A Composite Nodal Finite Element for Hexagons-Reference-Cited by-同舟云学术

A Composite Nodal Finite Element for Hexagons

Published:1997-10 Issue:2 Volume:127 Page:139-153
ISSN:0029-5639
Container-title:Nuclear Science and Engineering
language:en
Short-container-title:Nuclear Science and Engineering

Author:

Hennart J. P.¹,Mund E. H.²³,Del Valle E.⁴

Affiliation:

1. Universidad Nacional Autónoma de México, Departamento de Métodos Matemáticos y Numéricos Instituto de Investigaciones en Matemáticas Aplicadas y en Sistemas Apartado Postal 20-726, 01000 México D.F., Mexico

2. Université Libre de Bruxelles, Service de Métrologie Nucléaire Faculté des Sciences Appliquées, B-1050 Bruxelles, Belgium

3. Université Catholique de Louvain, Unité de Thermodynamique Faculté des Sciences Appliquées, B-1348 Louvain-la-Neuve, Belgium

4. Instituto Politécnico Nacional, Departamento de Ingeniería Nuclear Escuela Superior de Física y Mathemáticas Unidad Profesional “Adolfo López Mateos,” 07738 México D.F., Mexico

Publisher

Informa UK Limited

Subject

Nuclear Energy and Engineering

Link

https://www.tandfonline.com/doi/pdf/10.13182/NSE97-A28593

Reference23 articles.

1. Progress in nodal methods for the solution of the neutron diffusion and transport equations

2. Solution of the neutron diffusion equation in hexagonal geometries

3. R. D. LAWRENCE, “The DEF3D Nodal Neuronics Option for Two- and Three-Dimensional Diffusion Theory Calculations in Hexagonal Geometry,” ANL-83-1, Argonne National Laboratory (1983).

4. Three-Dimensional Nodal Diffusion and Transport Theory Methods for Hexagonal-zGeometry

5. Comments on the Treatment of Transverse Leakage in Advanced Nodal Codes for Hexagonal Nodes

Cited by 8 articles. 订阅此论文施引文献订阅此论文施引文献，注册后可以免费订阅5篇论文的施引文献，订阅后可以查看论文全部施引文献

1. High-Order Finite Element Second Moment Methods for Linear Transport;Nuclear Science and Engineering;2023-09-29

2. High-Order Mixed Finite Element Variable Eddington Factor Methods;Journal of Computational and Theoretical Transport;2023-02-23

3. Initial verification of AZNHEX hexagonal-z neutron diffusion code with MCNP6 for two different study cases;Progress in Nuclear Energy;2018-07

4. Lumping Techniques for Mixed Finite Element Diffusion Discretizations;Journal of Computational and Theoretical Transport;2018-05-08

5. Verification of the multi-group diffusion code AZNHEX using the OECD/NEA UAM Sodium Fast Reactor Benchmark;Annals of Nuclear Energy;2018-04