Author:
Feria F.,Aguado C.,Benavides J.,Benavides J.,Canencia-Hernanz R.,Cristobal-Beneyto M.,Fernández García J.,Galán H.,González C.,Hernandez-Avellaneda A.,Herranz L.E.,Jimenez G.,Martínez L.,Martinez-Murillo J.C.,Milena-Pérez A.,Palacio Alonso A.,Penalva J.,Plaza R.,Perez-Gallego D.,Rey L.,Rodriguez-Villagra N.,Ruiz-Hervias J.,Saiz de Omeñaca Tijero J.,Viñas-Peña P.
Subject
Mechanical Engineering,Waste Management and Disposal,Safety, Risk, Reliability and Quality,General Materials Science,Nuclear Energy and Engineering,Nuclear and High Energy Physics
Reference62 articles.
1. 10 CFR 72, 1999. Licensing requirements for the independent storage of spent nuclear fuel, high-level radioactive waste, and reactor-related greater than class C waste. Code of Federal Regulations (CFR) Title 10, Energy, Part 72. [WWW Document]. URL https://www.nrc.gov/reading-rm/doc-collections/cfr/part072/index.html.
2. Ascarza, A., Cerracín, A., Muñoz, J., Carrilho, L., Pan, G., 2017. Assessment of the integrity of the fuel rod with spalled oxide under hypothetical transportation accidents, in: Top Fuel 2017. Jeju, p. A-253.
3. Methodology for spent fuel dry cask thermal-hydraulics analysis for long term storage;Benavides,2021
4. Methodology for thermal analysis of spent nuclear fuel dry cask using CFD codes;Benavides;Ann. Nucl. Energy,2019
5. Thermo-mechanical analysis of a nuclear spent fuel dry cask using CFD results in a FE code;Benavides;Nucl. Eng. Des.,2021
Cited by
1 articles.
订阅此论文施引文献
订阅此论文施引文献，注册后可以免费订阅5篇论文的施引文献，订阅后可以查看论文全部施引文献