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Volumn 1311, Issue , 1997, Pages 261-272

Development of comprehensive material performance database for nuclear applications

Author keywords

Aluminum; Creep; Database; Fatigue crack growth; Fusion reactor; Hastelloy XR; High temperature gas cooled reactor; Hypertext; Internet; Light water reactor; Pressure vessel steel; Stainless steel; Tensile property; World Wide Web

Indexed keywords

ALUMINUM; COMPUTER NETWORKS; CRACK PROPAGATION; CREEP; FATIGUE OF MATERIALS; FUSION REACTORS; LIGHT WATER REACTORS; STAINLESS STEEL; TENSILE PROPERTIES;

EID: 0031152480     PISSN: 00660558     EISSN: None     Source Type: Conference Proceeding    
DOI: 10.1520/stp13778s     Document Type: Article
Times cited : (3)

References (15)
  • 12
    • 0027607069 scopus 로고
    • Statistical Analyses of Variability/Reproducibility of Environmentally-Assisted Cyclic Crack Growth Rate Data Relative to K Control Modes
    • Tsuji, H,. Yokoyama, N., Nakajima, H., and Kondo, T., "Statistical Analyses of Variability/Reproduci ibility of Environmentally-Assisted Cyclic Crack Growth Rate Data Relative to K Control Modes," Journal of Nuclear Materials, Vol. 202, 1993, pp. 79-86.
    • (1993) Journal of Nuclear Materials , vol.202 , pp. 79-86
    • Tsuji, H.1    Yokoyama, N.2    Nakajima, H.3    Kondo, T.4
  • 13
    • 0029306065 scopus 로고
    • Generating Material Strength Standards of Aluminum Alloys for Research Reactors I. Yields Strength Values Sy and Tensile Strength Values Su
    • Tsuji, H. and Miya, K., "Generating Material Strength Standards of Aluminum Alloys for Research Reactors I. Yields Strength Values Sy and Tensile Strength Values Su," Nuclear Engineering and Design, Vol. 155, 1995, pp. 527-546.
    • (1995) Nuclear Engineering and Design , vol.155 , pp. 527-546
    • Tsuji, H.1    Miya, K.2


* 이 정보는 Elsevier사의 SCOPUS DB에서 KISTI가 분석하여 추출한 것입니다.