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Kutty, T.R.G., Ganguly, C. (1993) Identation creep of Zircaloy-2 welds of nuclear fuel pins. Journal of Nuclear Materials, 207. 345-349 doi:10.1016/0022-3115(93)90279-8

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Reference TypeJournal (article/letter/editorial)
TitleIdentation creep of Zircaloy-2 welds of nuclear fuel pins
JournalJournal of Nuclear Materials
AuthorsKutty, T.R.G.Author
Ganguly, C.Author
Year1993 (December)Volume207
PublisherElsevier BV
DOIdoi:10.1016/0022-3115(93)90279-8Search in ResearchGate
Generate Citation Formats
Mindat Ref. ID4150805Long-form Identifiermindat:1:5:4150805:9
GUID0
Full ReferenceKutty, T.R.G., Ganguly, C. (1993) Identation creep of Zircaloy-2 welds of nuclear fuel pins. Journal of Nuclear Materials, 207. 345-349 doi:10.1016/0022-3115(93)90279-8
Plain TextKutty, T.R.G., Ganguly, C. (1993) Identation creep of Zircaloy-2 welds of nuclear fuel pins. Journal of Nuclear Materials, 207. 345-349 doi:10.1016/0022-3115(93)90279-8
In(1993) Journal of Nuclear Materials Vol. 207. Elsevier BV

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Kutty, T.R.G., Ganguly, C. (1991) Hot hardness and indentation creep studies on Ti modified stainless steel cladding material for nuclear fuel pins. Journal of Nuclear Materials, 182. 258-260 doi:10.1016/0022-3115(91)90437-c
Kutty, T. R. G., Ganguly, C. (1992) Indentation technique for evaluation of hot hardness and creep of SS 316 end-plug welds of nuclear, fuel pins. Journal of Materials Science, 27. 908-912 doi:10.1007/bf01197640
Kutty, T.R.G., Jarvis, T., Ganguly, C. (1997) Hot hardness and indentation creep studies on Zrî—¸1Nbî—¸1Snî—¸0.1Fe alloy. Journal of Nuclear Materials, 246 (2). 189-195 doi:10.1016/s0022-3115(97)00108-6
Kutty, T.R.G., Ganguly, C., Sastry, D.H. (1995) Thermal expansion of Alî—¸U and Alî—¸Uî—¸Zr alloys. Journal of Nuclear Materials, 226 (1). 197-205 doi:10.1016/0022-3115(95)00090-9
Kutty, T.R.G, Ravi, K, Ganguly, C (1999) Studies on hot hardness of Zr and its alloys for nuclear reactors. Journal of Nuclear Materials, 265 (1). 91-99 doi:10.1016/s0022-3115(98)00610-2
Huang, F.H. (1993) Brittle-fracture potential of irradiated Zircaloy-2 pressure tubes. Journal of Nuclear Materials, 207. 103-115 doi:10.1016/0022-3115(93)90252-t
Kutty, T.R.G., Ganguly, C., Jayadevan, N.C., Sastry, D.H. (1996) Role of zirconium addition on stability of UAl3 phase in Alî—¸U system. Journal of Nuclear Materials, 230 (3). 295-301 doi:10.1016/0022-3115(96)00019-0
Wadman, Boel, Andrén, Hans-Olof, Nyström, Anna-Lena, Rudling, Peter, Pettersson, Håkan (1993) Microstructural influence on uniform corrosion of Zircaloy nuclear fuel claddings. Journal of Nuclear Materials, 200 (2). 207-217 doi:10.1016/0022-3115(93)90331-r
Snowden, K.U. (1970) The effect of temperature on the logarithmic creep of zircaloy-2. Journal of Nuclear Materials, 36 (3). 347-349 doi:10.1016/0022-3115(70)90053-x
(1993) Editorial Board. Journal of Nuclear Materials, 207. doi:10.1016/0022-3115(93)90243-r
Lewis, B.J., Cox, D.S., Iglesias, F.C. (1993) A kinetic model for fission-product release and fuel oxidation behaviour for Zircaloy-clad fuel elements under reactor accident conditions. Journal of Nuclear Materials, 207. 228-241 doi:10.1016/0022-3115(93)90265-z
 
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