WorldCat Identities

Chopra, O. K.

Overview
Works: 51 works in 88 publications in 1 language and 5,314 library holdings
Roles: Author, Editor
Classifications: TK9166,
Publication Timeline
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Most widely held works by O. K Chopra
Fracture toughness and crack growth rates of irradiated austenitic stainless steels by O. K Chopra( Book )

2 editions published in 2003 in English and held by 163 WorldCat member libraries worldwide

Effects of LWR coolant environments on fatigue design curves of austenitic stainless steels by O. K Chopra( Book )

3 editions published in 1999 in English and held by 108 WorldCat member libraries worldwide

Mechanism and estimation of fatigue crack initiation in austenitic stainless steels in LWR environments by O. K Chopra( Book )

3 editions published in 2002 in English and held by 106 WorldCat member libraries worldwide

Estimation of fracture toughness of cast stainless steels during thermal aging in LWR systems by O. K Chopra( Book )

2 editions published in 1994 in English and held by 104 WorldCat member libraries worldwide

Effects of alloy chemistry, cold work, and water chemistry on corrosion fatigue and stress corrosion cracking of nickel alloys and welds by O. K Chopra( Book )

3 editions published in 2001 in English and held by 103 WorldCat member libraries worldwide

Environmental effects on fatigue crack initiation in piping and pressure vessel steels by O. K Chopra( Book )

3 editions published in 2001 in English and held by 102 WorldCat member libraries worldwide

Effects of LWR coolant environments on fatigue design curves of carbon and low-alloy steels by O. K Chopra( Book )

2 editions published in 1998 in English and held by 102 WorldCat member libraries worldwide

Initial assessment of the mechanisms and significance of low-temperature embrittlement of cast stainless steels in LWR systems by O. K Chopra( Book )

4 editions published in 1990 in English and held by 102 WorldCat member libraries worldwide

Mechanical properties of thermally aged cast stainless steels from Shippingport Reactor components by O. K Chopra( Book )

2 editions published in 1995 in English and held by 73 WorldCat member libraries worldwide

Effect of LWR coolant environments on the fatigue life of reactor materials : draft report for comment by O. K Chopra( Book )

3 editions published between 2006 and 2014 in English and held by 38 WorldCat member libraries worldwide

Crack growth rates and metallographic examinations of alloy 600 and alloy 82/182 from field components and laboratory materials tested in PWR environments by B Alexandreanu( Book )

2 editions published in 2008 in English and held by 36 WorldCat member libraries worldwide

In light water reactors, components made of nickel-base alloys are susceptible to environmentally assisted cracking. This report summarizes the crack growth rate results and related metallography for field and laboratory-procured Alloy 600 and its weld alloys tested in pressurized water reactor (PWR) environments. The report also presents crack growth rate (CGR) results for a shielded-metal-arc weld of Alloy 182 in a simulated PWR environment as a function of temperature between 290 C and 350 C. These data were used to determine the activation energy for crack growth in Alloy 182 welds. The tests were performed by measuring the changes in the stress corrosion CGR as the temperatures were varied during the test. The difference in electrochemical potential between the specimen and the Ni/NiO line was maintained constant at each temperature by adjusting the hydrogen overpressure on the water supply tank. The CGR data as a function of temperature yielded activation energies of 252 kJ/mol for a double-J weld and 189 kJ/mol for a deep-groove weld. These values are in good agreement with the data reported in the literature. The data reported here and those in the literature suggest that the average activation energy for Alloy 182 welds is on the order of 220-230 kJ/mol, higher than the 130 kJ/mol commonly used for Alloy 600. The consequences of using a larger value of activation energy for SCC CGR data analysis are discussed
Crack growth rates and fracture toughness of irradiated austenitic stainless steels in BWR environments by O. K Chopra( Book )

2 editions published in 2008 in English and held by 36 WorldCat member libraries worldwide

In light water reactors, austenitic stainless steels (SSs) are used extensively as structural alloys in reactor core internal components because of their high strength, ductility, and fracture toughness. However, exposure to high levels of neutron irradiation for extended periods degrades the fracture properties of these steels by changing the material microstructure (e.g., radiation hardening) and microchemistry (e.g., radiation-induced segregation). Experimental data are presented on the fracture toughness and crack growth rates (CGRs) of wrought and cast austenitic SSs, including weld heat-affected-zone materials, that were irradiated to fluence levels as high as H"2x 10²¹ n/cm² (E> 1 MeV) (H"3 dpa) in a light water reactor at 288-300 C. The results are compared with the data available in the literature. The effects of material composition, irradiation dose, and water chemistry on CGRs under cyclic and stress corrosion cracking conditions were determined. A superposition model was used to represent the cyclic CGRs of austenitic SSs. The effects of neutron irradiation on the fracture toughness of these steels, as well as the effects of material and irradiation conditions and test temperature, have been evaluated. A fracture toughness trend curve that bounds the existing data has been defined. The synergistic effects of thermal and radiation embrittlement of cast austenitic SS internal components have also been evaluated
Effect of thermal aging and neutron irradiation on crack growth rate and fracture toughness of cast stainless steels and austenitic stainless steel welds by O. K Chopra( Book )

2 editions published in 2015 in English and held by 4 WorldCat member libraries worldwide

Degradation of LWR core internal materials due to neutron irradiation by O. K Chopra( Book )

2 editions published in 2010 in English and held by 3 WorldCat member libraries worldwide

Effect of LWR coolant environments on the fatigue life of reactor materials : final report by O. K Chopra( Book )

2 editions published in 2007 in English and held by 2 WorldCat member libraries worldwide

Crack growth rates in a PWR environment of nickel alloys from the Davis-Besse and V.C. Summer power plants by B Alexandreanu( )

1 edition published in 2006 in English and held by 0 WorldCat member libraries worldwide

Crack growth rates of irradiated nickel alloy welds in a PWR environment by B Alexandreanu( )

1 edition published in 2006 in English and held by 0 WorldCat member libraries worldwide

In light water reactors (LWRs), vessel internal components made of nickel-base alloys are susceptible to environmentally assisted cracking. A better understanding of the causes and mechanisms of this cracking may permit less conservative estimates of damage accumulation and requirements on inspection intervals. A program is being conducted at Argonne National Laboratory to evaluate the resistance of Ni alloys and their welds to environmentally assisted cracking in simulated LWR coolant environments. This report presents crack growth rate (CGR) results for Alloy 182 shielded-metal-arc weld metal in a simulated pressurized water reactor (PWR) environment at 320 C. Crack growth tests were conducted on 1-T compact tension specimens with different weld orientations from both double-J and deep-groove welds. The results indicate little or no environmental enhancement of fatigue CGRs of Alloy 182 weld metal in the PWR environment. The CGRs of Alloy 182 in the PWR environment are a factor of ≈5 higher than those of Alloy 600 in air under the same loading conditions. The stress corrosion cracking for the Alloy 182 weld is close to the average behavior of Alloy 600 in the PWR environment. The weld orientation was found to have a profound effect on the magnitude of crack growth: cracking was found to propagate faster along the dendrites than across them. The existing CGR data for Ni-alloy weld metals have been compiled and evaluated to establish the effects of key material, loading, and environmental parameters on CGRs in PWR environments. The results from the present study are compared with the existing CGR data for Ni-alloy welds to determine the relative susceptibility of the specific Ni-alloy weld to environmentally enhanced cracking
Crack growth rates of irradiated austenitic stainless steel weld heat affected zone in BWR environments( )

1 edition published in 2006 in English and held by 0 WorldCat member libraries worldwide

Effect of material heat treatment on fatigue crack initiation in austenitic stainless steels in LWR environments by O. K Chopra( )

1 edition published in 2005 in English and held by 0 WorldCat member libraries worldwide

Review of the margins for ASME code fatigue design curve effects of surface roughness and material variability by O. K Chopra( )

1 edition published in 2003 in English and held by 0 WorldCat member libraries worldwide

 
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Languages
English (42)