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Electrochemical Corrosion Studies For Modeling Metallic Waste Form Release Rates
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Book Synopsis Electrochemical Corrosion Studies for Modeling Metallic Waste Form Release Rates by :
Download or read book Electrochemical Corrosion Studies for Modeling Metallic Waste Form Release Rates written by and published by . This book was released on 2016 with total page 26 pages. Available in PDF, EPUB and Kindle. Book excerpt: The isotope 99Tc is an important fission product generated from nuclear power production. Because of its long half-life (t1/2 = 2.13.105 years) and beta-radiotoxicity ([beta]-= 292 keV), it is a major concern in the long-term management of spent nuclear fuel.1 In the spent nuclear fuel, Tc is present as an alloy with Mo, Ru, Rh, and Pd called the epsilon-phase, the relative amount of which increases with fuel burn-up.2 In some separation schemes for spent nuclear fuel, Tc would be separated from the spent fuel and disposed of in a durable waste form.3 Technetium waste forms under consideration include metallic alloys, oxide ceramics and borosilicate glass.4, 5 In the development of a metallic waste form, after separation from the spent fuel, Tc would be converted to the metal, incorporated into an alloy and the resulting waste form stored in a repository.6 Metallic alloys under consideration include Tc-Zr alloys, Tc-stainless-steel alloys and Tc- Inconel alloys (Inconel is an alloy of Ni, Cr and iron which is resistant to corrosion). To predict the long term behavior of the metallic Tc waste form, understanding the corrosion properties of Tc metal and Tc alloys in various chemical environments is needed but efforts to model the behavior of Tc metallic alloys are limited. 7 One parameter that should also be considered in predicting the long-term behavior of the Tc waste form, is the ingrowth of stable Ru that occurs from the radioactive decay of 99Tc (99Tc "99Ru + [beta]- ). After a geological period of time, significant amount of Ru will be present in the Tc and may affect its corrosion properties. Studying the effect of Ru on the corrosion behavior of Tc is also of importance.
Book Synopsis Corrosion Mechanisms for Metal Alloy Waste Forms - Experiment and Theory Level 4 Milestone M4FT-14LA0804024 Fuel Cycle Research & Development by :
Download or read book Corrosion Mechanisms for Metal Alloy Waste Forms - Experiment and Theory Level 4 Milestone M4FT-14LA0804024 Fuel Cycle Research & Development written by and published by . This book was released on 2014 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: This document meets Level 4 Milestone: Corrosion mechanisms for metal alloy waste forms - experiment and theory. A multiphysics model is introduces that will provide the framework for the quantitative prediction of corrosion rates of metallic waste forms incorporating the fission product Tc. The model requires a knowledge of the properties of not only the metallic waste form, but also the passive oxide films that will be generated on the waste form, and the chemistry of the metal/oxide and oxide/environment interfaces. in collaboration with experimental work, the focus of this work is on obtaining these properties from fundamental atomistic models. herein we describe the overall multiphysics model, which is based on MacDonald's point-defect model for passivity. We then present the results of detailed electronic-structure calculations for the determination of the compatibility and properties of Tc when incorporated into intermetallic oxide phases. This work is relevant to the formation of multi-component oxides on metal surfaces that will incorporate Tc, and provide a kinetic barrier to corrosion (i.e. the release of Tc to the environment). Atomistic models that build upon the electronic structure calculations are then described using the modified embedded atom method to simulate metallic dissolution, and Buckingham potentials to perform classical molecular dynamics and statics simulations of the technetium (and, later, iron-technetium) oxide phases. Electrochemical methods were then applied to provide some benchmark information of the corrosion and electrochemical properties of Technetium metal. The results indicate that published information on Tc passivity is not complete and that further investigation is warranted.
Book Synopsis Modeling Corrosion and Constituent Release from a Metal Waste Form by :
Download or read book Modeling Corrosion and Constituent Release from a Metal Waste Form written by and published by . This book was released on 2000 with total page 10 pages. Available in PDF, EPUB and Kindle. Book excerpt: Several ANL ongoing experimental programs have measured metal waste form (MWF) corrosion and constituent release. Analysis of this data has initiated development of a consistent and quantitative phenomenology of uniform aqueous MWF corrosion. The effort so far has produced a preliminary fission product and actinide release model based on measured corrosion rates and calibrated by immersion test data for a 90 C J-13 and concentrated J-13 solution environment over 1-2 year exposure times. Ongoing immersion tests of irradiated and unirradiated MWF samples using more aggressive test conditions and improved tracking of actinides will serve to further validate, modify, and expand the application base of the preliminary model-including effects of other corrosion mechanisms. Sample examination using both mechanical and spectrographic techniques will better define both the nature and durability of the protective barrier layer. It is particularly important to assess whether the observations made with J-13 solution at 900 C persist under more aggressive conditions. For example, all the multiplicative factors in Table 1 implicitly assume the presence of protective barriers. Under sufficiently aggressive test conditions, such protective barriers may very well be altered or even eliminated.
Book Synopsis Comprehensive Nuclear Materials by :
Download or read book Comprehensive Nuclear Materials written by and published by Elsevier. This book was released on 2020-07-22 with total page 4871 pages. Available in PDF, EPUB and Kindle. Book excerpt: Materials in a nuclear environment are exposed to extreme conditions of radiation, temperature and/or corrosion, and in many cases the combination of these makes the material behavior very different from conventional materials. This is evident for the four major technological challenges the nuclear technology domain is facing currently: (i) long-term operation of existing Generation II nuclear power plants, (ii) the design of the next generation reactors (Generation IV), (iii) the construction of the ITER fusion reactor in Cadarache (France), (iv) and the intermediate and final disposal of nuclear waste. In order to address these challenges, engineers and designers need to know the properties of a wide variety of materials under these conditions and to understand the underlying processes affecting changes in their behavior, in order to assess their performance and to determine the limits of operation. Comprehensive Nuclear Materials, Second Edition, Seven Volume Set provides broad ranging, validated summaries of all the major topics in the field of nuclear material research for fission as well as fusion reactor systems. Attention is given to the fundamental scientific aspects of nuclear materials: fuel and structural materials for fission reactors, waste materials, and materials for fusion reactors. The articles are written at a level that allows undergraduate students to understand the material, while providing active researchers with a ready reference resource of information. Most of the chapters from the first Edition have been revised and updated and a significant number of new topics are covered in completely new material. During the ten years between the two editions, the challenge for applications of nuclear materials has been significantly impacted by world events, public awareness, and technological innovation. Materials play a key role as enablers of new technologies, and we trust that this new edition of Comprehensive Nuclear Materials has captured the key recent developments. Critically reviews the major classes and functions of materials, supporting the selection, assessment, validation and engineering of materials in extreme nuclear environments Comprehensive resource for up-to-date and authoritative information which is not always available elsewhere, even in journals Provides an in-depth treatment of materials modeling and simulation, with a specific focus on nuclear issues Serves as an excellent entry point for students and researchers new to the field
Book Synopsis Corrosion Mechanisms for Metal Alloy Waste Forms by :
Download or read book Corrosion Mechanisms for Metal Alloy Waste Forms written by and published by . This book was released on 2014 with total page 44 pages. Available in PDF, EPUB and Kindle. Book excerpt: This document meets Level 4 Milestone: Corrosion mechanisms for metal alloy waste forms - experiment and theory. A multiphysics model is introduces that will provide the framework for the quantitative prediction of corrosion rates of metallic waste forms incorporating the fission product Tc. The model requires a knowledge of the properties of not only the metallic waste form, but also the passive oxide films that will be generated on the waste form, and the chemistry of the metal/oxide and oxide/environment interfaces. in collaboration with experimental work, the focus of this work is on obtaining these properties from fundamental atomistic models. herein we describe the overall multiphysics model, which is based on MacDonald's point-defect model for passivity. We then present the results of detailed electronic-structure calculations for the determination of the compatibility and properties of Tc when incorporated into intermetallic oxide phases. This work is relevant to the formation of multi-component oxides on metal surfaces that will incorporate Tc, and provide a kinetic barrier to corrosion (id est the release of Tc to the environment). Atomistic models that build upon the electronic structure calculations are then described using the modified embedded atom method to simulate metallic dissolution, and Buckingham potentials to perform classical molecular dynamics and statics simulations of the technetium (and, later, iron-technetium) oxide phases. Electrochemical methods were then applied to provide some benchmark information of the corrosion and electrochemical properties of Technetium metal. The results indicate that published information on Tc passivity is not complete and that further investigation is warranted.
Book Synopsis Electrometallurgical Techniques for DOE Spent Fuel Treatment by : National Research Council
Download or read book Electrometallurgical Techniques for DOE Spent Fuel Treatment written by National Research Council and published by National Academies Press. This book was released on 2000-08-11 with total page 128 pages. Available in PDF, EPUB and Kindle. Book excerpt: The Committee on Electrometallurgical Techniques for DOE Spent Fuel Treatment was formed in September 1994 in response to a request made to the National Research Council (NRC) by the U.S. Department of Energy DOE. DOE requested an evaluation of electrometallurgical processing technology proposed by Argonne National Laboratory (ANL) for the treatment of DOE spent nuclear fuel. Electrometallurgical treatment of spent reactor fuel involves a set of operations designed to remove the remaining uranium metal and to incorporate the radioactive nuclides into well defined and reproducible waste streams. Over the course of the committee's operating life, this charge has remained constant. Within the framework of this overall charge, the scope of the committee's workâ€"as defined by its statement of taskâ€"has evolved in response to further requests from DOE, as well as technical accomplishments and regulatory and legal considerations. As part of its task, the committee has provided periodic assessments of ANL's R&D program on the electrometallurgical technology. Electrometallurgical Techniques for DOE Spent Fuel Treatment assesses the viability of electrometallurgical technology for treating DOE spent nuclear fuel and monitors the scientific and technical progress of the ANL program on electrometallurgical technology, specifically within the context of ANL's demonstration project on electrometallurgical treatment of EBR-II SNF. This report evaluates ANL's performance relative to the success criteria for the demonstration project, which have served as the basis for judging the efficacy of using electrometallurgical technology for the treatment of EBR-II spent nuclear fuel. It also addresses post-demonstration activities related to ANL's electrometallurgical demonstration project, and makes related recommendations in this area.
Book Synopsis Electrochemical Corrosion Testing of Metal Waste Forms by :
Download or read book Electrochemical Corrosion Testing of Metal Waste Forms written by and published by . This book was released on 1999 with total page 17 pages. Available in PDF, EPUB and Kindle. Book excerpt: Electrochemical corrosion tests have been conducted on simulated stainless steel-zirconium (SS-Zr) metal waste form (MWF) samples. The uniform aqueous corrosion behavior of the samples in various test solutions was measured by the polarization resistance technique. The data show that the MWF corrosion rates are very low in groundwaters representative of the proposed Yucca Mountain repository. Galvanic corrosion measurements were also conducted on MWF samples that were coupled to an alloy that has been proposed for the inner lining of the high-level nuclear waste container. The experiments show that the steady-state galvanic corrosion currents are small. Galvanic corrosion will, hence, not be an important mechanism of radionuclide release from the MWF alloys.
Book Synopsis OCRWM Publications Catalog on High-level Radioactive Waste Management by :
Download or read book OCRWM Publications Catalog on High-level Radioactive Waste Management written by and published by . This book was released on 1987-07 with total page 156 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Electrochemical corrosion studies on metallic packaging materials for high-level radioactive waste by : R. E. Schmitt
Download or read book Electrochemical corrosion studies on metallic packaging materials for high-level radioactive waste written by R. E. Schmitt and published by . This book was released on 1986 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Modeling the Long - Term Degradation of a Metallic Waste Form by :
Download or read book Modeling the Long - Term Degradation of a Metallic Waste Form written by and published by . This book was released on 2002 with total page 9 pages. Available in PDF, EPUB and Kindle. Book excerpt: The principal aim of this effort is to develop models of long-term metal waste form (MWF) degradation that are credible, mechanistically based, and empirically calibrated. Utilizing new experimental data and analyses, this paper outlines an updated approach and summarizes the progress made. The current modeling approach emphasizes the analysis of constituent release data from immersion tests. A significant amount of recently obtained immersion test data is described. Test solutions included both mild (well-water), and aggressive (high-chloride and strongly acidic) environments. In addition to predominant constituents Fe, Zr, Cr, and Ni, MWF test samples included: U, Pu, Tc, and Np. Guided by analysis of new immersion test data, a mechanistic model has been developed that describes the time dependence of MWF corrosion leading to passivation. A common functional form relates MWF degradation from different passivating solution environments via scale factors for magnitude and passivation time. Passivation is identified as the most important factor governing long-term durability, along with the long-term stability of oxide barrier layers that cause passivation. Experimental data demonstrated passivation behavior in nominal well water, concentrated well water, an aggressive high-chloride solution, but not in a strong acid. Credible bounding estimates of long-term corrosion for nominal well water solution environments are based on fits to time dependence scaled by the measured release of uranium (empirically identified as the most efficiently released MWF constituent). These estimates involve no significant extrapolation beyond the data and time span of the present experiments. However, using the mechanistic model, these estimates of corrosion and release could be lowered and/or extended to more aggressive solution environments (via scale factors) provided barrier layer stability can be assumed (or demonstrated) to persist for longer times.
Book Synopsis Development of Advanced Electrochemical Emission Spectroscopy for Monitoring Corrosion in Simulated DOE Liquid Waste by :
Download or read book Development of Advanced Electrochemical Emission Spectroscopy for Monitoring Corrosion in Simulated DOE Liquid Waste written by and published by . This book was released on 2008 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Various forms of general and localized corrosion represent principal threats to the integrity of DOE liquid waste storage tanks. These tanks, which are of a single wall or double wall design, depending upon their age, are fabricated from welded carbon steel and contain a complex waste-form comprised of NaOH and NaNO3, along with trace amounts of phosphate, sulfate, carbonate, and chloride. Because waste leakage can have a profound environmental impact, considerable interest exists in predicting the accumulation of corrosion damage, so as to more effectively schedule maintenance and repair. The different tasks that are being carried out under the current program are as follows: (1) Theoretical and experimental assessment of general corrosion of iron/steel in borate buffer solutions by using electrochemical impedance spectroscopy (EIS), ellipsometry and XPS techniques; (2) Development of a damage function analysis (DFA) which would help in predicting the accumulation of damage due to pitting corrosion in an environment prototypical of DOE liquid waste systems; (3) Experimental measurement of crack growth rate, acoustic emission signals and coupling currents for fracture in carbon and low alloy steels as functions of mechanical (stress intensity), chemical (conductivity), electrochemical (corrosion potential, ECP), and microstructural (grain size, precipitate size, etc) variables in a systematic manner, with particular attention being focused on the structure of the noise in the current and its correlation with the acoustic emissions; (4) Development of fracture mechanisms for carbon and low alloy steels that are consistent with the crack growth rate, coupling current data and acoustic emissions; (5) Inserting advanced crack growth rate models for SCC into existing deterministic codes for predicting the evolution of corrosion damage in DOE liquid waste storage tanks; (6) Computer simulation of the anodic and cathodic activity on the surface of the steel samples in order to exactly predict the corrosion mechanisms; (7) Wavelet analysis of EC noise data from steel samples undergoing corrosion in an environment similar to that of the high level waste storage containers, to extract data pertaining to general, pitting and stress corrosion processes, from the overall data. The Point Defect Model (PDM) is directly applied as the theoretical assessment method for describing the passive film formed on iron/steels. The PDM is used to describe general corrosion in the passive region of iron. In addition, previous work suggests that pit formation is due to the coalescence of cation vacancies at the metal/film interface which would make it possible to use the PDM parameters to predict the onset of pitting. This previous work suggests that once the critical vacancy density is reached, the film ruptures to form a pit. Based upon the kinetic parameters derived for the general corrosion case, two parameters relating to the cation vacancy formation and annihilation can be calculated. These two parameters can then be applied to predict the transition from general to pitting corrosion for iron/mild steels. If cation vacancy coalescence is shown to lead to pitting, it can have a profound effect on the direction of future studies involving the onset of pitting corrosion. The work has yielded a number of important findings, including an unequivocal demonstration of the role of chloride ion in passivity breakdown on nickel in terms of cation vacancy generation within the passive film, the first detection and characterization of individual micro fracture events in stress corrosion cracking, and the determination of kinetic parameters for the generation and annihilation of point defects in the passive film on iron. The existence of coupling between the internal crack environment and the external cathodic environment, as predicted by the coupled environment fracture model (CEFM), has also been indisputably established for the AISI 4340/NaOH system. It is evident from the studies that analysis of coupling current noise is a very sensitive tool for studying the crack tip processes in relation to the chemical, mechanical, electrochemical and microstructural properties of the system. Experiments are currently being carried out to explore these crack tip processes by simultaneous measurement of the acoustic activity at the crack tip in an effort to validate the coupling current data. These latter data are now being used to deterministically predict the accumulation of general and localized corrosion damage on carbon in prototypical DOE liquid waste storage tanks. Computer simulation of the cathodic and anodic activity on the steel surfaces is also being carried out in an effort to simulate the actual corrosion process. Wavelet analysis of the coupling current data promises to be a useful tool to differentiate between the different corrosion mechanisms.
Download or read book Energy Research Abstracts written by and published by . This book was released on 1995 with total page 782 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Electrochemical Corrosion Studies of Container Materials in Repository-relevant Environments by :
Download or read book Electrochemical Corrosion Studies of Container Materials in Repository-relevant Environments written by and published by . This book was released on 1995 with total page 30 pages. Available in PDF, EPUB and Kindle. Book excerpt: The Office of Civilian Radioactive Waste Management (OCRWM) of the United States Department of Energy (USDOE) is evaluating Yucca Mountain in southern Nevada to determine its suitability as a site for a mined geologic disposal system for the disposal of spent fuel and high-level nuclear waste. Framatome Cogema Fuels (FCF), as a part of the Management and Operating (M & O) team in support of the Yucca Mountain Site Characterization Project (YAD), is responsible for designing and developing the waste package for this potential repository. As part of this effort, Lawrence Livermore National Laboratory (LLNL), also a member of the M & O team is responsible for testing materials and developing models for the materials to be used in the waste package. Based on a literature review of the anticipated degradation modes that may occur under the repository-relevant environmental conditions, LLNL has identified a large number of engineering materials for the various components of the waste package. One step in evaluating the performance of these materials is to conduct preliminary tests under these repository-relevant environmental conditions. This report is aimed at presenting the results of scoping electrochemical cyclic potentiodynamic polarization (CPP) experiments using nine candidate waste package container materials in various environments.
Book Synopsis Metal Waste Form Corrosion Release Data from Immersion Tests by :
Download or read book Metal Waste Form Corrosion Release Data from Immersion Tests written by and published by . This book was released on 2005 with total page 505 pages. Available in PDF, EPUB and Kindle. Book excerpt: The compilation of Metal Waste Form (MWF) immersion test data in this document is part of the effort initiated to qualify the stainless steel-15% zirconium (SS-15Zr) alloy for repository disposal. The SS-15Zr alloy was developed as part of the waste stream from the Argonne National Laboratory (ANL) electrometallurgical process for spent nuclear fuel. There were four areas of significant relevance concerning MWF performance in a long-term repository setting addressed in the test model. The areas encompassed the study of the effects of (1) the solution aggressiveness [simulated by concentrated J13 solution (CJ13)], (2) high-chloride content of the solution [simulated by 10,000 ppm chloride solution (10KCl)], (3) solution pH [simulated by acidified J13 solution (AJ13)], and (4) the state of the metal surface--polished vs. oxidized on the releases. The simulated J-13 solution was intended to replicate the groundwater in the J-13 well at the Yucca Mountain geologic repository. A fifth area of interest was to determine if the releases were limited by iron saturation of the solution. The data obtained from the entire study will be compared with the data from the High Level Waste Glass (HLWG) form previously qualified for repository disposal. Even though the MWF samples used in these tests contained no actinides and no Tc, conclusions can be made with respect to the releases of the noble metal fission products and the stainless steel constituents. Fe releases are an order of magnitude or higher than the releases of the noble metal fission-product elements in all solutions. Releases of noble metal fission products and Cr and Ni in SJ13 and CJ13 solutions at 90 C are close to the limits of detection. Solution concentration increased the Zr release. Zr releases from CJ13 were about a factor of 2 lower than the Fe release. In CJ13, Zr releases from oxidized samples were higher than from polished samples. Releases of all elements increased in the AJ13, pH=2 solution. Total cumulative releases as a function of time continued to increase for the 308 days of tests unlike the behavior in other test solutions. Tests in solutions with pH between 2 and 8 are needed to understand the different behavior. Except for high chloride solutions, (10KCl), release rates of stainless steel elements and noble metal fission products from the MWF samples are lower than release rates from HLWG.
Book Synopsis Technical Progress Report for the Quarter ... by :
Download or read book Technical Progress Report for the Quarter ... written by and published by . This book was released on 1983 with total page 84 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Radioactive Waste Management written by and published by . This book was released on 1981 with total page 622 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Proceedings of the Topical Meeting on Nuclear Waste Isolation in the Unsaturated Zone by :
Download or read book Proceedings of the Topical Meeting on Nuclear Waste Isolation in the Unsaturated Zone written by and published by . This book was released on 1990 with total page 468 pages. Available in PDF, EPUB and Kindle. Book excerpt:
