Thermal Hydraulics and Thermal Radiation for Ultra High Temperature Gas-Cooled Nuclear Reactor With Pebble Type Fuel

2005 ◽  
Author(s):  
Motoo Fumizawa
Keyword(s):  
High Temperature ◽  
Thermal Radiation ◽  
Surface Temperature ◽  
Radiation Flux ◽  
Coolant Temperature ◽  
Present Calculation ◽  
System Pressure ◽  
High Temperature Reactor ◽  
Type Fuel ◽  
Ultra High Temperature

This report presents the results of thermal-hydraulic analysis for the Ultra High Temperature Reactor Experiment (UHTREX) as well as the modular Gas Turbine High Temperature Reactor 300 MWth (HTGR-GT300) loaded with Pebble Type Fuel. A thermal-hydraulic computer code was developed that was named PEBTEMP. In order to compare the present PBR case with UHTREX, a calculation for HTGR-GT300 was carried out in the similar conditions with UHTREX i.e. the inlet coolant temperature of 871°C, system pressure of 3.45 MPa and power density of 1.3 W/cm3. The hot channel factor of 1.0, 1.1, 1.2, and 1.3 are chosen for the present calculation. As the result, the fuel temperature for the present PBR case is extremely low when compared to the UHTREX case. The evaluated temperature is compared to the data of conventional optical high temperature camera using the principle of the thermal radiation flux dependence upon surface temperature. Therefore, the present PBR system design will be named as NUHTREX i.e. New UHTREX. The evaluated temperature is compared to the data of conventional optical high temperature camera using the principle of the thermal radiation flux dependence upon surface temperature.

Thermal Evaluation for a Ultra High Temperature Reactor With Pebble Type Fuels

2009 ◽  
Author(s):  
Motoo Fumizawa ◽  
Yuta Kosuge ◽  
Hidenori Horiuchi
Keyword(s):  
High Temperature ◽  
Power Density ◽  
Reactor Core ◽  
Coolant Temperature ◽  
Small Scale ◽  
Outlet Temperature ◽  
Fuel Temperature ◽  
System Pressure ◽  
High Temperature Reactor ◽  
Ultra High Temperature

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 °C 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.

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