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Technology Reviews

A Review on Current Status of Alloys 617 and 230 for Gen IV Nuclear Reactor Internals and Heat Exchangers

[+] Author and Article Information
Weiju Ren

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

Robert Swindeman

 Cromtech, 125 Amanda Drive, Oak Ridge, TN 37831rswindeman@comcast.net

Reduced from the initial 1000°C consideration based on analysis results that 950°C can satisfy the application requirements.

J. Pressure Vessel Technol 131(4), 044002 (May 26, 2009) (15 pages) doi:10.1115/1.3121522 History: Received August 13, 2007; Revised February 24, 2009; Published May 26, 2009

Alloys 617 and 230 are currently identified as two leading candidate metallic materials in the down selection for applications at temperatures above 760°C in the Gen IV nuclear reactor systems. Qualifying the materials requires significant information related to codification, mechanical behavior modeling, metallurgical stability, environmental resistance, and many other aspects. In the present paper, material requirements for the Gen IV nuclear reactor systems are discussed; available information regarding the two alloys for the intended applications are reviewed and analyzed; and further R&D activities are suggested. In the United States the major requirement for qualifying the materials is to satisfy the ASME Subsection NH, with adequate considerations for NRC, ASME NQA-1, and Section XI. In comparison, Alloy 617 is more studied with larger existing databases in air and helium, while Alloy 230 may have highly desired potentials but needs more exploration. To provide a sound technical basis for the material selection decision, more data should be generated to characterize behaviors of both alloys in creep, loading rate sensitivity, fatigue, creep-fatigue, crack resistance, toughness, product form dependency, and metallurgical stability.

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Copyright © 2009 by American Society of Mechanical Engineers
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Figures

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Figure 1

Template plot for permissible time/temperature data required for Subsection NH Codification of Alloys 617 and 230 that have been cold worked >x% and <y% and subjected to short-time high temperature transient

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Figure 2

Template plot for curves required for allowable stress intensity Smt as a function of temperature for Alloys 617 and 230 in Subsection NH Codification

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Figure 3

Template plot for expected minimum stress-to-rupture values required for Subsection NH Codification of Alloys 617 and 230

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Figure 4

Template plot for curves of fatigue strain range at various temperatures required for Subsection NH Codification of Alloys 617 and 230

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Figure 5

Template plot for creep-fatigue damage envelope required for Alloys 617 and 230 in Subsection NH Codification under the current criteria

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Figure 6

Template plot for time-temperature limits for application of Section II external pressure charts required for Alloys 617 and 230 in Subsection NH Codification

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Figure 7

Template plot for isochronous stress-strain curves required for Alloys 617 and 230 in Subsection NH Codification

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Figure 8

Strain-controlled tensile test curves at 24°C and 950°C and different loading rates

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Figure 9

Template plot for crack growth rate data desirable for estimating creep crack resistance of Alloys 617 and 230

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Figure 10

Template plot for crack growth rate data desirable for estimating fatigue crack resistance of Alloys 617 and 230

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Figure 11

Template plot for crack growth rate data desirable for estimating creep-fatigue crack resistance of Alloys 617 and 230

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Figure 12

Template plot for energy-temperature curves from Charpy tests desired for evaluating toughness of Alloys 617 and 230

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Figure 13

A schematic of time-temperature-transformation desired for Alloys 617 and 230

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Figure 14

Significant difference is observed between creep resistance of tube and foil product forms of Alloy 230

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