A NEW DESIGN OF A VERTICAL PRESSURE-TUBE TYPE SCWR
The 5th International Symposium on SuperCritical Water-cooled Reactors - 2011 March 13-16


Presented at:
The 5th International Symposium on SuperCritical Water-cooled Reactors
2011 March 13-16
Location:
Vancouver,Canada
Session Title:
Core Design

Authors:
Donghua Lu (China Guandong Nuclear Power Corporation)
Jue Yang (China Guandong Nuclear Power Corporation)
Xiangang Fu (China Guandong Nuclear Power Corporation)
Qianhua Su (China Guandong Nuclear Power Corporation)
Fan Peng (China Guandong Nuclear Power Corporation)
Jun Xing (China Guandong Nuclear Power Corporation)
Yong Zhang (China Guandong Nuclear Power Corporation)
  

Abstract

A conceptual super critical water reactor (SCWR) with vertical pressure tube (PT) is presented in this paper. The PT has re-entry flow path. The low temperature downward flow between the tube and fuel assemblies protects the tube from contacting high temperature heated fluid in fuel subchannels. A gas cylinder is established out of the PT to prevent heat loss from coolant at operation. This gas insulation can be removed out to cool PTs with heavy water moderator during severe accident. It can prevent any fuel pellets melting with the cooling from moderator.

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