PL EN


Preferences help
enabled [disable] Abstract
Number of results
2015 | 128 | 4 | 548-551
Article title

Creep Behaviour of a Zr-1 wt% Nb Alloy at Elevated Temperatures

Content
Title variants
Languages of publication
EN
Abstracts
EN
This paper presents experimental data regarding creep behaviour of a Zr-1 wt% Nb alloy at elevated (623 K) and at high temperatures (873-1123 K) corresponding to loss-of-cooling situation of fuel cladding tubes for nuclear reactors. For an elaboration of methodological procedure and comparison purposes, the tensile creep tests were conducted using both constant stress and constant load over a wide range of applied stress. The substantial differences in the acquired creep data between constant stress and constant load creep testing were found especially at high stresses and large creep strain levels.
Keywords
Contributors
author
  • Institute of Physics of Materials, Academy of Sciences of the Czech Republic, Žižkova 22, 616 62 Brno, Czech Republic
  • CEITEC-IPM, Institute of Physics of Materials, Academy of Sciences of the Czech Republic, Žižkova 22, 616 62 Brno, Czech Republic
  • Institute of Physics of Materials, Academy of Sciences of the Czech Republic, Žižkova 22, 616 62 Brno, Czech Republic
author
  • Institute of Physics of Materials, Academy of Sciences of the Czech Republic, Žižkova 22, 616 62 Brno, Czech Republic
author
  • Institute of Physics of Materials, Academy of Sciences of the Czech Republic, Žižkova 22, 616 62 Brno, Czech Republic
  • CEITEC-IPM, Institute of Physics of Materials, Academy of Sciences of the Czech Republic, Žižkova 22, 616 62 Brno, Czech Republic
References
  • [1] E. Perez-Ferö, C. Györi, L. Matus, L. Vasáros, Z. Hözer, P. Windberg, L. Maróti, M. Horváth, I. Nagy, A. Pintér-Csordás, T. Novotny, J. Nucl. Mater. 397, 48 (2010), doi: 10.1016/j.jnucmat.2009.12.005
  • [2] M. Négyesi, O. Bláhová, J. Adámek, J. Siegl, A. Přibyl, V. Vrtílková, J. Nucl. Mater. 416, 298 (2011), doi: 10.1016/j.jnucmat.2011.06.015
  • [3] M. Pahutová, J. Čadek, Mater. Sci. Eng. 11, 151 (1973), doi: 10.1016/0025-5416(73)90061-X
  • [4] M.E. Kassner, M.T. Perez-Prado, T.A. Haynes, L. Jiang, S.R. Barrabes, I.F. Lee, J. Mater. Sci. 48, 4492 ( 2013), doi: 10.1007/s10853-012-7060-4
  • [5] T.A. Hayes, M.E. Kassner, R.S. Rosen, Metall. Mater. Trans. 33A, 337 (2002), doi: 10.1007/s11661-002-0095-4
  • [6] T.A. Hayes, M.E. Kassner, Metall. Mater. Trans. 37A, 2389 (2006), doi: 10.1007/BF02586213
  • [7] I. Charif, K.L. Murty, J. Nucl. Mater. 374, 354 (2008), doi: 10.1016/j.jnucmat.2007.08.019
  • [8] W. Li, R.A. Holt, J. Nucl. Mater. 401, 25 (2010), doi: 10.1016/j.jnucmat.2010.03.015
  • [9] D. Kaddour, A.F. Gourgues-Lorenzon, J.C. Brachet, L. Portier, A. Pineau, J. Nucl. Mater. 408, 116 (2011), doi: 10.1016/j.jnucmat.2010.11.025
  • [10] V. Sklenička, L. Kloc, in: Power Plant Life Management and Performance Improvement, Ed. J.E. Oakey, Woodhead Publ., Oxford 2011, p. 180
Document Type
Publication order reference
Identifiers
YADDA identifier
bwmeta1.element.bwnjournal-article-appv128n419kz
JavaScript is turned off in your web browser. Turn it on to take full advantage of this site, then refresh the page.