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J. Berka, D. Marušáková and J. Kalivodová

LITERATURA 1. A technology roadmap for Generation IV Nuclear Energy System, U.S. DOE Nuclear Energy Research Advisory Committee and the Generation IV International Forum 2002 , [online]. http://130.88.20.21/uknuclear/pdfs/GenIV_Roadmap_September_2002.pdf ( accessed 1 Jan 2018 ). 2. Kissane M. P., Nuclear Engineering and Design 2009 , 239, 3076–3091. 3. ARCHER final meeting. [online] http://archer-project.eu/ . ( accessed 1 Jan 2018 ). 4. Berka J., Paliva 2013 , 5(4), 136–141. 5. Natesan K., Purohit A., Tam S. W., report

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J. Stoulil, M. Kouřil and D. Dobrev

Nuclear Waste Disposal Containers. Corrosion 2019 (available http://corrosionjournal.org/doi/pdf/10.5006/2994 ). 5. Rosborg, B., et al., Corrosion rate of pure copper in an oxic bentonite/saline groundwater environment. Corrosion Engineering, Science and Technology 2011 , 46 (2), 148-152. 6. Hall, D. S.; Keech, P. G., An overview of the Canadian corrosion program for the long-term management of nuclear waste. Corrosion Engineering, Science and Technology 2017 , 52 (S1), 2-5. 7. Kremer, E. P., Durability of the Canadian used fuel container

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J. Bystrianský, V. Šefl, P. Sajdl, J. Fojt and P. Bábková

-434. 7. Bystrianský,J. et al. Determination of conditions leading to localized corrosion initiation on UNS 32100 (AISI 321) stainless steels in nuclear power environments. Nuclear Engineering and Design 1995, 157, 123-136. 8. Vejvoda, S.; Bystrianský, J. Program DIALIFE _ KE; Blok - vysokoteplotní oxidace austenitických ocelí. 9. Aspden, J.D. et al. Some Aspects of Combined Oxygenated Treatment, Proceedings of VGB Conference, Mittwoch, 2001. 10. Kowaka, M. Metal Corrosion Damage and Protection Technology. Ch 5.3 Steam

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V. Šefl

References 1. Yao, J.; Munse, W. Low-cycle Fatigue of Metals. Literature Review; Defense Technical Information Center, 1961. 2. Deardorf, K. K. C. J., Fujikawa A.F. A survey of current US nuclear plant fatigue issues. 3rd International Conference on Fatigue of Reactor Componentss. 2004. 3. Materials Reliability Program: Operating Experience Regarding Thermal Fatigue of Piping Connected To PWR Reactor Coolant Systems (MRP-85). 4. Ehrnsten, U.; Ivanchenko, M.; Nevdacha, N.; Yagozinskyy, Y