EVALUATION OF THE JIC TESTING PROCEDURE BY ROUND ROBIN TESTS ON A533B CLASS-1 PRESSURE-VESSEL STEEL

被引：0

|

作者：

CLARKE, GA

机构：

来源：

JOURNAL OF TESTING AND EVALUATION | 1980年 / 8卷 / 05期

关键词：

Compilation and indexing terms; Copyright 2025 Elsevier Inc;

D O I：

10.1520/jte10613j

中图分类号：

TB3 [工程材料学];

学科分类号：

0805 ; 080502 ;

摘要：

14

引用

收藏

页码：213 / 220

页数：8

相关论文

共 44 条

[31] DYNAMIC FRACTURE-TOUGHNESS OF LWR PRESSURE-VESSEL STEEL A508 CL.3 - A JAPANESE ROUND-ROBIN STUDY
NAKANO, Y
SAKAI, Y
YAGAWA, G
ANDO, K
ANDO, Y
INTERNATIONAL JOURNAL OF PRESSURE VESSELS AND PIPING, 1988, 31 (04) : 255 - 270
[32] FATIGUE CRACK GROWTH CHARACTERISTICS OF HEAVY SECTION ASTM A533 GRADE-B, CLASS-1 STEEL WELDMENTS
CLARK, WG
MECHANICAL ENGINEERING, 1970, 92 (12) : 59 - &
[33] EFFECT OF THERMAL AGING ON IMPACT DUCTILITY OF THE NUCLEAR-REACTOR PRESSURE-VESSEL STEEL SA533B AND ITS WELD METAL
PELLI, R
FORSTEN, J
THEORETICAL AND APPLIED FRACTURE MECHANICS, 1987, 8 (01) : 25 - 31
[34] THE VIABILITY OF THE K1A PROCEDURE FOR PREDICTING THE ARREST OF A CRACK IN A NUCLEAR-REACTOR STEEL PRESSURE-VESSEL
SMITH, E
NUCLEAR ENGINEERING AND DESIGN, 1985, 90 (03) : 279 - 285
[35] FRACTURE TOUGHNESS PROPERTIES OF HEAVY SECTION A533, GRADE-B, CLASS-1 STEEL PLATE AND SUBMERGED ARC WELDMENT
MAGER, TR
NUCLEAR ENGINEERING AND DESIGN, 1971, 17 (01) : 76 - &
[36] FRACTURE TOUGHNESS KICD VALUES AT TEMPERATURES UP TO 550 DEGREES F FOR ASTM A533 GRADE-B, CLASS-1 STEEL
WITT, FJ
MAGER, TR
NUCLEAR ENGINEERING AND DESIGN, 1971, 17 (01) : 91 - &
[37] HIGH-TEMPERATURE CREEP AND TENSILE DATA FOR PRESSURE-VESSEL STEELS SA533B1 AND SA508-CL2
THINNES, GL
KORTH, GE
CHAVEZ, SA
WALKER, TJ
NUCLEAR ENGINEERING AND DESIGN, 1994, 148 (2-3) : 343 - 350
[38] DETERMINATION OF J-INTEGRAL R-CURVES FOR THE PRESSURE-VESSEL MATERIAL A533-B1 USING THE POTENTIAL-DROP TECHNIQUE AND THE MULTISPECIMEN METHOD
KROMPHOLZ, K
ULLRICH, G
ENGINEERING FRACTURE MECHANICS, 1986, 23 (05) : 803 - 820
[39] ACOUSTIC-EMISSION TESTING DURING A BURST TEST OF A THICK-WALLED 21/4 CR-1MO STEEL PRESSURE-VESSEL
TSUKIKAWA, T
YAMAMOTO, S
OHSHIO, Y
NAKANO, M
UEYAMA, H
WATANABE, J
OHNISHI, K
SAIKUDO, R
IWADATE, T
MATERIALS EVALUATION, 1979, 37 (07) : 64 - 64
[40] Comparison of applicability of current transition temperature shift models to SA533B-1 reactor pressure vessel steel of Korean nuclear reactors
Yoon, Ji-Hyun
Lee, Bong-Sang
NUCLEAR ENGINEERING AND TECHNOLOGY, 2017, 49 (05) : 1109 - 1112

← 1 2 3 4 5 →