Using Radioactive Tracers to Study Chloride Stress Corrosion Cracking of Stainless Steels

CORROSION ◽  
1966 ◽  
Vol 22 (2) ◽  
pp. 48-52 ◽  
Author(s):  
R. F. OVERMAN
Keyword(s):  
Stainless Steel ◽  
Stress Corrosion ◽  
Stress Corrosion Cracking ◽  
Stainless Steels ◽  
Radioactive Tracer ◽  
Corrosion Cracking ◽  
Radioactive Tracers ◽  
Surface Cracks ◽  
High Concentration ◽  
Chloride Stress Corrosion Cracking

Abstract A combination of radioactive tracer and metallurgical techniques has made it possible to study some of the conditions necessary to produce chloride stress corrosion cracks in stainless steel The existence of charged areas on the surface of steel was demonstrated by autoradiography of samples exposed to solutions containing radioactive tracers. Charged areas on the surface may be created by a high concentration of small sulfide inclusions; the cracks that appeared were initiated within these charged areas. Seven nanograms of chloride on one charged area was sufficient to start corrosion and subsequent surface cracks in a surface of steel stressed by grinding.

Chloride Stress Corrosion Cracking of Austenitic Stainless Steel—Effect of Temperature and pH★

CORROSION ◽  
1958 ◽  
Vol 14 (12) ◽  
pp. 60-64 ◽  
Author(s):  
L. R. SCHARFSTEIN ◽  
W. F. BRINDLEY
Keyword(s):  
Stainless Steel ◽  
Austenitic Stainless Steel ◽  
Stress Corrosion ◽  
Stress Corrosion Cracking ◽  
Stainless Steels ◽  
Chloride Ions ◽  
Corrosion Cracking ◽  
Effect Of Temperature ◽  
Type 304 ◽  
Chloride Stress Corrosion Cracking

Abstract Overstressed U-bends of Types 304 and 347 stainless steels were exposed to water containing chloride ions to determine the susceptibility of these steels to stress corrosion cracking between the temperatures of 165 F and 200 F. The pH was controlled at 6.5 to 7.5 and 10.6 to 11.2 for the tests. At the high pH, cracks appeared at the edges with little evidence of pitting. At the neutral pH, cracks were found at the edges and associated with pits. Sensitized Type 304 had longer and deeper cracks than annealed Types 304 and 347 in the same exposure time. Conclusion is made that chloride stress corrosion cracking of these steels in the temperature range of 165 F to 200 F is less severe than that experienced at 500 F and that specific conditions are required for corrosion cracking to occur at all. 3.2.2

Chloride Stress Corrosion Cracking Of Stainless Steel Deaerator Trays

CORROSION ◽  
1961 ◽  
Vol 17 (2) ◽  
pp. 53t-54t ◽  
Author(s):  
N. D. GROVES ◽  
L R. SCHARFSTEIN ◽  
C. M. EISENBROWN
Keyword(s):  
Stainless Steel ◽  
Stress Corrosion ◽  
Stress Corrosion Cracking ◽  
Stainless Steels ◽  
Austenitic Stainless Steels ◽  
Corrosion Cracking ◽  
Feed Water ◽  
Water Heater ◽  
Short Annealing ◽  
Chloride Stress Corrosion Cracking

Abstract A case history is given of failures of stainless steel deaerator trays used in a deaerating feed water heater. Trays fabricated from Type 201 and Type 329 stainless steels were reported to have failed by chloride stress corrosion cracking after several months' service. The cracking of the Type 201 was very severe. It is shown that conditions in parts of the deaerating heater promote failure by chloride stress corrosion cracking and the service life of austenitic stainless steels is very short. Annealing after welding of the Type 329 trays would improve resistance to cracking. It is also suggested that Type 430 stainless steel be considered since it is not susceptible to chloride stress corrosion cracking. 6.2.5, 3.5.8, 7.6.8

The Study on the Applicability of Laser Surface Modification Technology to Irradiated Stainless Steel

2008 ◽  
Author(s):  
Masatoshi Sato ◽  
Masanori Kanno ◽  
Kiyotomo Nakata ◽  
Hidenori Takahashi ◽  
Hiroshi Sakamoto
Keyword(s):  
Stainless Steel ◽  
Surface Modification ◽  
Stress Corrosion ◽  
Stress Corrosion Cracking ◽  
Stainless Steels ◽  
Corrosion Cracking ◽  
Laser Surface ◽  
Bending Test ◽  
Laser Surface Modification ◽  
Weld Heat

Recently, occurrence of stress corrosion cracking has been reported at core shrouds in Boiling Water Reactor (BWR) nuclear power plants. Yttrium aluminum garnet (YAG) laser surface modification technologies (i.e. Laser Surface Melting Technology (LSM), Laser Cladding Technology (LC)) have been developed as promising preventive maintenance technologies to stress corrosion cracking (SCC) of austenitic stainless steel structures and components. On the other hand, it has been also well-known that the helium transmuted from nickel and boron is accumulated to neutron irradiated stainless steel, and that helium related cracks may occur at weld heat affected zone which were attributed to nucleation along grain boundaries, coalescence and growth of helium bubbles due to thermal cycle and thermal stress during welding. Then, the laser surface modification technologies to the irradiated stainless steels was developed and the applicability of these technologies was evaluated based on the results of various tests (e.g. dye-penetrant test, micro structure observation and bending test) to the laser surface modified Type 304 and Type 316L specimens containing up to about 10 appm helium. The laser surface modification applicability diagram was developed as a function of weld heat input and helium concentration, which was supported by numerical simulation on helium bubble formation and growth during welding for irradiated stainless steels.

Sign in / Sign up

Export Citation Format

Share Document