Validation of the Monte Carlo Model Developed to Estimate the Neutron Activation of Stainless Steel in a Nuclear Reactor

Control rods in a nuclear reactor are activated by neutron irradiation. The activity generated will produce a dose around the rod, irrelevant while it is inside the reactor, but significant when the rod is withdrawn from the reactor and placed in a storage pool. This dose is a potential risk for workers in the surrounding area. In previous works, neutron activation and doses have been calculated for a Boiling Water Reactor using the MCNP5 code based on the Monte Carlo method. The model was validated comparing simulation results with experimental measurements in a NPP. On the other hand, most of the activation is produced in stainless steel components of the rod. Therefore, the Monte Carlo model can be also validated considering the activation produced in a piece of stainless steel exposed to some neutron flux in a reactor and measuring the dose around this piece. In this paper, Monte Carlo models developed for both activation of a piece of stainless steel and dose assessment are presented. Comparison of simulation results with experimental measurements in the Training Reactor AKR-2 of the Technical University Dresden shows a good agreement. Hence, the validation of Monte Carlo models can be confirmed.