CRACK INITIATION AND CRACK-GROWTH DURING THERMAL-SHOCK TESTS IN THE REACTOR PRESSURE-VESSEL OF THE HDR UNDER CORROSIVE MEDIUM CONDITIONS

被引：2

作者：

NEUBRECH, GE

KATZENMEIER, G

WOLF, L

机构：

[1] Kernforschungszentrum Karlsruhe GmbH, Germany

来源：

INTERNATIONAL JOURNAL OF PRESSURE VESSELS AND PIPING | 1988年 / 34卷 / 1-5期

关键词：

D O I：

10.1016/0308-0161(88)90050-6

中图分类号：

T [工业技术];

学科分类号：

08 ;

摘要：

Pressure Vessels

引用

页码：187 / 205

页数：19

共 50 条

[31] VISUAL OBSERVATION OF FATIGUE CRACK-GROWTH BEHAVIOR OF REACTOR PRESSURE-VESSEL STEEL IN HIGH-TEMPERATURE PRESSURIZED WATER
NAGATA, N
TETSU TO HAGANE-JOURNAL OF THE IRON AND STEEL INSTITUTE OF JAPAN, 1984, 70 (13): : 1229 - 1229
[32] THE PATH TO CRACK INITIATION DURING LOW-CYCLE THERMAL-SHOCK FATIGUE
GINSZTLER, J
INTERNATIONAL JOURNAL OF PRESSURE VESSELS AND PIPING, 1986, 26 (03) : 181 - 196
[33] CHARACTERIZATION OF WARM PRESTRESS PHENOMENON IN RELATION TO CRACK INITIATION DURING THERMAL-SHOCK
LOSS, FJ
GRAY, RA
HAWTHORNE, JR
REPORT OF NRL PROGRESS, 1976, (OCT): : 8 - 11
[34] FRACTOGRAPHY IN EVALUATION OF THE MECHANISM OF ENVIRONMENT-SENSITIVE CYCLIC CRACK-GROWTH OF NUCLEAR-REACTOR PRESSURE-VESSEL STEELS
KEMPPAINEN, H
HANNINEN, H
TORRONEN, K
SALONEN, S
ULTRAMICROSCOPY, 1982, 9 (04) : 396 - 397
[35] DISCUSSION OF A FRACTOGRAPHIC EVALUATION OF ENVIRONMENTALLY ASSISTED CYCLIC CRACK-GROWTH IN A533B REACTOR PRESSURE-VESSEL STEEL
SMITH, E
RES MECHANICA, 1984, 11 (04): : 303 - 310
[36] FRACTURE-MECHANICAL ANALYSIS OF A REACTER PRESSURE-VESSEL UNDER THERMAL-SHOCK LOADING
REIMERS, P
COMPUTERS & STRUCTURES, 1993, 47 (4-5) : 815 - 827
[37] STRUCTURAL INTEGRITY TESTS AT THE HDR PRESSURE-VESSEL AND PIPEWORK UNDER OPERATING AND ACCIDENT CONDITIONS
KATZENMEIER, G
DIEM, H
KERNTECHNIK, 1992, 57 (06) : 360 - 367
[38] EFFECT OF THE NATURE OF INTERRUPTING EXPERIMENTS ON THE CRACK-GROWTH RATE IN PRESSURE-VESSEL STEEL UNDER CYCLIC LOADING IN HIGH-TEMPERATURE REACTOR WATER
GNYP, IP
POPOV, AA
DUTSYAK, IZ
TIMONIN, VM
INDUSTRIAL LABORATORY, 1987, 53 (05): : 467 - 470
[39] 3D-FE-CALCULATIONS OF A PRESSURE-VESSEL UNDER THERMAL-SHOCK LOADING
STEGMEYER, R
SAUTER, A
HOFLER, A
SIEVERS, J
KORDISCH, H
NUCLEAR ENGINEERING AND DESIGN, 1990, 119 (2-3) : 281 - 286
[40] 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

← 1 2 3 4 5 →