TY - JOUR
T1 - Gemma
T2 - Development of a two-dimensional neutron transport code with the method of characteristics
AU - Reyes, Guillermo Ibarra
AU - Escamilla, Samuel Vargas
AU - Gómez Torres, Armando Miguel
AU - del Valle Gallegos, Edmundo
N1 - Publisher Copyright:
© 2018 Elsevier Ltd
PY - 2018/5
Y1 - 2018/5
N2 - This work describes the development of Gemma code, a next generation neutron transport solver capable of employing accurate solution methods with the ability to incorporating the latest computing techniques and providing a flexible developmental environment. The Gemma code is a 2D method of characteristics solver, which was written completely in the D programming language. In doing so, flexibility is provided on two fronts, for the end user and future developers. Users interact with the code through an input text file where the geometry, materials and calculation parameters are specified with input cards. This approach eliminates the need for leaning any programming language and any errors found are presented clearly.
AB - This work describes the development of Gemma code, a next generation neutron transport solver capable of employing accurate solution methods with the ability to incorporating the latest computing techniques and providing a flexible developmental environment. The Gemma code is a 2D method of characteristics solver, which was written completely in the D programming language. In doing so, flexibility is provided on two fronts, for the end user and future developers. Users interact with the code through an input text file where the geometry, materials and calculation parameters are specified with input cards. This approach eliminates the need for leaning any programming language and any errors found are presented clearly.
KW - Criticality
KW - Gemma code
KW - Method of characteristics
KW - Neutron transport
UR - http://www.scopus.com/inward/record.url?scp=85041522692&partnerID=8YFLogxK
U2 - 10.1016/j.anucene.2018.01.043
DO - 10.1016/j.anucene.2018.01.043
M3 - Artículo
AN - SCOPUS:85041522692
SN - 0306-4549
VL - 115
SP - 367
EP - 376
JO - Annals of Nuclear Energy
JF - Annals of Nuclear Energy
ER -