Szczegóły publikacji

Opis bibliograficzny

Trajectory periods folding method for modelling of uranium and thorium fuel transmutations / M. OETTINGEN, P. STANISZ // W: NRPM 2019 [Dokument elektroniczny] : international conference on Nuclear and Radiation Physics and Materials : June 17-20, 2019, Yerevan, Armenia : book of abstracts. — Wersja do Windows. — Dane tekstowe. — [Yerevan : s. n.], [2019]. — S. 19. — Wymagania systemowe: Adobe Reader. — Tryb dostępu: https://nrpm.yerphi.am/wp-content/uploads/2019/06/NRPM-2019-c... [2019-07-01]. — Bibliogr. s. 19

Autorzy (2)

Dane bibliometryczne

ID BaDAP122628
Data dodania do BaDAP2019-07-12
Rok publikacji2019
Typ publikacjimateriały konferencyjne (aut.)
Otwarty dostęptak
KonferencjaInternational conference on Nuclear and Radiation Physics and Materials

Abstract

The complexity of burnup process in the nuclear reactors requires application of an integrated calculation system, which allows taking into consideration spatial effects of heterogeneous reactor core model with continuous energy representation of cross section and the thermo-hydraulic coupling. The integrated Continuous Energy Monte Carlo Burnup Code (MCB) developed in recent years satisfies needed requirements [1]. The MCB code is a general-purpose tool dedicated for simulations of radiation transport and radiation-induced changes in matter. The code is developed at the Department of Nuclear Energy, Faculty of Energy and Fuels of the AGH University of Science and Technology, Krakow, Poland. The code integrates A General Monte Carlo N-Particle Transport Code (MCNP) for radiation transport simulations with the Transmutation Trajectory Analysis solver (TTA) for analysis of nuclide density time evolution [2]. The TTA approach allows to transfer numerical solution of the burnup problem described by the Bateman equations into a linear probability problem described by the set of linear chains for each separate burnup time step. In typical burnup calculation, transmutation rates calculated in a particular time step are used for the calculation of new material composition and they are no longer used, yet they are overwritten by the values of the following step. In the proposed methodology of trajectory periods folding, the mass flow of direct nuclide-to-nuclide transitions leading to nuclide transmutation chains in every step is interpreted over entire period of interest [3]. In this way, all quantitative information about the transmutation process for the period beyond single calculation step is preserved. The method builds sets of transmutation trajectories prepared for each computing time step and then combines them in the process of time period folding. Resulted period folded trajectories are interpreted as they would be obtained by the set of parameters from one calculation step. The trajectory periods folding methodology is an alternative to the matrix multiplication method. Both methods allow to obtain individual nuclide transmutation. The trajectory period folding methodology can give the same results. The method was derived from the observation that it is possible to prolong single trajectories evolution by calculating the transition of trajectories obtained from two consecutive steps, where the trajectory from the second step starts with the same nuclide as the trajectory from the first step ends. It turns out that the appropriate sum of trajectories transitions corresponds to the matrix element obtained as a result of matrices multiplication. A set of folded trajectories obtained for the considered period can be used to present various dependencies in the analyzed system. Folded trajectories describe the relation between nuclides through different sequential reactions. The trajectory period folding method can be used in modelling of every nuclear system like e.g. nuclear reactors of each generations. In the study we present the background of the method as well as its implementation for the modeling of chosen nuclear system with uranium and thorium fuel.

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artykuł
#123502Data dodania: 7.8.2019
Trajectory periods folding method for modeling of uranium and thorium fuel transmutations / M. OETTINGEN, P. STANISZ // Armenian Journal of Physics [Dokument elektroniczny]. - Czasopismo elektroniczne ; ISSN 1829-1171. — 2019 — vol. 12 iss. 2, s. 218–223. — Wymagania systemowe: Adobe Reader. — Bibliogr. s. 223, Abstr. — Publikacja dostępna online od: 2019-07-16
fragment książki
#110389Data dodania: 20.12.2017
Neutronic analysis of mixed thorium-uranium fuel bundle for CANDU reactors / Mikołaj OETTINGEN, Katarzyna SKOLIK, Mateusz MALICKI // W: SEED 2017 : 2nd international conference on the Sustainable Energy and Environment Development : Kraków, Poland, 14–17 November, 2017 : book of abstracts. — Krakow : Institute for Sustainable Energy, 2017. — ISBN: 978-83-944254-4-9. — S. 76. — Bibliogr. s. 76