A Functionally Graded Composite for Service in High-Temperature Lead- and Lead-Bismuth–Cooled Nuclear Reactors—I: Design

References

• “A Technology Roadmap for Generation IV Nuclear Energy Systems,” GIF-002-00, U.S. Department of Energy Nuclear Energy Research Advisory Committee and the Generation IV International Forum (2002).
   Google Scholar
• “Next Generation Nuclear Plant: A Report to Congress,” U.S. Department of Energy Office of Nuclear Energy; http://www.ne.doe.gov/pdfFiles/NGNP_ReporttoCongress_2010.pdf ( current as of Jan. 24, 2011).
   Google Scholar
• M. ICHIMIYA, T. MIZUNO, and S. KOTAKE, “A Next Generation Sodium-Cooled Fast Reactor Concept and Its R&D Program,” Nucl. Eng. Technol., 39, 171 (2007).
   Google Scholar
• H. A. ABDERRAHIM, V. SOBOLEV, and E. MALAMBU, “Fuel Design for the Experimental ADS MYRRHA,” presented at International Atomic Energy Agency Technical Mtg. Use of LEU in ADS, Vienna, Austria, October 10–12, 2005.
   Google Scholar
• C. STEVENS, “Generation IV International Forum Signs Agreement to Collaborate on Sodium Cooled Fast Reactors,” Online press release, U.S. Department of Energy (2006); http://www.energy.gov/news/archives/3218.htm (current as of Jan. 24, 2011).
   Google Scholar
• J. BUONGIORNO and P. E. MACDONALD, “Supercritical Water Reactor (SCWR): Progress Report for the FY-03 Generation-IV R&D Activities for the Development of the SCWR in the U.S.,” INEEL/EXT-03-01210, Idaho National Engineering and Environmental Laboratory (2003).
   Google Scholar
• N. F. CYCLE and M. SECTION, “Thorium Fuel Cycle—Potential Benefits and Challenges,” IAEA-TECDOC-1450, International Atomic Energy Agency (2005).
   Google Scholar
• M.-H. KIM, H.-S. LIM, and W.-J. LEE, “A Thermal-Fluid Assessment of a Cooled-Vessel Concept for a VHTR,” Nucl. Eng. Des., 238, 3360 (2008).
   Web of Science ®Google Scholar
• N. B. VARGAFTIK, Tables on the Thermophysical Properties of Liquids and Gases, Hemisphere Publishing Corporation (1975).
   Google Scholar
• V. SOBOLEV, “Thermophysical Properties of Lead and Lead-Bismuth Eutectic,” J. Nucl. Mater., 362, 235 (2007).
   Web of Science ®Google Scholar
• P. HEJZLAR et al., “Cross-Comparison of Fast Reactor Concepts with Various Coolants,” Nucl. Eng. Des., 239, 2672 (2009).
   Google Scholar
• P. GIERSZEWSKI, B. MIKIC, and N. TODREAS, “Property Correlations for Lithium, Sodium, Helium, FLiBe and Water in Fusion Reactor Applications,” PFC-RR-80-12, Massachusetts Institute of Technology Plasma Fusion Center (1980).
   Google Scholar
• G. H. HOLDEN and J. V. TOKOR, “Thermophysical Properties of Sodium,” ANL-7323, Argonne National Laboratory (1967).
   Google Scholar
• International Association for the Properties of Water and Steam, Aqueous Systems at Elevated Temperatures and Pressures, R. FERNANDEZ-PRINI, A. H. HARVEY, D. A. PALMER, Eds., Academic Press (2004).
   Google Scholar
• J. J. DUDERSTADT and L. J. HAMILTON, Nuclear Reactor Analysis, John Wiley & Sons (1976).
   Google Scholar
• R. G. BALLINGER and J. LIM, “An Overview of Corrosion Issues for the Design and Operation of High-Temperature Lead and Lead-Bismuth–Cooled Reactor Systems,” Nucl. Technol., 147, 418 (2004).
   Web of Science ®Google Scholar
• N. LI, “Active Control of Oxygen in Molten Lead-Bismuth Eutectic Systems to Prevent Steel Corrosion and Coolant Contamination,” J. Nucl. Mater., 300, 73 (2002).
   Web of Science ®Google Scholar
• L. SOLER, F. MARTíN, F. HERNáNDEZ, and D. GóMEZ-BRICEñO, “Corrosion of Stainless Steels in Lead Bismuth Eutectic up to 6008C,” J. Nucl. Mater., 335, 174 (2004).
   Web of Science ®Google Scholar
• N. POLMAR and K. J. MOORE, Cold War Submarines: The Design and Construction of U.S. and Soviet Submarines, Brassey’s, Inc. (2004).
   Google Scholar
• H. WRIEDT and H. OKAMOTO, “Binary Alloy Phase Diagrams,” ASM Handbooks Online Vol. 3: Alloy Phase Diagrams, ASM International (2004).
   Google Scholar
• L. TAN, M. MACHUT, K. SRIDHARAN, and T. ALLEN, “Corrosion Behavior of a Ferritic/Martensitic Steel HCM12A Exposed to Harsh Environments,” J. Nucl. Mater., 371, 161 (2007).
   Web of Science ®Google Scholar
• J. LIM, H. O NAM, and I. S HWANG, “Corrosion Test of Cr- and Al-Containing Alloys in Static LBE at 550°C,” Proc. Int. Congress Advances in Nuclear Power Plants (ICAPP’08), Anaheim, California, June 8–12, 2008, p. 632, American Nuclear Society (2008).
   Google Scholar
• S. TAKAYA et al., “Corrosion Resistance of Al Alloying High Cr ODS Steels in Stagnant Lead Bismuth,” J. Nucl. Mater., 398, 132 (2010).
   Google Scholar
• D. SAPUNDJIEV, S. V DYCK, and W. BOGAERTS, “Liquid Metal Corrosion of T91 and A316L Materials in Pb-Bi Eutectic at Temperatures 400–6008C,” Corros. Sci., 48, 577 (2006).
   Web of Science ®Google Scholar
• F. GNECCO, E. RICCI, C. BOTTINO, and A. PASSERONE, “Corrosion Behaviour of Steels in Lead Bismuth at 823K,” J. Nucl. Mater., 335, 185 (2004).
   Web of Science ®Google Scholar
• P. MOINARD and Y. MILLET, “Process for the Production of a Tubular Zircaloy 2 Blank Internally Clad with Zirconium and Suitable for Ultrasound Monitoring of the Zirconium Thickness,” U.S. Patent 5609697 (1997).
   Google Scholar
• G. Y. LAI, High-Temperature Corrosion and Materials Applications, ASM International (2007).
   Google Scholar
• J. ROBERTSON and M. I. MANNING, “Healing Layer Formation in Fe-Cr-Si Ferritic Steels. Mater. Sci. Technol., 5, 741 (1989).
   Web of Science ®Google Scholar
• M. P. SHORT, “The Design of a Functionally Graded Composite for Service in High Temperature Lead and Lead Bismuth Cooled Nuclear Reactors,” PhD Thesis, Massachusetts Institute of Technology (2010).
   Google Scholar
• R. KLUEH and A. NELSON, “Ferritic/Martensitic Steels for Next-Generation Reactors,” J. Nucl. Mater., 371, 37 (2007).
   Web of Science ®Google Scholar
• T. H. BAUER, G. R FENSKE, and J. M KRAMER, “Cladding Failure Margins for Metallic Fuel in the Integral Fast Reactor,” Structural Materials in Reactor Technology, Vol. C: Fuel Elements and Assemblies, p. 31, F. H. WITTMANN, Ed. (1987).
   Google Scholar
• A. L. JOHNSON et al., “Spectroscopic and Microscopic Investigation of the Corrosion of 316/316L Stainless Steel by Lead-Bismuth Eutectic (LBE) at Elevated Temperatures: Importance of Surface Preparation,” J. Nucl. Mater., 328, 88 (2004).
   Web of Science ®Google Scholar
• T. FURUKAWA et al., “Corrosion Behavior of FBR Candidate Materials in Stagnant Pb-Bi at Elevated Temperature,” J. Nucl. Sci. Technol., 41, 6 (2004).
   Google Scholar
• P. N. MARTYNOV and K. D. IVANOV, “Properties of Lead-Bismuth Coolant and Perspectives of Non-Electric Applications of Lead-Bismuth Reactor,” IAEA-TECDOC-1056, International Atomic Energy Agency (1997).
   Google Scholar
• R. KLUEH and J. VITEK, “Elevated-Temperature Tensile Properties of Irradiated 9Cr-1Mo VNb Steel,” J. Nucl. Mater., 132, 27 (1985).
   Web of Science ®Google Scholar
• W. L. HU and D. S. GELLES, “The Ductile-to-Brittle Transition Behavior of Martensitic Steels Neutron Irradiated to 26 dpa,” Influence of Radiation on Material Properties: 13th International Symposium (Part II), STP956, p. 83, American Society for Testing and Materials (1987).
   Google Scholar
• Y. DAI, X. JIA, and K. FARRELL, “Mechanical Properties of Modified 9Cr-1Mo (T91) Irradiated at ≤300°C in SINQ Target-3,” J. Nucl. Mater., 318, 192 (2003).
   Google Scholar
• F. H. HUANG, “Fracture Toughness and Tensile Properties of Alloy HT9 in Thin Sections Under High Neutron Fluences,” Effects of Radiation on Materials: 15th International Symposium, p. 1267, STP 1125, American Society for Testing and Materials (1992).
   Google Scholar
• E. A. LITTLE and D. A. STOW, “Void-Swelling in Irons and Ferritic Steels: II. An Experimental Survey of Materials Irradiated in a Fast Reactor,” J. Nucl. Mater., 87, 25 (1979).
   Web of Science ®Google Scholar
• R. L. KLUEH, D. J ALEXANDER, and E. A KENIK, “Development of Low-Chromium, Chromium-Tungsten Steels for Fusion,” J. Nucl. Mater., 227, 11 (1995).
   Web of Science ®Google Scholar
• K. SUZUKI, “Two-Phase Separation of Primary MX Carbonitride During Tempering in Creep Resistant 9Cr1 Mo VNb Steel,” ISIJ Int., 43, 1089 (2003).
   Web of Science ®Google Scholar
• F. A. GARNER, M. B TOLOCZKO, and B. H SENCER, “Comparison of Swelling and Irradiation Creep Behavior of fcc-Austenitic and bcc-Ferritic0Martensitic Alloys at High Neutron Exposure,” J. Nucl. Mater., 276, 123 (2000).
   Web of Science ®Google Scholar
• R. E. STOLLER, A. S KUMAR, and D. S GELLES, Eds., Effects of Radiation on Materials: 15th International Symposium, STP 1125, p. 818, American Society for Testing and Materials (1992).
   Google Scholar
• G. BONNY, D. TERENTYEV, and L. MALERBA, “On the Miscibility Gap of FeCr Alloys,” Scr. Mater., 59, 1193 (2008).
   Web of Science ®Google Scholar
• A. M. BABAKR et al., “Sigma Phase Formation and Embrittlement of Cast Iron-Chromium-Nickel (Fe-Cr-Ni) Alloys,” J. Miner. Mater. Charact. Eng., 7, 127 (2008).
   Google Scholar
• J. GLOWNIA, B. KALANDYK, and K. HüBNER, “Delta Ferrite Predictions for Cast Duplex Steels with High Nitrogen Content,” Mater. Charact., 47, 149 (2001).
   Web of Science ®Google Scholar
• G. E. TOTTEN, K. FUNATANI, and L. XIE, Handbook of Metallurgical Process Design, CRC Press, Boca Raton, Florida (2004).
   Google Scholar
• J. Y. LIM, M. P SHORT, R. B BALLINGER, and N. LI, “Corrosion Studies of Fe-Cr-Si Alloys for Service in Lead-Bismuth Eutectic Systems up to 7008C, Part I: Initial Alloy Development,” J. Nucl. Mater. (2011) (submitted for publication).
   Google Scholar
• G. MüLLER et al., “Behavior of Steels in Flowing Liquid PbBi Eutectic Alloy at 420– 6008C After 4000–7200 h,” J. Nucl. Mater., 335, 163 (2004).
   Web of Science ®Google Scholar
• L. MARTINELLI and F. BALBAUD-CéLéRIER, “Modelling of the Oxide Scale Formation on Fe-Cr Steel During Exposure in Liquid Lead-Bismuth Eutectic in the 450– 600°C Temperature Range,” Mater. Corros., 62, 531 (2011).
   Google Scholar
• G. MüLLER, G. SCHUMACHER, and F. ZIMMERMANN, “Investigation on Oxygen Controlled Liquid Lead Corrosion of Surface Treated Steels,” J. Nucl. Mater., 278, 85 (2000).
   Web of Science ®Google Scholar
• A. R. NIKOLAEV, A. A KORTEL, V. P KARASEV, and V. I IKONNIKOV, “Reaction of Periclase and Corundum Refractories with Killed Steel,” Refract. Ind. Ceram., 21, 635 (1980).
   Google Scholar
• C. T. LIU, E. H LEE, and C. G MCKAMEY, “An Environmental Effect as the Major Cause for Room-Temperature Embrittlement in FeAl,” Scr. Metall., 23, 6, 875 (1989).
   Google Scholar
• K. D. ADAMS and J. N. DUPONT, “Influence of Ti and C on the Solidification Microstructure of Fe-10Al-5Cr Alloys,” Metall. Mater. Trans. A, 41A, 194 (2010).
   Google Scholar
• J. N. DUPONT, J. R REGINA, and K. ADAMS, “Improving the Weldability of FeCrAl Weld Overlay Coatings,” Proc. 21st Conf. Fossil Energy Materials, Knoxville, Tennessee, April 30–May 2, 2007, p. 131 (2007).
   Google Scholar
• J. R. REGINA, J. N DUPONT, and A. R MARDER, “The Effect of Chromium on the Weldability and Microstructure of Fe-Cr-Al Weld Cladding,” Weld. Res., 86, 170s (2007).
   Google Scholar
• D. A. JONES, Principles and Prevention of Corrosion, 2nd ed., Prentice Hall (1996).
   Google Scholar
• J. Y. LIM, “Effects of Chromium and Silicon on Corrosion of Iron Alloys in Lead-Bismuth Eutectic,” PhD Thesis, Massachusetts Institute of Technology (2006).
   Google Scholar
• M. K. MILLER, K. F RUSSELL, J. KOCIK, and E. KEILOVA, “Embrittlement of Low Copper VVER 440 Surveillance Samples Neutron-Irradiated to High Fluences,” J. Nucl. Mater., 282, 83 (2000).
   Web of Science ®Google Scholar
• B. ESMAILZADEH, A. KUMAR, and F. A GARNER, “The Influence of Silicon on Void Nucleation in Irradiated Alloys,” J. Nucl. Mater., 133–134, 590 (1985).
   Web of Science ®Google Scholar
• J. VAN DEN BOSCH, P. HOSEMANN, A. ALMAZOUZI, and S. MALOY, “Liquid Metal Embrittlement of Silicon Enriched Steel for Nuclear Applications,” J. Nucl. Mater., 398, 116 (2010).
   Google Scholar
• F. BARBIER and A. RUSANOV, “Corrosion Behavior of Steels in Flowing Lead-Bismuth,” J. Nucl. Mater., 296, 231 (2001).
   Web of Science ®Google Scholar
• A. WEISENBURGER, A. HEINZEL, G. MüLLER, H. MUSCHER, and A. ROUSANOV, “T91 Cladding Tubes with and Without Modified FeCrAlY Coatings Exposed in LBE at Different Flow, Stress and Temperature Conditions,” J. Nucl. Mater., 376, 274 (2008).
   Web of Science ®Google Scholar
• V. ENGELKO, B. YATSENKO, G. MüLLER, and H. BLUHM, “Pulsed Electron Beam Facility (GESA) for Surface Treatment of Materials,” Vacuum, 62, 211 (2001).
   Google Scholar
• M. P. SHORT and R. G. BALLINGER, “A Functionally Graded Composite for Service in High-Temperature Lead and Lead-Bismuth–Cooled Nuclear Reactors—II: Processing,” Nucl. Technol. (to be published).
   Google Scholar
• G. GUNTZ et al., The T91 Book, Vallourec Industries, France (1990).
   Google Scholar
• M. KAZIMI, E. MONIZ, and C. FORSBERG, The Future of the Nuclear Fuel Cycle, Massachusetts Institute of Technology (2010).
   Google Scholar
• B. YILDIZ and M. S. KAZIMI, “Efficiency of Hydrogen Production Systems Using Alternative Nuclear Energy Technologies,” Int. J. Hydrogen Energy, 31, 77 (2006).
   Web of Science ®Google Scholar
• C. FORSBERG, B. BISCHOFF, L. K MANSUR, L. TROWBRIDGE, and P. TORTORELLI, “A Lower-Temperature Iodine-Westinghouse-Ispra Sulfur Process for Thermochemical Production of Hydrogen,” Proc. Int. Conf. Atoms for Prosperity: Updating Eisenhower’s Global Vision for Nuclear Energy (Global 2003), New Orleans, Louisiana, November 16–20, 2003, p. 1478, American Nuclear Society (2003).
   Google Scholar
• A. NIKIFOROVA, P. HEJZLAR, and N. E TODREAS, “Lead-Cooled Flexible Conversion Ratio Fast Reactor,” Nucl. Eng. Des., 239, 2596 (2009).
   Google Scholar
• M. SCHüTZE, Protective Oxide Scales and Their Breakdown, John Wiley & Sons (1997).
   Google Scholar