Journal ArticleDOI
Comparison of two three-dimensional heterogeneous variational nodal methods for PWR control rod cusping effect and pin-by-pin calculation
TLDR
In this paper, two heterogeneous nodal methods based on the Variational Nodal Method (VNM) with diffusion approximation in three-dimensional Cartesian geometry are investigated with a code named Violet-Het3D for PWR control rod cusping effect and pin-by-pin calculation.About:
This article is published in Progress in Nuclear Energy.The article was published on 2017-11-01. It has received 10 citations till now.read more
Citations
More filters
Journal ArticleDOI
An improved variational nodal method for the solution of the three-dimensional steady-state multi-group neutron transport equation
TL;DR: In this article, an improved variational nodal method is presented for the solution of the three-dimensional (3D) steady-state multi-group neutron transport equation, where 3D orthogonal polynomials are used to approximate the spatial flux distribution within nodes and across the nodal interfaces.
Journal ArticleDOI
Control rod treatment for FEM based radiation transport methods
Sebastian Schunert,Yaqi Wang,Javier Ortensi,Vincent Laboure,Frederick N. Gleicher,Mark DeHart,Richard C. Martineau +6 more
TL;DR: It is demonstrated that the smoothly varying cross sections can be obtained by projecting the piecewise set of cross sections onto the set of Legendre polynomials up to a finite order and provided accurate results based on the C5G7-TD benchmark.
Journal ArticleDOI
Development and implementation of an integral variational nodal method to the hexagonal geometry nuclear reactors
TL;DR: In this article, a variational nodal method utilizing an integral form of the with-in node angular flux distribution was proposed to generate response matrices more efficiently. But, the results of the proposed method were limited to the TAKEDA-4 benchmark cases.
Journal ArticleDOI
Application of stiffness confinement method within variational nodal method for solving time-dependent neutron transport equation
TL;DR: In this article , the stiffness confinement method (SCM) is implemented in the variational nodal method (VNM) framework to solve time-dependent multi-group neutron transport equations.
Journal ArticleDOI
Validation of NECP-Bamboo with BEAVRS and AP1000 measurements
TL;DR: In this paper, the BEAVRS is used to validate the NECP-Bamboo fuel management code system, including critical boron concentration (CBC), control rod worth, temperature coefficient, detector response, and letdown curve.
References
More filters
Book
An Introduction to the Finite Element Method
TL;DR: Second-order Differential Equations in One Dimension: Finite Element Models (FEM) as discussed by the authors is a generalization of the second-order differential equation in two dimensions.
Book
The Finite Element Method: Its Basis and Fundamentals
TL;DR: The Finite Element Method: Its Basis and Fundamentals offers a complete introduction to the basis of the finite element method, covering fundamental theory and worked examples in the detail required for readers to apply the knowledge to their own engineering problems and understand more advanced applications.
Journal ArticleDOI
Assembly homogenization techniques for light water reactor analysis
TL;DR: In this paper, the development and application of advanced assembly homogenization methods for light water reactor analysis is reviewed and numerical examples given, as well as practical difficulties arising from conventional flux-weighting approximations are discussed.
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
Advanced PWR Core Calculation Based on Multi-group Nodal-transport Method in Three-dimensional Pin-by-Pin Geometry
Masahiro Tatsumi,Akio Yamamoto +1 more
TL;DR: In this paper, a parallel production code, SCOPE2, has been developed for advanced calculations in the reactor core design of PWRs, where the multi-group diffusion and SP3 transport equations are solved by the Red/Black iterative method within the framework of the finite difference method or the advanced nodal method without non-linear iterations.
Related Papers (5)
Cell homogenization methods for pin-by-pin core calculations tested in slab geometry
Global/local iterative methods for equivalent diffusion theory parameters in nodal calculation
Hark Rho Kim,Nam Zin Cho +1 more