Improvement and Benchmarking of the New Shutdown Dose Estimation Method by Monte Carlo Code

In the ITER (International Thermonuclear Experimental Reactor, [1]) project calculations of the dose rate after shutdown are very important and their results are critical for the machine design. A new method has been proposed [2] which makes use of MCNP [3] also for decay gamma-ray transport calculations. The objective is to have an easy tool giving results affected by low uncertainty due to the modeling or simplifications in the flux shape assumptions. Further improvements to this method are here presented.