AMPP Store - Products tagged with 'environmental degradation 2022'

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A Novel Approach To Simulate Realistic Concrete Microstructures Under Irradiation

Product Number: ED22-17280-SG

Author: Amani Cheniour, Yujie Li, Elena Tajuelo Rodriguez, Shane C. Henderson, Yann Le Pape, José David Arregui Mena, Thomas M. Rosseel

Publication Date: 2022

$20.00

The concrete biological shields (CBSs) of light water reactors are affected by neutron and gamma irradiation at high radiation doses, resulting in the degradation of the concrete’s material properties. Several studies in the literature focused on evaluating both the expansion of aggregate-forming minerals and the resulting loss of mechanical properties. Modeling efforts have been carried out to predict the
radiation-induced volumetric expansion (RIVE) and damage using different numerical methods such as the finite element method or fast-Fourier transform (FFT).

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Acceleration Of 316L Stainless Steel Corrosion By Proton-Irradiation-Induced Displacement Damage In Hydrogenated Steam

Product Number: ED22-17134-SG

Author: Rigel D. Hanbury, Jonas K. Heuer, Gary S. Was

Publication Date: 2022

$20.00

From stress corrosion cracking of baffle-former bolts to radiological hazards from Co-60, corrosion of structural materials is the root of many operational issues that occur in light water nuclear reactors. Corrosion must be controlled to mitigate the risks of larger problems that reduce the operational time and lifespan of a reactor. One fundamental feature of nuclear reactors is the radiation field which is known to impact corrosion behavior. However, there is a severe lack of understanding the underlying mechanisms of radiation effects on corrosion, especially for stainless steels. Ion irradiation experiments allow for the controlled study of radiation effects on corrosion and to compensate for the lack of reactor data on structural materials.

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Acceleration Of Long-Range Ordering in NiCrFe Alloys Using Proton Irradiation

Product Number: ED22-18352-SG

Author: Cole Evered, Nicholas Aerne, David J. Sprouster, Julie D. Tucker

Publication Date: 2022

$20.00

The extension of nuclear reactor lifetimes beyond 40 years requires the qualification of plant components to ensure performance past their initial design requirements. Nickel-based alloys containing chromium (NiCr) are of concern at these extended lifetimes, as these types of alloys form an embrittling precipitate phase. Below a critical temperature—which is above the normal 300-400⁰C reactor operating temperatures—NiCr alloys form a stable, fully coherent MoPt2-typelong-range ordered (LRO) phase with stoichiometry Ni2Cr.

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Adhesion And Wear Resistance Of PVD Nitride-Based Coatings On Zircaloy Substrates

Product Number: ED22-17266-SG

Author: C.Dever, H.M. Nordin, M.Mattucci

Publication Date: 2022

$20.00

The Fukushima Daiichi Accident in 2011, which was the result of the Great East Japan Earthquake, tsunami, and prolonged station blackout, increased the focus on developing accident tolerant fuel cladding (ATFC), especially on the use of protective coatings. Coatings have been widely used in a variety of industries, including automotive, aerospace, and nuclear to improve corrosion resistance, enhance hardness and physical properties, and reduce wear. In an accident scenario, a coating may aid in reducing the oxidation kinetics and hydrogen evolution rates. The present study investigates the benefits that physical vapour deposited nitride-based coatings may have for ATFC.

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Alloy 182 Models for the Prediction of the Susceptibility to SCC of BMI Nozzle J-welds

Product Number: ED22-17286-SG

Author: Thierry Couvant

Publication Date: 2022

$20.00

Stress Corrosion Cracking (SCC) models are important for engineering and regulatory assessments. The SCC time to the growth of a crack of engineering scale is the main fraction of component life prior to failure and is therefore of significant interest for modeling. However, the stochastic characteristics of early crack development is challenging for model development and validation.

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An Experimental Method for Environmental Assisted Fatigue of 304L Stainless Steel in Simulated LWR Water

Product Number: ED22-18335-SG

Author: Mustafa Subasic, Jean Smith, Pål Efsing, Martin Bjurman, Mattias Thuvander, Carl Dahlberg, Bo Alfredsson

Publication Date: 2022

$20.00

Environmental assisted fatigue, also known as corrosion fatigue, is a well-known degradation phenomenon in structural materials that may develop as a consequence of long-time exposure of components to cyclic loads at the presence of an aggressive environment. This phenomenon constitutes an increased environmental risk for fatigue initiation in many industrial applications. One such application is the piping system in a nuclear power plant where the structural material is subjected to an aggressive water environment. Here, the cyclic loads arise from thermal fluctuations and mechanically induced vibrations.

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Application Of Digital Image Correlation (DIC) And Infrared Thermography Techniques To Evaluate Fuel Cladding Behavior During Accident Conditions

Product Number: ED22-18327-SG

Author: Samuel Bell, Ben Garrison, Nathan Capps, Ryan Sweet, Kenneth Kane

Publication Date: 2022

$20.00

Accident scenarios, such as a loss-of-coolant accident (LOCA), subject claddings to rapid thermal transients, internal loading, and a high temperature steam environment. Understanding cladding behavior in this dynamic setting allows for better assessment of safety concerns such as coolant flow blockage and fuel relocation and dispersal. Improvement in model predictability and multi-physics fuel performance codes such as BISON are at the forefront of cladding related research. Particularly, efforts aim at addressing model accuracy to support burnup extension and increases in fuel cycle lengths.

Assessing Environmentally Assisted Cracking Of Structural Alloys In Molten Salts

Product Number: ED22-17120-SG

Author: George Young, Jake Quincey, Andrew Brittan, Pit Shulze, Stella Tsotsos, Lars Parrington, Josef Parrington, Anne Demma, Micah Hackett, Samuel Briggs and Julie D. Tucker

Publication Date: 2022

$20.00

The potential for structural alloys to undergo environmentally assisted cracking in molten salts is relatively unexplored due to their limited industrial application. However, fluoride salts are of prime interest to many advanced reactors including the Kairos Power FHR reactors. Table I summarizes literature studies of EAC in molten fluoride salts. For the ten studies shown, seven are for Ni-Mo-Cr family of alloys (INOR-8 / Hastelloy N or variants) that were used in the Molten Salt Reactor Experiment (MSRE), two studies investigate austenitic stainless steels, and there is one report of EAC in oxygen free high conductivity (OFHC) copper.

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Assessing Stainless Steel Compatibility in Flowing Fluoride Salts

Product Number: ED22-18337-SG

Author: B. A. Pint, C. G. Parker, Y.-F. Su, D. Sulejmanovic, M. J. Lance, R. Pillai

Publication Date: 2022

$20.00

There is considerable interest in molten halide salts for several applications including thermal storage and next generation nuclear reactors. While molten salt as a working fluid and/or fuel media offers advantages, salt compatibility with structural and functional materials is a concern. Various reports in the literature suggest that chloride and fluoride salts can be highly corrosive to structural alloys but do not always clearly describe how the salt was handled and dried/purified prior to and during the corrosion experiment.

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Assessment Of Neutron Irradiation Damage In Aggregates

Product Number: ED22-17265-SG

Author: Elena Tajuelo Rodriguez, Lawrence M. Anovitz, Michael Cheshire, Yann Le Pape, Jan Ilavsky, Thomas M. Rosseel

Publication Date: 2022

$20.00

The required electrical power in the United States has led the utilities and the US Nuclear Regulatory Commission to evaluate second license renewals for operating light-water reactors, and some extensions have already been reviewed for extended operation to 80 years. As these plants were licensed to operate for 40 years with options for additional 20 year extensions, the extended operation raised questions in terms of materials performance under extreme conditions and extended time. The effects of prolonged irradiation must be understood and evaluated to predict and ensure the reliability of plant components.

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Characterization of 304 Stainless Steel Crack Tips Exhibiting High Temperature Retardation in Deaerated Water

Product Number: ED22-18392-SG

Author: Robert Morris, Tyler Moss, David Morton, Kevin Fisher

Publication Date: 2022

$20.00

Understanding and mitigating stress corrosion cracking (SCC) in stainless steels used in light water reactors is important, and experimental efforts to characterize this behavior have been performed over the last several decades. While SCC growth has been shown to follow an Arrhenius temperature functionality, a departure from this functionality has been observed due to high temperature SCC growth rate retardation (HTR). This paper characterizes observed trends between different cold work levels and temperature effects on cracking behavior and crack tip morphologies in 304 stainless steel.

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Characterization Of Grain Boundary Cavity Evolution During Long-Term Crack Initiation Testing Of Cold Worked Alloy 690 In Simulated PWR Primary Water

Product Number: ED22-17324-SG

Author: Ziqing Zhai, Mychailo Toloczko, Stephen Bruemmer

Publication Date: 2022

$20.00

Determining the resistance of high-Cr Ni-base Alloy 690 to environmental degradation during long-term pressurized water reactor (PWR) exposure is needed to confirm its viability as the replacement material for Alloy 600 and help establish a quantitative factor of improvement for stress corrosion crack (SCC) initiation. SCC initiation testing on cold-worked (CW) Alloy 600 materials in PWR primary water has demonstrated that intergranular (IG) attack is the precursor to SCC initiation in this material. In comparison, an equivalent degradation and cracking process does not exist in CW Alloy 690.

Products tagged with 'environmental degradation 2022'

Association for Materials Protection and Performance