TENSILE PROPERTIES OF 2-1/4CR-1MO STEEL IRRADIATED TO 23 DPA AT 390-DEGREES-C TO 550-DEGREES-C

被引:6
|
作者
KLUEH, RL
VITEK, JM
机构
关键词
D O I
10.1016/0022-3115(86)90241-2
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
引用
收藏
页码:140 / 148
页数:9
相关论文
共 50 条
  • [1] TENSILE PROPERTIES OF 9CR-1MOVNB AND 12CR-1MOVW STEELS IRRADIATED TO 23-DPA AT 390 TO 550-DEGREES-C
    KLUEH, RL
    VITEK, JM
    JOURNAL OF NUCLEAR MATERIALS, 1991, 182 : 230 - 239
  • [2] EQUILIBRIUM OF CARBIDES IN 2-1/4CR-1MO STEEL AT 712-DEGREES-C
    WADA, H
    DOBRUSIN, EM
    JOURNAL OF METALS, 1985, 37 (08): : A24 - A24
  • [3] AGE SOFTENING CHARACTERISTICS OF ANNEALED 2-1/4CR-1MO STEEL IN THE TEMPERATURE-RANGE 424-DEGREES-C TO 704-DEGREES-C
    PIZZO, PP
    MANDURRAGO, GL
    JOURNAL OF ENGINEERING MATERIALS AND TECHNOLOGY-TRANSACTIONS OF THE ASME, 1981, 103 (01): : 62 - 70
  • [4] DEGRADATION DUE TO CREEP DEFORMATION OF 1CR-1MO-1/4V STEEL AT 550-DEGREES-C
    KIMURA, K
    KISANUKI, T
    KOMATSU, S
    MATSUO, T
    TANAKA, R
    TETSU TO HAGANE-JOURNAL OF THE IRON AND STEEL INSTITUTE OF JAPAN, 1985, 71 (15): : 1803 - 1810
  • [5] EVALUATION OF INELASTIC CONSTITUTIVE MODELS UNDER PLASTICITY CREEP INTERACTION FOR 2-1/4CR-1MO STEEL AT 600-DEGREES-C
    INOUE, T
    OHNO, N
    SUZUKI, A
    IGARI, T
    NUCLEAR ENGINEERING AND DESIGN, 1989, 114 (03) : 295 - 309
  • [6] FATIGUE OF BAINITIC 2-1/4 CR-1 MO STEEL WELDMENTS AT 482-DEGREES-C
    SWINDEMAN, RW
    WILLIAMS, BC
    MECHANICAL ENGINEERING, 1984, 106 (09) : 114 - 114
  • [7] FREQUENCY-ANALYSIS OF AE SIGNAL OBTAINED DURING BREAKAWAY OXIDATION AND INTERNAL CRACKING OF 2-1/4CR-1MO STEEL AT 900-DEGREES-C
    JHA, BB
    RAJ, B
    KHANNA, AS
    OXIDATION OF METALS, 1986, 26 (3-4): : 263 - 273
  • [8] STUDY OF CREEP EMBRITTLEMENT OF 2-1/4CR-1MO STEEL WELD METAL
    SWIFT, RA
    ROGERS, HC
    WELDING JOURNAL, 1976, 55 (07) : S188 - S198
  • [9] INELASTIC STRESS-STRAIN RESPONSE FOR NOTCHED SPECIMEN OF 2-1/4CR1MO STEEL AT 600-DEGREES-C
    INOUE, T
    IMATANI, S
    FUKUDA, Y
    FUJIYAMA, K
    AOTO, K
    TAMURA, K
    NUCLEAR ENGINEERING AND DESIGN, 1994, 150 (01) : 129 - 139
  • [10] FATIGUE-CREEP LIFE PREDICTION FOR A NOTCHED SPECIMEN OF 2-1/4CR1MO STEEL AT 600-DEGREES-C
    INOUE, T
    SAKANE, M
    FUKUDA, Y
    IGARI, T
    MIYAHARA, M
    OKAZAKI, M
    NUCLEAR ENGINEERING AND DESIGN, 1994, 150 (01) : 141 - 149