Open AccessNumerical calculation of spectral problems in SP3 approximation by FEM
Author(s) -
Alexander O. Vasilev,
Alexander V. Avvakumov,
V. F. Strizhov,
Petr N. Vabishchevich
Publication year - 2019
Publication title -
journal of physics. conference series
Language(s) - English
Resource type - Journals
SCImago Journal Rank - 0.21
H-Index - 85
eISSN - 1742-6596
pISSN - 1742-6588
DOI - 10.1088/1742-6596/1392/1/012076
Subject(s) - neutron transport , diffusion , neutron , work (physics) , finite element method , convection–diffusion equation , heavy traffic approximation , transient (computer programming) , diffusion theory , physics , mathematics , diffusion equation , computational physics , mathematical analysis , computer science , nuclear physics , thermodynamics , discrete mathematics , engineering , metric (unit) , operations management , operating system
The SP 3 approximation of the neutron transport equation allows improving the accuracy for both static and transient simulations for reactor core analysis compared with the neutron diffusion theory. Besides, the SP 3 calculation costs are much less than higher order transport methods (S N or P N ). Another advantage of the SP 3 approximation is a similar structure of equations that is used in the diffusion method. Therefore, there is no difficulty to implement the SP 3 solution option to the multi-group neutron diffusion codes. In this work, the application of the SP 3 methodology based on solution of the - and -spectral problems has been tested for reactor benchmarks. The FEM is chosen to achieve the geometrical generality. The results calculated with the diffusion and SP 3 methods are compared with the reference calculation results.