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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

ABB/Combustion Engineering, Inc., Bechtel National, Inc., Gas-Cooled Reactor Associates, General Atomics, Massachusetts Institute of Technology, Oak Ridge National Laboratory, Stone & Webster Engineering Corp., 1994, “Evaluation of the Gas Turbine Modular Helium Reactor,” Gas-Cooled Reactor Associates, San Diego, CA, Paper No. DOE-GT-MHR-100002.
Shenoy, A., and Potter, R. C., 1996, “Gas Turbine-Modular Helium Reactor (GT-MHR) Conceptual Design Description Report,” 910720 Revision 1, General Atomics, San Diego, CA.
Ren, W., and Swindeman, R. W., 2009, “A Review on Current Status of Alloys 617 and 230 for Gen IV Nuclear Reactor Internals and Heat Exchangers,” ASME J. Pressure Vessel Technol., 131(4), p. 044002. [CrossRef]
AREVA NP Inc., 2008, “ASME/DOE Gen IV Task 7 Part 1 Review of Current Experience on Intermediate Heat Exchanger (IHX),” AREVA NP Inc., Document No. 12-9097380-001., 2008, “ASME/DOE Gen IV Task 7 Part 1 Review of Current Experience on Intermediate Heat Exchanger (IHX),” AREVA NP Inc., Document No. 12-9097380-00.
Hayner, G. O., Shaber, E. L., Mizia, R. E., Bratton, R. L., Sowder, W. K., 2004, “Next Generation Nuclear Plant Materials Research and Development Program Plan,” Idaho National Engineering and Environmental Laboratory, Idaho Falls, ID, Paper No. INEEL/EXT-04-02347, Revision 1, No. 83415.
Martin, J. M., and Duke, J. M., 1975, Private Communication, “INCOLOY Alloy 800 Data for Use in Design of Gas Cooled and Liquid Metal Fast Reactors,” Westinghouse Electric Company, Tampa, FL.
Booker, M. K., Baylor, V. B., and Booker, B. P. L., 1978, “Survey of Available Creep and Tensile Data for Alloy 800 H,” Oak Ridge National Laboratory, Oak Ridge, TN, Paper No. ORNL/TM-6029.
Sessions, C. E., and McGeehan, P. J., 1978, “ASME B&PV Code Recommendations of Design Stresses for Use of Annealed Alloy 800 in Elevated Temperature Nuclear Vessels,” Status of Incoloy Alloy 800 Development for Breeder Reactor Steam Generators, Oak Ridge National Laboratory, Oak Ridge, TN, Paper No. ORNL/Sub-4308/3, pp. 89–193.
Trester, P. W., Johnson, W. R., Simnad, M. T., Burnette, R. D., and Roberts, D. I., 1982, “Assessment of Effects of Fort St. Vrain HTGR Primary Coolant on Alloy 800,” Electric Power Research Institute, Palo Alto, CA, Paper No. EPRI NP-2548.
McCoy, H. E., and King, J. F., 1983, “Creep and Tensile Properties of Alloy 800 H-Hastelloy X Weldments,” Oak Ridge National Laboratory, Oak Ridge, TN, Paper No. ORNL/TM-8728.
Baldwin, D. H., Kimball, O. F., and Williams, R. A., 1986, “Design Data for Reference Alloys: Inconel 617 and Alloy 800 H,” General Electric Company, Sunnyvale, CA, HTGR-041.
McCoy, H. E., 1991, “Interim Report on Mechanical Properties Data Analysis of Low Carbon Alloy 800 in Support of ASME Code Case N-47 Code Stress Allowables (INCO and ERA Interim Data Sets),” Oak Ridge National Laboratory, Oak Ridge, TN, unpublished report.
McCoy, H. E., 1993, “Tensile and Creep Tests on a Single Heat of Alloy 800 H,” Oak Ridge National Laboratory, Oak Ridge, TN, ORNL/TM-12436.
Nakajima, H., 1974, High-Temperature Alloys for Structural Applications, Japan Atomic Energy Research Institute, O-arai-machi, Higashi-ibaraki-gun, Ibaraki, Japan.
Hosoi, Y., and Abe, S., 1975, “The Effect of Helium Environment on Creep Rupture Properties of Inconel 617 at 1000 C,” Metall. Trans., 6A, pp. 1171–1178. [CrossRef]
Kitagawa, M., Wright, R. N., Windes, W. E., Totemeier, T. C., Moore, K. A., Corwin, W. R., Burchell, T. D., Corum, J. M., J. Klett, W., Nanstad, R. K., Snead, L. L., Rittenhouse, P. L., Swindeman, R. W., Wilson, D. F., McGreevy, T. E., Jones, R., Gardner, F., 1976, “Some Problems in Developing the High Temperature Design Code for a 1.5MWT Helium Heat Exchanger,” Elevated Temperature Design Symposium, American Society for Mechanical Engineers, New York pp. 33–40.
Cook, R. H., and Sutton, J. C., 1978, “Creep Cracking of Alloy 800 H in Air and Helium at 850–950 °C,” High Temperature Materials Programme, Flight Refuelling Limited, Dorset, England, HTMP Report No. 34.
Bruch, U., Schumacher, D., Ennis, P. J., and Heesen, O., 1984, “Tensile and Impact Properties of Candidate Alloys for High Temperature Gas-Cooled Reactor Applications,” Nucl. Technol., 66, pp. 357–362.
Ennis, P. J., Mohr, K. P., and Schuster, H., 1984, “Effect of Carburizing Service Environments on Mechanical Properties of High-Temperature Alloys,” Nucl. Technol., 66, pp. 363–368.
Meurer, H.-P., Gunter, K., Gnirss, H., Mergler, W., Gerhard, R., Schuster, H., Ullrich, G., 1984, “Investigations on the Fatigue Behavior for High-Temperature Alloys for High-Temperature Gas-Cooled Reactor Components,” Nucl. Technol., 66, pp. 315–323.
Schneider, K., and Ilschner, B., 1984, “Creep Behavior of Materials for High-Temperature,” Nucl. Technol., 66, pp. 289–295.
Schubert, F., Bruch, U., Cook, R., Diehl, H., Ennis, P. J., Jakobeit, W. H.,Penkalla, J., Heesen, E. T., and Ullrich, G., 1984, “Creep Rupture Behavior of Candidate Materials for Nuclear Process Heat Applications,” Nucl. Technol., 66, pp. 227–240.
Aplin, P. F., 1985, “Alloy 800: Summary of the Accumulated Data,” ERA Technology Ltd, Leatherhead, Surrey, UK, ERA Report No: 85-0127.
Degischer, H. P., Aigner, H., Lahodny, H., and Spiradek, K., 1985, “Qualification of Stationary Creep of the Carbide Precipitating Alloy 800 H,” High Temperature Alloy, Elsevier Applied Science, London, UK, pp. 487–498.
Schubert, F., Over, H. H., and Nickel, H., 1986, “Principles for Structural Design Codes for Components in the Creep Temperature Region Mainly Above 800 °C,” The International Conference on Creep, Institute of Mechanical Engineers, London, pp. 539–543.
Diehl, H., and Bodmann, E., 1990, “Alloy 800: New Stress Rupture and Creep Data for Pressurized Components in High Temperature Reactors,” Nucl. Eng. Des., 119, pp. 195–206. [CrossRef]
Diehl, H., and Bodmann, E., 1990, “Alloy 800 Specifications in Compliance With Component Requirements,” J. Nucl. Mater., 171, pp. 63–70. [CrossRef]
Schubert, F., Nickel, H., and Breitbach, G., 1991, “Structural Design Criteria for HTR—A Summary Report,” Nucl. Eng. Des., 132, pp. 75–84. [CrossRef]
Lamagnere, Pierre 2005, “Selection and Qualification of Materials for the Primary Circuit and Intermediate Heat Exchanger of Very High Temperature Reactor (VHTR),” Proceedings of ICAPP’05, Seoul, Korea, May 15–19, Paper No. 5419.
Schubert, F., Breitbach, G., and Nickel, H., 1993, “German Structural Design Rule KTA 3221 for Metallic HTR-Components,” High Temperature Service and Time Dependent Failure, American Society of Mechanical Engineers, New York, PVP-Vol. 262, pp. 9–18.
ASME Boiler and Pressure Vessel Committee, 2011, ASME Boiler and Pressure Vessel Code, an International Code, American Society of Mechanical Engineers, New York.
Jetter, R. I., 2002, “Subsection NH-Class 1 Components in Elevated Temperature Service,” Companion Guide to the ASME Boiler & Pressure Vessel Code, K. R.Rao, ed., American Society of Mechanical Engineers, New York, pp. 369–404.
Corum, J. M., and Blass, J. J., 1991, “Rules for Design of Alloy 617 Nuclear Components to Very High Temperatures,” Fatigue, Fracture, and Risk, American Society of Mechanical Engineers, New York, Paper No. PVP-Vol. 215, pp. 147–153.
Idaho National Laboratory, 2008, “Summary of Bounding Requirements for the NGNP Demonstration Plant F&ORs,” Idaho National Laboratory, Idaho Falls, ID, Paper No. INL/EXT-08014395.
Collins, J., 2008, “Next Generation Nuclear Plant System Requirements Manual,” Idaho National Laboratory, Idaho Falls, ID, INL/EXT-07-12999.
1993, “Regeln des Kemtechnischen Ausschusses (KTA-Regeln) KTA 3221.1,” Metallische HTR-Komponenten, KTA-Sitzung am.
Booker, M. K., 1982, “Time-Dependent Allowable Stresses for ASME Code Case N-47- A Second Look,” Oak Ridge National Laboratory, Oak Ridge, TN, ORNL-5837.
Roberts, D. I., 1979, General Atomic Company, private communication to the Working Group on Materials Behavior SG-ETD on “Revised Design Stresses for Alloy 800 H in Case N-47.”
McCoy, H. E., 1993, Use of the MCM for Analysis of Alloy 800 H Rupture Data, Oak Ridge National Laboratory, Oak Ridge, TN.
Swindeman, R. W., Swindeman, M. J., Roberts, B. W., Thurgood, B. E., and Marriott, D. L., 2007, “A Report on the Review of Databases, Data Analysis Procedures, and Verification of Minimum Yield and Ultimate Strengths for Alloy 800 H in ASME Section III, Subsection NH,” Report on Task 1 submitted to ASME ST-LLC, American Society of Mechanical Engineers, New York.
Harrod, D. L., Langford, P. J., and Moon, D. M., 1978, “Relation of Physical Metallurgy to Mechanical Creep Behavior of Alloy 800,” Status of Incoloy Alloy 800 Development for Breeder Reactor Steam Generators, Westinghouse Electric Company Tampa Division, Tampa, FL, Paper No. ORNL/Sub-4308/3, pp. 195–269.
Swindeman, R. W., Zamrik, S. Y., and Maziasz, P. J., 2007, “Effects of Long-Term Service on the Microstructure and Tensile Properties of Alloy 800 H,” Proceedings of the Eighth International Conference on Creep and Fatigue at Elevated Temperatures, San Antonio, TX, July 22–26, Paper No. PVP2007-26167.
Ren, W., and Swindeman, R. W., 2007, “Preliminary Consideration of Alloys 617 and 230 for Generation IV Nuclear Reactor Applications,” Proceedings of the ASME Pressure Vessels and Piping Division Conference, San Antonio, TX, July 22–26, Paper No. PVP200726091.
Ren, W., and Swindeman, R., 2009, “A Review on Current Status of Alloys 617 and 230 for Gen IV Nuclear Reactor Internals and Heat Exchangers,” ASME J. Pressure Vessel Technol., 131(4), p. 044002. [CrossRef]
Swindeman, R. W., Swindeman, M. J., and Ren, W., 2006, “Can Coverage of Alloy 800 H in ASME Section III Subsection NH be Extended to 850 °C?,” Proceedings of the ASME Pressure Vessels and Piping Division Conference, Vancouver, BC, July 23–27, Paper No. PVP2006-ICPVT11-93333.
Ren, W., and Swindeman, R. W., 2004, “High Temperature Metallic Materials Test Plan for Generation IV Nuclear Reactors,” U.S. Department of Energy Generation IV Nuclear Energy Systems Program, Office of Nuclear Energy Science and Technology, U. S. Department of Energy, Paper No. ORNL/TM-2005/507.
Prager, M., 1996, “Proposed Implementation of Criteria for Assignment of Allowable Stresses High in the Creep Range,” Structural Integrity, NDE, Risk and Material Performance for Petroleum, Process, and Power, American Society of Mechanical Engineers, New York, PVP-Vol. 336.
Suzuki, K., and Asayama, T., 2009, “Operating Condition Allowable Stress Values,” submitted to ASME ST-LLC, American Society of Mechanical Engineers, New York.
Swindeman, R. W., Swindeman, M. J., and Ren, W., 2005, “A Brief Review of Models Representing Creep of Alloy 617,” Proceedings of the ASME Pressure Vessels and Piping Conference, Denver, CO, July 17–21, Paper No. PVP2005-71784.
Prager, M., 2000, “The Omega Method-An Engineering Approach to Life Assessment,” ASME J. Pressure Vessel Technol., 122(3), pp. 273–280. [CrossRef]
Evans, R., and Wilshire, B., 1985, Creep of Metals and Alloys, Institute of Metals, London.
Dyson, B., 2000, “Use of CDM in Materials Modeling and Component Creep Life Prediction,” ASME J. Pressure Vessel Technol., 122(3), pp. 281–296. [CrossRef]
Marriott, D. L., 1995, “Extension of ASME VIII, Division 1 Design Limits,” International Pressure Vessels and Piping Codes and Standards: Vol. 2 Current Perspectives, American Society of Mechanical Engineers, New York Paper No. PVP-Vol. 313-1, pp. 459–469.
NIMS, National Institute for Materials Science, 1999, “Data Sheets on the Elevated-Temperature Stress Relaxation Properties of Iron Based 21Cr-32Ni-Ti-Al Alloy for Corrosion-Resisting and Heat-Resisting Superalloy Bar (NCF 800 H-B),” NIMS Creep Data Sheet No. 47.
Wright, J. K., 2008, “Next Generation Nuclear Plant Intermediate Heat Exchanger Materials Research and Development Plan,” Idaho National Laboratory, Idaho Falls, Paper No. ID, INL/EXT-08-14107.
Coffin, L. F., 1976, “The Concept of Frequency Separation in Life Prediction of Time-Dependent Fatigue,” ASME-MPC Symposium on Creep-Fatigue Interactions, MPC-3, American Society of Mechanical Engineers, New York, pp. 349–364.
Halford, G. R., Hirschberg, M. H., and Manson, S. S., 1973, “Temperature Effects on the Strainrange Partitioning Approach for Creep Fatigue Analysis,” Fatigue at Elevated Temperatures, STP 520, American Society for Testing and Materials, Philadelphia, PA, pp. 658–667.
Ren, W., 1995, “Time-Dependent Fracture Mechanics Characterization of Haynes HR160 Superalloy,” Fatigue and Fracture Mechanics in Pressure Vessels and Piping, PVP-Vol. 304, pp. 563–584, ASME/JSME PVPD.
Shill, T. V., 1979, “Creep-Fatigue Interaction Correlation for Incoloy Alloy 800,” Huntington Alloys, Inc., Huntington, WV, Report No. C-1R.
Kaae, J. L., 1986, Creep-Fatigue Behavior of Alloy 800 H, DOE-HTGR-86-107, General Atomics, Inc., San Diego, CA.
Huddleston, R. L., 1991, “An Assessment of the Adequacy of Selected Creep-Fatigue Models for Design of Alloy 800 H Steel Components,” Oak Ridge National Laboratory, ORNL/NPR-90/31.
Corum, J. M., Greenstreet, W. L., Liu, K. C., Pugh, C. E., and Swindeman, R. W., 1974, “Interim Guidelines for Detailed Inelastic Analysis of High-Temperature Reactor Systems,” ORNL-5014.
Bodmann, E., Breuer, H.-J., Raule, G., and Rodig, M., 1984, “Material Behavior Under Complex Loading,” Nucl. Technol., 66, pp. 667–674.
Corum, J. M., 1989, “Evaluation of Weldment Creep and Fatigue Strength-Reduction Factors for Elevated Temperature Design,” Creep, Ratchet, Fatigue, and Fracture, American Society of Mechanical Engineers, New York, NY, PVP-Vol. 163.
Swindeman, R. W., Swindeman, M. J., Roberts, B. W., Thurgood, B. E., and Marriott, D. L., 2007, “A Review of Available Tensile and Creep Rupture Data Sources and Data Analysis Procedures for Deposited Weld Metal and Weldments of Alloy 800 H,” report on Task 1 submitted to ASME ST-LLC, American Society of Mechanical Engineers, New York, NY.
Nickel, H., Schubert, F., Rödig, M., and Penkalla, H.-J., 1986, “Multiaxial Creep of Tubes at Temperatures above 800 C,” Proceedings of the International Conference on Creep, Tokyo, April 14–18, pp. 509–513.
Sessions, C. E., 1976, Study of the Softening and Recrystallization Response of Cold Worked and Annealed Alloy 800, Westinghouse Electric Company, Tampa Division, Tampa, FL.
Bassford, T. H., and Hosier, J. C., 1984, “Production and Welding Technology of Some High-Temperature Nickel Alloys in Relation to Their Properties,” Nucl. Technol., 66, pp. 35–43.
Swindeman, R. W., Swindeman, M. J., Roberts, B. W., Thurgood, B. E., Marriott, D. L., and Shaughnessy, G., 2008, “Verification of Allowable Stresses in ASME Section III Subsection NH for Alloy 800 H, Part 2: Creep,” ASME Standards Technology, LLC, New York, NY, STP-NU-020.
Ren, W., 1995, “Time-Dependent Fracture Mechanics Characterization of Haynes HR160 Superalloy,” Ph.D. thesis, The University of Tennessee.
Gore, B., Ren, W., and Liaw, P., 2000, “Creep-Crack Growth Testing,” ASM Handbook Vol. 8, Mechanical Testing and Evaluation, pp. 586–595.
Mansur, L. K., 1987, “Mechanisms of Kinetics of Radiation Effects in Metals and Alloys,” Kinetics of Nonhomogeneous Processes: A Practical Introduction for Chemists, Biologists, Physicists, and Materials Scientists, G. R.Freeman, ed., Wiley, New York, pp. 377–463.
Shewmon, P. G., 1971, “Radiation-Induced Swelling of Stainless Steel,” Science, 173(4001), pp. 987–991. [CrossRef] [PubMed]
Lewthwaite, G. W., Mosedale, D., and Ward, I. R., 1967, “Irradiation Creep in Several Metals and Alloys at 100 °C,” Nature (London), 216, pp. 472–473. [CrossRef]
Harries, D. R., 1966, “Neutron Irradiation Embrittlement of Austenitic Stainless Steels and Nickel Base Alloys,” J. Br. Nucl. Energy Soc., 5(1–4), pp. 74–87.
Harries, D. R., 1979, “Neutron Irradiation-Induced Embrittlement in Type 316 and Other Austenitic Steels and Alloys,” J. Nucl. Mater., 82, pp. 2–21. [CrossRef]
Mansur, L. K., and Grossbeck, M. L., 1988, “Mechanical Property Changes Induced in Structural Alloys by Neutron Irradiations With Different Helium to Displacement Ratios,” J. Nucl. Mater., 155–157, pp. 130–147. [CrossRef]
Bloom, E. E., 1976, “Irradiation Strengthening and Embrittlement,” Radiation Damage in Metals, S. D.Hackneys and N. L.Petersen, eds., American Society for Metals, Metals Park, OH, pp. 295–392.
Boothby, R. M., 1990, “Modeling Grain Boundary Cavity Growth in Irradiated Nimonic PE16,” J. Nucl. Mater., 171, pp. 215–222. [CrossRef]

Figures

Grahic Jump Location
Fig. 1

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

Grahic Jump Location
Fig. 2

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

Grahic Jump Location
Fig. 3

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

Grahic Jump Location
Fig. 4

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

Grahic Jump Location
Fig. 5

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

Grahic Jump Location
Fig. 6

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

Grahic Jump Location
Fig. 7

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

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