Rolla, MO, United States
Rolla, MO, United States

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This invention relates to low density radioactive magnesium-aluminum-silicate (MAS) microparticles for radiotherapy and/or radioimaging.


Grant
Agency: Department of Energy | Branch: | Program: STTR | Phase: Phase I | Award Amount: 225.00K | Year: 2013

Nuclear power is a key component in the strategy to meet the countrys energy goals and technologies are needed to improve the reliability of current reactors and disposing safely of nuclear wastes. Vitrification is considered the preferred process for nuclear waste disposal and the U.S. Department of Energy (DOE) currently approves only borosilicate glasses (BS) for that purpose. However, many nuclear wastes have complex compositions that are poorly soluble in BS glasses while Fe-phosphate (FeP) glasses can dissolve larger amounts of problematic components (i.e., S, Al, Na, halides, and heavy metals). This work will provide a property/composition model for FeP glasses containing simulated AZ102 LAW (low activity waste), a defense waste stream that is difficult to vitrify in BS glass due to its high combined sulfate (17 wt. %) and alkali (80 wt. %) content. Similar statistical modeling work can then be applied to wastes from domestic fuel cycles. Phase I will focus on the system P2O5Fe2O3Al2O3Na2OSO3 (which corresponds to 91 6 wt. % of the final vitrified waste, based on previous work) to identify a potential compositional region for further study in Phase II and vitrifying the Hanford AZ102 LAW. The properties for the modeling include, melting temperature and glass formability of the compositions, and chemical durability of the FeP glass waste forms. Phase II task will be extended to include a statistically experimental design with a larger number of components to produce a qualified composition region with melt processing parameters and glass form properties that meet DOE requirements. The deliverables are intended to include (1) highest attainable waste loading, (2) good glass formation tendency, and low melting temperatures, (3) high retention of sulfate, SO3, and other volatile/ hazardous species, and (4) a chemical durability that meets DOE requirements. Prior work with the AZ102 waste has demonstrated that this waste can be vitrified in FeP glasses with an sulfate content exceeding in 40% the DOE recommended sulfur retention limit. FeP glasses can vitrify wastes that are poorly suited for BS glasses. In particular, FeP glasses can dissolve and retain a much high sulfate content than is possible in BS glass. This work will provide additional data confirming the potential of FeP glasses to vitrify problem wastes at Hanford and a method for analyzing other similar wastes.


Grant
Agency: Department of Energy | Branch: | Program: STTR | Phase: Phase I | Award Amount: 149.95K | Year: 2014

Solid oxide fuel cells (SOFCs) require robust seals that can prevent intermixing of air and fuel, remain inert in reducing and oxidizing environments while in contact with SOFC materials, and maintain their effectiveness through repeated thermal cycles. Recent research has focused on compliant (or viscous) glasses that remain vitreous over time in the SOFC stack operating environment, and are able to tolerate relative motion between the surfaces being sealed without the development of permanent leaks. Certain glasses (under investigation by MO-SCI and others) considered for this sealing application have broadly desirable thermo-mechanical properties and thermo-chemical characteristics, but have been found to chemically react with both bare and aluminized stainless steel SOFC interconnects, consequently forming phases that may adversely affect the integrity of the seal. On the other hand, these glasses do not react with the yttria-stabilized zirconia (YSZ) electrolyte used in most SOFC designs. Thus, YSZ could be an attractive barrier layer between the metallic SOFC interconnect and the sealing glass. The main goal of the proposed nine month, STTR Phase I program is to develop a dense and well-bonded YSZ coating on an SOFC interconnect alloy. The coating method proposed in this project utilizes the two-step YSZ powder/polymer process that has successfully deposited YSZ coatings on SOFC electrodes. This two-step YSZ infiltration method does not require special equipment such as plasma or laser deposition source, and the process can be scaled up and is suitable for coating larger and more complex surfaces. Our preliminary studies have already demonstrated proof-of- concept. During the Phase 1 program, we will (1) determine the relationships between processing parameters and the YSZ coating thickness; (2) determine how these processing conditions affect the interactions between the YSZ coatings and the viscous sealing glass; and (3) characterize the long-term interfacial reactions between optimized coating and the underlying stainless steel as well as the viscous sealing glass. Commercial Applications and Other Benefits: This STTR project will assist the nations SOFCs program in meeting its cost and performance targets by ensuring a stable barrier layer between SOFC interconnects and seals, and consequently achieving reliable seal operation over an extended operating life. The program will ultimately enable fuel cell-based near-zero emission coal plants with greatly reduced water requirements and the capability of capturing 97 percent or greater of carbon at costs not exceeding the typical cost of electricity available today. Achieving this goal will significantly impact the nation given the size of the market, expected growth in energy demand, and the age of the existing power plant fleet. It will also provide the technology base to enable grid-independent distributed generation applications.


This invention relates to low density radioactive magnesium-aluminum-silicate (MAS) microparticles for radiotherapy and/or radioimaging.


Grant
Agency: National Aeronautics and Space Administration | Branch: | Program: SBIR | Phase: Phase I | Award Amount: 124.99K | Year: 2014

Sealing glasses, either rigid glass-ceramics or viscous, non-crystallizing compositions, will be developed and sealing processes will be optimized based on NASA's solid oxide fuel cell (SOFC) designs. SOFC design constraints, including material selection and operational conditions, will guide compositional development, and then these new compositions will be used for long-term (>500 hours) material compatibility tests under SOFC operational conditions. Prototype seals will be produced and will be thermally cycled between room temperature and 850?C to test the thermo-mechanical compatibility of the sealing materials with SOFC components. At the end of this Phase I project, sealing compositions and processes will be identified for SOFC applications identified by NASA.


Patent
MO-SCI Corporation | Date: 2014-10-21

This invention relates to strontium-phosphate microparticles that incorporate radioisotopes for radiation therapy and imaging.


Patent
MO-SCI Corporation | Date: 2014-10-21

This invention relates to a method for making strontium-phosphate microparticles that incorporate radioisotopes for radiation therapy and imaging.


Patent
MO-SCI Corporation | Date: 2016-06-30

A resorbable bone graft scaffold material, including a plurality of overlapping and interlocking fibers defining a scaffold structure, plurality of pores distributed throughout the scaffold, and a plurality of glass microspheres distributed throughout the pores. The fibers are characterized by fiber diameters ranging from about 5 nanometers to about 100 micrometers, and the fibers are a bioactive, resorbable material. The fibers generally contribute about 20 to about 40 weight percent of the scaffold material, with the microspheres contributing the balance.


Patent
MO-SCI Corporation | Date: 2016-06-30

A resorbable bone graft scaffold material, including a plurality of overlapping and interlocking fibers defining a scaffold structure, plurality of pores distributed throughout the scaffold, and a plurality of glass microspheres distributed throughout the pores. The fibers are characterized by fiber diameters ranging from about 5 nanometers to about 100 micrometers, and the fibers are a bioactive, resorbable material. The fibers generally contribute about 20 to about 40 weight percent of the scaffold material, with the microspheres contributing the balance.


Grant
Agency: Department of Energy | Branch: | Program: SBIR | Phase: Phase II | Award Amount: 999.87K | Year: 2015

Most liquid high-level nuclear waste is currently being immobilized to a solid form as a borosilicate glass by vitrification. However, many nuclear wastes have complex and diverse chemical compositions that reduce their compatibility with borosilicate glass. The current baseline spent nuclear fuel reprocess generates secondary waste streams that generally include large amounts of MoO3 and noble metals that are poorly soluble in borosilicate glasses and thereby limit the waste loading. New waste forms as alternatives to borosilicate glass are being sought to increase the waste loading while retaining acceptable chemical durability and thus to decrease the total nuclear waste volume required for storage and disposal. The main goal of the SBIR Phase I and Phase II projects is to develop suitable iron phosphate-based compositions for vitrifying the MoO3-rich waste (Collins-CLT) generated from reprocessed spent nuclear fuel with greater waste loadings than can presently be achieved with borosilicate glass and while retaining chemical durability that meets or exceeds appropriate Department of Energy (DOE) standards. The Phase I research successfully produced an iron phosphate waste form containing 40 wt% of simulated Collins-CLT waste, and this waste form can be prepared at 1300C. The product consistency test (PCT) response and the vapor hydration test (VHT) corrosion rate of this waste form (as-cast) meet current DOE chemical durability requirements. Structure-composition-property relationships in simplified Na-Fe-Mo-phosphate glasses were also studied to better understand the more complex waste-loaded glasses. Phase II activities will build on the Phase I accomplishments by optimizing the iron phosphate compositions and measuring useful thermal, electrical, and chemical properties of the iron phosphate waste forms for commercial-scale production. The Phase II work will also address the unanswered questions identified in Phase I, including the preferential molybdenum leach rate, the nature of the Mo-Fe redox reactions in glass melts, and the effects of melt redox on the waste form structure and chemical stability. Commercial-scale (60 kg) melting of a selected iron phosphate waste form in a cold crucible induction melter will be demonstrated. The proposed research will produce chemically stable iron phosphate waste forms with increased radioactivity concentrations that will reduce by up to 50% the total nuclear waste volume from spent nuclear fuel needed for long-term storage and disposal. This would lead to considerable savings of time and money for the Nations effort to remediate nuclear waste especially that associated with the advanced domestic fuel cycle program.

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