RELAP5 code
Author:
Publisher
Elsevier BV
Subject
Mechanical Engineering,General Materials Science,Nuclear Energy and Engineering,Civil and Structural Engineering
Reference7 articles.
1. Development of the water cooled ceramic breeder test blanket module in Japan;Enoeda;Fusion Eng. Des.,2012
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3. Compact DEMO Slim CS: design progress and issues;Tobita;Nucl. Fusion,2009
4. Simplification of blanket system for Slim CS fusion DEMO reactor;Someya;Fusion Eng. Des.,2011
5. Design and technology development of solid breeder blanket cooled by supercritical water in Japan;Enoeda;Nucl. Fusion,2003
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1. The flow instability phenomenon in the loss of coolant accident of the water cooled blanket;Fusion Engineering and Design;2020-11
2. Analysis of Measuring Characteristics of the Differential Pressure Water-Level Measurement System Under Depressurization Condition;Frontiers in Energy Research;2020-08-27
3. Primary heat transfer system design of the WCCB blanket for multiple operation modes of CFETR;Fusion Engineering and Design;2020-04
4. Study on the temperature control mechanism of the tritium breeding blanket for CFETR;Nuclear Fusion;2017-10-04
5. Thermal hydraulic responses of the Primary Heat Transfer System of the WCCB blanket to accident cases for CFETR;Fusion Engineering and Design;2017-10
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