- J. Böhmert, M. Dietrich, J. Linek, Comparative studies on high-temperature corrosion of Zr–1%Nb and Zircaloy-4, Nucl. Eng. Des. 147, 53 (1993) [CrossRef]
- L. Yegorova, K. Lioutov, N. Jouravkova, A. Knobeev, V. Smirnov, V. Chesanov, A. Goryachev, Experimental study of embrittlement of Zr–1%Nb VVER cladding under LOCA-Relevant conditions, NUREG/IA-0211, IRSN 2005-194, March 2005
- Y.K. Bibilashvili, N.B. Sokolov, L.N. Andreyeva-Andrievskaya, A.V. Salatov, High temperature interaction of fuel rod cladding material (Zr1%Nb alloy) with oxygen-containing mediums, IAEA-TEDOC-921 (IAEA, 1995)
- M. Grosse, Comparison of the high-temperature steam oxidation kinetics of advanced cladding materials, Nucl. Technol. 170, 272 (2010) [CrossRef]
- M. Steinbruck, J. Borchley, A.V. Goryachev, M. Grosse, T.J. Haste, Z. Hozer, A.E. Kisselev, V.I. Nalivaev, V.P. Semishkin, L. Sepold, J. Stuckert, N. Ver, M.S. Veshchunov, Status of studies on high-temperature oxidation and quench behaviour of zircaloy-4 and E110 cladding alloys, presented at 3rd European Rev. Mtg. Severe Accident Research (ERMSAR-2008), Nessebar, Bulgaria (2008)
- Z. Hozér, E. Perez-Fero, T. Novotny, I. Nagy, M. Horváth, A. Pintér-Csirdás, A. Vimi, M. Kunstár, T. Kemény, Experimental comparison of the behavior of E110 and E110G claddings at high temperature, in Zirconium in the nuclear industry: 17th International Symposium, STP 1543 (2015), pp. 932–951
- J. Sopoušek, Phase diagrams selected alloys based on system Zr–Nb–Fe–O–H, Research report, in Czech language, Brno, 2015
- V.I. Solyany, Yu.K. Bibilashvili, V.Yu. Tonkov, High temperature oxidation and deformation of Zr1%Nb alloy claddings of WWER fuels, in Proceedings, OECD-NEA-CSNI/IAEA Specialists’ Meeting on Water Reactor Fuel Safety and Fission Product Release in Off-Normal and Accident Conditions, Riso, Denmark, 16–20 May 1983 (1983), p. 163
- P. Van Uffelen, C. Gyori, A. Schubert, J. van de Laar, Z. Hózer, G. Spykman, Extending the application range of a fuel performance code from normal to operating to design basis accident conditions, J. Nucl. Mater. 383, 137 (2008) [CrossRef]
- J.V. Cathcart, Quarterly Progress Report on the Zirconium Metal-Water Oxidation Kinetics Program Sponsored by the NRC Division of Reactor Safety Research for April–June 1976, ORNL/NUREG/TM-41 (Oak Ridge National Laboratory, 1976)
- L. Baker, L.C. Just, Studies of metal-water reactions at high temperatures (Argonne National Laboratory, ANL-6548, 1962) [CrossRef]
- S. Leistikow, G. Schanz, High temperature oxidation of zircaloy-4 cladding tubes in steam (600–1600 °C), in 9th International Congress on Metallic Corrosion, Toronto, Canada, 3–7 June 1984 (1984), pp. 282–287
EPJ Nuclear Sci. Technol.
Volume 3, 2017
|Number of page(s)||6|
|Published online||14 June 2017|
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