Neutronic Analysis on Potential Accident Tolerant Fuel-Cladding Combination U<sub>3</sub>Si<sub>2</sub>-FeCrAl

<div>Concentration of <sup>239</sup>Pu for 580 and 610 K moderator temperature.</div>

Science and Technology of Nuclear Installations

Figure 12: Neutronic Analysis on Potential Accident Tolerant Fuel-Cladding Combination U<sub>3</sub>Si<sub>2</sub>-FeCrAl 