AMPP Store - Products tagged with 'environmental degradation 2022'

Development And Application Of A Thermochemical Database (MSTDB-TC) To Modeling Corrosion In Molten Salt Reactors

Product Number: ED22-17137-SG

Author: Theodore M. Besmann, Jacob A. Yingling, Johnathan C. Ard, Matthew S. Christian, Amir M. Mofrad, Juliano Schorne Pinto, Mahmoud A. A. Aslani

Publication Date: 2022

$20.00

Accurate representations of the thermochemistry and phase equilibria of relevant molten salt constituents and their aggregate behavior are critical to the development, design, operation, and licensing of any molten salt reactor (MSR). This need is currently being addressed by the creation of a dedicated, high quality/validated MSR thermochemical database, the Molten Salt Thermal Properties Database-Thermochemical (MSTDB-TC). MSTDB-TC is being populated with prioritized models and values for vapor species, and liquid and crystalline phases of chloride and fluoride fuel and coolant salts with relevant fission product and transuranic elements, and more recently with corrosion-relevant systems with chromium, iron, and nickel. Multi-cation crystalline and melt solution models are being incorporated, including newly developed relations as necessary, to obtain real system behavior.

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Diffusion Limited Oxidation of XLPE Nuclear Electrical Cable Insulation

Product Number: ED22-17263-SG

Author: M. Spencer, D. Li, M.R. Pallaka, L.S. Fifield, W.K Fuchs, Y. Ni, A. Zwoster

Publication Date: 2022

$20.00

Approximately 20% of the electricity produced in the United States (U.S.) comes from nuclear power plants (NPPs). Originally, U.S. NPPs were qualified for an operational lifetime of 40 years and NPPs can apply for 20-year license extensions following the original 40-year operating period. While most NPPs have entered extended license periods to 60 years, some are considering license extension to 80 years of operation. The viability of a subsequent license renewal (SLR) is dependent upon NPPs operating safely in accordance with a licensing basis similar to that established with the original 40-year license.

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Discussion On Long Range Ordering Of Ni-Based Alloys Used In BWR Environment

Product Number: ED22-18533-SG

Author: Yun Wang, Ryoji Obata, Shinichi Ishioka

Publication Date: 2022

$20.00

Due to the strength, ductility, fracture toughness, corrosion resistance and especially the coefficient of thermal expansion, which is between stainless steel and low alloy steel, Ni-based alloys are used as weld metals in BWR and ABWR internals. Ni-based alloys with high chromium (Cr) concentration, such as Alloy 52 (Cr: 28-31.5 wt.%), Alloy 52i (Cr: 26-28 wt.%) and so on are expected to have higher SCC resistance than 182 (Cr: 13-17 wt.%) and Alloy 82 (Cr: 18-22 wt.%) in BWR environment.

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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.

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Effect of Applied Stress on the Selective Oxidation of Alloy 600 Exposed To PWR Primary Water and Rhines Pack Environments

Product Number: ED22-17328-SG

Author: Karen Kruska, Ziqing Zhai, Brian J Riley, Matthew J Olszta, Daniel K Schreiber

Publication Date: 2022

$20.00

Alloy 600 is known to be susceptible to intergranular attack (IGA) and stress corrosion cracking (SCC) under pressurized water reactor (PWR) primary water conditions, leading to the replacement of some steam generator components with the more SCC-resistant Alloy 690.3 Despite this shift many Alloy 600 components are still found in service today. A substantial body of research has identified many underlying processes leading to the degradation of Alloy 600.

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Effect of Complex Deformation on Corrosion Fatigue and Stress Corrosion Cracking of 304/304L Stainless Steel Elbows in Aerated and Deaerated Water

Product Number: ED22-17115-SG

Author: William C. Moshier, Kevin B. Fisher, Justin R. Hesterberg, and Denise J. Par

Publication Date: 2022

$20.00

Stress corrosion cracking (SCC) growth in 300-series stainless steels (SS) exposed to high temperature water is known to generally increase with increasing levels of cold work. The influence of cold work on SCC has been reported for both oxygenated boiling water reactor (BWR) normal water chemistry as well as for hydrogenated pressurized water reactor (PWR) water chemistry.

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Effect Of Dissolved Oxygen On The SCC Susceptibility And Oxidation Of Cold-Worked 316L SS In PWR Primary Water

Product Number: ED22-17254-SG

Author: Thalita De Paula, Cécilie Duhamel, Catherine Guerre, Jérôme Crépin, Ian De Curières, Frédéric Datcharry, Marc Maisonneuve

Publication Date: 2022

$20.00

Austenitic stainless steels (SS), such as 304L and 316L alloys, are largely used for structural components in nuclear power plants due to their good corrosion resistance, especially under high temperatures and aqueous environments. However, operational experience on the primary circuit of pressurized water reactors (PWRs) has shown an increasing number of cases of stress corrosion cracking (SCC) on austenitic stainless steels components after long-term exposure.

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Effect Of Heat Treatment, Cold Working And Long-Term Ageing In Air On The Stress Corrosion Cracking Growth Rate In Simulated PWR Primary Water For Commercial TT

Product Number: ED22-18356-SG

Author: Toshio Yonezawa, Atsushi Hashimoto

Publication Date: 2022

$20.00

About 39 years ago, the first author of this paper has successfully developed the Thermally Treated (TT) Alloy 690, with his colleagues from Mitsubishi Heavy Industries, Ltd. at that time and with people from Sumitomo Metal Industries, Ltd. (the company name at that time, now Nippon Steel Corporation). And they have practically applied TT Alloy 690 to steam generator (SG) tubes. The developed TT
Alloy 690 consists of the combinations between the fully solution heat treatment (SHT) condition before TT and carbon content, particularly selected with an optimized microstructure verified by transmission electron microscopy (TEM).

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Effect Of Localized Stress On Initiation Of IGSCC

Product Number: ED22-17308-SG

Author: Takaharu Maeguchi, Kyohei Hayakawa, Kimihisa Sakima, Tomotaka Miyazawa

Publication Date: 2022

$20.00

In a polycrystalline material, the stress distribution on a microscopic scale is not uniform due to the elastic anisotropy and slip systems of constituent crystal grains. This leads to localized high stresses, especially at grain boundaries, when a load is applied to the material. In this paper, this localized stress is called as “microscopic stress”, distinguishing it from that in a homogeneous continuous body.

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Effect Of Microstructure On Mechanical Behaviour Of Ni-Base Alloy Dissimilar Metal Welds

Product Number: ED22-17104-SG

Author: Noora Hytönen, Yanling Ge, Zaiqing Que, Sebastian Lindqvist, Jari Lydman, Ulla Ehrnstén, Paavo Rautala,Iikka Virkkunen, Pål Efsing

Publication Date: 2022

$20.00

Dissimilar metal welds (DMWs) are commonly used in the pressure vessel nozzle to safe-end weld between the ferritic low-alloy steels (LAS) and the austenitic stainless steels (SS), using a nickel-base filler metal. The complex DMW interface consists of different microstructural regions including, for instance, the heat-affected zone (HAZ), carbon-depleted zone (CDZ), carbon build-up at fusion boundary, partially melted zone (PMZ) and carbide precipitation zone. There is still knowledge lacking on the microstructural characteristics of the interface of DMWs upon post-weld heat treatment (PWHT). DMWs are potential concerns regarding the structural integrity of the nuclear power systems. In particular, the LAS/nickel-base alloy weld metal interface is known to develop a local strength mismatch upon PWHT and during long-term ageing. A significant chemical composition gradient, especially in terms of carbon (C) and chromium (Cr) associated with a complex microstructure have been observed to form at the interfaces. The different welding orientation, heat transfer and PWHT can result in different microstructure and mechanical properties.

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Effect Of Residual Strain On Short Time Oxidation Kinetics In PWR Simulated Primary Water

Product Number: ED22-17127-SG

Author: Rachel E. Turfitt, John A. Savchik, Bryan A. Webler, Kevin B. Fisher

Publication Date: 2022

$20.00

Type 304 stainless steel is commonly used in pressurized water reactor (PWR) primary circuits, where it is exposed to high temperature, high pressure water. Combination of material and environment influence the oxidation behavior in these systems. In addition to oxidation of the surface, 304 is also susceptible to stress corrosion cracking and corrosion fatigue, which are both types of environmentally assisted cracking, or EAC. EAC is a function of prior material condition, environment, and stress induced during exposure.

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Effect Of Thermal Aging On The Microstructure And Mechanical Properties Of High-Ni And Ni-Base Alloys

Product Number: ED22-17125-SG

Author: Caitlin Huotilainen, Zaiqing Que, Yanling Ge, Petteri Lappalainen, Noora Hytönen, Ritva Korhonen, Santtu Huotilainen

Publication Date: 2022

$20.00

High-strength materials with excellent corrosion resistance and mechanical properties are highly sought after for use in light water reactor (LWR) type nuclear power plants (NPP). In western pressurized water reactors (PWR), nickel-base alloys are often the main structural materials for the steam generator (SG) tubes, while in Russian PWRs or water-water energetic reactor (VVER) high-nickel alloys, for example XH35BT (35 wt.% Ni), can be found in some primary side high strength applications, such as reactor pressure vessel internals (RVI).

Products tagged with 'environmental degradation 2022'

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