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Preconditioned Multigroup GMRES Algorithms for the Variational Nodal Method
Nuclear Science and Engineering, 2015Combinations of three approaches are examined as options to replace the algorithms presently employed in the variational nodal code VARIANT.
Yunzhao Li +4 more
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Computer Physics Communications, 2022
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Wei Xiao +6 more
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zbMATH Open Web Interface contents unavailable due to conflicting licenses.
Wei Xiao +6 more
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Annals of Nuclear Energy, 2022
Abstract High Flux Engineering Test Reactor (HFETR) focuses on the irradiation test of reactor fuel elements, thus the accurate determination of power or flux distribution becomes important. Since HFETR contains complex geometry assembly and different types of irradiation channels, the traditional simulation methods such as Monte Carlo method and ...
Kun Zhuang +8 more
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Abstract High Flux Engineering Test Reactor (HFETR) focuses on the irradiation test of reactor fuel elements, thus the accurate determination of power or flux distribution becomes important. Since HFETR contains complex geometry assembly and different types of irradiation channels, the traditional simulation methods such as Monte Carlo method and ...
Kun Zhuang +8 more
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Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, 2022
Abstract This paper presents an implementation of the stiffness confinement method in the framework of the variational nodal method (VNM) to solve time-dependent pin resolved neutron transport equations. With frequency-transform, the time-dependent neutron transport equation is decoupled from the precursor equation and transformed into a
Wei Xiao +4 more
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Abstract This paper presents an implementation of the stiffness confinement method in the framework of the variational nodal method (VNM) to solve time-dependent pin resolved neutron transport equations. With frequency-transform, the time-dependent neutron transport equation is decoupled from the precursor equation and transformed into a
Wei Xiao +4 more
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Finite element, nodal and response matrix methods: A variational synthesis for neutron transport
Progress in Nuclear Energy, 1986Abstract The variational principle used to derive finite element approximations to the even-parity neutron transport equation is modified to include the odd parity flux as a Lagrange multiplier along the interelement boundaries. The result is a functional that guarantees nodal balance over each element or node, regardless of the form of the space ...
E.E. Lewis, I. Dilber
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Nuclear Science and Engineering, 2001
Numerical methods based on transformation of variables are developed to improve the computational efficiency of the variational nodal method (VNM). Reordering and orthogonal transformations of the nodal unknowns are found to reduce the coefficient matrices of VNM into block-diagonal forms.
W. S. Yang, G. Palmiotti, E. E. Lewis
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Numerical methods based on transformation of variables are developed to improve the computational efficiency of the variational nodal method (VNM). Reordering and orthogonal transformations of the nodal unknowns are found to reduce the coefficient matrices of VNM into block-diagonal forms.
W. S. Yang, G. Palmiotti, E. E. Lewis
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Nuclear Science and Engineering, 2002
A new nodal diffusion method for the neutronics analysis of light water reactor cores has been developed. The method is based on an expansion of neutron fluxes within a node into a series of functions that are numerically obtained from single-assembly calculations without the process of assembly homogenization.
Makoto Tsuiki, Sverre Hval
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A new nodal diffusion method for the neutronics analysis of light water reactor cores has been developed. The method is based on an expansion of neutron fluxes within a node into a series of functions that are numerically obtained from single-assembly calculations without the process of assembly homogenization.
Makoto Tsuiki, Sverre Hval
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Nuclear Science and Engineering, 1992
The variational nodal transport method is generalized for the effective treatment of multigroup criticality problems in two and three dimensions.
C. B. Carrico, E. E. Lewis, G. Palmiotti
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The variational nodal transport method is generalized for the effective treatment of multigroup criticality problems in two and three dimensions.
C. B. Carrico, E. E. Lewis, G. Palmiotti
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Interface Angular Coupling Reductions in Variational Nodal Methods for Neutron Transport
Nuclear Science and Engineering, 1989Variational nodal methods for neutron transport are modified to reduce the angular coupling between spatial nodes without a commensurate loss of accuracy. In both one and two dimensions, the interfact conditions of the variational principle allow near P/sub n/ accuracy to be obtained with only P/sub n-2/ interface coupling.
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