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

<div>Radial distribution of <sup>239</sup>Pu.</div>

Science and Technology of Nuclear Installations

Figure 15: Neutronic Analysis on Potential Accident Tolerant Fuel-Cladding Combination U<sub>3</sub>Si<sub>2</sub>-FeCrAl 