Development of small punch test for EAC evaluation

被引：9

作者：

Isselin, J ^{[1
]}

Wang, SC

Komazaki, SI

Shoji, T

机构：

[1] Tohoku Univ, Grad Sch Engn, Fracture & Reliabil Res Inst, Aoba Ku, Sendai, Miyagi, Japan

[2] Muroran Inst Technol, Muroran, Hokkaido, Japan

来源：

ADVANCES IN FRACTURE AND STRENGTH, PTS 1- 4 | 2005年 / 297-300卷

关键词：

stress corrosion cracking; Small-Punch test; sensitized stainless steel; boiling water reactor; in-situ observation system;

D O I：

10.4028/www.scientific.net/KEM.297-300.980

中图分类号：

TQ174 [陶瓷工业]; TB3 [工程材料学];

学科分类号：

0805 ; 080502 ;

摘要：

We are developing a Small-Punch SCC testing apparatus with an in-situ observation system applied to high temperature water and high pressure. This new testing apparatus is used to evaluate the Environmentally Assisted Cracking effect. A constant loading rate was carried out with different values of speed, of water flow rate and different polishing of the sample. In BWR (Boiling Water Reactor) conditions (9MPa and 288 degrees C) it was found that the loading rate, water flow rate and surface preparation of the sample have some influence if the test is performed during a short time (maximum 4 days). After the test, by SEM observation, studying the secondary microcracks, it is possible to find all the sequences of EAC process. The in-situ observation system permits to study the strain of the sample during the test.

引用

页码：980 / 985

页数：6

共 7 条

[1] HARUNA T, 2001, 10 INT C ENV DEGR MA
[2] SMALL PUNCH TESTS FOR EVALUATING DUCTILE BRITTLE TRANSITION BEHAVIOR OF IRRADIATED FERRITIC STEELS
MISAWA, T
ADACHI, T
SAITO, M
HAMAGUCHI, Y
[J]. JOURNAL OF NUCLEAR MATERIALS, 1987, 150 (02) : 194 - 202
[3] STRESS-CORROSION CRACKING AND HYDROGEN EMBRITTLEMENT STUDIES OF AUSTENITIC AND FERRITIC STEELS BY SMALL PUNCH TEST
MISAWA, T
HAMAGUCHI, Y
SAITO, M
[J]. JOURNAL OF NUCLEAR MATERIALS, 1988, 155 (pt B) : 749 - 753
[4] Development of a fundamental crack tip strain rate equation and its application to quantitative prediction of stress corrosion cracking of stainless steels in high temperature oxygenated water
Peng, QJ
Kwon, J
Shoji, T
[J]. JOURNAL OF NUCLEAR MATERIALS, 2004, 324 (01) : 52 - 61
[5] A REVIEW OF IRRADIATION ASSISTED STRESS-CORROSION CRACKING
SCOTT, P
[J]. JOURNAL OF NUCLEAR MATERIALS, 1994, 211 (02) : 101 - 122
[6] EFFECTS OF IRRADIATION ON INTERGRANULAR STRESS-CORROSION CRACKING
WAS, GS
BRUEMMER, SM
[J]. JOURNAL OF NUCLEAR MATERIALS, 1994, 216 : 326 - 347
[7] Threshold for stress corrosion cracking initiation of alloy X750 under long-term uniaxial constant load test in high-temperature water
Yamamoto, M
Kuniya, J
Uchida, S
[J]. CORROSION, 2004, 60 (03) : 229 - 236

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