AZTUSIA: A new application software for Uncertainty and Sensitivity analysis for nuclear reactors

Author:

Reyes-Fuentes MelisaORCID,del-Valle-Gallegos EdmundoORCID,Duran-Gonzalez JulianORCID,Ortíz-Villafuerte Javier,Castillo-Durán Rogelio,Gómez-Torres Armando,Queral Cesar

Funder

Consejo Nacional de Ciencia y Tecnología

Secretaría de Energía de México

Publisher

Elsevier BV

Subject

Industrial and Manufacturing Engineering,Safety, Risk, Reliability and Quality

Reference61 articles.

1. Gómez-Torres AM, Puente-Espel F, del ValleGallegos E, Francois-Lacouture JL, Martin-delCampo C, Espinosa-Paredes G. Mexican platform for analysis and design of nuclear reactors. In: Proceedings of the International Congress on Advances in Nuclear Power Plants ICAPP. 2015.

2. HPC implementation in the time-dependent neutron diffusion code AZKIND;RodríguezHernández;Ann Nucl Energy,2017

3. Verification of the multi-group diffusion code AZNHEX using the OECD/NEA UAM Sodium Fast reactor Benchmark;Del ValleGallegos;Ann Nucl Energy,2018

4. Verification of AZTRAN V1.2 code with a PWR-MOX benchmark problem, Vol. 116;VallejoQuintero,2017

5. QuezadaGarcía S, EspinosaParedes G, CentenoPérez J, SánchezMora H. Elcódigo AZTHECA. In: Proceedings of the: XXVIII Congreso Anual de la Sociedad Nuclear Mexicana, LAS/ANS Symposium. Mexico City, Mexico, June 18–21; 2017.

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