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3445 total products found.
Picture for Determination Of Activation Energies Of Thermally Aged Nuclear Cable Insulation Materials
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Determination of Activation Energies for Nuclear Electrical Cable Insulation Using Density and Total Color Difference

Product Number: ED22-17336-SG
Author: D.Li, Y.Ni, A.Zwoster, M.R. Pallaka, M.Spencer, L.S. Fifield
Publication Date: 2022
$20.00

Electrical cables are critical components of nuclear power plants (NPPs) that ensure their safe operation. In use they are exposed to a wide range of environmental stresses, such as elevated temperature, gamma radiation, moisture, and electrical stress. Among the different environmental stresses, elevated temperature leads to the thermo-oxidative degradation of electrical cable insulation, which may cause early failure of electrical cables and subsequently lead to unplanned plant shutdowns, electrical transients, and/or a loss of safety redundancy.
Picture for Evaluation Of Copper Catalytic Effects In Cable Insulation Polymers
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Evaluation Of Copper Catalytic Effects In Cable Insulation Polymers

Product Number: ED22-17260-SG
Author: Trevor Toll, Casey Sexton, Codi Ferree, Patrick Ward
Publication Date: 2022
$20.00

This paper summarizes work performed to evaluate a phenomenon that can occur in electrical cable insulation polymers during the aging process. This phenomenon, the copper catalytic effect, occurs because of diffusion of copper ions from the conductor into the insulation polymers during the aging process. In this research, the copper catalytic effects observed in cross-linked polyethylene, cross-linked polyolefin, and ethylene propylene rubber insulation subjected to thermal accelerated aging at both 120˚C and 130 ˚C were evaluated. In addition, the insulation polymers from cables removed from service in operating nuclear power plants were also evaluated to determine if this effect is prevalent for naturally aged materials. The results acquired from this work were used to characterize the copper catalytic effects observed in these polymers, analyze how this phenomenon affects the degradation process of the materials, and determine the impact that the copper catalytic effect has on condition monitoring data acquired during the aging process.
Picture for SCC Behavior Of Alloy 52M Weld Butter On SA-508 LAS From The Double-Repair Dissimilar Metal Weld In A PWR Environment
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SCC Behavior Of Alloy 52M Weld Butter On SA-508 LAS From The Double-Repair Dissimilar Metal Weld In A PWR Environment

Product Number: ED22-17283-SG
Author: Bogdan Alexandreanu, Yiren Chen
Publication Date: 2022
$20.00

This paper presents the results of a confirmatory research program conducted with the purpose of evaluating the susceptibility of Nickel-base Alloy 690 and 52/152 and variant welds to stress corrosion cracking (SCC) with a focus on the SCC response of Alloy 52/152 weldments with repairs.Nickel-base Alloy 690 and the associated weld Alloys 52 and 152 are typically used for nozzle penetrations in replacement heads for pressurized water reactor (PWR) vessels, repairs of existing components as well as for designs of advanced nuclear reactors because of their increased resistance to stress corrosion cracking (SCC) relative to Alloys 600, 82, and 182. 
Picture for Multi-Axial Fatigue Specimen Design, Testing And Fracture Analysis
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ulti-Axial Fatigue Initiation Testing and Specimen Characterization of 304 Stainless Steel

Product Number: ED22-18372-SG
Author: Eleanor M Grieveson, Peter Gill, Paul Onwuarolu, Ben Coult, Alistair Garner
Publication Date: 2022
$20.00

Current fatigue assessments for the fatigue life of a plant component are usually based on methodologies that use uniaxial fatigue test data (i.e. ASME Section III, and are intended to be conservative for design and fitness-for-purpose assessments when applied to plant components and loading. This data is generated through cyclic loading of specimens at a constant amplitude, and failure is usually defined as when there is a load drop of 25% from steady state stress under strain-controlled conditions (or specimen separation for stress control). The corresponding number of cycles is then used as the definition of fatigue life for a particular strain amplitude. It is known that there are differences between fatigue behaviour in an idealised laboratory setting and in-service components which can contribute to excessive conservatism in plant assessments.
Picture for 10307 Sulfide Stress Cracking Resistance Limit for a 125KSI Grade High Strength Low Alloy Steel OCTG
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10307 Sulfide Stress Cracking (SSC) Resistance Limits for a 125KSI Grade High Strength Low Alloy Steel OCTG Developed for Mildly Sour Service

Product Number: 51300-10307-SG
ISBN: 10307 2010 CP
Author: Tomohiko Omura, Taro Ohe, Toshiharu Abe, Masakatsu Ueda, Perry Ian Nice and John W. Martin
Publication Date: 2010
$20.00
Picture for Water Chemistry In Fusion Cooling Systems: Assessment Of Borated Water For The DTT Vacuum Vessel
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DTT Vacuum Vessel Cooling Circuit: Borated Water Chemistry Assessment

Product Number: ED22-17307-SG
Author: Claudia Gasparrini, Luigi Di Pace, Nicholas Terranova, Rosaria Villari, Emanuela Martelli, Piergiorgio Sonato, Mauro Dalla Palma, Giuseppe G Scatigno
Publication Date: 2022
$20.00

Water chemistry definition in nuclear fusion research experiments is under development. Many nuclear fusion experiments, such as the Italian Divertor Tokamak Test Facility (DTT)[1], the Korea Superconducting Tokamak Advanced Research (KSTAR) [2] and Japan Torus-60 Super Advanced (JT60SA) [3] reactors consider the use of enriched boric acid (up to 95% 10B) in water to shield the superconducting coils by neutrons generated from nuclear fusion reactions in the plasma chamber.
Picture for LWR Aging Management For Life Beyond 80
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LWR Aging Management For Life Beyond 80

Product Number: ED22-17299-SG
Author: Thomas M. Rosseel, Xiang Chen, Elena Tajuelo Rodriguez, Mikhail Sokolov, Maxim Gussev, Yann Le Pape, Frank Garner, Leo S. Fifield, S. W. Glass
Publication Date: 2022
$20.00

Based on US Energy Information Administration (EIA) Annual Energy Outlook (AOE) predictions, by 2050, the US nuclear capacity for electricity generation may decrease to ~ 80% of 2021 levels, Moreover, by 2050, nearly 50% of the existing US LWR fleet will be within 10 years of 80 years of operation suggesting that without a Life Beyond 80 (LBE) plan and limited new builds and advanced reactors, the US could lose up to 50% of its nuclear capacity resulting in a ~30-gigawatt (GW) capacity shortage by 2060. These numbers could change dramatically depending upon oil and gas supplies, and the growth of renewables.
Examination of Corrosion Sensor Data from Long-Term Field Exposures
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Examination Of Corrosion Sensor Data From Long-Term Field Exposures

Product Number: 51322-18198-SG
Author: Erica Macha, Andrew Keller, Shengyen Li, James Dante
Publication Date: 2022
$20.00

The current approach to corrosion severity prediction is to use long-term averages of environmental parameters (such as relative humidity, temperature, and pollutants), geographic features (such as coastal proximity), and witness coupon corrosion rates of indicator materials to classify an environment into one of a small number of severity categories. However, recent work has revealed that brief changes in environmental conditions—even those lasting only a few hours—can significantly affect total corrosion damage, and long-term averages of environmental conditions are not sufficient to accurately predict cumulative corrosion damage. To more accurately measure the corrosion damage from these short-term events, corrosion sensors are becoming increasingly popular.  The frequent acquisition of data and increased measurement sensitivity are attractive features, however the data from these corrosion sensors is still difficult to interpret in many cases.   
Picture for The Complexity And Challenges Of Irradiation-Induced Phase Instability Phenomenon In Nuclear Power Plant Components
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The Complexity And Challenges Of Irradiation-Induced Phase Instability Phenomenon In Nuclear Power Plant Components

Product Number: ED22-17322-SG
Author: D.A. Merezhko, M.N. Gussev, M.S. Merezhko, T.M. Rosseel, F. A. Garner
Publication Date: 2022
$20.00

Austenitic stainless steels (AuSS) are widely used as structural materials for nuclear reactor vessel internals (RVIs), as well as for fuel cladding and pressurizer components. Some of these components cannot be removed and replaced, and therefore the irradiation performance of the steel determines the lifetime of each reactor component. Typical irradiation-induced detrimental effects in light water-cooled power reactors include embrittlement, accelerated creep, and radiation-altered corrosion. Some second-order effects such as void swelling, hydrogen accumulation, and radiation-induced phase instability might be slowly evolving to first-order importance, especially as Western nuclear power plants are being considered for lifetime extensions to 60 and possibly 80 total years.
Picture for Dealloying And Its Relationship To SCC Of Alloy 800 And Ni-Fe-Cr Alloys In Boiling Caustic Solutions

Dealloying And Its Relationship To SCC Of Alloy 800 And Ni-Fe-Cr Alloys In Boiling Caustic Solutions

Product Number: ED22-17138-SG
Author: Hooman Gholamzadeh, Adil Shaik, Bander Alsekhan, Kevin Daub, Matthew Topping, Mark R. Daymond, Suraj Persaud
Publication Date: 2022
$20.00

Ni-based alloys and stainless steels have superior mechanical properties and good resistance to general and localized corrosion, mainly due to the formation of a passive film. Due to their properties, Ni-based
alloys and stainless steels have been historically used in applications where an aggressive environment is involved. For example, Ni- and Fe- based alloys have been extensively used in the nuclear power
industry. Despite their good corrosion performance, these materials have been shown to suffer from environmentally assisted cracking (EAC) in certain environments.
Picture for Environmental Degradation Of Materials Considered For Accident Tolerant Fuels In Light Water Reactors.
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Environmental Degradation Of Materials Considered For Accident Tolerant Fuels In Light Water Reactors.

Product Number: ED22-17252-SG
Author: Michael D. Worku, Russ M. Fawcett, Rajnikant V. Umretiya, Dan R. Lutz, AndrewK. Hoffman, Evan J. Dolley, Liang Yin, Liang Yin, Raul B. Rebak
Publication Date: 2022
$20.00

In recent years and months some countries started to label nuclear energy as clean energy because it does not increase the carbon footprint in the planet. Figure 1 shows that nuclear energy is the largest contribution of clean (or green) energy in the USA. This clean energy comes from the commercial operation of boiling water reactors (BWR) and pressurized water reactors (PWR). The total number of nuclear power reactors in the USA is slowly decreasing in time because they became non-economical to operate compared to the burning of natural gas. The International Atomic Energy Agency (IAEA) reported that in 2013 there were 102 light water reactors (LWR) producing electricity in the USA, but in 2020 the total LWR number decreased to 94 due to the decommissioning of eight reactors.
Picture for Acceleration Of Ni2cr Ordered Phase Formation Via Proton Irradiation
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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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