ISSN 2079-3537      

 
 
 
                                                                                                                                                                                                                                                                                                                                                                                                                                                                             
Scientific Visualization
Issue Year: 2012
Quarter: 1
Volume: 4
Number: 1
Pages: 22 - 30
Article Name: APPLICATION OF VISUALIZATION TOOLS FOR ANALYSIS OF STATISTICAL UNCERTAINTIES IN MONTE CARLO CALCULATIONS OF CHANNEL-WISE FUNCTIONALS IN RBMK-1000
Authors: I. Ivanov (Russia), S. Bychkkov (Russia), V. Druzhinin (Russia), I. Moiseyev (Russia), U. Shmonin (Russia), N. Shchukin (Russia)
Address: I. Ivanov
ilShai-Hulud@yandex.ru
National Research Nuclear University "MEPhI", Moscow, Russia
Joint stock company "All-Russia Research Institute for Nuclear Power Plants Operation" (VNIIAES), Moscow, Russia
 
S. Bychkkov
bbk_family@mail.ru
Joint stock company "All-Russia Research Institute for Nuclear Power Plants Operation" (VNIIAES), Moscow, Russia
 
V. Druzhinin
Joint stock company "All-Russia Research Institute for Nuclear Power Plants Operation" (VNIIAES), Moscow, Russia
 
I. Moiseyev
Joint stock company "All-Russia Research Institute for Nuclear Power Plants Operation" (VNIIAES), Moscow, Russia
 
U. Shmonin
Joint stock company "All-Russia Research Institute for Nuclear Power Plants Operation" (VNIIAES), Moscow, Russia
 
N. Shchukin
NVShchukin@mephi.ru
National Research Nuclear University "MEPhI", Moscow, Russia
Abstract: The paper considers the problem of qualitative and quantitative evaluation of statistical uncertainties in Monte Carlo calculations of various functionals in reactor of RBMK-1000 type. Analysis of the statistical uncertainties was carried out with application of visualization tools. It was revealed that spatial correlations between neighboring source iterations can produce a random "macro-fluctuation" of neutron distribution in the reactor core. The paper presents numerical evaluations of statistical uncertainties in determination of various neutron functionals and some recommendations on selection of model parameters for precision calculations of RBMK-1000 by Monte Carlo codes.
Language: Russian