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Author: Publisher: ISBN: Category : Languages : en Pages : 11
Book Description
Development and characterizations of phosphate and borosilicate glasses for vitrifying high level waste (HLW) solutions in Russia has been extensive. The technical data generated were for low concentrations (less than 0.05% Pu) of plutonium. Limited studies have been performed with plutonium concentrations one to two orders of magnitude larger. The results of these studies are being used to plan and implement an expanded experimental program to establish the limitations and characteristics of plutonium in similar glass compositions.
Author: Publisher: ISBN: Category : Languages : en Pages : 11
Book Description
Development and characterizations of phosphate and borosilicate glasses for vitrifying high level waste (HLW) solutions in Russia has been extensive. The technical data generated were for low concentrations (less than 0.05% Pu) of plutonium. Limited studies have been performed with plutonium concentrations one to two orders of magnitude larger. The results of these studies are being used to plan and implement an expanded experimental program to establish the limitations and characteristics of plutonium in similar glass compositions.
Author: Publisher: ISBN: Category : Languages : en Pages : 10
Book Description
As the nuclear weapon arsenals of the United States and the Former Soviet Union are reduced, metric tonnage quantities of fissile material must be dispositioned. One of the potential disposition options for fissile weapons material is vitrification into a stable form -- essentially a plutonium or uranium single phase glass product. Savannah River Technology Center (SRTC) at Savannah River Site (SRS) is actively developing suitable glass formulations for the long term safe storage of plutonium and uranium. These investigations are also being extended to develop glasses for the stabilization and storage of kilogram amounts of neptunium, americium, and curium that are currently stored as solutions in the process canyons at SRS -- thus the glasses are called actinide glasses. SRTC is also in the process of developing a remote process demonstration which can produce metric tonnage quantities of the glasses. This paper discusses the chemical compositions and durabilities of two types of actinide glasses under development. One of the glasses is a borosilicate, and the other an iron phosphate. In this initial study thorium and uranium were used as the actinides. Because of the low radioactivity of these elements, the glasses could be prepared and tested on the bench top. In studies beginning in FY '95, glasses containing neptunium, plutonium, americium and curium will be produced. These glasses will be prepared and tested remotely in the shielded cells and glovebox facilities at Savannah River Technology Center. In the initial study, a considerable number (>20) of thorium and uranium bearing glasses have been prepared. An equivalent number of rare earth surrogate (non-radioactive) glasses have also been prepared and tested. The glasses were prepared by mixing dry chemicals and melting them at 1425C for the borosilicate glasses and at 1100C for the iron phosphate glasses. (Abstract Truncated).
Author: J. Marra Publisher: ISBN: Category : Languages : en Pages :
Book Description
The Department of Energy Office of Environmental Management (DOE/EM) plans to conduct the Plutonium Disposition Project at the Savannah River Site (SRS) to disposition excess weapons-usable plutonium. A plutonium glass waste form is the preferred option for immobilization of the plutonium for subsequent disposition in a geologic repository. A reference glass composition (Lanthanide Borosilicate (LaBS) Frit B) was developed during the Plutonium Immobilization Program (PIP) to immobilize plutonium in the late 1990's. A limited amount of performance testing was performed on this baseline composition before efforts to further pursue Pu disposition via a glass waste form ceased. Recent FY05 studies have further investigated the LaBS Frit B formulation as well as development of a newer LaBS formulation denoted as LaBS Frit X. The objectives of this present task were to fabricate plutonium loaded LaBS Frit X glass and perform corrosion testing to provide near-term data that will increase confidence that LaBS glass product is suitable for disposal in the Yucca Mountain Repository. Specifically, testing was conducted in an effort to provide data to Yucca Mountain Project (YMP) personnel for use in performance assessment calculations. Plutonium containing LaBS glass with the Frit X composition with a 9.5 wt% PuO{sub 2} loading was prepared for testing. Glass was prepared to support Product Consistency Testing (PCT) at Savannah River National Laboratory (SRNL). The glass was thoroughly characterized using x-ray diffraction (XRD) and scanning electron microscopy coupled with energy dispersive spectroscopy (SEM/EDS) prior to performance testing. A series of PCTs were conducted at SRNL using quenched Pu Frit X glass with varying exposed surface areas. Effects of isothermal and can-in-canister heat treatments on the Pu Frit X glass were also investigated. Another series of PCTs were performed on these different heat-treated Pu Frit X glasses. Leachates from all these PCTs were analyzed to determine the dissolved concentrations of key elements. Acid stripping of leach vessels was performed to determine the concentration of the glass constituents that may have sorbed on the vessels during leach testing. Additionally, the leachate solutions were ultrafiltered to quantify colloid formation.
Author: Ian W. Donald Publisher: John Wiley & Sons ISBN: 1444319361 Category : Science Languages : en Pages : 526
Book Description
The safe storage in glass-based materials of both radioactiveand non-radioactive hazardous wastes is covered in a single book,making it unique Provides a comprehensive and timely reference source at thiscritical time in waste management, including an extensive andup-to-date bibliography in all areas outlined to waste conversionand related technologies, both radioactive and non-radioactive Brings together all aspects of waste vitrification, drawscomparisons between the different types of wastes and treatments,and outlines where lessons learnt in the radioactive waste fieldcan be of benefit in the treatment of non-radioactive wastes
Author: Alfred Margaryan Publisher: World Scientific ISBN: 9814494682 Category : Science Languages : en Pages : 192
Book Description
The study of the effect of ligand and modifier ions on the spectroscopic properties of dn or fn elements in vitreous materials is important for the development of controllable lasers and amplifiers. The spectroscopic characteristics of inorganic compounds of transition elements and their solutions are well understood theoretically in the spectrochemistry of complexes, but developments for vitreous materials in these conditions have not been well documented. This book fills the gap by applying the ligand field theory of solid materials to the vitreous state, and presenting the data obtained from luminescence, electron absorption spectra and electron paramagnetic resonance.This unique book is a valuable addition to the field of spectroscopy of doped vitreous materials and optical glasses. It will benefit all materials scientists, solid state physicists, spectroscopists and physical chemists, as well as graduate students.
Author: E.R. Merz Publisher: Springer Science & Business Media ISBN: 9780792338413 Category : Science Languages : en Pages : 360
Book Description
This NATO Advanced Research Workshop on Disposal of Weapons Plutonium is a follow-up event to two preceding workshops, each dealing with a special subject within the overall disarmament issue: "Disposition of Weapon Plutonium", sponsored by the NATO Science Committee. The first workshop of this series was held at the Royal Institute of International Affairs in London on 24-25 January 1994, entitled "Managing the Plutonium Surplus, Applications, and Options". Its over all goal was to clarify the current situation with respect to pluto nium characteristics and availability, the technical options for use or disposal, and their main technical, environmental, and economic constraints. In the immediate term, plutonium recovered from dismantled nuclear warheads will have to be stored securely, and under international safeguards if possible. In the intermediate term, the principal alter natives for disposition of this plutonium are: irradiation in mixed oxide (MOX) fuel assemblies in existing commercial light-water reac tors or in specially adapted light-water reactors capable of operation with full cores of MOX fuel .and irradiation in future fast reactors. Another option is to blend plutonium with high-level waste as it is vitrified for final disposal in a geologic repository. In both cases, the high radioactivity of the resulting products provides "self shielding" and prevents separation of plutonium without already developed and available sophisticated technology. The so-called "spent fuel standard" as an effective protection barrier is - quired in either case.
Author: United States. Congress. House. Committee on Commerce. Subcommittee on Oversight and Investigations Publisher: ISBN: Category : Public contracts Languages : en Pages : 420
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Author: American Nuclear Society
Author: J. Marra
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Author: Ian W. Donald
Author: Alfred Margaryan
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Author: E.R. Merz
Author: United States. Congress. House. Committee on Commerce. Subcommittee on Oversight and Investigations