The influence of alloy microstructure on stress corrosion cracking of mild steel in caustic-nitrate synthetic nuclear waste solutions was studied. An evaluation was made of the effect of heat treatment on a representative material (ASTM A 516 Grade 70) used in the construction of high activity radioactive waste storage tanks at Savannah River Plant. Several different microstructures were tested for susceptibility to stress corrosion cracking. Precracked fracture specimens loaded in either constant load or constant crack opening displacement were exposed to a variety of caustic-nitrate and nitrate solutions. Results were correlated with the mechanical and corrosion properties of the microstructures. Crack velocity and crack arrest stress int...
The Hanford tank reservation contains approximately 50 million gallons of liquid legacy radioactive ...
Fracture mechanics techniques were employed to study stress corrosion cracking (SCC) of AISI C-1018 ...
The stress corrosion cracking (SCC) behaviour of low alloy steel AISI 4140 was investigated in 33% s...
A nuclear grade 316L stainless steel and a 508-111 quenched and tempered pressure vessel steel were ...
PhDThe stress-corrosion cracking of 0.08% C and 0.30% C steels in boiling nitrate solution has been ...
The evaporator recycle streams of nuclear waste tanks may contain waste in a chemistry and temperatu...
Laboratory tests were conducted to investigate the stress corrosion cracking (SCC) of 304L stainless...
Liquid waste generated by the PUREX process for separation of nuclear materials is concentrated and ...
Irradiation-assisted stress corrosion cracking is a costly degradation mechanism for austenitic stai...
Stress corrosion crack (SCC) growth rate tests and analytical electron microscopy (AEM) studies were...
Stress corrosion cracking (SCC) of ASME SA 516 Grade 70 steel was studied in hot (92°C) NaOH solu...
The stress corrosion cracking (SCC) of A516 Gr. 70 steel was investigated in three solution composed...
Stress corrosion cracking (SCC) of type 316 stainless steel was studied in hot (92°C) solutions of 3...
Stress corrosion cracking (SCC) refers to the damage of mechanical components which are under the co...
The stress corrosion cracking (SCC) of an At ST C-1018 mild steel was investigated in three solution...
The Hanford tank reservation contains approximately 50 million gallons of liquid legacy radioactive ...
Fracture mechanics techniques were employed to study stress corrosion cracking (SCC) of AISI C-1018 ...
The stress corrosion cracking (SCC) behaviour of low alloy steel AISI 4140 was investigated in 33% s...
A nuclear grade 316L stainless steel and a 508-111 quenched and tempered pressure vessel steel were ...
PhDThe stress-corrosion cracking of 0.08% C and 0.30% C steels in boiling nitrate solution has been ...
The evaporator recycle streams of nuclear waste tanks may contain waste in a chemistry and temperatu...
Laboratory tests were conducted to investigate the stress corrosion cracking (SCC) of 304L stainless...
Liquid waste generated by the PUREX process for separation of nuclear materials is concentrated and ...
Irradiation-assisted stress corrosion cracking is a costly degradation mechanism for austenitic stai...
Stress corrosion crack (SCC) growth rate tests and analytical electron microscopy (AEM) studies were...
Stress corrosion cracking (SCC) of ASME SA 516 Grade 70 steel was studied in hot (92°C) NaOH solu...
The stress corrosion cracking (SCC) of A516 Gr. 70 steel was investigated in three solution composed...
Stress corrosion cracking (SCC) of type 316 stainless steel was studied in hot (92°C) solutions of 3...
Stress corrosion cracking (SCC) refers to the damage of mechanical components which are under the co...
The stress corrosion cracking (SCC) of an At ST C-1018 mild steel was investigated in three solution...
The Hanford tank reservation contains approximately 50 million gallons of liquid legacy radioactive ...
Fracture mechanics techniques were employed to study stress corrosion cracking (SCC) of AISI C-1018 ...
The stress corrosion cracking (SCC) behaviour of low alloy steel AISI 4140 was investigated in 33% s...