1977
DOI: 10.1016/0308-0161(77)90023-0
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Mechanical property correlations for Cr-1 Mo steel in support of nuclear reactor systems design

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Cited by 10 publications
(11 citation statements)
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“…Without the influence of grain boundary precipitates, the ductility of alloys gradually increases with the increase of temperature and decreases with the increase of strain rate (Li and Ghosh, 2003). Because of dynamic recovery and dynamic recrystallization, the strength of 2 1 / 4 Cr-1Mo steel (Booker et al., 1977) declines greatly at elevated temperatures, and the ductility obviously increases, as shown in Figure 15. The ZL205A alloy is softened with the increase of temperature, thus improving the ductility of the alloy.…”
Section: Discussionmentioning
confidence: 99%
“…Without the influence of grain boundary precipitates, the ductility of alloys gradually increases with the increase of temperature and decreases with the increase of strain rate (Li and Ghosh, 2003). Because of dynamic recovery and dynamic recrystallization, the strength of 2 1 / 4 Cr-1Mo steel (Booker et al., 1977) declines greatly at elevated temperatures, and the ductility obviously increases, as shown in Figure 15. The ZL205A alloy is softened with the increase of temperature, thus improving the ductility of the alloy.…”
Section: Discussionmentioning
confidence: 99%
“…The experimental data showed the applicability of strain hardening rule and Von Mises' flow rule to Hastelloy XR. The statistical analyses revealed that the time function proposed by Garofalo et al (1963) correlates the creep curve data in the superior agreement to the rational time function (Booker et al, 1977). Fig.…”
Section: Creep Bucklingmentioning
confidence: 92%
“…7S y f or austenitic steels (23) Note that the temperature for the 2S y allowable is based on the average wall temperature of the range.…”
Section: R5 Volume 2/3 Analysis Resultsmentioning
confidence: 99%
“…• Oak Ridge National Laboratory (ORNL)/TM-5329, Mechanical Property Correlations for 2-1/4Cr-1Mo Steel in Support of Nuclear Reactor Systems Design [23] • API 579-1/ASME FFS-1 (2007), Part 10 and Annex F [2] • API RP 530: Calculation of Heater-tube Thickness in Petroleum Refineries, Sixth Edition [24] • ASME Boiler and Pressure Vessel Code, Section III, Subsection NH [25] • European Creep Collaborative Committee (ECCC) Data Sheets [26] The most common available data is creep rupture, while API 579-1 and ORNL provide fairly complete descriptions of expected creep behavior. The creep rupture data from the above sources is plotted in Figure 5.…”
Section: Geometry and Materials Background Infor-mationmentioning
confidence: 99%