...A. Ya. Rogozyanov; G. P. Kobylyansky; A. A. Nuzhdov The objective of this work was to study the irradiation-thermal creep behavior of cladding tubes made of two Russian zirconium alloys: the widely used E110 (Zr-1Nb) alloy and the advanced E635 (Zr-1Nb-1.2Sn-0.35Fe); and to demonstrate...

.... , Nikulina , A. V. , and Reshetnikov , N. G.   Zirconium Alloys for the Nuclear Energetics , Energoatomizdat , Moscow , 1994 (in Russian). Zavodchikov , S. Y. , Zuev , L. B. , Belov , V. I. , Lositskiy , A. F. , and Shevnin , Y. P. , “ Plastic Deformation and Fracture...

... phenomenon. 15 03 2004 23 02 2005 22 06 2005 dislocation channeling irradiation loop internal stress zirconium alloy 2004-06-13 - 2004-06-15 Zirconium in the Nuclear Industry: Fourteenth International Symposium References Geyer , P. , Feaugas , X...

... 2004 29 12 2004 08 06 2005 zirconium alloy strain rate plasticity resistance to deformation hot extrusion 2004-06-13 - 2004-06-15 Zirconium in the Nuclear Industry: Fourteenth International Symposium References “ The Method of Manufacturing of Tubing from Zirconium...

..., dimensional change, zirconium alloy, irradiationthermal creep, creep model, irradiation growth Introduction A change in the dimensions of VVER fuel rods (decrease of the cladding diameter, elongation of fuel rod length) can result in some negative consequences: fuel rod loosening in spacer grids, decrease...

... the hydrided materials become brittle at a lower weight gain than as-received materials; this embrittlement is due both to an intrinsic hydrogen-embrittlement effect and to the oxygen content increase resulting from the effect of hydrogen on its solubility in prior-Beta phase. LOCA zirconium alloy creep...

... on these results, a tentative hydrogen absorption mechanism is proposed, explaining both roles of the electrochemical potential gradient over oxide film and the SPP window for the hydrogen absorption. 15 03 2004 22 06 2004 01 11 2004 hydrogen absorption corrosion zirconium alloy...