Results 351 to 360 of about 1,067,811 (382)

Influencing factors and mechanism of iodine-induced stress corrosion cracking of zirconium alloy cladding: A review

International Journal of Minerals, Metallurgy, and Materials, 2022
Yusha Li, C. Ge, Yanhong Liu, Guangbin Li, Xiaoxu Dong, Zong-xi Gu, Yingchun Zhang   +6 more
semanticscholar   +1 more source

Hydride Formation in Zirconium Alloys

JOM, 2012
The ingress of hydrogen during corrosion in service can degrade the mechanical properties of zirconium alloy nuclear fuel cladding because of the formation of brittle hydrides. The formation of these hydrides is reviewed in light of recent synchrotron radiation experimental results and phase-field modeling computational results that provide new insight
Long Qing Chen, Arthur T. Motta
openaire   +2 more sources

Zirconium alloys in nuclear technology

Proceedings of the Indian Academy of Sciences Section C: Engineering Sciences, 1981
This paper describes the historical development of zirconium and its alloys as structural materials for nuclear reactors. The various problems encountered in the early stages of the development of zircaloys and their performance in reactors operating presently are described in detail. The development of Zr-2.5 % Nb alloys for pressure tube applications
Ranjani Krishnan, M. K. Asundi
openaire   +2 more sources

Welding of Zirconium Alloys

1993
Abstract Zirconium and its alloys are available in two general categories: commercial grade and reactor grade. This article discusses the welding processes that can be used for welding any of the zirconium alloys. These include gas-tungsten arc welding (GTAW), gas-metal arc welding (GMAW), plasma arc welding (PAW), electron-beam welding (
openaire   +2 more sources

Dispersion-strengthened zirconium alloys

Journal of the Less Common Metals, 1965
Abstract Inert particle strengthening concepts were extended to zirconium-base alloys. By using powder metallurgy techniques inert particles of Y2O3 were mechanically dispersed in a Zircaloy-2 matrix. Hot-hardness, elevated-temperature tensile, 343°C creep, and 400°C steam corrosion data for the resulting materials were obtained and interpreted. The
K.C. Antony, H.H. Klepfer
openaire   +2 more sources

Cracking Zirconium Alloys in Hydrogen

1984
We have loaded precracked double-cantilever-beam specimens of coldworked Zircaloy-2 and Zr-2.5Nb to a constant displacement in a hydrogen atmosphere at 290 to 420 K and measured the characteristics of crack propagation using optical and acoustic emission techniques.
CE Coleman, B Cox
openaire   +2 more sources

Zirconium and zirconium alloys

2011
Klaus John, Gundula Jänsch-Kaiser, David H. Sharp   +2 more
openaire   +1 more source

Evaluation of artifacts generated by titanium, zirconium, and titanium-zirconium alloy dental implants on MRI, CT, and CBCT images: A phantom study.

Oral surgery, oral medicine, oral pathology and oral radiology, 2019
H. Demirturk Kocasarac, G. Ustaoğlu, S. Bayrak, R. Katkar, H. Geha, S. T. Deahl, B. Mealey, M. Danacı, M. Noujeim   +8 more
semanticscholar   +1 more source

Effect of Electrolyte Composition on Protective Properties of the PEO Coating on Zr–1Nb Zirconium Alloy

Surface Engineering and Applied Electrochemistry, 2019
R. Farrakhov, E. Parfenov, V. R. Mukaeva, M. Gorbatkov, P. V. Tarasov, A. R. Fatkullin, N. Rameshbabu, B. Ravisankar   +7 more
semanticscholar   +1 more source

Superconductivity of Zirconium Alloys

Physical Review, 1955
E. Corenzwit, B.T. Matthias
openaire   +2 more sources