Subject
Mechanical Engineering,Waste Management and Disposal,Safety, Risk, Reliability and Quality,General Materials Science,Nuclear Energy and Engineering,Nuclear and High Energy Physics
Reference14 articles.
1. STH-CFD codes coupled calculations applied to HLM loop and pool systems;Angelucci;Sci. Technol. Nucl. Installations,2017
2. Heat transfer on HLM cooled wire-spaced fuel pin bundle simulator in the NACIE-UP facility;Di Piazza;Nucl. Eng. Des.,2016
3. Technology Roadmap Update for Generation IV Nuclear Energy Systems;Generation IV International Forum,2014
4. Kazimi, M.S., Carelli, M.D., 1976. Clinch River Breeder Reactor Plant Heat Transfer Correlation for Analysis of CRBRP Assemblies, Westinghouse, CRBRP-ARD-0034.
5. Martelli, D., Forgione, N., Barone, G., Del Nevo, A., Di Piazza, I., Tarantino, M., 2014. Coupled simulation of natural and forced circulation tests in nacie facility using Relap5 and ansys fluent codes. In: Proceedings of International Conference On Nuclear Engineering, ICONE22, Prague, pp. 1–10.
Cited by
15 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