Article ID Journal Published Year Pages File Type
6761579 Nuclear Engineering and Design 2015 9 Pages PDF
Abstract
The results indicate that the new developed code has good feasibility to transient analysis of supercritical water-cooled test. And the peak cladding temperature caused by blockage in the fuel bundle can be reduced effectively by the safety measures proposed in this paper.
Related Topics
Physical Sciences and Engineering Energy Energy Engineering and Power Technology
Preview
Sub-channel/system coupled code development and its application to SCWR-FQT loop
Authors
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