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Ibrahim, E.F. (1975) In-reactor creep of zirconium alloys by thermal spikes. Journal of Nuclear Materials, 58 (3). 302-310 doi:10.1016/0022-3115(75)90122-1

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Reference TypeJournal (article/letter/editorial)
TitleIn-reactor creep of zirconium alloys by thermal spikes
JournalJournal of Nuclear Materials
AuthorsIbrahim, E.F.Author
Year1975 (December)Volume58
Issue3
PublisherElsevier BV
DOIdoi:10.1016/0022-3115(75)90122-1Search in ResearchGate
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Mindat Ref. ID4142009Long-form Identifiermindat:1:5:4142009:8
GUID0
Full ReferenceIbrahim, E.F. (1975) In-reactor creep of zirconium alloys by thermal spikes. Journal of Nuclear Materials, 58 (3). 302-310 doi:10.1016/0022-3115(75)90122-1
Plain TextIbrahim, E.F. (1975) In-reactor creep of zirconium alloys by thermal spikes. Journal of Nuclear Materials, 58 (3). 302-310 doi:10.1016/0022-3115(75)90122-1
In(1975, December) Journal of Nuclear Materials Vol. 58 (3) Elsevier BV

See Also

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Ibrahim, E.F. (1981) In-reactor deformation of zirconium alloy tubes at 330 K. Journal of Nuclear Materials, 101 (1). 1-8 doi:10.1016/0022-3115(81)90438-4
Northwood, D.O., London, I.M., Bähen, L.E. (1975) Elastic constants of zirconium alloys. Journal of Nuclear Materials, 55 (3). 299-310 doi:10.1016/0022-3115(75)90071-9
Fidleris, V. (1968) Uniaxial in-reactor creep of Zirconium alloys. Journal of Nuclear Materials, 26 (1). 51-76 doi:10.1016/0022-3115(68)90158-x
Veevers, K. (1975) Strain ageing in zirconium alloys. Journal of Nuclear Materials, 55 (1). 109-110 doi:10.1016/0022-3115(75)90140-3
Ibrahim, E.F. (1981) Creep ductility of cold-worked Zr-2.5 wt% Nb and Zircaloy-2 tubes in-reactor. Journal of Nuclear Materials, 96 (3). 297-304 doi:10.1016/0022-3115(81)90573-0
Carpenter, G.J.C., Ibrahim, E.F., Watters, J.F. (1981) The aging response of zirconium-tin alloys. Journal of Nuclear Materials, 102 (3). 280-291 doi:10.1016/0022-3115(81)90495-5
Pieroy, G.B. (1968) Mechanisms for the in-reactor creep of Zirconium alloys. Journal of Nuclear Materials, 26 (1). 18-50 doi:10.1016/0022-3115(68)90157-8
Ibrahim, E.F. (1973) In-reactor tubular creep of Zircaloy-2 at 260 to 300 °C. Journal of Nuclear Materials, 46 (2). 169-182 doi:10.1016/0022-3115(73)90133-5
Agarwala, R.P, Paul, A.R (1975) Diffusion of carbon in zirconium and some of its alloys. Journal of Nuclear Materials, 58 (1). 25-30 doi:10.1016/0022-3115(75)90162-2
Sawatzky, A., Wilkins, B.J.S. (1967) Hydrogen solubility in zirconium alloys determined by thermal diffusion. Journal of Nuclear Materials, 22 (3). 304-310 doi:10.1016/0022-3115(67)90048-7
Ibrahim, E.F., Holt, R.A. (1980) Anisotropy of irradiation creep and growth of zirconium alloy pressure tubes. Journal of Nuclear Materials, 91 (2). 311-321 doi:10.1016/0022-3115(80)90231-7
 
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