Author

Gary P. Wozadlo

Observed names: G Wozadlo, G. P. Wozadlo, G. Wozadlo, G. P. Wozadlo, G.P. Wozadlo, Wozadlo, G. P.

Observed institution: General Electric (United States)

OpenAlex ID: A5018819871

Low-Temperature Annealing: A Process to Mitigate Irradiation-Assisted Stress Corrosion Cracking

1995 · A.J. Jacobs, G.P. Wozadlo, et al. · CORROSION · 31

The concept of noble metal chemical addition technology for IGSCC mitigation of structural materials

1995 · S. Hettiarachchi, G.P. Wozadlo, et al. · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information) · 26

Irradiation-assisted stress corrosion cracking as a factor in nuclear power plant aging

1988 · A. J. Jacobs, G. P. Wozadlo · Journal of Materials Engineering · 26

Corrosion of Carbon Steel in Simulated Boiling Water and Superheat Reactor Environments

1965 · W. L. Pearl, G. P. Wozadlo · CORROSION · 26

High-temperature solution annealing as an IASCC mitigation technique

1991 · A. J. Jacobs, C. M. Shepherd, et al. · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information) · 16

Grain Boundary Composition and Irradiation-Assisted Stress Corrosion Cracking Resistance in Type 348 Stainless Steel

1994 · A.J. Jacobs, G.P. Wozadlo, et al. · CORROSION · 15

Investigation of the Protection Potential against IASCC

1992 · M. E. Indig, J. Lawrence Nelson, et al. · NACE CORROSION Conference · 15

Carbon Transport in Flowing Sodium

1971 · Prodyot Roy, Gary P. Wozadlo · Nuclear Technology · 12

Stress Corrosion Testing of Irradiated Type 304 SS Under Constant Load

1993 · A.J. Jacobs, G.P. Wozadlo, et al. · CORROSION · 10

General Corrosion of Incoloy-800® in Simulated Superheat Reactor Environment

1965 · W. L. Pearl, E. G. Brush, et al. · Nuclear Applications · 10

Effect of Neutron-Irradiation at 560 K on the Mechanical Properties in Austenitic Stainless Steels

1988 · Kiyotomo Nakata, Toshimi Yoshida, et al. · Journal of the Japan Institute of Metals and Materials · 7

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General Corrosion of Incoloy-800 in Simulated Superheat Reactor Environment

1964 · W.L. Pearl, E.G. Brush, et al. · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information) · 7

Fuel Cladding Corrosion Testing in Simulated Superheater Reactor Environment: Phase-II: Localized Corrosion of Stainless Steels and High Nickel Alloys

1964 · W. L. Pearl, G. G. Gaul, et al. · Nuclear Science and Engineering · 6

Use of a Constant Deflection Test to Evaluate Susceptibility to Irradiation-Assisted Stress Corrosion Cracking

1993 · A.J. Jacobs, G.P. Wozadlo, et al. · CORROSION · 5

Susceptibility to Intergranular Cracking in Pressurized High Temperature Water in Neutron-Irradiated Austenitic Stainless Steels

1988 · Kiyotomo Nakata, Toshimi Yoshida, et al. · Journal of the Japan Institute of Metals and Materials · 4

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General Corrosion of Materials for Nuclear Superheat Applications

1965 · W. Pearl, E. Brush, et al. · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information) · 4

Evaluation of irradiated fuel rods with pulsed eddy currents

1972 · General Electric Co., Sunnyvale, Calif. (USA). Breeder Reactor Dept., R. Asamoto, et al. · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information) · 3

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MASS TRANSPORT AND CORROSION OF STAINLESS STEELS IN FLOWING SODIUM SYSTEMS AT 1300$sup 0$F.

1969 · Prodyot Roy, G.P. Wozadlo, et al. · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information) · 3

Low-Temperature Annealing — a Process to Mitigate IASCC

1995 · A.J. Jacobs, G.P. Wozadlo, et al. · NACE CORROSION Conference · 2

A Novel Approach for Noble Metal Deposition on Surfaces for IGSCC Mitigation of Boiling Water Reactor Internals

1995 · S. Hettiarachchi, G.P. Wozadlo, et al. · NACE CORROSION Conference · 2

The Correlation of Grain Boundary Composition in Irradiated Type 348 Stainless Steel with IASCC Resistance

1994 · A.J. Jacobs, G.P. Wozadlo, et al. · NACE CORROSION Conference · 2

Influence of Zinc Additions on the Intergranular Stress Corrosion Crack Initiation and Growth of Sensitized Stainless Steel in High Temperature Water

1995 · S. Hettiarachchi, G.P. Wozadlo, et al. · NACE CORROSION Conference · 1

Stress Corrosion Testing of Irradiated Type 304SS under Constant Load

1991 · A. J. Jacobs, G. P. Wozadlo · NACE CORROSION Conference · 1

Tritium Analysis of Mixed-oxide Fuel Rods Irradiated in a Fast Flux.

1972 · General Electric Co., Sunnyvale, Calif. Breeder Reactor Dept., G Wozadlo, et al. · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information) · 1

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Carbon Transport Methods Under a Temperature Gradient in Flowing Sodium.

1970 · Prodyot Roy, G.P. Wozadlo · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information) · 1

Works count: 39

Citation count: 237

H-index: 10

I10-index: 10