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 with different percentage of void of moderator.</div>

Science and Technology of Nuclear Installations

Figure 19: Neutronic Analysis on Potential Accident Tolerant Fuel-Cladding Combination U<sub>3</sub>Si<sub>2</sub>-FeCrAl 