High-Level Waste Melter Study Report
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1, 2002, Sheraton Crystal City Hotel, Arlington, Virginia
Minutes for the Nuclear Energy Research Advisory Committee Meeting September 30 to October 1, 2002, Sheraton Crystal City Hotel, Arlington, Virginia NERAC members present: John Ahearne Dale Klein (Monday only) Thomas Cochran Robert Long Joseph Comfort Warren F. Miller, Jr. Michael Corradini Sekazi Mtingwa Jose Luis Cortez Richard Reba (Monday only) Maureen Crandall (Monday afternoon Joy Rempe and Tuesday only) Allen Sessoms Allen Croff Daniel Sullivan James Duderstadt (Chair) John Taylor Marvin Fertel (Monday only) Neil Todreas Beverly Hartline Joan Woodard (Monday only) Andrew Klein NERAC members absent: Steve Fetter Lura Powell Leslie Hartz C. Bruce Tarter J. Bennett Johnston Ashok Thadani (ad hoc) Linda C. Knight Charles E. Till Benjamin F. Montoya Also present: Ralph Bennett, Director for Advanced Nuclear Energy, Idaho National Engineering and Environmental Laboratory David Berg, Office of Environmental Management, DOE Nancy Carder, NERAC Staff Herbert Feinroth, President, Gamma Engineering Corp. John Gutteridge, University Programs, NE, USDOE Norton Haberman, Senior Technical Advisor, NE, USDOE Anthony Hechanova, Director, AAA University Participation Program, University of Nevada at Las Vegas R. Shane Johnson, Associate Director, Office of Technology and International Cooperation, NE, USDOE Silvia Jurisson, Department of Chemistry, University of Missouri, Columbia Owen Lowe, Associate Director, Office of Isotopes for Medicine and Science, NE, USDOE William Magwood, Director, NE, USDOE William Martin, Washington Policy Institute -
Mar Customer Order Form
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Ceramic Mineral Waste-Forms for Nuclear Waste Immobilization
materials Review Ceramic Mineral Waste-Forms for Nuclear Waste Immobilization Albina I. Orlova 1 and Michael I. Ojovan 2,3,* 1 Lobachevsky State University of Nizhny Novgorod, 23 Gagarina av., 603950 Nizhny Novgorod, Russian Federation 2 Department of Radiochemistry, Lomonosov Moscow State University, Moscow 119991, Russia 3 Imperial College London, South Kensington Campus, Exhibition Road, London SW7 2AZ, UK * Correspondence: [email protected] Received: 31 May 2019; Accepted: 12 August 2019; Published: 19 August 2019 Abstract: Crystalline ceramics are intensively investigated as effective materials in various nuclear energy applications, such as inert matrix and accident tolerant fuels and nuclear waste immobilization. This paper presents an analysis of the current status of work in this field of material sciences. We have considered inorganic materials characterized by different structures, including simple oxides with fluorite structure, complex oxides (pyrochlore, murataite, zirconolite, perovskite, hollandite, garnet, crichtonite, freudenbergite, and P-pollucite), simple silicates (zircon/thorite/coffinite, titanite (sphen), britholite), framework silicates (zeolite, pollucite, nepheline /leucite, sodalite, cancrinite, micas structures), phosphates (monazite, xenotime, apatite, kosnarite (NZP), langbeinite, thorium phosphate diphosphate, struvite, meta-ankoleite), and aluminates with a magnetoplumbite structure. These materials can contain in their composition various cations in different combinations and ratios: Li–Cs, Tl, Ag, Be–Ba, Pb, Mn, Co, Ni, Cu, Cd, B, Al, Fe, Ga, Sc, Cr, V, Sb, Nb, Ta, La, Ce, rare-earth elements (REEs), Si, Ti, Zr, Hf, Sn, Bi, Nb, Th, U, Np, Pu, Am and Cm. They can be prepared in the form of powders, including nano-powders, as well as in form of monolith (bulk) ceramics. -
Nuclear Waste Vitrification Efficiency: Cold Cap Reactions
Journal of Non-Crystalline Solids 358 (2012) 3559–3562 Contents lists available at SciVerse ScienceDirect Journal of Non-Crystalline Solids journal homepage: www.elsevier.com/ locate/ jnoncrysol Nuclear waste vitrification efficiency: Cold cap reactions P. Hrma a,b,⁎, A.A. Kruger c, R. Pokorny d a Division of Advanced Nuclear Engineering, Pohang University of Science and Technology, Pohang, Republic of Korea b Pacific Northwest National Laboratory, Richland, WA 99352, USA c U.S. Department of Energy Hanford Tank Waste Treatment and Immobilization Plant Federal Project Office, Engineering Division, Richland, WA 99352, USA d Institute of Chemical Technology, Prague, Czech Republic article info abstract Article history: Batch melting takes place within the cold cap, i.e., a batch layer floating on the surface of molten glass in a Received 26 July 2011 glass-melting furnace. The conversion of batch to glass consists of various chemical reactions, phase transi- Received in revised form 5 January 2012 tions, and diffusion-controlled processes. This study introduces a one-dimensional (1D) mathematical Available online 7 March 2012 model of the cold cap that describes the batch-to-glass conversion within the cold cap as it progresses in a vertical direction. With constitutive equations and key parameters based on measured data, and simplified Keywords: boundary conditions on the cold-cap interfaces with the glass melt and the plenum space of the melter, Glass melting; Glass foaming; the model provides sensitivity analysis of the response of the cold cap to the batch makeup and melter con- Waste vitrification; ditions. The model demonstrates that batch foaming has a decisive influence on the rate of melting. -
Final Vitrification Melter Evaluation
Waste-Incidental-to-Reprocessing Evaluation for the West Valley Demonstration Project Vitrification Melter February 2012 Prepared by the U.S. Department of Energy West Valley, New York This page is intentionally blank. WASTE-INCIDENTAL-TO-REPROCESSING EVALUATION FOR THE WVDP VITRIFICATION MELTER CONTENTS NOTATION (Acronyms, Abbreviations, and Units).................................................. v 1.0 INTRODUCTION ...................................................................................................... 1 1.1 Purpose. ................................................................................................................. 2 1.2 Scope and Technical Basis ....................................................................................... 2 1.3 Consultation and Opportunity for Public Review ........................................................ 3 1.4 Background ............................................................................................................ 4 1.4.1 The Western New York Nuclear Service Center .............................................. 4 1.4.2 Spent Nuclear Fuel Processing ...................................................................... 6 1.4.3 The West Valley Demonstration Project ......................................................... 7 1.4.4 Characterization of the Vitrification Melter ..................................................... 7 1.4.5 Incorporation into a Solid Physical Form ........................................................ 8 1.4.6 Potential Waste Disposal -
Progress in Nuclear Waste Vitrification by Ceramic Melter Technique
JP9950237 PROGRESS IN NUCLEAR WASTE VITRIFICATION BY CERAMIC MELTER TECHNIQUE S. WEISENBURGER Forschungszentrum Karlsruhe Institut fur Nukleare Entsorgungstechnik P.O.BOX 3640, 76021 Karlsruhe, Germany ABSTRACT Nuclear waste vitrification by using the liquid-fed ceramic-lined waste glass melter process started in 1973 with the pioneering development at Batelle Pacific Northwest Laboratory. The first radioactive plant applying this technique was the PAMELA plant in Mol/ Belgium which was put into hot operation in 1985. A main part of the technology for this plant including the melter was developed by the Institut fur Nukleare Entsorgungstechnik (INE) of Forschungszentrum Karlsruhe (FZK)! For the time being there is an increasing demand for the availability of small-scale vitrification units for processing of small stocks of high level liquid wastes (HLLW). Limited quantities of HLLW solutions were obtained during the period of development of reprocessing techniques at various international sites. One example is the former WAK (Wiederaufarbeitungs-anlage Karlsruhe) reprocessing plant. It is located at the site of Forschungszentrum Karlsruhe and is now under decommissioning. The overall decommissioning program includes vitrification of 70 m3 of stored HLLW with a total p7y radioactivity of 8.9 x E17 Bq. This paper focuses on progress achieved in the design of small-scale liquid-fed ceramic glass melters for these purposes. Improvements are described regarding extension of power electrode life time by optimized air cooling, glass pouring operation, off-gas pipe cleaning, glass level detection system in the melt tank, and arrangement of a small-scale melter in a hot a cell. Some test results achieved with the new melter are also outlined. -
Vitrification of Ion-Exchange (IEX) Resins: Advantages and Technical Challenges
WSRC-MS-95-0518 Vitrification of Ion-Exchange (IEX) Resins: Advantages and Technical Challenges bv C. M. Jantzen Westinghouse Savannah River Company Savannah River, Site Aiken, South Carolina 29808 D. K. Paster G. A. Cicero A document prepared for AMERICAN CERAMIC SOCIETY ANNUAL MEETING, NUCLEAR DIVISION at Indianapolis frorrt 04/14/95 - 04/17/95. DOE Contract No. DE-AC09-89SR18035 This paper was prepared in connection with work done under the above contract number with the U. S. Department of Energy. By acceptance of this paper, the publisher and/or recipient acknowledges the U. S. Government's right to retain a nonexclusive, royalty-free license in and to any copyright covering this paper, along with the right to reproduce and to authorize others to reproduce all or part of the copyrighted paper. 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. -
Economic Development Board 1 South Australia
ECONOMIC DEVELOPMENT BOARD 1 SOUTH AUSTRALIA 3 August 2015 Rear Admiral the Honourable Kevin Sca rce AC CSC RAN (Rtd) Roya l Commissioner for the Nuclear Fuel Cycle Royal Commission Level 5, 50 Grenfell Street Adelaide SA 5000 Dear Commissioner RE: Nuclear fuel Cycle Royal Commission I write to provide a discussion paper prepared by ThinkCiimate for the Economic Development Board (EDB), that responds to the four issues papers released by the Nuclear Fuel Cycle Roya l Commission on: Exploration, Extraction and Milling; Further Processing and Manufacture; Electricity Generation; and Management, Storage and Disposal of Waste. In October 2014, in the absence of reliable and cu rrent data and evidence on the nuclear value chain, the EDB commissioned ThinkCiimate Consulting to prepare a discussion paper. The purpose of the discussion paper was to explore the opportunities for an expanded role for South Australia in the nuclear value chain and to provide a high level business case to indicate if there is sufficient economic potential to warrant a more thorough investigation. The discussion paper, provided to you as Attachment 1 to this letter, explores the economic opportunities for South Australia at each point in the nuclear value cha in and, therefore, responds to the four Issues Papers released. The discussion paper concludes that: • There is potentially a major economic opportunity for South Australia in the safe management of spent nuclear fuel based on merging mature Intermediate Spent Fuel Storage Installation (ISFI) technology with Generation IV recycling and reactor technology. • Further a preliminary project assessment finds that a proposed configuration of an ISFSI and Integrated Fast Reactor (IFR) technology would utilise up to approximately 99% of the stored fuel to generate electricity as a low-cost, emissions free baseload with potentially significant economic benefits to South Australia within a relatively short timeframe. -
Transformation (T TT) Diagram for EPY® Epoxy System
18 2018, 63, nr 1 Glass transition temperature-cure temperature- ® -transformation (TgTT) diagram for EPY epoxy system Magdalena Urbaniak1) DOI: dx.doi.org/10.14314/polimery.2018.1.3 Abstract: The EPY® epoxy system applied for the production of machine foundation chocks was iso- thermally cured at varying cure temperatures and times. The thermal behavior during the curing of the system was monitored by means of the glass transition temperature (Tg) and conversion degree (α) measured using differential scanning calorimetry (DSC) and rotational viscometry (ARES). Also, the thermal decomposition was measured by thermogravimetry and differential thermal analysis (TG-DTA). The results were analyzed and summarized in the generalized phase diagram, as well as in the Tg-cure temperature-transformation (TgTT) cure diagram. The phase diagram has reference to the transformations (in liquid, ungelled glass, gelled glass and rubber state) encountered at time to gelation and vitrification. Whereas theT gTT diagram shows that there are three types of behavior related to the temperature of cure and makes a useful framework for understanding and analyzing the relations and interdependencies during the curing process of the epoxy system. Keywords: epoxy system, curing, gelation, vitrification, glass transition temperature, glass transition temperature-cure temperature-transformation diagram. Diagram temperatura zeszklenia-temperatura sieciowania-przemiana (TgTT) dla układu epoksydowego EPY® Streszczenie: Próbki układu epoksydowego EPY®, używanego do wytwarzania podkładek funda- mentowych maszyn, sieciowano izotermicznie stosując różne temperatury i różny czas sieciowania. Metodami różnicowej kalorymetrii skaningowej (DSC) i wiskozymetrii rotacyjnej (ARES) zbadano przemiany tak przygotowanych układów pod wpływem zmian temperatury wyznaczając temperaturę zeszklenia (Tg) i stopień konwersji (α). Badano także rozkład termiczny próbek za pomocą symulta- nicznej termograwimetrycznej i różnicowej analizy termicznej (TG-DTA). -
Invincible Iron Man: Stark Resilient Vol
INVINCIBLE IRON MAN: STARK RESILIENT VOL. 5, BOOK 1 PDF, EPUB, EBOOK Matt Fraction,Salvador Larroca | 128 pages | 23 Feb 2011 | Marvel Comics | 9780785145561 | English | New York, United States Invincible Iron Man: Stark Resilient Vol. 5, book 1 PDF Book But I don't blame Fraction for that. Science Fiction. Invincible Iron Man Vol. Apparently he's been doing this for the entirety of Iron Man's run. Yet the way Stark chose to kill himself was so convoluted and drawn out that it made no sense. No more producing weapons, but rather producing green energy for the whole world. Oct 18, Jeff Lanter rated it really liked it Shelves: graphic-novels. I say that because I am in that category and would have never tried Iron Man otherwise. I think this Omnibus also does a great job of introducing characters from the wider Marvel universe. A good Iron Man story always needs a good secondary story concerning Stark and this book delivers on that front. Fraction does a good job of writing an action-packed story. Invincible Iron Man Collected Editions 1 - 10 of 12 books. The only reason this didn't get 5 stars is because of the sexist artwork. Only the next arc is set up for the one after and so on and so on. Unfortunately, I dislike all of these storylines intensely. Yes, people whine about how there isn't enough Iron Man action, but that doesn't bother me. Tony's broke and is trying to make amends for his years in the weapons biz by creating cheap energy products the first prototype being a repulsar powered car. -
Progress Report
SYNROC STUDY GROUP PROGRESS REPORT August 1991 SYNROC STUDY PROGRESS REPORT August 1991 The Broken Hill Proprietary Company Limited (A.CN. 004 028 077) CRA Limited (A.C.N. 004 458 404) Energy Resources of Australia Limited (A.C.N. 008 550 865) Western Mining Corporation Limited (A.C.N. 004 184 598) Australian Nuclear Science and Technology Organisation Australian National University OVERVIEW This Progress Report has been prepared by the Synroc Study Group (SSG), comprising staff members of The Australian Nuclear Science and Technology Organisation (ANSTO), The Australian National University (ANU), BHP, CRA, Energy Resources of Australia (ERA) and Western Mining Corporation (WMC). It also draws upon work undertaken for the SSG by consultants from Nuclear Assurance Corporation (market estimates), the Swedish Nuclear Fuel and Waste Management Company (SKB) (cost estimates and other data) and Wave Hill Associates (US and international perspectives). Synroc is applicable solely to the immobilisation of liquid high-level waste after such waste has been separated from spent fuel in a reprocessing operation; use of Synroc therefore requires prior construction of a reprocessing plant An alternative management strategy, based upon direct disposal of encapsulated spent nuclear fuel, does not require reprocessing, and therefore makes no use of Synroc. The SSG has examined both of these alternatives and also a third, which is to defer decision-making on reprocessing versus direct disposal for a lengthy period while spent fuel is held in interim storage. The SSG recognises that many utilities and countries have deferred decisions as between reprocessing and direct disposal of spent fuel. The construction of interim spent fuel storage facilities and related infrastructure appears to be a practical strategy in the short term, although for many utilities and countries this period of satisfactory and acceptable deferral may be starting to run out. -
Letterhead World Nuclear Association
ISSUES PAPER 4 – MANAGEMENT, STORAGE, DISPOSAL OF NUCLEAR AND RADIOACTIVE WASTE Submission from the World Nuclear Association to the South Australian Nuclear Fuel Cycle Royal Commission Introduction The World Nuclear Association is grateful for this opportunity to answer the Commission’s questions regarding the management, storage and disposal of radioactive wastes in South Australia. There is considerable international experience in handling radioactive material and wastes, which it may be noted are neither particularly hazardous nor hard to manage relative to some other toxic industrial wastes. The storage and handling of civil nuclear wastes has been safely undertaken for more than 50 years. The aim in radioactive waste management is to protect people and the environment utilising three general principles – concentration and containment, dilution and dispersal, delay and decay. The first two principles are also used in the management of other, non-radioactive, wastes. The third principle works by storing the waste long enough until radioactive decay renders the waste no longer radiologically hazardous. Unlike some other toxic wastes, such as heavy metals, the principal hazard associated with nuclear waste – radioactivity – diminishes with time. The pillar of any national waste management plan is the responsible implementation of an institutional framework. Authoritative international organisations provide advice on institutional frameworks for the management of nuclear wastes. These include the International Atomic Energy Agency (IAEA), the Nuclear Energy Agency (NEA) of the Organisation for Economic Co-operation and Development (OECD), the European Commission (EC) and the International Commission on Radiological Protection (ICRP). International agreements in the form of conventions under the auspices of the IAEA have also been established, such as the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management.