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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

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Reference TypeJournal (article/letter/editorial)
TitleIn-reactor tubular creep of Zircaloy-2 at 260 to 300 °C
JournalJournal of Nuclear Materials
AuthorsIbrahim, E.F.Author
Year1973 (March)Volume46
Issue2
PublisherElsevier BV
DOIdoi:10.1016/0022-3115(73)90133-5Search in ResearchGate
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Mindat Ref. ID4141331Long-form Identifiermindat:1:5:4141331:7
GUID0
Full ReferenceIbrahim, 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
Plain TextIbrahim, 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
In(1973, March) Journal of Nuclear Materials Vol. 46 (2) Elsevier BV

See Also

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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
Ibrahim, E.F., Winegar, J.E. (1973) Dimensional changes of unstressed Zircaloy-2 and Zr-2.5 wt % Nb specimens in a fast neutron flux. Journal of Nuclear Materials, 45 (4). 335-338 doi:10.1016/0022-3115(73)90168-2
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
Ibrahim, E.F. (1983) Deformation of cold-drawn tubes of Zr-2.5 wt% Nb after 7 years in-reactor. Journal of Nuclear Materials, 118 (2). 260-268 doi:10.1016/0022-3115(83)90233-7
Lewthwaite, G.W., Proctor, K.J. (1973) Irradiation-creep in a materials testing reactor. Journal of Nuclear Materials, 46 (1). 9-22 doi:10.1016/0022-3115(73)90117-7
Wood, D.S., Watkins, B. (1971) A creep limit approach to the design of Zircaloy-2 reactor pressure tubes at 275 °C. Journal of Nuclear Materials, 41 (3). 327-340 doi:10.1016/0022-3115(71)90170-x
Lewthwaite, G.W. (1973) Irradiation-creep during void production. Journal of Nuclear Materials, 46 (3). 324-328 doi:10.1016/0022-3115(73)90048-2
Causey, A.R. (1974) In-reactor creep of zircaloy-2, zircaloy-4 and Zr-1.15 wt % Cr-0.1 wt % Fe at 568 K derived from their stress-relaxation behaviour. Journal of Nuclear Materials, 54 (1). 64-72 doi:10.1016/0022-3115(74)90076-2
Pandarinathan, P.R., Vasudevan, P. (1980) Cumulative damage fatigue tests on nuclear reactor Zircaloy-2 fuel tubes at room temperature and 300°C. Journal of Nuclear Materials, 91 (1). 59-62 doi:10.1016/0022-3115(80)90032-x
Donaldson, A.T., Evaaans, H.E. (1981) Oxidation-induced creep in Zircaloy-2. Journal of Nuclear Materials, 99 (1). 38-46 doi:10.1016/0022-3115(81)90136-7
Pandarinathan, P.R., Vasudevan, P. (1980) Low-cycle fatigue studies on nuclear reactor Zircaloy-2 fuel tubes at room temperature, 300 and 350°C. Journal of Nuclear Materials, 91 (1). 47-58 doi:10.1016/0022-3115(80)90031-8
 
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