Neutronic and thermal-hydraulic feasibility studies for High Flux Isotope Reactor conversion to low-enriched uranium silicide dispersion fuel

Autor: Chandler, D., Betzler, B., Cook, D., Ilas, G., Renfro, D.
Zdroj: In Annals of Nuclear Energy August 2019 130:277-292
Databáze: ScienceDirect