메뉴 건너뛰기




Volumn 2, Issue 7, 2005, Pages 197-205

Development of fuel clad materials for high burn-up operation of LWR

Author keywords

Aging effect; Impact property; Tensile property

Indexed keywords

AGING OF MATERIALS; ALLOYING; ALUMINUM COATED STEEL; LIGHT WATER REACTORS; TENSILE PROPERTIES; THERMOANALYSIS;

EID: 30644478493     PISSN: None     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.jbiotec.2005.03.008     Document Type: Article
Times cited : (10)

References (13)
  • 1
    • 0000043887 scopus 로고    scopus 로고
    • Development of oxide dispersion strengthened ferritic steels for FBR core application (1) improvement of mechanical properties by recrystallization processing
    • Ukai, S., Nishida, T., Okada, H., Okuda, T., Fujiwara, M., and Asabe, K., "Development of Oxide Dispersion Strengthened Ferritic Steels for FBR Core Application (1) Improvement of Mechanical Properties by Recrystallization Processing," Journal of Nuclear Science and Technology, Vol. 34, No. 3, 1997, p. 256.
    • (1997) Journal of Nuclear Science and Technology , vol.34 , Issue.3 , pp. 256
    • Ukai, S.1    Nishida, T.2    Okada, H.3    Okuda, T.4    Fujiwara, M.5    Asabe, K.6
  • 2
    • 0032045790 scopus 로고    scopus 로고
    • Development of oxide dispersion strengthened ferritic steels for FBR core application (II) morphology improvement by martensite transformation
    • Ukai, S., Nishida, T., Okuda, T., and Yoshitake, T., "Development of Oxide Dispersion Strengthened Ferritic Steels for FBR Core Application (II) Morphology Improvement by Martensite Transformation," Journal of Nuclear Science and Technology, Vol. 35, No. 4, 1998, p. 294.
    • (1998) Journal of Nuclear Science and Technology , vol.35 , Issue.4 , pp. 294
    • Ukai, S.1    Nishida, T.2    Okuda, T.3    Yoshitake, T.4
  • 3
    • 30644456874 scopus 로고    scopus 로고
    • R&D of oxide dispersion strengthened ferritic/martensitic steels for FBR
    • Ukai, S., Nishida, T., Okuda, T., and Yoshitake, T., "R&D of Oxide Dispersion Strengthened Ferritic/Martensitic Steels for FBR," Journal of Nuclear Materials, 1745, 1998, pp. 258-263.
    • (1998) Journal of Nuclear Materials , vol.1745 , pp. 258-263
    • Ukai, S.1    Nishida, T.2    Okuda, T.3    Yoshitake, T.4
  • 6
    • 30644461103 scopus 로고    scopus 로고
    • Burst properties of irradiated oxide dispersion strengthened ferritic steel claddings
    • Yoshitake, T., Ohmori, T., and Miyakawa, S., "Burst Properties of Irradiated Oxide Dispersion Strengthened Ferritic Steel Claddings," Journal of Nuclear Materials, 788, 2002, pp. 307-311.
    • (2002) Journal of Nuclear Materials , vol.788 , pp. 307-311
    • Yoshitake, T.1    Ohmori, T.2    Miyakawa, S.3
  • 7
    • 32544454367 scopus 로고    scopus 로고
    • Hardening accompanied by no reduction of ductility in neutron irradiated oxide dispersion strengthened steels
    • to be published
    • Kasada, R. and Kimura, A., "Hardening Accompanied by no Reduction of Ductility in Neutron Irradiated Oxide Dispersion Strengthened Steels," Journal of Nuclear Materials, to be published.
    • Journal of Nuclear Materials
    • Kasada, R.1    Kimura, A.2
  • 8
    • 84961930505 scopus 로고
    • Iron and steels
    • [in Japanese]
    • K. Igaki, Ed, "Iron and Steels," Japan Institute of Metals, Vol. 4, 1985, p. 169 [in Japanese].
    • (1985) Japan Institute of Metals , vol.4 , pp. 169
    • Igaki, K.1
  • 10
    • 0034547395 scopus 로고    scopus 로고
    • Effect of mechanical alloying parameters on irradiation damage in oxide dispersion strengthened ferritic steels
    • Yamashita, S., Watanabe, S., Ohnuki, S., Takahashi, H., Akasaka, N., and Ukai, S., "Effect of Mechanical Alloying Parameters on Irradiation Damage in Oxide Dispersion Strengthened Ferritic Steels," Journal of Nuclear Materials, 2000, pp. 283-287 and 647-651.
    • (2000) Journal of Nuclear Materials , pp. 283-287
    • Yamashita, S.1    Watanabe, S.2    Ohnuki, S.3    Takahashi, H.4    Akasaka, N.5    Ukai, S.6
  • 11
    • 3342962710 scopus 로고    scopus 로고
    • Corrosion properties of oxide dispersion strengthened steels in super-critical water environment
    • Cho, H. S., Kimura, A., Ukai, S., and Fujiwara, M., "Corrosion Properties of Oxide Dispersion Strengthened Steels in Super-Critical Water Environment," Journal of Nuclear Materials, 2004, pp. 329-333 and 387-391.
    • (2004) Journal of Nuclear Materials , pp. 329-333
    • Cho, H.S.1    Kimura, A.2    Ukai, S.3    Fujiwara, M.4


* 이 정보는 Elsevier사의 SCOPUS DB에서 KISTI가 분석하여 추출한 것입니다.