Open AccessThree-dimensional time-dependent neutron diffusion simulation using average current nodal expansion method
Author(s) -
Kambiz Valavi,
Ali Pazirandeh,
Gholamreza Jahanfarnia
Publication year - 2020
Publication title -
nuclear technology and radiation protection
Language(s) - English
Resource type - Journals
SCImago Journal Rank - 0.31
H-Index - 16
eISSN - 1452-8185
pISSN - 1451-3994
DOI - 10.2298/ntrp2003189v
Subject(s) - neutron transport , discretization , transient (computer programming) , nuclear reactor core , nuclear reactor , diffusion , diffusion equation , steady state (chemistry) , work (physics) , blanket , nuclear engineering , computer science , neutron , mathematics , physics , mathematical analysis , materials science , nuclear physics , thermodynamics , chemistry , economy , engineering , economics , service (business) , operating system , composite material
In this work, the average current nodal expansion method was developed for the time-dependent neutronic simulation of transients in a nuclear reactor's core. For this purpose, an adopted iterative algorithm was proposed for solving the 3-D time-dependent neutron diffusion equation. In the average current nodal expansion method, the domain of the reactor core can be modeled by coarse meshes for neutronic calculation associated with reasonable precision of results. The discretization of time differential terms in the time-dependent equations was fulfilled, according to the implicit scheme. The proposed strategy was implemented in some kinetic problems including an infinite slab reactor, TWIGL 2-D seed-blanket reactor, and 3-D LMW LWR. At first, the steady-state solution was carried out for each test case, and then, the dynamic neutronic calculation was performed during the time for a specified transient scenario. Obtained results of static and dynamic solutions were verified in comparison with well-known references. Results can indicate the ability of the developed calculator to simulate transients in a nuclear reactor's core.