The effects of long-time irradiation and thermal aging on 304 stainless steel

2000 ◽  
Vol 282 (2-3) ◽  
pp. 171-179 ◽  
Author(s):  
T.R Allen ◽  
J.I Cole ◽  
C.L Trybus ◽  
D.L Porter
Keyword(s):  
Stainless Steel ◽  
Thermal Aging ◽  
304 Stainless Steel ◽  
Long Time

scholarly journals A Study on the Failure of AISI 304 Stainless Steel Tubes in a Gas Heater Unit

Metals ◽  
2019 ◽  
Vol 9 (9) ◽  
pp. 969 ◽  
Author(s):  
Abbas Bahrami ◽  
Peyman Taheri
Keyword(s):  
Stainless Steel ◽  
Grain Boundary ◽  
Mitigation Strategies ◽  
304 Stainless Steel ◽  
Petrochemical Plant ◽  
Aisi 304 Stainless Steel ◽  
Aisi 304 ◽  
Long Time ◽  
Cause Of Failure ◽  
Electron Microscopes

This paper investigates a failure in convection section tubes of a gas heater unit in a petrochemical plant. Tubes are made of AISI 304 stainless steel. The failure is reported after 5 years of service at working temperature 500 °C. The failure is in the form of circumferential cracks in the vicinity of the weld. Various characterization techniques, including optical and electron microscopes as well as energy-dispersive X-ray spectroscopy (EDS), were used to study the failure. Results showed that that the damage has initiated in the heat affected zone (HAZ) area parallel to the weld/base metal interface. Cracks have propagated alongside grain boundaries, resulting in an intergranular fracture. The main cause of failure was concluded to be attributable to the grain boundary sensitization and intergranular grain boundary attack due to improper welding and long time exposure of tubes to high temperature. Possible mitigation strategies to minimize similar failures will be discussed.

Grain Boundary Character Distributions of Strain-Annealed 304 Stainless Steel

2007 ◽  
Vol 26-28 ◽  
pp. 1335-1340
Author(s):  
Xiao Ying Fang ◽  
Xin Zhang ◽  
Hong Guo ◽  
Wei Guo Wang ◽  
Bang Xin Zhou
Keyword(s):  
Stainless Steel ◽  
Grain Boundary ◽  
Electron Back Scatter Diffraction ◽  
304 Stainless Steel ◽  
Boundary Character ◽  
Special Boundaries ◽  
Grain Boundary Character ◽  
Long Time ◽  
High Fraction ◽  
Type 304

Grain boundary character distributions (GBCD) of type 304 stainless steel cold rolled and then annealed at 1173K were analyzed by electron back scatter diffraction (EBSD). The results showed that low strain (~6%) followed by long-time annealing (96h) resulted in a GBCD containing a high fraction of Σ9 and Σ27 boundaries. The connectivity of general high angle grain boundary (HAB) network was interrupted significantly by Σ3n(n=1,2,3) boundaries(special boundaries).

Thermal Aging Effect of 17-4PH Martensitic Stainless Steel Valves for Nuclear Power Plant

2016 ◽  
Vol 850 ◽  
pp. 96-100 ◽  
Author(s):  
Bing Bai ◽  
Chang Yi Zhang ◽  
Jia Sheng Wang ◽  
Zhen Feng Tong ◽  
Qun Xian Lv ◽  
...  
Keyword(s):  
Stainless Steel ◽  
Thermal Aging ◽  
Nuclear Power ◽  
Martensitic Stainless Steel ◽  
Aging Effect ◽  
Fracture Morphology ◽  
Valve Stem ◽  
Long Time ◽  
Metallurgical Structure ◽  
Hardness Increase

In this work, impact toughness and tensile properties of valve stem used in NPP are obtained. Combining with microstructure analysis of fracture morphology and metallurgical structure, the thermal aging behavior of the martensitic stainless steel is studied. The results show that the thermal aging embrittlement is significant when the valve stem serves in high temperature for a long time. The ductile to brittle transition temperature (DBTT) and the hardness increase, and the upper platform energy decreases.

Effect of Element Segregation on Thermal Aging Behavior of 17-4PH Martensitic Stainless Steel for Nuclear Power Plant

2017 ◽  
Author(s):  
Bing Bai ◽  
Hanxiao Wang ◽  
Changyi Zhang ◽  
Zhenfeng Tong ◽  
Wen Yang
Keyword(s):  
Stainless Steel ◽  
Power Plant ◽  
Nuclear Power Plant ◽  
Thermal Aging ◽  
Nuclear Power ◽  
Martensitic Stainless Steel ◽  
Lath Martensite ◽  
Optical Microscope ◽  
Valve Stem ◽  
Long Time

The valve stem used in the main steam system of nuclear power plant is usually 17-4PH martensitic stainless steel. When it served in 300 C° for a long time, the thermal aging embrittlement of valve stem will be significant, with the performance of the ductile brittle transition temperature (DBTT) and the hardness increased, the upper stage energy (USE) decreased. It will seriously affect the safety and economic operation of nuclear power plant (NPP). It is important to study the thermal aging effect of the 17-4PH steel for safe operation of nuclear power plant. In this work, Three-Dimensional Atom Probe (3DAP), Energy Dispersive X-Ray Spectroscopy (EDX), Scanning Electron Microscope (SEM) and Optical Microscope (OM) are used to analyze the element distribution in 17-4PH steel. The results show that lath martensite will grow significantly under high temperature for a long time. More δ-ferrite will be found between lath martensite, and some carbide aggregates at its interface. In addition, the number density of Cu clusters in the17-4PH steel is increased. It is found that Ni and Mn have obvious segregation with the Cu cluster.

Comparison of Recovery and Recrystallization in Stainless Steel Following Plane-Wave Shock Loading and Explosive Forming

1970 ◽  
Vol 28 ◽  
pp. 428-429 ◽  
Author(s):  
J. A. Korbonski ◽  
L. E. Murr
Keyword(s):  
Stainless Steel ◽  
Shock Loading ◽  
Pressure Pulse ◽  
Shock Pressure ◽  
304 Stainless Steel ◽  
Strain Rates ◽  
Two Dimensional ◽  
Aisi 304 Stainless Steel ◽  
Aisi 304 ◽  
Explosive Forming

Comparison of recovery rates in materials deformed by a unidimensional and two dimensional strains at strain rates in excess of 104 sec.−1 was performed on AISI 304 Stainless Steel. A number of unidirectionally strained foil samples were deformed by shock waves at graduated pressure levels as described by Murr and Grace. The two dimensionally strained foil samples were obtained from radially expanded cylinders by a constant shock pressure pulse and graduated strain as described by Foitz, et al.

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