Metallurgical characterizations of Fe–Cr–Ni–Zr base alloys developed for geological disposal of radioactive hulls
作者： N Das , Pranesh Sengupta , S Roychowdhury , G Sharma , PS Gawde
DOI: 10.1016/J.JNUCMAT.2011.11.008
关键词: Mixed oxide 、 Non-blocking I/O 、 Zirconium 、 Metallurgy 、 Monoclinic crystal system 、 Oxide 、 Materials science 、 Alloy 、 Corrosion 、 Tetragonal crystal system
摘要: Abstract Alloy melting route is currently being considered for radioactive hulls immobilization. Towards this, wide range of alloys, belonging to Zirconium–Iron binary and Zirconium–Stainless steel pseudo-binary systems have been prepared through vacuum arc route. Detail microstructural characterization quantitative phase analyses these alloys along with interaction study between Zirconium Stainless coupons at elevated temperatures identify Zr(Fe,Cr) 2 , Zr(Fe,Cr), Zr (Fe,Cr), 3 (Fe,Ni), (Fe,Cr,Ni), β-Zr α-Zr as the most commonly occurring phases within system rich bulk compositions. Nano-indentation studies found extremely hard, (Fe,Ni) moderately ductile β-Zr, (Fe,Cr) ones among present. Steam oxidation based on weight gain/loss procedure mixed oxide layers, suggest that each responded corrosive environment differently. Fe O NiFe 4 NiO, monoclinic ZrO tetragonal are be common constituents layers developed alloys. Integrating microstructural, mechanical corrosion properties, ZrFeCrNi3 (Zr: 84.00, Fe: 11.20, Cr: 3.20, Ni: 1.60, in wt.%) identified acceptable base alloy disposal hulls.
harvard.edu
elsevier.com
sci-hub.se 参考文章(47)
Michael I Ojovan, William E Lee, Stepan N Kalmykov, An introduction to nuclear waste immobilisation ,(2005)
K. Poulard, A. Chevarier, N. Moncoffre, P. Trocellier, D. Crusset, Study of zircaloy-4 fuel cladding corrosion using ion beams.: Application to long-term disposal of nuclear wastes Nuclear Instruments & Methods in Physics Research Section B-beam Interactions With Materials and Atoms. ,vol. 181, pp. 640- 643 ,(2001) , 10.1016/S0168-583X(01)00533-X
Tracy S. Rudisill, Decontamination of Zircaloy cladding hulls from spent nuclear fuel Journal of Nuclear Materials. ,vol. 385, pp. 193- 195 ,(2009) , 10.1016/J.JNUCMAT.2008.10.016
V Grover, Ankita Banerji, P Sengupta, AK Tyagi, None, Raman, XRD and microscopic investigations on CeO2–Lu2O3 and CeO2–Sc2O3 systems: A sub-solidus phase evolution study Journal of Solid State Chemistry. ,vol. 181, pp. 1930- 1935 ,(2008) , 10.1016/J.JSSC.2008.04.001
Ludovic Bellot-Gurlet, Delphine Neff, Solenn Réguer, Judith Monnier, Mandana Saheb, Philippe Dillmann, Raman studies of corrosion layers formed on archaeological irons in various media Journal of Nano Research. ,vol. 8, pp. 147- 156 ,(2009) , 10.4028/WWW.SCIENTIFIC.NET/JNANOR.8.147
C. Rodrı́guez, D.A. Barbiric, M.E. Pepe, J.A. Kovacs, J.A. Alonso, R. Hojvat de Tendler, Metastable phase stability in the ternary Zr–Fe–Cr system Intermetallics. ,vol. 10, pp. 205- 216 ,(2002) , 10.1016/S0966-9795(01)00130-3
K Poulard, A Chevarier, N Moncoffre, D Crusset, Iodine release from oxidised Zircaloy cladding in contact with an alkaline solution Journal of Nuclear Materials. ,vol. 306, pp. 99- 104 ,(2002) , 10.1016/S0022-3115(02)00918-2
S.M. McDeavitt, D.P. Abraham, J.Y. Park, Evaluation of stainless steel zirconium alloys as high-level nuclear waste forms Journal of Nuclear Materials. ,vol. 257, pp. 21- 34 ,(1998) , 10.1016/S0022-3115(98)00433-4
M Ahmad, JI Akhter, MA Shaikh, M Akhtar, M Iqbal, MA Chaudhry, None, Hardness and microstructural studies of electron beam welded joints of Zircaloy-4 and stainless steel Journal of Nuclear Materials. ,vol. 301, pp. 118- 121 ,(2002) , 10.1016/S0022-3115(01)00757-7
V Grover, SV Chavan, P Sengupta, AK Tyagi, None, CeO2–YO1.5–NdO1.5 system: An extensive phase relation study Journal of The European Ceramic Society. ,vol. 30, pp. 3137- 3143 ,(2010) , 10.1016/J.JEURCERAMSOC.2010.06.005