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Synthesis and Photoelectrochemical Characterization of Tantalum Oxide Nanoparticles and Their Nitrogen Derivatives
University of Nevada, Reno Synthesis and Photoelectrochemical Characterization of Tantalum Oxide Nanoparticles and their Nitrogen Derivatives A dissertation submitted in partial fulfillment of the requirements for the degree of Doctor of Philosophy in Chemical engineering by Vijay Khanal Dr. Vaidyanathan (Ravi) Subramanian – Advisor August 2019 The Graduate School We recommend that the dissertation prepared under our supervision by VIJAY KHANAL Entitled Synthesis and Photoelectrochemical Characterization of Tantalum Oxide Nanoparticles and their nitrogen Derivatives Be accepted in partial fulfillment of the Requirements for the degree of DOCTOR OF PHILOSOPHY Vaidyanathan (Ravi) Subramanian, Ph.D., Advisor Dhanesh Chandra, Ph.D., Committee Member Alan Fuchs, Ph.D., Committee Member Victor Vasquez, Ph.D., Committee Member Mario A. Alpuche, Ph.D. Graduate School Representative David W. Zeh, Ph.D., Dean, Graduate School August 2019 i ABSTRACT This work presents a surfactant-mediated approach for the synthesis of Ta2O5 nanopar- 2 1 2 1 ticles with a very high surface area (41 m g− vs. 1.6 m g− for commercial equivalent), and their subsequent nitridation to yield two distinct nitrogen derivatives: TaON and Ta3N5. Excellent photocatalytic efficiency of Ta2O5 toward photodegradation of methy- lene blue and NOx removal is reported. Ta3N5 shows significant photoconversion of methylene blue attributable to its lowered bandgap and high adsorption capability of MB molecules on its surface. A new method for simplifying the existing synthesis protocols of single phase Tantalum oxynitride (TaON) was devised. Series of photoelectrochemical characterization shows that the newly synthesized TaON can significantly enhance the photoassisted charge generation, separation, and transportation compared to the parent oxide (Ta2O5). -
Uranium Oxide Aerosol Transport in Porous Graphite
PNNL-21014 Prepared for the U.S. Department of Energy under Contract DE-AC05-76RL01830 Uranium Oxide Aerosol Transport in Porous Graphite J Blanchard C Brown DC Gerlach C Lovin RD Scheele CH Delegard ML Stewart A Zelenyuk BD Reid EC Buck PA Gauglitz BJ Riley LM Bagaasen CA Burns January 2012 PNNL-XXXXX PNNL-21014 Uranium Oxide Aerosol Transport in Porous Graphite J Blanchard C Brown DC Gerlach C Lovin RD Scheele CH Delegard ML Stewart A Zelenyuk BD Reid EC Buck PA Gauglitz BJ Riley LM Bagaasen CA Burns January 2012 Prepared for the U.S. Department of Energy under Contract DE-AC05-76RL01830 Pacific Northwest National Laboratory Richland, Washington 99352 PNNL-21014 Summary Conditions exist in carbon dioxide (CO2) gas-cooled, graphite moderated reactors that might allow for gaseous transport of uranium oxide (UO2) particles into the graphite moderator. The transport of UO2 in the reactor coolant system, and subsequent deposition of this material in the graphite, is of interest due to the potential to influence the application of the Graphite Isotope Ratio Method (GIRM). GIRM was developed to validate the declared operation of graphite moderated reactors. Uranium impurities in nuclear grade graphite are one of several possible indicator elements that can be used for a GIRM assessment. During fuel failures, uranium metal in the fuel is exposed to the CO2 coolant and oxidizes as either UO2 or U3O8. Measurements in adjacent fuel channels indicate that CO2 coolant readily flows through the porous graphite moderator blocks. Therefore, the potential exists for the coolant gas to transport UO2 particles, as an aerosol, into the porous graphite, thereby invalidating uranium as an indicator element. -
3 - 20 Progress in Fabrication of UC Ceramic Nuclear Fuels
· 56 · IMP & HIRFL Annual Report 2018 formation of such carbonyl complexes. Reference [1] Y. Wang, S. W. Cao, J. C. Zhang, et al., Physical Chemistry Chemical Physics, 21(2019)7147. [2] Y. Wang, Y. Wittwer, J. Zhang, et al., PSI Annual Report, (2019). 3 - 20 Progress in Fabrication of UC Ceramic Nuclear Fuels Tian Wei and Qin Zhi Uranium dioxide nuclear fuel has been widely used in pressurized water reactors (PWR), because of its high melting point, isotropic expansion, excellent radiation behaviors and mechanical properties[1]. However, it is easy to embrittlement and the thermal conductivity is quite low. Compared with traditional uranium oxides nuclear fuel, the uranium carbide has extremely high hardness and no phase transition occurs in wide temperature range[2]. The thermal conductivity, density and uranium fraction of UC is 21.7 W/(m·K) (1 237 K), 13.63 g/cm3 and 95.2% respectively, which are much higher than that of UO2. Uranium carbide ceramic fuel has been considered as a potential candidate nuclear fuel for the next-generation fast-neutron reactors, especially for the Accelerator-Driven Systems (ADS). Based on the accelerator driven recycling used nuclear fuel, uranium carbide can recrystallize with plutonium (Pu) and minor actinides (MAs). Therefore uranium carbide is chosen as the fuel format in ADS. Uniform sized ceramic UC microspheres with a diameter of (675 10) µm were successfully fabricated by an improved microwave-assisted rapid internal gelation process combined with carbothermic reduction (Fig. 1). First of all, the nanoparticle carbon was dispersed into the HMUR stock solution, and the C-UO3·2 H2O gelled microspheres were prepared using an improved microwave-assisted internal gelation process without cooling the initial stock solutions. -
Appendix a of Final Environmental Impact Statement for a Geologic Repository for the Disposal of Spent Nuclear Fuel and High-Lev
Appendix A Inventory and Characteristics of Spent Nuclear Fuel, High-Level Radioactive Waste, and Other Materials Inventory and Characteristics of Spent Nuclear Fuel, High-Level Radioactive Waste, and Other Materials TABLE OF CONTENTS Section Page A. Inventory and Characteristics of Spent Nuclear Fuel, High-Level Radioactive Waste, and Other Materials ................................................................................................................................. A-1 A.1 Introduction .............................................................................................................................. A-1 A.1.1 Inventory Data Summary .................................................................................................... A-2 A.1.1.1 Sources ......................................................................................................................... A-2 A.1.1.2 Present Storage and Generation Status ........................................................................ A-4 A.1.1.3 Final Waste Form ......................................................................................................... A-6 A.1.1.4 Waste Characteristics ................................................................................................... A-6 A.1.1.4.1 Mass and Volume ................................................................................................. A-6 A.1.1.4.2 Radionuclide Inventories ...................................................................................... A-8 A.1.1.4.3 -
Preparation of Uranium Carbonitride by Reaction of UC with Ammonia
Journal of NUCLEARSCIENCE and TECHNOLOGY,5[8], p. 414~418 (August 1968). Preparation of Uranium Carbonitride by Reaction of UC with Ammonia Yumi AKIMOTO* and Koji TANAKA* Received January 24, 1968 Revised April 11, 1968 With the view to establishing a method of directly converting uranium carbide into uranium carbonitride and hydrocarbons, an attempt has been made to induce reaction between UC and am- monia under various temperatures from 25d to 600dc and pressures from 1 to 1,500 kg/cm2. The reaction aimed at was realized to the extent of practical significance under pressures exceeding 500 kg/cm2 at 450dc and exceeding 250 kg/cm2 at 500dc. The hydrocarbons produced thereby were found to be mainly methane, indicating that the formula of the predominant reaction was UC+NH3 -> UN2-x+CH4+H2. Upon heating the powdery fine black product to 1,800dc in vacuo, unexpectedly marked sinter- ing was found to occur, resulting in dense uranium monocarbonitride without any compaction pre- treatment. carbon is also reported. I. INTRODUCTION Another commonly known nitriding reac- Uranium mononitride (UN), and uranium tion is that between uranium carbides and carbonitride (UC1-xNx) have attracted much nitrogen, to result in a pulverized mixture of attention as possible fuel materials with quali- higher uranium nitrides and carbon(6)(7): ties surpassing uranium carbide (UC) with 2UC+3/2N2=U2N3+2C. (2) respect to chemical stability and simplicity of stoichiometric control. From the standpoint This reaction also fails to serve the purpose of fuel cost however, UN and UC1-xNx still of producing UN or UC1-xNx because carbon, yield to UC because the process at present once produced, cannot easily be separated available for the preparation of pure UN and from the nitride. -
This Thesis Has Been Submitted in Fulfilment of the Requirements for a Postgraduate Degree (E.G
This thesis has been submitted in fulfilment of the requirements for a postgraduate degree (e.g. PhD, MPhil, DClinPsychol) at the University of Edinburgh. Please note the following terms and conditions of use: This work is protected by copyright and other intellectual property rights, which are retained by the thesis author, unless otherwise stated. A copy can be downloaded for personal non-commercial research or study, without prior permission or charge. This thesis cannot be reproduced or quoted extensively from without first obtaining permission in writing from the author. The content must not be changed in any way or sold commercially in any format or medium without the formal permission of the author. When referring to this work, full bibliographic details including the author, title, awarding institution and date of the thesis must be given. Development of a High Temperature Sensor Suitable for Post-Processed Integration with Electronics Aleksandr Tabasnikov A thesis submitted for the degree of Doctor of Philosophy The University of Edinburgh 2016 Declaration of originality I declare that this thesis has been composed by me, the work is my own, and it has not been submitted for any other degree or professional qualification. Research recorded was carried out by me except as specified below: X-ray diffraction measurement results obtained using X-ray diffractometer Siemens D5000 were collected by Richard Yongqing Fu and his students Jimmy Zhou and Chao Zhao at the University of West of Scotland. Measurement results are analysed in section 4.4.6 of Chapter 4 and have been jointly published in 2014 (DOIs: 10.1109/ICMTS.2014.6841491). -
Surface Modification of G-C3N4 by Hydrazine: Simple Way for Noble-Metal Free Hydrogen Evolution Catalysts
Surface modification of g-C3N4 by hydrazine: Simple way for noble-metal free hydrogen evolution catalysts Item Type Article Authors Chen, Yin; Lin, Bin; Wang, Hong; Yang, Yong; Zhu, Haibo; Yu, Weili; Basset, Jean-Marie Citation Surface modification of g-C3N4 by hydrazine: Simple way for noble-metal free hydrogen evolution catalysts 2015 Chemical Engineering Journal Eprint version Post-print DOI 10.1016/j.cej.2015.10.080 Publisher Elsevier BV Journal Chemical Engineering Journal Rights NOTICE: this is the author’s version of a work that was accepted for publication in Chemical Engineering Journal. Changes resulting from the publishing process, such as peer review, editing, corrections, structural formatting, and other quality control mechanisms may not be reflected in this document. Changes may have been made to this work since it was submitted for publication. A definitive version was subsequently published in Chemical Engineering Journal, 2 November 2015. DOI: 10.1016/ j.cej.2015.10.080 Download date 03/10/2021 23:51:44 Link to Item http://hdl.handle.net/10754/581797 Accepted Manuscript Surface modification of g-C3N4 by hydrazine: Simple way for noble-metal free hydrogen evolution catalysts Yin Chen, Bin Lin, Hong Wang, Yong Yang, Haibo Zhu, Weili Yu, Jean-marie Basset PII: S1385-8947(15)01491-6 DOI: http://dx.doi.org/10.1016/j.cej.2015.10.080 Reference: CEJ 14356 To appear in: Chemical Engineering Journal Received Date: 18 June 2015 Revised Date: 9 October 2015 Accepted Date: 26 October 2015 Please cite this article as: Y. Chen, B. Lin, H. Wang, Y. -
Tantalum Nitride Nanotube Photoanodes: Establishing a Beneficial Back-Contact by Lift-Off and Transfer to Titanium Nitride Layer
Tantalum nitride nanotube photoanodes: establishing a beneficial back-contact by lift-off and transfer to titanium nitride layer Lei Wang, a Anca Mazare, a Imgon Hwang, a and Patrik Schmuki a,b,* a Department of Materials Science and Engineering, WW4-LKO, University of Erlangen- Nuremburg, Martensstrasse 7, D-91058 Erlangen, Germany. b Department of Chemistry, King Abdulaziz University, Jeddah, Saudi Arabia * E-mail: [email protected] Abstract In this work we introduce the use of TiN/Ti2 N layers as a back contact for lifted-off membranes of anodic Ta3N5 nanotube layers. In photoelectrochemical H2 generation experiments under simulated AM 1.5G light, shift of the onset potential for anodic photocurrents to lower potentials is observed, as well as a higher magnitude of the photocurrents compared to conventional Ta3N5 nanotubes (~0.5 V RHE ). We ascribe this beneficial effect to the improved conductive properties of the TiNx -based back contact layer that enables a facilitated electron-transport for tantalum-nitride based materials to the conductive substrate. Key words: tantalum nitride; nanotube membranes; titanium nitride; water splitting Link to the published article: http://dx.doi.org/10.1016/j.elecom.2016.08.012 1. Introduction Ta3N5 is considered to be one of the most important semiconductor materials for photoelectrochemical (PEC) water splitting. It has a visible-light active band gap of ~2.1 eV that embraces the H2O H2/O2 reduction-oxidation potentials, and thus may yield a 15.9% theoretical maximum solar-to-hydrogen (STH) conversion efficiency [1-9]. Extensive research has focused on nanostructuring the Ta3N5 photoelectrodes, in the form of nanoparticles, nanorods, or nanotubes [10-15]. -
Tanねlum Penねchlorid』E with Ammo血血the Vapor Pkase An《量properties of the Tan.Tal㎜ N’Itride Forme通
676 DENKI KAGAKU Fomation Process of Tanね1㎜Nitri-e by the Reaction of Tanねlum Penねchlorid』e with Ammo血血the VaPor Pkase an《量Properties of the Tan.tal㎜ N’itride Forme通 Akimasa YAJIMA*,Ryoko MATsuzAKI*and Yuzo SAEKI* The reaction products of gaseous TaC15with ammonia were TaCl5・5NH3at2QO。CラTaC15・5 NH3,Ta3N5,NH4Cl at250~600℃,Ta3N5and NH4Cl at650~950。C,Ta3N5,Ta4N5・and NH4Cl at 10000C,and Ta4N5シTa2N,θ一TaN,ε一TaN,NH4Cl,and HCl at1100~1400。C.In the vapor、phase reaction of gaseous TaCl5with ammonia,the reaction of gaseous TaC15with ammonia to form TaCI5・5NH3㏄curs丘rst.Above6α.235。C,the TaC15・5NH3reacts with ammonia to form Ta3N5. Above侃.1000。C,the Ta3N5decomposes to Ta4N5.Above侃。1100。C,in addition to these reactiolls, the nitriding of tantalum,formed by the reduction of gaseous TaCI5with hydrogen resulting from the thermal dissociation of ammonia,also o㏄urs to form Ta2Nシθ一TaN,andε一TaN.On heating the Ta3N5,formed by the vapor-phase reaction,in an argon atmosphere,it changed to Ta4N5at6α・ 9000C,to Ta5N6,θ一TaN,andε一TaN at6α.1100。C,and then toθ一TaN andε一TaN at1300~1400。C. The tantalum nitrides formed above1200。C were uniform,ultra丘ne powders with the particle diametersoftheorderof1/100粋m. 11ntroduction 2 Experimental The vapor-phase reaction of transition metal 2.1Materials chlorides with ammonia has recently become The TaCl,used was prepared by the reaction important for the preparation of6ne powders of tantalum powder(Ta99.8形,Hermann C. or thin丘lms of transition metal nitrides,which Starck Berlin)with chlorine at350℃and puri一 are aquiring importance -
Mathematical Model of the Oxidation of a Uranium Carbide Fuel Pellet Including an Adherent Product Layer
This is a repository copy of Mathematical Model of the Oxidation of a Uranium Carbide Fuel Pellet Including an Adherent Product Layer. White Rose Research Online URL for this paper: http://eprints.whiterose.ac.uk/110903/ Version: Accepted Version Article: Shepherd, JS, Fairweather, M, Hanson, BC orcid.org/0000-0002-1720-1656 et al. (1 more author) (2017) Mathematical Model of the Oxidation of a Uranium Carbide Fuel Pellet Including an Adherent Product Layer. Applied Mathematical Modelling, 45. pp. 784-801. ISSN 0307-904X https://doi.org/10.1016/j.apm.2017.01.041 © 2017 Elsevier Inc. This manuscript version is made available under the CC-BY-NC-ND 4.0 license http://creativecommons.org/licenses/by-nc-nd/4.0/ Reuse Unless indicated otherwise, fulltext items are protected by copyright with all rights reserved. The copyright exception in section 29 of the Copyright, Designs and Patents Act 1988 allows the making of a single copy solely for the purpose of non-commercial research or private study within the limits of fair dealing. The publisher or other rights-holder may allow further reproduction and re-use of this version - refer to the White Rose Research Online record for this item. Where records identify the publisher as the copyright holder, users can verify any specific terms of use on the publisher’s website. Takedown If you consider content in White Rose Research Online to be in breach of UK law, please notify us by emailing [email protected] including the URL of the record and the reason for the withdrawal request. -
Nonaqueous Syntheses of Metal Oxide and Metal Nitride Nanoparticles
Max-Planck Institut für Kolloid and Grenzflächenforschung Nonaqueous Syntheses of Metal Oxide and Metal Nitride Nanoparticles Dissertation zur Erlangung des akademischen Grades “doctor rerum naturalium” (Dr. rer. nat.) in der Wissenschaftsdisziplin “Kolloidchemie” eingereicht an der Mathematisch-Naturwissenschaftlichen Fakultät Universität Potsdam von Jelena Buha Potsdam, im Januar 2008 Dieses Werk ist unter einem Creative Commons Lizenzvertrag lizenziert: Namensnennung - Keine kommerzielle Nutzung - Weitergabe unter gleichen Bedingungen 2.0 Deutschland Um die Lizenz anzusehen, gehen Sie bitte zu: http://creativecommons.org/licenses/by-nc-sa/2.0/de/ Elektronisch veröffentlicht auf dem Publikationsserver der Universität Potsdam: http://opus.kobv.de/ubp/volltexte/2008/1836/ urn:nbn:de:kobv:517-opus-18368 [http://nbn-resolving.de/urn:nbn:de:kobv:517-opus-18368] С’ вером у Богa Abstract Nanostructured materials are materials consisting of nanoparticulate building blocks on the scale of nanometers (i.e. 10-9 m). Composition, crystallinity and morphology can enhance or even induce new properties of the materials, which are desirable for todays and future technological applications. In this work, we have shown new strategies to synthesise metal oxide and metal nitride nanomaterials. The first part of the work deals with the study of nonaqueous synthesis of metal oxide nanoparticles. We succeeded in the synthesis of In2O3 nanopartcles where we could clearly influence the morphology by varying the type of the precursors and the solvents; of ZnO mesocrystals by using acetonitrile as a solvent; of transition metal oxides (Nb2O5, Ta2O5 and HfO2) that are particularly hard to obtain on the nanoscale and other technologically important materials. Solvothermal synthesis however is not restricted to formation of oxide materials only. -
Tlju^Tt^ PROPERTIES of FUELS for HIGH-TEMPERATURE REACTOR
Tlju^tt^ PROPERTIES OF FUELS FOR HIGH-TEMPERATURE REACTOR CONCEPTS BATTELLE MEMORIAL INSTITUTE DISCLAIMER This report was prepared as an account of work sponsored by an agency of the United States Government. Neither the United States Government nor any agency Thereof, nor any of their employees, makes any warranty, express or implied, or assumes any legal liability or responsibility for the accuracy, completeness, or usefulness of any information, apparatus, product, or process disclosed, or represents that its use would not infringe privately owned rights. Reference herein to any specific commercial product, process, or service by trade name, trademark, manufacturer, or otherwise does not necessarily constitute or imply its endorsement, recommendation, or favoring by the United States Government or any agency thereof. The views and opinions of authors expressed herein do not necessarily state or reflect those of the United States Government or any agency thereof. DISCLAIMER Portions of this document may be illegible in electronic image products. Images are produced from the best available original document. CORRIGENDA BMI- 1598, PROPERTIES OF FUELS FOR HIGH-TEMPERATURE REACTOR CONCEPTS July 1, 1963 Please attach to report or make the following changes on the appropriate pages. Page Fuel Comparison Table: Substitute the following values for the thermal con ductivities for UO2 in cal/(sec)(cm)(C): 0. 026 at 20 C, 0. 008 at 600 C, 0. 005 at 1200 C. 11 Section C6: Rupture time :fo r 1600 F siloul d be 60. 2 ins tead of 60 2. 17 Section C6: Revise as follows; Stress for Creep Rate Shown, psi Rupture Data Temperature, 0.001 Per 0.01 Per 0.