Development of a Kinetic Model for the Dissolution of the UO2 Spent Nuclear Fuel

Development of a Kinetic Model for the Dissolution of the UO2 Spent Nuclear Fuel PDF Author: Jordi Bruno
Publisher:
ISBN:
Category : Radioactive waste disposal
Languages : en
Pages : 118

Get Book Here

Book Description

Development of a Kinetic Model for the Dissolution of the UO2 Spent Nuclear Fuel

Development of a Kinetic Model for the Dissolution of the UO2 Spent Nuclear Fuel PDF Author: Jordi Bruno
Publisher:
ISBN:
Category : Radioactive waste disposal
Languages : en
Pages : 118

Get Book Here

Book Description


Development of a Kinetic Model to Predict the Rate of Oxidation and Dissolution of Nuclear Fuel (UO@) by the Radiolysis of Water

Development of a Kinetic Model to Predict the Rate of Oxidation and Dissolution of Nuclear Fuel (UO@) by the Radiolysis of Water PDF Author: H. Christensen
Publisher: Pinewa, Man. : Whiteshell Laboratories
ISBN:
Category : Nuclear fuels
Languages : en
Pages : 44

Get Book Here

Book Description
Radiolysis of groundwater would produce oxidants and reductants that could affect the oxidation and dissolution of used fuel (UO2) placed in a geological disposal vault. To avoid the extensive experimentation involved, a kinetic model originally proposed by Christensen and Bjergbakke to predict the rate of UO2 dissolution induced by water radiolysis is being refined. This report summarizes the understanding of the mechanisms of oxidation and dissolution of UO2 as well as other pertinent experimental results used in then of UO2 as well as other pertinent experimental results used in the refinement of the original model. The model and its refinements are described and the rates predicted are presented. These predicted dissolution rates are then compared with the rates determined from the electro-chemical model. The limitations and necessary further developments are then discussed.

Determination of the Microscopic Kinetic Parameters of the Dissolution of UXPu1-XO2 in Nitric Acid - Development and Qualification of the Method on UO2

Determination of the Microscopic Kinetic Parameters of the Dissolution of UXPu1-XO2 in Nitric Acid - Development and Qualification of the Method on UO2 PDF Author: Guilherme Da Silva Cardoso
Publisher:
ISBN:
Category :
Languages : en
Pages :

Get Book Here

Book Description
The reprocessing of spent nuclear fuel is a very important step in the nuclear fuel cycle and one of the greatest ways to ensure the sustainability of the civil nuclear industry. In France, the PUREX process is used to separate the reusable Uranium and Plutonium from the fission products and minor actinides that will then be disposed as waste. The dissolution of the spent fuel is at the head-end of this process and thus has a big impact on the following stages. The present work was done in the context of the development of a model for the dissolution step that will be used to design the dissolution reactors of the future. Some of the inputs this model will need are the kinetic constants of the dissolution reactions, which are quite complex. To achieve this, the dissolution of small grains of UO2 was studied under several experimental conditions. An algorithm was developed with the software MatLab which takes as input the images of the grains taken at regular intervals during the dissolution and as an output the dissolution rates in nm/s and mol/m2 /s. The algorithm binarises the grain images in order to have a clear distinction between grain and background, follows the area and perimeter of the oxide grains throughout the dissolution and finally calculates the wished results. The dissolution speeds at different experimental conditions will allow for the calculations of kinetic constants and activation energies which will then feed the dissolution model.

Advances in Transport Phenomena

Advances in Transport Phenomena PDF Author: Liqiu Wang
Publisher: Springer Science & Business Media
ISBN: 3642026907
Category : Science
Languages : en
Pages : 250

Get Book Here

Book Description
The term transport phenomena is used to describe processes in which mass, momentum, energy and entropy move about in matter. Advances in Transport Phenomena provide state-of-the-art expositions of major advances by theoretical, numerical and experimental studies from a molecular, microscopic, mesoscopic, macroscopic or megascopic point of view across the spectrum of transport p- nomena, from scientific enquiries to practical applications. The annual review series intends to fill the information gap between regularly published journals and university-level textbooks by providing in-depth review articles over a broader scope than in journals. The authoritative articles, contributed by international- leading scientists and practitioners, establish the state of the art, disseminate the latest research discoveries, serve as a central source of reference for fundamentals and applications of transport phenomena, and provide potential textbooks to senior undergraduate and graduate students. The series covers mass transfer, fluid mechanics, heat transfer and thermo- namics. The 2009 volume contains the four articles on biomedical, environmental and nanoscale transports. The editorial board expresses its appreciation to the c- tributing authors and reviewers who have maintained the standard associated with Advances in Transport Phenomena. We also would like to acknowledge the efforts of the staff at Springer who have made the professional and attractive pr- entation of the volume. Serial Editorial Board Editor-in-Chief Professor L. Q. Wang The University of Hong Kong, Hong Kong; lqwang@hku. hk Editors Professor A. R. Balakrishnan Indian Institute of Technology Madras, India Professor A.

Geological Repository Systems for Safe Disposal of Spent Nuclear Fuels and Radioactive Waste

Geological Repository Systems for Safe Disposal of Spent Nuclear Fuels and Radioactive Waste PDF Author: Michael J Apted
Publisher: Elsevier
ISBN: 1845699785
Category : Technology & Engineering
Languages : en
Pages : 789

Get Book Here

Book Description
Geological disposal has been internationally adopted as the most effective approach to assure the long-term, safe disposition of the used nuclear fuels and radioactive waste materials produced from nuclear power generation, nuclear weapons programs, medical, treatments, and industrial applications. Geological repository systems take advantage of natural geological barriers augmented with engineered barrier systems to isolate these radioactive materials from the environment and from future populations. Geological repository systems for safe disposal of spent nuclear fuels and radioactive waste critically reviews the state-of-the-art technologies, scientific methods, regulatory developments, and social engagement approaches directly related to the implementation of geological repository systems. Part one introduces geological disposal, including multiple-barrier geological repositories, as well as reviewing the impact of nuclear fuel recycling practices and underground research laboratory activities on the development of disposal concepts. Part two reviews geological repository siting in different host rocks, including long-term stability analysis and radionuclide transport modelling. Reviews of the range of engineered barrier systems, including waste immobilisation technologies, container materials, low pH concretes, clay-based buffer and backfill materials, and barrier performance are presented in Part three. Part four examines total system performance assessment and safety analyses for deep geological and near-surface disposal, with coverage of uncertainty analysis, use of expert judgement for decision making, and development and use of knowledge management systems. Finally, Part five covers regulatory and social approaches for the establishment of geological disposal programs, from the development of radiation standards and risk-informed, performance-based regulations, to environmental monitoring and social engagement in the siting and operation of repositories. With its distinguished international team of contributors, Geological repository systems for safe disposal of spent nuclear fuels and radioactive waste is a standard reference for all nuclear waste management and geological repository professionals and researchers. Critically reviews the state-of-the-art technologies, scientific methods, regulatory developments, and social engagement approaches related to the implementation of geological repository systems Chapters introduce geological disposal and review the development of disposal concepts Examines long-term stability analysis, the range of engineered barrier systems and barrier performance

State-of-the-art Report on the Progress of Nuclear Fuel Cycle Chemistry

State-of-the-art Report on the Progress of Nuclear Fuel Cycle Chemistry PDF Author:
Publisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 148

Get Book Here

Book Description
The implementation of advanced nuclear systems requires that new technologies associated with the back end of the fuel cycle are developed. The separation of minor actinides from other fuel components is one of the advanced concepts being studied to help close the nuclear fuel cycle and to improve the long-term effects on the performance of geological repositories. Separating spent fuel elements and subsequently converting them through transmutation into short-lived nuclides should considerably reduce the longterm risks associated with nuclear power generation.

Interlaboratory Comparison of UO2 Dissolution Rates

Interlaboratory Comparison of UO2 Dissolution Rates PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 6

Get Book Here

Book Description
Direct disposal of spent nuclear fuel in deep underground geologic repositories (vaults) is being pursued by several countries. Isolation relies on multiple barriers consisting of the site geology, engineered barriers including containers to surround the fuel, and the spent fuel itself. These barriers are intended to inhibit dissolution and transport of radionuclides by groundwater, which is virtually the only mechanism available to release radionuclides from the repository. Performance assessment studies are needed to demonstrate the adequacy of the various repository designs. Essential to this performance assessment is an understanding of the dissolution behavior of the spent fuel. Since the dissolution behavior of spent fuel in an actual repository cannot be adequately approximated in a laboratory, laboratory tests and data must be used to develop a mechanistic model that can predict long-term behavior in a repository. Three different laboratories have performed flowthrough dissolution tests at room temperature on portions of the same batch of unirradiated UO2 powder, and good agreement was achieved between the different test results. Dissolution rates obtained from electrochemical studies conducted with UO2 electrodes at Whiteshell Laboratories are compared with the flowthrough test results.

Experimental Determination and Chemical Modelling of Radiolytic Processes at the Spent Fuel/water Interface

Experimental Determination and Chemical Modelling of Radiolytic Processes at the Spent Fuel/water Interface PDF Author:
Publisher:
ISBN:
Category : Radiation chemistry
Languages : en
Pages : 82

Get Book Here

Book Description


Charged Particle and Photon Interactions with Matter

Charged Particle and Photon Interactions with Matter PDF Author: Yoshihiko Hatano
Publisher: CRC Press
ISBN: 1439811806
Category : Science
Languages : en
Pages : 1068

Get Book Here

Book Description
Building on Mozumder's and Hatano's Charged Particle and Photon Interactions with Matter: Chemical, Physicochemical, and Biological Consequences with Applications (CRC Press, 2004), Charged Particle and Photon Interactions with Matter: Recent Advances, Applications, and Interfaces expands upon the scientific contents of the previous volume by cover

Site Characterization Progress Report

Site Characterization Progress Report PDF Author:
Publisher:
ISBN:
Category : Radioactive waste disposal in the ground
Languages : en
Pages : 840

Get Book Here

Book Description