FATIGUE CRACK-GROWTH OF IRRADIATED PRESSURE-VESSEL STEELS IN SIMULATED, REACTOR-GRADE WATER ENVIRONMENT

被引：0

作者：

CULLEN, WH ^{[1
]}

WATSON, HE ^{[1
]}

PROVENZANO, V ^{[1
]}

机构：

[1] USN, RES LAB, WASHINGTON, DC 20375 USA

来源：

TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY | 1980年 / 34卷 / JUN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

页码：182 / 183

页数：2

共 50 条

[21] LOW-CYCLE FATIGUE BEHAVIORS OF PRESSURE-VESSEL STEELS IN A SIMULATED BWR ENVIRONMENT
SATO, S
TETSU TO HAGANE-JOURNAL OF THE IRON AND STEEL INSTITUTE OF JAPAN, 1986, 72 (05): : S565 - S565
[22] Modeling of ductile crack growth in reactor pressure-vessel steels and determination of JR curves
Margolin B.Z.
Kostylev V.I.
Minkin A.I.
Il’In A.V.
Strength of Materials, 2002, 34 (02) : 120 - 130
[23] FRACTURE-TOUGHNESS AND CRACK-GROWTH RESISTANCE OF PRESSURE-VESSEL PLATE AND WELD METAL STEELS
MOSKOVIC, R
ENGINEERING FRACTURE MECHANICS, 1988, 30 (06) : 839 - &
[24] STUDIES ON FRACTURE-TOUGHNESS AND FATIGUE CRACK-GROWTH IN PRESSURE-VESSEL STEELS SUBJECTED TO PRIOR DAMAGE FROM HYDROGEN ATTACK
PENDSE, RD
PARKER, ER
RITCHIE, RO
JOURNAL OF METALS, 1984, 36 (12): : 98 - 99
[25] Prediction of crack growth resistance for ductile fracture of neutron-irradiated reactor pressure-vessel steels. Part 1
Margolin, B.Z.
Kostylev, V.I.
Problemy Prochnosti, 2001, (04): : 25 - 34
[26] Prediction of crack growth resistance for ductile fracture for neutron-irradiated reactor pressure-vessel steels. Part 2
Margolin, B.Z.
Kostylev, V.I.
Problemy Prochnosti, 2001, (05): : 5 - 18
[27] Factors affecting the crack growth rates of reactor pressure vessel steels under simulated boiling water reactor conditions
Chen, Y. Y.
Shih, H. C.
Wang, L. H.
Oung, J. C.
CORROSION, 2006, 62 (05) : 403 - 418
[28] Modeling of ductile crack growth in reactor pressure-vessel steels and construction of JR-curves
Margolin, B.Z.
Kostylev, V.I.
Minkin, A.I.
Il'in, A.V.
Problemy Prochnosti, 2002, (02): : 20 - 34
[29] Prediction of ductile-brittle transition for ductile crack growth in reactor pressure-vessel steels
Margolin B.Z.
Kostylev V.I.
Strength of Materials, 1999, 31 (6) : 525 - 538
[30] AN EMPIRICAL-APPROACH TO FATIGUE CRACK-GROWTH DATA FOR FERRITIC STEELS IN A PRESSURIZED WATER-REACTOR ENVIRONMENT
TEMPLE, JAG
NUCLEAR ENERGY-JOURNAL OF THE BRITISH NUCLEAR ENERGY SOCIETY, 1985, 24 (01): : 53 - 62

← 1 2 3 4 5 →