Numerical analysis of the 2D C5G7 MOX benchmark using PL equations and a nodal collocation method-Reference-Cited by-同舟云学术

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Numerical analysis of the 2D C5G7 MOX benchmark using PL equations and a nodal collocation method

Published:2018-04 Issue: Volume:114 Page:32-41
ISSN:0306-4549
Container-title:Annals of Nuclear Energy
language:en
Short-container-title:Annals of Nuclear Energy

Author:

Capilla M.T.,Talavera C.F.,Ginestar D.,Verdú G.

Funder

Spanish Ministerio de Economía

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference36 articles.

1. DANTSYS: A Diffusion Accelerated Neutral Particle Transport Code System. LA-12969-M;Alcouffe,1995

2. PETSc Users Manual. Technical Report ANL-95/11 – Revision 3.7;Balay,2016

3. The simplified P3 approximation;Brantley;Nucl. Sci. Eng.,2000

4. MCNP–A General Monte Carlo N-particle Transport Code, version 4C. Technical Report LA-13709-M;Briesmeister,2000

5. Forms of Approximate Radiation Transport. Tech. Report SAND2002-1778;Brunner,2002

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2. Validation of the SHNC time-dependent transport code based on the spherical harmonics method for complex nuclear fuel assemblies;Journal of Computational and Applied Mathematics;2020-09

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