1. Development of advanced accident-tolerant fuels for commercial LWRs;Bragg-Sitton;Nucl. News,2014
2. Neutronic performance of uranium nitride composite fuels in a PWR;Brown;Nucl. Eng. Des.,2014
3. Overview of the U.S. DOE Accident Tolerant Fuel Development Program;Carmack,2013
4. Chadwick, M., Herman, M., Obložinský, P., et al., 2011. ENDF/B-VII.1 nuclear data for science and technology: cross sections, covariances, fission product yields and decay data. Nuclear Data Sheets 112, 2887-2996. Special Issue on ENDF/B-VII.1 Library.
5. Chen, S., Yuan, C., 2017. Neutronic Analysis on Potential Accident Tolerant Fuel-Cladding Combination U3Si2-FeCrAl.https://www.hindawi.com/journals/stni/2017/3146985/abs/.