EXAMINATION AND EVALUATION OF EXPERIMENTAL BOILING WATER REACTOR PRESSURE-VESSEL CLADDING

被引：0
|
作者：
SUTTON, CR
BALAI, N
WIMUNC, EA
JONES, RF
机构：
来源：
TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY | 1966年 / 9卷 / 01期
关键词：
D O I：
暂无
中图分类号：
TL [原子能技术]; O571 [原子核物理学];
学科分类号：
0827 ; 082701 ;
摘要：
引用
收藏
页码：222 / &
相关论文
共 50 条
  • [1] RADIATION EFFECTS IN BOILING WATER-REACTOR PRESSURE-VESSEL STEELS
    KASS, JN
    GIANNUZZI, AJ
    HUGHES, DA
    JOURNAL OF ENGINEERING MATERIALS AND TECHNOLOGY-TRANSACTIONS OF THE ASME, 1980, 102 (02): : 177 - 186
  • [2] EVALUATION OF THE J-INTEGRAL AND THE CLADDING EFFECT OF A CRACK IN THE REACTOR PRESSURE-VESSEL
    KIKUCHI, M
    MIYAMOTO, H
    SUGAWARA, S
    BULLETIN OF THE JSME-JAPAN SOCIETY OF MECHANICAL ENGINEERS, 1986, 29 (258): : 4026 - 4031
  • [3] FLAW DENSITY EXAMINATIONS OF A CLAD BOILING WATER-REACTOR PRESSURE-VESSEL SEGMENT
    COOK, KV
    MCCLUNG, RW
    NUCLEAR ENGINEERING AND DESIGN, 1988, 108 (1-2) : 211 - 219
  • [4] TRANSIENT HEAT-TRANSFER FOR BOILING WATER AT A VERTICAL PLATE OF A REACTOR PRESSURE-VESSEL
    BURCK, E
    HUFSCHMIDT, W
    CLERCQ, ED
    ATOMKERNENERGIE, 1973, 21 (02): : 127 - 135
  • [5] GAMMA-RAY DISPLACEMENT DAMAGE IN THE PRESSURE-VESSEL OF THE ADVANCED BOILING WATER-REACTOR
    ALEXANDER, DE
    REHN, LE
    JOURNAL OF NUCLEAR MATERIALS, 1994, 217 (1-2) : 213 - 216
  • [6] REACTOR PRESSURE-VESSEL MATERIALS
    WECHSLER, MS
    BERGGREN, RG
    NUCLEAR SAFETY, 1964, 5 (04): : 342 - &
  • [7] IRRADIATION AND POSTIRRADIATION EXAMINATION TECHNIQUES FOR REACTOR PRESSURE-VESSEL STEELS AT GKSS
    AHLF, J
    SCHMITT, FJ
    ATOMKERNENERGIE, 1977, 29 (02): : 128 - 132
  • [8] PISC FULL SCALE REACTOR PRESSURE-VESSEL VALIDATION OF NONDESTRUCTIVE EXAMINATION
    CRUTZEN, S
    HERKENRATH, H
    KUSSMAUL, K
    MLETZKO, U
    NUCLEAR ENGINEERING AND DESIGN, 1990, 119 (2-3) : 475 - 490
  • [9] REACTOR PRESSURE-VESSEL INTEGRITY .2. IN-SERVICE EXAMINATION
    SMITH, D
    NUCLEAR ENGINEERING INTERNATIONAL, 1974, 19 (220): : 757 - 761
  • [10] BOILING WATER REACTOR PRESSURE VESSEL INTEGRITY EVALUATION BY PROBABILISTIC FRACTURE MECHANICS
    Chen, Bo-Yi
    Huang, Chin-Cheng
    Chou, Hsoung-Wei
    Liu, Ru-Feng
    Lin, Hsien-Chou
    PROCEEDINGS OF THE ASME PRESSURE VESSELS AND PIPING CONFERENCE 2010, VOL 7, 2010, : 149 - 155
12345