scholarly journals DETECTION OF THERMAL AGING OF DUPLEX STAINLESS STEELS WITH SQUID MAGNETOMETER

1999 ◽  
Vol 48 (3Appendix) ◽  
pp. 51-56
Author(s):  
Yoshihiro ISOBE ◽  
Toyokazu AOKI
Keyword(s):  
Stainless Steels ◽  
Thermal Aging ◽  
Duplex Stainless Steels ◽  
Squid Magnetometer

scholarly journals Thermal Aging Phenomena in Cast Duplex Stainless Steels

JOM ◽  
2015 ◽  
Vol 68 (2) ◽  
pp. 507-516 ◽  
Author(s):  
T. S. Byun ◽  
Y. Yang ◽  
N. R. Overman ◽  
J. T. Busby
Keyword(s):  
Stainless Steels ◽  
Thermal Aging ◽  
Duplex Stainless Steels ◽  
Aging Phenomena

Thermal Ageing Embrittlement of Casting Duplex Stainless Steels for Nuclear Power Plant

2010 ◽  
Author(s):  
Yuhong Yao ◽  
Jianfeng Wei ◽  
Jiangnan Liu ◽  
Zhengpin Wang ◽  
Yu Wang
Keyword(s):  
Stainless Steels ◽  
Thermal Aging ◽  
Nuclear Power ◽  
Power Plants ◽  
Ageing Time ◽  
Thermal Ageing ◽  
Duplex Stainless Steels ◽  
Impact Properties ◽  
Α Phase ◽  
The Impact

Cast duplex stainless steels (CSS) used for PWR pipes are degraded due to thermal ageing embrittlement during long-term service at 288 °C to 327 °C. Z3CN20-09M Cast duplex Stainless Steels (CSS) made in France for domestic nuclear power plants were thermally aged at 400 °C for 100 h, 300 h, 1000 h, 3000 h and 10000 h. The tensile properties and the impact properties at different thermal aging duration were measured and the effects of the thermal aging time on the microscopic structures and substructures of Z3CN20-09M were respectively investigated by optical microscopy and transmission electron microscopy. The results showed that the tensile strengths of Z3CN20-09M CSS increased gradually with the increment of the thermal ageing time, whereas the impact properties decreased with the prolonging of the thermal ageing time. After long thermal ageing time the dislocation configurations were greatly changed in austenite, and there were precipitates along the austenite-ferrite interface. Moreover, the iron-rich α phase and the chromium-rich α phase precipitated in ferrite aged for 10000h by nucleation and growth rather than the spinodal decomposition. All of above revealed that Z3CN20-09M CSS became brittle during thermal ageing.

On the high cycle fatigue behavior of duplex stainless steels: Influence of thermal aging

1997 ◽  
Vol 234-236 ◽  
pp. 850-852 ◽  
Author(s):  
L. Llanes ◽  
A. Mateo ◽  
P. Violan ◽  
J. Méndez ◽  
M. Anglada
Keyword(s):  
Stainless Steels ◽  
Thermal Aging ◽  
High Cycle Fatigue ◽  
Fatigue Behavior ◽  
Duplex Stainless Steels ◽  
Cycle Fatigue

Effects of long-term thermal aging on bulk and local mechanical behavior of ferritic-austenitic duplex stainless steels

2018 ◽  
Vol 720 ◽  
pp. 130-139 ◽  
Author(s):  
Samuel C. Schwarm ◽  
Sarah Mburu ◽  
R. Prakash Kolli ◽  
Daniel E. Perea ◽  
Sreeramamurthy Ankem
Keyword(s):  
Mechanical Behavior ◽  
Stainless Steels ◽  
Thermal Aging ◽  
Duplex Stainless Steels

Prediction Method of Tensile Properties and Fracture Toughness of Thermal Aged Cast Duplex Stainless Steel Piping

2005 ◽  
Author(s):  
Seiichi Kawaguchi ◽  
Takeharu Nagasaki ◽  
Koji Koyama
Keyword(s):  
Mechanical Properties ◽  
Fracture Toughness ◽  
Stainless Steels ◽  
Thermal Aging ◽  
Power Plants ◽  
True Strain ◽  
Prediction Method ◽  
Strain Curve ◽  
Duplex Stainless Steels

Cast duplex stainless steels of CF8M and CF8 are used in major components because of their superior characteristics, such as corrosion resistance, weldability, and so on. However, these stainless steels are known to have tendency of thermal aging embrittlement after long term service. Therefore, the mechanical properties have been investigated using tensile test specimens and fracture toughness specimens aged at 300 to 450°C for up to 40,000 hours. From the results, the effects of thermal aging on the mechanical properties of these cast duplex stainless steels were identified. The true stress-true strain curve prediction method (TSS model) and fracture toughness prediction method (H3T model) after long term service were established. These prediction methods are used for the evaluation on the plant life management of nuclear power plants in Japan.

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