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Monte-Carlo Method

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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.

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ENS conferences

 
TopSafe 2017

TopSafe 2017
12-16 Feb. 2017
Vienna, Austria

PIME 2017

PIME 2017
19 - 22 March 2017, Middelburg Netherlands

RRFM 2017

RRFM 2017
14 - 18 May 2017 in Rotterdam, Netherlands

ETRAP 2017

ETRAP 2017
30 May - 2 June 2017, Valencia, Spain