| dc.description.abstract | The fuel volume fraction analysis has been
carried out with uranium carbide in GasCooled Fast Reactor using the SRAC Code
(Standard Reactor Analysis Code). This code
was developed by the Japan Atomic Energy
Agency (JAEA) and uses the latest nuclear data
library JENDL 4.0. There are two calculation
has been used, fuel pin cell calculation (PIJ
Calculation) and core calculation (CITATION
Calculation). In core calculation, the leakage is
calculated so the calculation more precise. The
CITATION calculation use two type of core
configuration, i.e. homogeneous core
configuration and heterogeneous core
configuration. The power density value of two
type core configuration is quite difference. It is
better use heterogeneous core configuration
than homogeneous core configuration, because
the power density of heterogeneous core
configuration is flatter than the other. The
optimum design based on the analysis that has
been carried out is the fuel volume fraction of
49% with a heterogeneous core configuration
of 3 types of fuel percentages, for Fuel type 1 =
9%, Fuel type 2 = 12% and Fuel type 3 = 15%
with the reactor is cylindrical and has a core
diameter of 240 cm and a core height of 100 cm | en_US |
