journal article·2014-10

Effect of creep and α-Zr ↔ (α + β)-Zr transition in Zr1Nb cladding on texture analyzed by neutron diffraction

Ivan Vetvicka

Journal of Nuclear Materials· Volume 453· Issue 1-3
Publisher page

Abstract

Abstract Zr1Nb alloy tubes used as nuclear fuel cladding in VVER reactors were deformed by isothermal creep under a temperature comprised between 350 °C and 850 °C and constant tensile stress of 5–200 MPa in axial direction (AD). Deformation texture was analyzed by neutron diffraction. Two types of texture were found. For the final type of texture, the test temperature was the decisive factor. Within the temperature range up to 600 °C, the effect of creep or plastic deformation dominates and the texture changes continuously with increasing deformation. The influence of the ratio of wall thickness reduction to diameter reduction (Rw/Rd) on texture originated by plastic deformation by compression of seamless tubes made of elemental zirconium or Zircaloy described by Tenckhoff (2005), was verified for textures formed by creep of cladding tubes made of Zr1Nb alloy (E110) by constant tensile stress at the 350–600 °C range. At 700 °C temperature or higher, the texture was formed mainly by reversible α-Zr ↔ (α + β)-Zr phase transition of significant proportion of zirconium crystals and the formation of a new texture was observed: The highest pole density in the TD have been observed for the pyramid ( 1 0 1 ¯ 1 ) followed by the prism ( 1 0 1 ¯ 0 ), which can be the effect of { 1 1 2 ¯ 1 } 〈 1 ¯ 1 ¯ 2 6 〉 twining. The prism ( 1 1 2 ¯ 0 ) rotates preferentially perpendicular to AD, while the pole density of prism ( 1 0 1 ¯ 0 ) is markedly low.
Source: openaire · Quality: candidate unverified · Source record ↗

Research context

OpenAlex topics: Nuclear Materials and Properties · Titanium Alloys Microstructure and Properties · Fusion materials and technologies

SciVX discovery tags are terminology-based. OpenAlex topics are source-provided classifications.

References (18)

Show source-provided references
1. Lee · 2007
2. L. Yegorova, K. Lioutov, N. Jouravkova, A. Konobeev, Experimental study of embrittlement of Zr – 1% Nb VVER cladding under LOCA – relevant conditions, International Agreement Report, United States Nuclear Regulatory Commission, Washington, 2005.
3. Sabol · J. ASTM Int. · 2005 · 2 · 310.1520/JAI12942 ↗
4. Foster · J. ASTM Int. · 2008 · 5 · 1310.1520/JAI101188 ↗
5. Bossis · J. ASTM Int. · 2006 · 3 · 49410.1520/JAI12404 ↗
6. J. Veselý, V. Hamouz, B. Ransdorfová, Behaviour of spent fuel from VVER-440 nuclear reactors under abnormal conditions of dry storage, UJP PRAHA a.s. Research Report 857, Prague, 1998 (in Czech).
7. J. Veselý, Creep and oxidation behaviour of unirradiated Zr1Nb and zircaloy-4 cladding during dry storage of spent nuclear fuel, UJP PRAHA a.s. Research Report 897, Prague, 1999 (in Czech).
8. Tenckhoff · 1988
9. Tenckhoff · J. ASTM Int. · 2005 · 2 · 2510.1520/JAI12945 ↗
10. Tenckhoff · J. Nucl. Mater. · 1970 · 35 · 1410.1016/0022-3115(70)90022-X ↗
11. Kim · Nucl. Eng. Des. · 2008 · 238 · 333110.1016/j.nucengdes.2008.08.013 ↗
12. V. Sklenička, K. Kuchařová, Project of creep tests of cladding tubes for light water reactors – pilot testing, ÚFM AV ČR Research Report 704309, Brno, 2009 (in Czech).
13. Harris · Philos. Mag. Ser. · 1952 · 336 · 11310.1080/14786440108520972 ↗
14. Dlouhá · Solid State Phenom. · 2005 · 105 · 29710.4028/www.scientific.net/SSP.105.297 ↗
15. Krůželová · Mater. Struct. · 2011 · 18 · 184
16. Cheadle · J. Nucl. Mater. · 1967 · 23 · 19910.1016/0022-3115(67)90065-7 ↗
17. Kaddour · J. Nucl. Mater. · 2011 · 408 · 11610.1016/j.jnucmat.2010.11.025 ↗
18. Négyesi · J. Nucl. Mater. · 2012 · 420 · 31410.1016/j.jnucmat.2011.10.022 ↗