Neutronic analysis of silicon carbide cladding accident-tolerant fuel assemblies in pressurized water reactors
Author:
Publisher
Springer Science and Business Media LLC
Subject
Nuclear Energy and Engineering,Nuclear and High Energy Physics
Link
http://link.springer.com/content/pdf/10.1007/s41365-019-0575-5.pdf
Reference29 articles.
1. L.J. Ott, K.R. Robb, D. Wang, Preliminary assessment of accident-tolerant fuels on LWR performance during normal operation and under DB and BDB accident conditions. J. Nucl. Mater. 448, 520–533 (2014). https://doi.org/10.1016/j.jnucmat.2013.09.052
2. S.J. Zinkle, K.A. Terrani, J.C. Gehin et al., Accident tolerant fuels for LWRs: a perspective. J. Nucl. Mater. 448, 374–379 (2014). https://doi.org/10.1016/j.jnucmat.2013.12.005
3. N.R. Brown, H. Ludewig, A. Aronson et al., Neutronic evaluation of a PWR with fully ceramic microencapsulated fuel. Part II: nodal core calculations and preliminary study of thermal hydraulic feedback. Ann. Nucl. Energy 62, 548–557 (2013). https://doi.org/10.1016/j.anucene.2013.05.027
4. N.R. Brown, H. Ludewig, A. Aronson et al., Neutronic evaluation of a PWR with fully ceramic microencapsulated fuel. Part I: Lattice benchmarking, cycle length, and reactivity coefficients. Ann. Nucl. Energy 62, 538–547 (2013). https://doi.org/10.1016/j.anucene.2013.05.025
5. H. Ahmed, K.S. Chaudri, S.M. Mirza, Comparative analyses of coated and composite UN fuel—Monte Carlo based full core LWR study. Prog. Nucl. Energy 93, 260–266 (2016). https://doi.org/10.1016/j.pnucene.2016.08.014
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