Thermal Analysis for an Ultra High Temperature Gas-Cooled Reactor with Pebble Type Fuels
International Journal of Energy and Power Engineering
Volume 4, Issue 4, August 2015, Pages: 189-196
Received: May 29, 2015; Accepted: Jun. 12, 2015; Published: Jul. 1, 2015
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Authors
Motoo Fumizawa, Department of Mechanical Engineering, Shonan Institute of Technology, Fujisawa, Kanagawa, Japan
Naoya Uchiyama, Department of Mechanical Engineering, Shonan Institute of Technology, Fujisawa, Kanagawa, Japan
Takahiro Nakayama, Department of Mechanical Engineering, Shonan Institute of Technology, Fujisawa, Kanagawa, Japan
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Abstract
This study presents a predictive thermal-hydraulic analysis with packed spheres in a nuclear gas-cooled reactor core. The predictive analysis considering the effects of high power density and the some porosity value were applied as a design condition for an Ultra High Temperature Reactor (UHTR). The thermal-hydraulic computer code was developed and identified as PEBTEMP. The highest outlet coolant temperature of 1316 oC was achieved in the case of an UHTREX at LASL, which was a small scale UHTR using hollow-rod as a fuel element. In the present study, the fuel was changed to a pebble type, a porous media. Several calculation based on HTGR-GT300 through GT600 were 4.8 w/cm3 through 9.6 w/cm3, respectively. As a result, the relation between the fuel temperature and the power density was obtained under the different system pressure and coolant outlet temperature. Finally, available design conditions are selected.
Keywords
Thermal Hydraulics, Ultra High Temperature Reactor (UHTR), Pressure Drop, Porosity and Pebble Type Fuel
To cite this article
Motoo Fumizawa, Naoya Uchiyama, Takahiro Nakayama, Thermal Analysis for an Ultra High Temperature Gas-Cooled Reactor with Pebble Type Fuels, International Journal of Energy and Power Engineering. Vol. 4, No. 4, 2015, pp. 189-196. doi: 10.11648/j.ijepe.20150404.11
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