Published: 2023-08-05

Articles

Effect of PWHT on Dominating Parameters Affecting SCC Growth Rate of Ni-base Weld Metals

K. Kumagai, Takayuki Kaminaga
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Effect of Water Chemistry on Crack Growth Rates in Neutron Irradiated Additively Manufactured 316L and 718

Drew C. Johnson, Michael McMurtrey, Michael Heighes, John Jackson, Myles Connor, P.L. Andresen
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Interim Result of a Detailed Investigation on a Cracked Pipe Weld in the Pressurizer Spray Line of a PWR in Japan

Yasufumi Miura, Dan Akazawa, Taku Arai, R. Saeki
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Irradiation Assisted Stress Corrosion Cracking of 304L and 347 Stainless Steel Alloys in Simulated PWR Primary Water

Abdullah S. Sinjlawi, Lijin Dong, Srinivasan Swaminathan, Mickael Ickes, Kai Sun, Gary S. Was
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Investigating the effect of hydrodynamics and coolant chemistry on CRUD deposition in regions of accelerated fluid flow.

Liam Smith, Peter Johnstone, Jonathan Duff, Nathan Lee, Fred Lord, Michele Curioni, Fabio Scenini
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SCC damage identification of 718 alloy, obtained by laser powder bed fusion (LPBF) in simulated PWR medium

Vanina Pelouard, Didier Bardel, Eric Andrieu
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Durability of Online NobleChem™ During Impurity Transients in Boiling Water Reactors

M. Mura, P.L. Andresen, J. Giannelli
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Understanding the effect of temperature on the fatigue crack growth of austenitic stainless steels in hydrogenated water

Benjamin Howe, M.G. Burke, R. Mann, N. Riddle, Fabio Scenini
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Radiation Damage in a PWR Baffle-Bolt CW 316 Austenitic Stainless Steel Irradiated by Self-ions at High Doses and Temperatures: Comparison with a Fast Reactor Irradiation

Jan Michalička, Z. Jaio, Gary S. Was
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The Role of Delta Phase in the Stress Corrosion Cracking (SCC) of Alloy 718 in Simulated Pressurized Water Reactor (PWR) Primary Water (PW) Environment

Mi Wang, Maio Song, Gary S. Was
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Best Practices for Fracture Mechanics Based Testing for Environmentally Assisted Cracking in Advanced Reactor Applications

Andrew Brittan, Mark Petkov, Pierre-Alexandre Juan, Kevin Chan, Micah J. Hackett, Brian P. Somerday, George A. Young
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Industrially Scalable Fabrication of Additively Manufactured Molybdenum Alloys

M.J. Brand, J. Goodrich, R.A. Bloom, E.L. Tegtmeier, J.S. Carpenter
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Non-Destructive Detection of Spinodal Decomposition in Cast Austenitic Stainless Steels

Aljazzy K. Alahmadi, Thak Sang Byun, James J. Wall, Kuba Anglin, M. Grace Burke, Cody A. Dennett, Samuel W. McAlpine, Benjamin R. Dacus, Saleem A. Al Dajani, Michael P. Short
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IGSCC initiation and crack growth models for cold worked stainless steels

Thierry Couvant, Romain Badyka, Claire Rainasse, Maxine Mison, Emmanuel Lemaire
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The effect of different sizes and shapes of 304 Stainless Steels on the oxide removal by electrochemical decontamination

Fu-Sheng Wang, Tsung-Kuang Yeh, Mei-Ya Wang
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Surface and intergranular oxidation in simulated primary water of model Alloy 600 with aluminum and magnesium oxide inclusions.

Colette Perez, Thierry Couvant, Cecile Duhamel, Vincent Guipont, G. Kermouche, Eric Visse, Lara Arasse-Amanzou
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Stress Corrosion Crack Growth Testing of Weld Root Defects: Test Techniques and Implications for Testing of Smaller Welding-Induced Defects

Denise J. Paraventi, Heather H. Mohr, Robert A. Etien
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A Novel Facility for Studying Corrosion via in-situ Raman Spectroscopy and Proton Irradiation: Oxidation of Proton Irradiated and Cold-Worked SS 304L in Water at 300°C

V.S. Ramsundar, Kevin Daub, Suraj Y. Persaud, Mark R. Daymond
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Preferential intergranular oxidation of Alloy X-750 spacers in CANDU off-chemistry environments

A.E. Yaedu, L. Volpe, A. Shaik, F. Long, Kevin Daub, Fabio Scenini, Suraj Y. Persaud
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Effect of Chloride and Sulfate Transients on Crack Growth Rates of Stainless Steels and Alloy 182 Welds

P.L. Andresen
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SCC Crack Growth Rate Testing of LPBF Additive 316L SS

P.L. Andresen, S. Tate
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An Investigation into High Temperature Water Corrosion on Reduced Activation Ferritic Martensitic Steel Eurofer 97

D. Kumar, R. Clark, T. Martin, M. Zimina, P.L. Andresen, L. Volpe, R. Burrows
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Laboratory Analysis of Lower End Cap Weld

C.D. Williams, J.W. Hyres, George F. Borum
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Testing of Lead Stress Corrosion Cracking (PbSCC) Inhibitor Candidate

B.M. Campbell, Nicholas Huin, J. Smith
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Study on SCC Growth Resistance of Nickel-base Alloy Weld Materials with High Chromium Content in BWR Environments

Takahiro Hayashi, S. Yoshida, M. Itatani, H. Takahashi, M. Itow
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Impact of Hydrogen on SCC of Ni Alloys in Low Hydrogen Environments

Ainsley C. Pinkowitz, Timothy D. Boldt, David S. Morton
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The Effect of Shot Peening on Corrosion and Deuterium Pickup in Zr-2.5Nb

H.M. Nordin
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Methodology for Assessing Stainless Steel Compatibility in Fluoride Salts at 550°-850°C

B.A. Pint, D. Sulejmanovic, R. Pillai
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Effects of long-term isothermal aging on microstructural and mechanical property evolution in ferritic-martensitic steels for sodium-cooled fast reactor applications

A. Koziol, Benjamin Adam, David Sprouster, C. Huotilainen, Julie D. Tucker
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Coupled Microstructure-Based Stress Corrosion Cracking Simulations of Type 304 Stainless Steel with Fast Fourier Transform Crystal Plasticity

Benjamin S. Anglin
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Investigation of Short Crack Nucleation in Cold Worked Alloy 690 and its Weld Metals under Constant Load in Simulate PWR Primary Water

Ziqing Zhai, Karen Kruska, J. Liu, Mychailo Toloczko
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In Situ Strain Analysis of Cr-coated Zircaloy-4 Under Simulated LOCA Conditions

M.J. Ridley, S.B. Bell, N.A. Capps
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High-resolution microscopy investigation of early SCC initiation of Alloy 182 in simulated PWR primary water

Matthew Olszta, Ziqing Zhai, Nicole Overman, Mychailo Toloczko
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Corrosion and stress corrosion cracking behavior of 316 L stainless steel produced by additive manufacturing wire processes in water environments

Michaela Goland, Catherine Guerre, Josiane Nguejio, Matthias Rousseau, Fanny Balbaud, Joel Ribis, Paul Buttin
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Scratch Beneath the Surface: Corrosion Performance of Wire-Based AM 308L Stainless Steel and the Effect of Surface Finish

C.L. Clark, L.B. O’Brien, W.P. Winter, J.A. Stull
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High Temperature Creep and Fatigue Deformation and Mechanisms of Alloy 800H Weldments Using Different Filler Materials

Wenjing Li, Lin Xiao, Maurizio Ienzi, Greg Kasprick, Robyn Sloan, Lori Walters
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Effect of Helium Concentrations on Weldability of Irradiated Stainless Steel 304

Wenjing Li, Jian Chen, Jonathan Tatman, Zhili Feng, Matthew Latour, Roger Miller, Lori Walters, Thomas M. Rosseel, Greg Frederick
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Hydrogen and Oxygen Analyzer in high Gamma Radiation

John Doe
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Irradiation and Oxygen Effects on Silicon Carbide Corrosion under Hydrothermal Conditions

L. Qiu, L. Yao, C. McGregor
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Microstructure evolution and degradation of mechanical properties due to short-term thermal aging of cast austenitic stainless steels

S. Mehboob, H.J. Eom, C. Jang, S.S. Kang
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Development of Fatigue Crack Growth Rate Equations for Ni-Base Alloys

K.J. Fuhr, G.A. White, D.J. Shim
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Radiolysis modeling in PWR core. A parametric analysis based on radiation field contributors along fuel assemblies and simulation of the inhibition of water α-radiolysis via H2 addition

Damien Kaczorowski, Jérôme Roland
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Accelerated characterization of Zircaloy-4 and ATF cladding creep behavior in accident relevant conditions

S.B. Bell, M.J. Ridley, C.P. Massey, N.A. Capps
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First-principles study on stability of intermetallic phases in Cr-alloy coated Zr-alloy cladding of nuclear fuel

Y. Chen, T. Davey, N-D. Tran, Hiroshi Abe
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Overview of the EPRI-NRC Ni-Base Alloy Primary Water Stress Corrosion Cracking Initiation Testing Project

E. Focht, C. Wax, Mychailo Toloczko
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The Effects of Water Chemistry on Zn and Co Incorporation in the Oxide of 316 SS formed in Simulated BWR water

Dora Capone, Y. Wada, H. Hosokawa, T. Ito, Fabio Scenini, M.G. Burke, J. Duff, K. Mukahiwa, E. Aradi, M. Nagase
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Crack Growth Rate in Irradiated Core Barrel Weld and Heat-Affected Zone in PWR Primary Water

A. Jenssen, J. Stjarnsater, J.M. Smith
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Corrosion and Cracking of Short Listed Cladding Materials for Supercritical Water-Cooled Reactors

Lefu Zhang, Tao Huang, Haozhan Su, Jiamei Wang, Kai Chen
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Modelling SCC crack tip electrochemistry of austenitic stainless steel in high temperature water

Yule Wua, Lefu Zhang
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Urania fuel degradation to U3O8 and point defects and fission products studies.

Jayangani I. Ranasinghe, Barbara Szpunar, Jerzy A. Szpunar
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A coupled analyses of water radiolysis and ECP for evaluation of the corrosive conditions in BWRs and PWRs

Kuniki Hata, Shunsuke Uchida, Satoshi Hanawa, Yasuhiro Chimi, Tomonori Satoh
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Corrosion behavior in simulated PWR primary water and microstructural changes of stainless steel welds after thermal aging and ion-irradiation

K. Fujii, T. Yamada, K. Yabuuchi, K. Fukuya
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Stress Corrosion Cracking, Fatigue and Combined Crack Growth Rates of Alloy 600 in a PWR environment

C. Gillen, J. Beswick, K. Cooper, S. Medway, J. Borg, T. Watkins
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HIGH TEMPERATURE MECHANICAL PERFORMANCE OF TYPE 316L STEELS MANUFACTURED BY POWDER METALLURGY HOT ISOSTATIC PRESSING

Mark D. Callaghan, Mark Chatterton, David Coon, Will Kyffin, Andrew Wisbey
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Factors Contributing to PLLA Biomedical Device Degradation During In-Core Irradiation

M. Tigwell, A. Armstrong
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Simulating High-Temperature Fretting Wear Degradation in Representative Environments

Anne McLellan, Salim El Bouzidi, Fabrice Guerout, Paul Feenstra, Brandon St Pierre
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Mechanical properties of CrN coatings on Zircaloy substrates for the development of accident-tolerant fuel cladding

Mahdi Bagheripoor, Hongbing Yu, Heidi Nordin
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Hydride Related Failure under Hoop Stress in Zircaloy-4 Cladding

N.A.P. Kiran Kumar, Wen Qin, M.S. Islam, Jerzy A. Szpunar
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Functionally Graded NiMo Overlays for Improved Corrosion Resistance in Molten Salts

Tim D. Hall, B.A. Pint, Holly Garich, Maria Inman, D. Sulejmanovic, Chad Beamer
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Quantification of Nickel Leaching Rates from Nickel-Bound Tungsten Carbide (WC) Rotors used in Primary Heat Transport System and Reactor Cooling System Mechanical Pump Seals

R. Ortega, J. Turnbull, J. Smith, C. Zhang, J. Vandal
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Mechanistic study of internal oxidation of alloy 690 in hydrogenated steam

Ai Riahi, Hao Zhu, Ali Eskandari, Suraj Y. Persaud, Roger C. Newman
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Assessing the performance of a novel Fe-based material for replacement of Co-based alloy Stellite in CANDU reactor components

H. Ha, Heidi Nordin
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Effect of surface finish on SCC susceptibility of 316L stainless steel in high-temperature oxygenated water

Hiroshi Abe, Yutaka Watanabe, Ken Oyama, Tadashi Tatsuki
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Stress corrosion crack growth behavior of precipitation hardening martensitic stainless steel in simulated BWR environment

Dan Akazawa, Yasufumi Miura, Kenji Kako, Taku Arai
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Effect of aerated transients on stress corrosion cracking of 316L SS in high temperature water

Marc Maisonneuve, T. De Paula, Catherine Guerre, Cecile Duhamel, Jerome Crepin, Ian De Curieres
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Effects of microstructure and environment's chemical composition on oxidation and IGSCC of alloy 600 on the secondary side of PWRs

Pierre Mestre-Rinn, Cecile Duhamel, R. Verlet, Thierry Couvant, A. Muccioli, O. De Bouvier
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Combined effects of chloride ion and dissolved oxygen on SCC growth of low-alloy steels in high temperature water

Tomohiro Takita, Hiroshi Abe, Yutaka Watanabe, Inagaki Hiromitsu
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Understanding the effect of stress on carburisation of Type 316H stainless steel in a simulated AGR gas coolant

James Rafferty, Sandor Palko, Marc Chevalier, Enrique Jiminez-Melero, Fabio Scenini
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Microstructural characterization on initial stage of IGSCC and TGSCC of Type316L stainless steel in PWR primary water environment

Shinji Fujimoto, Kimika Nishida, Hiroaki Tsuchiya
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Fatigue Performance of Additively Manufactured 316L Stainless Steel in Air

Yiren Chen, B. Alexandreanu, Xuan Zhang, W-Y. Chen
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TEM characterization of surface and crack oxidation of a 316L stainless steel in PWR water after hydrogenated-oxygenated cycles

Cecile Duhamel, Marc Maisonneuve, Catherine Guerre, Jerome Crepin, Ian De Curieres
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Te-Induced Embrittlement of Alloy 617 in Molten FLiNaK

Mohammad Umar Farooq Khan, Lesley Frame, Stephen S. Raiman
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Launch of Research Program for the Study of Leaking Repository Groundwater Interactions with Cladding and Used Fuel Container Materials During Spent SMR Fuel Storage

O.Y. Palazhchenko, Cassidy Perry, J.A. Flood, Jane P. Ferguson, William G. Cook, Xin Pang
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Recent Enhancements and Extensions of the OECD Nuclear Energy Agency FIRE Database (53)

Markus Beilmann, Abderrazzaq Bounagui, Laima Kuriene, Christian Northe, Marina Röwekamp, Andreas Werner
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