scholarly journals 2240-MW(th) high-temperature reactor core power density study

1984 ◽  
Author(s):  
D. R. Vondy
Keyword(s):  
High Temperature ◽  
Power Density ◽  
Reactor Core ◽  
High Temperature Reactor ◽  
Density Study

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.

High temperature reactor core physics and reactor dynamics

1990 ◽  
Vol 121 (2) ◽  
pp. 227-240 ◽  
Author(s):  
L. Wolf ◽  
W. Scherer ◽  
W. Giesser ◽  
W. Feltes
Keyword(s):  
High Temperature ◽  
Reactor Core ◽  
Reactor Dynamics ◽  
High Temperature Reactor
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