Statistical calculation procedure, e.g. to calculate
the neutron flux distribution in burnup and shielding calculations.
In this context, the history of individual, statistically sampled neutrons
is calculated until sufficient individual simulations (individual destinies)
result in numerical average values for the neutron flux at the points
considered. The calculation, which is simple in itself, requires a very
large number of individual calculations, since a high degree of accuracy
is achieved only with a large number of individual destiny calculations.
11 - 15 March 2018
30 September - 04 October 2018
Prague, Czech Republic