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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

## Abstract

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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## Figures

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

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

Figure 3

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

Figure 4

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

Figure 5

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

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

Figure 7

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

Figure 8

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

Figure 9

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

Figure 10

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

Figure 11

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

Figure 12

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

Figure 13

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

Figure 14

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

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