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Initial verification of AZNHEX hexagonal-z neutron diffusion code with MCNP6 for two different study cases

  • Published:2018-07 Issue: Volume:106 Page:284-292
  • ISSN:0149-1970
  • Container-title:Progress in Nuclear Energy
  • language:en
  • Short-container-title:Progress in Nuclear Energy

Author:

Galicia-Aragón Juan,François Juan-LuisORCID,Bastida-Ortiz Guillermo E.,Martín-del-Campo Cecilia,Vallejo-Quintero Julio A.,del-Valle-Gallegos Edmundo

Funder

Secretaría de Energía de México

Consejo Nacional de Ciencia y Tecnología

Publisher

Elsevier BV

Subject

Waste Management and Disposal,Energy Engineering and Power Technology,Safety, Risk, Reliability and Quality,Nuclear Energy and Engineering

Reference34 articles.

1. The Consortium for Advanced Simulation of LWR's;CASL,2017

2. Review of computational methods for space-time reactor kinetics;Chae;Journal of the Korean Nuclear Society,1979

3. NURESIM – a european simulation platform for nuclear reactor safety: multi-scale and multi-physics calculations, sensitivity and uncertainty analysis;Chauliac;Nucl. Eng. Des.,2011

4. RTk/SN solutions of the two-dimensional multigroup transport equations in hexagonal geometry;Del Valle;Nucl. Sci. Eng.,2004

5. Verification of the multi-group diffusion code AZNHEX using the OECD/NEA UAM sodium fast reactor benchmark;Del Valle-Gallegos;Ann. Nucl. Energy,2018

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