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TECHNICAL PAPERS

Evaluation Procedures for Irradiation Effects and Sodium Environmental Effects for the Structural Design of Japanese Fast Breeder Reactors

[+] Author and Article Information
Tai Asayama, Yasuhiro Abe, Noriko Miyaji, Mamoru Koi, Tomohiro Furukawa, Eiichi Yoshida

Oarai Engineering Center, Japan Nuclear Cycle Development Institute, Ibaraki, Japan

J. Pressure Vessel Technol 123(1), 49-57 (Oct 27, 2000) (9 pages) doi:10.1115/1.1338119 History: Received October 18, 1999; Revised October 27, 2000
Copyright © 2001 by ASME
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References

Billington, D. S., and Crawford, Jr, J. H., 1961, Radiation Damage in Solids, Princeton University Press, Princeton, NJ.
Holmes,  J. J., Robbins,  R. E., Brimhall,  J. L., and Mastel,  B., 1968, “Elevated Temperature Irradiation Hardening in Austenitic Stainless Steel,” Acta Metall., 16, p. 955.
Williams,  J. A., and Carter,  J. W., 1967, “Creep of Annealed Type 304 Stainless Steel During Irradiation and Its Engineering Significance,” ASTM Spec. Tech. Publ., 426, p. 149.
Bloom, E. E., 1968, “In-Reactor and Postirradiation Creep-Rupture Properties of Type 304 Stainless Steel, at 650 C,” ORNL-TM-2130.
Breitling, H., 1983, “Influence of Medium Dose Neutron Irradiation (≤1022 ncm−2) on Design Properties for Elastic Analysis of X6 CRNI 18 11 for Permanent Structures of SNR300,” Specialist Meeting on Mechanical Properties of Structural Materials Including Environmental Effects, IWGFR-49, p. 801.
Tavassoli,  A.-A., Picker,  C., and Wareing,  J., 1996, “Data Collection on the Effect of Irradiation on the Mechanical Properties of Austenitic Stainless Steels and Weld Metals,” ASTM Spec. Tech. Publ., 1270, p. 995.
Iida,  K., Asada,  Y., Okabayashi,  K., and Nagata,  T., 1987, “Construction Codes Developed for Prototype FBR Monju,” Nucl. Eng. Des., 98, p. 283.
Wada, Y., Yoshida, E, Kobayashi, T., and Aoto, K., 1991, “Development of New Materials for LMFBR Components—Evaluation on Mechanical Properties of 316FR Steel,” Int. Conf. on Fast Reactors and Related Fuel Cycles, I , p. 7.2
Aoto, K., and Wada, Y., 1994, “Concept of Design Criteria of Low Dose Irradiation for FBR Structural Materials,” Proc. The International Working Group for Fast Reactors, p. 79.
Aoto, K., Abe, Y., Shibahara, I., and Wada, Y., 1994, “Effects of Neutron Irradiation on Creep Properties of FBR Grade 316 Stainless Steel,” Proc. The International Working Group for Fast Reactors, p. 27.
Goldmann, K., 1970, “Environmental Design Factors for Sodium-Cooled Fast Reactors Components, Sodium Cooled Fast Reactor Engineering,” IAEA, Vienna, p. 905.
Thorley, A. W., and Tyzack, C., 1973, “Corrosion and Mass Transport of Steel and Nickel Alloys in Sodium Systems, Liquid Alkali Metals,” BNES, p. 257.
Natesan, K., Chopra, O. K., and Kassner, F., 1980, “Creep-Rupture and Low-Cycle Fatigue Behavior of Types 304 and 316 Stainless Steel Exposed to a Sodium Environment,” The 2nd International Conference on Liquid Metal Technology in Energy, pp. 19–41.
Chopra, O. K., Natesan, K., and Kassner, T. F., 1980, “Influence of Sodium Environment on the Low-Cycle Fatigue and Creep-Fatigue Behavior of Fe-2 1/4Cr-1Mo Steel,” The 2nd International Conference on Liquid Metal Technology in Energy, p. 19-9.
Aoto,  K., Komine,  R., Ueno,  F., Kawasaki,  H., and Wada,  Y., 1994, “Creep-Fatigue Evaluation of Normalized Tempered Modified 9Cr-1Mo,” Nucl. Eng. Des., 153, p. 97.
Kano, S., et al., 1988, “In-Air Mechanical Properties and Sodium Compatibility of Mod.9Cr-1Mo Steel for Large-Scale Fast Breeder Reactor,” Proc. Fourth International Conference on Liquid Metal Engineering and Technology, Vol. 3, p. 536-1.
Ito,  T., Kato,  S., Aoki,  M., Yoshida,  E., Kobayashi,  T., and Wada,  Y., 1992, “Evaluation of Carburization and Decarburization Behavior of Fe-9Cr-Mo Ferritic Steels in Sodium Environment,” J. Nucl. Sci. Technol., 29-4, p. 367.
Furukawa, T., Yoshida, E., Kato, S., and Komine, R., 1998, “Effect of Sodium on Mechanical Strength of FBR Grade Type 316 Stainless Steel,” ASME PVP-Vol. 373, p. 301.
Hirano, M., Komine, R., Kitao, K., Nihei, I., and Yoshitoshi, A., 1983, “Low-Cycle Fatigue Properties of SUS304 Stainless Steel in High-Temperature Sodium,” Proc. Specialist Meeting on Mechanical Properties of Structural Materials Including Environmental Effects, IWGFR-49, Vol. 2, p. 741.
Maruyama, T., Kato, S., Komine, R., Hirano, M., Wada, Y., Kano, S., and Nihei, I., 1988, “Low-Cycle Fatigue Properties of SUS304 Stainless Steel in Elevated Temperature Fluid Sodium,” Proc. Fourth International Conference on Liquid Metal Engineering and Technology, Vol. 2, p. 512-1.
Mimura, H., Ito, T., Yoshida, E., Tsuchida, Y., Kano, S., and Nihei, I., 1988, “An Assessment of Carburization Behavior of SUS304 Stainless Steel in FBR Secondary System,” Proc. Fourth International Conference on Liquid Metal Engineering and Technology, Vol. 2, p. 505-1.
Asayama, T., Kagawa, H., Komine, R., and Wada, Y., 1991, “Creep-Fatigue Behavior of SUS304 Stainless Steel Tested in Carburized Sodium at 550 C,” Preprints of Mechanical Behavior of Materials-VI, Vol. 2, p. 291.
Wada, Y., Yoshida, E., Aoki, M., Kato, S., and Ito, T., 1991, “Influence of Sodium Exposure on Creep Rupture Strength of Type 304 and 316 Steels,” Proc. International Atomic Energy Agency Specialists’ Meeting on Fast Reactors, KfK 4935 IWGFR/84, p. 17.
Yoshida, E., et al., 1995, “Post-Corrosion and Metallurgical Analysis of Sodium Piping Materials Operated for 100,000 Hours,” Liquid Metal Systems, Plenum Press, p. 55.
Wada, Y., Asayama, T., and Komine, R., 1991, “Influence of Carburizing Sodium on Creep-Fatigue Behavior of Type 304 Steel,” Proc. International Atomic Energy Agency Specialists’ Meeting on Fast Reactors, KfK 4935 IWGFR/84, p. 149.
Miyaji,  N., Abe,  Y., Ukai,  S., and Onose,  S., 1999, “Post Irradiation Creep Rupture Properties of FBR Grade 316 S.S.,” J. Nucl. Mater., 271&272, pp. 173–178.
Gilbert,  E. R., and Harding,  N. E., 1969, “Comparison of In-Reactor Creep and Postirradiation Creep Tests of Structural Materials for Nuclear Applications,” ASTM Spec. Tech. Publ., 457, p. 17.
Bloom,  E. E., and Wolfer,  W. G., 1979, “In-Reactor Deformation and Fracture of Austenitic Stainless Steels,” ASTM Spec. Tech. Publ., 683, p. 656.
Wassilew,  C., Ehrlich,  K., and Bergmann,  H-J., 1987, “Analysis of the In-Reactor Creep and Rupture Life Behavior of Stabilized Austenitic Stainless Steels and the Nickel-Base Alloy Hastelloy-X,” Influence of Radiation on Material Properties: 13th International Symposium, ASTM Spec. Tech. Publ., 956, p. 30.
Papirno, R., 1968, “Ductility in Structural Design,” Ductility, ASM, p. 343.
Atsumo, H., Yuhara, S., Maruyama, A., Kanoh, S., Aoki, N., and Mochizuki, 1976, “Sodium Compatibility and Corrosion Tests for Component Materials,” Proc. International Conference on Liquid Metal Technology in Energy Production, p. 849.
Ito, T., Hagi, S., and Wada, Y., 1990, “Carburization and Denitrided Behavior of Modified SUS316 Steels in Sodium,” Proc. The 28th Symposium on High Temperature Strength of Materials, p. 101.

Figures

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Tensile elongation of irradiated material (316FR)
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Creep rupture time of irradiated material (316FR)
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Creep fracture elongation of irradiated material (316FR)
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Steady-state creep rate of irradiated material (316FR)
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Creep life reduction factor for irradiated material
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Steady-state creep rate increase factor for irradiated material
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Microstructures of specimens subjected to high and low fast neutron fluence—(a) fracture surface (SEM), (b) grain (TEM), (c) grain boundary (TEM)
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Creep rupture time of 316FR in sodium
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Creep elongation of 316FR in sodium
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Microstructure observation of creep specimen tested in sodium (823K, 274.4 MPa, tr=17291.0h)—(a) void in the bulk of sepcimen, (b) surface degradation layer
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Fatigue/creep-fatigue life of 316FR in sodium
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Creep rupture time of Mod.9Cr-1Mo in sodium
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Fatigue/creep-fatigue life of Mod.9Cr-1Mo

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