The Minerals, Metals & Materials Series - Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors

Scoring Process for Evaluating Laboratory PWSCC Crack Growth Rate Data of Thick-Wall Alloy 690 Wrought Material and Alloy 52, 152, and Variant Weld Material

The Minerals, Metals & Materials Series - Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors ◽

10.1007/978-3-030-04639-2_1 ◽

2018 ◽

pp. 3-14

Author(s):

Amanda R. Jenks ◽

Glenn A. White ◽

Paul Crooker

Keyword(s):

Growth Rate ◽

Crack Growth Rate ◽

Crack Growth ◽

Thick Wall ◽

Rate Data ◽

Weld Material ◽

Alloy 690

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Oxidation and SCC Initiation Studies of Type 304L SS in PWR Primary Water

The Minerals, Metals & Materials Series - Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors ◽

10.1007/978-3-030-04639-2_51 ◽

2017 ◽

pp. 793-810

Author(s):

F. Scenini ◽

J. Lindsay ◽

Litao Chang ◽

Y. L. Wang ◽

M. G. Burke ◽

...

Keyword(s):

Primary Water

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Using Modern Microscopy to “Fingerprint” Secondary Side SCC in Ni–Fe Alloys

The Minerals, Metals & Materials Series - Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors ◽

10.1007/978-3-030-04639-2_163 ◽

2017 ◽

pp. 2421-2451

Author(s):

S. Y. Persaud ◽

J. M. Smith ◽

C. D. Judge ◽

M. Bryk ◽

R. C. Newman ◽

...

Keyword(s):

Fe Alloys ◽

Secondary Side

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Influence of Alloying Elements and Effect of Stress on Anisotropic Hydrogen Diffusion in Zr-Based Alloys Predicted by Accelerated Kinetic Monte Carlo Simulations

The Minerals, Metals & Materials Series - Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors ◽

10.1007/978-3-030-04639-2_122 ◽

2017 ◽

pp. 1815-1826 ◽

Cited By ~ 1

Author(s):

Jianguo Yu ◽

Chao Jiang ◽

Yongfeng Zhang

Keyword(s):

Monte Carlo ◽

Monte Carlo Simulations ◽

Hydrogen Diffusion ◽

Kinetic Monte Carlo ◽

Alloying Elements ◽

Kinetic Monte Carlo Simulations

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Steam Oxidation Behavior of FeCrAl Cladding

The Minerals, Metals & Materials Series - Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors ◽

10.1007/978-3-030-04639-2_96 ◽

2017 ◽

pp. 1451-1460

Author(s):

B. A. Pint ◽

K. A. Terrani ◽

R. B. Rebak

Keyword(s):

Oxidation Behavior ◽

Steam Oxidation

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Accident Tolerant FeCrAl Fuel Cladding: Current Status Towards Commercialization

The Minerals, Metals & Materials Series - Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors ◽

10.1007/978-3-030-04639-2_91 ◽

2017 ◽

pp. 1381-1389

Author(s):

Kevin G. Field ◽

Yukinori Yamamoto ◽

Bruce A. Pint ◽

Maxim N. Gussev ◽

Kurt A. Terrani

Keyword(s):

Current Status ◽

Fuel Cladding

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Interdiffusion Behavior of FeCrAl with U3Si2

The Minerals, Metals & Materials Series - Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors ◽

10.1007/978-3-030-04639-2_92 ◽

2017 ◽

pp. 1391-1400

Author(s):

Rita E. Hoggan ◽

Lingfeng He ◽

Jason M. Harp

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Aqueous Degradation in Harvested Medium Voltage Cables in Nuclear Power Plants

The Minerals, Metals & Materials Series - Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors ◽

10.1007/978-3-030-04639-2_80 ◽

2017 ◽

pp. 1257-1265

Author(s):

R. C. Duckworth ◽

A. Ellis ◽

B. Hinderliter ◽

E. Hill ◽

M. Maurer-Jones

Keyword(s):

Nuclear Power ◽

Power Plants ◽

Nuclear Power Plants ◽

Medium Voltage

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Frequency Domain Reflectometry Modeling and Measurement for Nondestructive Evaluation of Nuclear Power Plant Cables

The Minerals, Metals & Materials Series - Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors ◽

10.1007/978-3-030-04639-2_81 ◽

2017 ◽

pp. 1267-1280

Author(s):

S. W. Glass ◽

L. S. Fifield ◽

A. M. Jones ◽

T. S. Hartman

Keyword(s):

Power Plant ◽

Nuclear Power Plant ◽

Nondestructive Evaluation ◽

Frequency Domain ◽

Nuclear Power ◽

Frequency Domain Reflectometry

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Mechanistic Understanding of Environmentally Assisted Fatigue Crack Growth of Austenitic Stainless Steels in PWR Environments

The Minerals, Metals & Materials Series - Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors ◽

10.1007/978-3-030-04639-2_61 ◽

2017 ◽

pp. 957-986

Author(s):

S. L. Medway ◽

D. R. Tice ◽

N. Platts ◽

A. Griffiths ◽

G. Ilevbare ◽

...

Keyword(s):

Fatigue Crack ◽

Fatigue Crack Growth ◽

Crack Growth ◽

Stainless Steels ◽

Austenitic Stainless Steels ◽

Mechanistic Understanding

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The Minerals, Metals & Materials Series - Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors
Latest Publications

TOTAL DOCUMENTS

H-INDEX

Published By Springer International Publishing

Scoring Process for Evaluating Laboratory PWSCC Crack Growth Rate Data of Thick-Wall Alloy 690 Wrought Material and Alloy 52, 152, and Variant Weld Material

Oxidation and SCC Initiation Studies of Type 304L SS in PWR Primary Water

Using Modern Microscopy to “Fingerprint” Secondary Side SCC in Ni–Fe Alloys

Influence of Alloying Elements and Effect of Stress on Anisotropic Hydrogen Diffusion in Zr-Based Alloys Predicted by Accelerated Kinetic Monte Carlo Simulations

Steam Oxidation Behavior of FeCrAl Cladding

Accident Tolerant FeCrAl Fuel Cladding: Current Status Towards Commercialization

Interdiffusion Behavior of FeCrAl with U3Si2

Aqueous Degradation in Harvested Medium Voltage Cables in Nuclear Power Plants

Frequency Domain Reflectometry Modeling and Measurement for Nondestructive Evaluation of Nuclear Power Plant Cables

Mechanistic Understanding of Environmentally Assisted Fatigue Crack Growth of Austenitic Stainless Steels in PWR Environments

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The Minerals, Metals & Materials Series - Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water ReactorsLatest Publications

TOTAL DOCUMENTS

H-INDEX

Published By Springer International Publishing

Scoring Process for Evaluating Laboratory PWSCC Crack Growth Rate Data of Thick-Wall Alloy 690 Wrought Material and Alloy 52, 152, and Variant Weld Material

Oxidation and SCC Initiation Studies of Type 304L SS in PWR Primary Water

Using Modern Microscopy to “Fingerprint” Secondary Side SCC in Ni–Fe Alloys

Influence of Alloying Elements and Effect of Stress on Anisotropic Hydrogen Diffusion in Zr-Based Alloys Predicted by Accelerated Kinetic Monte Carlo Simulations

Steam Oxidation Behavior of FeCrAl Cladding

Accident Tolerant FeCrAl Fuel Cladding: Current Status Towards Commercialization

Interdiffusion Behavior of FeCrAl with U3Si2

Aqueous Degradation in Harvested Medium Voltage Cables in Nuclear Power Plants

Frequency Domain Reflectometry Modeling and Measurement for Nondestructive Evaluation of Nuclear Power Plant Cables

Mechanistic Understanding of Environmentally Assisted Fatigue Crack Growth of Austenitic Stainless Steels in PWR Environments

The Minerals, Metals & Materials Series - Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors
Latest Publications