Journal ArticleDOI
A Simple and Efficient Control Rod Cusping Model for Three-Dimensional Pin-by-Pin Core Calculations
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In this paper, a new solution for the control rod cusping problem in the three-dimensional pin-by-pin core calculation is proposed, and the current advanced nodal code resolves this issue by estimating...Abstract:
A new solution for the control rod cusping problem in the three-dimensional pin-by-pin core calculation is proposed in this paper. The current advanced nodal code resolves this issue by estimating ...read more
Citations
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Radiation Safety Information Computational Center
TL;DR: The September 2003 edition, of the International Handbook of Evaluated Criticality Safety Benchmark Experiments is scheduled to be ready for distribution on CD-ROM near the end of September.
Journal ArticleDOI
Moving meshes to solve the time-dependent neutron diffusion equation in hexagonal geometry
TL;DR: A moving mesh scheme based on hp-finite element method is proposed for the time dependent neutron diffusion equation that uses spatial meshes that change with the movement of the control rods avoiding the necessity of using equivalent material cross sections for the partially inserted cells.
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
Comparison of two three-dimensional heterogeneous variational nodal methods for PWR control rod cusping effect and pin-by-pin calculation
TL;DR: 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.
Journal ArticleDOI
A nonoverlapping local/global iterative method with 2-D/1-D fusion transport kernel and p-CMFD wrapper for transient reactor analysis
Bumhee Cho,Nam Zin Cho +1 more
TL;DR: The NLG iteration method is extended to make it capable of transient calculations of 3-D heterogeneous problems, and a neighboring spectral index (NSI) weighting method is suggested as a tool for correcting the rod cusping phenomenon for rod ejection problems.
References
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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.
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.
Journal ArticleDOI
Asymptotic Derivation of the Multigroup P1 and Simplified PN Equations with Anisotropic Scattering
TL;DR: The multigroup and P{sub 1} and simplified P {sub N} equations were shown to be a family of asymptotic approximation to the multigroup transport equation with anisotropic scattering in this article.
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.
ReportDOI
A quasi-static polynomial nodal method for nuclear reactor analysis
TL;DR: Thesis (Ph. D.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1992 as discussed by the authors, Boston, Massachusetts, United States of America, Boston, MA