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Technology Review

Status of Alloy 800 H in Considerations for the Gen IV Nuclear Energy Systems

[+] Author and Article Information
Weiju Ren

Oak Ridge National Laboratory,
Materials Science and Technology Division,
MS-6155, Building 4500-S,
Oak Ridge, TN 37831
e-mail: renw@ornl.gov

Robert Swindeman

Cromtech,
125 Amanda Dr,
Oak Ridge, TN 37831
e-mail: rswindeman@comcast.net

Contributed by the Pressure Vessel and Piping Division of ASME for publication in the JOURNAL OF PRESSURE VESSEL TECHNOLOGY. Manuscript received March 3, 2011; final manuscript received October 12, 2011; published online June 24, 2014. Assoc. Editor: Allen C. Smith.

J. Pressure Vessel Technol 136(5), 054001 (Jun 24, 2014) (12 pages) Paper No: PVT-11-1075; doi: 10.1115/1.4025093 History: Received March 03, 2011; Revised October 12, 2011

Alloy 800 H is currently under consideration for applications in the next generation nuclear plant (NGNP) at operational temperatures above 750 °C. This paper first describes service requirements of the nuclear system for structural materials; and then an extensive review of Alloy 800 H is given on its codification with respect to development and research history, mechanical behavior and design allowables, metallurgical aging resistance, environmental effect considerations, data requirements and availability, weldments, as well as many other aspects relevant to the intended nuclear application. Finally, further research and development activities to support the materials qualification are suggested.

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References

Figures

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Fig. 1

Comparison of the strength based on 100,000 h for candidate materials considered for service at temperatures around 800 °C

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Fig. 2

Comparison of typical UTS values of Alloy 800 H and other candidate materials at various temperatures

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Fig. 3

Comparison of typical YS values of Alloy 800 H and other candidate materials at various temperatures

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Fig. 4

Stress versus the Larson-Miller parameter for rupture of Alloy 800 H

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Fig. 5

Damage interaction diagram for Alloy 800 and Alloy 800 H determined from three analyses

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Fig. 6

Stress-rupture factors for Alloy 800 H welded with SFA-5.11 ERNiCrFe-2 (INCO A)

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Fig. 7

Stress-rupture factors for Alloy 800 H welded with SFA-5.14 ERNiCr-3 (INCO 82)

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