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

Short and Ballinger
A COMPOSITE FOR HIGH-TEMPERATURE LEAD- AND LEAD-BISMUTH–COOLED REACTORS—I
Downloaded by [Australian Catholic University] at 03:26 17 August 2017
26. 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!.
27. G. Y. LAI, High-Temperature Corrosion and Materials
Applications, ASM International ~2007!.
28. J. ROBERTSON and M. I. MANNING, “Healing Layer
Formation in Fe-Cr-Si Ferritic Steels. Mater. Sci. Technol., 5,
741 ~1989!.
29. 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!.
30. R. KLUEH and A. NELSON, “Ferritic0Martensitic Steels
for Next-Generation Reactors,” J. Nucl. Mater., 371,37~2007!.
31. 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!.
32. A. L. JOHNSON et al., “Spectroscopic and Microscopic
Investigation of the Corrosion of 3160316L Stainless Steel by
Lead-Bismuth Eutectic ~LBE! at Elevated Temperatures: Importance
of Surface Preparation,” J. Nucl. Mater., 328, 88
~2004!.
33. T. FURUKAWA et al., “Corrosion Behavior of FBR Candidate
Materials in Stagnant Pb-Bi at Elevated Temperature,”
J. Nucl. Sci. Technol., 41, 6~2004!.
34. 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!.
35. R. KLUEH and J. VITEK, “Elevated-Temperature Tensile
Properties of Irradiated 9Cr-1MoVNb Steel,” J. Nucl. Mater.,
132, 27~1985!.
36. 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!.
37. Y. DAI, X. JIA, and K. FARRELL, “Mechanical Properties
of Modified 9Cr-1Mo ~T91! Irradiated at 3008C in SINQ
Target-3,” J. Nucl. Mater., 318, 192 ~2003!.
38. 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!.
39. 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!.
40. 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!.
41. K. SUZUKI, “Two-Phase Separation of Primary MX Carbonitride
During Tempering in Creep Resistant 9Cr1MoVNb
Steel,” ISIJ Int., 43, 1089 ~2003!.
42. F. A. GARNER, M. B. TOLOCZKO, and B. H. SENCER,
“Comparison of Swelling and Irradiation Creep Behavior of
fcc-Austenitic and bcc-Ferritic0MartensiticAlloys at High Neutron
Exposure,” J. Nucl. Mater., 276, 123 ~2000!.
43. 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!.
44. G. BONNY, D. TERENTYEV, and L. MALERBA, “On
the Miscibility Gap of FeCr Alloys,” Scr. Mater., 59, 1193
~2008!.
45. 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!.
46. J. GLOWNIA, B. KALANDYK, and K. HÜBNER, “Delta
Ferrite Predictions for Cast Duplex Steels with High Nitrogen
Content,” Mater. Charact., 47, 149 ~2001!.
47. G. E. TOTTEN, K. FUNATANI, and L. XIE, Handbook of
Metallurgical Process Design, CRC Press, Boca Raton, Florida
~2004!.
48. 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!.
49. 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!.
50. 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 450–6008C
Temperature Range,” Mater. Corros., 62, 531 ~2011!.
51. G. MÜLLER, G. SCHUMACHER, and F. ZIMMER-
MANN, “Investigation on Oxygen Controlled Liquid Lead Corrosion
of Surface Treated Steels,” J. Nucl. Mater., 278, 85
~2000!.
52. 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!.
53. 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!.
380 NUCLEAR TECHNOLOGY VOL. 177 MAR. 2012