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

<div>Comparison of thermal conductivity of UO<sub>2</sub> and ATF materials [<a href="/journals/stni/2018/5327146/#B1">1</a>, <a href="/journals/stni/2018/5327146/#B10">10</a>, <a href="/journals/stni/2018/5327146/#B11">11</a>, <a href="/journals/stni/2018/5327146/#B16">16</a>].</div>

Science and Technology of Nuclear Installations

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Figure 1

Figure 1: Assessment of Neutronic Characteristics of Accident-Tolerant Fuel and Claddings for CANDU Reactors 