Assessment of Neutronic Characteristics of Accident-Tolerant Fuel and Claddings for CANDU Reactors

<div>Enrichment requirements for FCM fuel for 4044 MWh/bundle exit burnup.</div>

Science and Technology of Nuclear Installations

Figure 6: Assessment of Neutronic Characteristics of Accident-Tolerant Fuel and Claddings for CANDU Reactors 