메뉴 건너뛰기




Volumn 123, Issue 1, 2001, Pages 49-57

Evaluation procedures for irradiation effects and sodium environmental effects for the structural design of japanese fast breeder reactors

Author keywords

[No Author keywords available]

Indexed keywords


EID: 0242597436     PISSN: 00949930     EISSN: 15288978     Source Type: Journal    
DOI: 10.1115/1.1338119     Document Type: Article
Times cited : (28)

References (32)
  • 2
    • 0041373295 scopus 로고
    • Elevated Temperature Irradiation Hardening in Austenitic Stainless Steel
    • 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.
    • (1968) Acta Metall , vol.16 , pp. 955
    • Holmes, J.J.1    Robbins, R.E.2    Brimhall, J.L.3    Mastel, B.4
  • 3
    • 85024624142 scopus 로고
    • Creep of Annealed Type 304 Stainless Steel During Irradiation and Its Engineering Significance
    • 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.
    • (1967) ASTM Spec. Tech. Publ , vol.426 , pp. 149
    • Williams, J.A.1    Carter, J.W.2
  • 5
    • 0342644986 scopus 로고
    • Influence of Medium Dose Neutron Irradiation (<1022 ncm22) on Design Properties for Elastic Analysis of X6 CRNI 18 11 for Permanent Structures of SNR300
    • IWGFR-49
    • Breitling, H., 1983, “Influence of Medium Dose Neutron Irradiation (<1022 ncm22) 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.
    • (1983) Specialist Meeting on Mechanical Properties of Structural Materials including Environmental Effects , pp. 801
    • Breitling, H.1
  • 6
    • 0030219366 scopus 로고    scopus 로고
    • Data Collection on the Effect of Irradiation on the Mechanical Properties of Austenitic Stainless Steels and Weld Metals
    • 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.
    • (1996) ASTM Spec. Tech. Publ , vol.1270 , pp. 995
    • Tavassoli, A.-A.1    Picker, C.2    Wareing, J.3
  • 7
    • 0021775359 scopus 로고
    • Construction Codes Developed for Prototype FBR Monju
    • Iida, K., Asada, Y., Okabayashi, K., and Nagata, T., 1987, “Construction Codes Developed for Prototype FBR Monju,” Nucl. Eng. Des., 98, p. 283.
    • (1987) Nucl. Eng. Des , vol.98 , pp. 283
    • Iida, K.1    Asada, Y.2    Okabayashi, K.3    Nagata, T.4
  • 8
  • 9
    • 0343079153 scopus 로고
    • Concept of Design Criteria of Low Dose Irradiation for FBR Structural Materials
    • 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.
    • (1994) Proc. The International Working Group for Fast Reactors , pp. 79
    • Aoto, K.1    Wada, Y.2
  • 12
    • 0015770427 scopus 로고
    • Corrosion and Mass Transport of Steel and Nickel Alloys in Sodium Systems, Liquid Alkali Metals
    • 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.
    • (1973) BNES , pp. 257
    • Thorley, A.W.1    Tyzack, C.2
  • 15
    • 0028749819 scopus 로고
    • Creep-Fatigue Evaluation of Normalized Tempered Modified 9Cr-1Mo
    • 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.
    • (1994) Nucl. Eng. Des , vol.153 , pp. 97
    • Aoto, K.1    Komine, R.2    Ueno, F.3    Kawasaki, H.4    Wada, Y.5
  • 16
    • 0343515266 scopus 로고
    • In-Air Mechanical Properties and Sodium Compatibility of Mod.9Cr-1Mo Steel for Large-Scale Fast Breeder Reactor
    • 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.
    • (1988) Proc. Fourth International Conference on Liquid Metal Engineering and Technology , vol.3 , pp. 536-541
    • Kano, S.1
  • 17
    • 0026845550 scopus 로고
    • Evaluation of Carburization and Decarburization Behavior of Fe-9Cr-Mo Ferritic Steels in Sodium Environment
    • 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.
    • (1992) J. Nucl. Sci. Technol , vol.29 , Issue.1 , pp. 367
    • Ito, T.1    Kato, S.2    Aoki, M.3    Yoshida, E.4    Kobayashi, T.5    Wada, Y.6
  • 18
    • 0031620046 scopus 로고    scopus 로고
    • Effect of Sodium on Mechanical Strength of FBR Grade Type 316 Stainless Steel
    • 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.
    • (1998) ASME PVP , vol.373 , pp. 301
    • Furukawa, T.1    Yoshida, E.2    Kato, S.3    Komine, R.4
  • 23
    • 0343515261 scopus 로고
    • Influence of Sodium Exposure on Creep Rupture Strength of Type 304 and 316 Steels,” Proc. International Atomic Energy Agency Specialists
    • KfK 4935 IWGFR/84
    • 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.
    • (1991) Meeting on Fast Reactors , pp. 17
    • Wada, Y.1    Yoshida, E.2    Aoki, M.3    Kato, S.4    Ito, T.5
  • 24
    • 0343951041 scopus 로고
    • Post-Corrosion and Metallurgical Analysis of Sodium Piping Materials Operated for 100,000 Hours
    • Plenum Press
    • 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.
    • (1995) Liquid Metal Systems , pp. 55
    • Yoshida, E.1
  • 26
    • 0033132462 scopus 로고    scopus 로고
    • Post Irradiation Creep Rupture Properties of FBR Grade 316 S.S
    • 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.
    • (1999) J. Nucl. Mater , vol.271 , Issue.272 , pp. 173-178
    • Miyaji, N.1    Abe, Y.2    Ukai, S.3    Onose, S.4
  • 27
    • 0343515237 scopus 로고
    • Comparison of In-Reactor Creep and Postirradiation Creep Tests of Structural Materials for Nuclear Applications,” ASTM Spec
    • 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.
    • (1969) Tech. Publ , vol.457 , pp. 17
    • Gilbert, E.R.1    Harding, N.E.2
  • 28
    • 0018754278 scopus 로고
    • In-Reactor Deformation and Fracture of Austenitic Stainless Steels
    • Bloom, E. E., and Wolfer, W. G., 1979, “In-Reactor Deformation and Fracture of Austenitic Stainless Steels,” ASTM Spec. Tech. Publ., 683, p. 656.
    • (1979) ASTM Spec. Tech. Publ , vol.683 , pp. 656
    • Bloom, E.E.1    Wolfer, W.G.2
  • 30
    • 13644250223 scopus 로고
    • Ductility in Structural Design
    • ASM
    • Papirno, R., 1968, “Ductility in Structural Design,” Ductility, ASM, p. 343.
    • (1968) Ductility , pp. 343
    • Papirno, R.1


* 이 정보는 Elsevier사의 SCOPUS DB에서 KISTI가 분석하여 추출한 것입니다.