The primary objective of control rod management is to ensure the safe, reliable and
optimum use of the nuclear fuel in the reactor, while remain within the limits imposed
by the design of the fuel assembly and reactor w.r.t the safety analysis. In numerous
reactors, the control rods perform the function of reactivity control, both globally and
locally, latter also control the power distribution of the core. Most control rods are
completely withdrawn from the core during operations and fully inserted during
shutdown of the reactor. This are the prove of an investigative study into optimization
of the heterogeneous control rods, the safety management of an additional safety rod,
and control rod drop hydrodynamic analysis which will be able to provide an efficient
and maximum safety procedure for emergency shut down system in the reactor. It is
also will be very important safety features of the reactor. To design the additional
safety rod at the inner irradiation sites with boron carbide (absorber material) and
stainless steel (clad) and also to design a simple heterogeneous control rod design to
analyse the effects of geometry self-shielding, the Monte Carlo Neutron Particle Code,
version 5 (MCNP5) was used. By simulating the unsteady flow field around the control
rod, the hydrodynamic analysis of the control rod can be analysed. A correlation based
on the achieved data was proposed to provide useful information on the safety
management during the research.