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Corrosion-fatigue crack-growth rates in austenitic stainless steels in light water reactor environments
Corrosion-fatigue crack-growth rates in austenitic stainless steels in light water reactor environments
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Corrosion-fatigue crack-growth rates in austenitic stainless steels in light water reactor environments

Gilman, J.D. ; Rungta, R. ; Hinds, P. ; Mindlin, H.

The International journal of pressure vessels and piping, 1988, Vol.31 (1), p.55-68 [Periódico revisado por pares]

Oxford: Elsevier Ltd

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2
Metallurgical Aspects of the Failure of the Point Pleasant Bridge
Metallurgical Aspects of the Failure of the Point Pleasant Bridge
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Metallurgical Aspects of the Failure of the Point Pleasant Bridge

Bennett, J A ; Mindlin, H

ASTM J. Testing Eval, 1973-03, Vol.1 (2), p.152-161

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3
Applications of EPRI Database on Environmentally Assisted Cracking in the Nuclear Industry
Applications of EPRI Database on Environmentally Assisted Cracking in the Nuclear Industry
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Applications of EPRI Database on Environmentally Assisted Cracking in the Nuclear Industry

Rungta, R ; Mindlin, H ; Gilman, J D

Computers in Corrosion Control; Houston, Texas; USA; 17-18 Mar. 1986, 1986-03, p.46-64

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4
CORROSION FATIGUE CRACK GROWTH RATES IN AUSTENITIC STAINLESS STEELS IN LIGHT WATER REACTOR ENVIRONMENTS
CORROSION FATIGUE CRACK GROWTH RATES IN AUSTENITIC STAINLESS STEELS IN LIGHT WATER REACTOR ENVIRONMENTS
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CORROSION FATIGUE CRACK GROWTH RATES IN AUSTENITIC STAINLESS STEELS IN LIGHT WATER REACTOR ENVIRONMENTS

Gilman, J O ; Rungta, R ; Hinds, P ; Mindlin, H

J.O. Gilman, R. Rungta, P. Hinds, H. Mindlin, Int. J. Pressure Vessels & Piping, vol. 31, no. 1, 1988, p. 55-68, 1988-01

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5
Verification of a Model for Predicting Corrosion-Fatigue Crack-Growth Rates in Austenitic Stainless Steels in Light Water Reactor Environments
Verification of a Model for Predicting Corrosion-Fatigue Crack-Growth Rates in Austenitic Stainless Steels in Light Water Reactor Environments
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Verification of a Model for Predicting Corrosion-Fatigue Crack-Growth Rates in Austenitic Stainless Steels in Light Water Reactor Environments

Gilman, J D ; Rungta, R ; Hinds, P ; Mindlin, H

Structural Mechanics in Reactor Technology. Vol. F. LWR Pressure Components; Lausanne; Switzerland; 17-21 Aug. 1987, 1987-08, p.253-258

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6
EDEAC-PC: EPRI DATABASE ON ENVIRONMENTALLY ASSISTED CRACKING IN NUCLEAR COMPONENTS
EDEAC-PC: EPRI DATABASE ON ENVIRONMENTALLY ASSISTED CRACKING IN NUCLEAR COMPONENTS
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EDEAC-PC: EPRI DATABASE ON ENVIRONMENTALLY ASSISTED CRACKING IN NUCLEAR COMPONENTS

Kuchinski, E J ; Anderson, D B ; Mindlin, H ; Syrett, B C ; Pathania, R

E.J. Kuchinski, D.B. Anderson, H. Mindlin, B.C. Syrett, and R. Pathania, Paper No. 109, Presented at CORROSION/92 (April 26 to May 1, 1992, Nashville, TN), Sponsored by NACE, $5, 1992-04

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7
Combined Low-Cycle Fatigue and Stress Relaxation of Alloy 800 and Type 304 Stainless Steel at Elevated Temperatures
Combined Low-Cycle Fatigue and Stress Relaxation of Alloy 800 and Type 304 Stainless Steel at Elevated Temperatures
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Combined Low-Cycle Fatigue and Stress Relaxation of Alloy 800 and Type 304 Stainless Steel at Elevated Temperatures

Jaske, C E ; Mindlin, H ; Perrin, J S

Fatigue at Elevat ed Temperatures, 1973, 365-375, 1973-01

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8
Cyclic Stress-Strain Behavior of Two Alloys At High Temperature
Cyclic Stress-Strain Behavior of Two Alloys At High Temperature
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Cyclic Stress-Strain Behavior of Two Alloys At High Temperature

Jaske, C E ; Mindlin, H ; Perrin, J S

Cyclic Stress-Strain Behavior--Analysis, Experimentation and Failure Prediction, 1973, 13-27, 1973-01

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