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At least 1,531 records · Page 85

Nuclear Canister Corrosion Detection

The software titled "nccd" is used for running residual neural networks (ResNets) on images of nuclear canisters. The software provides only the code for the implementation (based on the fastai library), but it does not share the image data. The compute code allows the use of residual nets (and more generally of other deep learning models) for classifying images from nuclear canisters as corroded. or intact. An image is considered to be corroded if it contains pitting or stress corrosion cracks. The code trains ResNets on image tiles extracted from original images from nuclear canisters, and then implements a classification rule, which can be applied to a validation set to decide if each original image is corroded or intact. The software automates the process of using images taken from nuclear canisters to detect corrosion. It provides also scope for future research directions on the basis of the existing research and code.

Papamarkou, Theodore↗

Materials Selection for the Lead-Bismuth Corrosion and Erosion Tests in DELTA Loop

This report documents the selection of materials participating in the currently ongoing corrosion/erosion tests in LANL Development of Lead-Alloy Technology and Applications (DELTA) loop, a facility designed to study the long-term corrosive effects of liquid lead-bismuth eutectic (LBE) on structural materials for high temperature applications in advanced reactors, accelerator-driven systems and spallation sources. In this suite of experiments, LBE temperature in the DELTA loop test section is 500°C. Oxygen sensors are used to maintain an LBE Oxygen concentration of 1x10 -6 to 1x10 -8 wt%. Unique to the experimental conditions is the LBE high flow-rate of 3-3.5 m/s in the test section. Results obtained in these corrosion tests represent a substantial extension from existing experimental data currently limited to LBE velocities of maximum ~2 m/s.

36 MATERIALS SCIENCE↗

Exploration and Modeling of Structural changes in Waste Glass Under Corrosion

The corrosion of nuclear waste glasses is a complex process involving adsorption, diffusion, ionexchange, hydrolysis and precipitation of mineral alteration phases. These processes occur in parallel and their relative rates change significantly over the long term. Corrosion models are required to accurately reflect the long-term durability of vitrified high level waste so that geologic repositories can be designed to meet the targets of stability and security, and at the same time, make better utilization of the storage volume by increasing the density of HLW in the glass.

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗

Superhydrophobic Powder Additives to Enhance Chemical Agent Resistant Coating Systems for Military Equipment for the US Marine Corps (USMC) Corrosion Prevention and Control (CPAC) Program

The primary goal of the CPAC program at ORNL was to explore the feasibility of introducing various silica-based superhydrophobic (SH) powder additives as a way to improve the corrosion resistance of US Department of Defense (DOD) military-grade chemical agent resistant coating (CARC) systems. ORNL had previously developed and patented several SH technologies of interest to the USMC, and one of the objectives of this program was to identify methods to incorporate these technologies into the USMC’s corrosion-resistance strategy. This report discusses findings of the CPAC and their application.

45 MILITARY TECHNOLOGY, WEAPONRY, AND NATIONAL DEF↗

Preparation and testing of corrosion and spallation-resistant coatings

The goal of this project was to take a recently developed method of bonding oxide dispersion-strengthened (ODS) FeCrAl plating to nickel superalloys closer to commercial use in syngas-fired turbines. The project was designed to better understand and develop the bonding process and to determine if plating APMT®, a specific highly oxidation-resistant ODS FeCrAl alloy made by Kanthal, onto nickel-based superalloy turbine parts is a viable method for substantially improving the lifetimes and maximum use temperatures of the parts. The superalloys investigated for protection were CM247LC and Rene® 80, both alumina scale-forming alloys. The method for bonding the APMT plate to the superalloys is called evaporative metal bonding, which involves placing a thin foil of zinc between the plate and the superalloy, clamping them together, and heating in an atmosphere-controlled furnace. Upon heating, the zinc melts and dissolves the oxide skins of the alloys at the bond line, allowing the two alloys to diffuse into each other. The zinc then diffuses through the alloys and evaporates from their surfaces, creating a bond between the APMT and the superalloy that is stronger than the APMT itself. Testing showed that the diffusivity of zinc in both APMT and CM247LC is quite similar at 700°C but 15 times higher in the APMT at 1214°C. Coefficients of thermal expansion were determined for each of the alloys as a function of temperature. This information was entered into a finite-element model using ANSYS, which was used to design a clamping jig for pressing the APMT to the superalloys at the bonding temperature. Scanning electron microscopy analyses of representative joints showed that no zinc remained in the alloys after bonding Unfortunately, the analyses also showed some small pieces of broken aluminum oxide scale near the bond lines, indicating that its scale was not sufficiently removed during prebonding cleaning. Samples from each of the bonded blocks were sent to Siemens for its standard oxidation, spallation, and corrosion testing, which was scheduled for completion in the spring of 2016. However, because of commercial demands, the tests were not completed by the time of this report except some initial spallation tests at 1150°C. In those tests, several of the APMT plates separated from the CM247LC, likely because of the remaining aluminum oxide scale on the surface of the CM247LC. This implies that surface preparation may need to include machining to remove the oxide scale before bonding rather than just sandblasting. In previous tensile testing at 950°C, the breaks in the tensile samples always occurred in the APMT and not at the joints. Gasifier sampling was completed to determine what types of trace contaminants may occur in cleaned and combusted syngas and that could lead to corrosion or deposition in turbines firing coal syngas. The sampling was done from a pressurized fluidized-bed gasifier and a pressurized entrained-flow gasifier. The particles captured on a filter from syngas were typically 0.2 to 0.5 μm in diameter, whereas those captured from the combusted syngas were slightly larger and more spherical. X-ray photoelectron spectroscopy done at Oak Ridge National Laboratory showed that the particles do not contain any metals and have an atomic composition almost identical to that of the polycarbonate filter. This indicates that the particles are primarily soot-based and not formed from volatilization of metals in the gasifiers.

20 FOSSIL-FUELED POWER PLANTS↗

Impact of Glycolate Anion on Aqueous Corrosion in DWPF and Downstream Facilities

Glycolic acid is being evaluated as an alternate reductant in the preparation of high level waste for the Defense Waste Processing Facility (DWPF) at the Savannah River Site (SRS). During processing, the glycolic acid may not be completely consumed with small quantities of the glycolate anion being carried forward to other high level waste (HLW) facilities. The SRS liquid waste contractor requested an assessment of the impact of the glycolate anion on the corrosion of the materials of construction (MoC) throughout the waste processing system since this impact had not been previously evaluated. A literature review revealed that corrosion data were not available for the MoCs in glycolic-bearing solutions applicable to SRS systems. Data on the material compatibility with only glycolic acid or its derivative products were identified; however, data were limited for solutions containing glycolic acid or the glycolate anion. For the proprietary coating systems applied to the DWPF concrete, glycolic acid was deemed compatible since the coatings were resistant to more aggressive chemistries than glycolic acid. Additionally similar coating resins showed acceptable resistance to glycolic acid.

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗

Irradiation Assisted Stress Corrosion Cracking of Austenitic Stainless Steel in BWR Conditions

As a first step toward full scale utilization of the Advanced Test Reactor (ATR) and associated post irradiation examination (PIE) equipment at INL, the NRC and INL staffs have formulated a test program that is designed to help to establish INL and the Nuclear Science User Facilities (NSUF) as a viable destination for irradiation and PIE of reactor structural materials. This initial research program utilized two materials (304 Stainless Steel weld Heat Affected Zone (HAZ) and sensitized 304L stainless steel) that have previously been irradiated at the Halden reactor in Norway and tested at Argonne National Laboratory (ANL) so that test results may be compared, thereby establishing a measure of comparability between Halden and ATR irradiations. A secondary objective of this test program was to characterize the quality of data produced using INL’s newly constructed irradiation assisted stress corrosion cracking (IASCC) test cells. The specimens were be tested in typical boiling water reactor (BWR) conditions to measure stress corrosion cracking (SCC) and fracture toughness of un-irradiated specimens and then IASCC and fracture toughness of specimens irradiated to a fluence equal to approximately 1.0 X 10 21 n/cm 2 (E > 1 MeV).

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS↗

Evaluating Corrosion in SAVY Containers using Non-Destructive Techniques

Powerpoint presentation on Ultrasonic and Eddy Current NDT; UT Theory; Eddy current (ECA): How it works; Controlled Corrosion at NM Tech; Results – HCl Corrosion; Waveform Data for 10M HCl; Accuracy Statistics; Results – FeCl 3 Pitting; Waveforms for Anhydrous FeCl 3 ; Analyzing Corroded Stainless Steel 316L Plates; 316L Plate to Imitate Pitting; ECA Pit Depth Calibration Curve; C Scan Imaging; UT Pit Detection; SST Containers: Ultrasonic (UT) vs. CMM; UT Data Analysis; UT Conclusions and Observations; ECA Conclusions; Automated System Vision.

36 MATERIALS SCIENCE↗

Impact of Glycolate Anion on Aqueous Corrosion in DWPF and Downstream Facilities

Glycolic acid is being evaluated as an alternate reductant in the preparation of high level waste for the Defense Waste Processing Facility (DWPF) at the Savannah River Site (SRS). During processing, the glycolic acid may not be completely consumed with small quantities of the glycolate anion being carried forward to other high level waste (HLW) facilities. The SRS liquid waste contractor requested an assessment of the impact of the glycolate anion on the corrosion of the materials of construction (MoC) throughout the waste processing system since this impact had not been previously evaluated. A literature review revealed that corrosion data were not available for the MoCs in glycolic-bearing solutions applicable to SRS systems. Data on the material compatibility with only glycolic acid or its derivative products were identified; however, data were limited for solutions containing glycolic acid or the glycolate anion. For the proprietary coating systems applied to the DWPF concrete, glycolic acid was deemed compatible since the coatings were resistant to more aggressive chemistries than glycolic acid. Additionally, similar coating resins showed acceptable resistance to glycolic acid.

36 MATERIALS SCIENCE↗

Thermal Inertia Mapping to Quantify Corrosion Thinning in Metal Containers Final Report CRADA No. TSB-1149-95

The purpose of the CRADA was to adapt the unique thermal initial algorithms developed by LLNL to the Bales processor. The goal was to produce a single corrosion defect map that would eliminate clutter from excess sealants, ripples and surface features. This type of map could be incorporated in a commercial dual-band infrared (DBIR) scanner, making it easier to assess corrosion damage.

36 MATERIALS SCIENCE↗

Historical Review of Stress Corrosion Cracking in Concentrated Uranium-Molybdenum Alloys

This report presents a historical overview of stress corrosion cracking (SCC) in uranium-molybdenum alloys, focusing primarily on U-10 wt. pct. Mo (U-10Mo). This alloy has been chosen as the high density uranium monolithic fuel for converting research reactors from high enriched uranium (HEU) to low enriched uranium (LEU) fuel for its combination of fuel density and gamma phase stability. One disadvantage of U-10Mo is its propensity towards stress corrosion cracking (SCC), driven by high residual stresses resulting from its high yield strength. This report contains a metallurgical overview of U-10Mo alloys incorporating processing, microstructural evolution, and mechanical properties. This report also summarizes SCC literature including contributing factors, initiation and propagation, the mechanism responsible for U-10Mo SCC, and possible solutions to the problem. A brief synopsis of interviews with key personnel from several Department of Energy (DOE) facilities and BWX Technologies (BWXT) is also included. Recommendations for future studies are outlined.

22 GENERAL STUDIES OF NUCLEAR REACTORS↗

Accelerating High-Level Waste Glass Corrosion Research with Big Data

Savannah River National Laboratory (SRNL) is accelerating the research of high-level nuclear waste (HLW) glass corrosion using advanced big data techniques available through the Accelerated Leaching and Testing of GLASS (ALTGLASS) database. Developed, maintained and distributed by SRNL, ALTGLASS gives HLW researchers access to chemical durability data for hundreds of glass compositions, allowing scientists to use an “informatics approach” to analyze existing and new experimental data contained in the database to advance glass corrosion science.

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗

Design and Irradiation of a Molten Salt Corrosion Experiment in the Ohio State University Research Reactor

The primary containment system of any molten salt reactor (MSR) will be exposed to corrosive salt at high temperatures (>650°C) (McDuffee et al. 2018). Many MSR designs also use dissolved fuel, which introduces the challenge of fission product–induced corrosion. Even those designs that do not call for dissolved fuel might need to address the deleterious effects of dissolved fission products on the fuel containment system and potential particle failure.

22 GENERAL STUDIES OF NUCLEAR REACTORS↗

Innovative Technologies for Optical Detection of Stress Corrosion Cracks

Stress corrosion cracks (SCC) represent a major concern for the structural integrity of engineered metal structures. In hazardous or restricted-access environments, remote detection of corrosion or SCC frequently relies on visual methods; however, with standard VT-1 visual inspection techniques, probabilities of SCC detection are low. Here, we develop and evaluate an improved optical sensor for SCC in restricted access-environments by combining a robotically controlled camera/fiber-optic based probe with software-based super-resolution imaging (SRI) techniques to increase image quality and detection of SCC. SRI techniques combine multiple images taken at different viewing angles, locations, or rotations, to produce a single higher- resolution composite image. We have created and tested an imaging system and algorithms for combining optimized, controlled camera movements and super- resolution imaging, improving SCC detection probabilities, and potentially revolutionizing techniques for remote visual inspections of any type.

36 MATERIALS SCIENCE↗

Hydrothermal Corrosion of Second Generation FeCrAl Alloys in Boiling Water Reactor Conditions

As part of an effort to develop advanced fuel cladding for use in light water reactors, several ORNL-developed FeCrAl alloys were tested in BWR conditions to determine their resistance to hydrothermal corrosion. Coupons with alloy compositions Fe-10Cr-6Al-2Mo, Fe-13Cr-5Al-2Mo, Fe-13Cr-6Al-2Mo, Fe-13Cr-7Al-2Mo, and Fe-13Cr-5Al-2Mo-1Nb were tested in BWR-NWC and BWR-HWC for 9 months in continuously refreshing autoclaves. Commercial APMT and Zircaloy-2 were also tested for comparison. Among samples exposed to HWC, Alloy C06M (10Cr-6Al) performed best, with a mass loss of 0.34 mg/cm 2 over 9 months, and C037M performed worst with a mass loss of 1.2 mg/cm 2 over 9 months. This mass loss was similar to Gen-1 FeCrAl alloys, and represents an estimated annual thickness loss of approximately a few µm per year. Samples exposed to NWC had very small mass losses of less than 0.15 mg/cm 2 or mass gains up to 0.05 mg/cm 2 . These represent very small annual losses in thickness. Based on the results of this testing, the Gen-2 FeCrAl alloys tested have suitable resistance to hydrothermal corrosion for use as fuel cladding in BWR-NWC and BWR-HWC conditions.

22 GENERAL STUDIES OF NUCLEAR REACTORS↗

K-3 Refractory Corrosion and Sulfate Solubility Model Enhancement (Final Report)

As higher waste loading LAW glasses are formulated, sulfate solubility and K-3 refractory corrosion are two properties that become increasingly constraining; however, WTP baseline models were not developed for these properties. In previous work for ORP, VSL/Atkins developed preliminary glass property-composition models that relate LAW glass composition to these two essential properties to support the implementation of the higher waste loading LAW glass formulations at the WTP. The development of the initial LAW glass property-composition models for K-3 refractory corrosion and sulfate solubility was completed in 2015. The present work scope focused on enhancement of these models and included augmentation of property-composition datasets for these two properties with newly available data, review of the updated datasets, and development of enhanced models.

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗

Corrosion growth model for previously vacuum-baked LiH

In this report, a hydroxide corrosion growth model is proposed for the reaction of previously vacuum-baked LiH samples with moisture. The model is then validated experimentally by subjecting a previously vacuum-baked polycrystalline LiH sample to 35 ppm of H 2 O at room temperature while monitoring the corrosion growth as a function of time with diffuse-reflectance infrared Fourier transform (DRIFT) spectroscopy. Kinetic parameters extracted from the validating experiments can be used to make long-term prediction.

36 MATERIALS SCIENCE↗

LiOH corrosion growth and thermal stability investigated by diffuse reflectance infrared Fourier Transform (DRIFT) spectroscopy

In this period, we have measured the kinetics of LiOH corrosion growth on LiH substrate at 35 ppm of moisture for over 2 months. The serial DRIFT spectra are being analyzed to build the growth kinetics for LiOH interfacial states, surface states, and bulk states. Physical chemistry insight is being employed to describe the observed parabolic-linear growth of the corrosion layer grown on LiH samples that have been previously vacuum baked then re-exposed to low moisture over a long time. The thermal stabilities of LiOH interfacial states, surface states, and bulk states are also being quantified by measuring the reduction in LiOH DRIFT signals as a function of vacuum level and temperature, and will be needed to add an on/off switch to the current outgassing modeling.

36 MATERIALS SCIENCE↗