Study of neutron fluxes before and after the change HEU to LEU fuel for TRIGA mark III reactor of Mexico

Subjects

Subjects :

Nuclear reactor core
Activation product
Neutron flux
Uranium-233
Nuclear engineering
Radiochemistry
Environmental science
MOX fuel
Fuel element failure
TRIGA
Thorium fuel cycle

Details

ISSN :

0094243X

Database :

OpenAIRE

Journal :

AIP Conference Proceedings

Accession number :

edsair.doi...........b095b32d9dc5e0f35a1f6394c9985462

Full Text :

https://doi.org/10.1063/1.4813460