HEAT-TRANSFER ANALYSIS OF SUPERCRITICAL-WATER AND SUPERHEATED-STEAM-COOLED CHANNELS OF 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:
Thermalhydraulics Assessment

Authors:
Eugene Saltanov (University of Ontario Institute of Technology)
Wargha Peiman (University of Ontario Institute of Technology)
Shona Draper (University of Ontario Institute of Technology)
Igor Pioro (University of Ontario Institute of Technology)
  

Abstract

SuperCritical-Water-cooled Reactors (SCWRs) are being developed as one of the Generation-IV nuclear-reactor concepts. Main objectives of the development are to increase thermal efficiency of a Nuclear Power Plant (NPP) and to decrease capital and operational costs. The first objective can be achieved by introducing nuclear steamreheat inside a reactor and utilizing regenerative feedwater heaters. The second objective can be achieved by designing a steam cycle that closely matches that of the mature supercritical fossil-fuelled power plants.  A detailed steam-cycle layout of a 1200-MWel SCWR, which was scaled from a singlereheat 660-MWel modern thermal-power plant is presented in the paper. Heat transfer calculations were made for SuperCritical-Water (SCW) and SuperHeated-Steam (SHS) channels of the proposed reactor concept. In the calculations a uniform and three nonuniform Axial Heat Flux Profiles (AHFPs) were considered for two different fuels (UO2 and MOX). Bulk-fluid, sheath, and fuel centerline temperatures as well as Heat Transfer Coefficient (HTC) profiles were obtained along fuel channels. The HTC values are within a range of 4.7 – 20 kW/(m2 ·K) and 9.7 – 10 kW/(m2 ·K) for the SCW and SHS channels respectively.

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