Sample records for u-233 disposition medical

  1. EA-1488: Environmental Assessment for the U-233 Disposition, Medical

    Broader source: Energy.gov (indexed) [DOE]

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742Energy China U.S.ContaminationJuly 2011D APPENDIX D9 STAT.BPA's10 CFR 433: Energy

  2. Storage and disposition of weapons usable fissile materials (FMD) PEIS: Blending of U-233 to {lt}12% or {lt}5% enrichment at the Idaho National Engineering Laboratory. Data report, Draft: Version 1

    SciTech Connect (OSTI)

    Shaber, E.L.

    1995-08-01T23:59:59.000Z

    Uranium-233 (U-233), a uranium isotope, is a fissionable material capable of fueling nuclear reactors or being utilized in the manufacturing of nuclear weapons. As such, it is controlled as a special nuclear material. The Idaho National Engineering Laboratory (INEL) and Oak Ridge National Laboratory (ORNL) currently store the Department of Energy`s (DOE`s) supply of unirradiated U-233 fuel materials. Irradiated U-233 is covered by the national spent nuclear fuel (SNF) program and is not in the scope of this report. The U-233 stored at ORNL is relatively pure uranium oxide in the form of powder or monolithic solids. This material is currently stored in stainless steel canisters of variable lengths measuring about 3 inches in diameter. The ORNL material enrichment varies with some material containing considerable amounts of U-235. The INEL material is fuel from the Light Water Breeder Reactor (LWBR) Program and consists of enriched uranium and thorium oxides in zircaloy cladding. The DOE inventory of U-233 contains trace quantities of U-232, and daughter products from the decay of U-232 and U-233, resulting in increased radioactivity over time. These increased levels of radioactivity generally result in the need for special handling considerations.

  3. DOE/EA-1488: Environmental Assessment for the U-233 Disposition, Medical Isotope Production, and Building 3019 Complex Shutdown at the Oak Ridge National Laboratory (12/04)

    Office of Environmental Management (EM)

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  4. EA-1488: Environmental Assessment for the U-233 Disposition,...

    Broader source: Energy.gov (indexed) [DOE]

    material currently stored at other U. S. Department of Energy (DOE) sites in order to render it suitable for safe, long-term, economical storage. The 233U is stored within Bldg....

  5. Th/U-233 multi-recycle in PWRs.

    SciTech Connect (OSTI)

    Yun, D.; Kim, T. K.; Taiwo, T. A.; Nuclear Engineering Division

    2010-09-07T23:59:59.000Z

    The use of thorium in current or advanced light water reactors (LWRs) has been of interest in recent years. These interests have been associated with the need to increase nuclear fuel resources and the perceived non-proliferation advantages of the utilization of thorium in the fuel cycle. Various options have been considered for the use of thorium in the LWR fuel cycle including: (1) its use in a once-through fuel cycle to replace non-fissile uranium or to extend fuel burnup due to its attractive fertile material conversion, (2) its use for fissile plutonium burning in limited recycle cores, and (3) its advantage in limiting the transuranic elements to be disposed off in a repository (if only Th/U-233 fuel is used). The possibility for thorium utilization in multirecycle system has also been considered by various researchers, primarily because of the potential for near breeders with Th/U-233 in the thermal energy range. The objective of this project is to evaluate the potential of the Th/U-233 fuel multirecycle in current LWRs, with focus this year on pressurized water reactors (PWRs). In this work, approaches for ensuring a sustainable multirecycle without the need for external source of makeup fissile material have been investigated. The intent is to achieve a design that allows existing PWRs to be used with minimal modifications. In all cases including homogeneous and heterogeneous assembly designs, the assembly pitch is kept consistent with that of the current PWRs (21.5 cm used). Because of design difficulties associated with using the same geometry and dimensions as a PWR core, the potential modifications (other than assembly pitch) that would be needed for PWRs to ensure a sustainable multirecycle system have been investigated and characterized. Additionally, the implications of the use of thorium on the LWR fuel cycle are discussed. In Section 2, background information on studies evaluating the use of thorium in the fuel cycle is provided, but focusing on Th/U-233 multirecycle. Recent studies done internationally and in the U.S. are briefly summarized. Additionally, the previous U.S. thorium breeder experiment in the Shippingport reactor is briefly discussed. The objective of this work and the reactor design issues associated with multirecycle of Th/U-233 are discussed in Section 3. The approaches required to achieve a sustainable system are discussed and evaluated. Homogeneous assembly modeling results are presented in this section. In Section 4, a 17-by-17 heterogeneous assembly design has been selected and evaluated, based on its positive attributes for sustainable Th/U-233 multirecycle. A feasibility study is briefly discussed at the end of this section followed by recommendations for future activities. Section 5 discusses the attributes of the 17-by-17 heterogeneous assembly design. The material mass flow data and fuel cycle impact data are reported in this section. Discussions on the fuel cycle implications of thorium fuel utilization are provided in Section 6. This includes information on fuel sources, fuel manufacturing, fuel reprocessing, and re-fabrication. The conclusions of the study are provided in Section 7.

  6. Th/U-233 Multi-recycle in Pressurized Water Reactors: Feasibility Study of Multiple Homogeneous and Heterogeneous Assembly Designs

    E-Print Network [OSTI]

    Kemner, Ken

    Th/U-233 Multi-recycle in Pressurized Water Reactors: Feasibility Study of Multiple Homogeneous in the LWR fuel cycle. The possibility for thorium utilization in a multi-recycle system has also been fuel multi-recycle in current LWRs, focusing on pressurized water reactors (PWRs). Approaches

  7. Th/U-233 multi-recycle in pressurized water reactors : feasibility study of multiple homogeneous and heterogeneous assembly designs.

    SciTech Connect (OSTI)

    Yun, D.; Taiwo, T. A.; Kim, T. K.; Mohamed, A.; Nuclear Engineering Division

    2010-10-01T23:59:59.000Z

    The use of thorium in current or advanced light water reactors (LWRs) has been of interest in recent years. These interests have been associated with the need to increase nuclear fuel resources and the perceived non-proliferation advantages of the utilization of thorium in the fuel cycle. Various options have been considered for the use of thorium in the LWR fuel cycle. The possibility for thorium utilization in a multi-recycle system has also been considered in past literature, primarily because of the potential for near breeders with Th/U-233 in the thermal energy range. The objective of this study is to evaluate the potential of Th/U-233 fuel multi-recycle in current LWRs, focusing on pressurized water reactors (PWRs). Approaches for sustainable multi-recycle without the need for external fissile material makeup have been investigated. The intent is to obtain a design that allows existing PWRs to be used with minimal modifications.

  8. DOE/EA-1651: Final Environmental Assessment for U-233 Material Downblending and Disposition Project at the Oak Ridge National Laboratory Oak Ridge, Tennessee (January 2010)

    Office of Environmental Management (EM)

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  9. Records Disposition

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    1988-09-13T23:59:59.000Z

    To assign responsibilities and authorities and to prescribe policies, procedures, standards, and guidelines for the orderly disposition of records of the Department of Energy (DOE) and its management and operating contractors. Cancels DOE O 1324.2 dated 5-28-80. Chg 1 dated 4-9-92. Canceled by DOE O 1324.2B dated 1-12-95.

  10. Records Disposition

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    1980-05-28T23:59:59.000Z

    To assign responsibilities and authorities and to prescribe policies, procedures, standards, and guidelines for the orderly disposition of records of the Department of Energy (DOE) and its operating and onsite service contractors. Cancels DOE O 1324.1 dated 7-10-78. Chg 1 dated 7-2-81. Chg 2 dated 11-9-82. Canceled by DOE O 1324.2A dated 9-13-88.

  11. Used Fuel Disposition Campaign Preliminary Quality Assurance...

    Energy Savers [EERE]

    Used Fuel Disposition Campaign Preliminary Quality Assurance Implementation Plan Used Fuel Disposition Campaign Preliminary Quality Assurance Implementation Plan The primary...

  12. EM Waste and Materials Disposition & Transportation | Department...

    Office of Environmental Management (EM)

    EM Waste and Materials Disposition & Transportation EM Waste and Materials Disposition & Transportation DOE's Radioactive Waste Management Priorities: Continue to manage waste...

  13. Used Fuel Disposition Campaign Disposal Research and Development...

    Broader source: Energy.gov (indexed) [DOE]

    & Publications Used Fuel Disposition Campaign Disposal Research and Development Roadmap Used Fuel Disposition Campaign International Activities Implementation Plan Review of...

  14. Medical Plans

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

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  15. Weapons Dismantlement and Disposition NNSS Capabilities

    SciTech Connect (OSTI)

    Pat Arnold

    2011-12-01T23:59:59.000Z

    The U.S. Department of Energy (DOE) has tasked the WDD working group to disposition the large inventory of legacy classified weapon components scattered across the complex.

  16. Personal Property Disposition - Community Reuse Organizations...

    Broader source: Energy.gov (indexed) [DOE]

    Owen (signed) Director, Office of Worker and Community Transition Department of Energy Washington, DC 20505 January 22, 2003 Disposition of Excess Personal Property...

  17. Processing and Disposition of Special Actinide Target Materials - 13138

    SciTech Connect (OSTI)

    Robinson, Sharon M.; Patton, Brad D. [Oak Ridge National Laboratory, P.O. Box 2008, Oak Ridge, TN 37831 (United States)] [Oak Ridge National Laboratory, P.O. Box 2008, Oak Ridge, TN 37831 (United States); Allender, Jeffrey S. [Savannah River National Laboratory (United States)] [Savannah River National Laboratory (United States)

    2013-07-01T23:59:59.000Z

    The Department of Energy (DOE) manages an inventory of materials that contains a range of long-lived radioactive isotopes that were produced from the 1960's through the 1980's by irradiating targets in high-flux reactors at the Savannah River Site (SRS) to produce special heavy isotopes for DOE programmatic use, scientific research, and industrial and medical applications. Among the products were californium-252, heavy curium (including Cm-246 through Cm-248), and plutonium-242 and -244. Many of the isotopes are still in demand today, and they can be recovered from the remaining targets previously irradiated at SRS or produced from the recovered isotopes. Should the existing target materials be discarded, the plutonium (Pu) and curium (Cm) isotopes cannot be replaced readily with existing production sources. Some of these targets are stored at SRS, while other target material is stored at Oak Ridge National Laboratory (ORNL) at several stages of processing. The materials cannot be stored in their present form indefinitely. Their long-term management involves processing items for beneficial use and/or for disposition, using storage and process facilities at SRS and ORNL. Evaluations are under way for disposition options for these materials, and demonstrations of improved flow sheets to process the materials are being conducted at ORNL and the Savannah River National Laboratory (SRNL). The disposition options and a management evaluation process have been developed. Processing demonstrations and evaluations for these unique materials are under way. (authors)

  18. Naval Petroleum Reserve No. 3 Disposition Decision Analysis and...

    Energy Savers [EERE]

    Naval Petroleum Reserve No. 3 Disposition Decision Analysis and Timeline Naval Petroleum Reserve No. 3 Disposition Decision Analysis and Timeline This Report to Congress provides a...

  19. Surplus Plutonium Disposition Final Environmental Impact Statement

    SciTech Connect (OSTI)

    N /A

    1999-11-19T23:59:59.000Z

    In December 1996, the U.S. Department of Energy (DOE) published the ''Storage and Disposition of Weapons-Usable Fissile Materials Final Programmatic Environmental Impact Statement (Storage and Disposition PEIS)'' (DOE 1996a). That PEIS analyzes the potential environmental consequences of alternative strategies for the long-term storage of weapons-usable plutonium and highly enriched uranium (HEU) and the disposition of weapons-usable plutonium that has been or may be declared surplus to national security needs. The Record of Decision (ROD) for the ''Storage and Disposition PEIS'', issued on January 14, 1997 (DOE 1997a), outlines DOE's decision to pursue an approach to plutonium disposition that would make surplus weapons-usable plutonium inaccessible and unattractive for weapons use. DOE's disposition strategy, consistent with the Preferred Alternative analyzed in the ''Storage and Disposition PEIS'', allows for both the immobilization of some (and potentially all) of the surplus plutonium and use of some of the surplus plutonium as mixed oxide (MOX) fuel in existing domestic, commercial reactors. The disposition of surplus plutonium would also involve disposal of both the immobilized plutonium and the MOX fuel (as spent nuclear fuel) in a potential geologic repository.

  20. Evaluation of Calcine Disposition Path Forward

    SciTech Connect (OSTI)

    Birrer, S.A.; Heiser, M.B.

    2003-02-26T23:59:59.000Z

    This document describes an evaluation of the baseline and two alternative disposition paths for the final disposition of the calcine wastes stored at the Idaho Nuclear Technology and Engineering Center at the Idaho National Engineering and Environmental Laboratory. The pathways are evaluated against a prescribed set of criteria and a recommendation is made for the path forward.

  1. Evaluation of Calcine Disposition - Path Forward

    SciTech Connect (OSTI)

    Steve Birrer

    2003-02-01T23:59:59.000Z

    This document describes an evaluation of the baseline and two alternative disposition paths for the final disposition of the calcine wastes stored at the Idaho Nuclear Technology and Engineering Center at the Idaho National Engineering and Environmental Laboratory. The pathways are evaluated against a prescribed set of criteria and a recommendation is made for the path forward.

  2. ESTIMATING IMPURITIES IN SURPLUS PLUTONIUM FOR DISPOSITION

    SciTech Connect (OSTI)

    Allender, J.; Moore, E.

    2013-07-17T23:59:59.000Z

    The United States holds at least 61.5 metric tons (MT) of plutonium that is permanently excess to use in nuclear weapons programs, including 47.2 MT of weapons-grade plutonium. Surplus inventories will be stored safely by the Department of Energy (DOE) and then transferred to facilities that will prepare the plutonium for permanent disposition. The Savannah River National Laboratory (SRNL) operates a Feed Characterization program for the Office of Fissile Materials Disposition of the National Nuclear Security Administration and the DOE Office of Environmental Management. Many of the items that require disposition are only partially characterized, and SRNL uses a variety of techniques to predict the isotopic and chemical properties that are important for processing through the Mixed Oxide Fuel Fabrication Facility and alternative disposition paths. Recent advances in laboratory tools, including Prompt Gamma Analysis and Peroxide Fusion treatment, provide data on the existing inventories that will enable disposition without additional, costly sampling and destructive analysis.

  3. EIS-0283: Surplus Plutonium Disposition Environmental Impact Statement

    Broader source: Energy.gov [DOE]

    This EIS analyzes the potential environmental impacts associated with alternatives for the disposition of surplus plutonium.

  4. Proliferation resistance criteria for fissile material disposition

    SciTech Connect (OSTI)

    Close, D.A.; Fearey, B.L.; Markin, J.T.; Rutherford, D.A. [Los Alamos National Lab., NM (United States); Duggan, R.A.; Jaeger, C.D.; Mangan, D.L.; Moya, R.W.; Moore, L.R. [Sandia National Labs., Albuquerque, NM (United States); Strait, R.S. [Lawrence Livermore National Lab., CA (United States)

    1995-04-01T23:59:59.000Z

    The 1994 National Academy of Sciences study {open_quotes}Management and Disposition of Excess Weapons Plutonium{close_quotes} defined options for reducing the national and international proliferation risks of materials declared excess to the nuclear weapons program. This report proposes criteria for assessing the proliferation resistance of these options. The criteria are general, encompassing all stages of the disposition process from storage through intermediate processing to final disposition including the facilities, processing technologies and materials, the level of safeguards for these materials, and the national/subnational threat to the materials.

  5. Disposition of intravenous radioactive acyclovir

    SciTech Connect (OSTI)

    de Miranda, P.; Good, S.S.; Laskin, O.L.; Krasny, H.C.; Connor, J.D.; Lietman, P.S.

    1981-11-01T23:59:59.000Z

    The kinetic and metabolic disposition of (8-14C)acyclovir (ACV) was investigated in five subjects with advanced malignancy. The drug was administered by 1-hr intravenous infusion at doses of 0.5 and 2.5 mg/kg. Plasma and blood radioactivity-time, and plasma concentration-time data were defined by a two-compartment open kinetic model. There was nearly equivalent distribution of radioactivity in blood and plasma. The overall mean plasma half-life and total body clearance +/- SD of ACV were 2.1 +/- 0.5 hr and 297 +/- 53 ml/min/1.73 m2. Binding of ACV to plasma proteins was 15.4 +/- 4.4%. Most of the radioactive dose excreted was recovered in the urine (71% to 99%) with less than 2% excretion in the feces and only trace amounts in the expired Co2. Analyses by reverse-phase high-performance liquid chromatography indicated that 9-(carboxymethoxymethyl)guanine was the only significant urinary metabolite of ACV, accounting for 8.5% to 14.1% of the dose. A minor metabolite (less than 0.2% of dose) had the retention time of 8-hydroxy-9-((2-hydroxyethoxy)methyl)guanine. Unchanged urinary ACV ranged from 62% to 91% of the dose. There was no indication of ACV cleavage to guanine. Renal clearance of ACV was approximately three times the corresponding creatinine clearances.

  6. NRC comprehensive records disposition schedule. Revision 3

    SciTech Connect (OSTI)

    NONE

    1998-02-01T23:59:59.000Z

    Title 44 US Code, ``Public Printing and Documents,`` regulations issued by the General Service Administration (GSA) in 41 CFR Chapter 101, Subchapter B, ``Management and Use of Information and Records,`` and regulations issued by the National Archives and Records Administration (NARA) in 36 CFR Chapter 12, Subchapter B, ``Records Management,`` require each agency to prepare and issue a comprehensive records disposition schedule that contains the NARA approved records disposition schedules for records unique to the agency and contains the NARA`s General Records Schedules for records common to several or all agencies. The approved records disposition schedules specify the appropriate duration of retention and the final disposition for records created or maintained by the NRC. NUREG-0910, Rev. 3, contains ``NRC`s Comprehensive Records Disposition Schedule,`` and the original authorized approved citation numbers issued by NARA. Rev. 3 incorporates NARA approved changes and additions to the NRC schedules that have been implemented since the last revision dated March, 1992, reflects recent organizational changes implemented at the NRC, and includes the latest version of NARA`s General Records Schedule (dated August 1995).

  7. Excess plutonium disposition: The deep borehole option

    SciTech Connect (OSTI)

    Ferguson, K.L.

    1994-08-09T23:59:59.000Z

    This report reviews the current status of technologies required for the disposition of plutonium in Very Deep Holes (VDH). It is in response to a recent National Academy of Sciences (NAS) report which addressed the management of excess weapons plutonium and recommended three approaches to the ultimate disposition of excess plutonium: (1) fabrication and use as a fuel in existing or modified reactors in a once-through cycle, (2) vitrification with high-level radioactive waste for repository disposition, (3) burial in deep boreholes. As indicated in the NAS report, substantial effort would be required to address the broad range of issues related to deep bore-hole emplacement. Subjects reviewed in this report include geology and hydrology, design and engineering, safety and licensing, policy decisions that can impact the viability of the concept, and applicable international programs. Key technical areas that would require attention should decisions be made to further develop the borehole emplacement option are identified.

  8. Mission Need Statement: Calcine Disposition Project Major Systems Acquisition Project

    SciTech Connect (OSTI)

    J. T. Beck

    2007-04-26T23:59:59.000Z

    This document identifies the need to establish the Calcine Disposition Project to determine and implement the final disposition of calcine including characterization, retrieval, treatment (if necessary), packaging, loading, onsite interim storage pending shipment to a repository or interim storage facility, and disposition of related facilities.

  9. Characterizing Surplus US Plutonium for Disposition - 13199

    SciTech Connect (OSTI)

    Allender, Jeffrey S. [Savannah River National Laboratory, Aiken SC 29808 (United States)] [Savannah River National Laboratory, Aiken SC 29808 (United States); Moore, Edwin N. [Moore Nuclear Energy, LLC, Savannah River Site, Aiken SC 29808 (United States)] [Moore Nuclear Energy, LLC, Savannah River Site, Aiken SC 29808 (United States)

    2013-07-01T23:59:59.000Z

    The United States (US) has identified 61.5 metric tons (MT) of plutonium that is permanently excess to use in nuclear weapons programs, including 47.2 MT of weapons-grade plutonium. Surplus inventories will be stored safely by the Department of Energy (DOE) and then transferred to facilities that will prepare the plutonium for permanent disposition. The Savannah River National Laboratory (SRNL) operates a Feed Characterization program for the Office of Fissile Materials Disposition (OFMD) of the National Nuclear Security Administration (NNSA) and the DOE Office of Environmental Management (DOE-EM). SRNL manages a broad program of item tracking through process history, laboratory analysis, and non-destructive assay. A combination of analytical techniques allows SRNL to predict the isotopic and chemical properties that qualify materials for disposition through the Mixed Oxide (MOX) Fuel Fabrication Facility (MFFF). The research also defines properties that are important for other disposition paths, including disposal to the Waste Isolation Pilot Plant (WIPP) as transuranic waste (TRUW) or to high-level waste (HLW) systems. (authors)

  10. Characterizing surplus US plutonium for disposition

    SciTech Connect (OSTI)

    Allender, Jeffrey S.; Moore, Edwin N.

    2013-02-26T23:59:59.000Z

    The United States (US) has identified 61.5 metric tons (MT) of plutonium that is permanently excess to use in nuclear weapons programs, including 47.2 MT of weapons-grade plutonium. Surplus inventories will be stored safely by the Department of Energy (DOE) and then transferred to facilities that will prepare the plutonium for permanent disposition. The Savannah River National Laboratory (SRNL) operates a Feed Characterization program for the Office of Fissile Materials Disposition (OFMD) of the National Nuclear Security Administration (NNSA) and the DOE Office of Environmental Management (DOE-EM). SRNL manages a broad program of item tracking through process history, laboratory analysis, and non-destructive assay. A combination of analytical techniques allows SRNL to predict the isotopic and chemical properties that qualify materials for disposition through the Mixed Oxide (MOX) Fuel Fabrication Facility (MFFF). The research also defines properties that are important for other disposition paths, including disposal to the Waste Isolation Pilot Plant (WIPP) as transuranic waste (TRUW) or to high-level waste (HLW) systems.

  11. Disposition of surplus fissile materials via immobilization

    SciTech Connect (OSTI)

    Gray, L.W.; Kan, T.; Sutcliffe, W.G. [Lawrence Livermore National Lab., CA (United States); McKibben, J.M. [Westinghouse Savannah River Co., Aiken, SC (United States); Danker, W. [USDOE, Washington, DC (United States)

    1995-07-23T23:59:59.000Z

    In the Cold War aftermath, the US and Russia have agreed to large reductions in nuclear weapons. To aid in the selection of long-term management options, the USDOE has undertaken a multifaceted study to select options for storage and disposition of surplus plutonium (Pu). One disposition alternative being considered is immobilization. Immobilization is a process in which surplus Pu would be embedded in a suitable material to produce an appropriate form for ultimate disposal. To arrive at an appropriate form, we first reviewed published information on HLW immobilization technologies to identify forms to be prescreened. Surviving forms were screened using multi-attribute utility analysis to determine promising technologies for Pu immobilization. We further evaluated the most promising immobilization families to identify and seek solutions for chemical, chemical engineering, environmental, safety, and health problems; these problems remain to be solved before we can make technical decisions about the viability of using the forms for long-term disposition of Pu. All data, analyses, and reports are being provided to the DOE Office of Fissile Materials Disposition to support the Record of Decision that is anticipated in Summer of 1996.

  12. Surplus Plutonium Disposition (SPD) Environmental Data Summary

    SciTech Connect (OSTI)

    Fledderman, P.D.

    2000-08-24T23:59:59.000Z

    This document provides an overview of existing environmental and ecological information at areas identified as potential locations of the Savannah River Site's (SRS) Surplus Plutonium Disposition (SPD) facilities. This information is required to document existing environmental and baseline conditions from which SPD construction and operation impacts can be defined. It will be used in developing the required preoperational monitoring plan to be used at specific SPD facilities construction sites.

  13. The ultimate disposition of depleted uranium

    SciTech Connect (OSTI)

    Lemons, T.R. [Uranium Enrichment Organization, Oak Ridge, TN (United States)

    1991-12-31T23:59:59.000Z

    Depleted uranium (DU) is produced as a by-product of the uranium enrichment process. Over 340,000 MTU of DU in the form of UF{sub 6} have been accumulated at the US government gaseous diffusion plants and the stockpile continues to grow. An overview of issues and objectives associated with the inventory management and the ultimate disposition of this material is presented.

  14. Nuclear Materials Disposition | Department of Energy

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level:Energy: Grid Integration Redefining What's Possible for Renewable Energy:Nanowire3627 Federal Register /7 ThisNuclear Materials Disposition

  15. Portsmouth Proposed Plan for the Site-wide Waste Disposition...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Proposed Plan for the Site-wide Waste Disposition Evaluation Project DOE has evaluated alternatives for managing waste that would be created by decomtamination and...

  16. Additional public meeting on plutonium disposition on September...

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    produce an oxide form of plutonium suitable for disposition and the use of mixed oxide (MOX) fuel fabricated from surplus plutonium in domestic commercial nuclear power reactors...

  17. DRAFT EM SSAB Chairs Meeting Waste Disposition Strategies...

    Office of Environmental Management (EM)

    EM HQ Updates Waste Disposition Overview Christine Gelles Associate Deputy Assistant Secretary for Waste Management Office of Environmental Management EM SSAB Chairs Meeting 5...

  18. Process Guide for the Identification and Disposition of S/CI...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Process Guide for the Identification and Disposition of SCI or Defective Items at Department of Energy Facilities Process Guide for the Identification and Disposition of SCI or...

  19. Plutonium Disposition Program | National Nuclear Security Administration

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

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  20. Material Disposition | National Nuclear Security Administration

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645U.S. DOE Office of Science (SC)Integrated Codes |IsLove Your Home andDisposition | National Nuclear Security

  1. Weapons-grade plutonium dispositioning. Volume 2: Comparison of plutonium disposition options

    SciTech Connect (OSTI)

    Brownson, D.A.; Hanson, D.J.; Blackman, H.S. [and others

    1993-06-01T23:59:59.000Z

    The Secretary of Energy requested the National Academy of Sciences (NAS) Committee on International Security and Arms Control to evaluate disposition options for weapons-grade plutonium. The Idaho National Engineering Laboratory (INEL) offered to assist the NAS in this evaluation by investigating the technical aspects of the disposition options and their capability for achieving plutonium annihilation levels greater than 90%. This report was prepared for the NAS to document the gathered information and results from the requested option evaluations. Evaluations were performed for 12 plutonium disposition options involving five reactor and one accelerator-based systems. Each option was evaluated in four technical areas: (1) fuel status, (2) reactor or accelerator-based system status, (3) waste-processing status, and (4) waste disposal status. Based on these evaluations, each concept was rated on its operational capability and time to deployment. A third rating category of option costs could not be performed because of the unavailability of adequate information from the concept sponsors. The four options achieving the highest rating, in alphabetical order, are the Advanced Light Water Reactor with plutonium-based ternary fuel, the Advanced Liquid Metal Reactor with plutonium-based fuel, the Advanced Liquid Metal Reactor with uranium-plutonium-based fuel, and the Modular High Temperature Gas-Cooled Reactor with plutonium-based fuel. Of these four options, the Advanced Light Water Reactor and the Modular High Temperature Gas-Cooled Reactor do not propose reprocessing of their irradiated fuel. Time constraints and lack of detailed information did not allow for any further ratings among these four options. The INEL recommends these four options be investigated further to determine the optimum reactor design for plutonium disposition.

  2. Proliferation resistance criteria for fissile material disposition issues

    SciTech Connect (OSTI)

    Rutherford, D.A.; Fearey, B.L.; Markin, J.T.; Close, D.A. [Los Alamos National Lab., NM (United States); Tolk, K.M.; Mangan, D.L. [Sandia National Labs., Albuquerque, NM (United States); Moore, L. [Lawrence Livermore National Lab., CA (United States)

    1995-09-01T23:59:59.000Z

    The 1994 National Acdaemy of Sciences study ``Management and Disposition of Excess Weapons Plutonium`` defined options for reducing the national and international proliferation risks of materials declared excess to the nuclear weapons program. This paper proposes criteria for assessing the proliferation resistance of these options as well defining the ``Standards`` from the report. The criteria are general, encompassing all stages of the disposition process from storage through intermediate processing to final disposition including the facilities, processing technologies and materials, the level of safeguards for these materials, and the national/subnational threat to the materials.

  3. The ultimate disposition of depleted uranium

    SciTech Connect (OSTI)

    Not Available

    1990-12-01T23:59:59.000Z

    Significant amounts of the depleted uranium (DU) created by past uranium enrichment activities have been sold, disposed of commercially, or utilized by defense programs. In recent years, however, the demand for DU has become quite small compared to quantities available, and within the US Department of Energy (DOE) there is concern for any risks and/or cost liabilities that might be associated with the ever-growing inventory of this material. As a result, Martin Marietta Energy Systems, Inc. (Energy Systems), was asked to review options and to develop a comprehensive plan for inventory management and the ultimate disposition of DU accumulated at the gaseous diffusion plants (GDPs). An Energy Systems task team, under the chairmanship of T. R. Lemons, was formed in late 1989 to provide advice and guidance for this task. This report reviews options and recommends actions and objectives in the management of working inventories of partially depleted feed (PDF) materials and for the ultimate disposition of fully depleted uranium (FDU). Actions that should be considered are as follows. (1) Inspect UF{sub 6} cylinders on a semiannual basis. (2) Upgrade cylinder maintenance and storage yards. (3) Convert FDU to U{sub 3}O{sub 8} for long-term storage or disposal. This will include provisions for partial recovery of costs to offset those associated with DU inventory management and the ultimate disposal of FDU. Another recommendation is to drop the term tails'' in favor of depleted uranium'' or DU'' because the tails'' label implies that it is waste.'' 13 refs.

  4. Americium/Curium Disposition Life Cycle Planning Study

    SciTech Connect (OSTI)

    Jackson, W.N. [Westinghouse Savannah River Company, AIKEN, SC (United States); Krupa, J.; Stutts, P.; Nester, S.; Raimesch, R.

    1998-04-30T23:59:59.000Z

    At the request of the Department of Energy Savannah River Office (DOE- SR), Westinghouse Savannah River Company (WSRC) evaluated concepts to complete disposition of Americium and Curium (Am/Cm) bearing materials currently located at the Savannah River Site (SRS).

  5. Legacy sample disposition project. Volume 2: Final report

    SciTech Connect (OSTI)

    Gurley, R.N.; Shifty, K.L.

    1998-02-01T23:59:59.000Z

    This report describes the legacy sample disposition project at the Idaho Engineering and Environmental Laboratory (INEEL), which assessed Site-wide facilities/areas to locate legacy samples and owner organizations and then characterized and dispositioned these samples. This project resulted from an Idaho Department of Environmental Quality inspection of selected areas of the INEEL in January 1996, which identified some samples at the Test Reactor Area and Idaho Chemical Processing Plant that had not been characterized and dispositioned according to Resource Conservation and Recovery Act (RCRA) requirements. The objective of the project was to manage legacy samples in accordance with all applicable environmental and safety requirements. A systems engineering approach was used throughout the project, which included collecting the legacy sample information and developing a system for amending and retrieving the information. All legacy samples were dispositioned by the end of 1997. Closure of the legacy sample issue was achieved through these actions.

  6. EIS-0327: Disposition of Scrap Metals Programmatic EIS

    Broader source: Energy.gov [DOE]

    This EIS will evaluate the environmental impacts of policy alternatives for the disposition of scrap metals (primarily carbon steel and stainless steel) that may have residual surface radioactivity. DOE is cancelling this EIS.

  7. A Study of Cattle Disposition: Exploring QTL Associated with Temperament

    E-Print Network [OSTI]

    Boldt, Clayton Ryan

    2008-05-16T23:59:59.000Z

    In any production setting, cattle disposition (temperament) has a great impact on handling and performance. Thus, behavior can be economically important, yielding the rationale for study. Wegenhoft (2005) previously identified several quantitative...

  8. Highly enriched uranium (HEU) storage and disposition program plan

    SciTech Connect (OSTI)

    Arms, W.M.; Everitt, D.A.; O`Dell, C.L.

    1995-01-01T23:59:59.000Z

    Recent changes in international relations and other changes in national priorities have profoundly affected the management of weapons-usable fissile materials within the United States (US). The nuclear weapon stockpile reductions agreed to by the US and Russia have reduced the national security requirements for these fissile materials. National policies outlined by the US President seek to prevent the accumulation of nuclear weapon stockpiles of plutonium (Pu) and HEU, and to ensure that these materials are subjected to the highest standards of safety, security and international accountability. The purpose of the Highly Enriched Uranium (HEU) Storage and Disposition Program Plan is to define and establish a planned approach for storage of all HEU and disposition of surplus HEU in support of the US Department of Energy (DOE) Fissile Material Disposition Program. Elements Of this Plan, which are specific to HEU storage and disposition, include program requirements, roles and responsibilities, program activities (action plans), milestone schedules, and deliverables.

  9. SELECTION OF SURPLUS PLUTONIUM MATERIALS FOR DISPOSITION TO WIPP

    SciTech Connect (OSTI)

    Allender, J.; Mcclard, J.; Christopher, J.

    2012-06-08T23:59:59.000Z

    The U.S. Department of Energy (DOE) is preparing a Surplus Plutonium Disposition (SPD) Supplemental Environmental Impact Statement (SEIS). Included in the evaluation are up to 6 metric tons (MT) of plutonium in the form of impure oxides and metals for which a disposition plan has not been decided, among options that include preparation as feed for the Mixed Oxide Fuel Fabrication Facility; disposing to high-level waste through the Savannah River Site (SRS) HB Line and H Canyon; can-in-canister disposal using the SRS Defense Waste Processing Facility; and preparation for disposal at the Waste Isolation Pilot Plant (WIPP). DOE and SRS have identified at least 0.5 MT of plutonium that, because of high levels of chemical and isotopic impurities, is impractical for disposition by methods other than the WIPP pathway. Characteristics of these items and the disposition strategy are discussed.

  10. TRACKING SURPLUS PLUTONIUM FROM WEAPONS TO DISPOSITION

    SciTech Connect (OSTI)

    Allender, J.; Beams, J.; Sanders, K.; Myers, L.

    2013-07-16T23:59:59.000Z

    Supporting nuclear nonproliferation and global security principles, beginning in 1994 the United States has withdrawn more than 50 metric tons (MT) of government-controlled plutonium from potential use in nuclear weapons. The Department of Energy (DOE), including the National Nuclear Security Administration, established protocols for the tracking of this "excess" and "surplus" plutonium, and for reconciling the current storage and utilization of the plutonium to show that its management is consistent with the withdrawal policies. Programs are underway to ensure the safe and secure disposition of the materials that formed a major part of the weapons stockpile during the Cold War, and growing quantities have been disposed as waste, after which they are not included in traditional nuclear material control and accountability (NMC&A) data systems. A combination of resources is used to perform the reconciliations that form the basis for annual reporting to DOE, to U.S. Department of State, and to international partners including the International Atomic Energy Agency.

  11. SLIGHTLY IRRADIATED FUEL (SIF) INTERIM DISPOSITION PROJECT

    SciTech Connect (OSTI)

    NORTON SH

    2010-02-23T23:59:59.000Z

    CH2M HILL Plateau Remediation Company (CH2M HILL PRC) is proud to submit the Slightly Irradiated Fuel (SIF) Interim Disposition Project for consideration by the Project Management Institute as Project of the Year for 2010. The SIF Project was a set of six interrelated sub-projects that delivered unique stand-alone outcomes, which, when integrated, provided a comprehensive and compliant system for storing high risk special nuclear materials. The scope of the six sub-projects included the design, construction, testing, and turnover of the facilities and equipment, which would provide safe, secure, and compliant Special Nuclear Material (SNM) storage capabilities for the SIF material. The project encompassed a broad range of activities, including the following: Five buildings/structures removed, relocated, or built; Two buildings renovated; Structural barriers, fencing, and heavy gates installed; New roadways and parking lots built; Multiple detection and assessment systems installed; New and expanded communication systems developed; Multimedia recording devices added; and A new control room to monitor all materials and systems built. Project challenges were numerous and included the following: An aggressive 17-month schedule to support the high-profile Plutonium Finishing Plant (PFP) decommissioning; Company/contractor changeovers that affected each and every project team member; Project requirements that continually evolved during design and construction due to the performance- and outcome-based nature ofthe security objectives; and Restrictions imposed on all communications due to the sensitive nature of the projects In spite of the significant challenges, the project was delivered on schedule and $2 million under budget, which became a special source of pride that bonded the team. For years, the SIF had been stored at the central Hanford PFP. Because of the weapons-grade piutonium produced and stored there, the PFP had some of the tightest security on the Hanford nuclear reservation. Workers had to pass through metal detectors when they arrived at the plant and materials leaving the plant had to be scanned for security reasons. Whereas other high-security nuclear materials were shipped from the PFP to Savannah River, S.C. as part ofa Department of Energy (DOE) program to consolidate weapons-grade plutonium, it was determined that the SIF should remain onsite pending disposition to a national repository. Nevertheless, the SIF still requires a high level of security that the PFP complex has always provided. With the 60-year PFP mission of producing and storing plutonium concluded, the environmental cleanup plans for Hanford call for the demolition of the 63-building PFP complex. Consequently, if the SIF remained at PFP it not only would have interfered with the environmental cleanup plans, but would have required $100 million in facility upgrades to meet increased national security requirements imposed after the 9/11 terrorist attacks. A new smaller and more cost-effective area was needed to store this material, which led to the SIF Project. Once the SIF project was successfully completed and the SIF was safely removed from PFP, the existing Protected Area at PFP could be removed, and demolition could proceed more quickly without being encumbered by restrictive security requirements that an active Protected Area requires. The lightened PFP security level brought by safely removing and storing the SIF would also yield lowered costs for deactivation and demolition, as well as reduce overall life-cycle costs.

  12. FUEL CYCLE POTENTIAL WASTE FOR DISPOSITION

    SciTech Connect (OSTI)

    Carter, J.

    2011-01-03T23:59:59.000Z

    The United States (U.S.) currently utilizes a once-through fuel cycle where used nuclear fuel (UNF) is stored on-site in either wet pools or in dry storage systems with ultimate disposal in a deep mined geologic repository envisioned. Within the Department of Energy's (DOE) Office of Nuclear Energy (DOE-NE), the Fuel Cycle Research and Development Program (FCR&D) develops options to the current commercial fuel cycle management strategy to enable the safe, secure, economic, and sustainable expansion of nuclear energy while minimizing proliferation risks by conducting research and development of advanced fuel cycles, including modified open and closed cycles. The safe management and disposition of used nuclear fuel and/or nuclear waste is a fundamental aspect of any nuclear fuel cycle. Yet, the routine disposal of used nuclear fuel and radioactive waste remains problematic. Advanced fuel cycles will generate different quantities and forms of waste than the current LWR fleet. This study analyzes the quantities and characteristics of potential waste forms including differing waste matrices, as a function of a variety of potential fuel cycle alternatives including: (1) Commercial UNF generated by uranium fuel light water reactors (LWR). Four once through fuel cycles analyzed in this study differ by varying the assumed expansion/contraction of nuclear power in the U.S. (2) Four alternative LWR used fuel recycling processes analyzed differ in the reprocessing method (aqueous vs. electro-chemical), complexity (Pu only or full transuranic (TRU) recovery) and waste forms generated. (3) Used Mixed Oxide (MOX) fuel derived from the recovered Pu utilizing a single reactor pass. (4) Potential waste forms generated by the reprocessing of fuels derived from recovered TRU utilizing multiple reactor passes.

  13. FUEL CYCLE POTENTIAL WASTE FOR DISPOSITION

    SciTech Connect (OSTI)

    Jones, R.; Carter, J.

    2010-10-13T23:59:59.000Z

    The United States (U.S.) currently utilizes a once-through fuel cycle where used nuclear fuel (UNF) is stored on-site in either wet pools or in dry storage systems with ultimate disposal in a deep mined geologic repository envisioned. Within the Department of Energy's (DOE) Office of Nuclear Energy (DOE-NE), the Fuel Cycle Research and Development Program (FCR&D) develops options to the current commercial fuel cycle management strategy to enable the safe, secure, economic, and sustainable expansion of nuclear energy while minimizing proliferation risks by conducting research and development of advanced fuel cycles, including modified open and closed cycles. The safe management and disposition of used nuclear fuel and/or nuclear waste is a fundamental aspect of any nuclear fuel cycle. Yet, the routine disposal of used nuclear fuel and radioactive waste remains problematic. Advanced fuel cycles will generate different quantities and forms of waste than the current LWR fleet. This study analyzes the quantities and characteristics of potential waste forms including differing waste matrices, as a function of a variety of potential fuel cycle alternatives including: (1) Commercial UNF generated by uranium fuel light water reactors (LWR). Four once through fuel cycles analyzed in this study differ by varying the assumed expansion/contraction of nuclear power in the U.S; (2) Four alternative LWR used fuel recycling processes analyzed differ in the reprocessing method (aqueous vs. electro-chemical), complexity (Pu only or full transuranic (TRU) recovery) and waste forms generated; (3) Used Mixed Oxide (MOX) fuel derived from the recovered Pu utilizing a single reactor pass; and (4) Potential waste forms generated by the reprocessing of fuels derived from recovered TRU utilizing multiple reactor passes.

  14. Fissile material disposition program final immobilization form assessment and recommendation

    SciTech Connect (OSTI)

    Cochran, S.G.; Dunlop, W.H.; Edmunds, T.A.; MacLean, L.M.; Gould, T.H. [Westinghouse Savannah River Co., Aiken, SC (United States)

    1997-10-03T23:59:59.000Z

    Lawrence Livermore National Laboratory (LLNL), in its role as the lead laboratory for the development of plutonium immobilization technologies for the Department of Energy`s Office of Fissile Materials Disposition (MD), has been requested by MD to recommend an immobilization technology for the disposition of surplus weapons- usable plutonium. The recommendation and supporting documentation was requested to be provided by September 1, 1997. This report addresses the choice between glass and ceramic technologies for immobilizing plutonium using the can-in-canister approach. Its purpose is to provide a comparative evaluation of the two candidate technologies and to recommend a form based on technical considerations.

  15. California Institute of Technology Records Retention and Disposition Policy

    E-Print Network [OSTI]

    of the Records Retention and Disposition Policy is to establish and maintain a uniform records management policy activities and are subject to records management review and evaluation prior to any decisions regarding of Technology Records Retention Schedule ("Retention Schedule"). Department and division management should

  16. SNM measurement uncertainites: potential impacts for materials disposition

    SciTech Connect (OSTI)

    Fearey, B.L.; Burr, T.L.; Pickrell, M.M.

    1996-09-01T23:59:59.000Z

    A discussion of nuclear material measurement uncertainties and impacts to the Materials Disposition (MD) Program is presented. Many of the options under consideration by the disposition program present new measurement challenges include significant material processing throughputs, a variety of material forms, unique waste streams, and difficult-to-measure matrices. There are also some questions regarding the ability to achieve International Atomic Energy Agency (IAEA) verification requirements and to achieve measurement uncertainties that are small enough to meet the IAEA loss detection goals. We present a detailed formalism for determining the measurement error for nondestructive assay systems applied to the MD Program, which is an essential component for planning the safeguards and security of these systems.

  17. Plutonium disposition via immobilization in ceramic or glass

    SciTech Connect (OSTI)

    Gray, L.W.; Kan, T.; Shaw, H.F.; Armantrout, A.

    1997-03-05T23:59:59.000Z

    The management of surplus weapons plutonium is an important and urgent task with profound environmental, national, and international security implications. In the aftermath of the Cold War, Presidential Policy Directive 13, and various analyses by renown scientific, technical, and international policy organizations have brought about a focused effort within the Department of Energy to identify and implement paths for the long term disposition of surplus weapons- usable plutonium. The central goal of this effort is to render surplus weapons plutonium as inaccessible and unattractive for reuse in nuclear weapons as the much larger and growing stock of plutonium contained in spent fuel from civilian reactors. One disposition option being considered for surplus plutonium is immobilization, in which the plutonium would be incorporated into a glass or ceramic material that would ultimately be entombed permanently in a geologic repository for high-level waste.

  18. Joint U.S./Russian plutonium disposition study: Nonproliferation issues

    SciTech Connect (OSTI)

    Jaeger, C. [Sandia National Labs., Albuquerque, NM (United States); Erkkila, B.; Fearey, B. [Los Alamos National Lab., NM (United States); Ehinger, M. [Oak Ridge National Lab., TN (United States); McAllister, S. [Lawrence Livermore National Lab., CA (United States); Chitaykin, V. [Inst. of Physics and Power Engineering, Obninsk (Russian Federation); Ptashny, V. [Inst. of Technical Physics, Snezhinsk (Russian Federation)

    1996-07-01T23:59:59.000Z

    In an effort to establish joint activities in the disposition of fissile materials from nuclear materials, the US and Russia agreed to conduct joint work to develop consistent comparisons of various alternatives for the disposition of weapons-grade plutonium. Joint working groups were established for the analysis of alternatives for plutonium management for water reactors, fast reactors, storage, geological formations, immobilization and stabilization of solutions and other forms. In addition cross-cutting working groups were established for economic analysis and nonproliferation (NP). This paper reviews the activities of the NP working group in support of these studies. The NP working group provided integrated support in the area of nuclear NP to the other US/Russian Study teams. It involved both domestic safeguards and security and international safeguards. The analysis of NP involved consideration of the resistance to theft or diversion and resistance to retrieval, extraction or reuse.

  19. Update of the Used Fuel Disposition Campaign Implementation Plan

    SciTech Connect (OSTI)

    Jens Birkholzer; Robert MacKinnon; Kevin McMahon; Sylvia Saltzstein; Ken Sorenson; Peter Swift

    2014-09-01T23:59:59.000Z

    This Campaign Implementation Plan provides summary level detail describing how the Used Fuel Disposition Campaign (UFDC) supports achievement of the overarching mission and objectives of the Department of Energy Office of Nuclear Energy Fuel Cycle Technologies Program The implementation plan begins with the assumption of target dates that are set out in the January 2013 DOE Strategy for the Management and Disposal of Used Nuclear Fuel and High-Level Radioactive Waste (http://energy.gov/downloads/strategy-management-and-disposal-used-nuclear-fuel-and-high-level-radioactive-waste). These target dates and goals are summarized in section III. This implementation plan will be maintained as a living document and will be updated as needed in response to progress in the Used Fuel Disposition Campaign and the Fuel Cycle Technologies Program.

  20. MPC&A for plutonium disposition in the Russian federation

    SciTech Connect (OSTI)

    Sutcliffe, W.G.

    1995-08-08T23:59:59.000Z

    The issue of what to do with excess fissile materials from dismantled nuclear weapons has been discussed for a number of years. The options or alternatives commanding the most attention were identified by the American National Academy of Sciences. For plutonium these options are: (1) the fabrication and use of mixed-oxide (MOX) reactor fuel followed by the disposal of the spent fuel, or (2) vitrification (immobilization) of plutonium combined with highly radioactive material followed by direct disposal. The Academy report also identified the alternative of disposal in a deep borehole as requiring further study before being eliminated or accepted. The report emphasized security of nuclear materials as a principal factor in considering management and disposition decisions. Security of materials is particularly important in the near term-now-long before ultimate disposition can be accomplished. The MOX option was the subject of a NATO workshop held at Obninsk, Russia in October 1994. Hence this paper does not deal with the MOX alternative in detail. It deals with the following: materials protection, control, and accounting (MPC&A) for immobilization and disposal; the immobilization vs MOX alternatives; the security of disposed plutonium; the need to demonstrate MTC&A for plutonium disposition; and, finally, a recommended investment to quickly and inexpensively improve the protection of fissile materials in Russia. It is the author`s view that near-term management is of overriding importance. That is, with respect to the ultimate disposition of excess nuclear materials, how we get there is more important than where we are going.

  1. Preliminary siting characterization Salt Disposition Facility - Site B

    SciTech Connect (OSTI)

    Wyatt, D.

    2000-01-04T23:59:59.000Z

    A siting and reconnaissance geotechnical program has been completed in S-Area at the Savannah River Site in South Carolina. This program investigated the subsurface conditions for the area known as ``Salt Disposition Facility (SDF), Site B'' located northeast of H-Area and within the S-Area. Data acquired from the Site B investigation includes both field exploration and laboratory test data.

  2. Radium Disposition Options for the Department of Energy

    SciTech Connect (OSTI)

    Parks, D. L.; Thiel, E. C.; Seidel, B. R.

    2002-02-26T23:59:59.000Z

    The Department of Energy (DOE) has developed plans to disposition its excess nuclear materials, including radium-containing materials. Within DOE, there is no significant demand for radium at this time. However, DOE is exploring reuse options, including uses that may not exist at this time. The Nonactinide Isotopes and Sealed Sources Management Group (NISSMG) has identified 654 radium-containing items, and concluded that there are no remaining radium items that do not have a pathway to disposition. Unfortunately, most of these pathways end with disposal, whereas reuse would be preferable. DOE has a number of closure sites that must remove the radium at their sites as part of their closure activities. NISSMG suggests preserving the larger radium sources that can easily be manufactured into targets for future reuse, and disposing the other items. As alternatives to disposal, there exist reuse options for radium, especially in nuclear medicine. These options were identified by NISSMG. The NISSMG recommends that DOE set up receiver sites to store these radium materials until reuse options become available. The NISSMG recommends two pathways for dispositioning radium sources, depending on the activity and volume of material. Low activity radium sources can be managed as low level radioactive waste per DOE Order 5820.2A. Higher activity radium sources are more appropriate for reuse in nuclear medicine applications and other applications.

  3. Safeguards and security issues for the disposition of fissile materials

    SciTech Connect (OSTI)

    Jaeger, C.D.; Moya, R.W.; Duggan, R.A.; Mangan, D.L.; Tolk, K.M. [Sandia National Labs., Albuquerque, NM (United States); Rutherford, D.; Fearey, B. [Los Alamos National Lab., NM (United States); Moore, L. [Lawrence Livermore National Lab., CA (United States)

    1995-07-01T23:59:59.000Z

    The Department of Energy`s Office of Fissile Material Disposition (FMD) is analyzing long-term storage and disposition options for surplus weapons-usable fissile materials, preparing a programmatic environmental impact statement (PEIS), preparing for a record of decision (ROD) regarding this material and conducting other activities. The primary security objectives of this program are to reduce major security risks and strengthen arms reduction and nonproliferation (NP). To help achieve these objectives, a safeguards and security (S&S) team consisting of participants from Sandia, Los Alamos, and Lawrence Livermore National Laboratories was established. The S&S activity for this program is a cross-cutting task which addresses all of the FMD program options. It includes both domestic and international safeguards and includes areas such as physical protection, nuclear materials accountability and material containment and surveillance. This paper will discuss the activities of the Fissile Materials Disposition Program (FMDP) S&S team as well as some specific S&S issues associated with various FMDP options/facilities. Some of the items to be discussed include the threat, S&S requirements, S&S criteria for assessing risk, S&S issues concerning fissile material processing/facilities, and international and domestic safeguards.

  4. Disposition of actinides released from high-level waste glass

    SciTech Connect (OSTI)

    Ebert, W.L.; Bates, J.K.; Buck, E.C.; Gong, M.; Wolf, S.F.

    1994-05-01T23:59:59.000Z

    A series of static leach tests was conducted using glasses developed for vitrifying tank wastes at the Savannah River Site to monitor the disposition of actinide elements upon corrosion of the glasses. In these tests, glasses produced from SRL 131 and SRL 202 frits were corroded at 90{degrees}C in a tuff groundwater. Tests were conducted using crushed glass at different glass surface area-to-solution volume (S/V) ratios to assess the effect of the S/V on the solution chemistry, the corrosion of the glass, and the disposition of actinide elements. Observations regarding the effects of the S/V on the solution chemistry and the corrosion of the glass matrix have been reported previously. This paper highlights the solution analyses performed to assess how the S/V used in a static leach test affects the disposition of actinide elements between fractions that are suspended or dissolved in the solution, and retained by the altered glass or other materials.

  5. Medical Plans for Medicare-Eligible Retirees

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645U.S. DOE Office of Science (SC)Integrated Codes |IsLove Your Home andDispositionMechanical R&DMakingMedical

  6. Update to the Fissile Materials Disposition program SST/SGT transportation estimation

    SciTech Connect (OSTI)

    John Didlake

    1999-11-15T23:59:59.000Z

    This report is an update to ``Fissile Materials Disposition Program SST/SGT Transportation Estimation,'' SAND98-8244, June 1998. The Department of Energy Office of Fissile Materials Disposition requested this update as a basis for providing the public with an updated estimation of the number of transportation loads, load miles, and costs associated with the preferred alternative in the Surplus Plutonium Disposition Final Environmental Impact Statement (EIS).

  7. Site selection for the Salt Disposition Facility at the Savannah River Site

    SciTech Connect (OSTI)

    Bowers, J.A.

    2000-01-03T23:59:59.000Z

    The purpose of this report is to identify, assess, and rank potential sites for the proposed Salt Disposition Facility (SDF) at the Savannah River Site.

  8. Microsoft Word - CX-MountainAvenueDispositionFY12_WEB.doc

    Broader source: Energy.gov (indexed) [DOE]

    1, 2012 REPLY TO ATTN OF: KEPR-4 SUBJECT: Environmental Clearance Memorandum Joan Kendall Realty Specialist - TERR-3 Proposed Action: Disposition of Mountain Avenue Substation and...

  9. EIS-0229: Storage and Disposition of Weapons-Usable Fissile Materials

    Broader source: Energy.gov [DOE]

    The EIS will evaluate the reasonable alternatives and potential environmental impacts for the proposed siting, construction, and operation of three types of facilities for plutonium disposition.

  10. Site Selection for Surplus Plutonium Disposition Facilities at the Savannah River Site

    SciTech Connect (OSTI)

    Wike, L.D.

    2000-12-13T23:59:59.000Z

    The purpose of this study is to identify, assess, and rank potential sites for the proposed Surplus Plutonium Disposition Facilities complex at the Savannah River Site.

  11. SPIE Medical Imaging Medical Imaging

    E-Print Network [OSTI]

    Miga, Michael I.

    CT and SPECT (GE Hawkeye) SPIE Medical Imaging 2006 28 CT/PET System Combined CT and PET (Siemens Medical Imaging 2006 10 Computed Tomography (CT) 3D Tomography from multiple projections #12;6 SPIE: Scintillation Camera SPIE Medical Imaging 2006 26 PET and SPECT PET = Positron Emission Tomography SPECT

  12. History of the US weapons-usable plutonium disposition program leading to DOE`s record of decision

    SciTech Connect (OSTI)

    Spellman, D.J.; Thomas, J.F.; Bugos, R.G.

    1997-04-01T23:59:59.000Z

    This report highlights important events and studies concerning surplus weapons-usable plutonium disposition in the United States. Included are major events that led to the creation of the U.S. Department of Energy (DOE) Office of Fissile Materials Disposition in 1994 and to that DOE office issuing the January 1997 Record of Decision for the Storage and Disposition of Weapons-Useable Fissile Materials Final Programmatic Environmental Impact Statement. Emphasis has been given to reactor-based plutonium disposition alternatives.

  13. Supplement to the Surplus Plutonium Disposition Draft Environmental Impact Statement

    SciTech Connect (OSTI)

    N /A

    1999-05-14T23:59:59.000Z

    On May 22, 1997, DOE published a Notice of Intent in the Federal Register (62 Federal Register 28009) announcing its decision to prepare an environmental impact statement (EIS) that would tier from the analysis and decisions reached in connection with the ''Storage and Disposition of Weapons-Usable Fissile Materials Final Programmatic EIS (Storage and Disposition PEIS)''. ''The Surplus Plutonium Disposition Draft Environmental Impact Statement'' (SPD Draft EIS) (DOWEIS-0283-D) was prepared in accordance with NEPA and issued in July 1998. It identified the potential environmental impacts of reasonable alternatives for the proposed siting, construction, and operation of three facilities for plutonium disposition. These three facilities would accomplish pit disassembly and conversion, immobilization, and MOX fuel fabrication. For the alternatives that included MOX fuel fabrication, the draft also described the potential environmental impacts of using from three to eight commercial nuclear reactors to irradiate MOX fuel. The potential impacts were based on a generic reactor analysis that used actual reactor data and a range of potential site conditions. In May 1998, DCE initiated a procurement process to obtain MOX fuel fabrication and reactor irradiation services. The request for proposals defined limited activities that may be performed prior to issuance of the SPD EIS Record of Decision (ROD) including non-site-specific work associated with the development of the initial design for the MOX fuel fabrication facility, and plans (paper studies) for outreach, long lead-time procurements, regulatory management, facility quality assurance, safeguards, security, fuel qualification, and deactivation. No construction on the proposed MOX facility would begin before an SPD EIS ROD is issued. In March 1999, DOE awarded a contract to Duke Engineering & Services; COGEMA, Inc.; and Stone & Webster (known as DCS) to provide the requested services. The procurement process included the environmental review specified in DOE's NEPA regulations in 10 CFR 1021.216. The six reactors selected are Catawba Nuclear Station Units 1 and 2 in South Carolina McGuire Nuclear Station Units 1 and 2 in North Carolina, and North Anna Power Station Units 1 and 2 in Virginia. The Supplement describes the potential environmental impacts of using MOX fuel in these six specific reactors named in the DCS proposal as well as other program changes made since the SPD Draft EIS was published.

  14. EIS-0240: Disposition of Surplus Highly Enriched Uranium

    Broader source: Energy.gov [DOE]

    The Department proposes to eliminate the proliferation threat of surplus highly enriched uranium (HEU) by blending it down to low enriched uranium (LEU), which is not weapons-usable. The EIS assesses the disposition of a nominal 200 metric tons of surplus HEU. The Preferred Alternative is, where practical, to blend the material for use as LEU and use overtime, in commercial nuclear reactor field to recover its economic value. Material that cannot be economically recovered would be blended to LEU for disposal as low-level radioactive waste.

  15. Implementation Guide for Surveillance and Maintenance during Facility Transition and Disposition

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    1999-09-29T23:59:59.000Z

    As DOE facilities complete mission operations and are declared excess, they pass into a transition phase that ultimately prepares them for disposition. The disposition phase of a facility's life cycle usually includes deactivation, decommissioning, and surveillance and maintenance (S&M) activities.

  16. U-233: Oracle Database INDEXTYPE CTXSYS.CONTEXT Bug Lets Remote...

    Broader source: Energy.gov (indexed) [DOE]

    Bug Lets Remote Authenticated Users Gain Elevated Privileges PLATFORM: Oracle Database Server versions 10.2.0.3, 10.2.0.4, 10.2.0.5, 11.1.0.7, 11.2.0.2, 11.2.0.3 ABSTRACT: A remote...

  17. U-233: Oracle Database INDEXTYPE CTXSYS.CONTEXT Bug Lets Remote

    Broader source: Energy.gov (indexed) [DOE]

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742EnergyOn April 23,EnergyChicopeeTechnologyfactTuscaroraDepartment ofDepartment of

  18. MANAGING HANFORD'S LEGACY NO-PATH-FORWARD WASTES TO DISPOSITION

    SciTech Connect (OSTI)

    WEST LD

    2011-01-13T23:59:59.000Z

    The U.S. Department of Energy (DOE) Richland Operations Office (RL) has adopted the 2015 Vision for Cleanup of the Hanford Site. This vision will protect the Columbia River, reduce the Site footprint, and reduce Site mortgage costs. The CH2M HILL Plateau Remediation Company's (CHPRC) Waste and Fuels Management Project (W&FMP) and their partners support this mission by providing centralized waste management services for the Hanford Site waste generating organizations. At the time of the CHPRC contract award (August 2008) slightly more than 9,000 m{sup 3} of waste was defined as 'no-path-forward waste.' The majority of these wastes are suspect transuranic mixed (TRUM) wastes which are currently stored in the low-level Burial Grounds (LLBG), or stored above ground in the Central Waste Complex (CWC). A portion of the waste will be generated during ongoing and future site cleanup activities. The DOE-RL and CHPRC have collaborated to identify and deliver safe, cost-effective disposition paths for 90% ({approx}8,000 m{sup 3}) of these problematic wastes. These paths include accelerated disposition through expanded use of offsite treatment capabilities. Disposal paths were selected that minimize the need to develop new technologies, minimize the need for new, on-site capabilities, and accelerate shipments of transuranic (TRU) waste to the Waste Isolation Pilot Plant (WIPP) in Carlsbad, New Mexico.

  19. A comparative assessment of the economics of plutonium disposition

    SciTech Connect (OSTI)

    Williams, K.A.; Miller, J.W.; Reid, R.L.

    1997-04-01T23:59:59.000Z

    The US Department of Energy office of Fissile Materials Disposition (DOE/MD) has been evaluating three technologies for the disposition of approximately 50 metric tons of surplus plutonium from defense-related programs: reactors, immobilization, and deep boreholes. As part of the process supporting an early CY 1997 Record of Decision (ROD), a comprehensive assessment of technical viability, cost, and schedule has been conducted by DOE/MD and its national laboratory contractors. Oak Ridge National Laboratory has managed and coordinated the life-cycle cost (LCC) assessment effort for this program. This paper discusses the economic analysis methodology and the results prior to ROD. A secondary intent of the paper is to discuss major technical and economic issues that impact cost and schedule. To evaluate the economics of these technologies on an equitable basis, a set of cost-estimating guidelines and a common cost-estimating format were utilized by all three technology teams. This paper also includes the major economic analysis assumptions and the comparative constant-dollar and discounted-dollar LCCs.

  20. R&D plan for immobilization technologies: fissile materials disposition program. Revision 1.0

    SciTech Connect (OSTI)

    Shaw, H.F.; Armantrout, G.A.

    1996-09-01T23:59:59.000Z

    In the aftermath of the Cold War, the US and Russia have agreed to large reductions in nuclear weapons. To aid in the selection of long- term fissile material management options, the Department of Energy`s Fissile Materials Disposition Program (FMDP) is conducting studies of options for the storage and disposition of surplus plutonium (Pu). One set of alternatives for disposition involve immobilization. The immobilization alternatives provide for fixing surplus fissile materials in a host matrix in order to create a solid disposal form that is nuclear criticality-safe, proliferation-resistant and environmentally acceptable for long-term storage or disposal.

  1. Disposition of clorazepate in dogs after single- and multiple-dose oral administration

    E-Print Network [OSTI]

    Forrester, Sharon Dru

    1989-01-01T23:59:59.000Z

    to compare single-dose disposition values with multiple-dose disposition values. The paired t test was also used to compare body weight on day 0 with that on day 21. Analysis of variance with repeated measures was used to evaluate results of routine... on both sets of parameters, comparing single-dose with multiple-dose disposition. Hecause the values for Vd(ss)/F from trapezoidal analysis were not normally distributed, nonparametric statistical analysis (ie, Wilcoxon rank sum test) was used...

  2. Integration of Environment, Safety, and Health into Facility Disposition Activities

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    1998-05-01T23:59:59.000Z

    Volume One of this Standard has been revised to provide a Department of Energy (DOE) approved methodology for preparing a Documented Safety Analysis (DSA) for decommissioning of nuclear facilities, as well as environmental restoration activities that involve work not done within a permanent structure. Methodologies provided in this Standard are intended to be compliant with Title 10 of the Code of Federal Regulations (CFR) Part 830, Nuclear Safety Management, Subpart B, Safety Basis Requirements. Volume Two contains the appendices that provide additional environment, safety and health (ES&H) information to complement Volume 1 of this Standard. Volume 2 of the Standard is much broader in scope than Volume 1 and satisfies several purposes. Integrated safety management expectations are provided in accordance with facility disposition requirements contained in DOE O 430.1B, Real Property Asset Management.

  3. An Evaluation of Single Phase Ceramic Formulations for Plutonium Disposition

    SciTech Connect (OSTI)

    Stennett, Martin C.; Hyatt, Neil C. [Engineering Materials, University of Sheffield, Mappin Street, Sheffield, S1 3JD (United Kingdom); Maddrell, Ewan R.; Scales, Charlie R. [Nexia Solutions Ltd., Sellafield, Seascale, CA20 1PG (United Kingdom); Livens, Francis R.; Gilbert, Matthew [Chemistry, University of Manchester, Oxford Road, Manchester, M13 9PL (United Kingdom)

    2007-07-01T23:59:59.000Z

    Ceramics are promising potential hosts for the immobilization of actinide containing wastes. Work has been reported in the literature on multiphase systems, such as SYNROC [1], and on single phase systems such as pyrochlores [2] and zirconia [3], but assessment of the different waste-forms by direct comparison of literature data is not always easy due to the different processing and fabrication routes employed. In this study a potential range of different ceramic systems were investigated for plutonium disposition using the same processing scheme. Durable actinide containing minerals exist in nature and provided excellent target phases for the titanate, zirconate, silicate and phosphate based formulations examined here [4]. The Ce solid solution limits for each particular substitution mechanism were established and the processing parameters required to produce high quality ceramic specimens were optimised. Importantly, this was achieved within the constraints of a generic processing route suitable for fabrication of Pu bearing samples. (authors)

  4. Analysis of disposition alternatives for radioactively contaminated scrap metal

    SciTech Connect (OSTI)

    Nieves, L.A.; Chen, S.Y.; Kohout, E.J.; Nabelssi, B.; Tilbrook, R.W.; Wilson, S.E.

    1997-01-01T23:59:59.000Z

    Millions of tonnes of slightly radioactive, scrap iron and steel, stainless steel, and copper are likely to become available as nuclear and other facilities and equipment are withdrawn from service. Disposition of this material is an international policy issue under consideration currently. The major alternatives for managing this material are to either develop a regulatory process for decontamination and recycling that will safeguard human health or to dispose of the scrap and replace the metal stocks. To evaluate the alternatives, we estimate quantities of scrap arising from nuclear power plant decommissioning, evaluate potential price impacts of recycling on regional markets, and assess the health and environmental impacts of the management alternatives. We conclude that decontaminating and recycling the scrap is the superior alternative.

  5. Acceleration of Los Alamos National Laboratory transuranic waste disposition

    SciTech Connect (OSTI)

    O'Leary, G.A.; Palmer, B.A.; Starke, T.P.; Phelps, A.K. [Los Alamos National Security, L.L.C., Los Alamos National Laboratory, Los Alamos, NM (United States)

    2007-07-01T23:59:59.000Z

    One of Los Alamos National Laboratory's (LANL's) most significant risks is the site's inventory of transuranic waste retrievably stored above and below-ground in Technical Area (TA) 54 Area G, particularly the dispersible high-activity waste stored above-ground in deteriorating facilities. The high activity waste represents approximately 50% (by activity) of the total 292,000 PE-Ci inventory remaining to be disposed. The transuranic waste inventory includes contact-handled and remote-handled waste packaged in drums, boxes, and oversized containers which are retrievably stored both above and below-ground. Although currently managed as transuranic waste, some of the inventory is low-level waste that can be disposed onsite or at approved offsite facilities. Dis-positioning the transuranic waste inventory requires retrieval of the containers from above and below- ground storage, examination and repackaging or remediation as necessary, characterization, certification and loading for shipment to the Waste Isolation Pilot Plant in Carlsbad, New Mexico, all in accordance with well-defined requirements and controls. Although operations are established to process and characterize the lower-activity contact-handled transuranic waste containers, LANL does not currently have the capability to repack high activity contact-handled transuranic waste containers (> 56 PE-Ci) or to process oversized containers with activity levels over 0.52 PE-Ci. Operational issues and compliance requirements have resulted in less than optimal processing capabilities for lower activity contact-handled transuranic waste containers, limiting preparation and reducing dependability of shipments to the Waste Isolation Pilot Plant. Since becoming the Los Alamos National Laboratory contractor in June 2006, Los Alamos National Security (LANS) L.L.C. has developed a comprehensive, integrated plan to effectively and efficiently disposition the transuranic waste inventory, working in concert with the Department of Energy Los Alamos Site Office, Carlsbad Field Office and the Department of Energy Headquarters. Rather than simply processing containers as retrieved, the plan places priority on efficient curie disposition, a direct correlation to reducing risk. Key elements of the approach include balancing inventory and operational risks, tailoring methods to meet requirements, optimizing existing facilities, equipment and staff, and incorporating best practices from other Department of Energy sites. With sufficient funding this will enable LANL to ship the above-ground high activity contact-handled transuranic waste offsite by the end of Fiscal Year (FY) 2007 and to disposition the remaining above- and below-ground contact-handled and remote-handled transuranic waste inventory by December 2010. Nearly 70% of the contact-handled transuranic waste containers, including the high activity waste, require processing and repackaging before characterization and certification for shipment to the Waste Isolation Pilot Plant. LANL is employing a balanced risk approach that accomplishes significant long-term risk reduction by accepting short-term increased facility operations risk under well-developed and justified interim controls. Reviews of facility conditions and additional analyses show that the Waste Characterization, Reduction and Repackaging Facility and the Radioassay and Nondestructive Testing Facility are the most appropriate facilities to safely remediate, repackage, and ship lower activity and the remaining high activity drums. Updated safety documentation supporting limited Hazard Category 2 operations in these facilities has been developed. Once approved, limited-term operations to process the high activity drums can begin in early 2007, building upon the experience base established performing Hazard Category 3 operations processing lower activity waste in these facilities. LANL is also implementing a series of actions to improve and sustain operations for processing contact-handled transuranic waste inventory. Building 412 Decontamination and Volume Reduction Fa

  6. ACCELERATION OF LOS ALAMOS NATIONAL LABORATORY TRANSURANIC WASTE DISPOSITION

    SciTech Connect (OSTI)

    O'LEARY, GERALD A. [Los Alamos National Laboratory

    2007-01-04T23:59:59.000Z

    One of Los Alamos National Laboratory's (LANL's) most significant risks is the site's inventory of transuranic waste retrievably stored above and below-ground in Technical Area (TA) 54 Area G, particularly the dispersible high-activity waste stored above-ground in deteriorating facilities. The high activity waste represents approximately 50% (by activity) of the total 292,000 PE-Ci inventory remaining to be disposed. The transuramic waste inventory includes contact-handled and remote-handled waste packaged in drums, boxes, and oversized containers which are retrievably stored both above and below-ground. Although currently managed as transuranic waste, some of the inventory is low-level waste that can be disposed onsite or at approved offsite facilities. Dispositioning the transuranic waste inventory requires retrieval of the containers from above and below-ground storage, examination and repackaging or remediation as necessary, characterization, certification and loading for shipment to the Waste Isolation Pilot Plant in Carlsbad New Mexico, all in accordance with well-defined requirements and controls. Although operations are established to process and characterize the lower-activity contact-handled transuranic waste containers, LAN L does not currently have the capability to repack high activity contact-handled transuranic waste containers (> 56 PE-Ci) or to process oversized containers with activity levels over 0.52 PE-Ci. Operational issues and compliance requirements have resulted in less than optimal processing capabilities for lower activity contact-handled transuranic waste containers, limiting preparation and reducing dependability of shipments to the Waste Isolation Pilot Plant. Since becoming the Los Alamos National Laboratory contract in June 2006, Los Alamos National Security (LANS) L.L.C. has developed a comprehensive, integrated plan to effectively and efficiently disposition the transuranic waste inventory, working in concert with the Department of Energy Los Alamos Site Office, Carlsbad Field Office and the Department of Energy Headquaeters. Rather than simply processing containers as retrieved, the plan places priority on efficient curie disposition, a direct correlation to reducing risk. Key elements of the approch include balancing inventory and operational risks, tailoring methods to meet requirements, optimizing existing facilities, equipment and staff, and incorporating best practices from other Department of Energy sites. With sufficient funding this will enable LANL to ship the above-ground high activity contact-handled transuranic waste offsite by the end of Fiscal Year (FY) 2007 and to disposition the remaining above- and below-ground contact-handled and remote-handled transuranic waste inventory by December 2010. Nearly 70% of the contact-handled transuranic waste containers, including the high activity waste, require processing and repackaging before characterization and certification for shipment to the Waste Isolation Pilot Plant. LANL is employing a balanced risk approach that accomplishes significant long-term risk reduction by accepting short-term increased facility operations risk under well-developed and justified interim controls. Reviews of facility conditions and additional analyses show that the Waste Characterization, Reduction and Repackaging Facility and the Radioassay and Nondestructive Testing Facility are the most appropriate facilities to safetly remediate, repackage, and ship lower activity and the remaining high activity drums. Updated safety documentation supporting limited Hazard Category 2 operations in these facilities has been developed. Once approved, limited-term operations to process the high activity drums can begin in early 2007, building upon the experience base established performing Hazard Category 3 operations processing lower activity waste in these facilities. LANL is also implementing a series of actions to improve and sustain operations for processing contact-handled transuranic waste inventory. Building 412 Decontamination and Volume Facility and Dom

  7. Reactor-Based Plutonium Disposition: Opportunities, Options, and Issues

    SciTech Connect (OSTI)

    Greene, S.R.

    1999-07-17T23:59:59.000Z

    The end of the Cold War has created a legacy of surplus fissile materials (plutonium and highly enriched uranium) in the United States (U.S.) and the former Soviet Union. These materials pose a danger to national and international security. During the past few years, the U.S. and Russia have engaged in an ongoing dialog concerning the safe storage and disposition of surplus fissile material stockpiles. In January 1997, the Department of Energy (DOE) announced the U. S. would pursue a dual track approach to rendering approximately 50 metric tons of plutonium inaccessible for use in nuclear weapons. One track involves immobilizing the plutonium by combining it with high-level radioactive waste in glass or ceramic ''logs''. The other method, referred to as reactor-based disposition, converts plutonium into mixed oxide (MOX) fuel for nuclear reactors. The U.S. and Russia are moving ahead rapidly to develop and demonstrate the technology required to implement the MOX option in their respective countries. U.S. MOX fuel research and development activities were started in the 1950s, with irradiation of MOX fuel rods in commercial light water reactors (LWR) from the 1960s--1980s. In all, a few thousand MOX fuel rods were successfully irradiated. Though much of this work was performed with weapons-grade or ''near'' weapons-grade plutonium--and favorable fuel performance was observed--the applicability of this data for licensing and use of weapons-grade MOX fuel manufactured with modern fuel fabrication processes is somewhat limited. The U.S. and Russia are currently engaged in an intensive research, development, and demonstration program to support implementation of the MOX option in our two countries. This paper focuses on work performed in the U.S. and provides a brief summary of joint U.S./Russian work currently underway.

  8. Environmental behavior of hafnium : the impact on the disposition of weapons-grade plutonium

    E-Print Network [OSTI]

    Cerefice, Gary Steven

    1999-01-01T23:59:59.000Z

    Experimental and analytical studies were performed to examine the environmental behavior of hafnium and its utility as a neutron poison for the disposition of weapons-grade plutonium in Yucca Mountain. The hydrolysis of ...

  9. Enabling completion of the material disposition area G closure at the Los Alamos National Laboratory

    SciTech Connect (OSTI)

    Blankenhorn, James Allen [Los Alamos National Laboratory; Bishop, Milton L [Los Alamos National Laboratory

    2010-01-01T23:59:59.000Z

    Los Alamos National Security, LLC (LANS) and the Los Alamos Site Office (LASO) have developed and are implementing an integrated strategy to accelerate the disposition of Los Alamos National Laboratory (LANL) legacy transuranic waste inventory currently stored in Technical Area 54, Material Disposition Area (MDA) G. As that strategy has been implemented the easier waste streams have been certified and shipped leaving the harder more challenging wastes to be dispositioned. Lessons learned from around the complex and a partnership with the National Transuranic Program located in Carlsbad, New Mexico, are enabling this acceleration. The Waste Disposition Program is responsible for the removal of both the above ground and below grade, retrievably stored transuranic waste in time to support the negotiated consent order with the State of New Mexico which requires closure of MDA G by the year 2015. The solutions and strategy employed at LANL are applicable to any organization that is currently managing legacy transuranic waste.

  10. EIS-0283-S2: Surplus Plutonium Disposition Supplemental Environmental Impact Statement

    Broader source: Energy.gov [DOE]

    This Supplemental EIS (SEIS) analyzes the potential environmental impacts associated with changes to the surplus plutonium disposition program, including changes to the inventory of surplus plutonium and proposed new alternatives.

  11. Barriers and Issues Related to Achieving Final Disposition of Depleted Uranium

    SciTech Connect (OSTI)

    Gillas, D. L.; Chambers, B. K.

    2002-02-26T23:59:59.000Z

    Approximately 750,000 metric tons (MT) of surplus depleted uranium (DU) in various chemical forms are stored at several Department of Energy (DOE) sites throughout the United States. Most of the DU is in the form of DU hexafluoride (DUF6) that resulted from uranium enrichment operations over the last several decades. DOE plans to convert the DUF6 to ''a more stable form'' that could be any one or combination of DU tetrafluoride (DUF4 or green salt), DU oxide (DUO3, DUO2, or DU3O8), or metal depending on the final disposition chosen for any given quantity. Barriers to final disposition of this material have existed historically and some continue today. Currently, the barriers are more related to finding uses for this material versus disposing as waste. Even though actions are beginning to convert the DUF6, ''final'' disposition of the converted material has yet to be decided. Unless beneficial uses can be implemented, DOE plans to dispose of this material as waste. This expresses the main barrier to DU disposition; DOE's strategy is to dispose unless uses can be found while the strategy should be only dispose as a last resort and make every effort to find uses. To date, only minimal research programs are underway to attempt to develop non-fuel uses for this material. Other issues requiring resolution before these inventories can reach final disposition (uses or disposal) include characterization, disposal of large quantities, storage (current and future), and treatment options. Until final disposition is accomplished, these inventories must be managed in a safe and environmentally sound manner; however, this is becoming more difficult as materials and facilities age. The most noteworthy final disposition technical issues include the development of reuse and treatment options.

  12. Medical Messages

    Office of Environmental Management (EM)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742 33Frequently Asked Questions forCheney suggestingTechnologiesMaterials(IDIQ/25/11 Medical

  13. DEVELOPMENT OF GLASS AND CRYSTALLINE CERAMIC FORMS FOR DISPOSITION OF EXCESS PLUTONIUM

    SciTech Connect (OSTI)

    Marra, James; Cozzi, A; Crawford, C.; Herman, C.; Marra, John; Peeler, D.

    2009-09-10T23:59:59.000Z

    In the aftermath of the Cold War, the United States Department of Energy (DOE) has identified up to 50 metric tons of excess plutonium that needs to be dispositioned. The bulk of the material is slated to be blended with uranium and fabricated into a Mixed Oxide (MOX) fuel for subsequent burning in commercial nuclear reactors. Excess plutonium-containing impurity materials making it unsuitable for fabrication into MOX fuel will need to be dispositioned via other means. Glass and crystalline ceramics have been developed and studied as candidate forms to immobilize these impure plutonium feeds. A titanate-based ceramic was identified as an excellent actinide material host. This composition was based on Synroc compositions previously developed for nuclear waste immobilization. These titanate ceramics were found to be able to accommodate extremely high quantities of fissile material and exhibit excellent aqueous durability. A lanthanide borosilicate (LaBS) glass was developed to accommodate high concentrations of plutonium and to be very tolerant of impurities yet still maintain good aqueous durability. Recent testing of alkali borosilicate compositions showed promise of using these compositions to disposition lower concentrations of plutonium using existing high level waste vitrification processes. The developed waste forms all appear to be suitable for Pu disposition. Depending on the actual types and concentrations of the Pu residue streams slated for disposition, each waste form offers unique advantages.

  14. Alternative technical summary report for direct disposition in deep boreholes: Direct disposal of plutonium metal/plutonium dioxide in compound canisters, Version 4.0. Fissile Materials Disposition Program

    SciTech Connect (OSTI)

    Wijesinghe, A.M.

    1996-08-23T23:59:59.000Z

    This report summarizes and compares the Immobilized and Direct Beep Borehole Disposition Alternatives. The important design concepts, facility features and operational procedures are briefly described, and a discussion of the issues that affect the evaluation of each alternative against the programmatic assessment criteria that have been established for selecting the preferred alternatives for plutonium disposition.

  15. Generation!and!Disposition!of!Municipal!Solid!Waste! (MSW)!in!the!United!States!A!National!Survey!

    E-Print Network [OSTI]

    Columbia University

    ! 1! ! Generation!and!Disposition!of!Municipal!Solid!Waste! (MSW on Municipal Solid Waste (MSW) Generation and Disposition in the U.S., in collaboration with Ms. Nora Goldstein of solid wastes and advance sustainable waste management in the U.S. to the level of several leading

  16. Superfund Policy Statements and Guidance Regarding Disposition of Radioactive Waste in Non-NRC Licensed Disposal Facilities - 13407

    SciTech Connect (OSTI)

    Walker, Stuart [U.S. Environmental Protection Agency (United States)] [U.S. Environmental Protection Agency (United States)

    2013-07-01T23:59:59.000Z

    This talk will discuss EPA congressional testimony and follow-up letters, as well as letters to other stakeholders on EPA's perspectives on the disposition of radioactive waste outside of the NRC licensed disposal facility system. This will also look at Superfund's historical practices, and emerging trends in the NRC and agreement states on waste disposition. (author)

  17. Fuel qualification issues and strategies for reactor-based surplus plutonium disposition

    SciTech Connect (OSTI)

    Cowell, B.S.; Copeland, G.L.; Moses, D.L.

    1997-08-01T23:59:59.000Z

    The Department of Energy (DOE) has proposed irradiation of mixed-oxide (MOX) fuel in existing commercial reactors as a disposition method for surplus plutonium from the weapons program. The burning of MOX fuel in reactors is supported by an extensive technology base; however, the infrastructure required to implement reactor-based plutonium disposition does not exist domestically. This report identifies and examines the actions required to qualify and license weapons-grade (WG) plutonium-based MOX fuels for use in domestic commercial light-water reactors (LWRs).

  18. Medical Device Reliability BIOMATERIALS

    E-Print Network [OSTI]

    NEMI Medical Electronics team to address short- and long-term reliability issues with medical devices. OurMedical Device Reliability BIOMATERIALS Our goal is to provide medical device manufacturers, and consistency of active implantable medical devices. These devices, including pacemakers, cardiac defibrillators

  19. EIS-0475: Disposition of the Bannister Federal Complex, Kansas City, MO

    Broader source: Energy.gov [DOE]

    NNSA/DOE announces its intent to prepare an EIS for the disposition of the Bannister Federal Complex, Kansas City, MO. NNSA previously decided in a separate NEPA review (EA-1592) to relocate its operations from the Bannister Federal Complex to a newly constructed industrial campus eight miles from the current location.

  20. Sample Results From The Interim Salt Disposition Program Macrobatch 6 Tank 21H Qualification Samples

    SciTech Connect (OSTI)

    Peters, T. B.; Fink, S. D.

    2012-12-20T23:59:59.000Z

    Savannah River National Laboratory (SRNL) analyzed samples from Tank 21H in support of qualification of Macrobatch (Salt Batch) 6 for the Interim Salt Disposition Project (ISDP). This document reports partial results of the analyses of samples of Tank 21H. No issues with the projected Salt Batch 6 strategy are identified.

  1. Sample Results from the Interim Salt Disposition Program Macrobatch 6 Tank 21H Qualification Samples

    SciTech Connect (OSTI)

    Peters, T. B.; Fink, S. D.

    2012-12-11T23:59:59.000Z

    Savannah River National Laboratory (SRNL) analyzed samples from Tank 21H in support of qualification of Macrobatch (Salt Batch) 6 for the Interim Salt Disposition Project (ISDP). This document reports partial results of the analyses of samples of Tank 21H. No issues with the projected Salt Batch 6 strategy are identified.

  2. HLW Salt Disposition Alternatives Identification Preconceptual Phase I Summary Report (Including Attachments)

    SciTech Connect (OSTI)

    Piccolo, S.F.

    1999-07-09T23:59:59.000Z

    The purpose of this report is to summarize the process used by the Team to systematically develop alternative methods or technologies for final disposition of HLW salt. Additionally, this report summarizes the process utilized to reduce the total list of identified alternatives to an ''initial list'' for further evaluation. This report constitutes completion of the team charter major milestone Phase I Deliverable.

  3. DEVELOPING AN INTEGRATED NATIONAL STRATEGY FOR THE DISPOSITION OF SPENT NUCLEAR FUEL

    SciTech Connect (OSTI)

    Gelles, C.M.

    2003-02-27T23:59:59.000Z

    This paper summarizes the Department of Energy's (DOE's) current efforts to strengthen its activities for the management and disposition of DOE-owned spent nuclear fuel (SNF). In August 2002 an integrated, ''corporate project'' was initiated by the Office of Environmental Management (EM) to develop a fully integrated strategy for disposition of the approximately {approx}250,000 DOE SNF assemblies currently managed by EM. Through the course of preliminary design, the focus of this project rapidly evolved to become DOE-wide. It is supported by all DOE organizations involved in SNF management, and represents a marked change in the way DOE conducts its business. This paper provides an overview of the Corporate Project for Integrated/Risk-Driven Disposition of SNF (Corporate SNF Project), including a description of its purpose, scope and deliverables. It also summarizes the results of the integrated project team's (IPT's) conceptual design efforts, including the identification of project/system requirements and alternatives. Finally, this paper highlights the schedule of the corporate project, and its progress towards development of a DOE corporate strategy for SNF disposition.

  4. IDENTIFYING IMPURITIES IN SURPLUS NON PIT PLUTONIUM FEEDS FOR MOX OR ALTERNATIVE DISPOSITION

    SciTech Connect (OSTI)

    Allender, J; Moore, E

    2010-07-14T23:59:59.000Z

    This report provides a technical basis for estimating the level of corrosion products in materials stored in DOE-STD-3013 containers based on extrapolating available chemical sample results. The primary focus is to estimate the levels of nickel, iron, and chromium impurities in plutonium-bearing materials identified for disposition in the United States Mixed Oxide fuel process.

  5. A HOLISTIC APPROACH FOR DISPOSITION OF LONG-LIVED RADIOACTIVE MATERIALS

    SciTech Connect (OSTI)

    Eriksson, Leif G.; Dials, George E.; Parker, Frank L.

    2003-02-27T23:59:59.000Z

    During the past 45 years, one of the most challenging scientific, engineering, socio-economic, and political tasks and obligations of our time has been to site and develop technical, politically acceptable, solutions to the safe disposition of long-lived radioactive materials (LLRMs). However, at the end of the year 2002, the Waste Isolation Pilot Plant (WIPP) site in the United States of America (USA) hosts the world's only operating LLRM-disposal system, which (1) is based on the LLRM-disposal principles recommended by the National Academy of Sciences (NAS) in 1957, i.e., deep geological disposal in a ''stable'' salt vault/repository, (2) complies with the nation's ''Environmental Radiation Protection Standards for the Management and Disposal of Spent Nuclear Fuel, High-Level and Transuranic Radioactive Wastes'', and (3) may receive 175,584 cubic meters (m3) of transuranic radioactive waste (TRUW)a. Pending the scheduled opening of repositories for once-used nuclear fuel (OUNF) in the USA, Sweden, and Finland in the years 2010, 2015, and 2017, respectively, LLRM-disposal solutions remain the missing link in all national LLRM-disposition programs. Furthermore, for a variety of reasons, many nations with nuclear programs have chosen a ''spectator'' stance in terms of enhancing the global nuclear safety culture and the nuclear renaissance, and have either ''slow-tracked'' or deferred their LLRM-disposal programs to allow time for an informed national consensus to evolve based on LLRM-disposition experiences and solutions gained elsewhere. In the meantime, LLRMs will continue to amass in different types and levels of safeguarded storage facilities around the world. In an attempt to contribute to the enhancement of the global nuclear safety culture and the nuclear renaissance, the authors developed the sample holistic approach for synergistic disposition of LLRMs comprising LLRM-disposition components considered either ''proven'' or ''promising'' by the authors. The fundamental principles of the holistic approach are: (1) Risk minimization; (2) Minimization of the LLRM volume requiring deep geological disposal; and (3) LLRM-disposition flexibility. An integral element of these principles is to allow time for LLRM-disposition solutions to evolve/mature technically, financially, and politically. Furthermore, contingent upon the desired outcome(s), available financial, scientific, and technical resources, and political will, these components may be implemented separately or in combinations by one or a group of nations.

  6. Study of plutonium disposition using the GE Advanced Boiling Water Reactor (ABWR)

    SciTech Connect (OSTI)

    NONE

    1994-04-30T23:59:59.000Z

    The end of the cold war and the resulting dismantlement of nuclear weapons has resulted in the need for the U.S. to disposition 50 to 100 metric tons of excess of plutonium in parallel with a similar program in Russia. A number of studies, including the recently released National Academy of Sciences (NAS) study, have recommended conversion of plutonium into spent nuclear fuel with its high radiation barrier as the best means of providing long-term diversion resistance to this material. The NAS study {open_quotes}Management and Disposition of Excess Weapons Plutonium{close_quotes} identified light water reactor spent fuel as the most readily achievable and proven form for the disposition of excess weapons plutonium. The study also stressed the need for a U.S. disposition program which would enhance the prospects for a timely reciprocal program agreement with Russia. This summary provides the key findings of a GE study where plutonium is converted into Mixed Oxide (MOX) fuel and a 1350 MWe GE Advanced Boiling Water Reactor (ABWR) is utilized to convert the plutonium to spent fuel. The ABWR represents the integration of over 30 years of experience gained worldwide in the design, construction and operation of BWRs. It incorporates advanced features to enhance reliability and safety, minimize waste and reduce worker exposure. For example, the core is never uncovered nor is any operator action required for 72 hours after any design basis accident. Phase 1 of this study was documented in a GE report dated May 13, 1993. DOE`s Phase 1 evaluations cited the ABWR as a proven technical approach for the disposition of plutonium. This Phase 2 study addresses specific areas which the DOE authorized as appropriate for more in-depth evaluations. A separate report addresses the findings relative to the use of existing BWRs to achieve the same goal.

  7. LLNL MOX fuel lead assemblies data report for the surplus plutonium disposition environmental impact statement

    SciTech Connect (OSTI)

    O`Connor, D.G.; Fisher, S.E.; Holdaway, R. [and others

    1998-08-01T23:59:59.000Z

    The purpose of this document is to support the US Department of Energy (DOE) Fissile Materials Disposition Program`s preparation of the draft surplus plutonium disposition environmental impact statement. This is one of several responses to data call requests for background information on activities associated with the operation of the lead assembly (LA) mixed-oxide (MOX) fuel fabrication facility. The DOE Office of Fissile Materials Disposition (DOE-MD) has developed a dual-path strategy for disposition of surplus weapons-grade plutonium. One of the paths is to disposition surplus plutonium through irradiation of MOX fuel in commercial nuclear reactors. MOX fuel consists of plutonium and uranium oxides (PuO{sub 2} and UO{sub 2}), typically containing 95% or more UO{sub 2}. DOE-MD requested that the DOE Site Operations Offices nominate DOE sites that meet established minimum requirements that could produce MOX LAs. LLNL has proposed an LA MOX fuel fabrication approach that would be done entirely inside an S and S Category 1 area. This includes receipt and storage of PuO{sub 2} powder, fabrication of MOX fuel pellets, assembly of fuel rods and bundles, and shipping of the packaged fuel to a commercial reactor site. Support activities will take place within a Category 1 area. Building 332 will be used to receive and store the bulk PuO{sub 2} powder, fabricate MOX fuel pellets, and assemble fuel rods. Building 334 will be used to assemble, store, and ship fuel bundles. Only minor modifications would be required of Building 332. Uncontaminated glove boxes would need to be removed, petition walls would need to be removed, and minor modifications to the ventilation system would be required.

  8. Used fuel disposition campaign international activities implementation plan.

    SciTech Connect (OSTI)

    Nutt, W. M. (Nuclear Engineering Division)

    2011-06-29T23:59:59.000Z

    The management of used nuclear fuel and nuclear waste is required for any country using nuclear energy. This includes the storage, transportation, and disposal of low and intermediate level waste (LILW), used nuclear fuel (UNF), and high level waste (HLW). The Used Fuel Disposition Campaign (UFDC), within the U.S. Department of Energy (DOE), Office of Nuclear Energy (NE), Office of Fuel Cycle Technology (FCT), is responsible for conducting research and development pertaining to the management of these materials in the U.S. Cooperation and collaboration with other countries would be beneficial to both the U.S. and other countries through information exchange and a broader participation of experts in the field. U.S. participation in international UNF and HLW exchanges leads to safe management of nuclear materials, increased security through global oversight, and protection of the environment worldwide. Such interactions offer the opportunity to develop consensus on policy, scientific, and technical approaches. Dialogue to address common technical issues helps develop an internationally recognized foundation of sound science, benefiting the U.S. and participating countries. The UNF and HLW management programs in nuclear countries are at different levels of maturity. All countries utilizing nuclear power must store UNF, mostly in wet storage, and HLW for those countries that reprocess UNF. Several countries either utilize or plan to utilize dry storage systems for UNF, perhaps for long periods of time (several decades). Geologic disposal programs are at various different states, ranging from essentially 'no progress' to selected sites and pending license applications to regulators. The table below summarizes the status of UNF and HLW management programs in several countriesa. Thus, the opportunity exists to collaborate at different levels ranging from providing expertise to those countries 'behind' the U.S. to obtaining access to information and expertise from those countries with more mature programs. The U.S. fuel cycle is a once through fuel cycle involving the direct disposal of UNF, as spent nuclear fuel, in a geologic repository (previously identified at Yucca Mountain, Nevada), following at most a few decades of storage (wet and dry). The geology at Yucca Mountain, unsaturated tuff, is unique among all countries investigating the disposal of UNF and HLW. The decision by the U.S. Department of Energy to no longer pursue the disposal of UNF at Yucca Mountain and possibly utilize very long term storage (approaching 100 years or more) while evaluating future fuel cycle alternatives for managing UNF, presents a different UNF and HLW management R&D portfolio that has been pursued in the U.S. In addition, the research and development activities managed by OCRWM have been transferred to DOE-NE. This requires a reconsideration of how the UFDC will engage in cooperative and collaborative activities with other countries. This report presents the UFDC implementation plan for international activities. The DOE Office of Civilian Radioactive Waste Management (OCRWM) has cooperated and collaborated with other countries in many different 'arenas' including the Nuclear Energy Agency (NEA) within the Organization for Economic Co-operation and Development (OECD), the International Atomic Energy Agency (IAEA), and through bilateral agreements with other countries. These international activities benefited OCRWM through the acquisition and exchange of information, database development, and peer reviews by experts from other countries. DOE-NE cooperates and collaborates with other countries in similar 'arenas' with similar objectives and realizing similar benefits. However the DOE-NE focus has not typically been in the area of UNF and HLW management. This report will first summarize these recent cooperative and collaborative activities. The manner that the UFDC will cooperate and collaborate in the future is expected to change as R&D is conducted regarding long-term storage and the potential disposal of UNF and HLW in different geolo

  9. Medical Aspects of Reliability

    SciTech Connect (OSTI)

    Atencio, Julian J.

    2014-05-05T23:59:59.000Z

    This presentation covers the medical evaluation as part of a human reliability program, particularly the various medical qualifications and potential disqualifiers.

  10. Alternative technical summary report for immobilized disposition in deep boreholes: Immobilized disposal of plutonium in coated ceramic pellets in grout without canisters, Version 4.0. Fissile materials disposition program

    SciTech Connect (OSTI)

    Wijesinghe, A.M.

    1996-08-23T23:59:59.000Z

    This paper summarizes and compares the immobilized and direct borehole disposition alternatives previously presented in the alternative technical summary. The important design concepts, facility features and operational procedures are first briefly described. This is followed by a discussion of the issues that affect the evaluation of each alternative against the programmatic assessment criteria that have been established for selecting the preferred alternatives for plutonium disposition.

  11. Medical Management Treatment Manual

    E-Print Network [OSTI]

    Bezrukov, Sergey M.

    Medical Management Treatment Manual: A Clinical Guide for Researchers and Clinicians) This manual is an adaptation of: Medical Management Treatment Manual: A Clinical Research Guide for Medically, Maryland #12;Message to the Users of this Medical Management (MM) Manual from the Editors Background

  12. Complications of New Medications

    E-Print Network [OSTI]

    Roldan, Carlos J.; Paniagua, Linda

    2015-01-01T23:59:59.000Z

    with 60% neutrophils. A computed tomography demonstrated “of New Medications Figure. Computed tomography of the face

  13. Used fuel disposition research and development roadmap - FY10 status.

    SciTech Connect (OSTI)

    Nutt, W. M. (Nuclear Engineering Division)

    2010-10-01T23:59:59.000Z

    Since 1987 the U.S. has focused research and development activities relevant to the disposal of commercial used nuclear fuel and U.S. Department of Energy (DOE) owned spent nuclear fuel and high level waste on the proposed repository at Yucca Mountain, Nevada. At the same time, the U.S. successfully deployed a deep geologic disposal facility for defense-related transuranic waste in bedded salt at the Waste Isolation Pilot Plant. In 2009 the DOE established the Used Fuel Disposition Campaign (UFDC) within the Office of Nuclear Energy. The Mission of the UFDC is to identify alternatives and conduct scientific research and technology development to enable storage, transportation and disposal of used nuclear fuel and wastes generated by existing and future nuclear fuel cycles. The U.S. national laboratories have participated on these programs and has conducted research and development related to these issues to a limited extent. However, a comprehensive research and development (R&D) program investigating a variety of geologic media has not been a part of the U.S. waste management program since the mid 1980s. Such a comprehensive R&D program is being developed in the UFDC with a goal of meeting the UFDC Grand Challenge to provide a sound technical basis for absolute confidence in the safety and security of long-term storage, transportation, and disposal of used nuclear fuel and wastes from the nuclear energy enterprise. The DOE has decided to no longer pursue the development of a repository at Yucca Mountain, Nevada. Since a repository site will ultimately have to be selected, sited, characterized, designed, and licensed, other disposal options must now be considered. In addition to the unsaturated volcanic tuff evaluated at Yucca Mountain, several different geologic media are under investigation internationally and preliminary assessments indicate that disposal of used nuclear fuel and high level waste in these media is feasible. Considerable progress has been made in the U.S. and other nations in understanding disposal concepts in different geologic media, but gaps in knowledge still exist. A principal aspect of concern to the UFDC as it considers the broad issues of siting a repository in different geologic media are the marked differences in the regulatory bases for assessing suitability and safety of a repository between the U.S. and other nations. Because the probability based - risked informed nature of the current U.S. regulations for high-level radioactive waste and spent nuclear fuel is sufficiently different from other regulations, information gained in previous studies, while useful, likely need to be supplemented to enable more convincing communication with the public, better defense of the numerical models, and stronger safety cases. Thus, it was recognized when the UFDC was established that there were readily identified disposal-related R&D opportunities to address knowledge gaps. An effort to document these research opportunities was a key component of Fiscal Year (FY) 2010 engineered system, natural system, and system-level modeling activities for a range of disposal environments. A principal contribution to identifying these gaps was a workshop held to gather perspectives from experts both within and external to the UFDC regarding R&D opportunities. In the planning for FY2010 it was expected that these activities would culminate with a UFDC research and development roadmap that would identify the knowledge gaps, discuss the R&D needed to fill these gaps, and prioritize the proposed R&D over both the near- and long-term. A number of knowledge gaps and needed R&D were identified and are discussed in this report. However, these preliminary R&D topics have not been evaluated in detail nor have they been prioritized to support future planning efforts. This will be completed in FY11 and the final UFDC Research and Development Roadmap will be completed. This report discusses proposed R&D topics in three areas related to repository siting, design, and performance: natural systems

  14. Evaluation of disposition scores in Bos indicus/Bos taurus cross calves at different stages of production

    E-Print Network [OSTI]

    Funkhouser, Rena Rebecca

    2008-10-10T23:59:59.000Z

    Rebecca Funkhouser, B.S., Virginia Tech Chair of Advisory Committee: Dr. Jim Sanders Aggressiveness, nervousness, flightiness, gregariousness and overall disposition were evaluated in F 2 Nellore-Angus embryo transfer calves (n = 443) from 13 full... for use in QTL analysis for major genes for disposition in Nellore-Angus cross cattle. v ACKNOWLEDGEMENTS First and foremost I would like to thank Dr. Sanders for being so much more than a committee chair. Your help and support both...

  15. DOE Plutonium Disposition Study: Pu consumption in ALWRs. Volume 1, Final report

    SciTech Connect (OSTI)

    Not Available

    1993-05-15T23:59:59.000Z

    The Department of Energy (DOE) has contracted with Asea Brown Boveri-Combustion Engineering (ABB-CE) to provide information on the capability of ABB-CE`s System 80 + Advanced Light Water Reactor (ALWR) to transform, through reactor burnup, 100 metric tonnes (MT) of weapons grade plutonium (Pu) into a form which is not readily useable in weapons. This information is being developed as part of DOE`s Plutonium Disposition Study, initiated by DOE in response to Congressional action. This document, Volume 1, presents a technical description of the various elements of the System 80 + Standard Plant Design upon which the Plutonium Disposition Study was based. The System 80 + Standard Design is fully developed and directly suited to meeting the mission objectives for plutonium disposal. The bass U0{sub 2} plant design is discussed here.

  16. U.S. weapons-usable plutonium disposition policy: Implementation of the MOX fuel option

    SciTech Connect (OSTI)

    Woods, A.L. [ed.] [Amarillo National Resource Center for Plutonium, TX (United States); Gonzalez, V.L. [Texas A and M Univ., College Station, TX (United States). Dept. of Political Science

    1998-10-01T23:59:59.000Z

    A comprehensive case study was conducted on the policy problem of disposing of US weapons-grade plutonium, which has been declared surplus to strategic defense needs. Specifically, implementation of the mixed-oxide fuel disposition option was examined in the context of national and international nonproliferation policy, and in contrast to US plutonium policy. The study reveals numerous difficulties in achieving effective implementation of the mixed-oxide fuel option including unresolved licensing and regulatory issues, technological uncertainties, public opposition, potentially conflicting federal policies, and the need for international assurances of reciprocal plutonium disposition activities. It is believed that these difficulties can be resolved in time so that the implementation of the mixed-oxide fuel option can eventually be effective in accomplishing its policy objective.

  17. Disposition of PUREX facility tanks D5 and E6 uranium and plutonium solutions. Final report

    SciTech Connect (OSTI)

    Harty, D.P.

    1993-12-01T23:59:59.000Z

    Approximately 9 kilograms of plutonium and 5 metric tons of uranium in a 1 molar nitric acid solution are being stored in two PUREX facility vessels, tanks D5 and E6. The plutonium was accumulated during cleanup activities of the plutonium product area of the PUREX facility. Personnel at PUREX recently completed a formal presentation to the Surplus Materials Peer Panel (SMPP) regarding disposition of the material currently in these tanks. The peer panel is a group of complex-wide experts who have been chartered by EM-64 (Office of Site and Facility Transfer) to provide a third party independent review of disposition decisions. The information presented to the peer panel is provided in the first section of this report. The panel was generally receptive to the information provided at that time and the recommendations which were identified.

  18. Disposition and transportation of surplus radioactive low specific activity nitric acid. Volume 1, Environmental Assessment

    SciTech Connect (OSTI)

    NONE

    1995-05-01T23:59:59.000Z

    DOE is deactivating the PUREX plant at Hanford; this will involve the disposition of about 692,000 liters (183,000 gallons) of surplus nitric acid contaminated with low levels of U and other radionuclides. The nitric acid, designated as low specific activity, is stored in 4 storage tanks at PUREX. Five principal alternatives were evaluated: transfer for reuse (sale to BNF plc), no action, continued storage in Hanford upgraded or new facility, consolidation of DOE surplus acid, and processing the LSA nitric acid as waste. The transfer to BNF plc is the preferred alternative. From the analysis, it is concluded that the proposed disposition and transportation of the acid does not constitute a major federal action significantly affecting the quality of the human environment within the meaning of NEPA; therefore an environmental impact statement is not required.

  19. The environmental assessment of nuclear materials disposition options: A transportation perspective

    SciTech Connect (OSTI)

    Wilson, R.K.; Clauss, D.B.; Moyer, J.W.

    1994-12-31T23:59:59.000Z

    The US Department of Energy has undertaken a program to evaluate and select options for the long-term storage and disposition of fissile materials declared surplus to defense needs as a result of the end of the Cold War. The transport of surplus fissile material will be an important and highly visible aspect of the environmental impact studies and other planning documents required for implementation of the disposition options. This report defines the roles and requirements for transportation of fissile materials in the program, and discusses an existing methodology for determining the environmental impact in terms of risk. While it will be some time before specific alternatives are chosen that will permit the completion of detailed risk calculations, the analytical models for performing the probabilistic risk assessments already exist with much of the supporting data related to the transportation system. This report summarizes the various types of data required and identifies sources for that data.

  20. --No Title--

    Broader source: Energy.gov (indexed) [DOE]

    extract thorium from the inventory for medical research and then downblend the U-233 with depleted uranium for long-term storage. In 2006, however, Congress directed that thorium...

  1. US weapons-useable plutonium disposition policy: implementation of the MOX fuel option 

    E-Print Network [OSTI]

    Gonzalez, Vanessa L

    1998-01-01T23:59:59.000Z

    be construed as conflicting with the current proposed policy to use mixed-oxide fuel. Additionally, the plutonium disposition policy is completely contingent upon the United States' ability to secure a bilateml agreement with Russia for reciprocal plutonium..., Russia and India- may attempt to establish a global plutonium economy in which the U. S. , under its current policy, could not be a participant (Davis and Donnelly 1994). In fact, despite the United States' efforts to curtail proliferation risks...

  2. Medical Information | Jefferson Lab

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645U.S. DOE Office of Science (SC)Integrated Codes |IsLove Your Home andDispositionMechanical R&DMaking

  3. Environmental Assessment for U-233 Stabilization, and Building 3019 Complex Shutdown at the Oak Ridge National Laboratory Oak Ridge, Tennessee

    Office of Environmental Management (EM)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742 33 1112011AT&T,OfficeEnd of Year 2010 SNFEnergySession0-02 -RailroadEnvironmentalAssessment574

  4. Study of plutonium disposition using existing GE advanced Boiling Water Reactors

    SciTech Connect (OSTI)

    Not Available

    1994-06-01T23:59:59.000Z

    The end of the cold war and the resulting dismantlement of nuclear weapons has resulted in the need for the US to dispose of 50 to 100 metric tons of excess of plutonium in a safe and proliferation resistant manner. A number of studies, including the recently released National Academy of Sciences (NAS) study, have recommended conversion of plutonium into spent nuclear fuel with its high radiation barrier as the best means of providing permanent conversion and long-term diversion resistance to this material. The NAS study ``Management and Disposition of Excess Weapons Plutonium identified Light Water Reactor spent fuel as the most readily achievable and proven form for the disposition of excess weapons plutonium. The study also stressed the need for a US disposition program which would enhance the prospects for a timely reciprocal program agreement with Russia. This summary provides the key findings of a GE study where plutonium is converted into Mixed Oxide (MOX) fuel and a typical 1155 MWe GE Boiling Water Reactor (BWR) is utilized to convert the plutonium to spent fuel. A companion study of the Advanced BWR has recently been submitted. The MOX core design work that was conducted for the ABWR enabled GE to apply comparable fuel design concepts and consequently achieve full MOX core loading which optimize plutonium throughput for existing BWRs.

  5. Safeguards and security requirements for weapons plutonium disposition in light water reactors

    SciTech Connect (OSTI)

    Thomas, L.L.; Strait, R.S. [Lawrence Livermore National Lab., CA (United States). Fission Energy and Systems Safety Program

    1994-10-01T23:59:59.000Z

    This paper explores the issues surrounding the safeguarding of the plutonium disposition process in support of the United States nuclear weapons dismantlement program. It focuses on the disposition of the plutonium by burning mixed oxide fuel in light water reactors (LWR) and addresses physical protection, material control and accountability, personnel security and international safeguards. The S and S system needs to meet the requirements of the DOE Orders, NRC Regulations and international safeguards agreements. Experience has shown that incorporating S and S measures into early facility designs and integrating them into operations provides S and S that is more effective, more economical, and less intrusive. The plutonium disposition safeguards requirements with which the US has the least experience are the implementation of international safeguards on plutonium metal; the large scale commercialization of the mixed oxide fuel fabrication; and the transportation to and loading in the LWRs of fresh mixed oxide fuel. It is in these areas where the effort needs to be concentrated if the US is to develop safeguards and security systems that are effective and efficient.

  6. Life cycle costs for the domestic reactor-based plutonium disposition option

    SciTech Connect (OSTI)

    Williams, K.A.

    1999-10-01T23:59:59.000Z

    Projected constant dollar life cycle cost (LCC) estimates are presented for the domestic reactor-based plutonium disposition program being managed by the US Department of Energy Office of Fissile Materials Disposition (DOE/MD). The scope of the LCC estimate includes: design, construction, licensing, operation, and deactivation of a mixed-oxide (MOX) fuel fabrication facility (FFF) that will be used to purify and convert weapons-derived plutonium oxides to MOX fuel pellets and fabricate MOX fuel bundles for use in commercial pressurized-water reactors (PWRs); fuel qualification activities and modification of facilities required for manufacture of lead assemblies that will be used to qualify and license this MOX fuel; and modification, licensing, and operation of commercial PWRs to allow irradiation of a partial core of MOX fuel in combination with low-enriched uranium fuel. The baseline cost elements used for this document are the same as those used for examination of the preferred sites described in the site-specific final environmental impact statement and in the DOE Record of Decision that will follow in late 1999. Cost data are separated by facilities, government accounting categories, contract phases, and expenditures anticipated by the various organizations who will participate in the program over a 20-year period. Total LCCs to DOE/MD are projected at approximately $1.4 billion for a 33-MT plutonium disposition mission.

  7. PROGRESS IN REDUCING THE NUCLEAR THREAT: UNITED STATES PLUTONIUM CONSOLIDATION AND DISPOSITION

    SciTech Connect (OSTI)

    Allender, J.; Koenig, R.; Davies, S.

    2009-06-01T23:59:59.000Z

    Following the end of the Cold War, the United States identified 61.5 metric tons (MT) of plutonium and larger quantities of enriched uranium that are permanently excess to use in nuclear weapons programs. The Department of Energy (DOE) also began shutting down, stabilizing, and removing inventories from production facilities that were no longer needed to support weapons programs and non-weapons activities. The storage of 'Category I' nuclear materials at Rocky Flats, Sandia National Laboratories, and several smaller sites has been terminated to reduce costs and safeguards risks. De-inventory continues at the Hanford site and the Lawrence Livermore National Laboratory. Consolidation of inventories works in concert with the permanent disposition of excess inventories, including several tonnes of plutonium that have already been disposed to waste repositories and the preparation for transfers to the planned Mixed Oxide (MOX) Fuel Fabrication Facility (for the bulk of the excess plutonium) and alternative disposition methods for material that cannot be used readily in the MOX fuel cycle. This report describes status of plutonium consolidation and disposition activities and their impacts on continuing operations, particularly at the Savannah River Site.

  8. DOE standard: Integration of environment, safety, and health into facility disposition activities. Volume 2: Appendices

    SciTech Connect (OSTI)

    NONE

    1998-05-01T23:59:59.000Z

    This volume contains the appendices that provide additional environment, safety, and health (ES and H) information to complement Volume 1 of this Standard. Appendix A provides a set of candidate DOE ES and H directives and external regulations, organized by hazard types that may be used to identify potentially applicable directives to a specific facility disposition activity. Appendix B offers examples and lessons learned that illustrate implementation of ES and H approaches discussed in Section 3 of Volume 1. Appendix C contains ISMS performance expectations to guide a project team in developing and implementing an effective ISMS and in developing specific performance criteria for use in facility disposition. Appendix D provides guidance for identifying potential Applicable or Relevant and Appropriate Requirements (ARARs) when decommissioning facilities fall under the Comprehensive Environmental Response, Compensation, Liability Act (CERCLA) process. Appendix E discusses ES and H considerations for dispositioning facilities by privatization. Appendix F is an overview of the WSS process. Appendix G provides a copy of two DOE Office of Nuclear Safety Policy and Standards memoranda that form the bases for some of the guidance discussed within the Standard. Appendix H gives information on available hazard analysis techniques and references. Appendix I provides a supplemental discussion to Sections 3.3.4, Hazard Baseline Documentation, and 3.3.6, Environmental Permits. Appendix J presents a sample readiness evaluation checklist.

  9. Emergency Medical Support

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    1997-08-21T23:59:59.000Z

    This volume defines coordination between emergency planners and emergency medical support. Canceled by DOE G 151.1-4.

  10. Medical Student Resource Guide

    E-Print Network [OSTI]

    Chapman, Michael S.

    20132014 O.H.S.U. Medical Student Resource Guide #12;2013-2014 Medical Student Resource Guide 1 Oregon Health & Science University School of Medicine - Medical Student Resource Guide Welcome This is an exciting time to be in medicine. Advances in the sciences basic to the study and practice of medicine

  11. Medical Student Procedure Guide

    E-Print Network [OSTI]

    Chapman, Michael S.

    20132014 O.H.S.U. Medical Student Procedure Guide #12;2013-2014 Medical Student Procedure Guide 1 Oregon Health & Science University School of Medicine - Medical Student Procedure Guide Welcome This is an exciting time to be in medicine. Advances in the sciences basic to the study and practice of medicine

  12. ANL-W MOX fuel lead assemblies data report for the surplus plutonium disposition environmental impact statement

    SciTech Connect (OSTI)

    O`Connor, D.G.; Fisher, S.E.; Holdaway, R. [and others

    1997-08-01T23:59:59.000Z

    The purpose of this document is to support the US Department of Energy (DOE) Fissile Materials Disposition Program`s preparation of the draft surplus plutonium disposition environmental impact statement (EIS). This is one of several responses to data call requests for background information on activities associated with the operation of the lead assembly (LA) mixed-oxide (MOX) fuel fabrication facility. The DOE Office of fissile Materials Disposition (DOE-MD) has developed a dual-path strategy for disposition of surplus weapons-grade plutonium. One of the paths is to disposition surplus plutonium through irradiation of MOX fuel in commercial nuclear reactors. MOX fuel consists of plutonium and uranium oxides (PuO{sub 2} and UO{sub 2}), typically containing 95% or more UO{sub 2}. DOE-MD requested that the DOE Site Operations Offices nominate DOE sites that meet established minimum requirements that could produce MOX LAs. The paper describes the following: Site map and the LA facility; process descriptions; resource needs; employment requirements; wastes, emissions, and exposures; accident analysis; transportation; qualitative decontamination and decommissioning; post-irradiation examination; LA fuel bundle fabrication; LA EIS data report assumptions; and LA EIS data report supplement.

  13. OKLAHOMA STATE UNIVERSITY MEDICAL AUTHORITY

    E-Print Network [OSTI]

    Veiga, Pedro Manuel Barbosa

    OKLAHOMA STATE UNIVERSITY MEDICAL AUTHORITY June 30, 2010 #12;OKLAHOMA STATE UNIVERSITY MEDICAL Authority Members Oklahoma State University Medical Authority Tulsa, Oklahoma We have audited the accompanying statements of financial position of the Oklahoma State University Medical Authority (the

  14. OKLAHOMA STATE UNIVERSITY MEDICAL AUTHORITY

    E-Print Network [OSTI]

    Veiga, Pedro Manuel Barbosa

    OKLAHOMA STATE UNIVERSITY MEDICAL AUTHORITY June 30, 2009 #12;OKLAHOMA STATE UNIVERSITY MEDICAL Authority Members Oklahoma State University Medical Authority Tulsa, Oklahoma We have audited the accompanying statements of financial position of the Oklahoma State University Medical Authority (the

  15. continued next page... Medical Education

    E-Print Network [OSTI]

    Chaudhuri, Sanjay

    in the healthcare scene. With the explosion of medical information and advances in medical technology, medical In this digital era of information explosion and rapid advances in medical sciences and medical technologyinside continued next page... Medical Education: Enhancing Learning in the Affective (Feeling

  16. Independent Assessment of the Savannah River Site High-Level Waste Salt Disposition Alternatives Evaluation

    SciTech Connect (OSTI)

    J. T. Case (DOE-ID); M. L. Renfro (INEEL)

    1998-12-01T23:59:59.000Z

    This report presents the results of the Independent Project Evaluation (IPE) Team assessment of the Westinghouse Savannah River Company High-Level Waste Salt Disposition Systems Engineering (SE) Team's deliberations, evaluations, and selections. The Westinghouse Savannah River Company concluded in early 1998 that production goals and safety requirements for processing SRS HLW salt to remove Cs-137 could not be met in the existing In-Tank Precipitation Facility as currently configured for precipitation of cesium tetraphenylborate. The SE Team was chartered to evaluate and recommend an alternative(s) for processing the existing HLW salt to remove Cs-137. To replace the In-Tank Precipitation process, the Savannah River Site HLW Salt Disposition SE Team downselected (October 1998) 140 candidate separation technologies to two alternatives: Small-Tank Tetraphenylborate (TPB) Precipitation (primary alternative) and Crystalline Silicotitanate (CST) Nonelutable Ion Exchange (backup alternative). The IPE Team, commissioned by the Department of Energy, concurs that both alternatives are technically feasible and should meet all salt disposition requirements. But the IPE Team judges that the SE Team's qualitative criteria and judgments used in their downselection to a primary and a backup alternative do not clearly discriminate between the two alternatives. To properly choose between Small-Tank TPB and CST Ion Exchange for the primary alternative, the IPE Team suggests the following path forward: Complete all essential R and D activities for both alternatives and formulate an appropriate set of quantitative decision criteria that will be rigorously applied at the end of the R and D activities. Concurrent conceptual design activities should be limited to common elements of the alternatives.

  17. GLASS FABRICATION AND PRODUCT CONSISTENCY TESTING OF LANTHANIDE BOROSILICATE FRIT X COMPOSITION FOR PLUTONIUM DISPOSITION

    SciTech Connect (OSTI)

    Marra, J

    2006-11-15T23:59:59.000Z

    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.

  18. DOE plutonium disposition study: Pu consumption in ALWRs. Volume 2, Final report

    SciTech Connect (OSTI)

    Not Available

    1993-05-15T23:59:59.000Z

    The Department of Energy (DOE) has contracted with Asea Brown Boveri-Combustion Engineering (ABB-CE) to provide information on the capability of ABB-CE`s System 80 + Advanced Light Water Reactor (ALWR) to transform, through reactor burnup, 100 metric tonnes (MT) of weapons grade plutonium (Pu) into a form which is not readily useable in weapons. This information is being developed as part of DOE`s Plutonium Disposition Study, initiated by DOE in response to Congressional action. This document Volume 2, provides a discussion of: Plutonium Fuel Cycle; Technology Needs; Regulatory Considerations; Cost and Schedule Estimates; and Deployment Strategy.

  19. DATA QUALITY OBJECTIVES SUMMARY REPORT FOR WASTE DISPOSITION OF FY2004 ISRM INJECTION & MONITORING WELLS

    SciTech Connect (OSTI)

    THOMAS, G.

    2004-03-03T23:59:59.000Z

    The purpose of this data quality objective (DQO) summary report is to develop a sampling plan for waste disposition of soil cuttings and other drilling-related wastes that will result from the drilling of 21 injection wells and one groundwater monitoring well west of the 184-D Powerhouse Ash Pit in the 100-D Area of the Hanford Site. The 21 In Situ Redox Manipulation (ISRM) wells will inject treatment solutions to assist in intercepting and preventing the discharge of a hexavalent chromium plume to the Columbia River. The monitoring well will help establish groundwater chemistry downgradient of the ISRM zone. The proposed well locations are shown.

  20. SAVANNAH RIVER SITE'S H-CANYON FACILITY: IMPACTS OF FOREIGN OBLIGATIONS ON SPECIAL NUCLEAR MATERIAL DISPOSITION

    SciTech Connect (OSTI)

    Magoulas, V.

    2013-06-03T23:59:59.000Z

    The US has a non-proliferation policy to receive foreign and domestic research reactor returns of spent fuel materials of US origin. These spent fuel materials are returned to the Department of Energy (DOE) and placed in storage in the L-area spent fuel basin at the Savannah River Site (SRS). The foreign research reactor returns fall subject to the 123 agreements for peaceful cooperation. These “123 agreements” are named after section 123 of the Atomic Energy Act of 1954 and govern the conditions of nuclear cooperation with foreign partners. The SRS management of these foreign obligations while planning material disposition paths can be a challenge.

  1. SAMPLE RESULTS FROM THE INTEGRATED SALT DISPOSITION PROGRAM MACROBATCH 5 TANK 21H QUALIFICATION SAMPLES

    SciTech Connect (OSTI)

    Peters, T.; Fink, S.

    2012-03-26T23:59:59.000Z

    Savannah River National Laboratory (SRNL) analyzed samples from Tank 21H in support of qualification of Macrobatch (Salt Batch) 5 for the Integrated Salt Disposition Project (ISDP). This document reports partial results of the analyses of samples of Tank 21H. No issues with the projected Salt Batch 5 strategy are identified. Results of the analyses of the Tank 21H samples from this report in conjunction with the findings of the previous report, indicates that the material does not display any unusual characteristics.

  2. A preliminary analysis of the reactor-based plutonium disposition alternative deployment schedules

    SciTech Connect (OSTI)

    Zurn, R.M.

    1997-09-01T23:59:59.000Z

    This paper discusses the preliminary analysis of the implementation schedules of the reactor-based plutonium disposition alternatives. These schedule analyses are a part of a larger process to examine the nine decision criteria used to determine the most appropriate method of disposing of U.S. surplus weapons plutonium. The preliminary analysis indicates that the mission durations for the reactor-based alternatives range from eleven years to eighteen years and the initial mission fuel assemblies containing surplus weapons-usable plutonium could be loaded into the reactors between nine and fourteen years after the Record of Decision.

  3. The Nuclear Material Focus Area Roadmapping Process Utilizing Environmental Management Complex-Wide Nuclear Material Disposition Pathways

    SciTech Connect (OSTI)

    Sala, D. R.; Furhman, P.; Smith, J. D.

    2002-02-26T23:59:59.000Z

    This paper describes the process that the Nuclear Materials Focus Area (NMFA) has developed and utilizes in working with individual Department of Energy (DOE) sites to identify, address, and prioritize research and development efforts in the stabilization, disposition, and storage of nuclear materials. By associating site technology needs with nuclear disposition pathways and integrating those with site schedules, the NMFA is developing a complex wide roadmap for nuclear material technology development. This approach will leverage technology needs and opportunities at multiple sites and assist the NMFA in building a defensible research and development program to address the nuclear material technology needs across the complex.

  4. MODELING OF PLUTONIUM RECOVERY AND DISCARD PROCESSES FOR THE PURPOSE OF SELECTING OPTIMUM (MINIMUM WASTE, COST AND DOSE) RESIDUE DISPOSITIONS

    SciTech Connect (OSTI)

    M. A. ROBINSON; M. B. KINKER; ET AL

    2001-04-01T23:59:59.000Z

    Researchers have developed a quantitative basis for disposition of actinide-bearing process residues. Research included the development of a technical rationale for determining when residues could be considered unattractive for proliferation purposes, and establishing plutonium-concentration-based discard ceilings of unimmobilized residues and richer discard ceilings for immobilized monolithic waste forms. Further quantitative analysis (process modeling) identifies the plutonium (Pu) concentration at which residues should be discarded to immobilization in order to minimize the quantifiable negative consequences of residue processing (cost, waste, dose). Results indicate that optimum disposition paths can be identified by process modeling, and that across-the-board discard decisions maximize negative consequences.

  5. Termination of Safeguards on ULWBR Material

    SciTech Connect (OSTI)

    Ivan R. Thomas; Ernest L. Laible

    2008-07-01T23:59:59.000Z

    The Department of Energy (DOE), Office of Environmental Management, has approved the disposition of 31 metric tons of Unirradiated Light Water Breeder Reactor (ULWBR) material in canisters stored within dry wells of the Underground Fuel Storage Facility at the Idaho Nuclear Technology and Engineering Center (INTEC). This unirradiated material consists primarily of ceramic pellets of thorium oxide in stainless steel cladding, but it also contains 300 kilograms of uranium that is 98 wt% U-233. The ULWBR material was not processed at the INTEC because it was incompatible with prior chemical separation schemes. Other economical recovery options have not been identified, and expressions of interest for consolidating the material with existing projects at other DOE sites have not been received. The U-233 could be used for producing the medical isotope Actinium-225, but the proof-of-principle demonstration and follow-on pilot program have not been developed to the point of requiring production quantities of U-233. Consequently, the selected disposition of the ULWBR material was burial as Low Level Waste at the Nevada Test Site (NTS), which required terminating safeguards controls for the contained Category II quantity of Attractiveness Level D special nuclear material (SNM). The requested termination followed the twelve point evaluation criteria of the Historical Defense Program Discard Guidance and included a security analysis for evaluating the risks of theft, diversion, and radiological sabotage associated with the material. Continuity of knowledge in the book inventory was assured by documenting that the original shipper’s measurements accurately reflected the quantities of materials received and that the ULWBR materials had remained under adequate physical protection and had been subject to periodic physical inventories. The method selected for substantiating the book values as the basis for terminating safeguards was the nondestructive assay used during physical inventories. Shipping arrangements included refurbishing a licensed cask to be reused over the duration of the termination process. An accompanying batching plan and shipping schedule were developed to accommodate multiple commercial shipments of Category III quantities of SNM in the selected cask, such that all canisters would be received at NTS prior to the expiration of the nonrenewable cask license.

  6. University Loaned Normal Uranium Slug Disposition Study: University survey responses. Predecisional draft

    SciTech Connect (OSTI)

    Becker, G.W. Jr.

    1992-09-01T23:59:59.000Z

    During the 1950`s and 1960`s, the Atomic Energy Commission loaned rejected natural uranium slugs from the Savannah River Site to United States universities for use in subcritical assemblies. Currently, there are sixty-two universities holding 91,798 slugs, containing about 167 metric tons of natural uranium. It was originally planned that the universities would return the material to Fernald when they no longer required it. Fernald has not received slugs since it was shut down in 1988. The Department of Energy`s Office of Weapons and Materials Planning requested that the Planning Support Group develop information to assist them in facilitating the return of the unwanted slugs to one or more of their facilities and develop alternatives for the ultimate disposition of this material. This supplemental report to the University Loaned Normal Uranium Slug Disposition Study documents responses to and summarizes the results of a survey of fifty-eight universities. University contacts and survey responses covering loaned slug descriptions, historical information, radiological data, current status, and plans and schedules are documented.

  7. DOE standard: Integration of environment, safety, and health into facility disposition activities. Volume 1: Technical standard

    SciTech Connect (OSTI)

    NONE

    1998-05-01T23:59:59.000Z

    This Department of Energy (DOE) technical standard (referred to as the Standard) provides guidance for integrating and enhancing worker, public, and environmental protection during facility disposition activities. It provides environment, safety, and health (ES and H) guidance to supplement the project management requirements and associated guidelines contained within DOE O 430.1A, Life-Cycle Asset Management (LCAM), and amplified within the corresponding implementation guides. In addition, the Standard is designed to support an Integrated Safety Management System (ISMS), consistent with the guiding principles and core functions contained in DOE P 450.4, Safety Management System Policy, and discussed in DOE G 450.4-1, Integrated Safety Management System Guide. The ISMS guiding principles represent the fundamental policies that guide the safe accomplishment of work and include: (1) line management responsibility for safety; (2) clear roles and responsibilities; (3) competence commensurate with responsibilities; (4) balanced priorities; (5) identification of safety standards and requirements; (6) hazard controls tailored to work being performed; and (7) operations authorization. This Standard specifically addresses the implementation of the above ISMS principles four through seven, as applied to facility disposition activities.

  8. Plutonium stabilization and disposition focus area, FY 1999 and FY 2000 multi-year program plan

    SciTech Connect (OSTI)

    NONE

    1998-03-01T23:59:59.000Z

    Consistent with the Environmental Management`s (EM`s) plan titled, ``Accelerating Cleanup: Paths to Closure``, and ongoing efforts within the Executive Branch and Congress, this Multi-Year Program Plan (MYPP) for the Plutonium Focus Area was written to ensure that technical gap projects are effectively managed and measured. The Plutonium Focus Area (PFA) defines and manages technology development programs that contribute to the effective stabilization of nuclear materials and their subsequent safe storage and final disposition. The scope of PFA activities includes the complete spectrum of plutonium materials, special isotopes, and other fissile materials. The PFA enables solutions to site-specific and complex-wide technology issues associated with plutonium remediation, stabilization, and preparation for disposition. The report describes the current technical activities, namely: Plutonium stabilization (9 studies); Highly enriched uranium stabilization (2 studies); Russian collaboration program (2 studies); Packaging and storage technologies (6 studies); and PFA management work package/product line (3 studies). Budget information for FY 1999 and FY 2000 is provided.

  9. Implementation of safeguards and security for fissile materials disposition reactor alternative facilities

    SciTech Connect (OSTI)

    Jaeger, C.D.; Duggan, R.A.; Tolk, K.M.

    1995-10-01T23:59:59.000Z

    A number of different disposition alternatives are being considered and include facilities which provide for long-ten-n and interim storage, convert and stabilize fissile materials for other disposition alternatives, immobilize fissile material in glass and/or ceramic material, fabricate fissile material into mixed oxide (MOX) fuel for reactors, use reactor based technologies to convert material into spent fuel, and dispose of fissile material using a number of geologic alternatives. Particular attention will be given to the reactor alternatives which include existing, partially completed, advanced or evolutionary LWRs and CANDU reactors. The various reactor alternatives are all very similar and include processing which converts Pu to a usable form for fuel fabrication, a MOX fuel fab facility located in either the US or in Europe, US LWRs or the CANDU reactors and ultimate disposal of spent fuel in a geologic repository. This paper focuses on how the objectives of reducing security risks and strengthening arms reduction and nonproliferation will be accomplished and the possible impacts of meeting these objectives on facility operations and design. Some of the areas in this paper include: (1) domestic and international safeguards requirements, (2) non-proliferation criteria and measures, (3) the threat, and (4) potential proliferation risks, the impacts on the facilities, and safeguards and security issues unique to the presence of Category 1 or strategic special nuclear material.

  10. SAMPLE RESULTS FROM THE INTEGRATED SALT DISPOSITION PROGRAM MACROBATCH 4 TANK 21H QUALIFICATION SAMPLES

    SciTech Connect (OSTI)

    Peters, T.; Fink, S.

    2011-06-22T23:59:59.000Z

    Savannah River National Laboratory (SRNL) analyzed samples from Tank 21H to qualify them for use in the Integrated Salt Disposition Program (ISDP) Batch 4 processing. All sample results agree with expectations based on prior analyses where available. No issues with the projected Salt Batch 4 strategy are identified. This revision includes additional data points that were not available in the original issue of the document, such as additional plutonium results, the results of the monosodium titanate (MST) sorption test and the extraction, scrub strip (ESS) test. This report covers the revision to the Tank 21H qualification sample results for Macrobatch (Salt Batch) 4 of the Integrated Salt Disposition Program (ISDP). A previous document covers initial characterization which includes results for a number of non-radiological analytes. These results were used to perform aluminum solubility modeling to determine the hydroxide needs for Salt Batch 4 to prevent the precipitation of solids. Sodium hydroxide was then added to Tank 21 and additional samples were pulled for the analyses discussed in this report. This work was specified by Task Technical Request and by Task Technical and Quality Assurance Plan (TTQAP).

  11. A comparative assessment of the economics of plutonium disposition including comparison with other nuclear fuel cycles

    SciTech Connect (OSTI)

    Williams, K.A.; Miller, J.W.; Reid, R.L.

    1997-05-01T23:59:59.000Z

    DOE has been evaluating three technologies for the disposition of approximately 50 metric tons of surplus plutonium from defense-related programs: reactors, immobilization, and deep boreholes. As part of the process supporting an early CY 1997 Record of Decision (ROD), a comprehensive assessment of technical viability, cost, and schedule has been conducted. Oak Ridge National Laboratory has managed and coordinated the life-cycle cost (LCC) assessment effort for this program. This paper discusses the economic analysis methodology and the results prior to ROD. Other objectives of the paper are to discuss major technical and economic issues that impact plutonium disposition cost and schedule. Also to compare the economics of a once-through weapons-derived MOX nuclear fuel cycle to other fuel cycles, such as those utilizing spent fuel reprocessing. To evaluate the economics of these technologies on an equitable basis, a set of cost estimating guidelines and a common cost-estimating format were utilized by all three technology teams. This paper also includes the major economic analysis assumptions and the comparative constant-dollar and discounted-dollar LCCs.

  12. Evaluation of alternatives for the disposition of surplus weapons-usable plutonium

    SciTech Connect (OSTI)

    Dyer, J.S.; Butler, J.C. [Univ. of Texas, Austin, TX (United States); Edmunds, T. [Lawrence Livermore National Lab., CA (United States)] [and others

    1997-04-04T23:59:59.000Z

    The Department of Energy Record of Decision (ROD) selected alternatives for disposition of surplus, weapons grade plutonium. A major objective of this decision was to prevent the proliferation of nuclear weapons. Other concerns addressed included economic, technical, institutional, schedule, environmental, and health and safety issues. The analysis reported here was conducted in parallel with technical, environmental, and nonproliferation analyses; it uses multiattribute utility theory to combine these considerations in order to facilitate an integrated evaluation of alternatives. This analysis is intended to provide additional insight regarding alternative evaluation and to assist in understanding the rationale for the choice of alternatives recommended in the ROD. Value functions were developed for objectives of disposition, and used to rank alternatives. Sensitivity analyses indicated that the ranking of alternatives for the base case was relatively insensitive to changes in assumptions over reasonable ranges. The analyses support the recommendation of the ROD to pursue parallel development of the vitrification immobilization alternative and the use of existing light water reactors alternative. 27 refs., 109 figs., 20 tabs.

  13. Optimization and implementation study of plutonium disposition using existing CANDU Reactors. Final report

    SciTech Connect (OSTI)

    NONE

    1996-09-01T23:59:59.000Z

    Since early 1994, the Department of Energy has been sponsoring studies aimed at evaluating the merits of disposing of surplus US weapons plutonium as Mixed Oxide (MOX) fuel in existing commercial Canadian Pressurized Heavy Water reactors, known as CANDU`s. The first report, submitted to DOE in July, 1994 (the 1994 Executive Summary is attached), identified practical and safe options for the consumption of 50 to 100 tons of plutonium in 25 years in some of the existing CANDU reactors operating the Bruce A generating station, on Lake Huron, about 300 km north east of Detroit. By designing the fuel and nuclear performance to operate within existing experience and operating/performance envelope, and by utilizing existing fuel fabrication and transportation facilities and methods, a low cost, low risk method for long term plutonium disposition was developed. In December, 1995, in response to evolving Mission Requirements, the DOE requested a further study of the CANDU option with emphasis on more rapid disposition of the plutonium, and retaining the early start and low risk features of the earlier work. This report is the result of that additional work.

  14. Disposition of Radioisotope Thermoelectric Generators Currently Located at the Oak Ridge National Laboratory - 12232

    SciTech Connect (OSTI)

    Glenn, J. [U.S. Department of Energy, Oak Ridge Operations Office, 200 Administrative Road, Oak Ridge, TN 37830 (United States); Patterson, J.; DeRoos, K. [SEC Federal Services Corporation (SEC), 2800 Solway Road, Knoxville, TN 37931 (United States); Patterson, J.E.; Mitchell, K.G. [Strata-G, LLC, 2027 Castaic Lane, Knoxville, TN 37932 (United States)

    2012-07-01T23:59:59.000Z

    Under the American Recovery and Reinvestment Act (ARRA), the U.S. Department of Energy (DOE) awarded SEC Federal Services Corporation (SEC) a 34-building demolition and disposal (D and D) project at the Oak Ridge National Laboratory (ORNL) that included the disposition of six Strontium (Sr-90) powered Radioisotope Thermoelectric Generators (RTGs) stored outside of ORNL Building 3517. Disposition of the RTGs is very complex both in terms of complying with disposal facility waste acceptance criteria (WAC) and U.S. Department of Transportation (DOT) requirements for packaging and transportation in commerce. Two of the RTGs contain elemental mercury which requires them to be Land Disposal Restrictions (LDR) compliant prior to disposal. In addition, all of the RTGs exceed the Class C waste concentration limits under Nuclear Regulatory Commission (NRC) Waste Classification Guidelines. In order to meet the LDR requirements and Nevada National Security Site (NNSS) WAC, a site specific treatability variance for mercury was submitted to the U.S. Environmental Protection Agency (EPA) to allow macro-encapsulation to be an acceptable treatment standard for elemental mercury. By identifying and confirming the design configuration of the mercury containing RTGs, the SEC team proved that the current configuration met the macro-encapsulation standard of 40 Code of Federal Regulations (CFR) 268.45. The SEC Team also worked with NNSS to demonstrate that all radioisotope considerations are compliant with the NNSS low-level waste (LLW) disposal facility performance assessment and WAC. Lastly, the SEC team determined that the GE2000 Type B cask met the necessary size, weight, and thermal loading requirements for five of the six RTGs. The sixth RTG (BUP-500) required a one-time DOT shipment exemption request due to the RTG's large size. The DOT exemption justification for the BUP-500 relies on the inherent robust construction and material make-up of the BUP- 500 RTG. DOE-ORO, SEC, and the entire SEC RTG team are nearing the conclusion of the Sr-90 RTG disposition challenge - a legacy now 50 years in the making. Over 600,000 Ci of Sr-90 waste await disposal and its removal from ORNL will mark an historical moment in the clean-up of the cold-war legacy in the ORNL central industrial area. Elimination (i.e., removal) of the RTGs will reduce security risks at ORNL and disposal will permanently eliminate security risks. The RTGs will eventually decay to benign levels within a reasonable timeframe relative to radiological risks posed by long-lived isotopes. The safety authorization basis at ORNL Building 3517 will be reduced enabling greater operational flexibility in future clean-out and D and D campaigns. Upon disposition the Department of Energy will realize reduced direct and indirect surveillance and maintenance costs that can be reapplied to accelerated and enhanced clean-up of the Oak Ridge Reservation. At present, waste profiles for the RTGs are developed and under review by NNSS RWAP staff and approval authorities. Disposition schedule is driven by the availability of compliant shipping casks necessary to safely transport the RTGs from ORNL to NNSS. The first disposal of the RCA RTG is expected in April 2012 and the remaining RTGs disposed in 2012 and 2013. (authors)

  15. Conventional Medical Screening Program

    Broader source: Energy.gov [DOE]

    Medical screening is a strategy used to identify diseases or conditions in a select population at an early stage, often before signs and symptoms develop, and to refer individuals with suspicious findings to their personal physician or a specialist for further testing, diagnosis, and treatment. The program is not intended to serve as a substitute for routine medical exams through an individual's personal physician.

  16. Medical Robots Surgical Assistants

    E-Print Network [OSTI]

    Pulfrey, David L.

    1 Medical Robots Surgical Assistants · Efficacy of Procedure ­ Accuracy ­ Longevity ­ Invasiveness · Augment human capabilities ­ Enabling new procedures ­ Time under anaesthetic #12;2 Surgical Robots) ­ Sensei (Hansen Medical) Autonomous Surgical Robots Robodoc.com #12;3 Guided Surgical Robots Makosurgical

  17. Animal Testing Medical Research

    E-Print Network [OSTI]

    Bech, Claus

    Arondsen Marit Gystøl #12;ZO-8091 Forsøksdyrlære Animal experiments in medical research NTNU ­ Norges ..................................................................................................................................................... 14 #12;ZO-8091 Forsøksdyrlære Animal experiments in medical research NTNU ­ Norges Teknisk have come from animal research. Animal research is defined as the use of non-human animals

  18. Medical School AdmissionsMedical School AdmissionsMedical School AdmissionsMedical School Admissions Monday, April 23rd

    E-Print Network [OSTI]

    Sheridan, Jennifer

    Medical School AdmissionsMedical School AdmissionsMedical School AdmissionsMedical School Vaughn Asst. Dir. of Admissions: Stanford University School of Medicine · Jennifer Haluzak Dir. of Admissions: The Medical College of Wisconsin · Kurt Hansen Asst. Dean of Admissions: UW School of Medicine

  19. Green River Locks and Dams 3, 4, 5, 6 and Barren River Lock and Dam 1 Disposition, Kentucky

    E-Print Network [OSTI]

    US Army Corps of Engineers

    until 1981 when it was closed due to declining boat traffic. Since the failure of Green River Dam 4 by the dams and the impacts if the pool were to be lost, either by demolition or failure of the lock andGreen River Locks and Dams 3, 4, 5, 6 and Barren River Lock and Dam 1 Disposition, Kentucky 16

  20. Sample results from the integrated salt disposition program macrobatch 6 tank 21H qualifications MST solids sample

    SciTech Connect (OSTI)

    Peters, T. B.

    2013-02-26T23:59:59.000Z

    Savannah River National Laboratory (SRNL) performed experiments on qualification material for use in the Integrated Salt Disposition Program (ISDP) Batch 6 processing. As part of this qualification work, SRNL performed an Actinide Removal Process (ARP) test. From this test, the residual monosodium titanate (MST) was analyzed for radionuclide uptake. The results of these analyses are reported and are within historical precedent.

  1. Generation!and!Disposition!of!Municipal!Solid!Waste! (MSW)!in!the!United!States!A!National!Survey!

    E-Print Network [OSTI]

    ! 1! ! Generation!and!Disposition!of!Municipal!Solid!Waste! (MSW of solid wastes and advance sustainable waste management in the U.S. to the level of several leading-2010, the Earth Engineering Center (EEC) of Columbia University conducted a bi- annual survey on Municipal Solid

  2. A little here, a little there, a fairly big problem everywhere: Small quantity site transuranic waste disposition alternatives

    SciTech Connect (OSTI)

    D. Luke; D. Parker; J. Moss; T. Monk (INEEL); L. Fritz (DOE-ID); B. Daugherty (SRS); K. Hladek (WM Federal Services Hanford); S. Kosiewicx (LANL)

    2000-02-27T23:59:59.000Z

    Small quantities of transuranic (TRU) waste represent a significant challenge to the waste disposition and facility closure plans of several sites in the Department of Energy (DOE) complex. This paper presents the results of a series of evaluations, using a systems engineering approach, to identify the preferred alternative for dispositioning TRU waste from small quantity sites (SQSs). The TRU waste disposition alternatives evaluation used semi-quantitative data provided by the SQSs, potential receiving sites, and the Waste Isolation Pilot Plant (WIPP) to select and recommend candidate sites for waste receipt, interim storage, processing, and preparation for final disposition of contact-handled (CH) and remote-handled (RH) TRU waste. The evaluations of only four of these SQSs resulted in potential savings to the taxpayer of $33 million to $81 million, depending on whether mobile systems could be used to characterize, package, and certify the waste or whether each site would be required to perform this work. Small quantity shipping sites included in the evaluation included the Battelle Columbus Laboratory (BCL), University of Missouri Research Reactor (MURR), Energy Technology Engineering Center (ETEC), and Mound Laboratory. Candidate receiving sites included the Idaho National Engineering and Environmental Laboratory (INEEL), the Savannah River Site (SRS), Los Alamos National Laboratory (LANL), Oak Ridge (OR), and Hanford. At least 14 additional DOE sites having TRU waste may be able to save significant money if cost savings are similar to the four evaluated thus far.

  3. A Little Here, A Little There, A Fairly Big Problem Everywhere: Small Quantity Site Transuranic Waste Disposition Alternatives

    SciTech Connect (OSTI)

    Luke, Dale Elden; Parker, Douglas Wayne; Moss, J.; Monk, Thomas Hugh; Fritz, Lori Lee; Daugherty, B.; Hladek, K.; Kosiewicx, S.

    2000-03-01T23:59:59.000Z

    Small quantities of transuranic (TRU) waste represent a significant challenge to the waste disposition and facility closure plans of several sites in the Department of Energy (DOE) complex. This paper presents the results of a series of evaluations, using a systems engineering approach, to identify the preferred alternative for dispositioning TRU waste from small quantity sites (SQSs). The TRU waste disposition alternatives evaluation used semi-quantitative data provided by the SQSs, potential receiving sites, and the Waste Isolation Pilot Plant (WIPP) to select and recommend candidate sites for waste receipt, interim storage, processing, and preparation for final disposition of contact-handled (CH) and remote-handled (RH) TRU waste. The evaluations of only four of these SQSs resulted in potential savings to the taxpayer of $33 million to $81 million, depending on whether mobile systems could be used to characterize, package, and certify the waste or whether each site would be required to perform this work. Small quantity shipping sites included in the evaluation included the Battelle Columbus Laboratory (BCL), University of Missouri Research Reactor (MURR), Energy Technology Engineering Center (ETEC), and Mound. Candidate receiving sites included the Idaho National Engineering and Environmental Laboratory (INEEL), the Savannah River Site (SRS), Los Alamos National Laboratory (LANL), Oak Ridge (OR), and Hanford. At least 14 additional DOE sites having TRU waste may be able to save significant money if cost savings are similar to the four evaluated thus far.

  4. A Roadmap and Discussion of Issues for Physics Analyses Required to Support Plutonium Disposition in VVER-1000 Reactors

    SciTech Connect (OSTI)

    Primm, R.T.; Drischler, J.D.; Pavlovichev, A.M. Styrine, Y.A.

    2000-06-01T23:59:59.000Z

    The purpose of this report is to document the physics analyses that must be performed to successfully disposition weapons-usable plutonium in VVER-1000 reactors in the Russian Federation. The report is a document to support programmatic and financial planning. It does not include documentation of the technical procedures by which physics analyses are performed, nor are the results of any analyses included.

  5. Dispositional reflections 

    E-Print Network [OSTI]

    Brummans, Boris H. J. M.

    2005-02-17T23:59:59.000Z

    In this dissertation, I explicate how scholars implicate themselves in the subfield of organizational communication studies by engaging in antinomic language-games which make the conduct of research (and textwork in particular) possible. My...

  6. Dispositional reflections

    E-Print Network [OSTI]

    Brummans, Boris H. J. M.

    2005-02-17T23:59:59.000Z

    analysis suggests that the studied scholars enact these games to understand a more or less common object of knowledge, but also to constitute a more or less identifiable position in this given social space. Reflection on the ontological complicity between...

  7. End of FY10 report - used fuel disposition technical bases and lessons learned : legal and regulatory framework for high-level waste disposition in the United States.

    SciTech Connect (OSTI)

    Weiner, Ruth F.; Blink, James A. (Lawrence Livermore National Laboratory, Livermore, CA); Rechard, Robert Paul; Perry, Frank (Los Alamos National Laboratory, Los Alamos, NM); Jenkins-Smith, Hank C. (University of Oklahoma, Norman, OK); Carter, Joe (Savannah River Nuclear Solutions, Aiken, SC); Nutt, Mark (Argonne National Laboratory, Argonne, IL); Cotton, Tom (Complex Systems Group, Washington DC)

    2010-09-01T23:59:59.000Z

    This report examines the current policy, legal, and regulatory framework pertaining to used nuclear fuel and high level waste management in the United States. The goal is to identify potential changes that if made could add flexibility and possibly improve the chances of successfully implementing technical aspects of a nuclear waste policy. Experience suggests that the regulatory framework should be established prior to initiating future repository development. Concerning specifics of the regulatory framework, reasonable expectation as the standard of proof was successfully implemented and could be retained in the future; yet, the current classification system for radioactive waste, including hazardous constituents, warrants reexamination. Whether or not consideration of multiple sites are considered simultaneously in the future, inclusion of mechanisms such as deliberate use of performance assessment to manage site characterization would be wise. Because of experience gained here and abroad, diversity of geologic media is not particularly necessary as a criterion in site selection guidelines for multiple sites. Stepwise development of the repository program that includes flexibility also warrants serious consideration. Furthermore, integration of the waste management system from storage, transportation, and disposition, should be examined and would be facilitated by integration of the legal and regulatory framework. Finally, in order to enhance acceptability of future repository development, the national policy should be cognizant of those policy and technical attributes that enhance initial acceptance, and those policy and technical attributes that maintain and broaden credibility.

  8. Quick-release medical tape

    E-Print Network [OSTI]

    Laulicht, Bryan E.

    Medical tape that provides secure fixation of life-sustaining and -monitoring devices with quick, easy, damage-free removal represents a longstanding unmet medical need in neonatal care. During removal of current medical ...

  9. December 2009 ARMY MEDICAL LOGISTICS

    E-Print Network [OSTI]

    US Army Corps of Engineers

    FM 4-02.1 December 2009 ARMY MEDICAL LOGISTICS DISTRIBUTION RESTRICTION: Approved for public Medical Logistics Contents Page PREFACE...................................................................................................ix Chapter 1 OVERVIEW OF ARMY MEDICAL LOGISTICS................................................. 1-1 Section

  10. GLASS FABRICATION AND PRODUCT CONSISTENCY TESTING OF LANTHANIDE BOROSHILICATE FRIT X COMPOSITION FOR PLUTONIUM DISPOSITION

    SciTech Connect (OSTI)

    Marra, J

    2006-11-21T23:59:59.000Z

    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. Characterization of the quenched Pu Frit X glass prior to testing revealed that some crystalline plutonium oxide was present in the glass. The crystalline particles had a disklike morphology and likely formed via coarsening of particles in areas compositionally enriched in plutonium. Similar results had also been observed in previous Pu Frit B studies. Isothermal 1250 C heat-treated Pu Frit X glasses showed two different crystalline phases (PuO{sub 2} and Nd{sub 2}Hf{sub 2}O{sub 7}), as well as a peak shift in the XRD spectra that is likely due to a solid solution phase PuO{sub 2}-HfO{sub 2} formation. Micrographs of this glass showed a clustering of some of the crystalline phases. Pu Frit X glass subjected to the can-in-canister heating profile also displayed the two PuO{sub 2} and Nd{sub 2}Hf{sub 2}O{sub 7} phases from XRD analysis. Additional micrographs indicate crystalline phases in this glass were of varying forms (a spherical PuO{sub 2} phase that appeared to range in size from submicron to {approx}5 micron, a dendritic-type phase that was comprised of mixed lanthanides and plutonium, and a minor phase that contained Pu and Hf), and clustering of the phases was also observed.

  11. Site Selection for Surplus Plutonium Disposition Facilities at the Savannah River Site

    SciTech Connect (OSTI)

    Wike, L.D.

    2000-08-17T23:59:59.000Z

    A site selection study was conducted to evaluate locations for the proposed Surplus Plutonium Disposition Facilities. Facilities to be located include the Mixed Oxide (MOX) Fuel Fabrication Facility, the Pit Disassembly and Conversion Facility (PDCF), and the Plutonium Immobilization Project (PIP) facility. Objectives of the study include: (1) Confirm that the Department of Energy (DOE) selected locations for the MOX and PDCF were suitable based on selected siting criteria, (2) Recommend a site in the vicinity of F Area that is suitable for the PIP, and (3) Identify alternative suitable sites for one or more of these facilities in the event that further geotechnical characterization or other considerations result in disqualification of a currently proposed site.

  12. Development of a fresh MOX fuel transport package for disposition of weapons plutonium

    SciTech Connect (OSTI)

    Ludwig, S.B.; Pope, R.B.; Shappert, L.B.; Michelhaugh, R.D. [Oak Ridge National Lab., TN (United States); Chae, S.M. [Lockheed Martin Energy Systems, Inc., Oak Ridge, TN (United States)

    1998-11-01T23:59:59.000Z

    The US Department of Energy announced its Record of Decision on January 14, 1997, to embark on a dual-track approach for disposition of surplus weapons-usable plutonium using immobilization in glass or ceramics and burning plutonium as mixed-oxide (MOX) fuel in reactors. In support of the MOX fuel alternative, Oak Ridge National Laboratory initiated development of conceptual designs for a new package for transporting fresh (unirradiated) MOX fuel assemblies between the MOX fabrication facility and existing commercial light-water reactors in the US. This paper summarizes progress made in development of new MOX transport package conceptual designs. The development effort has included documentation of programmatic and technical requirements for the new package and development and analysis of conceptual designs that satisfy these requirements.

  13. GLASS FABRICATION AND PRODUCT CONSISTENCY TESTING OF LANTHANIDE BOROSILICATE FRIT B COMPOSITION FOR PLUTONIUM DISPOSITION

    SciTech Connect (OSTI)

    Marra, J

    2006-01-19T23:59:59.000Z

    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 a leading candidate 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. 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. Therefore, the objectives of this present task were to fabricate plutonium loaded LaBS Frit B glass and perform additional 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 B 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) and for additional performance testing at Argonne National Laboratory (ANL) and Pacific Northwest National Laboratory (PNNL). The glass was 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 with varying exposed surface area and test durations. The leachates from these tests 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. The leached solids from select PCTs were examined in an attempt to evaluate the Pu and neutron absorber release behavior from the glass and to identify the formation of alteration phases on the glass surface. Characterization of the glass prior to testing revealed that some undissolved plutonium oxide was present in the glass. The undissolved particles had a disk-like morphology and likely formed via coarsening of particles in areas compositionally enriched in plutonium. Similar disk-like PuO{sub 2} phases were observed in previous LaBS glass testing at PNNL. In that work, researchers concluded that plutonium formed with this morphology as a result of the leaching process. It was more likely that the presence of the plutonium oxide crystals in the PNNL testing was a result of glass fabrication. A series of PCTs were conducted at 90 C in ASTM Type 1 water. The PCT-Method A (PCT-A) was conducted to compare the Pu LaBS Frit B glass durability to current requirements for High Level Waste (HLW) glass in a geologic repository. The PCT-A test has a strict protocol and is designed to specifically be used to evaluate whether the chemical durability and elemental release characteristics of a nuclear waste glass have been consistently controlled during production and, thus, meet the repository acceptance requirements. The PCT-A results on the Pu containing LaBS Frit B glass showed that the glass was very durable with a normalized elemental release value for boron of approximately 0.02 g/L. This boron release value was better than two orders of magnitude better from a boron release standpoint than the current Environmental Assessment (EA) glass used for repository acceptance. The boron release value for EA glass is 16.7 g/L.

  14. Engineering evaluation of alternatives for the disposition of Niagara Falls Storage Site, its residues and wastes

    SciTech Connect (OSTI)

    Not Available

    1984-01-01T23:59:59.000Z

    The final disposition scenarios selected by DOE for assessment in this document are consistent with those stated in the Notice of Intent to prepare an Environmental Impact Statement (EIS) for the Niagara Falls Storage Site (NFSS) (DOE, 1983d) and the modifications to the alternatives resulting from the public scoping process. The scenarios are: take no action beyond interim remedial measures other than maintenance and surveillance of the NFSS; retain and manage the NFSS as a long-term waste management facility for the wastes and residues on the site; decontaminate, certify, and release the NFSS for other use, with long-term management of the wastes and residues at other DOE sites; and partially decontaminate the NFSS by removal and transport off site of only the more radioactive residues, and upgrade containment of the remaining wastes and residues on site. The objective of this document is to present to DOE the conceptual engineering, occupational radiation exposure, construction schedule, maintenance and surveillance requirements, and cost information relevant to design and implementation of each of the four scenarios. The specific alternatives within each scenario used as the basis for discussion in this document were evaluated on the bases of engineering considerations, technical feasibility, and regulatory requirements. Selected alternatives determined to be acceptable for each of the four final disposition scenarios for the NFSS were approved by DOE to be assessed and costed in this document. These alternatives are also the subject of the EIS for the NFSS currently being prepared by Argonne National Laboratory (ANL). 40 figures, 38 tables.

  15. Hanford MOX fuel lead assemblies data report for the surplus plutonium disposition environmental impact statement

    SciTech Connect (OSTI)

    O`Connor, D.G.; Fisher, S.E.; Holdaway, R. [and others

    1998-08-01T23:59:59.000Z

    The purpose of this document is to support the US Department of Energy (DOE) Fissile Materials Disposition Program`s preparation of the draft surplus plutonium disposition environmental impact statement. This is one of several responses to data call requests for background information on activities associated with the operation of the lead assembly (LA) mixed-oxide (MOX) fuel fabrication facility. DOE-MD requested that the DOE Site Operations Offices nominate DOE sites that meet established minimum requirements that could produce MOX LAs. Six initial site combinations were proposed: (1) Argonne National Laboratory-West (ANL-W) with support from Idaho National Engineering and Environmental Laboratory (INEEL), (2) Hanford, (3) Los Alamos National Laboratory (LANL) with support from Pantex, (4) Lawrence Livermore National Laboratory (LLNL), (5) Oak Ridge Reservation (ORR), and (6) Savannah River Site (SRS). After further analysis by the sites and DOE-MD, five site combinations were established as possible candidates for producing MOX LAs: (1) ANL-W with support from INEEL, (2) Hanford, (3) LANL, (4) LLNL, and (5) SRS. Hanford has proposed an LA MOX fuel fabrication approach that would be done entirely inside an S and S Category 1 area. An alternate approach would allow fabrication of fuel pellets and assembly of fuel rods in an S and S Category 1 facility. In all, a total of three LA MOX fuel fabrication options were identified by Hanford that could accommodate the program. In every case, only minor modification would be required to ready any of the facilities to accept the equipment necessary to accomplish the LA program.

  16. A Methodology for the Analysis and Selection of Alternative for the Disposition of Surplus Plutonium

    SciTech Connect (OSTI)

    NONE

    1999-08-31T23:59:59.000Z

    The Department of Energy (DOE) - Office of Fissile Materials Disposition (OFMD) has announced a Record of Decision (ROD) selecting alternatives for disposition of surplus plutonium. A major objective of this decision was to further U.S. efforts to prevent the proliferation of nuclear weapons. Other concerns that were addressed include economic, technical, institutional, schedule, environmental, and health and safety issues. The technical, environmental, and nonproliferation analyses supporting the ROD are documented in three DOE reports [DOE-TSR 96, DOE-PEIS 96, and DOE-NN 97, respectively]. At the request of OFMD, a team of analysts from the Amarillo National Resource Center for Plutonium (ANRCP) provided an independent evaluation of the alternatives for plutonium that were considered during the evaluation effort. This report outlines the methodology used by the ANRCP team. This methodology, referred to as multiattribute utility theory (MAU), provides a structure for assembling results of detailed technical, economic, schedule, environment, and nonproliferation analyses for OFMD, DOE policy makers, other stakeholders, and the general public in a systematic way. The MAU methodology has been supported for use in similar situations by the National Research Council, an agency of the National Academy of Sciences.1 It is important to emphasize that the MAU process does not lead to a computerized model that actually determines the decision for a complex problem. MAU is a management tool that is one component, albeit a key component, of a decision process. We subscribe to the philosophy that the result of using models should be insights, not numbers. The MAU approach consists of four steps: (1) identification of alternatives, objectives, and performance measures, (2) estimation of the performance of the alternatives with respect to the objectives, (3) development of value functions and weights for the objectives, and (4) evaluation of the alternatives and sensitivity analysis. These steps are described below.

  17. LANL MOX fuel lead assemblies data report for the surplus plutonium disposition environmental impact statement

    SciTech Connect (OSTI)

    Fisher, S.E.; Holdaway, R.; Ludwig, S.B. [and others

    1998-08-01T23:59:59.000Z

    The purpose of this document is to support the US Department of Energy (DOE) Fissile Materials Disposition Program`s preparation of the draft surplus plutonium disposition environmental impact statement. This is one of several responses to data call requests for background information on activities associated with the operation of the lead assembly (LA) mixed-oxide (MOX) fuel fabrication facility. LANL has proposed an LA MOX fuel fabrication approach that would be done entirely inside an S and S Category 1 area. This includes receipt and storage of PuO{sub 2} powder, fabrication of MOX fuel pellets, assembly of fuel rods and bundles, and shipping of the packaged fuel to a commercial reactor site. Support activities will take place within both Category 1 and 2 areas. Technical Area (TA) 55/Plutonium Facility 4 will be used to store the bulk PuO{sub 2} powder, fabricate MOX fuel pellets, assemble rods, and store fuel bundles. Bundles will be assembled at a separate facility, several of which have been identified as suitable for that activity. The Chemistry and Metallurgy Research Building (at TA-3) will be used for analytical chemistry support. Waste operations will be conducted in TA-50 and TA-54. Only very minor modifications will be needed to accommodate the LA program. These modifications consist mostly of minor equipment upgrades. A commercial reactor operator has not been identified for the LA irradiation. Postirradiation examination (PIE) of the irradiated fuel will take place at either Oak Ridge National Laboratory or ANL-W. The only modifications required at either PIE site would be to accommodate full-length irradiated fuel rods. Results from this program are critical to the overall plutonium distribution schedule.

  18. Idaho High-Level Waste & Facilities Disposition, Final Environmental Impact Statement

    SciTech Connect (OSTI)

    N /A

    2002-10-11T23:59:59.000Z

    This EIS analyzes the potential environmental consequences of alternatives for managing high-level waste (HLW) calcine, mixed transuranic waste/sodium bearing waste (SBW) and newly generated liquid waste at the Idaho National Engineering and Environmental Laboratory (INEEL) in liquid and solid forms. This EIS also analyzes alternatives for the final disposition of HLW management facilities at the INEEL after their missions are completed. After considering comments on the Draft EIS (DOE/EIS-0287D), as well as information on available treatment technologies, DOE and the State of Idaho have identified separate preferred alternatives for waste treatment. DOE's preferred alternative for waste treatment is performance based with the focus on placing the wastes in forms suitable for disposal. Technologies available to meet the performance objectives may be chosen from the action alternatives analyzed in this EIS. The State of Idaho's Preferred Alternative for treating mixed transuranic waste/SBW and calcine is vitrification, with or without calcine separations. Under both the DOE and State of Idaho preferred alternatives, newly generated liquid waste would be segregated after 2005, stored or treated directly and disposed of as low-level, mixed low-level, or transuranic waste depending on its characteristics. The objective of each preferred alternative is to enable compliance with the legal requirement to have INEEL HLW road ready by a target date of 2035. Both DOE and the State of Idaho have identified the same preferred alternative for facilities disposition, which is to use performance-based closure methods for existing facilities and to design new facilities consistent with clean closure methods.

  19. DOE plutonium disposition study: Analysis of existing ABB-CE Light Water Reactors for the disposition of weapons-grade plutonium. Final report

    SciTech Connect (OSTI)

    Not Available

    1994-06-01T23:59:59.000Z

    Core reactivity and basic fuel management calculations were conducted on the selected reactors (with emphasis on the System 80 units as being the most desirable choice). Methods used were identical to those reported in the Evolutionary Reactor Report. From these calculations, the basic mission capability was assessed. The selected reactors were studied for modification, such as the addition of control rod nozzles to increase rod worth, and internals and control system modifications that might also be needed. Other system modifications studied included the use of enriched boric acid as soluble poison, and examination of the fuel pool capacities. The basic geometry and mechanical characteristics, materials and fabrication techniques of the fuel assemblies for the selected existing reactors are the same as for System 80+. There will be some differences in plutonium loading, according to the ability of the reactors to load MOX fuel. These differences are not expected to affect licensability or EPA requirements. Therefore, the fuel technology and fuel qualification sections provided in the Evolutionary Reactor Report apply to the existing reactors. An additional factor, in that the existing reactor availability presupposes the use of that reactor for the irradiation of Lead Test Assemblies, is discussed. The reactor operating and facility licenses for the operating plants were reviewed. Licensing strategies for each selected reactor were identified. The spent fuel pool for the selected reactors (Palo Verde) was reviewed for capacity and upgrade requirements. Reactor waste streams were identified and assessed in comparison to uranium fuel operations. Cost assessments and schedules for converting to plutonium disposition were estimated for some of the major modification items. Economic factors (incremental costs associated with using weapons plutonium) were listed and where possible under the scope of work, estimates were made.

  20. The Relationship of Student Dispositions and Teacher Characteristics with the Mathematics Achievement of Students in Lebanon and Six Arab Countries in TIMSS 2007.

    E-Print Network [OSTI]

    Younes, Rayya

    2013-03-22T23:59:59.000Z

    The present study is divided into two parts. The first part examines the performance of Lebanese students in public and private schools in Lebanon in 8th grade using the TIMSS 2007 data. The effects of students’ dispositions and teacher...

  1. Transportation of medical isotopes

    SciTech Connect (OSTI)

    Nielsen, D.L.

    1997-11-19T23:59:59.000Z

    A Draft Technical Information Document (HNF-1855) is being prepared to evaluate proposed interim tritium and medical isotope production at the Fast Flux Test Facility (FFTF). This assessment examines the potential health and safety impacts of transportation operations associated with the production of medical isotopes. Incident-free and accidental impacts are assessed using bounding source terms for the shipment of nonradiological target materials to the Hanford Site, the shipment of irradiated targets from the FFTF to the 325 Building, and the shipment of medical isotope products from the 325 Building to medical distributors. The health and safety consequences to workers and the public from the incident-free transportation of targets and isotope products would be within acceptable levels. For transportation accidents, risks to works and the public also would be within acceptable levels. This assessment is based on best information available at this time. As the medical isotope program matures, this analysis will be revised, if necessary, to support development of a final revision to the Technical Information Document.

  2. Summary report of the screening process to determine reasonable alternatives for long-term storage and disposition of weapons-usable fissile materials

    SciTech Connect (OSTI)

    NONE

    1995-03-29T23:59:59.000Z

    Significant quantities of weapons-usable fissile materials (primarily plutonium and highly enriched uranium) have become surplus to national defense needs both in the US and Russia. These stocks of fissile materials pose significant dangers to national and international security. The dangers exist not only in the potential proliferation of nuclear weapons but also in the potential for environmental, safety and health consequences if surplus fissile materials are not properly managed. As announced in the Notice of Intent (NOI) to prepare a Programmatic Environmental Impact Statement (PEIS), the Department of Energy is currently conducting an evaluation process for disposition of surplus weapons-usable fissile materials determined surplus to National Security needs, and long-term storage of national security and programmatic inventories, and surplus weapons-usable fissile materials that are not able to go directly from interim storage to disposition. An extensive set of long-term storage and disposition options was compiled. Five broad long-term storage options were identified; thirty-seven options were considered for plutonium disposition; nine options were considered for HEU disposition; and eight options were identified for Uranium-233 disposition. Section 2 discusses the criteria used in the screening process. Section 3 describes the options considered, and Section 4 provides a detailed summary discussions of the screening results.

  3. Nonproliferation and arms control assessment of weapons-usable fissile material storage and excess plutonium disposition alternatives

    SciTech Connect (OSTI)

    NONE

    1997-01-01T23:59:59.000Z

    This report has been prepared by the Department of Energy`s Office of Arms Control and Nonproliferation (DOE-NN) with support from the Office of Fissile Materials Disposition (DOE-MD). Its purpose is to analyze the nonproliferation and arms reduction implications of the alternatives for storage of plutonium and HEU, and disposition of excess plutonium, to aid policymakers and the public in making final decisions. While this assessment describes the benefits and risks associated with each option, it does not attempt to rank order the options or choose which ones are best. It does, however, identify steps which could maximize the benefits and mitigate any vulnerabilities of the various alternatives under consideration.

  4. SAMPLE RESULTS FROM THE INTEGRATED SALT DISPOSITION PROGRAM MACROBATCH 5 TANK 21H QUALIFICATION MST, ESS AND PODD SAMPLES

    SciTech Connect (OSTI)

    Peters, T.; Fink, S.

    2012-04-24T23:59:59.000Z

    Savannah River National Laboratory (SRNL) performed experiments on qualification material for use in the Integrated Salt Disposition Program (ISDP) Batch 5 processing. This qualification material was a composite created from recent samples from Tank 21H and archived samples from Tank 49H to match the projected blend from these two tanks. Additionally, samples of the composite were used in the Actinide Removal Process (ARP) and extraction-scrub-strip (ESS) tests. ARP and ESS test results met expectations. A sample from Tank 21H was also analyzed for the Performance Objectives Demonstration Document (PODD) requirements. SRNL was able to meet all of the requirements, including the desired detection limits for all the PODD analytes. This report details the results of the Actinide Removal Process (ARP), Extraction-Scrub-Strip (ESS) and Performance Objectives Demonstration Document (PODD) samples of Macrobatch (Salt Batch) 5 of the Integrated Salt Disposition Program (ISDP).

  5. GLASS FABRICATION AND PRODUCT CONSISTENCY TESTING OF LANTHANIDE BOROSILICATE GLASS FOR PLUTONIUM DISPOSITION

    SciTech Connect (OSTI)

    Crawford, C; James Marra, J; Ned Bibler, N

    2007-02-12T23:59:59.000Z

    The Department of Energy Office of Environmental Management (DOE/EM) plans to conduct the Plutonium Disposition Project at the Savannah River Site (SRS) in Aiken, SC, to disposition excess weapons-usable plutonium. A plutonium glass waste form is a leading candidate for immobilization of the plutonium for subsequent disposition in a geologic repository. The objectives of this present task were to fabricate plutonium-loaded lanthanide borosilicate (LaBS) Frit B glass and perform testing to provide near-term data that will increase confidence that LaBS glass product is suitable for disposal in the proposed Federal 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 B composition with a 9.5 wt% PuO{sub 2} loading was prepared for testing. Glass was prepared to support glass durability testing via the ASTM Product Consistency Testing (PCT) at Savannah River National Laboratory (SRNL). The glass was characterized with X-ray diffraction (XRD) and scanning electron microscopy coupled with energy dispersive spectroscopy (SEM/EDS) prior to performance testing. This characterization revealed some crystalline PuO{sub 2} inclusions with disk-like morphology present in the as fabricated, quench-cooled glass. A series of PCTs was conducted at SRNL with varying exposed surface area and test durations. Filtered leachates from these tests were analyzed to determine the dissolved concentrations of key elements. The leachate solutions were also ultrafiltered to quantify colloid formation. Leached solids from select PCTs were examined in an attempt to evaluate the Pu and neutron absorber release behavior from the glass and to investigate formation of alteration phases on the glass surface. A series of PCTs was conducted at 90 C in ASTM Type 1 water to compare the Pu LaBS Frit B glass durability to current requirements for High Level Waste (HLW) glass in a geologic repository. The PCT (7-day static test with powdered glass) results on the Pu-containing LaBS Frit B glass at SA/V of {approx} 2000 m{sup -1} showed that the glass was very durable with an average normalized elemental release value for boron of 0.013 g/m{sup 2}. This boron release value is {approx} 640X lower than normalized boron release from current Environmental Assessment (EA) glass used for repository acceptance. The PCT-B (7, 14, 28 and 56-day, static test with powdered glass) normalized elemental releases were similar to the normalized elemental release values from PCT-A testing, indicating that the LaBS Frit B glass is very durable as measured by the PCT. Normalized plutonium releases were essentially the same within the analytical uncertainty of the ICP-MS methods used to quantify plutonium in the 0.45 {micro}m-filtered leachates and ultra-filtered leachates, indicating that colloidal plutonium species do not form under the PCT conditions used in this study.

  6. Los Alamos National Laboratory summary plan to fabricate mixed oxide lead assemblies for the fissile material disposition program

    SciTech Connect (OSTI)

    Buksa, J.J.; Eaton, S.L.; Trellue, H.R.; Chidester, K.; Bowidowicz, M.; Morley, R.A.; Barr, M.

    1997-12-01T23:59:59.000Z

    This report summarizes an approach for using existing Los Alamos National Laboratory (Laboratory) mixed oxide (MOX) fuel-fabrication and plutonium processing capabilities to expedite and assure progress in the MOX/Reactor Plutonium Disposition Program. Lead Assembly MOX fabrication is required to provide prototypic fuel for testing in support of fuel qualification and licensing requirements. It is also required to provide a bridge for the full utilization of the European fabrication experience. In part, this bridge helps establish, for the first time since the early 1980s, a US experience base for meeting the safety, licensing, safeguards, security, and materials control and accountability requirements of the Department of Energy and Nuclear Regulatory Commission. In addition, a link is needed between the current research and development program and the production of disposition mission fuel. This link would also help provide a knowledge base for US regulators. Early MOX fabrication and irradiation testing in commercial nuclear reactors would provide a positive demonstration to Russia (and to potential vendors, designers, fabricators, and utilities) that the US has serious intent to proceed with plutonium disposition. This report summarizes an approach to fabricating lead assembly MOX fuel using the existing MOX fuel-fabrication infrastructure at the Laboratory.

  7. X-ray fluorescence spectroscopy for the elemental analysis of plutonium-bearing materials for the materials disposition program

    SciTech Connect (OSTI)

    Voit, S.L.; Boerigter, S.T.; Rising, T.L.

    1997-11-01T23:59:59.000Z

    The US Fissile Materials Disposition (MD) program will disposition about 50 MT of plutonium in the next century. Both of the alternative technologies for disposition, MOX Fuel and Immobilization require knowledge of the incoming composition to 1--5 wt%. Wavelength Dispersive X-Ray Fluorescence (WDXRF) systems, a common elemental analysis technology with a variety of industrial applications and commercial vendors, can readily achieve this level of characterization. Since much of the excess plutonium will be packaged in a long-term storage container as part of the DOE Environmental Management (DOE-EM) program to stabilize plutonium-bearing materials, the characterization system must be implemented during the packaging process. The authors describe a preliminary design for the integration of the WDXRF system into the packaging system to be used at the Rocky Flats site. The Plutonium Stabilization and Packaging System (PuSPS), coupled with the WDXRF characterization system will provide MD with stabilized plutonium-bearing excess material that can be more readily fed to an immobilization facility. The overall added expense to the MD program of obtaining analytical information after materials have been packaged in long-term storage containers could far exceed the expense of implementing XRF analysis during the packaging process.

  8. Evaluation of Possible Surrogates for Validation of the Oxidation Furnace for the Plutonium Disposition Project

    SciTech Connect (OSTI)

    Duncan, A.

    2007-12-31T23:59:59.000Z

    The Plutonium Disposition project (PuD) is considering an alternative furnace design for direct metal oxidation (DMO) of plutonium metal to use as a feed for potential disposition routes. The proposed design will use a retort to oxidize the feed at temperatures up to 500 C. The atmosphere will be controlled using a metered mixture of oxygen, helium and argon to control the oxidation at approximately 400 torr. Since plutonium melts at 664 C, and may potentially react with retort material to form a lower melting point eutectic, the oxidation process will be controlled by metering the flow of oxygen to ensure that the bulk temperature of the material does not exceed this temperature. A batch processing time of <24 hours is desirable to meet anticipated furnace throughput requirements. The design project includes demonstration of concept in a small-scale demonstration test (i.e., small scale) and validation of design in a full-scale test. These tests are recommended to be performed using Pu surrogates due to challenges in consideration of the nature of plutonium and operational constraints required when handling large quantities of accountable material. The potential for spreading contamination and exposing workers to harmful levels of cumulative radioactive dose are motivation to utilize non-radioactive surrogates. Once the design is demonstrated and optimized, implementation would take place in a facility designed to accommodate these constraints. Until then, the use of surrogates would be a safer, less expensive option for the validation phase of the project. This report examines the potential for use of surrogates in the demonstration and validation of the DMO furnace for PuD. This report provides a compilation of the technical information and process requirements for the conversion of plutonium metal to oxide by burning in dry environments. Several potential surrogates were evaluated by various criteria in order to select a suitable candidate for large scale demonstration. First, the structure of the plutonium metal/oxide interface was compared to potential surrogates. Second the data for plutonium oxidation kinetics were reviewed and rates for oxidation were compared with surrogates. The criteria used as a basis for recommendation was selected in order to provide a reasonable oxidation rate during the validation phase. Several reference documents were reviewed and used to compile the information in this report. Since oxidation of large monolithic pieces of plutonium in 75% oxygen is the preferable oxidizing atmosphere for the intended process, this report does not focus on the oxidation of powders, but focuses instead on larger samples in flowing gas.

  9. Supplement Analysis for the Idaho High-Level Waste and Facilities Disposition Final Environmental Impact Statement

    SciTech Connect (OSTI)

    N /A

    2005-06-30T23:59:59.000Z

    In October 2002, DOE issued the Idaho High-Level Waste and Facilities Disposition Final Environmental Impact Statement (Final EIS) (DOE 2002) that provided an analysis of the potential environmental consequences of alternatives/options for the management and disposition of Sodium Bearing Waste (SBW), High-Level Waste (HL W) calcine, and HLW facilities at the Idaho Nuclear Technology and Engineering Center (INTEC) located at the Idaho National Engineering and Environmental Laboratory (INEEL), now known as the Idaho National Laboratory (INL) and referred to hereafter as the Idaho Site. Subsequent to the issuance of the Final EIS, DOE included the requirement for treatment of SBW in the Request for Proposals for Environmental Management activities on the Idaho Site. The new Idaho Cleanup Project (ICP) Contractor identified Steam Reforming as their proposed method to treat SBW; a method analyzed in the Final EIS as an option to treat SBW. The proposed Steam Reforming process for SBW is the same as in the Final EIS for retrieval, treatment process, waste form and transportation for disposal. In addition, DOE has updated the characterization data for both the HLW Calcine (BBWI 2005a) and SBW (BBWI 2004 and BBWI 2005b) and identified two areas where new calculation methods are being used to determine health and safety impacts. Because of those changes, DOE has prepared this supplement analysis to determine whether there are ''substantial changes in the proposed action that are relevant to environmental concerns'' or ''significant new circumstances or information'' within the meaning of the Council of Environmental Quality and DOE National Environmental Policy Act (NEPA) Regulations (40 CFR 1502.9 (c) and 10 CFR 1021.314) that would require preparation of a Supplemental EIS. Specifically, this analysis is intended to determine if: (1) the Steam Reforming Option identified in the Final EIS adequately bounds impacts from the Steam Reforming Process proposed by the new ICP Contractor using the new characterization data, (2) the new characterization data is significantly different than the data presented in the Final EIS, (3) the new calculation methods present a significant change to the impacts described in the Final EIS, and (4) would the updated characterization data cause significant changes in the environmental impacts for the action alternatives/options presented in the Final EIS. There are no other aspects of the Final EIS that require additional review because DOE has not identified any additional new significant circumstances or information that would warrant such a review.

  10. SRS MOX fuel lead assemblies data report for the surplus plutonium disposition environmental impact statement

    SciTech Connect (OSTI)

    O`Connor, D.G.; Fisher, S.E.; Holdaway, R. [and others

    1998-08-01T23:59:59.000Z

    The purpose of this document is to support the US Department of Energy (DOE) Fissile Materials Disposition Program`s preparation of the draft surplus plutonium disposition environmental impact statement. This is one of several responses to data call requests for background information on activities associated with the operation of the lead assembly (LA) mixed-oxide (MOX) fuel fabrication facility. DOE-MD requested that the DOE Site Operations Offices nominate DOE sites that meet established minimum requirements that could produce MOX LAs. Six initial site combinations were proposed: (1) Argonne National Laboratory-West (ANL-W) with support from Idaho National Engineering and Environmental Laboratory (INEEL), (2) Hanford, (3) Los Alamos National Laboratory (LANL) with support from Pantex, (4) Lawrence Livermore National Laboratory (LLNL), (5) Oak Ridge Reservation (ORR), and (6) Savannah River Site(SRS). After further analysis by the sites and DOE-MD, five site combinations were established as possible candidates for producing MOX LAs: (1) ANL-W with support from INEEL, (2) Hanford, (3) LANL, (4) LLNL, and (5) SRS. SRS has proposed an LA MOX fuel fabrication approach that would be done entirely inside an S and S Category 1 area. An alternate approach would allow fabrication of fuel pellets and assembly of fuel rods in an S and S Category 2 or 3 facility with storage of bulk PuO{sub 2} and assembly, storage, and shipping of fuel bundles in an S and S Category 1 facility. The total Category 1 approach, which is the recommended option, would be done in the 221-H Canyon Building. A facility that was never in service will be removed from one area, and a hardened wall will be constructed in another area to accommodate execution of the LA fuel fabrication. The non-Category 1 approach would require removal of process equipment in the FB-Line metal production and packaging glove boxes, which requires work in a contamination area. The Immobilization Hot Demonstration Program equipment in the Savannah River Technology Center would need to be removed to accommodate pellet fabrication. This work would also be in a contaminated area.

  11. Medical imaging systems

    DOE Patents [OSTI]

    Frangioni, John V

    2013-06-25T23:59:59.000Z

    A medical imaging system provides simultaneous rendering of visible light and diagnostic or functional images. The system may be portable, and may include adapters for connecting various light sources and cameras in open surgical environments or laparascopic or endoscopic environments. A user interface provides control over the functionality of the integrated imaging system. In one embodiment, the system provides a tool for surgical pathology.

  12. STUDENT ASSESSMENT MEDICAL FORMSTUDENT ASSESSMENT MEDICAL FORMSTUDENT ASSESSMENT MEDICAL FORMSTUDENT ASSESSMENT MEDICAL FORM Yonsei University

    E-Print Network [OSTI]

    Burgstaller, Bernd

    NO 9) Have you ever received treatment for drug or alcohol addiction? YES NO 10) Have you ever been) Do you have any pre-existing conditions? YES NO 2) Do you currently receive any treatments? YES NO 11) Have you ever had treatment in a medical institution? YES NO 12) If you have answered

  13. Medication concepts, records, and lists in electronic medical record systems

    E-Print Network [OSTI]

    Chang, Jaime

    2006-01-01T23:59:59.000Z

    A well-designed implementation of medication concepts, records, and lists in an electronic medical record (EMR) system allows it to successfully perform many functions vital for the provision of quality health care. A ...

  14. Site Selection for the Salt Disposition Facility at the Savannah River Site

    SciTech Connect (OSTI)

    Gladden, J.B.; Rueter, K.J.; Morin, J.P.

    2000-11-15T23:59:59.000Z

    A site selection study was conducted to identify a suitable location for the construction and operation of a new Salt Disposition Facility (SDF) at the Savannah River Site (SRS). The facility to be sited is a single processing facility and support buildings that could house either of three technology alternatives being developed by the High Level Waste Systems Engineering Team: Small Tank Tetraphenylborate Precipitation, Crystalline Silicotitanate Non-Elutable Ion Exchange or Caustic Side Solvent Extraction. A fourth alternative, Direct Disposal in grout, is not part of the site selection study because a location has been identified that is unique to this technology (i.e., Z-Area). Facility site selection at SRS is a formal, documented process that seeks to optimize siting of new facilities with respect to facility-specific engineering requirements, sensitive environmental resources, and applicable regulatory requirements. In this manner, the prime objectives of cost minimization, environmental protection, and regulatory compliance are achieved. The results from this geotechnical characterization indicated that continued consideration be given to Site B for the proposed SDF. Suitable topography, the lack of surface hydrology and floodplain issues, no significant groundwater contamination, the presence of minor soft zones along the northeast portion of footprint, and no apparent geological structure in the Gordon Aquitard support this recommendation.

  15. Lessons Learned from Three Mile Island Packaging, Transportation and Disposition that Apply to Fukushima Daiichi Recovery

    SciTech Connect (OSTI)

    Layne Pincock; Wendell Hintze; Dr. Koji Shirai

    2012-07-01T23:59:59.000Z

    Following the massive earthquake and resulting tsunami damage in March of 2011 at the Fukushima Daiichi nuclear power plant in Japan, interest was amplified for what was done for recovery at the Three Mile Island Unit 2 (TMI-2) in the United States following its meltdown in 1979. Many parallels could be drawn between to two accidents. This paper presents the results of research done into the TMI-2 recovery effort and its applicability to the Fukushima Daiichi cleanup. This research focused on three topics: packaging, transportation, and disposition. This research work was performed as a collaboration between Japan’s Central Research Institute of Electric Power Industry (CRIEPI) and the Idaho National Laboratory (INL). Hundreds of TMI-2 related documents were searched and pertinent information was gleaned from these documents. Other important information was also obtained by interviewing employees who were involved first hand in various aspects of the TMI-2 cleanup effort. This paper is organized into three main sections: (1) Transport from Three Mile Island to Central Facilities Area at INL, (2) Transport from INL Central Receiving Facility to INL Test Area North (TAN) and wet storage at TAN, and (3) Transport from TAN to INL Idaho Nuclear Technology and Engineering Center (INTEC) and Dry Storage at INTEC. Within each of these sections, lessons learned from performing recovery activities are presented and their applicability to the Fukushima Daiichi nuclear power plant cleanup are outlined.

  16. Disposition of plutonium as non-fertile fuel for water reactors

    SciTech Connect (OSTI)

    Chidester, K.; Eaton, S.L.; Ramsey, K.B.

    1998-11-01T23:59:59.000Z

    This is the final report of a three-year, Laboratory Directed Research and Development (LDRD) project at the Los Alamos National Laboratory (LANL). The original intent of this project was to investigate the possible use of a new fuel form as a means of dispositioning the declared surplus inventory of weapons-grade plutonium. The focus soon changed, however, to managing the larger and rapidly growing inventories of plutonium arising in commercial spent nuclear fuel through implementation of a new fuel form in existing nuclear reactors. LANL embarked on a parallel path effort to study fuel performance using advanced physics codes, while also demonstrating the ability to fabricate a new fuel form using standard processes in LANL's Plutonium Facility. An evolutionary fuel form was also examined which could provide enhanced performance over standard fuel forms, but which could be implemented in a much shorter time frame than a completely new fuel form. Recent efforts have focused on implementation of results into global energy models and development of follow-on funding to continue this research.

  17. Sample Results From The Interim Salt Disposition Program Macrobatch 7 Tank 21H Qualification Samples

    SciTech Connect (OSTI)

    Peters, T. B.; Washington, A. L. II

    2013-08-08T23:59:59.000Z

    Savannah River National Laboratory (SRNL) analyzed samples from Tank 21H in support of qualification of Macrobatch (Salt Batch) 7 for the Interim Salt Disposition Program (ISDP). An ARP and several ESS tests were also performed. This document reports characterization data on the samples of Tank 21H as well as simulated performance of ARP/MCU. No issues with the projected Salt Batch 7 strategy are identified, other than the presence of visible quantities of dark colored solids. A demonstration of the monosodium titanate (0.2 g/L) removal of strontium and actinides provided acceptable 4 hour average decontamination factors for Pu and Sr of 3.22 and 18.4, respectively. The Four ESS tests also showed acceptable behavior with distribution ratios (D(Cs)) values of 15.96, 57.1, 58.6, and 65.6 for the MCU, cold blend, hot blend, and Next Generation Solvent (NGS), respectively. The predicted value for the MCU solvent was 13.2. Currently, there are no models that would allow a prediction of extraction behavior for the other three solvents. SRNL recommends that a model for predicting extraction behavior for cesium removal for the blended solvent and NGS be developed. While no outstanding issues were noted, the presence of solids in the samples should be investigated in future work. It is possible that the solids may represent a potential reservoir of material (such as potassium) that could have an impact on MCU performance if they were to dissolve back into the feed solution. This salt batch is intended to be the first batch to be processed through MCU entirely using the new NGS-MCU solvent.

  18. Assessing alternative strategies for the disposition of weapons-grade uranium and plutonium

    SciTech Connect (OSTI)

    Chow, B.G.

    1995-12-31T23:59:59.000Z

    Highly-enriched uranium (HEU) from dismantled nuclear weapons and military inventory can be blended down into proliferation-resistant low-enriched uranium and used economically as fuel in current nuclear reactors. However, the US can no longer expect the agreement to purchase and resell the uranium blended down from 500 metric tons of Russia`s HEU to be budget neutral. The authors recommend that other countries participate in the repurchase of blended-down uranium from the US and that a multilateral offer to Russia, which acts on behalf of all four former Soviet nuclear republics, be made for the purchase of the blended-down uranium from Russia`s remaining HEU. Since spent fuel in temporary storage worldwide contains enough plutonium to fuel breeders on any realistic buildup schedule in the event that breeders are needed, there is no need to save the weapons-grade plutonium for the future. This paper compares the costs of burning it in existing light water reactors, storing it indefinitely, and burying it after 20 years of storage. They found that the present-valued cost is about $1 to 2 billion in US dollars for all three alternatives. The deciding factor for selection should be an alternative`s proliferation resistance. Prolonged plutonium storage in Russia runs the risk of theft and, if the Russian political scene turns for the worse, the risk of re-use in its nuclear arsenal. The most urgent issue, however, is to determine not the disposition alternative but whether Russia will let its weapons-grade plutonium leave the former Soviet Republics (FSRs). The US should offer to buy and remove such plutonium from the FSRs. If Russia refuses even after the best US efforts, the US should then persuade Russia to burn or bury the plutonium, but not store it indefinitely for future breeder use.

  19. INFORMATION: Management Alert on Environmental Management's Select Strategy for Disposition of Savannah River Site Depleted Uranium Oxides

    SciTech Connect (OSTI)

    None

    2010-04-01T23:59:59.000Z

    The Administration and the Congress, through policy statements and passage of the American Recovery and Reinvestment Act of 2009 (Recovery Act), have signaled that they hope that proactive actions by agency Inspectors General will help ensure that Federal Recovery Act activities are transparent, effective and efficient. In that context, the purpose of this management alert is to share with you concerns that have been raised to the Office of Inspector General regarding the planned disposition of the Savannah River Site's (SRS) inventory of Depleted Uranium (DU) oxides. This inventory, generated as a by-product of the nuclear weapons production process and amounting to approximately 15,600 drums of DU oxides, has been stored at SRS for decades. A Department source we deem reliable and credible recently came to the Office of Inspector General expressing concern that imminent actions are planned that may not provide for the most cost effective disposition of these materials. During April 2009, the Department chose to use funds provided under the Recovery Act to accelerate final disposition of the SRS inventory of DU oxides. After coordination with State of Utah regulators, elected officials and the U.S. Nuclear Regulatory Commission, the Department initiated a campaign to ship the material to a facility operated by EnergySolutions in Clive, Utah. Although one shipment of a portion of the material has already been sent to the EnergySolutions facility, the majority of the product remains at SRS. As had been planned, both for the shipment already made and those planned in the near term, the EnergySolutions facility was to have been the final disposal location for the material. Recently, a member of Congress and various Utah State officials raised questions regarding the radioactive and other constituents present in the DU oxides to be disposed of at the Clive, Utah, facility. These concerns revolved around the characterization of the material and its acceptability under existing licensing criteria. As a consequence, the Governor of Utah met with Department officials to voice concerns regarding further shipments of the material and to seek return of the initial shipment of DU oxides to SRS. Utah's objections and the Department's agreement to accede to the State's demands effectively prohibit the transfer of the remaining material from South Carolina to Utah. In response, the Department evaluated its options and issued a draft decision paper on March 1, 2010, which outlined an alternative for temporary storage until the final disposition issue could be resolved. Under the terms of the proposed option, the remaining shipments from SRS are to be sent on an interim basis to a facility owned by Waste Control Specialists (WCS) in Andrews, Texas. Clearly, this choice carries with it a number of significant logistical burdens, including substantial additional costs for, among several items, repackaging at SRS, transportation to Texas, storage at the interim site, and, repackaging and transportation to the yet-to-be-determined final disposition point. The Department source expressed the concern that the proposal to store the material on an interim basis in Texas was inefficient and unnecessary, asserting: (1) that the materials could remain at SRS until a final disposition path is identified, and that this could be done safely, securely and cost effectively; and, (2) that the nature of the material was not subject to existing compliance agreements with the State of South Carolina, suggesting the viability of keeping the material in storage at SRS until a permanent disposal site is definitively established. We noted that, while the Department's decision paper referred to 'numerous project and programmatic factors that make it impractical to retain the remaining inventory at Savannah River,' it did not outline the specific issues involved nor did it provide any substantive economic or environmental analysis supporting the need for the planned interim storage action. The only apparent driver in this case was a Recovery Act-related goal esta

  20. Providence Newberg Medical Center

    High Performance Buildings Database

    Newberg, OR In 2002, Providence Health & Services began planning a new 188,000 square foot medical center in Newberg, Oregon to respond to the growing community's need for accessible health care. Since this was Providence's first new hospital in almost thirty years, its leaders decided to approach the project through innovative planning, design, and construction, including the achievement of lifecycle energy savings and a potential LEED certification. The hospital is comprised of 40 inpatient beds with views out to the surrounding rural landscape or into lushly planted internal courtyards.

  1. Implantable medical sensor system

    DOE Patents [OSTI]

    Darrow, Christopher B. (Pleasanton, CA); Satcher, Jr., Joe H. (Modesto, CA); Lane, Stephen M. (Oakland, CA); Lee, Abraham P. (Walnut Creek, CA); Wang, Amy W. (Berkeley, CA)

    2001-01-01T23:59:59.000Z

    An implantable chemical sensor system for medical applications is described which permits selective recognition of an analyte using an expandable biocompatible sensor, such as a polymer, that undergoes a dimensional change in the presence of the analyte. The expandable polymer is incorporated into an electronic circuit component that changes its properties (e.g., frequency) when the polymer changes dimension. As the circuit changes its characteristics, an external interrogator transmits a signal transdermally to the transducer, and the concentration of the analyte is determined from the measured changes in the circuit. This invention may be used for minimally invasive monitoring of blood glucose levels in diabetic patients.

  2. Wavelets in medical imaging

    SciTech Connect (OSTI)

    Zahra, Noor e; Sevindir, Huliya A.; Aslan, Zafar; Siddiqi, A. H. [Sharda University, SET, Department of Electronics and Communication, Knowledge Park 3rd, Gr. Noida (India); University of Kocaeli, Department of Mathematics, 41380 Kocaeli (Turkey); Istanbul Aydin University, Department of Computer Engineering, 34295 Istanbul (Turkey); Sharda University, SET, Department of Mathematics, 32-34 Knowledge Park 3rd, Greater Noida (India)

    2012-07-17T23:59:59.000Z

    The aim of this study is to provide emerging applications of wavelet methods to medical signals and images, such as electrocardiogram, electroencephalogram, functional magnetic resonance imaging, computer tomography, X-ray and mammography. Interpretation of these signals and images are quite important. Nowadays wavelet methods have a significant impact on the science of medical imaging and the diagnosis of disease and screening protocols. Based on our initial investigations, future directions include neurosurgical planning and improved assessment of risk for individual patients, improved assessment and strategies for the treatment of chronic pain, improved seizure localization, and improved understanding of the physiology of neurological disorders. We look ahead to these and other emerging applications as the benefits of this technology become incorporated into current and future patient care. In this chapter by applying Fourier transform and wavelet transform, analysis and denoising of one of the important biomedical signals like EEG is carried out. The presence of rhythm, template matching, and correlation is discussed by various method. Energy of EEG signal is used to detect seizure in an epileptic patient. We have also performed denoising of EEG signals by SWT.

  3. Evaluation/disposition of observations no. 6-17, 6-18, and 6-22 from site electrical assessment report, 300 area powerhouse and emergency sys.

    SciTech Connect (OSTI)

    Ahola, E.L.

    1996-09-30T23:59:59.000Z

    Disposition of Observations 6-17, 6-18, 6-22 of Site Electrical Assessment Report. Application of generator differential protection, and synchro-check relay rewiring for generators of building 3621-D. In 1990, the WHC Site Electrical Task Group issued a Site Electrical Assessment Report, ``300 Area Powerhouse and Emergency System.`` This report included numerous findings and observations relating to observed deficiencies or opportunities for improvement in maintenance of the inspected electrical systems. The purpose of this letter report is to provide an evaluation and proposed disposition of Observations No. 6-1 7, 6-1 8, and 6-22 of the Site Electrical Assessment Report.

  4. Disposition of smoked cannabis with high {Delta}{sup 9}-tetrahydrocannabinol content: A kinetic model

    SciTech Connect (OSTI)

    Hunault, Claudine C., E-mail: claudine.hunault@rivm.n [National Poisons Information Center, National Institute for Public Health and the Environment, Bilthoven (Netherlands); Eijkeren, Jan C.H. van [Expertise Center for Methodology and Information Services, National Institute for Public Health and the Environment, Bilthoven (Netherlands); Mensinga, Tjeert T. [National Poisons Information Center, National Institute for Public Health and the Environment, Bilthoven (Netherlands); Clinic for treatment of drug addiction in Northern, Vondellaan 71-73, 9721 LB, Groningen (Netherlands); Vries, Irma de [National Poisons Information Center, National Institute for Public Health and the Environment, Bilthoven (Netherlands); Leenders, Marianne E.C. [National Poisons Information Center, National Institute for Public Health and the Environment, Bilthoven (Netherlands); Division of Perioperative and Emergency Care, University Medical Center Utrecht, 3584 CX (Netherlands); Meulenbelt, Jan [National Poisons Information Center, National Institute for Public Health and the Environment, Bilthoven (Netherlands); Division Intensive Care Center, University Medical Center Utrecht, 3584 CX, Utrecht (Netherlands); Institute for Risk Assessment Sciences, Utrecht University, Utrecht (Netherlands)

    2010-08-01T23:59:59.000Z

    Introduction: No model exists to describe the disposition and kinetics of inhaled cannabis containing a high THC dose. We aimed to develop a kinetic model providing estimates of the THC serum concentrations after smoking cannabis cigarettes containing high THC doses (up to 69 mg THC). Methods: Twenty-four male non-daily cannabis users smoked cannabis cigarettes containing 29.3 mg, 49.1 mg, and 69.4 mg THC. Blood samples were collected over a period of 0-8 h and serum THC concentrations were measured. A two-compartment open model was fitted on the individual observed data. Results: Large inter-individual variability was observed in the pharmacokinetic parameters. The median pharmacokinetic parameters generated by the model were C{sub max} = 175 ng/mL, T{sub max} = 14 min, and AUC{sub 0-8h} = 8150 ng x min/mL for the 69.4 mg THC dose. Median model results show an almost linear dose response relation for C{sub max}/Dose = 2.8 x 10{sup -6}/mL and AUC{sub 0-8h}/Dose = 136 x 10{sup -6} min/mL. However, for increasing dose level, there was a clear decreasing trend: C{sub max}/Dose = 3.4, 2.6 and 2.5 x 10{sup -6}/mL and AUC{sub 0-8h}/Dose = 157, 133 and 117 x 10{sup -6} min/mL for the 29.3, 49.1 and 69.4 mg dose, respectively. Within the restriction of 8 h of observation, the apparent terminal half life of THC was 150 min. Conclusion: The model offers insight into the pharmacokinetics of THC in recreational cannabis users smoking cannabis containing high doses of THC mixed with tobacco. The model is an objective method for providing serum THC concentrations up to 8 h after smoking cannabis with a high THC content (up to 23%).

  5. Fuel-Cycle and Nuclear Material Disposition Issues Associated with High-Temperature Gas Reactors

    SciTech Connect (OSTI)

    Shropshire, D.E.; Herring, J.S.

    2004-10-03T23:59:59.000Z

    The objective of this paper is to facilitate a better understanding of the fuel-cycle and nuclear material disposition issues associated with high-temperature gas reactors (HTGRs). This paper reviews the nuclear fuel cycles supporting early and present day gas reactors, and identifies challenges for the advanced fuel cycles and waste management systems supporting the next generation of HTGRs, including the Very High Temperature Reactor, which is under development in the Generation IV Program. The earliest gas-cooled reactors were the carbon dioxide (CO2)-cooled reactors. Historical experience is available from over 1,000 reactor-years of operation from 52 electricity-generating, CO2-cooled reactor plants that were placed in operation worldwide. Following the CO2 reactor development, seven HTGR plants were built and operated. The HTGR came about from the combination of helium coolant and graphite moderator. Helium was used instead of air or CO2 as the coolant. The helium gas has a significant technical base due to the experience gained in the United States from the 40-MWe Peach Bottom and 330-MWe Fort St. Vrain reactors designed by General Atomics. Germany also built and operated the 15-MWe Arbeitsgemeinschaft Versuchsreaktor (AVR) and the 300-MWe Thorium High-Temperature Reactor (THTR) power plants. The AVR, THTR, Peach Bottom and Fort St. Vrain all used fuel containing thorium in various forms (i.e., carbides, oxides, thorium particles) and mixtures with highly enriched uranium. The operational experience gained from these early gas reactors can be applied to the next generation of nuclear power systems. HTGR systems are being developed in South Africa, China, Japan, the United States, and Russia. Elements of the HTGR system evaluated included fuel demands on uranium ore mining and milling, conversion, enrichment services, and fuel fabrication; fuel management in-core; spent fuel characteristics affecting fuel recycling and refabrication, fuel handling, interim storage, packaging, transportation, waste forms, waste treatment, decontamination and decommissioning issues; and low-level waste (LLW) and high-level waste (HLW) disposal.

  6. The U.S.-Russian joint studies on using power reactors to disposition surplus weapon plutonium as spent fuel

    SciTech Connect (OSTI)

    Chebeskov, A.; Kalashnikov, A. [State Scientific Center, Obninsk (Russian Federation). Inst. of Physics and Power Engineering; Bevard, B.; Moses, D. [Oak Ridge National Lab., TN (United States); Pavlovichev, A. [State Scientific Center, Moscow (Russian Federation). Kurchatov Inst.

    1997-09-01T23:59:59.000Z

    In 1996, the US and the Russian Federation completed an initial joint study of the candidate options for the disposition of surplus weapons plutonium in both countries. The options included long term storage, immobilization of the plutonium in glass or ceramic for geologic disposal, and the conversion of weapons plutonium to spent fuel in power reactors. For the latter option, the US is only considering the use of existing light water reactors (LWRs) with no new reactor construction for plutonium disposition, or the use of Canadian deuterium uranium (CANDU) heavy water reactors. While Russia advocates building new reactors, the cost is high, and the continuing joint study of the Russian options is considering only the use of existing VVER-1000 LWRs in Russia and possibly Ukraine, the existing BN-60O fast neutron reactor at the Beloyarsk Nuclear Power Plant in Russia, or the use of the Canadian CANDU reactors. Six of the seven existing VVER-1000 reactors in Russia and the eleven VVER-1000 reactors in Ukraine are all of recent vintage and can be converted to use partial MOX cores. These existing VVER-1000 reactors are capable of converting almost 300 kg of surplus weapons plutonium to spent fuel each year with minimum nuclear power plant modifications. Higher core loads may be achievable in future years.

  7. MODERN MIRACLE MEDICAL MACHINES: PHYSICS INSTRUCTION FOR FUTURE MEDICAL STUDENTS

    E-Print Network [OSTI]

    Zollman, Dean

    1 MODERN MIRACLE MEDICAL MACHINES: PHYSICS INSTRUCTION FOR FUTURE MEDICAL STUDENTS DEAN ZOLLMAN a complete change in the course is not likely. So we are trying to bring some modern physics in the context--not just at the end when modern physics is typically presented. #12;2 2 Physics Education Research

  8. The Medical College of Wisconsin 6 THE MEDICAL COLLEGE OF WISCONSIN MEDICAL SCHOOL ACADEMIC BULLETIN 2011-2012

    E-Print Network [OSTI]

    for engagement in leading-edge science for students aspiring to advance medical knowledge through researchThe Medical College of Wisconsin 6 THE MEDICAL COLLEGE OF WISCONSIN MEDICAL SCHOOL ACADEMIC BULLETIN 2011-2012 The Medical College of Wisconsin offers MD, PhD, MA, MS and MPH degrees. There are more

  9. Discover your Library Medical Library

    E-Print Network [OSTI]

    Discover your Library Medical Library Welcome to the Gus Fraenkel Medical Library. The Library is a branch of the Flinders University Libraries including: Central (on the Plaza of the north ridge precinct) Law (on level 3 of the Central Library building) Sturt (at the Sturt precinct) as well

  10. The Academy Harvard Medical School

    E-Print Network [OSTI]

    Paulsson, Johan

    The Academy Harvard Medical School Annual Report 2010 - 2011 #12;#12;To the HMS Community Academic year 2011 was another exciting and productive period for the Harvard Medical School Academy. Our Collaborative was also strengthened as the Academy tried to expand upon its outreach initiatives to the clinical

  11. INCIDENT # CHARGE SECTION OF NYS PENAL LAW DISPOSITION TYPE REPORTED TO PLACE OF OCCURRENCE DATE & TIME OF OCCURRENCE DATE & TIME REPORTED 1304224 None

    E-Print Network [OSTI]

    Johnson Jr.,, Ray

    INCIDENT # CHARGE SECTION OF NYS PENAL LAW DISPOSITION TYPE REPORTED TO PLACE OF OCCURRENCE DATE Public Safety Department Music Building 6442 Kissena Blvd., Flushing, NY 11367 April 29, 2013 2:15PM Building 6660 Kissena Blvd., Flushing, NY 11367 May 1, 2013 12:15PM May 1, 2013 2:50PM 1305279 None Petit

  12. Cost-effective facility disposition planning with safety and health lessons learned and good practices from the Oak Ridge Decontamination and Decommissioning Program

    SciTech Connect (OSTI)

    NONE

    1998-05-01T23:59:59.000Z

    An emphasis on transition and safe disposition of DOE excess facilities has brought about significant challenges to managing worker, public, and environmental risks. The transition and disposition activities involve a diverse range of hazardous facilities that are old, poorly maintained, and contain radioactive and hazardous substances, the extent of which may be unknown. In addition, many excess facilities do not have historical facility documents such as operating records, plant and instrumentation diagrams, and incident records. The purpose of this report is to present an overview of the Oak Ridge Decontamination and Decommissioning (D and D) Program, its safety performance, and associated safety and health lessons learned and good practices. Illustrative examples of these lessons learned and good practices are also provided. The primary focus of this report is on the safety and health activities and implications associated with the planning phase of Oak Ridge facility disposition projects. Section 1.0 of this report provides the background and purpose of the report. Section 2.0 presents an overview of the facility disposition activities from which the lessons learned and good practices discussed in Section 3.0 were derived.

  13. Medical imaging systems

    DOE Patents [OSTI]

    Frangioni, John V. (Wayland, MA)

    2012-07-24T23:59:59.000Z

    A medical imaging system provides simultaneous rendering of visible light and fluorescent images. The system may employ dyes in a small-molecule form that remains in a subject's blood stream for several minutes, allowing real-time imaging of the subject's circulatory system superimposed upon a conventional, visible light image of the subject. The system may also employ dyes or other fluorescent substances associated with antibodies, antibody fragments, or ligands that accumulate within a region of diagnostic significance. In one embodiment, the system provides an excitation light source to excite the fluorescent substance and a visible light source for general illumination within the same optical guide that is used to capture images. In another embodiment, the system is configured for use in open surgical procedures by providing an operating area that is closed to ambient light. More broadly, the systems described herein may be used in imaging applications where a visible light image may be usefully supplemented by an image formed from fluorescent emissions from a fluorescent substance that marks areas of functional interest.

  14. Complications Associated with Long-Term Disposition of Newly-Generated Transuranic Waste: A National Laboratory Perspective

    SciTech Connect (OSTI)

    B.J. Orchard; L.A. Harvego; T.L. Carlson; R.P. Grant

    2009-03-01T23:59:59.000Z

    The Idaho National Laboratory (INL) is a multipurpose national laboratory delivering specialized science and engineering solutions for the U.S. Department of Energy (DOE). Sponsorship of INL was formally transferred to the DOE Office of Nuclear Energy, Science and Technology (NE) by Secretary Spencer Abraham in July 2002. The move to NE, and designation as the DOE lead nuclear energy laboratory for reactor technology, supports the nation’s expanding nuclear energy initiatives, placing INL at the center of work to develop advanced Generation IV nuclear energy systems; nuclear energy/hydrogen coproduction technology; advanced nuclear energy fuel cycle technologies; and providing national security answers to national infrastructure needs. As a result of the Laboratory’s NE mission, INL generates both contact-handled and remote-handled transuranic (TRU) waste from ongoing operations. Generation rates are relatively small and fluctuate based on specific programs and project activities being conducted; however, the Laboratory will continue to generate TRU waste well into the future in association with the NE mission. Currently, plans and capabilities are being established to transfer INL’s contact-handled TRU waste to the Advanced Mixed Waste Treatment Plant (AMWTP) for certification and disposal to the Waste Isolation Pilot Plant (WIPP). Remote-handled TRU waste is currently placed in storage at the Materials and Fuels Complex (MFC). In an effort to minimize future liabilities associated with the INL NE mission, INL is evaluating and assessing options for the management and disposition of all its TRU waste on a real-time basis at time of generation. This paper summarizes near-term activities to minimize future re handling of INL’s TRU waste, as well as, potential complications associated with the long-term disposition of newly-generated TRU waste. Potential complications impacting the disposition of INL newly-generated TRU waste include, but are not limited to: 1) required remote-handled TRU packaging configuration(s) vs. current facility capabilities, 2) long-term NE mission activities, 3) WIPP certification requirements, and 4) budget considerations.

  15. Final Demolition and Disposition of 209-E Critical Mass Laboratory - 12267

    SciTech Connect (OSTI)

    Woolery, Wade [US Department of Energy, Richland WA (United States); Dodd, Edwin III [CH2M Hill Plateau Remediation Company, Richland WA (United States)

    2012-07-01T23:59:59.000Z

    The 209-E Critical Mass Laboratory was constructed in 1960 to provide a heavy shielded reactor room where quantities of plutonium or uranium in solution could be brought to near-critical configurations under carefully controlled and monitored conditions. In the late 1980's, the responsible contractor, Pacific Northwest National Laboratory (PNNL), was directed by the Department of Energy (DOE) to prepare the facility for unoccupied status. The facility was demolished under a Removal Action Work Plan pursuant to the Comprehensive Environmental Response, Compensation, and Liability Act of 1980 (CERCLA). The funding for this project was provided by the American Recovery and Reinvestment Act (ARRA). The primary rooms of concern with regards to contamination in 209-E facility, which is over 9,000 square feet, are the criticality assembly room (CAR), the mix room, and the change room. The CAR contained two reactor hoods (HO-140 and HO-170), which each had a high efficiency particulate air (HEPA) filter system. The CAR contained 13 tanks ranging from 38 L (10 gal) to 401 L (106 gal). Tanks TK-109 and TK-110 are below grade, and were removed as part of this demolition and disposition remedy. Nonradiological and radiological hazardous substances were removed, decontaminated, or fixed in place, prior to demolition. Except for the removal of below grade tanks TK-109 and TK-110, the facility was demolished to slab-on-grade. PNNL performed stabilization and deactivation activities that included removal of bulk fissile material and chemicals, flushing tanks, stabilizing contamination within gloveboxes and hoods, and packaging and removing waste. The removal of the contaminated plutonium equipment and materials from the 209E facility presented a number of challenges similar in nature to those associated with the inventory reduction and cleanup activities at the Plutonium Finishing Plant. Although there were no bulk fissile materials or chemicals within the facility, there were residual radiological materials (isotopes of plutonium and americium) in the tanks and hoods. The complexity of the remedy was present because of the various configurations of the tanks and hoods, combined with the residual contaminants. Because of the weight and dimensional configuration, size reduction of the slab tanks, as well as removal and disposal of the different material used for moderation and absorption, were two examples of challenges that were resolved to complete the remedy. One of the key methods developed and implemented at the facility was the design and construction of a shroud to allow the cutting of the Pu contaminated tanks. The shroud design, development and implementation at the 209E Project was an example of enhanced work planning and task hazards analysis with worker involvement. This paper will present the lessons learned from the 209E facility inventory reduction activities including the shroud and other methodologies used. The initial Lessons Learned discussion for this project was scheduled for late January 2012. This facility is the first open-air demolition of a highly contaminated plutonium-contaminated facility accomplished by CH2M Hill under the Plateau Remediation Contract. The demolition was completed without spread of contamination to the workers and the surrounding area. As with any project of this complexity, there are significant accomplishments, as well as experience that can be applied to future demolition of plutonium-contaminated facilities on the Hanford Site. These experiences will be documented at a later date. (authors)

  16. Far-Field Accumulation of Fissile Material From Waste Packages Containing Plutonium Disposition Waste Form

    SciTech Connect (OSTI)

    J.P. Nicot

    2000-09-29T23:59:59.000Z

    The objective of this calculation is to estimate the quantity of fissile material that could accumulate in fractures in the rock beneath plutonium-ceramic (Pu-ceramic) and Mixed-Oxide (MOX) waste packages (WPs) as they degrade in the potential monitored geologic repository at Yucca Mountain. This calculation is to feed another calculation (Ref. 31) computing the probability of criticality in the systems described in Section 6 and then ultimately to a more general report on the impact of plutonium on the performance of the proposed repository (Ref. 32), both developed concurrently to this work. This calculation is done in accordance with the development plan TDP-DDC-MD-000001 (Ref. 9), item 5. The original document described in item 5 has been split into two documents: this calculation and Ref. 4. The scope of the calculation is limited to only very low flow rates because they lead to the most conservative cases for Pu accumulation and more generally are consistent with the way the effluent from the WP (called source term in this calculation) was calculated (Ref. 4). Ref. 4 (''In-Drift Accumulation of Fissile Material from WPs Containing Plutonium Disposition Waste Forms'') details the evolution through time (breach time is initial time) of the chemical composition of the solution inside the WP as degradation of the fuel and other materials proceed. It is the chemical solution used as a source term in this calculation. Ref. 4 takes that same source term and reacts it with the invert; this calculation reacts it with the rock. In addition to reactions with the rock minerals (that release Si and Ca), the basic mechanisms for actinide precipitation are dilution and mixing with resident water as explained in Section 2.1.4. No other potential mechanism such as flow through a reducing zone is investigated in this calculation. No attempt was made to use the effluent water from the bottom of the invert instead of using directly the effluent water from the WP. This calculation supports disposal criticality analysis and has been prepared in accordance with AP-3.12Q, Calculations (Ref. 49). This calculation uses results from Ref. 4 on actinide accumulation in the invert and more generally does reference heavily the cited calculation. In addition to the information provided in this calculation, the reader is referred to the cited calculation for a more thorough treatment of items applying to both the invert and fracture system such as the choice of the thermodynamic database, the composition of J-13 well water, tuff composition, dissolution rate laws, Pu(OH){sub 4} solubility and also for details on the source term composition. The flow conditions (seepage rate, water velocity in fractures) in the drift and the fracture system beneath initially referred to the TSPA-VA because this work was prepared before the release of the work feeding the TSPA-SR. Some new information feeding the TSPA-SR has since been included. Similarly, the soon-to-be-qualified thermodynamic database data0.ymp has not been released yet.

  17. BAYESIAN ENSEMBLE LEARNING FOR MEDICAL IMAGE DENOISING

    E-Print Network [OSTI]

    Oh, Hyuntaek

    2012-08-31T23:59:59.000Z

    Medical images are often affected by random noise because of both image acquisition from the medical modalities and image transmission from modalities to workspace in the main computer. Medical image denoising removes noise from the CT or MR images...

  18. WHAT IS MEDICAL MINERALOGY AND GEOCHEMISTRY?

    E-Print Network [OSTI]

    Sahai, Nita

    WHAT IS MEDICAL MINERALOGY AND GEOCHEMISTRY? The connection between human health of medical mineralogy and geochemistry (MMG) focuses on understanding the equilibria and reaction pathways phases with naturally occurring, inorganic solid phases within the human body. Medical mineralogy

  19. Sample Results From The Interim Salt Disposition Program Macrobatch 7 Tank 21H Qualification MST Solids Sample

    SciTech Connect (OSTI)

    Washington, A. L. II; Peters, T. B.

    2013-09-19T23:59:59.000Z

    Savannah River National Laboratory (SRNL) performed experiments on qualification material for use in the Interim Salt Disposition Program (ISDP) Batch 7 processing. The Marcrobatch 7 material was received with visible fine particulate solids, atypical for these samples. The as received material was allowed to settle for a period greater than 24 hours. The supernatant was then decanted and utilized as our clarified feed material. As part of this qualification work, SRNL performed an Actinide Removal Process (ARP) test using the clarified feed material. From this test, the residual monosodium titanate (MST) was analyzed for radionuclide uptake after filtration from H-Tank Farm (HTF) feed salt solution. The results of these analyses are reported and are within historical precedent.

  20. Final Environmental Assessment and Finding of No Significant Impact: Waste Disposition Activities at the Paducah Site Paducah, Kentucky

    SciTech Connect (OSTI)

    N /A

    2002-11-05T23:59:59.000Z

    The U.S. Department of Energy (DOE) has completed an environmental assessment (DOE/EA-1339), which is incorporated herein by reference, for proposed disposition of polychlorinated biphenyl (PCB) wastes, low-level radioactive waste (LLW), mixed low-level radioactive waste (MLLW), and transuranic (TRU) waste from the Paducah Gaseous Diffusion Plant Site (Paducah Site) in Paducah, Kentucky. All of the wastes would be transported for disposal at various locations in the United States. Based on the results of the impact analysis reported in the EA, DOE has determined that the proposed action is not a major federal action that would significantly affect the quality of the human environment with in the context of the National Environmental Policy Act of 1969 (NEPA). Therefore, preparation of an environmental impact statement is not necessary, and DOE is issuing this Finding of No Significant Impact (FONSI).

  1. THE NGA-DOE GRANT TO EXAMINE CRITICAL ISSUES RELATED TO RADIOACTIVE WASTE AND MATERIALS DISPOSITION INVOLVING DOE FACILITIES

    SciTech Connect (OSTI)

    Ann M. Beauchesne

    2000-01-01T23:59:59.000Z

    Through the National Governors Association (NGA) project ``Critical Issues Related to Radioactive Waste and Materials Disposition Involving DOE Facilities'' NGA brings together Governors' policy advisors, state regulators, and DOE officials to examine critical issues related to the cleanup and operation of DOE nuclear weapons and research facilities. Topics explored through this project include: Decisions involving disposal of mixed, low-level, and transuranic (TRU) waste and disposition of nuclear materials; Decisions involving DOE budget requests and their effect on environmental cleanup and compliance at DOE facilities; Strategies to treat mixed, low-level, and transuranic (TRU) waste and their effect on individual sites in the complex; Changes to the FFCA site treatment plans as a result of proposals in the Department's Accelerating Cleanup: Paths to Closure plan and contractor integration analysis; Interstate waste and materials shipments; and Reforms to existing RCRA and CERCLA regulations/guidance to address regulatory overlap and risks posed by DOE wastes. The overarching theme of this project is to help the Department improve coordination of its major program decisions with Governors' offices and state regulators and to ensure such decisions reflect input from these key state officials and stakeholders. This report summarizes activities conducted during the period from October 1, 1999 through January 31, 2000, under the NGA grant. The work accomplished by the NGA project team during the past three months can be categorized as follows: maintained open communication with DOE on a variety of activities and issues within the DOE environmental management complex; convened and facilitated the October 6--8 NGA FFCA Task Force Meeting in Oak Ridge, Tennessee; maintained communication with NGA Federal Facilities Compliance Task Force members regarding DOE efforts to formulate a configuration for mixed low-level waste and low-level treatment and disposal, external regulation of DOE; and continued to facilitate interactions between the states and DOE to develop a foundation for an ongoing substantive relationship between the Governors of key states and the Department.

  2. THE NGA-DOE GRANT TO EXAMINE CRITICAL ISSUES RELATED TO RADIOACTIVE WASTE AND MATERIALS DISPOSITION INVOLVING DOE FACILITIES

    SciTech Connect (OSTI)

    NONE

    1998-07-01T23:59:59.000Z

    Through the National Governors' Association (NGA) project ''Critical Issues Related to Radioactive Waste and Materials Disposition Involving DOE Facilities'' NGA brings together Governors' policy advisors, state regulators, and DOE officials to examine critical issues related to the cleanup and operation of DOE nuclear weapons and research facilities. Topics explored through this project include: Decisions involving disposal of mixed, low-level, and transuranic (TRU) waste and disposition of nuclear materials. Decisions involving DOE budget requests and their effect on environmental cleanup and compliance at DOE facilities. Strategies to treat mixed, low-level, and transuranic (TRU) waste and their effect on individual sites in the complex. Changes to the FFCA site treatment plans as a result of proposals in DOE's Accelerating Cleanup: Paths to Closure strategy and contractor integration analysis. Interstate waste and materials shipments. Reforms to existing RCRA and CERCLA regulations/guidance to address regulatory overlap and risks posed by DOE wastes. The overarching theme of this project is to help the Department improve coordination of its major program decisions with Governors' offices and state regulators and to ensure such decisions reflect input from these key state officials and stakeholders. This report summarizes activities conducted during the quarter from April 30, 1998 through June 30, 1998 under the NGA project. The work accomplished by the NGA project team during the past four months can be categorized as follows: maintained open communication with DOE on a variety of activities and issues within the DOE environmental management complex; and provided ongoing support to state-DOE interactions. maintained communication with NGA Federal Facilities Compliance Task Force members regarding DOE efforts to formulate a configuration for mixed low-level waste and low-level treatment and disposal, DOE's Environmental Management Budget, and DOE's proposed Intersite Discussions.

  3. Medical and Biohazardous Waste Generator's Guide (Revision 2)

    E-Print Network [OSTI]

    Waste Management Group

    2006-01-01T23:59:59.000Z

    Waste Supplies 8. Solid Medical Waste Disposal ProceduresMedical/Biohazardous Waste Pickup Containers Solid Medical/Security Notice 8. Solid Medical Waste Disposal Procedures

  4. General Counsel Legal Interpretation Regarding Medical Removal...

    Energy Savers [EERE]

    Regarding Medical Removal Protection Benefits Pursuant to 10 CFR Part 850, Chronic Beryllium Disease Prevention Program General Counsel Legal Interpretation Regarding Medical...

  5. Former Workers Medical Facilities with Experience Evaluating...

    Office of Environmental Management (EM)

    Workers Medical Facilities with Experience Evaluating Chronic Beryllium Disease Former Workers Medical Facilities with Experience Evaluating Chronic Beryllium Disease April 2011...

  6. ORISE Resources: Medical Office Preparedness Planner

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    partnership with CDC yields Medical Office Preparedness Planner for Primary Care Providers The Medical Office Preparedness Planner is a tool for primary care providers (PCPs) and...

  7. Modeling the Syn Disposition of Nitrogen Donors in Non-Heme Diiron Enzymes. Synthesis, Characterization, and Hydrogen Peroxide Reactivity of Diiron(III) Complexes with the Syn N-Donor Ligand H[subscript 2]BPG[subscript 2]DEV

    E-Print Network [OSTI]

    Friedle, Simone

    In order to model the syn disposition of histidine residues in carboxylate-bridged non-heme diiron enzymes, we prepared a new dinucleating ligand, H[subscript 2]BPG[subscript 2]DEV, that provides this geometric feature. ...

  8. SLUDGE TREATMENT PROJECT KOP DISPOSITION - THERMAL AND GAS ANALYSIS FOR THE COLD VACUUM DRYING FACILITY

    SciTech Connect (OSTI)

    SWENSON JA; CROWE RD; APTHORPE R; PLYS MG

    2010-03-09T23:59:59.000Z

    The purpose of this document is to present conceptual design phase thermal process calculations that support the process design and process safety basis for the cold vacuum drying of K Basin KOP material. This document is intended to demonstrate that the conceptual approach: (1) Represents a workable process design that is suitable for development in preliminary design; and (2) Will support formal safety documentation to be prepared during the definitive design phase to establish an acceptable safety basis. The Sludge Treatment Project (STP) is responsible for the disposition of Knock Out Pot (KOP) sludge within the 105-K West (KW) Basin. KOP sludge consists of size segregated material (primarily canister particulate) from the fuel and scrap cleaning process used in the Spent Nuclear Fuel process at K Basin. The KOP sludge will be pre-treated to remove fines and some of the constituents containing chemically bound water, after which it is referred to as KOP material. The KOP material will then be loaded into a Multi-Canister Overpack (MCO), dried at the Cold Vacuum Drying Facility (CVDF) and stored in the Canister Storage Building (CSB). This process is patterned after the successful drying of 2100 metric tons of spent fuel, and uses the same facilities and much of the same equipment that was used for drying fuel and scrap. Table ES-l present similarities and differences between KOP material and fuel and between MCOs loaded with these materials. The potential content of bound water bearing constituents limits the mass ofKOP material in an MCO load to a fraction of that in an MCO containing fuel and scrap; however, the small particle size of the KOP material causes the surface area to be significantly higher. This relatively large reactive surface area represents an input to the KOP thermal calculations that is significantly different from the calculations for fuel MCOs. The conceptual design provides for a copper insert block that limits the volume available to receive KOP material, enhances heat conduction, and functions as a heat source and sink during drying operations. This use of the copper insert represents a significant change to the thermal model compared to that used for the fuel calculations. A number of cases were run representing a spectrum of normal and upset conditions for the drying process. Dozens of cases have been run on cold vacuum drying of fuel MCOs. Analysis of these previous calculations identified four cases that provide a solid basis for judgments on the behavior of MCO in drying operations. These four cases are: (1) Normal Process; (2) Degraded vacuum pumping; (3) Open MCO with loss of annulus water; and (4) Cool down after vacuum drying. The four cases were run for two sets of input parameters for KOP MCOs: (1) a set of parameters drawn from safety basis values from the technical data book and (2) a sensitivity set using parameters selected to evaluate the impact of lower void volume and smaller particle size on MCO behavior. Results of the calculations for the drying phase cases are shown in Table ES-2. Cases using data book safety basis values showed dry out in 9.7 hours and heat rejection sufficient to hold temperature rise to less than 25 C. Sensitivity cases which included unrealistically small particle sizes and corresponding high reactive surface area showed higher temperature increases that were limited by water consumption. In this document and in the attachment (Apthorpe, R. and M.G. Plys, 2010) cases using Technical Databook safety basis values are referred to as nominal cases. In future calculations such cases will be called safety basis cases. Also in these documents cases using parameters that are less favorable to acceptable performance than databook safety values are referred to as safety cases. In future calculations such cases will be called sensitivity cases or sensitivity evaluations Calculations to be performed in support of the detailed design and formal safety basis documentation will expand the calculations presented in this document to include: additional features of th

  9. Medical research: assessing the benefits to society

    E-Print Network [OSTI]

    Rambaut, Andrew

    independent Academy of Medical Sciences promotes advances in medical science and campaigns to ensure from medical advances: `Exceptional Returns' 26 3.6 Discussion and conclusions 27 4 Bringing togetherMay 2006 Medical research: assessing the benefits to society A report by the UK Evaluation Forum

  10. EA-1977: Acceptance and Disposition of Used Nuclear Fuel Containing U.S.-Origin Highly Enriched Uranium from the Federal Republic of Germany

    Broader source: Energy.gov [DOE]

    This environmental assessment (EA) will evaluate the potential environmental impacts of a DOE proposal to accept used nuclear fuel from the Federal Republic of Germany at DOE’s Savannah River Site (SRS) for processing and disposition. This used nuclear fuel is composed of kernels containing thorium and U.S.-origin highly enriched uranium (HEU) embedded in small graphite spheres that were irradiated in nuclear reactors used for research and development purposes.

  11. Supporting Technology for Chain of Custody of Nuclear Weapons and Materials throughout the Dismantlement and Disposition Processes

    SciTech Connect (OSTI)

    Bunch, Kyle J. [United States Department of State, Bureau of Arms Control, Verification and Compliance, Office of Verification and Transparency Technologies, Washington, DC (United States); Jones, Anthony M. [Pacific Northwest National Laboratory (PNNL), Richland, WA (United States); Ramuhalli, Pradeep [Pacific Northwest National Laboratory (PNNL), Richland, WA (United States); Benz, Jacob M. [Pacific Northwest National Laboratory (PNNL), Richland, WA (United States); Denlinger, Laura Schmidt [Pacific Northwest National Laboratory (PNNL), Richland, WA (United States)

    2014-05-04T23:59:59.000Z

    The ratification and ongoing implementation of the New START Treaty have been widely regarded as noteworthy global security achievements for both the Obama Administration and the Putin (formerly Medvedev) regime. But deeper cuts that move beyond the United States and Russia to engage the P-5 and other nuclear weapons possessor states are envisioned under future arms control regimes, and are indeed required for the P-5 in accordance with their Article VI disarmament obligations in the Nuclear Non-Proliferation Treaty. Future verification needs will include monitoring the cessation of production of new fissile material for weapons, monitoring storage of warhead components and fissile materials and verifying dismantlement of warheads, pits, secondary stages, and other materials. A fundamental challenge to implementing a nuclear disarmament regime is the ability to thwart unauthorized material diversion throughout the dismantlement and disposition process through strong chain of custody implementation. Verifying the declared presence, or absence, of nuclear materials and weapons components throughout the dismantlement and disposition lifecycle is a critical aspect of the disarmament process. From both the diplomatic and technical perspectives, verification under these future arms control regimes will require new solutions. Since any acceptable verification technology must protect sensitive design information and attributes to prevent the release of classified or other proliferation-sensitive information, non-nuclear non-sensitive modalities may provide significant new verification tools which do not require the use of additional information barriers. Alternative verification technologies based upon electromagnetic and acoustics could potentially play an important role in fulfilling the challenging requirements of future verification regimes. For example, researchers at the Pacific Northwest National Laboratory (PNNL) have demonstrated that low frequency electromagnetic signatures of sealed metallic containers can be used to rapidly confirm the presence of specific components on a yes/no basis without revealing classified information. PNNL researchers have also used ultrasonic measurements to obtain images of material microstructures which may be used as templates or unique identifiers of treaty-limited items. Such alternative technologies are suitable for application in various stages of weapons dismantlement and often include the advantage of an inherent information barrier due to the inability to extract classified weapon design information from the collected data. As a result, these types of technologies complement radiation-based verification methods for arms control. This article presents an overview of several alternative verification technologies that are suitable for supporting a future, broader and more intrusive arms control regime that spans the nuclear weapons disarmament lifecycle. The general capabilities and limitations of each verification modality are discussed and example technologies are presented. Potential applications are defined in the context of the nuclear material and weapons lifecycle. Example applications range from authentication (e.g., tracking and signatures within the chain of custody from downloading through weapons storage, unclassified templates and unique identification) to verification of absence and final material disposition.

  12. Electronic Medical Device Reliability The growing sophistication of electronic medical devices results in

    E-Print Network [OSTI]

    Perkins, Richard A.

    Electronic Medical Device Reliability Objective The growing sophistication of electronic medical-defined lifetimes. To assist the medical electronics industry in achieving the needed reliability, this project-driven projects--medical electronic components, implant- ed electronic leads, and portable electronic medical

  13. Medical Guidelines Reconciling Medical Software and Electronic Devices: Imatinib Case-study

    E-Print Network [OSTI]

    De Micheli, Giovanni

    Medical Guidelines Reconciling Medical Software and Electronic Devices: Imatinib Case-study Alena as specification of a medical system that includes both software and electronic devices. However, often medical GLs. INTRODUCTION Recently, the set of electronic medical devices has a tendency to be extended with a new class

  14. Medical Imaging Technology | GE Global Research

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645U.S. DOE Office of Science (SC)Integrated Codes |IsLove Your Home andDispositionMechanical R&DMaking High-Value

  15. Medical Plans for Non-Medicare Retirees

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645U.S. DOE Office of Science (SC)Integrated Codes |IsLove Your Home andDispositionMechanical

  16. Medical Testing and Surveillance Facilities - Hanford Site

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645U.S. DOE Office of Science (SC)Integrated Codes |IsLove Your Home andDispositionMechanicalAbout Us > Hanford Site

  17. The Academy Harvard Medical School

    E-Print Network [OSTI]

    Paulsson, Johan

    The Academy Harvard Medical School Annual Report 2011 - 2012 #12;#12;To the HMS Community In many ways, academic year 2012 was the "Year of Critical Thinking" for the HMS Academy. Critical thinking and practice. When all of the Academy professional development programs are taken together, par- ticipation

  18. Medical Imaging Computed Tomography (CT)

    E-Print Network [OSTI]

    Massey, Thomas N.

    Module 10 Medical Imaging · X-rays · Computed Tomography (CT) · Positron Emission Tomography (PET Sources PET-TOF #12;Four Sources PET #12;Four Sources PET-TOF #12;PET Scan MRI CT scan #12;Endocrine Gland,000 pixels! #12;Modern Example of CT Scan with the addition of Surface Shading Standard CT With Surface

  19. EMERGENCY PHONE NUMBERS Medical Emergency

    E-Print Network [OSTI]

    Chou, James

    /Illness 4. Fire/Smoke/Explosion 5. Utility Disruption 6. Threat 7. Suspicious Package/Item 8. Hazardous Operations Center (617) 495-5560 · Fire/Smoke/Explosion · Flooding · Hazardous Material · Utility Failure. Describe the type of emergency (fire, medical, utility disruption, public safety, etc). Give the phone

  20. Interim salt disposition program macrobatch 6 tank 21H qualification monosodium titanate and cesium mass transfer tests

    SciTech Connect (OSTI)

    Washington, A. L. II; Peters, T. B.; Fink, S. D.

    2013-02-25T23:59:59.000Z

    Savannah River National Laboratory (SRNL) performed experiments on qualification material for use in the Interim Salt Disposition Program (ISDP) Batch 6 processing. This qualification material was a set of six samples from Tank 21H in October 2012. This sample was used as a real waste demonstration of the Actinide Removal Process (ARP) and the Extraction-Scrub-Strip (ESS) tests process. The Tank 21H sample was contacted with a reduced amount (0.2 g/L) of MST and characterized for strontium and actinide removal at 0 and 8 hour time intervals in this salt batch. {sup 237}Np and {sup 243}Am were both observed to be below detection limits in the source material, and so these results are not reported in this report. The plutonium and uranium samples had decontamination factor (DF) values that were on par or slightly better than we expected from Batch 5. The strontium DF values are slightly lower than expected but still in an acceptable range. The Extraction, Scrub, and Strip (ESS) testing demonstrated cesium removal, stripping and scrubbing within the acceptable range. Overall, the testing indicated that cesium removal is comparable to prior batches at MCU.

  1. INDEPENDENT TECHNICAL ASSESSMENT OF MANAGEMENT OF STORMWATER AND WASTEWATER AT THE SEPARATIONS PROCESS RESEARCH UNIT (SPRU) DISPOSITION PROJECT, NEW YORK

    SciTech Connect (OSTI)

    Abitz, R.; Jackson, D.; Eddy-Dilek, C.

    2011-06-27T23:59:59.000Z

    The U.S. Department of Energy (DOE) is currently evaluating the water management procedures at the Separations Process Research Unit (SPRU). The facility has three issues related to water management that require technical assistance: (1) due to a excessive rainfall event in October, 2010, contaminated water collected in basements of G2 and H2 buildings. As a result of this event, the contractor has had to collect and dispose of water offsite; (2) The failure of a sump pump at a KAPL outfall resulted in a Notice of Violation issued by the New York State Department of Environment and Conservation (NYSDEC) and subsequent Consent Order. On-site water now requires treatment and off-site disposition; and (3) stormwater infiltration has resulted in Strontium-90 levels discharged to the storm drains that exceed NR standards. The contractor has indicated that water management at SPRU requires major staff resources (at least 50 persons). The purpose of this review is to determine if the contractor's technical approach warrants the large number of staff resources and to ensure that the technical approach is compliant and in accordance with federal, state and NR requirements.

  2. Medical implants and methods of making medical implants

    DOE Patents [OSTI]

    Shaw, Wendy J; Yonker, Clement R; Fulton, John L; Tarasevich, Barbara J; McClain, James B; Taylor, Doug

    2014-09-16T23:59:59.000Z

    A medical implant device having a substrate with an oxidized surface and a silane derivative coating covalently bonded to the oxidized surface. A bioactive agent is covalently bonded to the silane derivative coating. An implantable stent device including a stent core having an oxidized surface with a layer of silane derivative covalently bonded thereto. A spacer layer comprising polyethylene glycol (PEG) is covalently bonded to the layer of silane derivative and a protein is covalently bonded to the PEG. A method of making a medical implant device including providing a substrate having a surface, oxidizing the surface and reacting with derivitized silane to form a silane coating covalently bonded to the surface. A bioactive agent is then covalently bonded to the silane coating. In particular instances, an additional coating of bio-absorbable polymer and/or pharmaceutical agent is deposited over the bioactive agent.

  3. Medical Surveillance for Former Workers

    SciTech Connect (OSTI)

    Tim Takaro

    2009-05-29T23:59:59.000Z

    The Former Hanford Worker Medical Monitoring Program, directed by the Occupational and Environmental Medicine Program at the University of Washington, served former production and other non-construction workers who were potentially exposed to workplace hazards while working for the USDOE or its contractors at Hanford. The USDOE Former Workers Program arose from Congressional action in the Defense Authorization of 1993 (Public Law 102). Section 3162 stated that, “The Secretary shall establish and carry out a program for the identification and ongoing medical evaluation of current and former Department of Energy employees who are subject to significant health risks as a result of exposure of such employees to hazardous or radioactive substances during such employment.” (This also covers former employees of USDOE contractors and subcontractors.) The key objective has been to provide these former workers with medical evaluations in order to determine whether workers have experienced significant risk due to workplace exposure to hazards. Exposures to asbestos, beryllium, and noise can produce specific medical conditions: asbestosis, berylliosis, and noise-induced hearing loss (NIHL). Each of these conditions can be identified by specific, non-invasive screening tests, which are widely available. Treatments are also available for individuals affected by these conditions. This project involved two phases. Phase I involved a needs and risk assessment, characterizing the nature and extent of workplace health hazards which may have increased the risk for long-term health effects. We categorized jobs and tasks by likelihood of exposures to specific workplace health hazards; and located and established contact with former Hanford workers. Phase II involved implementation of medical monitoring programs for former workers whose individual work history indicated significant risk for adverse health effects. We identified 118,000 former workers, employed from 1943 to 1997. After excluding current workers, construction workers, and deceased workers, the total estimated number of former workers eligible for screening was 72,611. By September, 2006, 53,010 workers had been contacted, 20,298 responded, 2,835 were eligible and authorized, and 2,773 workers were ultimately screened. The cohort was 80% male, 85% white, and had a mean age of 63 years (range 24-96 years) at the time of first exam. Participants completed an occupational health history survey prior to the medical exam. Former Hanford workers were considered eligible for an exam if they reported exposure to asbestos, beryllium, or noise, or if a review of their Hanford work history indicated possible or probable exposure to one of these three hazards. We also invited any former Hanford worker who requested an exam to participate, regardless of documentation of exposure. The screening exam included a problem-focused physical exam, along with screening tests for one or more of three specific medical conditions: asbestosis (chest X-ray and spirometry), berylliosis (chest X-ray, spirometry, and beryllium-induced lymphocyte proliferation test), and NIHL (audiometry). We assisted ill workers in filing appropriate workers’ compensation claims, and facilitated appropriate follow-up medical care. This program has made an important contribution to the health of former DOE contractor workers at the Hanford defense nuclear site.

  4. Medical ice slurry production device

    DOE Patents [OSTI]

    Kasza, Kenneth E. (Palos Park, IL); Oras, John (Des Plaines, IL); Son, HyunJin (Naperville, IL)

    2008-06-24T23:59:59.000Z

    The present invention relates to an apparatus for producing sterile ice slurries for medical cooling applications. The apparatus is capable of producing highly loaded slurries suitable for delivery to targeted internal organs of a patient, such as the brain, heart, lungs, stomach, kidneys, pancreas, and others, through medical size diameter tubing. The ice slurry production apparatus includes a slurry production reservoir adapted to contain a volume of a saline solution. A flexible membrane crystallization surface is provided within the slurry production reservoir. The crystallization surface is chilled to a temperature below a freezing point of the saline solution within the reservoir such that ice particles form on the crystallization surface. A deflector in the form of a reciprocating member is provided for periodically distorting the crystallization surface and dislodging the ice particles which form on the crystallization surface. Using reservoir mixing the slurry is conditioned for easy pumping directly out of the production reservoir via medical tubing or delivery through other means such as squeeze bottles, squeeze bags, hypodermic syringes, manual hand delivery, and the like.

  5. Medical Devices and Systems PRECISE Center

    E-Print Network [OSTI]

    Rajkumar, Ragunathan "Raj"

    that are not likely to be met by research in your field alone? ­ Advances in medical devices domain requires12/16/2008 1 Medical Devices and Systems Insup Lee PRECISE Center Department Computer and Information Science University of Pennsylvania 12/15/08 CPS Information Day Medical Devices Containing

  6. Medical Technologies Innovation Training 2014 BIOINNOVATE FELLOWSHIP

    E-Print Network [OSTI]

    Prinz, Friedrich B.

    Medical Technologies Innovation Training 2014 BIOINNOVATE FELLOWSHIP BioInnovate Ireland is now medical technology companies and for the development of innovative medical device products. Ireland solutions to meet those needs and implement a strategy to commercialise the technology. BioInnovate

  7. Medical Bioremediation: A Concept Moving Toward Reality

    E-Print Network [OSTI]

    Alvarez, Pedro J.

    Medical Bioremediation: A Concept Moving Toward Reality John Schloendorn,1,2 Tim Webb,2 Kent, primarily the pyridinium bisretinoid A2E. Medical bioremediation is the concept of reversing the substance bioremediation, the new ap- proach targeting aging diseases has been termed ``medical bioremediation

  8. University of Michigan Medical School Overview Introduction

    E-Print Network [OSTI]

    Kirschner, Denise

    University of Michigan Medical School Overview Introduction The University of Michigan opened its. The University of Michigan Medical School was among the first to change the role of the student from passive at the University of Michigan Medical School since the first graduating class of six students in 1851. Today, we

  9. aggressive medical management: Topics by E-print Network

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Engineering Websites Summary: Status Change MedicalPrescription Drug Card Medical Care Outside Ohio Dual Coverage Case ManagementAdministration of Medications Laboratory...

  10. ORISE: The Medical Basis for Radiation-Accident Preparedness...

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    The Medical Basis for Radiation-Accident Preparedness: Medical Management Proceedings of the Fifth International REACTS Symposium on the Medical Basis for Radiation-Accident...

  11. antihypertensive medical treatment: Topics by E-print Network

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    in methadone patients with HIV. University of California eScholarship Repository Summary: abuse treatment, medical care, and AIDS medications may beMedication coaching Voucher...

  12. alternative medical treatment: Topics by E-print Network

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    in methadone patients with HIV. University of California eScholarship Repository Summary: abuse treatment, medical care, and AIDS medications may beMedication coaching Voucher...

  13. (09)UC/05 BSc(Hons) Medical Physics/11 Bachelor of Science (Honours) Medical Physics

    E-Print Network [OSTI]

    Hickman, Mark

    is being added (CUAP Category 1). Justification Advances in the discipline Medical physicists, like most(09)UC/05 ­ BSc(Hons) Medical Physics/11 Bachelor of Science (Honours) Medical Physics 2005 Calendar, pages 348 and 681 (09)UC/05 ­ BSc(Hons) Medical Physics/1 Section A 1. Purpose of proposal

  14. Session 35 - Panel: Remaining US Disposition Issues for Orphan or Small Volume Low Level and Low Level Mixed Waste Streams

    SciTech Connect (OSTI)

    Blauvelt, Richard [Navarro Engineering Research Inc. (United States); Small, Ken [Doe Nevada (United States); Gelles, Christine [DOE EM HQ (United States); McKenney, Dale [Fluor Hanford (United States); Franz, Bill [LATA Portsmouth (United States); Loveland, Kaylin [Energy Solutions Inc. (United States); Lauer, Mike [Waste Control Specialists (United States)

    2006-07-01T23:59:59.000Z

    Faced with closure schedules as a driving force, significant progress has been made during the last 2 years on the disposition of DOE mixed waste streams thought previously to be problematic. Generators, the Department of Energy and commercial vendors have combined to develop unique disposition paths for former orphan streams. Recent successes and remaining issues will be discussed. The session will also provide an opportunity for Federal agencies to share lessons learned on low- level and mixed low-level waste challenges and identify opportunities for future collaboration. This panel discussion was organized by PAC member Dick Blauvelt, Navarro Research and Engineering Inc who served as co-chair along with Dave Eaton from INL. In addition, George Antonucci, Duratek Barnwell and Rich Conley, AFSC were invited members of the audience, prepared to contribute the Barnwell and DOD perspective to the issues as needed. Mr. Small provide information regarding the five year 20K M3 window of opportunity at the Nevada Test Site for DOE contractors to dispose of mixed waste that cannot be received at the Energy Solutions (Envirocare) site in Utah because of activity levels. He provided a summary of the waste acceptance criteria and the process sites must follow to be certified to ship. When the volume limit or time limit is met, the site will undergo a RCRA closure. Ms. Gelles summarized the status of the orphan issues, commercial options and the impact of the EM reorganization on her program. She also announced that there would be a follow-on meeting in 2006 to the very successful St. Louis meeting of last year. It will probably take place in Chicago in July. Details to be announced. Mr. McKenney discussed progress made at the Hanford Reservation regarding disposal of their mixed waste inventory. The news is good for the Hanford site but not good for the rest of the DOE complex since shipment for out of state of both low level and low level mixed waste will continue to be prohibited until the completion of a new NEPA study. This is anticipated to take several years. Bill Franz from Portsmouth and Dave Eaton representing the INL provided the audience with information regarding some of the problematic mixed waste streams at their respective sites. Portsmouth has some unique radiological issues with isotopes such as Tc-99 while the INL is trying to deal with mixed waste in the 10-100 nCi/g range. Kaylin Loveland spoke of the new,Energy Solutions organization and provided information on mixed waste treatment capabilities at the Clive site. Mike Lauer described the licensing activities at the WCS site in Texas where they are trying to eventually have disposal capabilities for Class A, B and C mixed waste from both DOE and the commercial sector. The audience included about 75 WM'06 attendees who asked some excellent questions and provided an active and informative exchange of information on the topic. (authors)

  15. Disposal R&D in the Used Fuel Disposition Campaign: A Discussion of Opportunities for Active International Collaboration

    SciTech Connect (OSTI)

    Birkholzer, J.T.

    2011-06-01T23:59:59.000Z

    For DOE's Used Fuel Disposition Campaign (UFDC), international collaboration is a beneficial and cost-effective strategy for advancing disposal science with regards to multiple disposal options and different geologic environments. While the United States disposal program focused solely on Yucca Mountain tuff as host rock over the past decades, several international programs have made significant progress in the characterization and performance evaluation of other geologic repository options, most of which are very different from the Yucca Mountain site in design and host rock characteristics. Because Yucca Mountain was so unique (e.g., no backfill, unsaturated densely fractured tuff), areas of direct collaboration with international disposal programs were quite limited during that time. The decision by the U.S. Department of Energy to no longer pursue the disposal of high-level radioactive waste and spent fuel at Yucca Mountain has shifted UFDC's interest to disposal options and geologic environments similar to those being investigated by disposal programs in other nations. Much can be gained by close collaboration with these programs, including access to valuable experience and data collected over recent decades. Such collaboration can help to efficiently achieve UFDC's long-term goals of conducting 'experiments to fill data needs and confirm advanced modeling approaches' (by 2015) and of having a 'robust modeling and experimental basis for evaluation of multiple disposal system options' (by 2020). This report discusses selected opportunities of active international collaboration, with focus on both Natural Barrier System (NBS) and Engineered Barrier System (EBS) aspects and those opportunities that provide access to field data (and respective interpretation/modeling) or allow participation in ongoing field experiments. This discussion serves as a basis for the DOE/NE-53 and UFDC planning process for FY12 and beyond.

  16. FY 2012 USED FUEL DISPOSITION CAMPAIGN TRANSPORTATION TASK REPORT ON INL EFFORTS SUPPORTING THE MODERATOR EXCLUSION CONCEPT AND STANDARDIZED TRANSPORTATION

    SciTech Connect (OSTI)

    D. K. Morton

    2012-08-01T23:59:59.000Z

    Following the defunding of the Yucca Mountain Project, it is reasonable to assume that commercial used fuel will remain in storage for a longer time period than initially assumed. Previous transportation task work in FY 2011, under the Department of Energy’s Office of Nuclear Energy, Used Fuel Disposition Campaign, proposed an alternative for safely transporting used fuel regardless of the structural integrity of the used fuel, baskets, poisons, or storage canisters after an extended period of storage. This alternative assures criticality safety during transportation by implementing a concept that achieves moderator exclusion (no in-leakage of moderator into the used fuel cavity). By relying upon a component inside of the transportation cask that provides a watertight function, a strong argument can be made that moderator intrusion is not credible and should not be a required assumption for criticality evaluations during normal or hypothetical accident conditions of transportation. This Transportation Task report addresses the assigned FY 2012 work that supports the proposed moderator exclusion concept as well as a standardized transportation system. The two tasks assigned were to (1) promote the proposed moderator exclusion concept to both regulatory and nuclear industry audiences and (2) advance specific technical issues in order to improve American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section III, Division 3 rules for storage and transportation containments. The common point behind both of the assigned tasks is to provide more options that can be used to resolve current issues being debated regarding the future transportation of used fuel after extended storage.

  17. Status and Path Forward for the Department of Energy Used Fuel Disposition Storage and Transportation Program - 12571

    SciTech Connect (OSTI)

    Sorenson, Ken [Sandia National Laboratories (United States); Williams, Jeffrey [U.S. Department of Energy, Office of Nuclear Energy (United States)

    2012-07-01T23:59:59.000Z

    The U.S. Department of Energy, Office of Nuclear Energy (DOE/NE) has sponsored a program since Fiscal Year (FY) 09 to develop the technical basis for extended dry storage of used fuel. This program is also working to develop the transportation technical basis for the transport of used fuel after the extended storage period. As this program has progressed, data gaps associated with dry storage systems (e.g., fuel, cask internals, canister, closure, overpack, and pad) have been identified that need to be addressed to develop the technical bases for extended storage and transportation. There has also been an initiation of experimental testing and analyses based on the identified data gaps. The technical aspects of the NE program are being conducted by a multi-lab team made up of the DOE laboratories. As part of this program, a mission objective is to also collaborate closely with industry and the international sector to ensure that all the technical issues are addressed and those programs outside the DOE program can be leveraged, where possible, to maximize the global effort in storage and transportation research. The DOE/NE program is actively pursuing the development of the technical basis to demonstrate the feasibility of storing UNF for extended periods of time with subsequent transportation of the UNF to its final disposition. This program is fully integrated with industry, the U.S. regulator, and the international community to assure that programmatic goals and objectives are consistent with a broad perspective of technical and regulatory opinion. As the work evolves, assessments will be made to ensure that the work continues to focus on the overall goals and objectives of the program. (authors)

  18. Fissile Material Disposition Program: Deep borehole disposal Facility PEIS date input report for immobilized disposal. Immobilized disposal of plutonium in coated ceramic pellets in grout with canisters. Version 3.0

    SciTech Connect (OSTI)

    Wijesinghe, A.M.; Shaffer, R.J.

    1996-01-15T23:59:59.000Z

    Following President Clinton`s Non-Proliferation Initiative, launched in September, 1993, an Interagency Working Group (IWG) was established to conduct a comprehensive review of the options for the disposition of weapons-usable fissile materials from nuclear weapons dismantlement activities in the United States and the former Soviet Union. The IWG review process will consider technical, nonproliferation, environmental budgetary, and economic considerations in the disposal of plutonium. The IWG is co-chaired by the White House Office of Science and Technology Policy and the National Security Council. The Department of Energy (DOE) is directly responsible for the management, storage, and disposition of all weapons-usable fissile material. The Department of Energy has been directed to prepare a comprehensive review of long-term options for Surplus Fissile Material (SFM) disposition, taking into account technical, nonproliferation, environmental, budgetary, and economic considerations.

  19. Identification and evaluation of alternatives for the disposition of fluoride fuel and flush salts from the molten salt reactor experiment at Oak Ridge National Laboratory, Oak Ridge, Tennessee

    SciTech Connect (OSTI)

    NONE

    1996-08-15T23:59:59.000Z

    This document presents an initial identification and evaluation of the alternatives for disposition of the fluoride fuel and flush salts stored in the drain tanks at the Molten Salt Reactor Experiment (MSRE) at Oak Ridge National Laboratory (ORNL). It will serve as a resource for the U.S. Department of Energy contractor preparing the feasibility study for this activity under the Comprehensive Environmental Response, Compensation and Liability Act (CERCLA). This document will also facilitate further discussion on the range of credible alternatives, and the relative merits of alternatives, throughout the time that a final alternative is selected under the CERCLA process.

  20. Compact accelerator for medical therapy

    DOE Patents [OSTI]

    Caporaso, George J.; Chen, Yu-Jiuan; Hawkins, Steven A.; Sampayan, Stephen E.; Paul, Arthur C.

    2010-05-04T23:59:59.000Z

    A compact accelerator system having an integrated particle generator-linear accelerator with a compact, small-scale construction capable of producing an energetic (.about.70-250 MeV) proton beam or other nuclei and transporting the beam direction to a medical therapy patient without the need for bending magnets or other hardware often required for remote beam transport. The integrated particle generator-accelerator is actuable as a unitary body on a support structure to enable scanning of a particle beam by direction actuation of the particle generator-accelerator.

  1. Retiree Medical Insurance for 2015

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645U.S. DOE Office of Scienceand Requirements RecentlyElectronicResources Resources About oneRethinkingMedical Plans

  2. THE DISCOVERY OF HD 37605c AND A DISPOSITIVE NULL DETECTION OF TRANSITS OF HD 37605b

    SciTech Connect (OSTI)

    Wang, Sharon Xuesong; Wright, Jason T.; Mahadevan, Suvrath [Department of Astronomy and Astrophysics, 525 Davey Laboratory, Pennsylvania State University, University Park, PA 16802 (United States); Cochran, William; Endl, Michael; MacQueen, Phillip J. [McDonald Observatory, University of Texas, Austin, TX 78712 (United States); Kane, Stephen R.; Von Braun, Kaspar [NASA Exoplanet Science Institute, Caltech, MS 100-22, 770 South Wilson Avenue, Pasadena, CA 91125 (United States); Henry, Gregory W. [Center of Excellence in Information Systems, Tennessee State University, 3500 John A. Merritt Boulevard, Box 9501, Nashville, TN 37209 (United States); Payne, Matthew J.; Ford, Eric B. [Department of Astronomy, University of Florida, 211 Bryant Space Science Center, P.O. Box 112055, Gainesville, FL 32611 (United States); Valenti, Jeff A. [Space Telescope Science Institute, 3700 San Martin Drive, Baltimore, MD 21218 (United States); Antoci, Victoria; Dragomir, Diana; Matthews, Jaymie M. [Department of Physics and Astronomy, University of British Columbia, Vancouver, BC V6T1Z1 (Canada); Howard, Andrew W.; Marcy, Geoffrey W.; Isaacson, Howard, E-mail: xxw131@psu.edu, E-mail: jtwright@astro.psu.edu [Department of Astronomy, University of California, Berkeley, CA 94720 (United States)

    2012-12-10T23:59:59.000Z

    We report the radial velocity discovery of a second planetary mass companion to the K0 V star HD 37605, which was already known to host an eccentric, P {approx} 55 days Jovian planet, HD 37605b. This second planet, HD 37605c, has a period of {approx}7.5 years with a low eccentricity and an Msin i of {approx}3.4 M{sub Jup}. Our discovery was made with the nearly 8 years of radial velocity follow-up at the Hobby-Eberly Telescope and Keck Observatory, including observations made as part of the Transit Ephemeris Refinement and Monitoring Survey effort to provide precise ephemerides to long-period planets for transit follow-up. With a total of 137 radial velocity observations covering almost 8 years, we provide a good orbital solution of the HD 37605 system, and a precise transit ephemeris for HD 37605b. Our dynamic analysis reveals very minimal planet-planet interaction and an insignificant transit time variation. Using the predicted ephemeris, we performed a transit search for HD 37605b with the photometric data taken by the T12 0.8 m Automatic Photoelectric Telescope (APT) and the MOST satellite. Though the APT photometry did not capture the transit window, it characterized the stellar activity of HD 37605, which is consistent of it being an old, inactive star, with a tentative rotation period of 57.67 days. The MOST photometry enabled us to report a dispositive null detection of a non-grazing transit for this planet. Within the predicted transit window, we exclude an edge-on predicted depth of 1.9% at the >>10{sigma} level, and exclude any transit with an impact parameter b > 0.951 at greater than 5{sigma}. We present the BOOTTRAN package for calculating Keplerian orbital parameter uncertainties via bootstrapping. We made a comparison and found consistency between our orbital fit parameters calculated by the RVLIN package and error bars by BOOTTRAN with those produced by a Bayesian analysis using MCMC.

  3. Disposition of the fluoride fuel and flush salts from the Molten Salt Reactor experiment at Oak Ridge National Laboratory

    SciTech Connect (OSTI)

    Peretz, F.J.

    1996-03-01T23:59:59.000Z

    The Molten Salt Reactor Experiment (MSRE) is an 8 MW reactor that was operated at Oak Ridge National Laboratory (ORNL) from 1965 through 1969. The reactor used a unique liquid salt fuel, composed of a mixture of LIF, BeF{sub 2}, ZrF{sub 4}, and UF{sub 4}, and operated at temperatures above 600{degrees}C. The primary fuel salt circulation system consisted of the reactor vessel, a single fuel salt pump, and a single primary heat exchanger. Heat was transferred from the fuel salt to a coolant salt circuit in the primary heat exchanger. The coolant salt was similar to the fuel salt, except that it contains only LiF (66%) and BeF, (34%). The coolant salt passed from the primary heat exchanger to an air-cooled radiator and a coolant salt pump, and then returned to the primary heat exchanger. Each of the salt loops was provided with drain tanks, located such that the salt could be drained out of either circuit by gravity. A single drain tank was provided for the non-radioactive coolant salt. Two drain tanks were provided for the fuel salt. Since the fuel salt contained radioactive fuel, fission products, and activation products, and since the reactor was designed such that the fuel salt could be drained immediately into the drain tanks in the event of a problem in the fuel salt loop, the fuel salt drain tanks were provided with a system to remove the heat generated by radioactive decay. A third drain tank connected to the fuel salt loop was provided for a batch of flush salt. This batch of salt, similar in composition to the coolant salt, was used to condition the fuel salt loop after it had been exposed to air and to flush the fuel salt loop of residual fuel salt prior to accessing the reactor circuit for maintenance or experimental activities. This report discusses the disposition of the fluoride fuel and flush salt.

  4. Weapons-grade plutonium dispositioning. Volume 3: A new reactor concept without uranium or thorium for burning weapons-grade plutonium

    SciTech Connect (OSTI)

    Ryskamp, J.M.; Schnitzler, B.G.; Fletcher, C.D. [and others

    1993-06-01T23:59:59.000Z

    The National Academy of Sciences (NAS) requested that the Idaho National Engineering Laboratory (INEL) examine concepts that focus only on the destruction of 50,000 kg of weapons-grade plutonium. A concept has been developed by the INEL for a low-temperature, low-pressure, low-power density, low-coolant-flow-rate light water reactor that destroys plutonium quickly without using uranium or thorium. This concept is very safe and could be designed, constructed, and operated in a reasonable time frame. This concept does not produce electricity. Not considering other missions frees the design from the paradigms and constraints used by proponents of other dispositioning concepts. The plutonium destruction design goal is most easily achievable with a large, moderate power reactor that operates at a significantly lower thermal power density than is appropriate for reactors with multiple design goals. This volume presents the assumptions and requirements, a reactor concept overview, and a list of recommendations. The appendices contain detailed discussions on plutonium dispositioning, self-protection, fuel types, neutronics, thermal hydraulics, off-site radiation releases, and economics.

  5. Production of fluorine-18 for medical applications

    E-Print Network [OSTI]

    Sullivan, Patricia Papa

    1973-01-01T23:59:59.000Z

    PRODUCTION OF FLUORINE-18 FOR MEDICAL APPLICATIONS A Thesis by PATRICIA PAPA SULLIVAN Submitted to the Graduate College of Texas ASM University in partial fulfillment of the requirement for the degree of MASTER OF SCIENCE December 1973... Production of Fluorine-18 for Medical Applications. (December 1973) Patricia Papa Sullivan, B. S. , Marquette University; Directed by: Dr. Ronald D. Macfarlane A method is described for the production of fluorine-18 for medical purposes using...

  6. Implementation Guide of Medical Standards for Firefighters

    Broader source: Energy.gov [DOE]

    These guidelines were prepared to assist the DOE contractor site occupational medical programs in developing NFPA-based firefighter standards that comply with the ADA.

  7. ORISE: REAC/TS Radiation Treatment Medications

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Treatment Medications The Radiation Emergency Assistance CenterTraining Site (REACTS) is a valuable resource in the use of drug therapies to treat radiation exposure. REACTS...

  8. Therapeutic Hypothermia: Protective Cooling Using Medical Ice...

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Therapeutic Hypothermia: Protective Cooling Using Medical Ice Slurry Technology available for licensing: Proprietary method and equipment for making an ice slurry coolant to induce...

  9. EIS-0249: Medical Isotopes Production Project

    Broader source: Energy.gov [DOE]

    This EIS evaluates the potential environmental impacts of a proposal to establish a production capability for molybdenum-99 (Mo-99) and related medical isotopes.

  10. Efficient design of precision medical robotics

    E-Print Network [OSTI]

    Hanumara, Nevan Clancy

    2012-01-01T23:59:59.000Z

    Medical robotics is increasingly demonstrating the potential to improve patient care through more precise interventions. However, taking inspiration from industrial robotics has often resulted in large, sometimes cumbersome ...

  11. ORNL's medical radioisotope project sees centennial campaign...

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    actinium-225 processing, which provides radioisotopes for medical uses that include cancer treatment. Actinium-225 is a source for bismuth-213, a short-lived, alpha-emitting...

  12. Math PUrview -- Mathematics Moves Mammograms to Medical ...

    E-Print Network [OSTI]

    Large-scale screenings can be difficult in rural and other areas traditionally underserved by health care professionals, where there may not be medical ...

  13. SUIVI MEDICAL DE SALARIES EXPOSES AU BERYLLIUM : Medical follow-up of beryllium -exposed workers

    E-Print Network [OSTI]

    Boyer, Edmond

    1 SUIVI MEDICAL DE SALARIES EXPOSES AU BERYLLIUM : Medical follow-up of beryllium - exposed workers-up of beryllium-exposed workers. Method: a medical follow-up of workers from a factory machining beryllium (Be preventive measures. Key words: beryllium, sensitisation, occupational exposure, prevention, Lymphocyte

  14. The use of zirconium hydride blankets in a minor actinide/thorium burner sodium-cooled reactor for void coefficient control with particular reference to UK's plutonium disposition problem

    E-Print Network [OSTI]

    Arias, Francisco J.; Parks, Geoffrey T.

    2015-04-21T23:59:59.000Z

    The use of zirconium hydride (Th–ZrH1.6) blankets in a thorium-fuelled sodium-cooled reactor for void reactivity control with particular reference to UK's plutonium disposition problem is proposed and considered. It is shown that, with the use...

  15. Facility Disposition Projects

    Office of Environmental Management (EM)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742 33 1112011 Strategic Plan| Department of.pdf6-OPAMDepartment6 FY 2007FY 2014Facilities Facilities

  16. Integrated Facilities Disposition Program

    Office of Environmental Management (EM)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742 33 1112011 Strategic2 OPAM Flash2011-12Approved onIngrid Milton SEMIANNUALC:\DocumentsFacilities

  17. Medical Surveillance n Based on risk assessment

    E-Print Network [OSTI]

    Collins, Gary S.

    Surveillance Risk Assessment 2.12 #12;n Top management n overall safety policy n resource allocation n2.12 #12;Medical Surveillance Criteria n Based on risk assessment n Pre-placement n evaluate of numbers exists n Predict an outcome given similar events Medical Surveillance Risk Assessment 2.12 #12;n

  18. Medical Examination Office of Human Resources

    E-Print Network [OSTI]

    Howat, Ian M.

    Medical Examination 4.40 Office of Human Resources Applies to: Faculty, staff, graduate associates, student employees, and applicants The Ohio State University Office of Human Resources Page 1 of 1 Policy 4.40 medical Examination ­ Resources Edited 12/10/13 Resources for Policy 4.40 Drug-Free Workplace, Policy 7

  19. HEALTH AND MEDICAL RESEARCH STRATEGIC REVIEW

    E-Print Network [OSTI]

    Viglas, Anastasios

    FOR RESEARCH TRANSLATION 55 3.1.1 Research partnerships with health care providers 55 3.1.2 ResearchHEALTH AND MEDICAL RESEARCH STRATEGIC REVIEW FINAL REPORT 14 JUNE 2013 #12;#12;CHAIRMAN'S FOREWORD does Sydney's performance in health and medical research compare? 19 1.3.2 Internal fragmentation 23 1

  20. University of Puerto Rico MEDICAL SCIENCES CAMPUS

    E-Print Network [OSTI]

    Quirk, Gregory J.

    University of Puerto Rico MEDICAL SCIENCES CAMPUS San Juan, Puerto Rico Institutional Review Board RESEARCH USING HUMAN BIOLOGICAL MATERIALS Policies and Procedure May, 2000 #12;University of Puerto Rico Medical Sciences Campus San Juan, Puerto Rico Institutional Review Board RESEARCH USING HUMAN BIOLOGICAL

  1. The Academy at Harvard Medical School

    E-Print Network [OSTI]

    Paulsson, Johan

    The Academy at Harvard Medical School The Academy Center for Teaching and Learning Annual Report 2009-2010 #12;Richard Schwartzstein, MD Director, Academy at Harvard Medical School Ellen and Melvin for the HMS Academy. With the assistance of an advisory council drawn from each of the major HMS affiliates

  2. Development of an inventory/archive program for the retention, management, and disposition of tank characterization samples at the 222-S laboratory

    SciTech Connect (OSTI)

    Seidel, C.M.

    1998-04-29T23:59:59.000Z

    The Hanford Tank Waste Remediation Systems (TWRS) Characterization Program is responsible for coordinating the sampling and analysis of the 177 large underground storage tanks at the Hanford site. The 222-S laboratory has been the primary laboratory for chemical analysis of this highly-radioactive material and has been accumulating these samples for many years. As part of the Fiscal Year 1998 laboratory work scope, the 222-S laboratory has performed a formal physical inventory of all tank characterization samples which are currently being stored. In addition, an updated inventory/archive program has been designed. This program defines sample storage, retention, consolidation, maintenance, and disposition activities which will ensure that the sample integrity is preserved to the greatest practical extent. In addition, the new program provides for continued availability of waste material in a form which will be useful for future bench-scale studies. Finally, when the samples have exceeded their useful lifetime, the program provides for sample disposition from,the laboratory in a controlled, safe and environmentally compliant manner. The 222-S laboratory maintains custody over samples of tank waste material which have been shipped to the laboratory for chemical analysis. The storage of these samples currently requires an entire hotcell, fully dedicated to sample archive storage, and is rapidly encroaching on additional hotcell space. As additional samples are received, they are beginning to limit the 222-S laboratory hotcell utility for other activities such as sample extrusion and subsampling. The 222-S laboratory tracks the number of sample containers and the mass of each sample through an internal database which has recently been verified and updated via a physical inventory.

  3. Securing the Sustainability of Global Medical Nuclear Supply Chains

    E-Print Network [OSTI]

    Nagurney, Anna

    Securing the Sustainability of Global Medical Nuclear Supply Chains Through Economic Cost Recovery University of Massachusetts Amherst Securing the Sustainability of Medical Nuclear Supply Chains #12 of Massachusetts Amherst Securing the Sustainability of Medical Nuclear Supply Chains #12;This presentation

  4. Complex Medical Processes as Context for Embedded George S. Avrunin

    E-Print Network [OSTI]

    Avrunin, George S.

    " in- fusion pumps for intravenous administration of medications and fluids. Infusion pumps were several channels infusing different medications. Errors in setting the pumps can lead to administration

  5. asymptomatic medical students: Topics by E-print Network

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    and previous Finley Jr., Russell L. 7 Medical Plan Detail Document for Funded Graduate Students Engineering Websites Summary: Status Change MedicalPrescription Drug Card...

  6. Merle West Medical Center Space Heating Low Temperature Geothermal...

    Open Energy Info (EERE)

    Merle West Medical Center Space Heating Low Temperature Geothermal Facility Jump to: navigation, search Name Merle West Medical Center Space Heating Low Temperature Geothermal...

  7. Jefferson Lab Medical Imager Spots Breast Cancer | Jefferson...

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Eric Rosen, Duke University Medical Center Jefferson Lab Medical Imager Spots Breast Cancer March 3, 2005 Newport News, VA - A study published in the February issue of the...

  8. ORISE: Agents of Opportunity for Terrorism Continuing Medical...

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    the Accreditation Council for Continuing Medical Education to provide continuing medical education for physicians. ORISE takes responsibility for the content, quality, and...

  9. Dynamic security for medical record sharing

    E-Print Network [OSTI]

    Cody, Patrick M. (Patrick Michael), 1980-

    2003-01-01T23:59:59.000Z

    Information routinely collected by health care organizations is used by researchers to analyze the causes of illness and evaluate the effectiveness of potential cures. Medical information sharing systems are built to ...

  10. Medical Student Research in Nephrology and Hypertension

    E-Print Network [OSTI]

    Finley Jr., Russell L.

    Medical Student Research in Nephrology and Hypertension Summer 2013 Research Opportunity Nancy Lightsey, MSRTP-NH Program Administrator Division of Nephrology and Hypertension Vanderbilt University or translational research in kidney disease or hypertension (no research experience required) · Career advice

  11. Computer- and robot-assisted Medical Intervention

    E-Print Network [OSTI]

    Troccaz, Jocelyne

    2009-01-01T23:59:59.000Z

    Medical robotics includes assistive devices used by the physician in order to make his/her diagnostic or therapeutic practices easier and more efficient. This chapter focuses on such systems. It introduces the general field of Computer-Assisted Medical Interventions, its aims, its different components and describes the place of robots in that context. The evolutions in terms of general design and control paradigms in the development of medical robots are presented and issues specific to that application domain are discussed. A view of existing systems, on-going developments and future trends is given. A case-study is detailed. Other types of robotic help in the medical environment (such as for assisting a handicapped person, for rehabilitation of a patient or for replacement of some damaged/suppressed limbs or organs) are out of the scope of this chapter.

  12. Medical physics calculations with MCNP: a primer

    E-Print Network [OSTI]

    Lazarine, Alexis D

    2006-10-30T23:59:59.000Z

    of Medical Internal Radiation Dose (MIRD) specific absorbed fraction (SAF) values using the ORNL MIRD phantom, x-ray phototherapy effectiveness, prostate brachytherapy lifetime dose calculations, and a radiograph of the head using the Zubal head phantom. Also...

  13. Acquisition of medical device start-ups

    E-Print Network [OSTI]

    Nair, Ganesh R

    2006-01-01T23:59:59.000Z

    Introduction: In the medical device space, a large proportion of the breakthrough inventions are developed by small firms that use private equity to bring their technologies from concept to varying stages of development. ...

  14. Medical physics calculations with MCNP: a primer 

    E-Print Network [OSTI]

    Lazarine, Alexis D

    2006-10-30T23:59:59.000Z

    of Medical Internal Radiation Dose (MIRD) specific absorbed fraction (SAF) values using the ORNL MIRD phantom, x-ray phototherapy effectiveness, prostate brachytherapy lifetime dose calculations, and a radiograph of the head using the Zubal head phantom. Also...

  15. IsoRay Medical William A. Cavanagh

    E-Print Network [OSTI]

    2011 #12;IsoRay Medical AMEX: ISR Founded: 1998 Richland, Washington Employees: 35 Market Cap (3 complex. The production facility is completely independent with it's own HVAC and Emergency Power Systems

  16. 21A.215 Medical Anthropology, Fall 2004

    E-Print Network [OSTI]

    Jackson, Jean E. (Jean Elizabeth), 1943-

    Examination of how medicine is practiced cross-culturally, with particular emphasis on Western biomedicine. Analysis of medical practice as a cultural system, focusing on the human, as opposed to the biological, side of ...

  17. DOE: Former Worker Medical Screening Program (FWP)

    Broader source: Energy.gov [DOE]

    FWP provides no-cost medical screenings to all former DOE Federal, contractor and subcontractor employees. The screening exams are offered by third party providers from universities, labor unions,...

  18. University of Puerto Rico Medical Science Campus

    E-Print Network [OSTI]

    Quirk, Gregory J.

    University of Puerto Rico Medical Science Campus Human Research Subjects Protection Office Main Building, 2nd Floor, Suite A-236A San Juan, Puerto Rico 00956 IRBWISE ACCOUNT REQUEST PERSONAL INFORMATION

  19. Preserving con dentiality when sharing medical database the Cellsecu system

    E-Print Network [OSTI]

    Chen, Sheng-Wei

    , with the rapid advances in the computerization of medical data, the question of protecting medical recordsPreserving con dentiality when sharing medical database the Cellsecu system Yu-Cheng Chiang y that contains sensitive information in medical database by automatically removing, generalizing, and expanding

  20. Medical and Biohazardous Waste Generator's Guide (Revision 2)

    E-Print Network [OSTI]

    Waste Management Group

    2006-01-01T23:59:59.000Z

    Solid Medical Waste Disposal Procedures Chart Sharps Container Used for ? All: Quick Links Benchtop Treatment

  1. Management of hazardous medical waste in Croatia

    SciTech Connect (OSTI)

    Marinkovic, Natalija [Medical School University of Zagreb, Department for Chemistry and Biochemistry, Salata 3b, 10 000 Zagreb (Croatia)], E-mail: nmarinko@snz.hr; Vitale, Ksenija; Holcer, Natasa Janev; Dzakula, Aleksandar ['Andrija Stampar' School of Public Health, Medical School University of Zagreb, Rockefellerova 4, 10 000 Zagreb (Croatia); Pavic, Tomo [Ministry of Health and Social Welfare, Ksaver 200, 10 000 Zagreb (Croatia)

    2008-07-01T23:59:59.000Z

    This article provides a review of hazardous medical waste production and its management in Croatia. Even though Croatian regulations define all steps in the waste management chain, implementation of those steps is one of the country's greatest issues. Improper practice is evident from the point of waste production to final disposal. The biggest producers of hazardous medical waste are hospitals that do not implement existing legislation, due to the lack of education and funds. Information on quantities, type and flow of medical waste are inadequate, as is sanitary control. We propose an integrated approach to medical waste management based on a hierarchical structure from the point of generation to its disposal. Priority is given to the reduction of the amounts and potential for harm. Where this is not possible, management includes reduction by sorting and separating, pretreatment on site, safe transportation, final treatment and sanitary disposal. Preferred methods should be the least harmful for human health and the environment. Integrated medical waste management could greatly reduce quantities and consequently financial strains. Landfilling is the predominant route of disposal in Croatia, although the authors believe that incineration is the most appropriate method. In a country such as Croatia, a number of small incinerators would be the most economical solution.

  2. Medical information and the right to privacy

    SciTech Connect (OSTI)

    Drell, D. [ed.

    1994-06-01T23:59:59.000Z

    This report is a compilation of submitted abstracts of papers presented at the DOE-supported workshop on medical information and the right to privacy held at the National Academy of Sciences in Washington, DC, on June 9 and 10, 1994. The aim of this meeting is to provide a forum to discuss the legal, ethical and practical issues related to the computerization and use of medical data, as well as the potential impact the use of these data may have on an individual`s privacy. Topical areas include an overview of the Federal and legal requirements to collect medical data, historical experiences with worker screening programs, currently available medical surveillance technologies (both biomedical and computer technologies) and their limitations. In addition, an-depth assessment of the needs and interests of a wide spectrum of parties as they relate to the use of medical data from both a legal and privacy perspective is provided. The needs of the individual, the public (e.g., blood and tissue banks), private enterprises (e.g., industry and insurance carriers), and the government (e.g., FBI) are discussed. Finally, the practical and legal issues relating to the use of computers to carry, store and transmit this information are also examined. The abstracts are presented in the intended order of presentation as indicated in the agenda for the meeting.

  3. Medical Remote Monitoring using sound environment analysis and wearable sensors 1 Medical Remote Monitoring using sound

    E-Print Network [OSTI]

    Paris-Sud XI, Université de

    Medical Remote Monitoring using sound environment analysis and wearable sensors 1 X Medical Remote Monitoring using sound environment analysis and wearable sensors Dan Istrate1, Jérôme Boudy2, Hamid Medjahed1. In Europe, for example, the life expectancy for men is about 71 years and for women about 79 years

  4. IEEE TRANSACTIONS ON MEDICAL IMAGING, VOL. 32, NO. 7, JULY 2013 1 Deformable Medical Image Registration: A Survey

    E-Print Network [OSTI]

    Paris-Sud XI, Université de

    recent advances in the domain. Additional emphasis has been given to techniques applied to medical imagesIEEE TRANSACTIONS ON MEDICAL IMAGING, VOL. 32, NO. 7, JULY 2013 1 Deformable Medical Image Paragios, Fellow, IEEE Abstract--Deformable image registration is a fundamental task in medical image

  5. Medical Monitoring Exam - HPMC Occupational Health Services

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645U.S. DOEThe Bonneville PowerCherries 82981-1cnHighand Retrievals from a NewCuneoTechnologyCHPRC NewsMarchMedicalMedical

  6. Research position in maternity at Hannover Medical School, Hannover Medical School is one of the leading medical universities in Germany with

    E-Print Network [OSTI]

    Manstein, Dietmar J.

    Research position in maternity at Hannover Medical School, Germany Hannover Medical School is one of the leading medical universities in Germany with excellent results in health care, research, education. In 2009, the only MSc Midwifery Programme in Germany was launched as part of the European Master

  7. Emergency Medical Rescue in a Radiation Environment

    SciTech Connect (OSTI)

    Briesmeister, L.; Ellington, Y.; Hollis, R.; Kunzman, J.; McNaughton, M.; Ramsey, G.; Somers, B.; Turner, A.; Finn, J.

    1999-09-14T23:59:59.000Z

    Previous experience with emergency medical rescues in the presence of radiation or contamination indicates that the training provided to emergency responders is not always appropriate. A new course developed at Los Alamos includes specific procedures for emergency response in a variety of radiological conditions.

  8. SUMMER ARCHITECTURE ACADEMY HOUSING AND MEDICAL

    E-Print Network [OSTI]

    SUMMER ARCHITECTURE ACADEMY HOUSING AND MEDICAL INFORMATION AND AUTHORIZATION FOR STUDENTS UNDER 18 YEARS OLD To: Summer Architecture Academy students and parents From: University of Oregon Department of Architecture We are looking forward to another exciting and educational Summer Architecture Academy. Many

  9. MEDICAL COLLEGE OF WISCONSIN Public Safety

    E-Print Network [OSTI]

    student from entering clerkship. At any time during an investigation, lockers are subject to searchMEDICAL COLLEGE OF WISCONSIN Public Safety Student Locker Assignment Record The following terms without prior notice. Your signature below indicates you have read and understand the terms and conditions

  10. Johns Hopkins Medical Campus Shuttle Services

    E-Print Network [OSTI]

    Shadmehr, Reza

    NBlaustein Research Building - Kimmel Cancer Center 6D 8 Children's House 4J 9 Cooley Center 3D 10 Credit Union 3K 11 1830 Building 2H 12 Hackerman-Patz House 5J 13 Hampton House 3D 14 HunJohns Hopkins Medical Campus Shuttle Services Free patient courtesy shuttle bus service

  11. Melanie I. Stefan Harvard Medical School

    E-Print Network [OSTI]

    Stefan, Melanie

    Melanie I. Stefan Harvard Medical School Gordon Hall Room 316 25 Shattuck St Boston, MA 02115, USA B melanie_stefan@hms.harvard.edu http://www.melaniestefan.net Research experience since Jul 2013. Keys, M. I. Stefan, C. S. Gillespie, P. Poulain, K. Shameer, R. Sugar, B. M. Invergo, L. J. Jensen, J

  12. Report of Refrigerated Medication Loss UConn Health

    E-Print Network [OSTI]

    Oliver, Douglas L.

    Report of Refrigerated Medication Loss UConn Health Please complete form & return to John Dempsey Other (Specify): Phone: E-mail: Address: Location of Refrigerator Affected: Date/time refrigerator was out of temperature range: Describe the event below: How long was the refrigerator out of range (hours

  13. MASTER'S OF ADVANCED STUDIES IN MEDICAL PHYSICS

    E-Print Network [OSTI]

    -2016 Trieste University Hospital Miramare, Trieste, Italy The Abdus Salam International Centre for Theoretical Physics (ICTP) has initiated the first ICTP and Trieste University Master's of Advanced Studies in Medical of Science (TWAS) with the patronage of the Trieste University Hospital. The Master's Degree will be awarded

  14. SchoolofMedicalSciences BSc (Hons) Immunology

    E-Print Network [OSTI]

    Levi, Ran

    Catalogue of Courses or SMS World Wide Web Pages for names). The Head of School of Medical Sciences incorporates a wide variety of biological disciplines. It explores the cells and molecules involved in defence, and in the transferable skills associated with mastering statistics, graphics and word processing software packages

  15. HEALTH AND MEDICAL RESEARCH STRATEGIC REVIEW

    E-Print Network [OSTI]

    Viglas, Anastasios

    with the Health System, Including Allied Health And Primary Health Care 17 Theme Three: Scale, Scope engagement with the health system including Allied Health and Primary Health Care 28 Scale, scopeHEALTH AND MEDICAL RESEARCH STRATEGIC REVIEW ISSUES PAPER 29 OCTOBER 2012 #12;#12;CONTENTS The Vice

  16. Protecting Privacy in Computerized Medical Information

    E-Print Network [OSTI]

    McCurley, Kevin

    ). #12;Foreword T he Clinton administration's health care reform proposal, announced by the President costs and improve health care delivery. By linking computerized health informa- tion through a national to improve patient care and expand resources for medical research and education, while lowering health care

  17. User Experience in Medical Search Engines

    E-Print Network [OSTI]

    User Experience in Medical Search Engines Róbert Andri Kristjánsson Kongens Lyngby 2014 IMM.imm.dtu.dk IMM-MSc-2014-???? #12;Summary (English) FindZebra.com is a specialized search engine for rare diseases that has been de- veloped to as an improvement to standard search engines. FindZebra.com has been shown

  18. University of Puerto Rico Medical Sciences Campus

    E-Print Network [OSTI]

    Quirk, Gregory J.

    University of Puerto Rico Medical Sciences Campus School of Medicine Division of Biomedical. Opportunities for Combine M.D./Ph.D. Studies 95 Mayo Foundation and University of Puerto Rico Integrated MD-PhD The MD-PhD Program at the University of Puerto Rico-School of Medicine VIII. Multidisciplinary Tracts 105

  19. Advanced Instruments, Inc. Applied Medical Resources

    E-Print Network [OSTI]

    Vajda, Sandor

    Cynosure Davol - C.R. Bard, Inc. Decision Resources DEKA Research and Development Corporation DePuy Spine, Inc. DocBox, Inc. Draeger Medical Systems, Inc. Eastman Kodak Company Eaton-Peabody Laboratory Elm USA-CMI GE Healthcare Gems Sensors Genzyme Corporation Goodyear-Veyance Technologies, Inc. Harvard

  20. AIR CONDITIONER REQUEST EXTREME MEDICAL CIRCUMSTANCES

    E-Print Network [OSTI]

    AIR CONDITIONER REQUEST DUE TO EXTREME MEDICAL CIRCUMSTANCES TO BE COMPLETED BY ATTENDING Moderate Significant Is the use of an air conditioner desirable Yes No OR essential Yes No to the management of allergy? Is the use of an air conditioner

  1. Contractor Employee Pension and Medical Benefits Policy

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    2006-06-19T23:59:59.000Z

    To ensure that reimbursement of costs incurred by Department of Energy (DOE) contractors' pension and medical benefits are reasonable in accordance with applicable laws, regulations and contract requirements and reflect prudent business practices. This directive has been suspended as of June 19, 2006, for 1 year. For more information, see DOE N 251.66.

  2. Former worekrs' notification adn medical screening Hanford

    SciTech Connect (OSTI)

    Patricia Quinn

    2005-11-30T23:59:59.000Z

    CPWR is carrying out a screening program for former Hanford construction workers. This program includes continuing screening and re-screening services for the former worker population. The Program contains the following general components: Start-up planning/needs assessment: A modified exposure assessment will be conducted to identify high-risk buildings or areas, primary exposures, and worker populations at risk. Outreach: CPWR, as the research arm of the Building and Construction Trades Department, AFL-CIO, has direct access to workers. CPWR will rely on direct mailings to lists of former workers, and work through and rely on existing organizations (unions, union pension funds, employers, DOE site administrators, etc.) to reach former workers and "get the word out." CPWR will establish/maintain an outreach office at each site listed above. This office will serve as the face of the Program to workers and their communities. Communications and intake center: CPWR has two established toll-free phone numbers (1-800-866-9663 and 1-888-464-0009). There is also a dedicated website for the program (btmed.org). Workers can register with the Program by mail, telephone, or on-line. Work history: A standardized, structured work history is administered with modules that accommodate unique exposure scenarios for different occupations and different DOE sites. A work history interview is administered by a trained program interviewer. The work histories are used to determine whether a participant is eligible for the medical examination and to interpret the findings from the medical examination. Medical evaluation: The Program contracts with local medical providers qualified to deliver occupational medical screening services. All providers are credentialed. The Program contracts with a certified national laboratory and with NIOSH certified B-readers to review x-rays. Based on the work history, the participant is referred to a credentialed medical provider who is located close to the participant's home. If it is not convenient to use a credentialed provider, the Program will make arrangements, if necessary, for the participant to receive a physical exam through the National Supplemental Screening Program. Eligible participants will receive the same core medical exam (including a Beryllium Lymphocyte Proliferation Test, BeLPT), and in addition, based on their work history, they may be assigned to exposure specific modules for asbestos, silica, lead, noise, cadmium, and chromium. Lab work will be sent to a national laboratory for processing, except the blood samples for the BeLPT, which will be sent to a DOE-approved laboratory for evaluation. Determination of work-relatedness and follow-up: A letter of findings will be sent to the participant within 60 days of the exam. The letter is written and/or reviewed by occupational medical health personnel with knowledge of the DOE site(s) where the participant has worked and will include specific follow-up recommendations. Urgent findings are followed up by the provider without delay. Evaluation and quality assurance: All data are entered into the Program Data Management System (DMS). The DMS is web-based and relies on electronic submission of results, whenever possible. A de-identified data set on all participants is provided to Duke University Medical Center for evaluation and analysis. Each participant is asked to complete a satisfaction survey. The DMS will be used for quality assurance purposes and to also report summary data to the DOE. The BTMED.ORG website is encrypted using the industry-standard Secure Sockets Layer (SSL) technology (128-bit encryption keys). Each individual that accesses the website is assigned a unique login ID, password, and token. Passwords are required to meet standards for "strength," including minimum length, multi-case, and use of numbers. The website is also protected by additional security layers including additional encryption, hardware and software firewalls, Virtual Private Networks (VPNs), and virus protection.

  3. Strategic inventory management of externally sourced medical devices

    E-Print Network [OSTI]

    Hillstrom, Nichole L. (Nichole Leigh)

    2013-01-01T23:59:59.000Z

    The purpose of this research was to determine inventory strategies for externally sourced medical devices. In the medical device industry, the desire for high levels of customer service often results in less than optimal ...

  4. Model for a web based medical technology assessment system

    E-Print Network [OSTI]

    Prabhu, Gopal

    1999-01-01T23:59:59.000Z

    Technology is the primary driving force for change in today's healthcare environment. Understanding the dynamics of medical technology and applying probative management measures can be accomplished with a medical technology assessment program...

  5. A medication extraction framework for electronic health records

    E-Print Network [OSTI]

    Bodnari, Andreea

    2012-01-01T23:59:59.000Z

    This thesis addresses the problem of concept and relation extraction in medical documents. We present a medical concept and relation extraction system (medNERR) that incorporates hand-built rules and constrained conditional ...

  6. Nanotechnology Medical Applications Breakthroughs in nanotechnology promise to revolutionize drug

    E-Print Network [OSTI]

    Hill, Wendell T.

    Nanotechnology Medical Applications Breakthroughs in nanotechnology promise to revolutionize drug manufacturing, drug delivery, and medical diagnostics. By learning how substances behave differently's Nanotechnology Center are creating novel tools and developing new methods for crucial research areas of drug

  7. Jackson Park Hospital Green Building Medical Center

    SciTech Connect (OSTI)

    William Dorsey; Nelson Vasquez

    2010-03-31T23:59:59.000Z

    Jackson Park Hospital completed the construction of a new Medical Office Building on its campus this spring. The new building construction has adopted the City of Chicago's recent focus on protecting the environment, and conserving energy and resources, with the introduction of green building codes. Located in a poor, inner city neighborhood on the South side of Chicago, Jackson Park Hospital has chosen green building strategies to help make the area a better place to live and work. The new green building houses the hospital's Family Medicine Residency Program and Specialty Medical Offices. The residency program has been vital in attracting new, young physicians to this medically underserved area. The new outpatient center will also help to allure needed medical providers to the community. The facility also has areas designated to women's health and community education. The Community Education Conference Room will provide learning opportunities to area residents. Emphasis will be placed on conserving resources and protecting our environment, as well as providing information on healthcare access and preventive medicine. The new Medical Office Building was constructed with numerous energy saving features. The exterior cladding of the building is an innovative, locally-manufactured precast concrete panel system with integral insulation that achieves an R-value in excess of building code requirements. The roof is a 'green roof' covered by native plantings, lessening the impact solar heat gain on the building, and reducing air conditioning requirements. The windows are low-E, tinted, and insulated to reduce cooling requirements in summer and heating requirements in winter. The main entrance has an air lock to prevent unconditioned air from entering the building and impacting interior air temperatures. Since much of the traffic in and out of the office building comes from the adjacent Jackson Park Hospital, a pedestrian bridge connects the two buildings, further decreasing the amount of unconditioned air that enters the office building. The HVAC system has an Energy Efficiency Rating 29% greater than required. No CFC based refrigerants were used in the HVAC system, thus reducing the emission of compounds that contribute to ozone depletion and global warming. In addition, interior light fixtures employ the latest energy-efficient lamp and ballast technology. Interior lighting throughout the building is operated by sensors that will automatically turn off lights inside a room when the room is unoccupied. The electrical traction elevators use less energy than typical elevators, and they are made of 95% recycled material. Further, locally manufactured products were used throughout, minimizing the amount of energy required to construct this building. The primary objective was to construct a 30,000 square foot medical office building on the Jackson Park Hospital campus that would comply with newly adopted City of Chicago green building codes focusing on protecting the environment and conserving energy and resources. The energy saving systems demonstrate a state of the-art whole-building approach to energy efficient design and construction. The energy efficiency and green aspects of the building contribute to the community by emphasizing the environmental and economic benefits of conserving resources. The building highlights the integration of Chicago's new green building codes into a poor, inner city neighborhood project and it is designed to attract medical providers and physicians to a medically underserved area.

  8. Coordinating Pediatric Medical Care during an Influenza Pandemic - Hospital Workbook

    SciTech Connect (OSTI)

    HCTT CHE

    2010-01-01T23:59:59.000Z

    This workbook is intended to assist hospitals with coordinating medical care for pediatric influenza-like illness across their community.

  9. 2015 Market Research Report on Global Medical Grade Dioctyl Industry...

    Open Energy Info (EERE)

    2015 Market Research Report on Global Medical Grade Dioctyl Industry Home There are currently no posts in this category. Syndicate...

  10. Jackson Park Hospital Green Building Medical Center

    SciTech Connect (OSTI)

    William Dorsey; Nelson Vasquez

    2010-03-01T23:59:59.000Z

    Jackson Park Hospital completed the construction of a new Medical Office Building on its campus this spring. The new building construction has adopted the City of Chicago�s recent focus on protecting the environment, and conserving energy and resources, with the introduction of green building codes. Located in a poor, inner city neighborhood on the South side of Chicago, Jackson Park Hospital has chosen green building strategies to help make the area a better place to live and work.

  11. Medical expense deduction for the individual taxpayer

    E-Print Network [OSTI]

    Winters, Gerald Milton

    1960-01-01T23:59:59.000Z

    , cure, mitigation, treatment, or prevention of disease, or for the purpose of affecting any structure or function of the body (including amounts paid for accident or health insurance), (1) A husband and wife who file a joint return may deduct only... primarily for and essential to the rendition of medical services or the prevention or alleviation of a physical or mental defect. Transportation made for improvement of general health is not deductible. The costs of meals and lodgings incurred while away...

  12. Ultrafine-grained titanium for medical implants

    DOE Patents [OSTI]

    Zhu, Yuntian T. (Los Alamos, NM); Lowe, Terry C. (Santa Fe, NM); Valiev, Ruslan Z. (Ufa, RU); Stolyarov, Vladimir V. (Ufa, RU); Latysh, Vladimir V. (Ufa, RU); Raab, Georgy J. (Ufa, RU)

    2002-01-01T23:59:59.000Z

    We disclose ultrafine-grained titanium. A coarse-grained titanium billet is subjected to multiple extrusions through a preheated equal channel angular extrusion (ECAE) die, with billet rotation between subsequent extrusions. The resulting billet is cold processed by cold rolling and/or cold extrusion, with optional annealing. The resulting ultrafine-grained titanium has greatly improved mechanical properties and is used to make medical implants.

  13. Medical Image Registration: A Quick Win

    E-Print Network [OSTI]

    Ansorge, Richard

    2008-11-11T23:59:59.000Z

    Medical Image Registration A Quick Win Richard Ansorge The problem CT, MRI, PET and Ultrasound produce 3D volume images Typically 256 x 256 x 256 = 16,777,216 image voxels. Combining modalities (inter modality) gives extra information. Repeated... imaging over time same modality, e.g. MRI, (intra modality) equally important. Have to spatially register the images. Example – brain lesion CT MRI PET PET-MR Fusion The PET image shows...

  14. Cogeneration at Iowa Methodist Medical Center

    E-Print Network [OSTI]

    Thunem, C. B.; Schebler, S. J.; Love, G. I.

    Medical Center of Des Moines, Iowa, is installing two 1,500 kW Fairbanks Morse turbocharged dual-fuel reciprocating engine generators. The system will be installed with re covery of exhaust waste heat as steam and jacket, lube Oil, and intercooler... waste heat as hot water. During periods of high steam demand, the waste heat boilers will be supplementally fired for additional steam production. The paper will present the feasibility study, predesign report, and detailed design results. Both gas...

  15. 0 | P a g e Economic Impact of Medical

    E-Print Network [OSTI]

    Walker, Lawrence R.

    for Consideration 7 Economic Impact Evaluation of Medical School Models 8 Facility Considerations 10 Key Findings 110 | P a g e Economic Impact of Medical Education Expansion in Nevada EconomicImpact Assessment Table of Contents Page Introduction 2 Evaluation of Market Needs 3 Medical School Models

  16. Medical Multimedia and Multimodality Databases Systems Peter L. Stanchev

    E-Print Network [OSTI]

    Stanchev, Peter

    multimedia systems, Medical images, Databases 1. INTRODCTION Recent advances in computer technologyMedical Multimedia and Multimodality Databases Systems Peter L. Stanchev Kettering University, Michigan, 48202 USA fotouhi@cs.wayne.edu ABSTRACT In this paper we make a review of some medical

  17. An Event Set Approach to Sequence Discovery in Medical Data

    E-Print Network [OSTI]

    Cook, Diane J.

    are many. With advances in medical technology have come many methods for treating such illnesses. AnalysisAn Event Set Approach to Sequence Discovery in Medical Data Jorge C. G. Ramirez1,2 , Diane J. Cook1, University of Texas Southwestern Medical Center, Dallas, TX, USA 75235-9103 dpeter@mednet.swmed.edu Contact

  18. University of Rochester Medical Center Advancement Major Gifts

    E-Print Network [OSTI]

    Portman, Douglas

    University of Rochester Medical Center Advancement Major Gifts Major Gift Officer, Neuromedicine, Medical Center department faculty and chairs, University Advancement Major Gift Officers and the overall medical center advancement team. The Director is expected to be a full and active member of the Major Gift

  19. Securing the Sustainability of Global Medical Nuclear Supply Chains

    E-Print Network [OSTI]

    Nagurney, Anna

    Securing the Sustainability of Global Medical Nuclear Supply Chains Through Economic Cost Recovery-17, 2012 University of Massachusetts Amherst Securing the Sustainability of Medical Nuclear Supply Chains-2013. University of Massachusetts Amherst Securing the Sustainability of Medical Nuclear Supply Chains #12;This

  20. Medical Plan Detail Document for Funded Graduate Students

    E-Print Network [OSTI]

    2004-05 Medical Plan Detail Document for Funded Graduate Students Program Provisions for Status Change Medical/Prescription Drug Card Medical Care Outside Ohio Dual Coverage Case Management Managed Health Care Systems (MHCS) 19 How Payment Is Determined 20 Annual Deductible Annual Out

  1. EPIDEMIOLOGICAL STUDIES ON RADIATION CARCINOGENESIS IN HUMAN POPULATIONS FOLLOWING ACUTE EXPOSURE: NUCLEAR EXPLOSIONS AND MEDICAL RADIATION

    E-Print Network [OSTI]

    Fabrikant, J.I.

    2010-01-01T23:59:59.000Z

    EXPOSURE: NUCLEAR EXPLOSIONS AND MEDICAL RADIATION . Jacobexposed to nuclear explosions and medical radiation. Sinceto nuclear explo ions or medical radiation, describes the

  2. DETERMINATION OF AGE AND GENDER DIFFERENCES IN BIOCHEMICAL PROCESSES AFFECTING THE DISPOSITION OF 2-BUTOXYETHANOL AND ITS METABOLITES IN MICE AND RATS TO IMPROVE PBPK MODELING

    SciTech Connect (OSTI)

    Corley, Rick A.; Grant, Donna M.; Farris, Elizabeth; Weitz, Karl K.; Soelberg, Jolen J.; Thrall, K D.; Poet, Torka S.

    2005-03-28T23:59:59.000Z

    2-Butoxyethanol (BE) is the most widely used glycol ether solvent. BE's major metabolite, butoxyacetic acid (BAA), causes hemolysis with significant species differences in sensitivity. Several PBPK models have been developed over the past two decades to describe the disposition of BE and BAA in male rats and humans to refine health risk assessments. More recent efforts by Lee et al. (1998) to describe the kinetics of BE and BAA in the National Toxicology Program (NTP) chronic inhalation studies required the use of several assumptions to extrapolate model parameters from earlier PBPK models developed for young male rats to include female F344 and both sexes of B6C3F1 mice and the effects of aging. To replace these assumptions, studies were conducted to determine the impact of age, gender and species on the metabolism of BE, and the tissue partitioning, renal acid transport and plasma protein binding of BAA. In the current study, the Lee et al. PBPK model was updated and expanded to include the further metabolism of BAA and the salivary excretion of BE and BAA which may contribute to the forestomach irritation observed in mice in the NTP study. The revised model predicted that peak blood concentrations of BAA achieved following 6-hr inhalation exposures are greatest in young adult female rats at concentrations up to 300 ppm. This is not the case predicted for old (>18 months) animals, where peak blood concentrations of BAA in male and female mice were similar to or greater than female rats. The revised model serves as a quantitative tool for integrating an extensive pharmacokinetic and mechanistic database into a format that can readily be used to compare internal dosimetry across dose, route of exposure and species.

  3. Materials for Medical Devices New materials have played a crucial role in the advancement of medical devices. For

    E-Print Network [OSTI]

    Li, Mo

    Materials for Medical Devices New materials have played a crucial role in the advancement of medical devices. For example, the introduction of titanium alloys provided a high strength basis

  4. Association of Medical Editors (WAME) and

    E-Print Network [OSTI]

    Dinesh M. Parmar

    I am indeed delighted to say that we are entering in the world of biomedical communications through the Journal of Clinical & Experimental Research (JCER), a multidisciplinary, peer reviewed, open access, online & print journal which invites submission of high quality manuscripts from all the medical disciplines in the field of clinical and experimental research. As the standard of a journal depends on its contributors, the JCER expects submission of scholarly manuscripts from the researchers. The JCER will follow the publication ethics guidelines developed by the International Committee of

  5. Medical Radioisotope Data Survey: 2002 Preliminary Results

    SciTech Connect (OSTI)

    Siciliano, Edward R.

    2004-06-23T23:59:59.000Z

    A limited, but accurate amount of detailed information about the radioactive isotopes used in the U.S. for medical procedures was collected from a local hospital and from a recent report on the U.S. Radiopharmaceutical Markets. These data included the total number of procedures, the specific types of procedures, the specific radioisotopes used in these procedures, and the dosage administered per procedure. The information from these sources was compiled, assessed, pruned, and then merged into a single, comprehensive and consistent set of results presented in this report. (PIET-43471-TM-197)

  6. Improved medical implants comes from nanostructuring

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645U.S. DOE Office of Science (SC) EnvironmentalGyroSolé(tm)HydrogenRFP » Important Trinity / NERSC-8Improved medical

  7. ORISE: Worker Health Studies - Medical Data Management

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645U.S. DOE Office of Science (SC)Integrated CodesTransparencyDOENurseResourcesThe Value The U.S.Medical Data Management

  8. Medical Exam Scheduling - HPMC Occupational Health Services

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645U.S. DOEThe Bonneville PowerCherries 82981-1cnHighand Retrievals from a NewCuneoTechnologyCHPRC NewsMarchMedical Exam

  9. Medical Exams - HPMC Occupational Health Services

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645U.S. DOEThe Bonneville PowerCherries 82981-1cnHighand Retrievals from a NewCuneoTechnologyCHPRC NewsMarchMedical

  10. ahip fmla medical: Topics by E-print Network

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Medical Assisting Mathematics Websites Summary: Radiologic Technology Respiratory Care Surgical Technology www.cte.umt.edu Department of Health Professions who are also...

  11. anticoagulant medication requiring: Topics by E-print Network

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    , published in "Medical Informatics in a United and Healthy Europe, Sarajevo : Bosnia And Herzegovina (2009 and work interruptions that, as known, are one of the causes of...

  12. Radioisotopes for Medical Diagnostics and Cancer Therapy at BNL...

    Office of Science (SC) Website

    Excess pulses (90%) are diverted to BLIP for medical radioisotope research and production. Major current projects include large scale distribution of Sr-82 for heart scans,...

  13. advanced medical therapy: Topics by E-print Network

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    are proud to offer a comprehensive and interactive online resource for your continuing Weber, David J. 2 Advanced Instruments, Inc. Applied Medical Resources Biotechnology...

  14. american medical education: Topics by E-print Network

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Graduate Medical Education Committee (GMEC) Policy on Accommodations for Disabilities Fossil Fuels Websites Summary: programs. We will adhere to all applicable federal and state...

  15. automated medical information: Topics by E-print Network

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    is an information business, tourists have to rely on the information available 4 Automation and Integration of Components for Generalized Semantic Markup of Electronic Medical...

  16. acute medical problems: Topics by E-print Network

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    areas of science and technology including medical imaging, geophysics, nondestructive testing, industrial process monitoring, remote sensing, and pricing Computer Technologies and...

  17. Medical bioremediation: Prospects for the application of microbial catabolic diversity

    E-Print Network [OSTI]

    Alvarez, Pedro J.

    Review Medical bioremediation: Prospects for the application of microbial catabolic diversity-effects. # 2005 Elsevier Ireland Ltd. All rights reserved. Keywords: Aggregates; Lysosomes; Bioremediation

  18. african medical staff: Topics by E-print Network

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    to implement the Biology and Medicine Websites Summary: with you: keys, wallet, eyeglasses, medications, etc. Shut down critical equipment in the areaEvacuation Expectations...

  19. Microfluidic Facility, Harvard Medical School UVO-42 Operation Manual

    E-Print Network [OSTI]

    Paulsson, Johan

    Microfluidic Facility, Harvard Medical School UVO-42 Operation Manual 1. Load the substrate then be opened the tray removed, and the parts unloaded. Calixto Saenz, Microfluidic Facility

  20. american medical colleges: Topics by E-print Network

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Page Topic Index 1 1Genetics in medicine American College of Medical Genetics and Genomics special article Biology and Medicine Websites Summary: ; customer information;...

  1. Molecule Nanoweaver Creates High-Tech Medical Patches and Multilayered...

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Molecule Nanoweaver Creates High-Tech Medical Patches and Multilayered Capsules Technology available for licensing: Molecule Nanoweaver, a unique tool that can be used as both a...

  2. ambulatory medical care: Topics by E-print Network

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    about the MethodsThe data presented in this report were collected in the 2003 National health care provided by hospital Hospital Ambulatory Medical Care Survey (NHAMCS). NHAMCS...

  3. antipsychotic medication adherence: Topics by E-print Network

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Clifford, Lucinda Jane 2013-01-01 2 Chronic medication adherence: its association with health care costs. Open Access Theses and Dissertations Summary: ??Effective treatment for...

  4. affairs medical center: Topics by E-print Network

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    to meet their unique needs," said commission Bogyo, Matthew 10 Faculty and Staff Handbook The University of Mississippi Medical Center Biology and Medicine Websites...

  5. affairs medical centers: Topics by E-print Network

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    to meet their unique needs," said commission Bogyo, Matthew 10 Faculty and Staff Handbook The University of Mississippi Medical Center Biology and Medicine Websites...

  6. Multi-channel medical imaging system

    DOE Patents [OSTI]

    Frangioni, John V

    2013-12-31T23:59:59.000Z

    A medical imaging system provides simultaneous rendering of visible light and fluorescent images. The system may employ dyes in a small-molecule form that remain in the subject's blood stream for several minutes, allowing real-time imaging of the subject's circulatory system superimposed upon a conventional, visible light image of the subject. The system may provide an excitation light source to excite the fluorescent substance and a visible light source for general illumination within the same optical guide used to capture images. The system may be configured for use in open surgical procedures by providing an operating area that is closed to ambient light. The systems described herein provide two or more diagnostic imaging channels for capture of multiple, concurrent diagnostic images and may be used where a visible light image may be usefully supplemented by two or more images that are independently marked for functional interest.

  7. Nuclear Materials Stewardship Within the DOE Environmental Management Program

    SciTech Connect (OSTI)

    Bilyeu, J. D.; Kiess, T. E.; Gates, M. L.

    2002-02-26T23:59:59.000Z

    The Department of Energy (DOE) Environmental Management (EM) Program has made significant progress in planning disposition of its excess nuclear materials and has recently completed several noteworthy studies. Since establishment in 1997, the EM Nuclear Material Stewardship Program has developed disposition plans for excess nuclear materials to support facility deactivation. All nuclear materials have been removed from the Miamisburg Environmental Management Project (Mound), and disposition planning is nearing completion for the Fernald Environmental Management Project and the Rocky Flats Environmental Technology Site. Only a few issues remain for materials at the Hanford and Idaho sites. Recent trade studies include the Savannah River Site Canyons Nuclear Materials Identification Study, a Cesium/Strontium Management Alternatives Trade Study, a Liquid Technical Standards Trade Study, an Irradiated Beryllium Reflectors with Tritium study, a Special Performance Assessment Required Trade Study, a Neutron Source Trade Study, and development of discard criteria for uranium. A Small Sites Workshop was also held. Potential and planned future activities include updating the Plutonium-239 storage study, developing additional packaging standards, developing a Nuclear Material Disposition Handbook, determining how to recover or dispose of Pu-244 and U-233, and working with additional sites to define disposition plans for their nuclear materials.

  8. On Going TRU Waste Disposition

    SciTech Connect (OSTI)

    Cody, Tom

    2010-01-01T23:59:59.000Z

    The ongoing effort to contain dangerous, radioactive TRU waste. Under the Recovery Act, the Savannah River Site is able to safely test and transport these items to WIPP in Carlsbad, New Mexico.

  9. On Going TRU Waste Disposition

    ScienceCinema (OSTI)

    Cody, Tom

    2012-06-14T23:59:59.000Z

    The ongoing effort to contain dangerous, radioactive TRU waste. Under the Recovery Act, the Savannah River Site is able to safely test and transport these items to WIPP in Carlsbad, New Mexico.

  10. Disposition of Depleted Uranium Oxide

    SciTech Connect (OSTI)

    Crandall, J.L.

    2001-08-13T23:59:59.000Z

    This document summarizes environmental information which has been collected up to June 1983 at Savannah River Plant. Of particular interest is an updating of dose estimates from changes in methodology of calculation, lower cesium transport estimates from Steel Creek, and new sports fish consumption data for the Savannah River. The status of various permitting requirements are also discussed.

  11. Must Dispositions Have A Basis?

    E-Print Network [OSTI]

    Hoffman, Joshua

    that even if one grants the possibilities on which these three objections to ET are based, it does not follow that ET is false. Hence, none of these objections are sufficient to refute ET. In the first section of this paper I shall explicate ET... some IC or set of ICs b is consistent with glass b's having £ and not having d. Hence, unless NNLs are impossible, (ii) is false. In other words, the possibility of SI does not by itself entail the falsity of ET; instead, the possibility of SI...

  12. Disposition Schedules | Department of Energy

    Energy Savers [EERE]

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page onYou are now leaving Energy.gov You are now leaving Energy.gov You are being directed off Energy.gov. Are you sure you want toworldPowerHome | DepartmentDeveloper

  13. Facility Disposition Safety Strategy RM

    Office of Environmental Management (EM)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742 33 1112011 Strategic Plan| Department of.pdf6-OPAMDepartment6 FY 2007FY 2014Facilities

  14. REQUEST FOR RECORDS DISPOSITION AUTHORITY

    Broader source: Energy.gov (indexed) [DOE]

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742EnergyOn April 23, 2014, an OHASeptember 2010In addition to 1 |D I S P U REPORT ofREPOWERINGFOR

  15. BLENDING STUDY FOR SRR SALT DISPOSITION INTEGRATION: TANK 50H SCALE-MODELING AND COMPUTER-MODELING FOR BLENDING PUMP DESIGN, PHASE 2

    SciTech Connect (OSTI)

    Leishear, R.; Poirier, M.; Fowley, M.

    2011-05-26T23:59:59.000Z

    The Salt Disposition Integration (SDI) portfolio of projects provides the infrastructure within existing Liquid Waste facilities to support the startup and long term operation of the Salt Waste Processing Facility (SWPF). Within SDI, the Blend and Feed Project will equip existing waste tanks in the Tank Farms to serve as Blend Tanks where 300,000-800,000 gallons of salt solution will be blended in 1.3 million gallon tanks and qualified for use as feedstock for SWPF. Blending requires the miscible salt solutions from potentially multiple source tanks per batch to be well mixed without disturbing settled sludge solids that may be present in a Blend Tank. Disturbing solids may be problematic both from a feed quality perspective as well as from a process safety perspective where hydrogen release from the sludge is a potential flammability concern. To develop the necessary technical basis for the design and operation of blending equipment, Savannah River National Laboratory (SRNL) completed scaled blending and transfer pump tests and computational fluid dynamics (CFD) modeling. A 94 inch diameter pilot-scale blending tank, including tank internals such as the blending pump, transfer pump, removable cooling coils, and center column, were used in this research. The test tank represents a 1/10.85 scaled version of an 85 foot diameter, Type IIIA, nuclear waste tank that may be typical of Blend Tanks used in SDI. Specifically, Tank 50 was selected as the tank to be modeled per the SRR, Project Engineering Manager. SRNL blending tests investigated various fixed position, non-rotating, dual nozzle pump designs, including a blending pump model provided by the blend pump vendor, Curtiss Wright (CW). Primary research goals were to assess blending times and to evaluate incipient sludge disturbance for waste tanks. Incipient sludge disturbance was defined by SRR and SRNL as minor blending of settled sludge from the tank bottom into suspension due to blending pump operation, where the sludge level was shown to remain constant. To experimentally model the sludge layer, a very thin, pourable, sludge simulant was conservatively used for all testing. To experimentally model the liquid, supernate layer above the sludge in waste tanks, two salt solution simulants were used, which provided a bounding range of supernate properties. One solution was water (H{sub 2}O + NaOH), and the other was an inhibited, more viscous salt solution. The research performed and data obtained significantly advances the understanding of fluid mechanics, mixing theory and CFD modeling for nuclear waste tanks by benchmarking CFD results to actual experimental data. This research significantly bridges the gap between previous CFD models and actual field experiences in real waste tanks. A finding of the 2009, DOE, Slurry Retrieval, Pipeline Transport and Plugging, and Mixing Workshop was that CFD models were inadequate to assess blending processes in nuclear waste tanks. One recommendation from that Workshop was that a validation, or bench marking program be performed for CFD modeling versus experiment. This research provided experimental data to validate and correct CFD models as they apply to mixing and blending in nuclear waste tanks. Extensive SDI research was a significant step toward bench marking and applying CFD modeling. This research showed that CFD models not only agreed with experiment, but demonstrated that the large variance in actual experimental data accounts for misunderstood discrepancies between CFD models and experiments. Having documented this finding, SRNL was able to provide correction factors to be used with CFD models to statistically bound full scale CFD results. Through the use of pilot scale tests performed for both types of pumps and available engineering literature, SRNL demonstrated how to effectively apply CFD results to salt batch mixing in full scale waste tanks. In other words, CFD models were in error prior to development of experimental correction factors determined during this research, which provided a technique to use CFD models fo

  16. Junior Mini Medical School Program Gross...Seriously Gross

    E-Print Network [OSTI]

    of middle school students in the fields of science and medicine. They give kids who may be curious about at the University of Iowa. The University of Iowa Carver College of Medicine Mini Medical School programs openJunior Mini Medical School Program Gross...Seriously Gross UI Gross Anatomy The University of Iowa

  17. architecture based medical: Topics by E-print Network

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    architecture based medical First Page Previous Page 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 Next Page Last Page Topic Index 1 Medical Nanorobot...

  18. Level MSc 2013/14 Medical Radiation Physics

    E-Print Network [OSTI]

    Martin, Ralph R.

    and Clinical Engineering 10 Credits Dr. RP Hugtenburg EGRM09 Radiation Protection 10 Credits Dr. RP HugtenburgLevel MSc 2013/14 Medical Radiation Physics MSc Medical Radiation Physics Coordinator: Dr. RP/Mr. SC Evans EGRM03 Radiation Physics 10 Credits Dr. RP Hugtenburg EGRM10 Radiotherapy Physics 10 Credits

  19. MILXView: A medical imaging, analysis and visualization platform.

    E-Print Network [OSTI]

    Paris-Sud XI, Université de

    MILXView: A medical imaging, analysis and visualization platform. Neil Burdett1 , Jurgen Fripp1, Jurgen Fripp, Pierrick Bourgeat, Olivier Salvado}@csiro.au Abstract. Medical imaging is a vital clinical and research tool that has made significant strides in the last few decades with impressive advances

  20. Computing support for advanced medical data analysis and imaging

    E-Print Network [OSTI]

    Wi?licki, W; Bia?as, P; Czerwi?ski, E; Kap?on, ?; Kochanowski, A; Korcyl, G; Kowal, J; Kowalski, P; Kozik, T; Krzemie?, W; Molenda, M; Moskal, P; Nied?wiecki, S; Pa?ka, M; Pawlik, M; Raczy?ski, L; Rudy, Z; Salabura, P; Sharma, N G; Silarski, M; S?omski, A; Smyrski, J; Strzelecki, A; Wieczorek, A; Zieli?ski, M; Zo?, N

    2014-01-01T23:59:59.000Z

    We discuss computing issues for data analysis and image reconstruction of PET-TOF medical scanner or other medical scanning devices producing large volumes of data. Service architecture based on the grid and cloud concepts for distributed processing is proposed and critically discussed.

  1. Verification of Medical Guidelines Using Background Knowledge in Task Networks

    E-Print Network [OSTI]

    Groot, Perry

    and to formalize criteria for good medical practice that a guideline should comply with. This framework are mainly concerned with checking the general quality criteria of good medical practice that a guideline on sound scientific evidence, which has been called evidence-based medicine [1], [2]. In practice, this has

  2. Energy Optimization in Wireless Medical Systems Using Physiological Behavior

    E-Print Network [OSTI]

    Potkonjak, Miodrag

    Energy Optimization in Wireless Medical Systems Using Physiological Behavior Hyduke Noshadi, Foad pressure sen- sors placed in each shoe, which cover the bottom of the entire foot, resulting in energy, Algorithm, Performance Keywords Wearable Medical Systems, Energy Optimization, Sensor Se- Permission to make

  3. A Healthy Heritage Collecting for the Future of Medical History

    E-Print Network [OSTI]

    Rambaut, Andrew

    policies of medical libraries today 42 Iain Milne Mapping the future of research libraries 49 Derek Law of the Library which bears his name. Successive generations of librarians and archivists have nurtured and developed his legacy, sustaining his vision of the importance of preserving the medical record of the past

  4. Clinical Electives Program for Medical and Dental Students

    E-Print Network [OSTI]

    Baker, Chris I.

    Clinical Electives Program for Medical and Dental Students The National Institutes of Health (NIH) offers short term (four- to 12-week) clinically oriented elective rotations to senior medical or dental students in a multitude of specialty fields and biomedical disciplines at the NIH Clinical Center

  5. Top 5 things you need to know Your medical benefits

    E-Print Network [OSTI]

    Polz, Martin

    maternity and inpatient mental health/substance abuse care). Combined rates (Student Medical Plan + Student:HollyHinman photo:HollyHinman #12;The MIT Extended Student Insurance Plan covers basic care provided on campus at MIT Medical. It's included with tuition and you get: · Primary care · Many specialty services · Urgent

  6. Top 5 things you need to know Your medical benefits

    E-Print Network [OSTI]

    Polz, Martin

    stays (including childbirth and inpatient mental health/substance abuse care). Rates are listed below:KatiaShtyrkovaphoto:WeiGuo photo:NamirJawdat #12;The MIT Student Medical Plan provides coverage for basic care provided on campus at MIT Medical. It's included with tuition and you get: · Primary care · Care from most specialists

  7. UCSD Medical Center Ergonomic Funding Assistance Form Purpose: The UCSD Medical Center Workers' Compensation Unit (WCU) currently has funds

    E-Print Network [OSTI]

    Gleeson, Joseph G.

    UCSD Medical Center Ergonomic Funding Assistance Form Purpose: The UCSD Medical Center Workers' Compensation Unit (WCU) currently has funds available to assist departments implement ergonomic recommendations identified during an ergonomic assessment. This program will match up to 50% of the cost of identified

  8. EA-1929: NorthStar Medical Technologies LLC, Commercial Domestic Production of the Medical Isotope Molybdenum-99

    Broader source: Energy.gov [DOE]

    This EA evaluates the potential environmental impacts of a proposal to use federal funds to support and accelerate Northstar Medical Radioisotopes' project to develop domestic, commercial production capability for the medical isotope Molybdenum-99 without the use of highly enriched uranium.

  9. Rotatable superconducting cyclotron adapted for medical use

    DOE Patents [OSTI]

    Blosser, Henry G. (East Lansing, MI); Johnson, David A. (Williamston, MI); Riedel, Jack (East Lansing, MI); Burleigh, Richard J. (Berkeley, CA)

    1985-01-01T23:59:59.000Z

    A superconducting cyclotron (10) rotatable on a support structure (11) in an arc of about 180.degree. around a pivot axis (A--A) and particularly adapted for medical use is described. The rotatable support structure (13, 15) is balanced by being counterweighted (14) so as to allow rotation of the cyclotron and a beam (12), such as a subparticle (neutron) or atomic particle beam, from the cyclotron in the arc around a patient. Flexible hose (25) is moveably attached to the support structure for providing a liquified gas which is supercooled to near 0.degree. K. to an inlet means (122) to a chamber (105) around superconducting coils (101, 102). The liquid (34) level in the cyclotron is maintained approximately half full so that rotation of the support structure and cyclotron through the 180.degree. can be accomplished without spilling the liquid from the cyclotron. With the coils vertically oriented, each turn of the winding is approximately half immersed in liquid (34) and half exposed to cold gas and adequate cooling to maintain superconducting temperatures in the section of coil above the liquid level is provided by the combination of cold gas/vapor and by the conductive flow of heat along each turn of the winding from the half above the liquid to the half below.

  10. Global Security, Medical Isotopes, and Nuclear Science

    SciTech Connect (OSTI)

    Ahle, L E

    2007-09-17T23:59:59.000Z

    Over the past century basic nuclear science research has led to the use of radioactive isotopes into a wide variety of applications that touch our lives everyday. Some are obvious, such as isotopes for medical diagnostics and treatment. Others are less so, such as National/Global security issues. And some we take for granted, like the small amount of 241Am that is in every smoke detector. At the beginning of this century, we are in a position where the prevalence and importance of some applications of nuclear science are pushing the basic nuclear science community for improved models and nuclear data. Yet, at the same time, the push by the basic nuclear science community to study nuclei that are farther and farther away from stability also offer new opportunities for many applications. This talk will look at several global security applications of nuclear science, summarizing current R&D and need for improved nuclear data It will also look at how applications of nuclear science, such as to medicine, will benefit from the push for more and more powerful radioactive ion beam facilities.

  11. Process-based Derivation of Requirements for Medical Heather M. Conboy

    E-Print Network [OSTI]

    Avrunin, George S.

    , consider the combination of an infusion pump and a medical process for an in-patient surgery where the infusion pump is used in that medical process to ad- minister intravenous fluids and medic

  12. Energy management techniques for ultra-small bio-medical implants

    E-Print Network [OSTI]

    Sanchez, William R

    2012-01-01T23:59:59.000Z

    Trends in the medical industry have created a growing demand for implantable medical devices. In particular, the need to provide medical professionals a means to continuously monitor bio-markers over long time scales with ...

  13. Medical Nuclear Supply Chain Design: A Tractable Network Model and Computational

    E-Print Network [OSTI]

    Nagurney, Anna

    Medical Nuclear Supply Chain Design: A Tractable Network Model and Computational Approach Anna Medical Nuclear Supply Chain Design #12;Outline Background and Motivation Supply Chain Challenges The Medical Nuclear Supply Chain Network Design Model The Computational Approach Summary and Suggestions

  14. Diversity in U.S. Medical Schools: Revitalizing Efforts to Increase Diversity in a Changing Context, 1960s-2000s

    E-Print Network [OSTI]

    Lee, Philip R.; Franks, Patricia E.

    2010-01-01T23:59:59.000Z

    2008. New Medical Schools Advance Through Accreditationthrough 2000, 12 and medical and public health advances havetechnology advances have also moved medical schools toward a

  15. French Army Medical Services in the mid-nineteenth century: a medical history of the French Crimean expedition

    E-Print Network [OSTI]

    Harbison, Burton Earl

    1987-01-01T23:59:59.000Z

    to the reign of Louis XIV. During the 1850s the French Military Health Service was still regarded as among the most efficient in Europe. The Crimean War of 1854-1856 brought military success to French Armies, but it also brought a medical catastrophe...'s military predominance, its military medical establishment enjoyed the same prestige that was bestowed on the other arms. First-rate armies rarely have shoddy medical support, and French armies from the time of Louis XIY until the Second Empire were...

  16. adverse self-medication behaviors: Topics by E-print Network

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    sexual behavior Medication Interactions 63 Self medication with antibiotics in Yogyakarta City Indonesia. Open Access Theses and Dissertations Summary: ??In Indonesia, legislation...

  17. E-Print Network 3.0 - alternative medical therapies Sample Search...

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    for: alternative medical therapies Page: << < 1 2 3 4 5 > >> 1 Louisiana State University Health Care Services Division Medical Center of Louisiana at New Orleans Summary: are...

  18. E-Print Network 3.0 - asahikawa medical college Sample Search...

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    UWM, Marquette, Children's Hospital of Wisconsin, Froedtert... delivery, health care reform and improving the life of populations. The Medical ... Source: Medical College...

  19. Chief, Medical Service VA Palo Alto Health Care System

    E-Print Network [OSTI]

    Quake, Stephen R.

    Community Based Outpatient Clinics (CBOC). VAPAHCS has 833 operating beds, which include 100 acute care beds, and students are trained each year. As the Chief, Medical Service, the incumbent will maintain a joint

  20. active implantable medical: Topics by E-print Network

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    patients who want to enter a prenatal fitness program and for ongoing medical surveillance of exercising pregnant patients. Instructions for use of the 4-page PARmed-X for...

  1. Computer-aided decision making for Medical Device Reporting

    E-Print Network [OSTI]

    Chen, Jih-Horn

    1987-01-01T23:59:59.000Z

    , and answer the questions'- "What to do, How, and When?" MDRSOFT, a computer-aided decision making aid for medical de ricr reporting, attempts to capture dynamic problem- solving knowledge through modeling man processed decision making in the domain...

  2. Modeling medical devices for plug-and-play interoperability

    E-Print Network [OSTI]

    Hofmann, Robert Matthew

    2007-01-01T23:59:59.000Z

    One of the challenges faced by clinical engineers is to support the connectivity and interoperability of medical-electrical point-of-care devices. A system that could enable plug-and-play connectivity and interoperability ...

  3. Automatic Indexing of Handwritten Medical Forms for Search Engines

    E-Print Network [OSTI]

    Boyer, Edmond

    and later searched. Both practical and theoretical numbers are reported. This research builds the notion with the Western Regional Emergency Medical Services (WREMS) division of the New York State (NYS) Department

  4. african medical journals: Topics by E-print Network

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    21 22 23 24 25 Next Page Last Page Topic Index 1 The Medical Journal CiteSeer Summary: Cough is a common and distressing symptom that results in significant health care costs from...

  5. Nuclear and Radiological Engineering and Medical Physics Programs

    E-Print Network [OSTI]

    Weber, Rodney

    Nuclear and Radiological Engineering and Medical Physics Programs The George W. Woodruff School #12 Year Enrollment - Fall Semester Undergraduate Graduate #12; Nuclear Power Industry Radiological Engineering Industry Graduate School DOE National Labs Nuclear Navy #12; 104 Operating Nuclear Power plants

  6. Medical Device Integration Copyright 2010 The University of Vermont

    E-Print Network [OSTI]

    Hayden, Nancy J.

    Case Study Medical Device Integration Copyright© 2010 The University of Vermont Physiologic Monitor232 Portable Device Patient Patient Patient Clinician Clinician ICU Biomedical EHR Device Integration. Challenge: Determine the feasibility of biomedical device integration to the electronic health record

  7. Factors influencing the time for FDA review of medical devices

    E-Print Network [OSTI]

    Singh, Inder Raj, S.M. Massachusetts Institute of Technology

    2007-01-01T23:59:59.000Z

    Companies must receive marketing authorization by the Food and Drug Administration (FDA) before they can begin commercial distribution of a new type of medical device in the United States. The premarket approval application ...

  8. Mergers and acquisitions in the medical device industry

    E-Print Network [OSTI]

    Ohashi, Kevin Lee

    2007-01-01T23:59:59.000Z

    Mergers and acquisitions in the Medical Device Industry are the primary mode of exit for early stage companies. The focus of this thesis is to examine factors which influence the value of these M&A transactions from the ...

  9. Environmental security planning : an application to the Longwood Medical Area

    E-Print Network [OSTI]

    Garmaise, Miriam Gail

    1982-01-01T23:59:59.000Z

    The thesis is a study of the security problems due to street crime in the Longwood Medical Area of Boston. The first part of the thesis defines the theories and practices of environmental security .planning, the urban ...

  10. Autonomic Neuroscience Institute, Royal Free and University College Medical

    E-Print Network [OSTI]

    Burnstock, Geoffrey

    ; Florence, Italy; 2 Department of Medicine, Division of Rheumatology, Medical Col- lege of Ohio, Toledo, USA27. © Copyright CLINICAL AND EXPERIMENTAL RHEUMATOLOGY 2004. Keywords: Microvascular endothelial control (13). Our aim was to study SP mRNA expression in human

  11. aerospace medical panel: Topics by E-print Network

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Summary: Rprint & Copyright @ by Aerospace Medical Association, Alexandria, V A w. P. ROACH, M.S., Ph.D., M, B.S., and CRAIG M. BRAMLETTE, A.S. ROACH WP, ROGERS ME, ROCKWELL BA,...

  12. Virtual Mentor American Medical Association Journal of Ethics

    E-Print Network [OSTI]

    Fujimura, Joan

    Virtual Mentor American Medical Association Journal of Ethics August 2012, Volume 14, Number 8: 657, such as a particular genetic variant that might be related www.virtualmentor.org Virtual Mentor, August 2012--Vol 14

  13. Cadaver Dissection and the Ritual Transformation of Medical Students

    E-Print Network [OSTI]

    Laudermilk, Ryan

    2011-12-31T23:59:59.000Z

    Human cadaver dissection is a common component of Western medical education. While most students react emotionally to the presence of such a deeply-held symbol of death, the expression of emotion is often seen as unprofessional, ...

  14. MIT Medical Department Pediatrics History Form Dear Parent

    E-Print Network [OSTI]

    Polz, Martin

    PAST MEDICAL HISTORY: 1. Has the child had: a. Blood: anemia (iron deficiency, Sickle Cell, Thalessemia: Cell/Other: Contact Information for Parent 2 Name: Email: Home Address: Home Phone: Work Phone: Cell

  15. Computer-aided decision making for Medical Device Reporting 

    E-Print Network [OSTI]

    Chen, Jih-Horn

    1987-01-01T23:59:59.000Z

    , and answer the questions'- "What to do, How, and When?" MDRSOFT, a computer-aided decision making aid for medical de ricr reporting, attempts to capture dynamic problem- solving knowledge through modeling man processed decision making in the domain...

  16. Healthcare Energy: State University of New York Upstate Medical...

    Broader source: Energy.gov (indexed) [DOE]

    at the East Wing, a hospital building addition at the State University of New York Upstate Medical University. In the figure above, click on items in the legend to focus...

  17. A system theoretic approach to design safety into medical device

    E-Print Network [OSTI]

    Song, Qingyang S.M. Massachusetts Institute of Technology

    2012-01-01T23:59:59.000Z

    The goal of this thesis is to investigate and demonstrate the application of a systems approach to medical device safety in China. Professor Leveson has developed an accident modeling framework called STAMP (Systems Theoretic ...

  18. Access to Medical and Exposure Records 1.0 Reference

    E-Print Network [OSTI]

    de Lijser, Peter

    : A. Any hazardous waste regulated by the Solid Waste Disposal Act, amended by the Resource for medical/exposure records access is to improve the detection, treatment and prevention of occupational

  19. Characteristics of disruptive innovation within the medical device industry

    E-Print Network [OSTI]

    Berlin, David B. (David Benjamin)

    2011-01-01T23:59:59.000Z

    Innovation within the medical device industry had led to tremendous advances in the provision of care for patients worldwide. Continued progress in the treatment of disease will require effective processes for managing and ...

  20. Green manufacturing in the medical device industry : a case study

    E-Print Network [OSTI]

    Gautreau, Leigh (Leigh Ann)

    2009-01-01T23:59:59.000Z

    Introduction: Med Dev (name changed to protect confidentiality), is a medical device start-up using tissue engineering and drug delivery techniques to help combat the negative effects associated with secondary injury. Med ...

  1. ORISE: REAC/TS Medical Management of Radiation Incidents

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Medical Management of Radiation Incidents As part of its primary mission for the U.S. Department of Energy (DOE), the Radiation Emergency Assistance CenterTraining Site (REACTS)...

  2. Bodies of information : reinventing bodies and practice in medical education

    E-Print Network [OSTI]

    Prentice, Rachel

    2004-01-01T23:59:59.000Z

    This dissertation recounts the development of graphic models of human bodies and virtual reality simulators for teaching anatomy and surgery to medical students, residents, and physicians. It considers how researchers from ...

  3. Oxygen generator for medical applications (USIC)

    SciTech Connect (OSTI)

    Staiger, C. L.

    2012-03-01T23:59:59.000Z

    The overall Project objective is to develop a portable, non-cryogenic oxygen generator capable of supplying medical grade oxygen at sufficient flow rates to allow the field application of the Topical Hyperbaric Oxygen Therapy (THOT{reg_sign}) developed by Numotech, Inc. This project was sponsored by the U.S. Department of Energy Global Initiatives for Proliferation Prevention (GIPP) and is managed by collaboration between Sandia National Laboratories (SNL), Numotech, Inc, and LLC SPE 'Spektr-Conversion.' The project had two phases, with the objective of Phase I being to develop, build and test a laboratory prototype of the membrane-pressure swing adsorber (PSA) system producing at 15 L/min of oxygen with a minimum of 98% oxygen purity. Phase II objectives were to further refine and identify the pre-requisites needed for a commercial product and to determine the feasibility of producing 15 L/min of oxygen with a minimum oxygen purity of 99%. In Phase I, Spektr built up the necessary infrastructure to perform experimental work and proceeded to build and demonstrate a membrane-PSA laboratory prototype capable of producing 98% purity oxygen at a flow rate of 5 L/min. Spektr offered a plausible path to scale up the process for 15 L/min. Based on the success and experimental results obtained in Phase I, Spektr performed work in three areas for Phase II: construction of a 15 L/min PSA; investigation of compressor requirements for the front end of the membrane/PSA system; and performing modeling and simulation of assess the feasibility of producing oxygen with a purity greater than 99%. Spektr successfully completed all of the tasks under Phase II. A prototype 15 L/min PSA was constructed and operated. Spektr determined that no 'off the shelf' air compressors met all of the specifications required for the membrane-PSA, so a custom compressor will likely need to be built. Modeling and simulation concluded that production of oxygen with purities greater than 99% was possible using a Membrane-PSA system.

  4. Impact of the Massachusetts Pharmaceutical and Medical Device Manufacturer Code of Conduct on medical device physician-industry collaboration

    E-Print Network [OSTI]

    Wolf, Daniel W. (Daniel William)

    2010-01-01T23:59:59.000Z

    The Massachusetts Pharmaceutical and Medical Device Manufacturer Code of Conduct (PCOC) or 105 CMR 970.000 was enacted by the Massachusetts state legislature and adopted by the Department of Public Health (DPH) in July ...

  5. Scenarios and the design process in medical application R. Rasoulifar*, G. Thomann, F. Villeneuve

    E-Print Network [OSTI]

    Paris-Sud XI, Université de

    discipline performing in the process of developing medical advances. On the engineering design side, manyScenarios and the design process in medical application R. Rasoulifar*, G. Thomann, F. Villeneuve G of medical application. Keywords: Scenario-Based Design (SBD), Medical Application, User integration 1

  6. Secure emergency medical architecture on the cloud using wireless sensor networks for emergency

    E-Print Network [OSTI]

    Paris-Sud XI, Université de

    the greatest success in medical appli- cations. Recent advances in medical sensors, wireless tech- nologiesSecure emergency medical architecture on the cloud using wireless sensor networks for emergency in the cyphertext itself. This makes ABE good solution to provide a fine-grained access control for medical

  7. Motion Planning Under Uncertainty for Image-Guided Medical Needle Steering

    E-Print Network [OSTI]

    Branicky, Michael S.

    Process, image-guided medical procedure 1 Introduction Advances in medical imaging modalities such as MRIMotion Planning Under Uncertainty for Image-Guided Medical Needle Steering Ron Alterovitz it to steerable needles, a new class of flexible bevel- tip medical needles that physicians can steer through soft

  8. Medical Nuclear Supply Chain Design: A Tractable Network Model and Computational

    E-Print Network [OSTI]

    Nagurney, Anna

    Medical Nuclear Supply Chain Design: A Tractable Network Model and Computational Approach Anna Chain Challenges The Medical Nuclear Supply Chain Network Design Model The Computational Approach Medical Nuclear Supply Chain Design #12;This presentation is based on the paper, "Medical Nuclear Supply

  9. Medical and biohazardous waste generator`s guide: Revision 1

    SciTech Connect (OSTI)

    Not Available

    1994-09-01T23:59:59.000Z

    This Guide describes the procedures required to comply with all federal and state laws and regulations and Lawrence Berkeley Laboratory (LBL) policy applicable to medical and biohazardous waste. The members of the LBL Biological Safety Subcommittee participated in writing these policies and procedures. The procedures and policies in this Guide apply to LBL personnel who work with infectious agents or potentially infectious agents, publicly perceived infectious items or materials (e.g., medical gloves, culture dishes), and sharps (e.g., needles, syringes, razor blades). If medical or biohazardous waste is contaminated or mixed with a hazardous chemical or material, with a radioactive material, or with both, the waste will be handled in accordance with the applicable federal and State of California laws and regulations for hazardous, radioactive, or mixed waste.

  10. A proposed standard on medical isotope production in fission reactors

    SciTech Connect (OSTI)

    Schenter, R. E. [Smart Bullets Inc., 2521 SW Luradel Street, Portland, OR 97219 (United States); Brown, G. J. [Ozarks Medical Center, Cancer Treatment Center, Shaw Medical Building, 1111 Kentucky Avenue, West Plains, MO 65775 (United States); Holden, C. S. [Thorenco LLC, 369 Pine Street, San Francisco, CA 94104 (United States)

    2006-07-01T23:59:59.000Z

    Authors Robert E. Sehenter, Garry Brown and Charles S. Holden argue that a Standard for 'Medical Isotope Production' is needed. Medical isotopes are becoming major components of application for the diagnosis and treatment of all the major diseases including all forms of cancer, heart disease, arthritis, Alzheimer's, among others. Current nuclear data to perform calculations is incomplete, dated or imprecise or otherwise flawed for many isotopes that could have significant applications in medicine. Improved data files will assist computational analyses to design means and methods for improved isotope production techniques in the fission reactor systems. Initial focus of the Standard is expected to be on neutron cross section and branching data for both fast and thermal reactor systems. Evaluated and reviewed tables giving thermal capture cross sections and resonance integrals for the major target and product medical isotopes would be the expected 'first start' for the 'Standard Working Group'. (authors)

  11. Nanoscience and Nanotechnology: From Energy Applications to Advanced Medical Therapies

    ScienceCinema (OSTI)

    Tijana Rajh

    2010-01-08T23:59:59.000Z

    Dr. Rajh will present a general talk on nanotechnology ? an overview of why nanotechnology is important and how it is useful in various fields. The specific focus will be on Solar energy conversion, environmental applications and advanced medical therapies. She has broad expertise in synthesis and characterization of nanomaterials that are used in nanotechnology including novel hybrid systems connecting semiconductors to biological molecules like DNA and antibodies. This technology could lead to new gene therapy procedures, cancer treatments and other medical applications. She will also discuss technologies made possible by organizing small semiconductor particles called quantum dots, materials that exhibit a rich variety of phenomena that are size and shape dependent. Development of these new materials that harnesses the unique properties of materials at the 1-100 nanometer scale resulted in the new field of nanotechnology that currently affects many applications in technological and medical fields.

  12. Portable, space-saving medical patient support system

    DOE Patents [OSTI]

    Bzorgi; Fariborz (Knoxville, TN)

    2011-02-01T23:59:59.000Z

    A support platform having a stowed configuration and a deployed configuration on a floor. The support platform is related to stretcher devices that are used for transporting, confining, or conducting medical procedures on medical patients in medical emergencies. The support platform typically includes a work surface that has a geometric extent. A base that typically includes a plurality of frame members is provided, and the frame members are disposed across the geometric extent of, and proximal to, the work surface in the stowed configuration. The frame members are typically disposed on the floor in the deployed configuration. There is a foldable bracing system engaged with the work surface and engaged with the base. At least a portion of the foldable bracing system is disposed substantially inside at least a portion of the plurality of frame members in the stowed configuration. Further, the foldable bracing system is configured for translocation of the work surface distal from the base in the deployed configuration.

  13. Designing for Energy Conservation - The Cypress Fairbanks Medical Center Hospital

    E-Print Network [OSTI]

    Wiernik, L. B.; Ranzau, P. A.

    1984-01-01T23:59:59.000Z

    ,000 'quare foot is heat gain. The longest dbeneions of the Cypress cmprised Of three 40-bed medical'sur&ical In-patient Medical Center are oriented northwest and southeast. care nureing floors, and the first floor which houses All of the external windows... are 1/4" solar bronze administrative, business, dienostic, treatment and and internally ehded by 3" wide vertical blinds. ancillary services. The hospital is adjoined by a First floor windows are ehaded by a -$-foot overhang. 40,000 square foot med...

  14. Global health education in U.S. Medical schools

    E-Print Network [OSTI]

    Khan, Omar A; Guerrant, Richard; Sanders, James; Carpenter, Charles; Spottswood, Margaret; Jones, David S; O’Callahan, Cliff; Brewer, Timothy F; Markuns, Jeffrey F; Gillam, Stephen; O’Neill, Joseph; Nathanson, Neal; Wright, Stephen

    2013-01-18T23:59:59.000Z

    35 (30%) did not; data were not obtained from 2 schools “See Figure 1”.Figure 1 Global health student interest group presence in medical scB. Review of existing recommendations for GH curricula [see Table 1] We searched for both ‘international health... in such offerings in US and Canadian medical schools [27]. As the field of GH in medicine matures, there may initially need to be a balance between prescriptiveness and libertarianism. There is general agreement on the concepts of GH com- petencies, sharing...

  15. Fissile Material Disposition Program: Deep Borehole Disposal Facility PEIS data input report for direct disposal. Direct disposal of plutonium metal/plutonium dioxide in compound metal canisters. Version 3.0

    SciTech Connect (OSTI)

    Wijesinghe, A.M.; Shaffer, R.J.

    1996-01-15T23:59:59.000Z

    The US Department of Energy (DOE) is examining options for disposing of excess weapons-usable nuclear materials [principally plutonium (Pu) and highly enriched uranium (HEU)] in a form or condition that is substantially and inherently more difficult to recover and reuse in weapons production. This report is the data input report for the Programmatic Environmental Impact Statement (PEIS). The PEIS examines the environmental, safety, and health impacts of implementing each disposition alternative on land use, facility operations, and site infrastructure; air quality and noise; water, geology, and soils; biotic, cultural, and paleontological resources; socioeconomics; human health; normal operations and facility accidents; waste management; and transportation. This data report is prepared to assist in estimating the environmental effects associated with the construction and operation of a Deep Borehole Disposal Facility, an alternative currently included in the PEIS. The facility projects under consideration are, not site specific. This report therefore concentrates on environmental, safety, and health impacts at a generic site appropriate for siting a Deep Borehole Disposal Facility.

  16. DEPARTMENTS OF CLINICAL SCIENCES AND MEDICAL EDUCATION College of Medicine

    E-Print Network [OSTI]

    Foroosh, Hassan

    APPENDIX C DEPARTMENTS OF CLINICAL SCIENCES AND MEDICAL EDUCATION College of Medicine University with a focus on progress toward your promotion. It also allows you to list the progress you made during to those goals, and end of the year progress report that includes a summary table. All faculty

  17. APPENDIX D PART 2 DEPARTMENTS OF CLINICAL SCIENCES AND MEDICAL

    E-Print Network [OSTI]

    Foroosh, Hassan

    APPENDIX D ­ PART 2 DEPARTMENTS OF CLINICAL SCIENCES AND MEDICAL EDUCATION College of Medicine:_______________________________ PROGRESS REPORT for Calendar Year _______ Refer to the Final assignment for the past year to review your your progress towards these goals. Activity and percentage Progress and achievements 1. Instructional

  18. Near-infrared spectroscopic tissue imaging for medical applications

    DOE Patents [OSTI]

    Demos; Stavros (Livermore, CA), Staggs; Michael C. (Tracy, CA)

    2006-03-21T23:59:59.000Z

    Near infrared imaging using elastic light scattering and tissue autofluorescence are explored for medical applications. The approach involves imaging using cross-polarized elastic light scattering and tissue autofluorescence in the Near Infra-Red (NIR) coupled with image processing and inter-image operations to differentiate human tissue components.

  19. Near-infrared spectroscopic tissue imaging for medical applications

    DOE Patents [OSTI]

    Demos, Stavros (Livermore, CA); Staggs, Michael C. (Tracy, CA)

    2006-12-12T23:59:59.000Z

    Near infrared imaging using elastic light scattering and tissue autofluorescence are explored for medical applications. The approach involves imaging using cross-polarized elastic light scattering and tissue autofluorescence in the Near Infra-Red (NIR) coupled with image processing and inter-image operations to differentiate human tissue components.

  20. Assessment of Research University Medical Centre Utrecht (UMC Utrecht)

    E-Print Network [OSTI]

    Utrecht, Universiteit

    Afzender Assessment of Research Quality University Medical Centre Utrecht (UMC Utrecht) 2001 - 2006) the absence of a national comparison. In this new procedure, The Board of Utrecht University has appointed of the research at the UMC Utrecht (see Appendix 1). The Board of Utrecht University determined in more detail

  1. A Network-based System Architecture for Remote Medical Applications

    E-Print Network [OSTI]

    Jantsch, Axel

    mobile technology [1] [2] [10]. 3G communication network provides a broadband, packet-based transmissionA Network-based System Architecture for Remote Medical Applications Huimin She1, 2 1 Dept-21-5135-5286 zhoud@fudan.edu.cn ABSTRACT Nowadays, the evolution of wireless communication and network technologies

  2. Information as published on the Norris Medical Library web page

    E-Print Network [OSTI]

    Zhang, Li I.

    Information as published on the Norris Medical Library web page http://www.usc.edu/hsc/nml/lib-services/cos.html COMMUNITY OF SCIENCE @ USC USC's membership in Community of Science (COS) provides you with access to web - Search the most comprehensive source of funding information available on the web, with up-to-date records

  3. University of California, Davis, Health System Office of Medical Education

    E-Print Network [OSTI]

    Leistikow, Bruce N.

    University of California, Davis, Health System Office of Medical Education Exhibitor Confirmation' tabletop or equivalent floor space. o Vendors provide their own electrical cords or pay for equipment provided by conference site AV services. o Decorating, security guard, internet and electricity

  4. Complex Medical Processes as Context for Embedded Systems

    E-Print Network [OSTI]

    Massachusetts at Amherst, University of

    of the process into account. Consider, for example, the new generation of "smart" infusion pumps for intravenous administration of medications and fluids. Infusion pumps were in- troduced over 30 years ago as limited rate per hour to many liters per hour, and may have several channels infusing Department of Computer

  5. "Developing `smart' algorithms for medical and wireless technologies to

    E-Print Network [OSTI]

    Acton, Scott

    , including medical devices for the treatment of diabetes, resource management in wireless systems, and network traffic engineering. In conjunction with the UVa Center for Diabetes Technology, our group has contributed to the development of algorithms for closed-loop and advisory mode control of type 1 diabetes, i

  6. Non-Confidential Disclosure Harvard Medical School Affiliate

    E-Print Network [OSTI]

    Zhang, Yi

    Non-Confidential Disclosure Harvard Medical School Affiliate Office of Technology Development 3 are underway to determine if administration of a blocking antibody or a soluble ligand-Ig chimera can prevent: Exclusive worldwide license Contact: Ryan Dietz Director, Office of Technology Development 617

  7. Improved Classification of Medical Data Using Abductive Network Committees

    E-Print Network [OSTI]

    Abdel-Aal, Radwan E.

    Improved Classification of Medical Data Using Abductive Network Committees Trained on Different 3 860 4281 #12;Summary This paper demonstrates the use of abductive network classifier committees the features and forming subsets of uniform predictive quality for training individual members. The abductive

  8. BETAVOLTAIC BATTERIES Long-Life Power for Defense & Medical Markets

    E-Print Network [OSTI]

    BETAVOLTAIC BATTERIES Long-Life Power for Defense & Medical Markets NREL Industry Growth Forum Jonathan W. Greene, CEO November 2, 2009 #12;·! Patented Betavoltaics ­ tiny, long life batteries targeting electronic and isotope powered batteries MS - 14 yrs management and engineering ·!Expert in patent

  9. Syllabus-PHY315-1 Biological and Medical Physics

    E-Print Network [OSTI]

    Movileanu, Liviu

    Syllabus-PHY315-1 Syllabus Biological and Medical Physics PHY 315 - Spring 2014 Professor Dr. Liviu in this syllabus. Administrative Assistance Mrs. Patricia Whitmore; Office: Room111, Physics Bldg.; Phone: 443;Syllabus-PHY315-2 Contents of the class: Why biology by the numbers? Design schemes for cells

  10. Medical waste management in Ibadan, Nigeria: Obstacles and prospects

    SciTech Connect (OSTI)

    Coker, Akinwale [Department of Civil Engineering, Faculty of Technology, University of Ibadan, Ibadan (Nigeria); School of Engineering and the Built Environment, University of Wolverhampton, Wolverhampton WV1 1SB (United Kingdom)], E-mail: cokerwale@yahoo.com; Sangodoyin, Abimbola [Department of Agricultural and Environmental Engineering, Faculty of Technology, University of Ibadan, Ibadan (Nigeria); Sridhar, Mynepalli [Division of Environmental Health, Faculty of Public Health, College of Medicine, University of Ibadan, Ibadan (Nigeria); Booth, Colin; Olomolaiye, Paul; Hammond, Felix [School of Engineering and the Built Environment, University of Wolverhampton, Wolverhampton WV1 1SB (United Kingdom)

    2009-02-15T23:59:59.000Z

    Quantification and characterization of medical waste generated in healthcare facilities (HCFs) in a developing African nation has been conducted to provide insights into existing waste collection and disposal approaches, so as to provide sustainable avenues for institutional policy improvement. The study, in Ibadan city, Nigeria, entailed a representative classification of nearly 400 healthcare facilities, from 11 local government areas (LGA) of Ibadan, into tertiary, secondary, primary, and diagnostic HCFs, of which, 52 HCFs were strategically selected. Primary data sources included field measurements, waste sampling and analysis and a questionnaire, while secondary information sources included public and private records from hospitals and government ministries. Results indicate secondary HCFs generate the greatest amounts of medical waste (mean of 10,238 kg/day per facility) followed by tertiary, primary and diagnostic HCFs, respectively. Characterised waste revealed that only {approx}3% was deemed infectious and highlights opportunities for composting, reuse and recycling. Furthermore, the management practices in most facilities expose patients, staff, waste handlers and the populace to unnecessary health risks. This study proffers recommendations to include (i) a need for sustained cooperation among all key actors (government, hospitals and waste managers) in implementing a safe and reliable medical waste management strategy, not only in legislation and policy formation but also particularly in its monitoring and enforcement and (ii) an obligation for each HCF to ensure a safe and hygienic system of medical waste handling, segregation, collection, storage, transportation, treatment and disposal, with minimal risk to handlers, public health and the environment.

  11. Comparison of Distance Metrics for Hierarchical Data in Medical Databases

    E-Print Network [OSTI]

    Aickelin, Uwe

    sufficiently well in clustering the patient population using k-means clustering algorithm. I. INTRODUCTIONComparison of Distance Metrics for Hierarchical Data in Medical Databases Diman Hassan, Uwe of these metrics have been compared to other measures to find their efficiency. In [5], a comparison has been made

  12. SchoolofMedicalSciences BSc (Hons) Molecular Biology

    E-Print Network [OSTI]

    Levi, Ran

    Catalogue of Courses or SMS World Wide Web Pages for names). The Head of School of Medical Sciences as to the development of improved crops. Graduates in molecular biology have a wide range of career options, including, and in the transferable skills associated with mastering statistics, graphics and word processing software packages

  13. Rationale and Architecture Principles for Medical Application Platforms John Hatcliff

    E-Print Network [OSTI]

    Huth, Michael

    , certification I. INTRODUCTION Historically, medical devices have been developed as stand-alone units. Though or not indicative of a patient's true health status. There are no engineering This work is supported in part, and the configuration of the devices in the system is known a priori. Due to the manner in which devices are constructed

  14. Patient Controlled Encryption: Ensuring Privacy of Electronic Medical Records

    E-Print Network [OSTI]

    Lauter, Kristin

    .S. President Barack Obama signed into law the American Recovery and Reinvestment Act of 2009, which containedPatient Controlled Encryption: Ensuring Privacy of Electronic Medical Records Josh Benaloh, Melissa,melissac,horvitz,klauter}@microsoft.com ABSTRACT We explore the challenge of preserving patients' privacy in electronic health record systems. We

  15. Graduate Medical Education Committee (GMEC) Policy on Accommodations for Disabilities

    E-Print Network [OSTI]

    Mohaghegh, Shahab

    safety must be assured as a top priority in these determinations. Residents must request accommodations the Department Chair and Designated Institutional Official that such a request has been made. The resident Institutional Requirements Approved by GMEC 1/12/07 II.D.4.n Office of Graduate Medical Education West Virginia

  16. Animations of Medical Training Scenarios in Immersive Virtual Environments

    E-Print Network [OSTI]

    Animations of Medical Training Scenarios in Immersive Virtual Environments Ivelina V. Alexandrova-line me- dia applications using Virtual Humans (VHs) 1 http://www.meti.com/ 3 http to express emotions, and syn- chronized body and facial animations, including human-like gaze behavior

  17. University of Michigan Medical School 2010 Residency Match Results

    E-Print Network [OSTI]

    Shyy, Wei

    University of Michigan Medical School 2010 Residency Match Results Name Institution Specialty Michael Ambrose U Michigan Hosps-Ann Arbor Pediatrics Kate Anderson Exempla St Joseph Hosp-CO Family Medicine Ketti Augusztiny U Michigan Hosps-Ann Arbor Family Med/Ypsilanti Kathryn Baker U Michigan Hosps

  18. CALIFORNIA STATE UNIVERSITY, FULLERTON MEDICAL CLEARANCE OF PERSONAL PHYSICIAN

    E-Print Network [OSTI]

    de Lijser, Peter

    CALIFORNIA STATE UNIVERSITY, FULLERTON Fit 4 Life MEDICAL CLEARANCE OF PERSONAL PHYSICIAN Name of Patient _______________________ Your patient is interested in participating in the Fit 4 Life class, one: - Chest Press and Leg Press Flexibility * Chair Sit and Reach yes ___ no ___ * Back Scratch yes

  19. benefit description Mit student/Affiliate Medical plan

    E-Print Network [OSTI]

    Polz, Martin

    that includes a variety of health care benefits. The MIT Student Health Plan is designed to fulfill the state is the Mit student Medical plan. It provides you with primary care, outpatient mental health care, and a wide hospitalization, inpatient mental health and substance abuse treatment, surgical procedures, and prescription

  20. Top 5 things you need to know Your medical benefits

    E-Print Network [OSTI]

    Polz, Martin

    procedures, and hospital stays (including childbirth and inpatient mental health/substance abuse care). Rates for basic care provided on campus at MIT Medical. · Primary care · Care from most specialists · Urgent Care-253-4371 or affplan@med.mit.edu. The MIT Affiliate Health Plan can cover health care for your family, too. · Your

  1. MEDICATION TREATMENT FOR ATTENTION DEFICIT DISORDERS UNLV STUDENT WELLNESS

    E-Print Network [OSTI]

    Hemmers, Oliver

    Jan 2010 MEDICATION TREATMENT FOR ATTENTION DEFICIT DISORDERS UNLV STUDENT WELLNESS SRWC (702) 895-3627 Due to the high potential for both abuse and possibly sudden unexpected death, UNLV Student Wellness for ADD/ADHD. You may contact the CAPS triage counselor or our care manager, Perris Kent, for an ADD

  2. Prediction-Based Compression Ratio Boundaries for Medical Images

    E-Print Network [OSTI]

    Qi, Xiaojun

    Prediction-Based Compression Ratio Boundaries for Medical Images Xiaojun Qi Computer Science present prediction-based image compression techniques take advantage of either intra- or inter function. The prediction-based compression technique has been applied on some magnetic resonance (MR) brain

  3. Segmentation for Medical Image Mining: A Technical Ashraf Elsayed1

    E-Print Network [OSTI]

    Atkinson, Katie

    Segmentation for Medical Image Mining: A Technical Report Ashraf Elsayed1 , Frans Coenen1 , Marta, such as relational databases, has been the focal point of much work in data mining. However, with advances, sound, etc). There is currently a very substantial collection of image data that can be mined

  4. Application of Data Mining Techniques for Medical Image Classification

    E-Print Network [OSTI]

    Zaiane, Osmar R.

    are necessary to assist the medical staff to achieve high efficiency and effectiveness. 1In the United States of cancer deaths in women today and it is the most common type of cancer in women. This paper presents some in cancer treatment and allows reaching a high survival rate. Mammography is considered the most reliable

  5. Reprint & Copyright by Aerospace Medical Association, Washington, DC

    E-Print Network [OSTI]

    Reprint & Copyright ©by Aerospace Medical Association, Washington, DC TECHNICAL NOTE Reflectance.EPICS Biomedical Engineering and Science Institute and Department of Electrical and Computer Engineering, Drexel and pulsatile and mean Doppler velocities were examined as predictors of impending peripheral light loss (PLL

  6. accident medical aspect: Topics by E-print Network

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    accident medical aspect First Page Previous Page 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 Next Page Last Page Topic Index 1 UNIVERSITY OF KENTUCKY REQUEST...

  7. Integrating Bioinformatics, Medical Sciences and Drug Discovery M. Madan Babu

    E-Print Network [OSTI]

    Babu, M. Madan

    .com Bioinformatics Bioinformatics, a term coined for the applications of computer science in biology is now emerging., Bioinformatics plays an important role for the integration of broad disciplines of Biology to understandIntegrating Bioinformatics, Medical Sciences and Drug Discovery M. Madan Babu Centre

  8. Ultra-low-power electronics for non-invasive medical monitoring

    E-Print Network [OSTI]

    Turicchia, Lorenzo

    New electronics for non-invasive medical monitoring promise low-cost, maintenance-free, and lightweight devices. These devices are critical in long-term medical measurements and in home-based tele-monitoring services, which ...

  9. Inductively Heated Shape Memory Polymer for the Magnetic Actuation of Medical Devices

    E-Print Network [OSTI]

    Buckley, Patrick R.

    2007-01-23T23:59:59.000Z

    Presently there is interest in making medical devices such as expandable stents and intravascular microactuators from shape memory polymer (SMP). One of the key challenges in realizing SMP medical devices is the implementation ...

  10. CollaboRhythm : new paradigms in doctor-patient interaction applied to HIV medication adherence

    E-Print Network [OSTI]

    Moore, John Oliver.

    2009-01-01T23:59:59.000Z

    Despite astounding advances in medical knowledge and treatment in recent decades, health outcomes are disappointing and costs continue to rise. The traditional paternalistic and episodic approach to medical care is not ...

  11. University of Rochester Medical Center Advancement Director for Advancement and Alumni Relations

    E-Print Network [OSTI]

    Portman, Douglas

    University of Rochester Medical Center Advancement Director for Advancement 58 Overview: Reporting to the Sr. Assistant Vice President for Medical Center Advancement for Academic Programs (SAVP), the Director of Advancement

  12. Domestic production of medical isotope Mo-99 moves a step closer

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Domestic production of medical isotope Mo-99 Domestic production of medical isotope Mo-99 moves a step closer Irradiated uranium fuel has been recycled and reused for molybdenum-99...

  13. Digitally-assisted, ultra-low power circuits and systems for medical applications

    E-Print Network [OSTI]

    Bohorquez, Jose L

    2010-01-01T23:59:59.000Z

    In recent years, trends in the medical industry have created a growing demand for a variety of implantable medical devices. At the same time, advances in integrated circuits techniques, particularly in CMOS, have opened ...

  14. From medical geography to germ theory in Colombia, 1860-1900 

    E-Print Network [OSTI]

    Garcia Lopez, Claudia Monica

    2009-01-01T23:59:59.000Z

    Before the consolidation of the germ theory of human diseases at the end of the nineteenth century, medical explanations about disease causation were dominated by the environmental notions of medical geography. This ...

  15. Medical images simulation, storage, and processing on the European DataGrid testbed

    E-Print Network [OSTI]

    Boyer, Edmond

    acquisition centers throughout the territory. Although national regulation con- cerning medical images are heterogeneous in Europe, the current trend is: (i) a free access of patients to their medical data, and (ii Energy Physics

  16. Creating, Curating, and Sharing Online Faculty Development Resources: The Medical Education in Cases Series Experience

    E-Print Network [OSTI]

    Chan, TM; Thoma, B; Lin, M

    2015-01-01T23:59:59.000Z

    MEdIC archive at the ALiEM Web site (www.aliem.com/medic/).time per page for the ALiEM Web site is 2 minutes:0 seconds.other contributions to these Web sites. Ethical approval:

  17. Validating the therapy prediction model through a breakdown analysis on ICU patient medical records

    E-Print Network [OSTI]

    You, Shu-Chyng

    2006-01-01T23:59:59.000Z

    With the rapid advancement of computational data analysis tools, medical informatics has emerged as a discipline that explores the use of medical information in clinical practice. It searches for ways to effectively integrate ...

  18. A systems theoretic application to design for the safety of medical diagnostic devices

    E-Print Network [OSTI]

    Balgos, Vincent H

    2012-01-01T23:59:59.000Z

    In today's environment, medical technology is rapidly advancing to deliver tremendous value to physicians, nurses, and medical staff in order to support them to ultimately serve a common goal: provide safe and effective ...

  19. Electromagnetic pulse (EMP), Part I: Effects on field medical equipment

    SciTech Connect (OSTI)

    Vandre, R.H.; Klebers, J.; Tesche, F.M.; Blanchard, J.P. (Walter Reed Army Medical Center, Washington, DC (United States))

    1993-04-01T23:59:59.000Z

    The electromagnetic pulse (EMP) from a high-altitude nuclear detonation has the potential to cover an area as large as the continental United States with damaging levels of EMP radiation. In this study, two of seven items of medical equipment were damaged by an EMP simulator. Computer circuit analysis of 17 different items showed that 11 of the 17 items would be damaged by current surges on the power cords, while two would be damaged by current surges on external leads. This research showed that a field commander can expect approximately 65% of his electronic medical equipment to be damaged by a single nuclear detonation as far as 2,200 km away.

  20. Medical catheters thermally manipulated by fiber optic bundles

    DOE Patents [OSTI]

    Chastagner, P.

    1992-10-06T23:59:59.000Z

    A maneuverable medical catheter comprising a flexible tube having a functional tip is described. The catheter is connected to a control source. The functional tip of the catheter carries a plurality of temperature activated elements arranged in parallel and disposed about the functional tip and held in spaced relation at each end. These elements expand when they are heated. A plurality of fiber optic bundles, each bundle having a proximal end attached to the control source and a distal end attached to one of the elements carry light into the elements where the light is absorbed as heat. By varying the optic fiber that is carrying the light and the intensity of the light, the bending of the elements can be controlled and thus the catheter steered. In an alternate embodiment, the catheter carries a medical instrument for gathering a sample of tissue. The instrument may also be deployed and operated by thermal expansion and contraction of its moving parts. 10 figs.

  1. E-Print Network 3.0 - alternative medical interventions Sample...

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Clinical Trial Design Developing Dynamic, Sequential Treatments that Optimize Mental Health Outcomes Summary: in the medical care process. Adaptive Interventions...

  2. Consumer Query Health Profile Saint Alphonsus Regional Medical Center

    E-Print Network [OSTI]

    Barrash, Warren

    Consumer Query Health Profile Saint Alphonsus Regional Medical Center Query resulted in 570 BSU Classified and Non-Classified employees that participated in the Fall 2004 Health Risk Appraisal. Non.2% 9.6% 7.7% 9.0% Heart Disease 2.3% 2.3% 2.6% 3.1% No Primary Care Physician 33.0% 31.8% 30.0% 24

  3. An Expectation States Approach to Examining Medical Team Information Exchange

    E-Print Network [OSTI]

    Manago, Bianca

    2013-07-30T23:59:59.000Z

    medical team research has reached a point where the linkages between information exchange, hierarchy, and team performance need to be clearly established. Several individual experiments demonstrate interesting findings, but the effects they display... 2010). Beyond that, teams are embedded in an ?encompassing organizational system, with boundaries and linkages to the broader system context and task environment? (Kozlowski and Ilgen 2006:79). That is, in the current research, teams are generally...

  4. Medical Imaging: Elec Eng -4BF3 Winter 2013

    E-Print Network [OSTI]

    Haykin, Simon

    @mcmaster.ca Campus Office: ETB-406 x23727 Hospital Office SJH-F126-4 x35218 Lab: Imaging Research Centre, St. Joseph Fridays 12:00noon - 2:30pm (ETB-406) Teaching Assistant (TA) Alireza Akbari akbaria@mcmaster.ca Office Hours Wed. 1:30pm - 2:20pm (ETB-303) From the Undergraduate Calendar Physical principles of medical

  5. Energy use baselining study for the National Naval Medical Center

    SciTech Connect (OSTI)

    Parker, G.B.; Halverson, M.A.

    1992-04-01T23:59:59.000Z

    This report provides an energy consumption profile for fourteen buildings at the National Naval Medical Center (NNMC) in Bethesda, Maryland. Recommendations are also made for viable energy efficiency projects funded with assistance from the servicing utility (Potomic Electric Power Company) in the form of rebates and incentives available in their Demand Side Management (DSM) program and through Shared Energy Savings (SES) projects. This report also provides estimates of costs and potential energy savings of the recommended projects.

  6. The Imaging and Medical Beam Line at the Australian Synchrotron

    SciTech Connect (OSTI)

    Hausermann, Daniel; Hall, Chris; Maksimenko, Anton; Campbell, Colin [Australian Synchrotron Company, 800 Blackburn Road, Clayton, Victoria 3168 (Australia)

    2010-07-23T23:59:59.000Z

    As a result of the enthusiastic support from the Australian biomedical, medical and clinical communities, the Australian Synchrotron is constructing a world-class facility for medical research, the 'Imaging and Medical Beamline'. The IMBL began phased commissioning in late 2008 and is scheduled to commence the first clinical research programs with patients in 2011. It will provide unrivalled x-ray facilities for imaging and radiotherapy for a wide range of research applications in diseases, treatments and understanding of physiological processes. The main clinical research drivers are currently high resolution and sensitivity cardiac and breast imaging, cell tracking applied to regenerative and stem cell medicine and cancer therapies. The beam line has a maximum source to sample distance of 136 m and will deliver a 60 cm by 4 cm x-ray beam1 - monochromatic and white - to a three storey satellite building fully equipped for pre-clinical and clinical research. Currently operating with a 1.4 Tesla multi-pole wiggler, it will upgrade to a 4.2 Tesla device which requires the ability to handle up to 21 kW of x-ray power at any point along the beam line. The applications envisaged for this facility include imaging thick objects encompassing materials, humans and animals. Imaging can be performed in the range 15-150 keV. Radiotherapy research typically requires energies between 30 and 120 keV, for both monochromatic and broad beam.

  7. Future Supply of Medical Radioisotopes for the UK Report 2014

    E-Print Network [OSTI]

    Neilly, Brian; Ballinger, Jim; Buscombe, John; Clarke, Rob; Ellis, Beverley; Flux, Glenn; Fraser, Louise; Hall, Adrian; Owen, Hywel; Paterson, Audrey; Perkins, Alan; Scarsbrook, Andrew

    2015-01-01T23:59:59.000Z

    The UK has no research nuclear reactors and relies on the importation of 99Mo and other medical radioisotopes (e.g. Iodine-131) from overseas (excluding PET radioisotopes). The UK is therefore vulnerable not only to global shortages, but to problems with shipping and importation of the products. In this context Professor Erika Denton UK national Clinical Director for Diagnostics requested that the British Nuclear Medicine Society lead a working group with stakeholders including representatives from the Science & Technology Facilities Council (STFC) to prepare a report. The group had a first meeting on 10 April 2013 followed by a working group meeting with presentations on 9th September 2013 where the scope of the work required to produce a report was agreed. The objectives of the report are: to describe the status of the use of medical radioisotopes in the UK; to anticipate the potential impact of shortages for the UK; to assess potential alternative avenues of medical radioisotope production for the UK m...

  8. TITLE: NON-RETALIATION Columbia University Medical Center will refrain from intimidating, threatening, coercing,

    E-Print Network [OSTI]

    Columbia University

    TITLE: NON-RETALIATION POLICY: Columbia University Medical Center will refrain from intimidating : Columbia University Medical Center is committed to protecting patient privacy as mandated by city, state-retaliation for exercising rights or reporting actual or suspected violations Columbia University Medical Center

  9. TITLE: MARKETING Columbia University Medical Center will not use or disclose a patient's Protected Health

    E-Print Network [OSTI]

    Columbia University

    TITLE: MARKETING POLICY: Columbia University Medical Center will not use or disclose a patient the procedures Columbia University Medical Center will follow in order to use a patient's PHI for marketing to patients: . describes a health-related product or service provided by Columbia University Medical Center

  10. Computational Models for Image Guided, Robot-Assisted and Simulated Medical Interventions

    E-Print Network [OSTI]

    Paris-Sud XI, Université de

    their potential use in a number of advanced medical applications including image guided, robot and force feedback. Such procedures require the use of advanced medical image analysis methods and have brought many advances in several medical fields includ- ing computer-aided diagnosis, therapy

  11. Search thousands of travel therapy destinations at: http://www.advanced-medical.net

    E-Print Network [OSTI]

    Weber, David J.

    Search thousands of travel therapy destinations at: http://www.advanced-medical.net Why do new grads travel with Advanced Medical? Mentorship: With accomplished mentors, new grad friendly facilities, and robust clinical support, trust Advanced Medical to take your professional growth seriously. Advanced

  12. An advanced computer system for medical research by WILLIAM J. SANDERS, G. BREITBARD,

    E-Print Network [OSTI]

    Wiederhold, Gio

    An advanced computer system for medical research by WILLIAM J. SANDERS, G. BREITBARD, D. CUMMINS, R. FLEXER, K. HOLTZ, J. MILLER and G. WIEDERHOLD ACME Project, Stanford Medical Center Stanford, California in 1959, with the purpose of more closely integrating medical research and educa- tion with the other

  13. Hand gestures for medical applica-tions provide an expressive, natural

    E-Print Network [OSTI]

    Wachs, Juan

    members to increasingly interact with medical equipment and computer systems. These advances haveHand gestures for medical applica- tions provide an expressive, natural and intuitive way reviews the highlights of a novel gesture-based system for medical image browsing in the OR called Gestix

  14. Graduate School of Advanced Science and Engineering Department of Life Science and Medical Research Instruction

    E-Print Network [OSTI]

    Kaji, Hajime

    Graduate School of Advanced Science and Engineering Department of Life Science and Medical Bioscience #12; Graduate School of Advanced Science and Engineering Department of Life Science and Medical; Graduate School of Advanced Science and Engineering Department of Life Science and Medical Bioscience

  15. Numerical Simulation for eHealth: Grid-enabled Medical Simulation Services Siegfried Benknera

    E-Print Network [OSTI]

    Middleton, Stuart E.

    advanced bio-medical simulation applications. Often, however, such applications have a very limited methodology advances. The European GEMSS Project [7] is concerned with the creation of medical Grid service1 Numerical Simulation for eHealth: Grid-enabled Medical Simulation Services Siegfried Benknera

  16. Efficient and Robust Non-Rigid Least-Squares Rectification of Medical Images

    E-Print Network [OSTI]

    Orchard, Jeffery J.

    imaging, robust statistics, least-squares. 1 Introduction Advances in medical imaging techniques haveEfficient and Robust Non-Rigid Least-Squares Rectification of Medical Images A. Wong Department of the major problems facing medical imaging is the presence of geometric distortions inherent in an imaging

  17. In Medical Science Monitor, 7(Suppl. 1):327-332, May 2001 Page 1 of 10

    E-Print Network [OSTI]

    Druzdzel, Marek J.

    in the field of computer-based medical systems. These advances have resulted in noticible improvementsIn Medical Science Monitor, 7(Suppl. 1):327-332, May 2001 Page 1 of 10 Wasyluk H.1 , Onisko A.2 , Druzdzel MJ.3 1 Medical Center of Postgraduate Education, Marymoncka 99, 01-813 Warszawa, Institute

  18. Medical Nuclear Supply Chain Design: A Tractable Network Model and Computational Approach

    E-Print Network [OSTI]

    Nagurney, Anna

    Medical Nuclear Supply Chain Design: A Tractable Network Model and Computational Approach Anna of medical nuclear supply chains. Our focus is on the molybdenum supply chain, which is the most commonly is of special relevance to healthcare given the medical nuclear product's widespread use as well as the aging

  19. THE UNIVERSITY OF TENNESSEE FLEXIBLE BENEFITS PLAN MEDICAL EXPENSE REIMBURSEMENT CLAIM FORM

    E-Print Network [OSTI]

    Davis, Lloyd M.

    addiction treatment Prescribed vitamins (requires written prescription from doctor) Eye examinations Special to obtaining medical treatment at a medical facility Braille books and magazines Medical out-of-pocket expenses surgery Orthodontic care Deductibles and co-payments ****Over-the-counter (OTC) expenses Dental out

  20. Job Title Ryan White Medical Case Manager (LMSW/LBSW) Employer/ Agency Houston Areas Community Services

    E-Print Network [OSTI]

    Azevedo, Ricardo

    and formulates diagnosis of social, emotional and substance abuse problems, develops treatment plans for each to mental health treatment, substance abuse treatment, medications, housing, and other client services, medications, and health care adherence particularly in regarding to HIV and other medical diagnoses