AP-1000 fuel assembly performance with UO 2 and UO 2 /U 3 Si 2 fuels and silicon carbide cladding from the viewpoint of neutronics
Author:
Affiliation:
1. Reactor and Nuclear Safety Research School, Nuclear Science and Technology Research Institute (NSTRI), Tehran, Iran
Funder
no funding
Publisher
Informa UK Limited
Link
https://www.tandfonline.com/doi/pdf/10.1080/15567036.2024.2356701
Reference21 articles.
1. Comparative study of neutronic, mechanical and thermodynamic properties of accident tolerant cladding materials: SiC, TiC and ZrC
2. Assembly-level analyses of accident-tolerant cladding concepts for a long-life civil marine SMR core using micro-heterogeneous duplex fuel
3. Sensitivity neutronic analysis of accident tolerant fuel concepts in APR1400
4. Chromium-Coated Zirconium Cladding Neutronics Impact for APR-1400 Reactor Core
5. Reactor and fuel cycle performance of light water reactor fuel with 235U enrichments above 5%
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