Journal ArticleDOI
An IFDF accelerated parallel nodal SN method for XYZ geometry in SARAX code system
TLDR
In this article, a simplified method to calculate the high-order transverse leakage terms was proposed based on the NEFD nodal SN scheme in XYZ geometry, which was used to solve the discretization system of a small fast reactor and the ZPPR-10B large fast reactor.About:
This article is published in Annals of Nuclear Energy.The article was published on 2022-02-01. It has received 1 citations till now. The article focuses on the topics: Computer science & Neutron transport.read more
Citations
More filters
Journal ArticleDOI
A Stable Condition and Adaptive Diffusion Coefficients for the Coarse-Mesh Finite Difference Method
TL;DR: In this paper , an adaptive diffusion coefficient equation is proposed to improve the stability of the coarse-mesh finite difference (CMFD) method and the corresponding revised CMFD method is called the rCMFD method, which was implemented in the hexagonal-Z nodal SN (discrete-ordinates) solver in the NECP-SARAX code system.
References
More filters
Journal ArticleDOI
Progress in nodal methods for the solution of the neutron diffusion and transport equations
TL;DR: In contrast with earlier nodal simulators, more recent nodal diffusion methods are characterized by the systematic derivation of spatial coupling relationships that are entirely consistent with the multigroup diffusion equation as discussed by the authors, which most often are derived by developing approximations to the one-dimensional equations obtained by integrating the multidimensional diffusion equation over directions transverse to each coordinate axis.
VARIANT: VARIational Anisotropic Nodal Transport for Multidimensional Cartesian and Hexagonal Geometry Calculation
TL;DR: The Variational Anisotropic Neutron Transport (VARIANT) as discussed by the authors is a hybrid finite element method that guarantees nodal balance and permits spatial refinement through the use of hierarchical complete polynomial trial functions.
Journal ArticleDOI
3-D Neutron Transport Benchmarks
Toshikazu Takeda,Hideaki Ikeda +1 more
TL;DR: In this article, the results of k eff, control rod worth, and region-averaged group fluxes for proposed four core models calculated by various 3D transport codes have been compared.
Journal ArticleDOI
The Weighted Diamond-Difference Form of Nodal Transport Methods
TL;DR: A general order, general dimensionality nodal transport method cast in a simple, compact, singleweight, weighted diamond-difference form is derived and is a consistently formulated nodal method, which can be solved using either the discrete nodal-transport method or the nodsal-equivalent finite difference algorithms without any approximations.
Journal ArticleDOI
Three-Dimensional Nodal Diffusion and Transport Theory Methods for Hexagonal- z Geometry
TL;DR: In this article, advanced nodal methods for the solution of the multigroup neutron diffusion and transport theory equations in three-dimensional hexagonal-z geometry are described, and the code HEXNOD allows an accurat...
Related Papers (5)
Scope2: object-oriented parallel code for multi-group diffusion/transport calculations in three-dimensional fine-mesh reactor core geometry
Masahiro Tatsumi,Akio Yamamoto +1 more