Download or read book Spent Nuclear Fuel Corrosion The Application of ICP MS Todirect Actinide Analysis written by U. -B. Eklund and published by . This book was released on 1995 with total page 18 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Spent Nuclear Fuel Corrosion written by Ronald Stewart Forsyth and published by . This book was released on 1994 with total page 36 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 1996 with total page 584 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Development of a Kinetic Model for the Dissolution of the UO2 Spent Nuclear Fuel written by Jordi Bruno and published by . This book was released on 1998 with total page 118 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Experimental Determination and Chemical Modelling of Radiolytic Processes at the Spent Fuel water Interface written by and published by . This book was released on 2003 with total page 64 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Corrosion of Spent Nuclear Fuel written by and published by . This book was released on 2002 with total page 5 pages. Available in PDF, EPUB and Kindle. Book excerpt: The successful disposal of spent nuclear fuel (SNF) is one of the most serious challenges to the success of the nuclear fuel cycle and the future of nuclear power generation. Spent nuclear fuel is essentially UO2 with approximately 4-5 atomic percent actinides and fission product elements. A number of these elements have long half-lives (239Pu: 24,100 years; 237Np: 2 million years; 129I: 16 million years; 79Se: 1.1 million years; 99Tc 200,000 years); hence, the long-term behavior of the UO2 is an essential concern in the evaluation of the safety of a repository for spent nuclear fuel. One of the unique and scientifically most difficult aspects of the successful disposal of spent nuclear fuel is the extrapolation of short-term laboratory data (hours to years) to the long time periods (103 to 105 years). The direct verification of these extrapolations or interpolations is not possible, but methods must be developed to demonstrate compliance with government regulations and to satisfy the public that there is a reasonable basis for accepting the long-term extrapolations of spent fuel behavior. In recent years ''natural analogues'' for both the repository environment (e.g., the Oklo natural reactors) and nuclear waste form behavior (e.g., corrosion and alteration of uraninite, UO2+x) have been cited as a fundamental means of achieving confirmation of long-term extrapolations. In particular, considerable effort has already been made to establish that uraninite, UO2+x, with its impurities, is a good structural and chemical analogue for the analysis of the long-term behavior of the UO2 in spent nuclear fuel. This research program is based on the study of uraninite and the naturally occurring alteration products of UO2+x under oxidizing and reducing conditions. We address the following issues: (1) What are the long-term corrosion products of natural UO2+x under reducing and oxidizing conditions? (2) What is the paragenesis or the reaction path of the phases that form during alteration? How is the paragenetic sequence of formation related to the structures and compositions of the phases? (3) What is the trace element content in the corrosion products (as compared with the original UO2), and does the trace element content substantiate models developed to predict radionuclide incorporation? (4) Are the corrosion products the phases that are predicted from reaction path models (e.g., EQ3/6) that are used in performance assessments? (5) How persistent over time are the metastable phase assemblages that form? Will these phases serve as barriers to radionuclide release? (6) Based on the structures of these phases (mostly sheet structures) can the thermodynamic stabilities of these phases be estimated, or at least bounded, in such a way as to provide for a convincing and substantive performance assessment?
Download or read book The Use of Thermodynamic Databases in Performance Assessment written by OECD Nuclear Energy Agency and published by OECD Publishing. This book was released on 2002 with total page 228 pages. Available in PDF, EPUB and Kindle. Book excerpt: The workshop was designed to provide a forum in which performance assessment of repository concepts for the geological disposal of long-lived radioactive waste using thermodynamic data could be discussed.
Download or read book Determination of Radionuclide Solubility Limits to be Used in SR 97 written by Jordi Bruno and published by . This book was released on 1997 with total page 206 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book The SKB Spent Fuel Corrosion Programme written by Roy Forsyth and published by . This book was released on 1997 with total page 266 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Government Reports Announcements Index written by and published by . This book was released on 1996-07 with total page 444 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Corrosion Testing of Spent Nuclear Fuel Performed at Argonne National Laboratory for Repository Acceptance written by and published by . This book was released on 2000 with total page 10 pages. Available in PDF, EPUB and Kindle. Book excerpt: Corrosion tests of DOE-owned spent nuclear fuel are performed at Argonne National Laboratory to support the license application for the Yucca Mountain Repository. The tests are designed to determine corrosion rates and degradation products formed when fuel is reacted at elevated temperature in different aqueous environments, including vapor, dripping water, submersion, and liquid film contact. Corrosion rates are determined from the quantity of radionuclides released from wetted fuel and from the weight loss of the test fuel specimen as a function of time. Degradation products include secondary mineral phases and dissolved, adsorbed, and colloidal species. Solid phase examinations determine fuel/mineral interface relationships, characterize radionuclide incorporation into secondary phases, and determine corrosion mechanisms at grain interfaces within the fuel. Leachate solution analyses quantify released radionuclides and determine the size and charge distribution of colloids. This paper presents selected results from corrosion tests on metallic fuels.
Download or read book Applications of Inductively Coupled Plasma Mass Spectrometry to the Determination of Actinides and Fission Products in High Level Radioactive Wastes at the Savannah River Site written by NE. Bibler and published by . This book was released on 1995 with total page 11 pages. Available in PDF, EPUB and Kindle. Book excerpt: Four years of experience in applying inductively coupled plasma-mass spectrometry (ICP-MS) to the analysis of actinides and fission products in high level waste (HLW) samples at the Savannah River Site has led to the development of a number of techniques to aid in the interpretation of the mass spectral data. Our goal has been to develop rapid and reliable analytical procedures that provide the necessary chemical and isotopic information to answer the process needs of the customers. Techniques that have been developed include the writing of computer software to strip the experimental data from the instrument data files into spreadsheets or into a spectral data processing package so that the raw mass spectra can be overlain for comparison or plotted with higher output resolution. These procedures have been applied to problems ranging from the analysis of the high level waste tanks to reactor moderator water as well as environmental samples. Criticality safety analyses in some HLW waste treatment processes depend upon actinide concentration and isotopic information generated by ICP-MS, particularly in tanks with high concentrations of 137Cs and 90Sr. Experimental results for a number of these applications will be presented. These procedures represent a considerable saving in time and expense as compared to conventional chemical separation followed by radiochemical analyses, as well as decreased radiation exposure for the analysts.
Download or read book Uncertainty Analysis for Corrosion Depth of Nuclear Spent Fuel Canister written by and published by . This book was released on 2002 with total page 8 pages. Available in PDF, EPUB and Kindle. Book excerpt: Uncertainty analysis for corrosion depth of the spent nuclear fuel canister has been studied using differential analysis. It shows that the mean value presents a second-order linear increase while the variance demonstrates a first-order linear increase in 1000-year time history. By respectively incorporating correlation into pitting factor, uniform corrosion factor, oxygen concentration and chlorine concentration, it is found that the covariance of uniform corrosion factor and chlorine concentration has the highest contribution in the variance of total loss.
Download or read book Corrosion of Spent Nuclear Fuel written by Rodney C. Ewing and published by . This book was released on 2003 with total page 5 pages. Available in PDF, EPUB and Kindle. Book excerpt: This research program is a broadly based effort to understand the long-term behavior of spent nuclear fuel (SNF) and its alteration products in a geologic repository. We have established by experiments and field studies that natural uraninite, UO2+x, and its alteration products are excellent ''natural analogues'' for the study of the corrosion of UO2 in SNF. This on-going research program has addressed the following major issues: (1) What are the long-term corrosion products of natural UO2+x, uraninite, under oxidizing and reducing conditions? (2) What is the paragenesis or the reaction path for the phases that form during alteration? (3) What is the radionuclide content in the corrosion products as compared with the original UO2+x? Do the trace element contents substantiate models developed to predict radionuclide incorporation into the secondary phases? Are the corrosion products accurately predicted from geochemical codes (e.g., EQ3/6 or Geochemist's Workbench) that are used in performance assessments? Can these codes be tested by studies of natural analogue sites (e.g., Oklo, Cigar Lake or Pena Blanca).
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.
Download or read book Radiation Induced Corrosion of Spent Nuclear Fuel written by Jessica Higgins and published by . This book was released on 2021 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book INIS Atomindex written by and published by . This book was released on 1995 with total page 640 pages. Available in PDF, EPUB and Kindle. Book excerpt:
