Szczegóły publikacji
Opis bibliograficzny
Parametric studies of the PWR fuel assembly modeling with Monte-Carlo method / Grzegorz KĘPISTY, Jerzy CETNAR, Przemysław STANISZ // Annals of Nuclear Energy ; ISSN 0306-4549. — 2016 — vol. 94, s. 189–207. — Bibliogr. s. 206–207, Abstr. — Publikacja dostępna online od: 2016-03-19
Autorzy (3)
Słowa kluczowe
Dane bibliometryczne
| ID BaDAP | 97420 |
|---|---|
| Data dodania do BaDAP | 2016-04-27 |
| DOI | 10.1016/j.anucene.2016.03.008 |
| Rok publikacji | 2016 |
| Typ publikacji | artykuł w czasopiśmie |
| Otwarty dostęp |  |
| Czasopismo/seria | Annals of Nuclear Energy |
Abstract
In this paper we present results of studies concerning modeling of critical nuclear systems performed by continuous energy Monte Carlo burnup code. We consider a geometry model of fuel assembly for Pressurized Water Reactor neutronic simulations with depletion calculated in the infinite medium. A variety of modeling parameters and common simplifications concerning geometry complexity have been investigated in order to observe their impact on key reactor parameters like: neutron multiplication factor, nuclide concentrations, conversion ratio and distribution of generated power. Comparison of different factors helps to draw conclusions about their significance and to choose the reliable modeling approach. The presented results should be valuable for a beginning reactor researcher, but the specialists will also find a part of results interesting due to their seldom direct consideration in literature. The conclusions are general and valid not only in case of Monte Carlo simulations. We found that the lack of reactivity control in the model biases the concentration of 235U by more than 10% at end of irradiation. Next, calculation time steps longer than 50 days lead to average discrepancy of neutron multiplication factor of 100 pcm or more. Axial discretization of fuel requires more than 20 burnable zones to provide asymptotic behavior of burnup calculation. Lack of thermal collision tables results in underestimation of minor actinides concentrations of the order of 10% at low burnup and several percent at the end-of-life. The discrepancies caused by: the radial discretization of fuel pins, the presence of the clad–pellet gap, the applied precision of Monte Carlo calculations and the separate treatment of fuel rods, have been observed at the end-of-life to lead to a maximum relative difference in concentrations of 235U and 239Pu below 1%. Nevertheless, some studies should take also these effects into account.
