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Electrochemical And Modelling Studies On Simulated Spent Nuclear Fuel Corrosion Under Permanent Waste Disposal Conditions
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Book Synopsis Electrochemical and modelling studies on simulated spent nuclear fuel corrosion under permanent waste disposal conditions by : Nazhen Liu
Download or read book Electrochemical and modelling studies on simulated spent nuclear fuel corrosion under permanent waste disposal conditions written by Nazhen Liu and published by . This book was released on 2017 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The safety assessment models for the deep geological disposal of spent nuclear fuel require a fundamental understanding of the corrosion of spent fuel in a failed waste container. The overall research goal of this project is to investigate the corrosion of simulated spent fuel under permanent disposal conditions, using both model simulations and experimental investigations. A model for fuel corrosion has been expanded to determine the relative importance of radiolytic hydrogen and hydrogen from corrosion of the steel vessel in suppressing fuel corrosion. It was shown that, for CANDU (CANada Deuterium Uranium) fuel with moderate in-reactor burnup, only micromolar concentrations of hydrogen from steel corrosion are required to completely suppress fuel corrosion. In a partially closed system (i.e., within cracks in the fuel) radiolytic hydrogen alone can suppress corrosion to a negligible level. The model was validated by comparing the calculated corrosion rates with published measurements. Agreement between calculated and measured rates indicated that corrosion is controlled by the rate of radiolytic production of oxidants, in particular hydrogen peroxide, irrespective of the reactivity of the fuel. Experimentally, the influence of rare earth doping on the reactivity of UO2 was investigated. For REIII-doped UO2, the onset of matrix dissolution was accompanied by the enhanced oxidation of the matrix to UIV1{u2212}2xUV2xO2+x. This can be attributed to the onset of tetragonal lattice distortions as oxidation proceeds which leads to the clustering of defects, enhanced diffusion of OI (interstitial oxygen)to deeper locations and destabilization of the fluorite lattice. A further investigation of the doping effect was performed on a series of (U1{u2212}yGdy)O2 materials (y = 0, 0.01, 0.03, 0.05, 0.07 and 0.10). Overall the increase in doping up to 10% does not exert a major influence on reactivity possibly due to the competition between an increase in the number of (Ov)s (oxygen vacancy) and a contraction in the lattice constant.
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 Electrochemical and Computational Modelling Studies on Spent Nuclear Fuel Dissolution and the Effect of Corrosion Product Deposits on UO2 Corrosion by : Yannick A. Beauregard
Download or read book Electrochemical and Computational Modelling Studies on Spent Nuclear Fuel Dissolution and the Effect of Corrosion Product Deposits on UO2 Corrosion written by Yannick A. Beauregard and published by . This book was released on 2011 with total page 292 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Application of electrochemical methods in the development of models for fuel dissolution and container corrosion under nuclear waste disposal conditions by : D. W. Shoesmith
Download or read book Application of electrochemical methods in the development of models for fuel dissolution and container corrosion under nuclear waste disposal conditions written by D. W. Shoesmith and published by . This book was released on 1997 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt: Recent inspections have indicated that carbon steel outlet feeder pipes in some candu reactors are experiencing wall loss near the exit from the reactor core. this phenomenon is not observed in inlet feeder pipes. examination of a sample of pipe removed from a candu 6 reactor has indicated that the mechanism causing the wall loss is flow-accelerated corrosion (fac), at rates higher than expected, but two orders of magnitude lower than those typically observed in secondary circuits of nuclear and conventional power plants. although the candu reactor outlet feeder operating temperatures and the use of lioh at a high ph should have ensured low corrosion rates, use of sa 106 grade b carbon steel with a low chromium content resulted in some susceptibility to fac. the main parameter influencing the rate of wall loss is the coolant velocity, with the bend angle playing a secondary role. a solubility-based mathematical model describing the effects of water chemistry and coolant hydrodynamics on the rate of fac has been developed and has been recently improved by the empirical incorporation of the effect of electrochemical potential on the solubility of magnetite. experiment and theory have indicated that the corrosion rates are lower at lower ph values within the permissible operating range. experiments are being conducted to obtain more information on the effects of water chemistry and material composition on fac. current results support the predicted effects of ph and carbon steel chromium content on the fac rate. remedial measures implemented include operation of existing reactors at the lower end of the specified ph range and the specification of a minimum of 0.20 wt% cr in the carbon steel of feeder pipes of future candu reactors.
Book Synopsis Models for used nuclear fuel corrosion under waste disposal conditions by : D. W. Shoesmith
Download or read book Models for used nuclear fuel corrosion under waste disposal conditions written by D. W. Shoesmith and published by . This book was released on 1997 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt:
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 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 Electrochemical and Corrosion Examination of Copper Under Deep Geologic Conditions for the Application of Nuclear Waste Containers by : Taylor L. Martino
Download or read book Electrochemical and Corrosion Examination of Copper Under Deep Geologic Conditions for the Application of Nuclear Waste Containers written by Taylor L. Martino and published by . This book was released on 2018 with total page 186 pages. Available in PDF, EPUB and Kindle. Book excerpt: Copper is the selected material for the fabrication of nuclear fuel waste containers in Sweden, Finland and Canada due to its corrosion resistance in the anoxic aqueous environments, anticipated in deep geological repositories. A potential oxidant for copper is bisulphide produced either by the dissolution of minerals or by sulphate-reducing bacteria. The primary goals of this thesis were to determine the mechanism of corrosion of copper in bisulphide environments and to investigate the chemistry of the bentonite porewater that will ultimately be in contact with the copper container. The mechanism of sulphide film growth and the details of copper corrosion in anoxic aqueous bisulphide solutions in the presence of various groundwater anions have been investigated electrochemically. The chalcocite films were analyzed via voltammetry, electrochemical impedance spectroscopy and surface analysis. Under these conditions, growth of a coherent film occurred initially but the development of interfacial stresses led rapidly to film fracture. Upon fracture, a resistive outer chalcocite deposit formed with continued growth governed by the mass transport of bisulphide. Specific anion effects were observed with chloride, a common groundwater ion, found to maintain porosity in the chalcocite film while the oxyanions, sulphate and bicarbonate were found to suppress film growth. At high bisulphide concentrations and positive potentials growth of the outer deposit caused an apparent partial passivation of the surface, which theoretically could lead to localized film breakdown and pitting. However, the required high bisulphide concentrations are not attainable in a deep geologic repository and pitting should not occur. Bentonite porewater chemistry was successfully monitored using a novel experimental set-up. Electrochemical sensors monitoring pH, chloride concentration and the copper corrosion potential were placed both on the surface and inside of a bentonite clay disk. The results showed that the bentonite acted like a pH buffer and chloride from bulk solution adsorbed onto the montmorillonite structure. Corrosion potential measurements suggested that corrosion likely occurred via formation of a copper chloride complex or growth of a cuprite film. Data collected from these studies will be used directly by SKB via incorporation into models.
Book Synopsis Simulation of Electrochemical Processes by : C. A. Brebbia
Download or read book Simulation of Electrochemical Processes written by C. A. Brebbia and published by Witpress. This book was released on 2005 with total page 272 pages. Available in PDF, EPUB and Kindle. Book excerpt: The 23 studies represent most of the presentations at the conference, which was called to gather researchers who have made significant contributions over recent years in modelling electrochemical processes used by engineers to protect structures against corrosion, to apply coatings and paints, and as a manufacturing process. They cover cathodic protection systems, modelling methodologies, electro-deposition and electro-forming, modelling coatings, and modelling stress corrosion cracking and corrosion fatigue. Among the topics are experimental versus computational system analysis, the time-dependent simulation of electrochemical machining under non- ideal conditions, and stress-corrosion in cold drawn pre-stressing steels. There is no subject index. The US office of WIT Press is Computational Mechanics. Annotation : 2005 Book News, Inc., Portland, OR (booknews.com).
Book Synopsis Electrochemical Corrosion Studies on a Selected Carbon Steelfor Application in Nuclear Waste Disposal Containers by : A. M. Farvaque-Béra
Download or read book Electrochemical Corrosion Studies on a Selected Carbon Steelfor Application in Nuclear Waste Disposal Containers written by A. M. Farvaque-Béra and published by . This book was released on 1994 with total page 21 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Electrochemical corrosion studies on a selected carbon steelfor application in nuclear waste disposal containers by : A. M. Farvaque-Béra
Download or read book Electrochemical corrosion studies on a selected carbon steelfor application in nuclear waste disposal containers written by A. M. Farvaque-Béra and published by . This book was released on 1994 with total page 34 pages. Available in PDF, EPUB and Kindle. Book excerpt:
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 2005 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: In this work, the examination of electrochemical noise data comprised three main approaches: one, a computer simulation of the anodic and cathodic activity relating to corrosion on a metal surface; two, experimental modeling of the electrochemical environment inside nuclear waste storage containers and collection of EN generated; and three, Wavelet analysis of the EN data from the first two parts. The simulation of EN proved to be effective in replicating the EN data of both general and pitting corrosion. Using competition mechanisms for the anodic and cathodic sites on the surface, the long-term, low-frequency data generated by localized pitting corrosion was reproduced. Disabling one or more of the rules of the simulation eliminated the low-frequency character of the data, and eliminating all of the rules effectively reproduced general corrosion noise. The simulation accuracy benefited from comparison to experimental data, and conversely, it improved the EN analysis by providing theory for the underlying mechanisms. The experimental electrochemical cell modeled the important factors in nuclear waste storage containers for this EN study; mainly increased temperature and the concentrations of corrosion-inducing or inhibiting chemicals. It also provided a platform for studying how the EN was affected by the competing chemicals.
Book Synopsis Corrosion of Breached Aluminide Fuel Under Potential Repository Conditions by :
Download or read book Corrosion of Breached Aluminide Fuel Under Potential Repository Conditions written by and published by . This book was released on 2000 with total page 9 pages. Available in PDF, EPUB and Kindle. Book excerpt: Permanent disposal of spent nuclear fuel is proposed in a repository located in the volcanic tuff beds near Yucca Mountain, Nevada, and it is the responsibility of the National Spent Nuclear Fuel Program (NSNFP) to provide the Yucca Mountain Project (YMP) with information related to the release of fission products from the DOE-owned SNF resulting from SNF corrosion. Hydrologically unsaturated spent fuel tests (''drip'' tests) are designed to simulate and monitor the release of radionuclides from the spent fuel under potential exposure conditions in the repository. Of the priority fuels being tested under the NSNFP, the aluminum-based fuels are included because of their high relative volume and uranium enrichment. The Al fuel structure is composed of fissile and aluminum powders pressed and annealed between Al plates to form thin metallic plates. The most widely used fissile powder was the intermetallic compound aluminide UAl(subscript x) (where x=2,3,4). As part of this testing program, preliminary corrosion tests using unirradiated UAl(subscript x) were initiated to address experimental design, sampling, and analysis issues prior to conducting tests with spent fuels. However, during this program the decision was made by U.S. DOE to convert the aluminum-based fuels to safer enrichment levels by using the melt-dilute process at Savannah River. Nonetheless, the product ingot of the melt-dilute process resembles low enriched UAl(subscript x) fuel and corrosion of the fuel is expected to be similar. This paper summarizes the preliminary testing results for the first year of the program and compares them to other corrosion testing results on aluminum fuels as well as other DOE fuel types.
Book Synopsis Simulation of Electrochemical Processes II by : V.G. DeGiorgi
Download or read book Simulation of Electrochemical Processes II written by V.G. DeGiorgi and published by WIT Press. This book was released on 2007-04-10 with total page 369 pages. Available in PDF, EPUB and Kindle. Book excerpt: This book contains papers presented at the Second International Conference in this successful series, which presents and discusses the state-of-the-art on the computer simulation of corrosion, electrochemical processes and the electrical and electromagnetic fields associated with them.Modern industry applies a wide range of electrochemical processes to protect against corrosion, provide surface treatments and to manufacture products. This book focuses on the computer modelling of these industrial processes and techniques by examining the developments of computational models and their application in practice.Featured topics include: Cathodic Protection Systems; Modelling Methodologies; Electrodeposition and Electroforming; Modelling of Coatings; Modelling Stress Corrosion, Cracking and Corrosion Fatigue; Modelling and Corrosion of Surface Coatings; Interference and Signature Control; Anodic Protection; Electrocoating and Plating; Optimisation of Control Systems; Detection and Monitoring of Corrosion; Measurement Techniques; Fuel on Photovoltaic Cells; Electrolysis Reactors; Comparison of Experimental Measurements and Computer results, Case Studies.
Book Synopsis Electrochemical corrosion studies on a selected carbon steel for application in nuclear waste disposal containers by : Anne-Marie Farvaque-Béra
Download or read book Electrochemical corrosion studies on a selected carbon steel for application in nuclear waste disposal containers written by Anne-Marie Farvaque-Béra and published by . This book was released on 1994 with total page 21 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis SPENT NUCLEAR FUEL STORAGE BASIN WATER CHEMISTRY by :
Download or read book SPENT NUCLEAR FUEL STORAGE BASIN WATER CHEMISTRY written by and published by . This book was released on 2007 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The factors affecting the optimal water chemistry of the Savannah River Site spent fuel storage basin must be determines in order to optimize facility efficiency, minimize fuel corrosion, and reduce overall environmental impact from long term spent nuclear fuel storage at the Savannah River Site. The Savannah River National Laboratory is using statistically designed experiments to study the effects of NO3−, SO42−, and Cl− concentrations on alloys commonly used not only as fuel cladding, but also as rack construction materials The results of cyclic polarization pitting and corrosion experiments on samples of Al 6061 and 1100 alloys will be used to construct a predictive model of the basin corrosion and its dependence on the species in the basin. The basin chemistry model and corrosion will be discussed in terms of optimized water chemistry envelope and minimization of cladding corrosion.
Book Synopsis Corrosion of Research Reactor Aluminium Clad Spent Fuel in Water by : International Atomic Energy Agency
Download or read book Corrosion of Research Reactor Aluminium Clad Spent Fuel in Water written by International Atomic Energy Agency and published by . This book was released on 2003 with total page 236 pages. Available in PDF, EPUB and Kindle. Book excerpt: This report describes research performed in ten laboratories within the framework of the IAEA Co-ordinated Research Project on Corrosion of Research Reactor Aluminium Clad Spent Fuel in Water. The project consisted of exposure of standard racks of corrosion coupons in the spent fuel pools of the participating research reactor laboratories and evaluation of the coupons after predetermined exposure times, along with periodic monitoring of the storage water. A group of experts in the field contributed a state of the art review and provided technical supervision of the project. Localized corrosion mechanisms are notoriously difficult to understand, and it was clear from the outset that obtaining consistency in the results and their interpretation from laboratory to laboratory would depend on the development of an excellent set of experimental protocols. These experimental protocols are described in the report, together with guidelines for the maintenance of optimum water chemistry to minimize the corrosion of aluminium clad research reactor fuel in wet storage.
