Vitaly Mogulian

Monte Carlo Variance Reduction Research & Code Developing & Nuclear Engineering

Steel Anthill toy model

All of the model parameters are the same as in Concrete Anthill, but steel is used as a shielding material instead of concrete one.


Figure 1: Horizontal model cross-section

In this calculation, the following techniques are used:

Expected value estimators;
Joint location-direction importance sampling for (for gamma only);
Energy importance sampling for (for gamma only);
Exponential transform;
Simplified adaptive splitting.

The primary computational gain is achieved here thanks to the simplified adaptive splitting, joint location-direction IS (for primary gamma), and exponential transform techniques.

Computed flux functional - ambient equivalent dose H*(10) [1] rates, the thickness of volumetric detectors are 100 cm. Below, some results of neutron-gamma and gamma problems 20.5 hours long computation are presented.. Despite the smoothness of the plots, valid estimations require much larger statistics for enough precision.


Figure 2: Neutron horizontal dose rates distribution


Figure 3: Secondary gamma horizontal dose rates distribution


Figure 4: Primary gamma horizontal dose rates distribution

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References

International Commission on Radiological Protection., International Commission on Radiation Units, and Measurements. Conversion coefficients for use in radiological protection against external radiation. Annals of the ICRP ; v. 26, no. 3/4. Published for the Commission by Pergamon Press, Oxford ;, 1st ed. edition, 1996 - 1997.