Fast reactor core analysis using AZNHEX neutron diffusion code

Juan Galicia-Aragón; Juan Luis François; Guillermo Elías Bastida-Ortiz; Edmundo Del-Valle-Gallegos; Armando Gomez-Torres

Fast reactor core analysis using AZNHEX neutron diffusion code

Juan Galicia-Aragón, Juan Luis François, Guillermo Elías Bastida-Ortiz, Edmundo Del-Valle-Gallegos, Armando Gomez-Torres

Escuela Superior de Física y Matemáticas (ESFM)

Research output: Contribution to journal › Conference article › peer-review

Translated title of the contribution	Análisis rápido del núcleo del reactor utilizando el código de difusión de neutrones AZNHEX
Original language	English
Pages (from-to)	1213-1216
Number of pages	4
Journal	Transactions of the American Nuclear Society
Volume	116
State	Published - 2017
Event	2017 Transactions of the American Nuclear Society, ANS 2017 - San Francisco, United States Duration: 11 Jun 2017 → 15 Jun 2017

Cite this

@article{7c56ff85003b4e088831fd88ff9f9d57,

title = "Fast reactor core analysis using AZNHEX neutron diffusion code",

author = "Juan Galicia-Arag{\'o}n and Fran{\c c}ois, {Juan Luis} and Bastida-Ortiz, {Guillermo El{\'i}as} and Edmundo Del-Valle-Gallegos and Armando Gomez-Torres",

note = "Funding Information: The authors acknowledge the financial support from the National Strategic Project No. 212602 (AZTLAN Platform) as part of the Sectorial Fund for Energetic Sustainability CONACYT – SENER.; 2017 Transactions of the American Nuclear Society, ANS 2017 ; Conference date: 11-06-2017 Through 15-06-2017",

year = "2017",

language = "Ingl{\'e}s",

volume = "116",

pages = "1213--1216",

journal = "Transactions of the American Nuclear Society",

issn = "0003-018X",

}

TY - JOUR

T1 - Fast reactor core analysis using AZNHEX neutron diffusion code

AU - Galicia-Aragón, Juan

AU - François, Juan Luis

AU - Bastida-Ortiz, Guillermo Elías

AU - Del-Valle-Gallegos, Edmundo

AU - Gomez-Torres, Armando

N1 - Funding Information: The authors acknowledge the financial support from the National Strategic Project No. 212602 (AZTLAN Platform) as part of the Sectorial Fund for Energetic Sustainability CONACYT – SENER.

PY - 2017

Y1 - 2017

UR - http://www.scopus.com/inward/record.url?scp=85033476931&partnerID=8YFLogxK

M3 - Artículo de la conferencia

AN - SCOPUS:85033476931

SN - 0003-018X

VL - 116

SP - 1213

EP - 1216

JO - Transactions of the American Nuclear Society

JF - Transactions of the American Nuclear Society

T2 - 2017 Transactions of the American Nuclear Society, ANS 2017

Y2 - 11 June 2017 through 15 June 2017

ER -

Fast reactor core analysis using AZNHEX neutron diffusion code

Other files and links

Cite this