Sample records for radioactive sealed sources

  1. Sealed Radioactive Source Accountability

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

    1991-12-24T23:59:59.000Z

    To establish Department of Energy (DOE) interim policy and to provide guidance for sealed radioactive source accountability. The directive does not cancel any directives. Extended by DOE N 5400.10 to 12-24-93 & Extended by DOE N 5400.12 to 12-24-94.

  2. Sealed Radioactive Source Accountability

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

    1994-12-22T23:59:59.000Z

    This Notice extends DOE N 5400.9, Sealed Radioactive Source Accountability, of 12-24-91, until 12-24-95, unless sooner superseded or rescinded. The contents of DOE N 5400.9 will be updated and incorporated in the revised DOE O 5480.11, Radiation Protection for Occupational Workers.

  3. Reporting of Radioactive Sealed Sources

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

    2008-02-27T23:59:59.000Z

    To establish U.S. Department of Energy requirements for inventory reporting, transaction reporting, verification of reporting, and assign responsibilities for reporting of radioactive sealed sources. DOE N 251.86 extends this notice until 5-6-11. No cancellations. Canceled by DOE O 231.1B

  4. Sealed Radioactive Source Accountability and Control Guide

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

    1999-04-15T23:59:59.000Z

    For use with Title 10, Code of Federal Regulations, Part 835, Occupational Radiation Protection. This Guide provides an acceptable methodology for establishing and operating a sealed radioactive source accountability and control program that will comply with U.S. Department of Energy (DOE) requirements specified in Title 10 of the Code of Federal Regulations (CFR), Part 835, Occupational Radiation Protection (DOE 1998a), hereinafter referred to as 10 CFR 835. In particular, this Guide provides guidance for achieving compliance with subpart M of 10 CFR 835. Canceled by DOE G 441.1-1B.

  5. Management of Disused Radioactive Sealed Sources in Egypt - 13512

    SciTech Connect (OSTI)

    Mohamed, Y.T.; Hasan, M.A.; Lasheen, Y.F. [Hot Laboratories and Waste Management Center, Egyptian Atomic Energy Authority, 11787, Cairo (Egypt)] [Hot Laboratories and Waste Management Center, Egyptian Atomic Energy Authority, 11787, Cairo (Egypt)

    2013-07-01T23:59:59.000Z

    The future safe development of nuclear energy and progressive increasing use of sealed sources in medicine, research, industry and other fields in Egypt depends on the safe and secure management of disused radioactive sealed sources. In the past years have determined the necessity to formulate and apply the integrated management program for radioactive sealed sources to assure harmless and ecological rational management of disused sealed sources in Egypt. The waste management system in Egypt comprises operational and regulatory capabilities. Both of these activities are performed under legislations. The Hot Laboratories and Waste Management Center HLWMC, is considered as a centralized radioactive waste management facility in Egypt by law 7/2010. (authors)

  6. Integrated Management Program Radioactive Sealed Sources in Egypt

    SciTech Connect (OSTI)

    Hasan, A.; Cochran, J. R.; El-Adham, K.; El-Sorougy, R.

    2003-02-26T23:59:59.000Z

    The radioactive materials in ''public'' locations are typically contained in small, stainless steel capsules known as sealed radiation sources (RS). These capsules seal in the radioactive materials, but not the radiation, because it is the radiation that is needed for a wide variety of applications at hospitals, medical clinics, manufacturing plants, universities, construction sites, and other facilities in the public sector. Radiation sources are readily available, and worldwide there are hundreds of thousands of RS. The IMPRSS Project is a cooperative development between the Egyptian Atomic Energy Authority (EAEA), Egyptian Ministry of Health (MOH), Sandia National Laboratories (SNL), New Mexico Tech University (NMT), and Agriculture Cooperative Development International (ACDI/VOCA). SNL will coordinate the work scope between the participant organizations.

  7. Conditioning and Repackaging of Spent Radioactive Cs-137 and Co-60 Sealed Sources in Egypt - 13490

    SciTech Connect (OSTI)

    Hasan, M.A.; Selim, Y.T.; El-Zakla, T. [Hot Labs and Waste Management Center, Atomic Energy Authority, 3 Ahmed El-Zomor St., El-Zohour District, Naser City, 11787, Cairo (Egypt)] [Hot Labs and Waste Management Center, Atomic Energy Authority, 3 Ahmed El-Zomor St., El-Zohour District, Naser City, 11787, Cairo (Egypt)

    2013-07-01T23:59:59.000Z

    Radioactive Sealed sources (RSSs) are widely use all over the world in medicine, agriculture, industry, research, etc. The accidental misuse and exposure to RSSs has caused significant environmental contamination, serious injuries and many deaths. The high specific activity of the materials in many RSSs means that the spread of as little as microgram quantities can generate significant risk to human health and inhibit the use of buildings and land. Conditioning of such sources is a must to protect humans and environment from the hazard of ionizing radiation and contamination. Conditioning is also increase the security of these sources by decreasing the probability of stolen and/or use in terrorist attacks. According to the law No.7/2010, Egyptian atomic energy authority represented in the hot laboratories and waste management center (centralized waste facility, HLWMC) has the responsibility of collecting, conditioning, storing and management of all types of radioactive waste from all Egyptian territory including spent radioactive sealed sources (SRSSs). This paper explains the conditioning procedures for two of the most common SRSSs, Cs{sup 137} and Co{sup 60} sources which make up more than 90% of the total spent radioactive sealed sources stored in our centralized waste facility as one of the major activities of hot laboratories and waste management center. Conditioning has to meet three main objectives, be acceptable for storage, enable their safe transport, and comply with disposal requirements. (authors)

  8. Management of Disused Radioactive Sealed Sources in the Slovak Republic - 12100

    SciTech Connect (OSTI)

    Salzer, Peter [DECOM, a.s., 91901 Trnava (Slovakia)

    2012-07-01T23:59:59.000Z

    After splitting-up the Czechoslovak Federation in 1993, the system of management of institutional radioactive waste, where disused sources represent its significant part, had had to build from beginning, since all corresponding activities had remained in the Czech part of the Federation. The paper presents the development of legislative and institutional framework of the disused radioactive sealed source management, development of the national inventory and development of management practices. According the Governmental decision (1994), the management of disused sealed sources and institutional radioactive waste at whole was based on maximal utilization of facilities inside nuclear facilities, particularly in the NPP A1 (shut down in the past, currently under decommissioning). This approach has been recently changing by Governmental decision (2009) to construct 'non-nuclear facility' - central storage for remained disused sealed sources collected from the places of use, where they were stored in some cases for tens of years. The approaches to siting and construction of this storage facility will be presented, as well as the current approaches to solution of the disused radioactive sources final disposal. Environmental impact assessment process in regard to the given facility/activity is slowly drawing to a close. The final statement of the Ministry of Environment can be expected in January or February 2012, probably recommending option 1 as preferred [6]. According to the Slovak legislation, the final statement has a status of recommendation for ongoing processes leading to the siting license. Very recently, in December 2012, Government of the Slovak republic decided to postpone putting the facility into operation by the end of June, 2014. (author)

  9. Radioactive sealed sources: Reasonable accountability, exemption, and licensing activity thresholds -- A technical basis

    SciTech Connect (OSTI)

    Lee, D.W. [Los Alamos National Lab., NM (United States); Shingleton, K.L. [Lawrence Livermore National Lab., CA (United States)

    1996-07-01T23:59:59.000Z

    Perhaps owing to their small size and portability, some radiation accidents/incidents have involved radioactive sealed sources (RSSs). As a result, programs for the control and accountability of RSSs have come to be recommended and emplaced that essentially require RSSs to be controlled in a manner different from bulk, unsealed radioactive material. Crucially determining the total number of RSSs for which manpower-intensive radiation protection surveillance is provided is the individual RSS activity above which such surveillance is required and below which such effort is not considered cost effective. Individual RSS activity thresholds are typically determined through scenarios which impart a chosen internal or external limiting dose to Reference Man under specified exposure conditions. The resultant RSS threshold activity levels have meaning commensurate with the assumed scenario exposure parameters, i.e., if they are realistic and technically based. A review of how the Department of Energy (DOE), the International Atomic Energy Agency (IAEA), and the Nuclear Regulatory Commission (NRC) have determined their respective accountability, exemption, and licensing threshold activity values is provided. Finally, a fully explained method using references readily available to practicing health physicists is developed using realistic, technically-based calculation parameters by which RSS threshold activities may be locally generated.

  10. BROOKHAVEN NATIONAL Sealed Source

    E-Print Network [OSTI]

    Homes, Christopher C.

    BROOKHAVEN NATIONAL LABORATORY Sealed Source Contamination Incident October 13, 2011 #12;2 Cesium (Cs-137) Source Failure On September 28th @ ~1600 contamination event discovered · Two Radiological Contamination was from a Cs-137 (265 micro-curie) "sealed source" used to test area radiation monitors. · Source

  11. Radioactive material package seal tests

    SciTech Connect (OSTI)

    Madsen, M.M.; Humphreys, D.L.; Edwards, K.R.

    1990-01-01T23:59:59.000Z

    General design or test performance requirements for radioactive materials (RAM) packages are specified in Title 10 of the US Code of Federal Regulations Part 71 (US Nuclear Regulatory Commission, 1983). The requirements for Type B packages provide a broad range of environments under which the system must contain the RAM without posing a threat to health or property. Seals that provide the containment system interface between the packaging body and the closure must function in both high- and low-temperature environments under dynamic and static conditions. A seal technology program, jointly funded by the US Department of Energy Office of Environmental Restoration and Waste Management (EM) and the Office of Civilian Radioactive Waste Management (OCRWM), was initiated at Sandia National Laboratories. Experiments were performed in this program to characterize the behavior of several static seal materials at low temperatures. Helium leak tests on face seals were used to compare the materials. Materials tested include butyl, neoprene, ethylene propylene, fluorosilicone, silicone, Eypel, Kalrez, Teflon, fluorocarbon, and Teflon/silicone composites. Because most elastomer O-ring applications are for hydraulic systems, manufacturer low-temperature ratings are based on methods that simulate this use. The seal materials tested in this program with a fixture similar to a RAM cask closure, with the exception of silicone S613-60, are not leak tight (1.0 {times} 10{sup {minus}7} std cm{sup 3}/s) at manufacturer low-temperature ratings. 8 refs., 3 figs., 1 tab.

  12. Special Analysis for the Disposal of the Neutron Products Incorporated Sealed Source Waste Stream at the Area 5 Radioactive Waste Management Site, Nevada National Security Site, Nye County, Nevada

    SciTech Connect (OSTI)

    Shott, Gregory

    2014-08-31T23:59:59.000Z

    The purpose of this special analysis (SA) is to determine if the Neutron Products Incorporated (NPI) Sealed Sources waste stream (DRTK000000056, Revision 0) is suitable for disposal by shallow land burial (SLB) at the Area 5 Radioactive Waste Management Site (RWMS). The NPI Sealed Sources waste stream consists of 850 60Co sealed sources (Duratek [DRTK] 2013). The NPI Sealed Sources waste stream requires a special analysis (SA) because the waste stream 60Co activity concentration exceeds the Nevada National Security Site (NNSS) Waste Acceptance Criteria (WAC) Action Levels.

  13. Management of disused plutonium sealed sources

    SciTech Connect (OSTI)

    Whitworth, Julia Rose [Los Alamos National Laboratory; Pearson, Michael W [Los Alamos National Laboratory; Abeyta, Cristy [Los Alamos National Laboratory

    2010-01-01T23:59:59.000Z

    The Global Threat Reduction Initiative's (GTRI) Offsite Source Recovery Project (OSRP) has been recovering excess and unwanted radioactive sealed sources since 1999, including more than 2,400 Plutonium (Pu)-238 sealed sources and 653 Pu-239-bearing sources that represent more than 10% of the total sources recovered by GTRI/OSRP to date. These sources have been recovered from hundreds of sites within the United States (US) and around the world. OSRP grew out of early efforts at the Los Alamos National Laboratory (LANL) to recover and disposition excess Plutonium-239 (Pu-239) sealed sources that were distributed in the 1960s and 1970s under the Atoms for Peace Program, a loan-lease program that serviced 31 countries, as well as domestic users. In the conduct of these recovery operations, GTRI/OSRP has been required to solve problems related to knowledge-of-inventory, packaging and transportation of fissile and heat-source materials, transfer of ownership, storage of special nuclear material (SNM) both at US Department of Energy (DOE) facilities and commercially, and disposal. Unique issues associated with repatriation from foreign countries, including end user agreements required by some European countries and denials of shipment, will also be discussed.

  14. Characterization of Greater-Than-Class C sealed sources. Volume 1, Sealed sources held by specific licensees

    SciTech Connect (OSTI)

    Harris, G.

    1994-09-01T23:59:59.000Z

    Sealed sources are small, relatively high-activity radioactive sources typically encapsulated in a metallic container. The activities can range from less than 1 mCi to over 1,000 Ci. They are used in a variety of industries and are commonly available. Many of the sources will be classified as Greater-Than-Class C low-level radioactive waste (GTCC LLW) for the purpose of waste disposal. The US Department of Energy is responsible for disposing of this class of low-level radioactive waste. To better understand the scope of the GTCC LLW situation regarding sealed sources and to provide data to a model that projects future quantities of GTCC material, data from a comprehensive 1991 US Nuclear Regulatory Commission (NRC) survey and a related 1992 survey of Agreement States were analyzed to estimate the number, volume, and activity of Potential GTCC sealed sources currently available from specific licensees. Potential GTCC sealed sources are sources that exceed the limits stated in 10 CFR 61 when isotope concentrations are averaged over the volume of the capsule. Based on the surveys, the estimated number of existing Potential GTCC sealed sources held by specific licensees is 89,000, with an unpackaged volume of 0.93 m{sup 3} and an activity of 2,300,000 Ci. However, current disposal practices allow concentration averaging over the disposal container, substantially reducing the number of sealed sources which will actually be classified as GTCC LLW.

  15. An ideal sealed source life-cycle

    SciTech Connect (OSTI)

    Tompkins, Joseph Andrew [Los Alamos National Laboratory

    2009-01-01T23:59:59.000Z

    In the last 40 years, barriers to compliant and timely disposition of radioactive sealed sources have become apparent. The story starts with the explosive growth of nuclear gauging technologies in the 1960s. Dozens of companies in the US manufactured sources and many more created nuclear solutions to industrial gauging problems. Today they do not yet know how many Cat 1, 2, or 3 sources there are in the US. There are, at minimum, tens of thousands of sources, perhaps hundreds of thousands of sources. Affordable transportation solutions to consolidate all of these sources and disposition pathways for these sources do not exist. The root problem seems to be a lack of necessary regulatory framework that has allowed all of these problems to accumulate with no national plan for solving the problem. In the 1960s, Pu-238 displaced Pu-239 for most neutron and alpha source applications. In the 1970s, the availability of inexpensive Am-241 resulted in a proliferation of low energy gamma sources used in nuclear gauging, well logging, pacemakers, and X-ray fluorescence applications for example. In the 1980s, rapid expansion of worldwide petroleum exploration resulted in the expansion of Am-241 sources into international locations. Improvements of technology and regulation resulted in a change in isotopic distribution as Am-241 made Pu-239 and Pu-238 obsolete. Many early nuclear gauge technologies have been made obsolete as they were replaced by non-nuclear technoogies. With uncertainties in source end of life disposition and increased requirements for sealed source security, nuclear gauging technology is the last choice for modern process engineering gauging solutions. Over the same period, much was learned about licensing LLW disposition facilities as evident by the closure of early disposition facilities like Maxey Flats. The current difficulties in sealed source disposition start with adoption of the NLLW policy act of 1985, which created the state LLW compact system they we have today. This regulation created a new regulatory framework seen as promising at the time. However, now they recognize that, despite the good intentions, the NIJWP/85 has not solved any source disposition problems. The answer to these sealed source disposition problems is to adopt a philosophy to correct these regulatory issues, determine an interim solution, execute that solution until there is a minimal backlog of sources to deal with, and then let the mechanisms they have created solve this problem into the foreseeable future. The primary philosophical tenet of the ideal sealed source life cycle follows. You do not allow the creation (or importation) of any source whose use cannot be justified, which cannot be affordably shipped, or that does not have a well-delinated and affordable disposition pathway. The path forward dictates that we fix the problem by embracing the Ideal Source Life cycle. In figure 1, we can see some of the elements of the ideal source life cycle. The life cycle is broken down into four portions, manufacture, use, consolidation, and disposition. These four arbitrary elements allow them to focus on the ideal life cycle phases that every source should go through between manufacture and final disposition. As we examine the various phases of the sealed source life cycle, they pick specific examples and explore the adoption of the ideal life cycle model.

  16. Dynamic radioactive particle source

    DOE Patents [OSTI]

    Moore, Murray E.; Gauss, Adam Benjamin; Justus, Alan Lawrence

    2012-06-26T23:59:59.000Z

    A method and apparatus for providing a timed, synchronized dynamic alpha or beta particle source for testing the response of continuous air monitors (CAMs) for airborne alpha or beta emitters is provided. The method includes providing a radioactive source; placing the radioactive source inside the detection volume of a CAM; and introducing an alpha or beta-emitting isotope while the CAM is in a normal functioning mode.

  17. Control of Sealed Radioactive Sources

    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 offOCHCO OverviewAttachments4 Chairs MeetingOrder 2005-01 Consent|Reserve | Department2-01 January

  18. Sealed Source Security and Disposition: Progress and Prospects - 13515

    SciTech Connect (OSTI)

    Jennison, Meaghan [National Nuclear Security Administration, Washington, DC (United States)] [National Nuclear Security Administration, Washington, DC (United States); Martin, David W. [National Nuclear Security Administration/Energetics Inc., Washington, DC (United States)] [National Nuclear Security Administration/Energetics Inc., Washington, DC (United States); Cuthbertson, Abigail [US DOE, Washington, DC (United States)] [US DOE, Washington, DC (United States)

    2013-07-01T23:59:59.000Z

    Due to their high activity and portability, unsecured or abandoned sealed sources could cause significant health or environmental damage. Further, some of these sources could be used either individually or in aggregate in radiological dispersal devices commonly referred to as 'dirty bombs', resulting in significant social disruption and economic impacts in the billions of dollars. Disposal access for disused sealed sources, however, has been a serious challenge. From 2008 to 2012, sealed source disposal was available to only 14 states; additionally, waste acceptance criteria for sealed sources at the low-level waste disposal facilities in operation both prior to and after 2012 exclude some common yet potentially dangerous sealed sources. Recent developments, however, suggest that significant improvement in addressing this challenge is possible, although challenges remain. These developments include 1) the initiation of operations at the Waste Control Specialists (WCS) commercial low-level radioactive waste (LLRW) disposal facility in Andrews County, Texas; 2) the potential for significant revisions of the U.S. Nuclear Regulatory Commission's (NRC) 1995 'Final Branch Technical Position on Concentration Averaging and Encapsulation' (1995 BTP); and 3) the Utah Department of Environmental Quality's (UDEQ) approval of a license variance for sealed source disposal at the EnergySolutions LLRW disposal facility near Clive, Utah. (authors)

  19. RCRA designation of discarded americium/beryllium sealed sources

    SciTech Connect (OSTI)

    Kirner, N.P. [Ebasco Environmental, Idaho Falls, ID (United States)

    1994-09-01T23:59:59.000Z

    Many sealed sources containing americium and beryllium are used throughout construction, industry, and research, and will eventually require disposal. For planning purposes it is necessary to determine whether these sources, when disposed, constitute a mixed waste, i.e., a waste containing hazardous constituents regulated under the Resource Conservation and Recovery Act and radioactive constituents regulated under the Atomic Energy Act. Waste designation criteria contained in 40 CFR 261 are evaluated in detail in this report. It is determined that discarded americium/beryllium sealed sources do not contain any wastes listed in Subpart D of 40 CFR 261, nor do the discarded sources exhibit any hazardous characteristics. Therefore, it is concluded that discarded americium/beryllium sealed sources are not a mixed waste under regulations established by the US Environmental Protection Agency. Hazardous waste regulatory programs delegated to States, however, may have regulations that differ from those of the Federal government.

  20. Detecting Illicit Radioactive Sources

    SciTech Connect (OSTI)

    McDonald, Joseph C.; Coursey, Bert; Carter, Michael

    2004-11-01T23:59:59.000Z

    Specialized instruments have been developed to detect the presence of illicit radioactive sources that may be used by terrorists in radiation dispersal devices, so-called ''dirty bombs'' or improvised nuclear devices. This article discusses developments in devices to detect and measure radiation.

  1. Ion sources for sealed neutron tubes

    SciTech Connect (OSTI)

    Burns, E.J.T. [Sandia National Labs., Albuquerque, NM (United States). Neutron Tube Dept.; Bischoff, G.C. [Lockheed Martin Specialty Components, Largo, FL (United States)

    1996-11-01T23:59:59.000Z

    Fast and thermal neutron activation analysis with sealed neutron generators has been used to detect oil (oil logging), hazardous waste, fissile material, explosives, and contraband (drugs). Sealed neutron generators, used in the above applications, must be small and portable, have good electrical efficiency and long life. The ion sources used in the sealed neutron tubes require high gas utilization efficiencies or low pressure operation with high ionization efficiencies. In this paper, the authors compare a number of gas ion sources that can be used in sealed neutron tubes. The characteristics of the most popular ion source, the axial Penning discharge will be discussed as part of the zetatron neutron generator. Other sources to be discussed include the SAMIS source and RF ion source.

  2. Potential GTCC LLW sealed radiation source recycle initiatives

    SciTech Connect (OSTI)

    Fischer, D

    1992-04-01T23:59:59.000Z

    This report suggests 11 actions that have the potential to facilitate the recycling (reuse or radionuclide) of surplus commercial sealed radiation sources that would otherwise be disposed of as greater-than-Class C low-level radioactive waste. The suggestions serve as a basis for further investigation and discussion between the Department of Energy, Nuclear Regulatory Commission, Agreement States, and the commercial sector. Information is also given that describes sealed sources, how they are used, and problems associated with recycling, including legal concerns. To illustrate the nationwide recycling potential, Appendix A gives the estimated quantity and application information for sealed sources that would qualify for disposal in commercial facilities if not recycle. The report recommends that the Department of Energy initiate the organization of a forum to explore the suggested actions and other recycling possibilities.

  3. Technology, safety, and costs of decommissioning a reference large irradiator and reference sealed sources

    SciTech Connect (OSTI)

    Haffner, D.R.; Villelgas, A.J. [Pacific Northwest Lab., Richland, WA (United States)

    1996-01-01T23:59:59.000Z

    This report contains the results of a study sponsored by the US Nuclear Regulatory Commission (NRC) to examine the decommissioning of large radioactive irradiators and their respective facilities, and a broad spectrum of sealed radioactive sources and their respective devices. Conceptual decommissioning activities are identified, and the technology, safety, and costs (in early 1993 dollars) associated with decommissioning the reference large irradiator and sealed source facilities are evaluated. The study provides bases and background data for possible future NRC rulemaking regarding decommissioning, for evaluation of the reasonableness of planned decommissioning actions, and for determining if adequate funds are reserved by the licensees for decommissioning of their large irradiator or sealed source facilities. Another purpose of this study is to provide background and information to assist licensees in planning and carrying out the decommissioning of their sealed radioactive sources and respective facilities.

  4. Characterization of Greater-Than-Class C sealed sources. Volume 3, Sealed sources held by general licensees

    SciTech Connect (OSTI)

    Harris, G.

    1994-09-01T23:59:59.000Z

    This is the third volume in a series of three volumes characterizing the population of sealed sources that may become greater-than-Class C low-level radioactive waste (GTCC LLW). In this volume, those sources possessed by general licensees are discussed. General-licensed devices may contain sealed sources with significant amounts of radioactive material. However, the devices are designed to be safe to use without special knowledge of radiological safety practices. Devices containing Am-241 or Cm-244 sources are most likely to become GTCC LLW after concentration averaging. This study estimates that there are about 16,000 GTCC devices held by general licensees; 15,000 of these contain Am-241 sources and 1,000 contain Cm-244 sources. Additionally, this study estimates that there are 1,600 GTCC devices sold to general licensees each year. However, due to a lack of available information on general licensees in Agreement States, these estimates are uncertain. This uncertainty is quantified in the low and high case estimates given in this report, which span approximately an order of magnitude.

  5. Technical Position, Regarding Appropriate Accountable Sealed Radioactive

    Energy Savers [EERE]

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  6. Offsite source recovery project - ten years of sealed source recovery and disposal

    SciTech Connect (OSTI)

    Whitworth, Julia Rose [Los Alamos National Laboratory; Pearson, Mike [Los Alamos National Laboratory; Witkowski, Ioana [Los Alamos National Laboratory; Wald - Hopkins, Mark [Los Alamos National Laboratory; Cuthbertson, A [NNSA

    2010-01-01T23:59:59.000Z

    The Global Threat Reduction Initiative's (GTRI) Offsite Source Recovery Project (OSRP) has been recovering excess and unwanted radioactive sealed sources for ten years. In January 2009, GTRI announced that the project had recovered 20,000 sealed radioactive sources (this number has since increased to more than 23,000). This project grew out of early efforts at Los Alamos National Laboratory (LANL) to recover and disposition excess Plutonium-239 (Pu-239) sealed sources that were distributed in the 1960s and 1970s under the Atoms for Peace Program. Decades later, these sources began to exceed their special form certifications or fall out of regular use. As OSRP has collected and stored sealed sources, initially using 'No Path Forward' waste exemptions for storage within the Department of Energy (DOE) complex, it has consistently worked to create disposal pathways for the material it has recovered. The project was initially restricted to recovering sealed sources that would meet the definition of Greater-than-Class-C (GTCC) low-level radioactive waste, assisting DOE in meeting its obligations under the Low-level Radioactive Waste Policy Act Amendments (PL 99-240) to provide disposal for this type of waste. After being transferred from DOE-Environmental Management (EM) to the U.S. National Nuclear Security Administration (NNSA) to be part of GTRI, OSRP's mission was expanded to include not only material that would be classified as GTCC when it became waste, but also any other materials that might constitute a 'national security consideration.' It was recognized at the time that the GTCC category was a waste designation having to do with environmental consequence, rather than the threat posed by deliberate or accidental misuse. The project faces barriers to recovery in many areas, but disposal continues to be one of the more difficult to overcome. This paper discusses OSRP's disposal efforts over its 10-year history. For sources meeting the DOE definition of 'transuranic,' OSRP has achieved many milestones, including defense determinations for various isotopes, a WIPP RCRA permit modification to accommodate headspace gas sampling requirements, and approval of a peer-reviewed non-assay radiological characterization methodology. For non-transuranic sources, which OSRP began to recover in 2004, OSRP has achieved NEP A coverage for storage and implemented consolidated storage at both DOE and commercial locations, as well as completing several specific disposal operations. The closure of the Barnwell low-level waste disposal site in 2008 has left 36 states with absolutely no commercial disposal pathway for most sealed sources, increasing the demands on OSRP. This and other current challenges and future work will also be discussed.

  7. RADIOACTIVE MATERIAL SHIPPING PACKAGINGS AND METAL TO METAL SEALS FOUND IN THE CLOSURES OF CONTAINMENT VESSELS INCORPORATING CONE SEAL CLOSURES

    SciTech Connect (OSTI)

    Loftin, B; Glenn Abramczyk, G; Allen Smith, A

    2007-06-06T23:59:59.000Z

    The containment vessels for the Model 9975 radioactive material shipping packaging employ a cone-seal closure. The possibility of a metal-to-metal seal forming between the mating conical surfaces, independent of the elastomer seals, has been raised. It was postulated that such an occurrence would compromise the containment vessel hydrostatic and leakage tests. The possibility of formation of such a seal has been investigated by testing and by structural and statistical analyses. The results of the testing and the statistical analysis demonstrate and procedural changes ensure that hydrostatic proof and annual leakage testing can be accomplished to the appropriate standards.

  8. Compilation of current literature on seals, closures, and leakage for radioactive material packagings

    SciTech Connect (OSTI)

    Warrant, M.M.; Ottinger, C.A.

    1989-01-01T23:59:59.000Z

    This report presents an overview of the features that affect the sealing capability of radioactive material packagings currently certified by the US Nuclear Regulatory Commission. The report is based on a review of current literature on seals, closures, and leakage for radioactive material packagings. Federal regulations that relate to the sealing capability of radioactive material packagings, as well as basic equations for leakage calculations and some of the available leakage test procedures are presented. The factors which affect the sealing capability of a closure, including the properties of the sealing surfaces, the gasket material, the closure method and the contents are discussed in qualitative terms. Information on the general properties of both elastomer and metal gasket materials and some specific designs are presented. A summary of the seal material, closure method, and leakage tests for currently certified packagings with large diameter seals is provided. 18 figs., 9 tabs.

  9. Comparison of General Purpose Heat Source testing with the ANSI N43.6-1977 (R1989) sealed source standard

    SciTech Connect (OSTI)

    Grigsby, C.O.

    1998-03-26T23:59:59.000Z

    This analysis provides a comparison of the testing of Radioisotope Thermoelectric Generators (RTGs) and RTG components with the testing requirements of ANSI N43.6-1977 (R1989) ``Sealed Radioactive Sources, Categorization``. The purpose of this comparison is to demonstrate that the RTGs meet or exceed the requirements of the ANSI standard, and thus can be excluded from the radioactive inventory of the Chemistry and Metallurgy Research (CMR) building in Los Alamos per Attachment 1 of DOE STD 1027-92. The approach used in this analysis is as follows: (1) describe the ANSI sealed source classification methodology; (2) develop sealed source performance requirements for the RTG and/or RTG components based on criteria from the accident analysis for CMR; (3) compare the existing RTG or RTG component test data to the CMR requirements; and (4) determine the appropriate ANSI classification for the RTG and/or RTG components based on CMR performance requirements. The CMR requirements for treating RTGs as sealed sources are derived from the radiotoxicity of the isotope ({sup 238}P7) and amount (13 kg) of radioactive material contained in the RTG. The accident analysis for the CMR BIO identifies the bounding accidents as wing-wide fire, explosion and earthquake. These accident scenarios set the requirements for RTGs or RTG components stored within the CMR.

  10. Radiation Sources and Radioactive Materials (Connecticut)

    Broader source: Energy.gov [DOE]

    These regulations apply to persons who receive, transfer, possess, manufacture, use, store, handle, transport or dispose of radioactive materials and/or sources of ionizing radiation. Some...

  11. The Nonactinide Isotope and Sealed Sources Management Group

    SciTech Connect (OSTI)

    Low, J. L.; Polansky, G. F.; Parks, D. L.

    2002-02-27T23:59:59.000Z

    The Nonactinide Isotope and Sealed Sources Management Group (NISSMG) is sponsored by the Department of Energy (DOE) Office of Environmental Management and managed by Albuquerque Operations Office (DOE/AL) to serve as a complex-wide resource for the management of DOE-owned Nonactinide Isotope and Sealed Source (NISS) materials. NISS materials are defined as including: any isotope in sealed sources or standards; and isotopes, regardless of form, with atomic number less than 90. The NISSMG assists DOE sites with the storage, reuse, disposition, transportation, and processing of these materials. The NISSMG has focused its efforts to date at DOE closure sites due to the immediacy of their problems. Recently, these efforts were broadened to include closure facilities at non-closure sites. Eventually, the NISSMG plans to make its resources available to all DOE sites. This paper documents the lessons learned in managing NISS materials at DOE sites to date.

  12. The IAEA and Control of Radioactive SourcesThe

    SciTech Connect (OSTI)

    Dodd, B.

    2004-10-03T23:59:59.000Z

    This presentation discusses the International Atomic Energy Agency (IAEA) and the control of radioactive sources.

  13. Radioactive Materials Manual Scope and Applicability

    E-Print Network [OSTI]

    Rhoads, James

    material. Radioactive material covered includes all sealed and unsealed sources. Sealed sources of radioactive material contained within machinery such as liquid scintillation counters, gas chromatographs radioactive material, such as x-ray equipment, electron microscopes, lasers, and radio-frequency generators

  14. One million curies of radioactive material recovered

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

    Removal Program and OSRP mission includes removal and disposal of excess, unwanted, abandoned, or orphan radioactive sealed sources that pose a potential risk to national...

  15. Particle beam generator using a radioactive source

    DOE Patents [OSTI]

    Underwood, David G. (Naperville, IL)

    1993-01-01T23:59:59.000Z

    The apparatus of the present invention selects from particles emitted by a radioactive source those particles having momentum within a desired range and focuses the selected particles in a beam having at least one narrow cross-dimension, and at the same time attenuates potentially disruptive gamma rays and low energy particles. Two major components of the present invention are an achromatic bending and focusing system, which includes sector magnets and quadrupole, and a quadrupole doublet final focus system. Permanent magnets utilized in the apparatus are constructed of a ceramic (ferrite) material which is inexpensive and easily machined.

  16. Particle beam generator using a radioactive source

    DOE Patents [OSTI]

    Underwood, D.G.

    1993-03-30T23:59:59.000Z

    The apparatus of the present invention selects from particles emitted by a radioactive source those particles having momentum within a desired range and focuses the selected particles in a beam having at least one narrow cross-dimension, and at the same time attenuates potentially disruptive gamma rays and low energy particles. Two major components of the present invention are an achromatic bending and focusing system, which includes sector magnets and quadrupole, and a quadrupole doublet final focus system. Permanent magnets utilized in the apparatus are constructed of a ceramic (ferrite) material which is inexpensive and easily machined.

  17. Quality assurance program plan for FRG sealed isotopic heat sources project (C-229)

    SciTech Connect (OSTI)

    Tanke, J.M.

    1997-05-16T23:59:59.000Z

    This QAPP implements the Quality Assurance Program Plan for the FRG Sealed Isotopic Heat Sources Project (C-229). The heat source will be relocated from the 324 Building and placed in interim storage at the Central Waste Complex (CWC).

  18. CLIMATIC MODULATION OF SOURCE, RESERVOIR AND SEAL FACIES ALONG THE ZONAL CLIMATIC GRADIENT OF PANGEA

    E-Print Network [OSTI]

    Olsen, Paul E.

    reservoir and seal combinations. Fundy-type sequences tend to have no or few organic-rich shales and have#12;CLIMATIC MODULATION OF SOURCE, RESERVOIR AND SEAL FACIES ALONG THE ZONAL CLIMATIC GRADIENT with new paleomagnetic data from the Newark basin of Eastern North America and the predictions of recent

  19. DECOMMISSIONING OF A CAESIUM-137 SEALED SOURCE PRODUCTION FACILITY

    SciTech Connect (OSTI)

    Murray, A.; Abbott, H.

    2003-02-27T23:59:59.000Z

    Amersham owns a former Caesium-137 sealed source production facility. They commissioned RWE NUKEM to carry out an Option Study to determine a strategy for the management of this facility and then the subsequent decommissioning of it. The decommissioning was carried out in two sequential phases. Firstly robotic decommissioning followed by a phase of manual decommissioning. This paper describes the remote equipment designed built and operated, the robotic and manual decommissioning operations performed, the Safety Management arrangements and summarizes the lessons learned. Using the equipment described the facility was dismantled and decontaminated robotically. Some 2300kg of Intermediate Level Waste containing in the order of 4000Ci were removed robotically from the facility. Ambient dose rates were reduced from 100's of R per hour {gamma} to 100's of mR per hour {gamma}. The Telerobotic System was then removed to allow man access to complete the decommissioning. Manual decommissioning reduced ambient dose rates further to less than 1mR per hour {gamma} and loose contamination levels to less than 0.25Bq/cm2. This allowed access to the facility without respiratory protection.

  20. Conditioning of the 4 Curies Radium-226 Sealed Radiation Source in Thailand

    SciTech Connect (OSTI)

    Punnachaiya, M.; Sawangsri, T.; Wanabongse, P.; Pruantonsai, P.; Nunjan, P.; Phattanasub, A.; Ya-Anant, N.; Thiangtrongjit, S. [Office of Atoms for Peace (OAP), Vibhavadi Rangsit Road, Chatuchak District, Bangkok 10900 (Thailand)

    2006-07-01T23:59:59.000Z

    This paper describes the conditioning of the 4 curies Radium-226 (Ra-226) sealed radiation source using as a teletherapy unit for cancer treatment in Thailand. The conditioning was under the International Atomic Energy Agency (IAEA) supervision and budgetary supports, comprised of 6 operational steps: the surface dose rate and actual dimension of radium unit measurements, the appropriate lead shielding design with IAEA approval, confirmation of radioactive contamination before conditioning (smear test and radon gas leakage test), transfer of radium source unit into the designed shielding, confirmation of radioactive contamination and dose rate measurement after conditioning, and transportation of Ra-226 conditioning waste package to OAP interim waste storage. The Ra-226 unit was taken out of OAP temporary waste storage for the surface dose rate and the actual dimension measurements behind the 12 inches thick heavy concrete shielding. The maximum measured surface dose rate was 70 R/hr. The special lead container was designed according to its surface dose rate along the source unit which the maximum permissible dose limit for surface dose rate of waste package after conditioning at 2 mSv/hr was applied. The IAEA approved container had total weight of 2.4 ton. After the confirmation of radioactive contamination, Ra-226 source unit was transferred and loaded in the designed lead shielding within 2 minutes. The results of smear test before and after conditioning including radon gas leakage test revealed that there was no radioactive contamination. After conditioning, the surface dose rate measured on the top, bottom were 15,10 mR/hr and varied from 6 - 50 mR/hr around lead container. The Ra-226 conditioning waste package was safely transported to store in OAP interim waste storage. Total working time including the time consumed for radon gas leakage test was 3.5 hours. The total radiation dose received by 16 operators, were ranged from 1 - 69.84 {mu}Sv and the operational team completed the conditioning safely within the effective dose limit for occupational exposure of 50 mSv/year (200 {mu}Sv/day). (authors)

  1. Benefits of PositionSensitive Detectors for Radioactive Source Detection

    E-Print Network [OSTI]

    Scott, Clayton

    of detecting radioactive sources is to count gamma­ray photons emitted from it. Such a detector, hereafter background. There is a wide body of literature on the problem of gamma­ ray source detection. A common-02 they appear point­like to a detector [1]. There are many gamma­ray detection modalities including stationary

  2. Registration for the Hanford Site: Sources of radioactive emissions

    SciTech Connect (OSTI)

    Silvia, M.J.

    1993-04-01T23:59:59.000Z

    This Registration Application serves to renew the registration for all Hanford Site sources of radioactive air emissions routinely reported to the State of Washington Department of Health (DOH). The current registration expires on August 15, 1993. The Application is submitted pursuant to the Washington Administrative Code (WAC) Chapter 246--247, and is consistent with guidance provided by DOH for renewal. The Application subdivides the Hanford Site into six major production, processing or research areas. Those six areas are in the 100 Area, 200 East Area, 200 West Area, 300 Area, 400 Area, and 600 Area. Each major group of point sources within the six areas listed above is represented by a Source Registration for Radioactive Air Emissions form. Annual emissions. for the sources are listed in the ``Radionuclide Air Emissions Report for the Hanford Site,`` published annually. It is a requirement that the following Statement of Compliance be provided: ``The radioactive air emissions from the above sources do meet the emissions standards contained in Chapter 173-480-040 WAC, Ambient Air Quality Standards and Emissions Limits for Radionuclides. As the Statement of Compliance pertains to this submittal, the phrase ``above sources`` is to be understood as meaning the combined air emissions from all sources registered by this submittal.

  3. Standard review plan for applications for sealed source and device evaluations and registrations

    SciTech Connect (OSTI)

    NONE

    1996-11-01T23:59:59.000Z

    The purpose of this document is to provide the reviewer of a request for a sealed source or device safety evaluation with the information and materials necessary to make a determination that the product is acceptable for licensing purposes. It provides the reviewer with a listing of the applicable regulations and industry standards, policies affecting evaluation and registration, certain administrative procedures to be followed, and information on how to perform the evaluation and write the registration certificate. Standard review plans are prepared for the guidance of the Office of Nuclear Material Safety and Safeguards staff responsible for the review of a sealed source or device application. This document is made available to the public as part of the Commission`s policy to inform the nuclear industry and the general public of regulatory procedures and policies. Standard review plans are not substitutes for regulatory guides or the Commission`s regulations and compliance with them is not required.

  4. Cable attachment for a radioactive brachytherapy source capsule

    DOE Patents [OSTI]

    Gross, Ian G; Pierce, Larry A

    2006-07-18T23:59:59.000Z

    In cancer brachytherapy treatment, a small californium-252 neutron source capsule is attached to a guide cable using a modified crimping technique. The guide cable has a solid cylindrical end, and the attachment employs circumferential grooves micromachined in the solid cable end. The attachment was designed and tested, and hardware fabricated for use inside a radioactive hot cell. A welding step typically required in other cable attachments is avoided.

  5. Justification Of The Use Of Boreholes For Disposal Of Sealed Radiological Sources

    SciTech Connect (OSTI)

    Zarling, John [Los Alamos National Laboratory; Johnson, Peter [Los Alamos National Laboratory

    2008-01-01T23:59:59.000Z

    Soon there will be only 14 states in two compacts that are able to dispose of Low Level Waste (LLW): the Northwest and Rocky Mountain compact with disposal options in Richland, Washington, and the Atlantic compact with disposal options in Barnwell, South Carolina. How do states not in one of the two compacts dispose of their LLW? The Off-Site Source Recovery Project can take possession and dispose of some of the unwanted transuranic sources at the Waste Isolation Pilot Plant (WIPP). However, there will be no path forward for states outside of the two compacts for disposal of their non-transuranic LLW. A solution that has been much discussed, debated and researched, but has not been put into wide scale practice, is the borehole disposal concept. It is the author's position that companies that drill and explore for oil have been disposing of sources in borehole-like structures for years. It should be noted that these companies are not purposely disposing of these sources, but the sources are irretrievable and must be abandoned. Additionally, there are Nuclear Regulatory Commission (NRC) regulations that must be followed to seal the well that contains the lost and abandoned source. According to the NRC Event Notification Reports database, there were a minimum of 29 reports of lost and abandoned sources in oil wells between December 1999 and October 2006. The sources were lost at depths between 2,018-18,887 feet, or 600-5,750 meters. The companies that are performing explorations with the aid of sealed radiological sources must follow regulation 10 CFR Part 39. Subsection 15 outlines the procedures that must be followed if sources are determined to be irretrievable and abandoned in place. If the NRC allows and has regulations in place for oil companies, why can't states and/or companies be allowed to dispose of LLW in a similar fashion?

  6. Flowsheets and source terms for radioactive waste projections

    SciTech Connect (OSTI)

    Forsberg, C.W. (comp.)

    1985-03-01T23:59:59.000Z

    Flowsheets and source terms used to generate radioactive waste projections in the Integrated Data Base (IDB) Program are given. Volumes of each waste type generated per unit product throughput have been determined for the following facilities: uranium mining, UF/sub 6/ conversion, uranium enrichment, fuel fabrication, boiling-water reactors (BWRs), pressurized-water reactors (PWRs), and fuel reprocessing. Source terms for DOE/defense wastes have been developed. Expected wastes from typical decommissioning operations for each facility type have been determined. All wastes are also characterized by isotopic composition at time of generation and by general chemical composition. 70 references, 21 figures, 53 tables.

  7. 2011 Radioactive Materials Usage Survey for Unmonitored Point Sources

    SciTech Connect (OSTI)

    Sturgeon, Richard W. [Los Alamos National Laboratory

    2012-06-27T23:59:59.000Z

    This report provides the results of the 2011 Radioactive Materials Usage Survey for Unmonitored Point Sources (RMUS), which was updated by the Environmental Protection (ENV) Division's Environmental Stewardship (ES) at Los Alamos National Laboratory (LANL). ES classifies LANL emission sources into one of four Tiers, based on the potential effective dose equivalent (PEDE) calculated for each point source. Detailed descriptions of these tiers are provided in Section 3. The usage survey is conducted annually; in odd-numbered years the survey addresses all monitored and unmonitored point sources and in even-numbered years it addresses all Tier III and various selected other sources. This graded approach was designed to ensure that the appropriate emphasis is placed on point sources that have higher potential emissions to the environment. For calendar year (CY) 2011, ES has divided the usage survey into two distinct reports, one covering the monitored point sources (to be completed later this year) and this report covering all unmonitored point sources. This usage survey includes the following release points: (1) all unmonitored sources identified in the 2010 usage survey, (2) any new release points identified through the new project review (NPR) process, and (3) other release points as designated by the Rad-NESHAP Team Leader. Data for all unmonitored point sources at LANL is stored in the survey files at ES. LANL uses this survey data to help demonstrate compliance with Clean Air Act radioactive air emissions regulations (40 CFR 61, Subpart H). The remainder of this introduction provides a brief description of the information contained in each section. Section 2 of this report describes the methods that were employed for gathering usage survey data and for calculating usage, emissions, and dose for these point sources. It also references the appropriate ES procedures for further information. Section 3 describes the RMUS and explains how the survey results are organized. The RMUS Interview Form with the attached RMUS Process Form(s) provides the radioactive materials survey data by technical area (TA) and building number. The survey data for each release point includes information such as: exhaust stack identification number, room number, radioactive material source type (i.e., potential source or future potential source of air emissions), radionuclide, usage (in curies) and usage basis, physical state (gas, liquid, particulate, solid, or custom), release fraction (from Appendix D to 40 CFR 61, Subpart H), and process descriptions. In addition, the interview form also calculates emissions (in curies), lists mrem/Ci factors, calculates PEDEs, and states the location of the critical receptor for that release point. [The critical receptor is the maximum exposed off-site member of the public, specific to each individual facility.] Each of these data fields is described in this section. The Tier classification of release points, which was first introduced with the 1999 usage survey, is also described in detail in this section. Section 4 includes a brief discussion of the dose estimate methodology, and includes a discussion of several release points of particular interest in the CY 2011 usage survey report. It also includes a table of the calculated PEDEs for each release point at its critical receptor. Section 5 describes ES's approach to Quality Assurance (QA) for the usage survey. Satisfactory completion of the survey requires that team members responsible for Rad-NESHAP (National Emissions Standard for Hazardous Air Pollutants) compliance accurately collect and process several types of information, including radioactive materials usage data, process information, and supporting information. They must also perform and document the QA reviews outlined in Section 5.2.6 (Process Verification and Peer Review) of ES-RN, 'Quality Assurance Project Plan for the Rad-NESHAP Compliance Project' to verify that all information is complete and correct.

  8. Experiments with radioactive samples at the Advanced Photon Source.

    SciTech Connect (OSTI)

    Veluri, V. R.; Justus, A.; Glagola, B.; Rauchas, A.; Vacca, J.

    2000-11-01T23:59:59.000Z

    The Advanced Photon Source (APS) at Argonne National Laboratory is a national synchrotron-radiation light source research facility. The 7 GeV electron Storage Ring is currently delivering intense high brilliance x-ray beams to a total of 34 beamlines with over 120 experiment stations to members of the international scientific community to carry out forefront basic and applied research in several scientific disciplines. Researchers come to the APS either as members of Collaborative Access Teams (CATs) or as Independent Investigators (IIs). Collaborative Access Teams comprise large number of investigators from universities, industry, and research laboratories with common research objectives. These teams are responsible for the design, construction, finding, and operation of beamlines. They are the owners of their experimental enclosures (''hutches'') designed and built to meet their specific research needs. Fig. 1 gives a plan view of the location of the Collaborative Access Teams by Sector and Discipline. In the past two years, over 2000 individual experiments were conducted at the APS facility. Of these, about 60 experiments involved the use of radioactive samples, which is less than 3% of the total. However, there is an increase in demand for experiment stations to accommodate the use of radioactive samples in different physical forms embedded in various matrices with activity levels ranging from trace amounts of naturally occurring radionuclides to MBq (mCi) quantities including transuranics. This paper discusses in some detail the steps in the safety review process for experiments involving radioactive samples and how ALARA philosophy is invoked at each step and implemented.

  9. Probing New Physics with Underground Accelerators and Radioactive Sources

    E-Print Network [OSTI]

    Eder Izaguirre; Gordan Krnjaic; Maxim Pospelov

    2014-05-19T23:59:59.000Z

    New light, weakly coupled particles can be efficiently produced at existing and future high-intensity accelerators and radioactive sources in deep underground laboratories. Once produced, these particles can scatter or decay in large neutrino detectors (e.g Super-K and Borexino) housed in the same facilities. We discuss the production of weakly coupled scalars $\\phi$ via nuclear de-excitation of an excited element into the ground state in two viable concrete reactions: the decay of the $0^+$ excited state of $^{16}$O populated via a $(p,\\alpha)$ reaction on fluorine and from radioactive $^{144}$Ce decay where the scalar is produced in the de-excitation of $^{144}$Nd$^*$, which occurs along the decay chain. Subsequent scattering on electrons, $e(\\phi,\\gamma)e$, yields a mono-energetic signal that is observable in neutrino detectors. We show that this proposed experimental set-up can cover new territory for masses $250\\, {\\rm keV}\\leq m_\\phi \\leq 2 m_e$ and couplings to protons and electrons, $10^{-11} new physics component to the neutrino and nuclear astrophysics programs at underground facilities.

  10. MARSAME Appendix B B. SOURCES OF BACKGROUND RADIOACTIVITY

    E-Print Network [OSTI]

    : · The Nuclear Regulatory Commission (NRC) provides information concerning background radioactivity in Background as a Residual Radioactivity Criterion for Decommissioning NUREG-1501 (NRC 1994). · The United Nations Scientific

  11. EA-1059: Radioactive Source Recovery Program, Los Alamos, New Mexico

    Broader source: Energy.gov [DOE]

    This EA evaluates the environmental impacts of the proposal to establish a program to accept and recover surplus americium-241 mixed with beryllium metal (Be) and plutonium-238 mixed with Be sealed...

  12. Nuclear reactor sealing system

    DOE Patents [OSTI]

    McEdwards, James A. (Calabasas, CA)

    1983-01-01T23:59:59.000Z

    A liquid metal-cooled nuclear reactor sealing system. The nuclear reactor includes a vessel sealed at its upper end by a closure head. The closure head comprises at least two components, one of which is rotatable; and the two components define an annulus therebetween. The sealing system includes at least a first and second inflatable seal disposed in series in an upper portion of the annulus. The system further includes a dip seal extending into a body of insulation located adjacent a bottom portion of the closure head. The dip seal comprises a trough formed by a lower portion of one of the components, and a seal blade pendently supported from the other component and extending downwardly into the trough. A body of liquid metal is contained in the trough which submerges a portion of the seal blade. The seal blade is provided with at least one aperture located above the body of liquid metal for providing fluid communication between the annulus intermediate the dip seal and the inflatable seals, and a body of cover gas located inside the vessel. There also is provided means for introducing a purge gas into the annulus intermediate the inflatable seals and the seal blade. The purge gas is introduced in an amount sufficient to substantially reduce diffusion of radioactive cover gas or sodium vapor up to the inflatable seals. The purge gas mixes with the cover gas in the reactor vessel where it can be withdrawn from the vessel for treatment and recycle to the vessel.

  13. Seals and Sealing Rings

    E-Print Network [OSTI]

    Younger, John G.

    2010-01-01T23:59:59.000Z

    A short encyclopedia entry about seals and signet rings, and their use, from antiquity to modernity....

  14. Mycenaean Seals and Sealings

    E-Print Network [OSTI]

    Younger, John G.

    2010-01-01T23:59:59.000Z

    This encyclopedia entry summarizes what we know about the use of seals on the Mycenaean mainland....

  15. Radiation Awareness TrainingRadiation Awareness Training Radioactive Material &Radioactive Material &

    E-Print Network [OSTI]

    Sherrill, David

    · Check all incoming radioactive packages for contamination · Survey all radioactive materials labs) · Sealed sources ­ Nickel-63 (Gas chromatograph) ­ Cesium-137 (Liquid Scintillation Counter) ­ Neutron · CONTAMINATION CONTROL IS THE KEY · Should not leave room until surveyed by ORS #12;Protective Measures ·· Time

  16. Radiological Characterization Technical Report on Californium-252 Sealed Source Transuranic Debris Waste for the Off-Site Source Recovery Project at Los Alamos National Laboratory

    SciTech Connect (OSTI)

    Feldman, Alexander [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2014-04-24T23:59:59.000Z

    This document describes the development and approach for the radiological characterization of Cf-252 sealed sources for shipment to the Waste Isolation Pilot Plant. The report combines information on the nuclear material content of each individual source (mass or activity and date of manufacture) with information and data on the radionuclide distributions within the originating nuclear material. This approach allows for complete and accurate characterization of the waste container without the need to take additional measurements. The radionuclide uncertainties, developed from acceptable knowledge (AK) information regarding the source material, are applied to the summed activities in the drum. The AK information used in the characterization of Cf-252 sealed sources has been qualified by the peer review process, which has been reviewed and accepted by the Environmental Protection Agency.

  17. Surface Contamination Surface contamination from radioactive isotopes is a source of background in the Borex-

    E-Print Network [OSTI]

    Chapter 5 Surface Contamination Surface contamination from radioactive isotopes is a source of background in the Borex- ino detector. Surface contaminants can be in the form of macroscopic dust particles contamination is primarily a problem because the radioactive contaminants can be trans- ferred from the surfaces

  18. Import and Export of Category 1 and 2 Radioactive Sources and Aggregated Quantities

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

    2008-11-10T23:59:59.000Z

    This Order has been developed to provide requirements and responsibilities pertaining to the International Atomic Energy Agency CODEOC/2004, Code of Conduct on the Safety and Security of Radioactive Sources. No cancellation. Admin Chg 1, 7-10-13.

  19. Import and Export of Category 1 and 2 Radioactive Sources Aggregated Quantities

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

    2008-11-10T23:59:59.000Z

    To formalize relevant guidance contained in the International Atomic Energy Agency (IAEA) CODEOC 2004, Code of Conduct on the Safety and Security of Radioactive Sources, January 2004 and IAEA CODEOC IMP-EXP 2005, Guidance on the Import and Export of Radioactive Sources, March 2005 and to assign responsibilities and prescribe procedures for DOE elements and contractors in support of the Import-Export Guidance. Admin Chg 1, 7-10-2013. Certified 12-3-14.

  20. Operating Experience Level 3 2012-01: Control of Sealed Radioactive Sources

    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 offOCHCO Overview OCHCO Overview OCHCO OCHCO OverviewFreedom ofDepartment offor Mitigating|

  1. Disused Radioactive Sources Secured in Georgia | National Nuclear...

    National Nuclear Security Administration (NNSA)

    of disused high activity sources from the Institute of Radiobiology to a more secure storage facility. As part of NNSA's broader cooperative effort to help prevent nuclear and...

  2. Problems with packaged sources in foreign countries

    SciTech Connect (OSTI)

    Abeyta, Cristy L [Los Alamos National Laboratory; Matzke, James L [Los Alamos National Laboratory; Zarling, John [Los Alamos National Laboratory; Tompkin, J. Andrew [Los Alamos National Laboratory

    2010-01-01T23:59:59.000Z

    The Global Threat Reduction Initiative's (GTRI) Off-Site Source Recovery Project (OSRP), which is administered by the Los Alamos National Laboratory (LANL), removes excess, unwanted, abandoned, or orphan radioactive sealed sources that pose a potential threat to national security, public health, and safety. In total, GTRI/OSRP has been able to recover more than 25,000 excess and unwanted sealed sources from over 825 sites. In addition to transuranic sources, the GTRI/OSRP mission now includes recovery of beta/gamma emitting sources, which are of concern to both the U.S. government and the International Atomic Energy Agency (IAEA). This paper provides a synopsis of cooperative efforts in foreign countries to remove excess and unwanted sealed sources by discussing three topical areas: (1) The Regional Partnership with the International Atomic Energy Agency; (2) Challenges in repatriating sealed sources; and (3) Options for repatriating sealed sources.

  3. DOEE A-1059 Environmental Assessment Radioactive Source Recovery...

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

    Alamos County are remote from major metropolitan areas and major sources of industrial pollution. In 1992, a i r quality at LANL was much better than ambient air quality...

  4. An ion source module for the Beijing Radioactive Ion-beam Facility

    SciTech Connect (OSTI)

    Cui, B., E-mail: cui@ciae.ac.cn; Huang, Q.; Tang, B.; Ma, R.; Chen, L.; Ma, Y. [China Institute of Atomic Energy, Beijing (China)] [China Institute of Atomic Energy, Beijing (China)

    2014-02-15T23:59:59.000Z

    An ion source module is developed for Beijing Radioactive Ion-beam Facility. The ion source module is designed to meet the requirements of remote handling. The connection and disconnection of the electricity, cooling and vacuum between the module and peripheral units can be executed without on-site manual work. The primary test of the target ion source has been carried out and a Li{sup +} beam has been extracted. Details of the ion source module and its primary test results are described.

  5. Sealing device

    SciTech Connect (OSTI)

    Garcia-Crespo, Andres Jose

    2013-12-10T23:59:59.000Z

    A sealing device for sealing a gap between a dovetail of a bucket assembly and a rotor wheel is disclosed. The sealing device includes a cover plate configured to cover the gap and a retention member protruding from the cover plate and configured to engage the dovetail. The sealing device provides a seal against the gap when the bucket assemply is subjected to a centrifugal force.

  6. Low-level radioactive waste source terms for the 1992 integrated data base

    SciTech Connect (OSTI)

    Loghry, S L; Kibbey, A H; Godbee, H W; Icenhour, A S; DePaoli, S M

    1995-01-01T23:59:59.000Z

    This technical manual presents updated generic source terms (i.e., unitized amounts and radionuclide compositions) which have been developed for use in the Integrated Data Base (IDB) Program of the U.S. Department of Energy (DOE). These source terms were used in the IDB annual report, Integrated Data Base for 1992: Spent Fuel and Radioactive Waste Inventories, Projections, and Characteristics, DOE/RW-0006, Rev. 8, October 1992. They are useful as a basis for projecting future amounts (volume and radioactivity) of low-level radioactive waste (LLW) shipped for disposal at commercial burial grounds or sent for storage at DOE solid-waste sites. Commercial fuel cycle LLW categories include boiling-water reactor, pressurized-water reactor, fuel fabrication, and uranium hexafluoride (UF{sub 6}) conversion. Commercial nonfuel cycle LLW includes institutional/industrial (I/I) waste. The LLW from DOE operations is category as uranium/thorium fission product, induced activity, tritium, alpha, and {open_quotes}other{close_quotes}. Fuel cycle commercial LLW source terms are normalized on the basis of net electrical output [MW(e)-year], except for UF{sub 6} conversion, which is normalized on the basis of heavy metal requirement [metric tons of initial heavy metal ]. The nonfuel cycle commercial LLW source term is normalized on the basis of volume (cubic meters) and radioactivity (curies) for each subclass within the I/I category. The DOE LLW is normalized in a manner similar to that for commercial I/I waste. The revised source terms are based on the best available historical data through 1992.

  7. A Low-Tech, Low-Budget Storage Solution for High Level Radioactive Sources

    SciTech Connect (OSTI)

    Brett Carlsen; Ted Reed; Todd Johnson; John Weathersby; Joe Alexander; Dave Griffith; Douglas Hamelin

    2014-07-01T23:59:59.000Z

    The need for safe, secure, and economical storage of radioactive material becomes increasingly important as beneficial uses of radioactive material expand (increases inventory), as political instability rises (increases threat), and as final disposal and treatment facilities are delayed (increases inventory and storage duration). Several vendor-produced storage casks are available for this purpose but are often costly — due to the required design, analyses, and licensing costs. Thus the relatively high costs of currently accepted storage solutions may inhibit substantial improvements in safety and security that might otherwise be achieved. This is particularly true in areas of the world where the economic and/or the regulatory infrastructure may not provide the means and/or the justification for such an expense. This paper considers a relatively low-cost, low-technology radioactive material storage solution. The basic concept consists of a simple shielded storage container that can be fabricated locally using a steel pipe and a corrugated steel culvert as forms enclosing a concrete annulus. Benefits of such a system include 1) a low-tech solution that utilizes materials and skills available virtually anywhere in the world, 2) a readily scalable design that easily adapts to specific needs such as the geometry and radioactivity of the source term material), 3) flexible placement allows for free-standing above-ground or in-ground (i.e., below grade or bermed) installation, 4) the ability for future relocation without direct handling of sources, and 5) a long operational lifetime . ‘Le mieux est l’ennemi du bien’ (translated: The best is the enemy of good) applies to the management of radioactive materials – particularly where the economic and/or regulatory justification for additional investment is lacking. Development of a low-cost alternative that considerably enhances safety and security may lead to a greater overall risk reduction than insisting on solutions that remain economically and/or politically ‘out of reach’.

  8. Conformable seal

    DOE Patents [OSTI]

    Neef, W.S.; Lambert, D.R.

    1982-08-10T23:59:59.000Z

    Sealing apparatus and method, comprising first and second surfaces or membranes, at least one of which surfaces is deformable, placed in proximity to one another. Urging means cause these surfaces to contact one another in a manner such that the deformable surface deforms to conform to the geometry of the other surface, thereby creating a seal. The seal is capable of undergoing multiple cycles of sealing and unsealing.

  9. Security seal

    DOE Patents [OSTI]

    Gobeli, Garth W. (Albuquerque, NM)

    1985-01-01T23:59:59.000Z

    Security for a package or verifying seal in plastic material is provided by a print seal with unique thermally produced imprints in the plastic. If tampering is attempted, the material is irreparably damaged and thus detectable. The pattern of the imprints, similar to "fingerprints" are recorded as a positive identification for the seal, and corresponding recordings made to allow comparison. The integrity of the seal is proved by the comparison of imprint identification records made by laser beam projection.

  10. Seal assembly

    DOE Patents [OSTI]

    Johnson, Roger Neal (Hagaman, NY); Longfritz, William David (Fonda, NY)

    2001-01-01T23:59:59.000Z

    A seal assembly that seals a gap formed by a groove comprises a seal body, a biasing element, and a connection that connects the seal body to the biasing element to form the seal assembly. The seal assembly further comprises a concave-shaped center section and convex-shaped contact portions at each end of the seal body. The biasing element is formed from an elastic material and comprises a convex-shaped center section and concave-shaped biasing zones that are opposed to the convex-shaped contact portions. The biasing element is adapted to be compressed to change a width of the seal assembly from a first width to a second width that is smaller than the first width. In the compressed state, the seal assembly can be disposed in the groove. After release of the compressing force, the seal assembly expands. The contact portions will move toward a surface of the groove and the biasing zones will move into contact with another surface of the groove. The biasing zones will bias the contact portions of the seal body against the surface of the groove.

  11. WM'05 Conference, February 27 March 3, 2005, Tucson, AZ WM-5278 IDENTIFYING RADIOACTIVE SOURCES AT THE DEMOLITION SITE

    E-Print Network [OSTI]

    ), in a cooperative partnership with the scrap metal industry, developed a CD ROM based training program to provide's scrap metal supply. In order to prevent this unwanted radioactive material from entering metal will be detected in scrap metal loads. Shielding of the sources by the metal scrap, location of the source within

  12. Simulated Performance of Algorithms for the Localization of Radioactive Sources from a Position Sensitive Radiation Detecting System (COCAE)

    SciTech Connect (OSTI)

    Karafasoulis, K. [Greek Atomic Energy Commission, Patriarxou Grigoriou and Neapoleos, 15310, Athens (Greece); Hellenic Army Academy, 16673 Vari (Greece); Zachariadou, K. [Greek Atomic Energy Commission, Patriarxou Grigoriou and Neapoleos, 15310, Athens (Greece); Technological Educational Institute of Piraeus, Thivon 250, 12244, Egaleo (Greece); Seferlis, S.; Kaissas, I.; Potiriadis, C. [Greek Atomic Energy Commission, Patriarxou Grigoriou and Neapoleos, 15310, Athens (Greece); Lambropoulos, C. [Technological Educational Institute of Chalkida, Psachna Evias, 34400 Greece (Greece); Loukas, D. [Institute of Nuclear Physics, National Center for Scientific Research Demokritos 15310, Athens (Greece)

    2011-12-13T23:59:59.000Z

    Simulation studies are presented regarding the performance of algorithms that localize point-like radioactive sources detected by a position sensitive portable radiation instrument (COCAE). The source direction is estimated by using the List Mode Maximum Likelihood Expectation Maximization (LM-ML-EM) imaging algorithm. Furthermore, the source-to-detector distance is evaluated by three different algorithms based on the photo-peak count information of each detecting layer, the quality of the reconstructed source image, and the triangulation method. These algorithms have been tested on a large number of simulated photons over a wide energy range (from 200 keV to 2 MeV) emitted by point-like radioactive sources located at different orientations and source-to-detector distances.

  13. Effect of geometrical configuration of radioactive sources on radiation intensity in beta-voltaic nuclear battery system: A preliminary result

    SciTech Connect (OSTI)

    Basar, Khairul, E-mail: khbasar@fi.itb.ac.id; Riupassa, Robi D., E-mail: khbasar@fi.itb.ac.id; Bachtiar, Reza, E-mail: khbasar@fi.itb.ac.id; Badrianto, Muldani D., E-mail: khbasar@fi.itb.ac.id [Nuclear Physics and Biophysics Research Division, Faculty of Mathematics and Natural Sciences, Institut Teknologi Bandung (Indonesia)

    2014-01-01T23:59:59.000Z

    It is known that one main problem in the application of beta-voltaic nuclear battery system is its low efficiency. The efficiency of the beta-voltaic nuclear battery system mainly depends on three aspects: source of radioactive radiation, interface between materials in the system and process of converting electron-hole pair to electric current in the semiconductor material. In this work, we show the effect of geometrical configuration of radioactive sources on radiation intensity of beta-voltaic nuclear battery system.

  14. IMPACTS OF SOURCE TERM HETEROGENEITIES ON WATER PATHWAY DOSE.

    SciTech Connect (OSTI)

    SULLIVAN, T.; GUSKOV, A.; POSKAS, P.; RUPERTI, N.; HANUSIK, V.; ET AL.

    2004-09-15T23:59:59.000Z

    Radioactive sealed sources are used extensively throughout the world in different field and various activities such as medicine, agriculture, industry, research, education military applications, as well as nuclear facilities. The International Basic Safety Standards for Protection against Ionizing Radiation and for the Safety of Radiation sources [1] defines a sealed source as ''radioactive material that is (a) permanently sealed in capsule or (b) closely bounded and in a solid form. The capsule or material of sealed source shall be strong enough to maintain remain leak free under the conditions of use and wear for which the source was designed, also under foreseeable mishaps''. When a radioactive sealed source is no longer needed, or becomes unfit for the intended application it is considered spent. A spent sealed source is not necessarily a waste because it can be used in other applications. If for any technical or economic reason (decay, obsolete equipment and technique, worn out equipment) no further use is foreseen, the spent sealed source is considered spent and becomes radioactive waste [2] [3]. In addition, a source may be taken out of service temporarily or indefinitely. In this case the source is out of used (''disused'') but not considered spent [4]. Sources that are not in active use and have not being declared as spent are considered as disused sealed sources [4]. Considering the potential radiation hazards associated with such waste it has to be managed and disposed of in a way that will ensure that the potential radiation hazards are adequately managed and controlled in compliance with the appropriate safety principles and criteria. It is recognized that there exists today experience and means for all steps in the management of disused sealed sources, except disposal of [2]. In many countries, disused sealed sources represent a part of the radioactive waste inventory being characterized generally with high specific activities and small physical sizes and for which a solution has to be found in term of long-term disposal. Together with their casing and packaging, they are one form of heterogeneous waste; many other forms of waste with heterogeneous properties exist. They may arise in very small quantities and with very specific characteristics in the case of small producers, or in larger streams with standard characteristics in others. This wide variety of waste induces three main different levels of waste heterogeneity: (1) hot spot (e.g. disused sealed sources); (2) large item inside a package (e.g. metal components); and (3) very large items to be disposed of directly in the disposal unit (e.g. irradiated pipes, vessels). Safety assessments generally assume a certain level of waste homogeneity in most of the existing or proposed disposal facilities. There is a need to evaluate the appropriateness of such an assumption and the influence on the results of safety assessment. This need is especially acute in the case of sealed sources. There are many cases where are storage conditions are poor, or there is improper management leading to a radiological accident, some with significant or detrimental impacts. Disposal in a near surface disposal facility has been used in the past for some disused sealed sources. This option is currently in use for others sealed sources, or is being studied for the rest of them. The regulatory framework differs greatly between countries. In some countries, large quantities of disused sealed sources have been disposed of without any restriction, in others their disposal is forbidden by law. In any case, evaluation of the acceptability of disposal of disused sealed sources in near surface disposal facility is of utmost importance.

  15. Quick-sealing design for radiological containment

    SciTech Connect (OSTI)

    Rampolla, Donald S. (Pittsburgh, PA); Speer, Elmer (Ruffsdale, PA)

    1991-01-01T23:59:59.000Z

    A quick-sealing assembly and method for forming an adhesive seal on opposite sides of a mechanical seal for a flexible containment bag of the type used for working with radioactively contaminated objects. The assembly includes an elongated mechanical fastener having opposing engaging members affixed at a predetermined distance from each of the elongated edges, with an adhesive layer formed between the mechanical fastener and the elongated edge such that upon engagement of the mechanical fastener and adhesive layers to opposing containment fabric, a neat triple hermetic seal is formed.

  16. Quick-sealing design for radiological containment

    SciTech Connect (OSTI)

    Rampolia, Donald S. (Pittsburgh, PA); Speer, Elmer (Ruffsdale, PA)

    1990-01-01T23:59:59.000Z

    A quick-sealing assembly and method for forming an adhesive seal on opposite sides of a mechanical seal for a flexible containment bag of the type used for working with radioactively contaminated objects. The assembly includes an elongated mechanical fastener having opposing engaging members affixed at a predetermined distance from each of the elongated edges, with an adhesive layer formed between the mechanical fastener and the elongated edge such that upon engagement of the mechanical fastener and adhesive layers to opposing containment fabric, a neat triple hermetic seal is formed.

  17. Quick-sealing design for radiological containment

    SciTech Connect (OSTI)

    Rampdla, D.S.; Speer, E.

    1991-11-05T23:59:59.000Z

    This patent describes a quick-sealing assembly and method for forming an adhesive seal on opposite sides of a mechanical seal for a flexible containment bag of the type used for working with radioactively contaminated objects. The assembly includes an elongated mechanical fastener having opposing engaging members affixed at a predetermined distance from each of the elongated edges, with an adhesive layer formed between the mechanical fastener and the elongated edge such that upon engagement of the mechanical fastener and adhesive layers to opposing containment fabric, a neat triple hermetic seal is formed.

  18. Quick-sealing design for radiological containment

    SciTech Connect (OSTI)

    Rampolia, D.S.; Speer, E.

    1990-04-10T23:59:59.000Z

    This patent describes a quick-sealing assembly and method for forming an adhesive seal on opposite sides of a mechanical seal for a flexible containment bag of the type used for working with radioactively contaminated objects. The assembly includes an elongated mechanical fastener having opposing engaging members affixed at a predetermined distance from each of the elongated edges, with an adhesive layer formed between the mechanical fastener and the elongated edge such that upon engagement of the mechanical fastener and adhesive layers to opposing containment fabric, a neat triple hermetic seal is formed.

  19. Radioactive waste disposal package

    DOE Patents [OSTI]

    Lampe, Robert F. (Bethel Park, PA)

    1986-01-01T23:59:59.000Z

    A radioactive waste disposal package comprising a canister for containing vitrified radioactive waste material and a sealed outer shell encapsulating the canister. A solid block of filler material is supported in said shell and convertible into a liquid state for flow into the space between the canister and outer shell and subsequently hardened to form a solid, impervious layer occupying such space.

  20. The Effect of Gamma-ray Detector Energy Resolution on the Ability to Identify Radioactive Sources

    SciTech Connect (OSTI)

    Nelson, K E; Gosnell, T B; Knapp, D A

    2009-03-05T23:59:59.000Z

    This report describes the results of an initial study on radiation detector spectral resolution, along with the underlying methodology used. The study was done as part of an ongoing effort in Detection Modeling and Operational Analysis (DMOA) for the DNDO System Architecture Directorate. The study objective was to assess the impact of energy resolution on radionuclide identification capability, measured by the ability to reliably discriminate between spectra associated with 'threats' (defined as fissile materials) and radioactive 'non-threats' that might be present in the normal stream of commerce. Although numerous factors must be considered in deciding which detector technology is appropriate for a specific application, spectral resolution is a critical one for homeland security applications in which a broad range of non-threat sources are present and very low false-alarm rates are required. In this study, we have proposed a metric for quantifying discrimination capability, and have shown how this metric depends on resolution. In future work we will consider other important factors, such as efficiency and volume, and the relative frequency of spectra known to be discrimination challenges in practical applications.

  1. Handling of Highly Radioactive Radiation Sources in a Hot Cell Using a Mechanically Driven Cell Crane - 13452

    SciTech Connect (OSTI)

    Klute, Stefan; Huber, Wolfgang-Bruno [Siempelkamp Nukleartechnik GmbH, Am Taubenfeld 25/1, 69123 Heidelberg (Germany)] [Siempelkamp Nukleartechnik GmbH, Am Taubenfeld 25/1, 69123 Heidelberg (Germany); Meyer, Franz [Nuclear Engineering Seibersdorf GmbH, 2444 Seibersdorf (Austria)] [Nuclear Engineering Seibersdorf GmbH, 2444 Seibersdorf (Austria)

    2013-07-01T23:59:59.000Z

    In 2010, Siempelkamp Nukleartechnik GmbH was awarded the contract for design and erection of a Hot Cell for handling and storage of highly radioactive radiation sources. This Hot Cell is part of a new hot cell laboratory, constructed for the NHZ (Neues Handhabungszentrum = New Handling Center) of the Nuclear Engineering Seibersdorf GmbH (NES). All incurring radioactive materials from Austria are collected in the NHZ, where they are safely conditioned and stored temporarily until their final storage. The main tasks of the NES include, apart from the collection, conditioning and storage of radioactive waste, also the reprocessing and the decontamination of facilities and laboratories originating from 45 years of research and development at the Seibersdorf site as well as the operation of the Hot Cell Laboratory [1]. The new Hot Cell Laboratory inside the NHZ consists of the following room areas: - One hot cell, placed in the center, for remote controlled, radiation protected handling of radioactive materials, including an integrated floor storage for the long-term temporary storage of highly radioactive radiation sources; - An anteroom for the loading and unloading of the hot cell; - One control room for the remote controlling of the hot cell equipment; - One floor storage, placed laterally to the hot cell, for burial, interim storage and removal of fissionable radioactive material in leak-proof packed units in 100 l drums. The specific design activity of the hot cell of 1.85 Pbq relating to 1-Me-Radiator including the integrated floor storage influences realization and design of the components used in the cell significantly. (authors)

  2. User`s Manual for the SOURCE1 and SOURCE2 Computer Codes: Models for Evaluating Low-Level Radioactive Waste Disposal Facility Source Terms (Version 2.0)

    SciTech Connect (OSTI)

    Icenhour, A.S.; Tharp, M.L.

    1996-08-01T23:59:59.000Z

    The SOURCE1 and SOURCE2 computer codes calculate source terms (i.e. radionuclide release rates) for performance assessments of low-level radioactive waste (LLW) disposal facilities. SOURCE1 is used to simulate radionuclide releases from tumulus-type facilities. SOURCE2 is used to simulate releases from silo-, well-, well-in-silo-, and trench-type disposal facilities. The SOURCE codes (a) simulate the degradation of engineered barriers and (b) provide an estimate of the source term for LLW disposal facilities. This manual summarizes the major changes that have been effected since the codes were originally developed.

  3. Radioactive waste management in the USSR: A review of unclassified sources. Volume 2

    SciTech Connect (OSTI)

    Bradley, D.J.

    1991-03-01T23:59:59.000Z

    The Soviet Union does not currently have an overall radioactive waste management program or national laws that define objectives, procedures, and standards, although such a law is being developed, according to the Soviets. Occupational health and safety does not appear to receive major attention as it does in Western nations. In addition, construction practices that would be considered marginal in Western facilities show up in Soviet nuclear power and waste management operations. The issues involved with radioactive waste management and environmental restoration are being investigated at several large Soviet institutes; however, there is little apparent interdisciplinary integration between them, or interaction with the USSR Academy of Sciences. It is expected that a consensus on technical solutions will be achieved, but it may be slow in coming, especially for final disposal of high-level radioactive wastes and environmental restoration of contaminated areas. Meanwhile, many treatment, solidification, and disposal options for radioactive waste management are being investigated by the Soviets.

  4. Radioactive waste management in the USSR: A review of unclassified sources

    SciTech Connect (OSTI)

    Bradley, D.J.

    1991-03-01T23:59:59.000Z

    The Soviet Union does not currently have an overall radioactive waste management program or national laws that define objectives, procedures, and standards, although such a law is being developed, according to the Soviets. Occupational health and safety does not appear to receive major attention as it does in Western nations. In addition, construction practices that would be considered marginal in Western facilities show up in Soviet nuclear power and waste management operations. The issues involved with radioactive waste management and environmental restoration are being investigated at several large Soviet institutes; however, there is little apparent interdisciplinary integration between them, or interaction with the USSR Academy of Sciences. It is expected that a consensus on technical solutions will be achieved, but it may be slow in coming, especially for final disposal of high-level radioactive wastes and environmental restoration of contaminated areas. Meanwhile, many treatment, solidification, and disposal options for radioactive waste management are being investigated by the Soviets.

  5. RADIOACTIVE WASTE MANAGEMENT IN THE USSR: A REVIEW OF UNCLASSIFIED SOURCES, 1963-1990

    SciTech Connect (OSTI)

    Bradley, D. J.; Schneider, K. J.

    1990-03-01T23:59:59.000Z

    The Soviet Union operates a vast and growing radioactive waste management system. Detailed information on this system is rare and a general overall picture only emerges after a review of a great deal of literature. Poor waste management practices and slow implementation of environmental restoration activities have caused a great deal of national concern. The release of information on the cause and extent of an accident involving high-level waste at the Kyshtym production reactor site in 1957, as well as other contamination at the site, serve to highlight past Soviet waste management practices. As a result, the area of waste management is now receiving greater emphasis, and more public disclosures. Little is known about Soviet waste management practices related to uranium mining, conversion, and fuel fabrication processes. However, releases of radioactive material to the environment from uranium mining and milling operations, such as from mill tailings piles, are causing public concern. Official Soviet policy calls for a closed fuel cycle, with reprocessing of power reactor fuel that has been cooled for five years. For power reactors, only VVER-440 reactor fuel has been reprocessed in any significant amount, and a decision on the disposition of RBMK reactor fuel has been postponed indefinitely. Soviet reprocessing efforts are falling behind schedule; thus longer storage times for spent fuel will be required, primarily at multiple reactor stations. Information on reprocessing in the Soviet Union has been severely limited until 1989, when two reprocessing sites were acknowledged by the Soviets. A 400-metric ton (MT) per year reprocessing facility, located at Kyshtym, has been operational since 1949 for reprocessing production reactor fuel. This facility is reported to have been reprocessing VVER-440 and naval reactor fuel since 1978, with about 2000 MT of VVER-440 fuel being reprocessed by July 1989. A second facility, located near Krasnoyarsk and having a 1500 MT per year capacity as the first of several modules, was about 30% completed by July 1989. The completion of this plant was subsequently "indefinitely postponed." The initial reprocessing scheme at the Kyshtym site used sodium uranyl acetate precipitation from fuel dissolved in nitric acid solutions. The basic method~ ology now appears to be based on the conventional PUREX process. Dry reprocessing on a pilot or laboratory scale has been under way in Dimitrovgrad since 1984, and a larger unit is now being built, according to the French CEA. Perhaps significantly, much research is being done on partitioning high-level waste into element fractions. The Soviets appear to have the technology to remove radioactive noble gases released during reprocessing operations; however, there are no indications of its implementation. Millions of curies of liquid low- and intermediate-level wastes have been disposed of by well injection into underground areas where they were supposedly contained by watertight rock strata. Some gaseous wastes were also disposed of by well injection. This practice is not referred to in recent literature and thus may not be widely used today. Rather, it appears that these waste streams are now first treated to reduce volume, and then solidified using bitumen or concrete. These solidified liquid wastes from Soviet nuclear power reactor operations, along with solid wastes, are disposed of in shallow-land burial sites located at most large power reactor stations. In addition, 35 shallow-land burial sites have been alluded to by the Soviets for disposal of industrial, medical, and research low-level wastes as well as ionization sources. Research on tritium-bearing and other gaseous wastes is mentioned, as well as a waste minimization program aimed at reducing the volume of waste streams by 30%. The Soviets have announced that their high-level waste management plan is to 1) store liquid wastes for 3-5 years; 2) incorporate the waste into glass (at a final glass volume of 100-150 liters/MT of fuel reprocessed); 3) set it aside in air-cooled storage

  6. Triple acting radial seal

    DOE Patents [OSTI]

    Ebert, Todd A (West Palm Beach, FL); Carella, John A (Jupiter, FL)

    2012-03-13T23:59:59.000Z

    A triple acting radial seal used as an interstage seal assembly in a gas turbine engine, where the seal assembly includes an interstage seal support extending from a stationary inner shroud of a vane ring, the interstage seal support includes a larger annular radial inward facing groove in which an outer annular floating seal assembly is secured for radial displacement, and the outer annular floating seal assembly includes a smaller annular radial inward facing groove in which an inner annular floating seal assembly is secured also for radial displacement. A compliant seal is secured to the inner annular floating seal assembly. The outer annular floating seal assembly encapsulates the inner annular floating seal assembly which is made from a very low alpha material in order to reduce thermal stress.

  7. Regenerator seal

    DOE Patents [OSTI]

    Davis, Leonard C. (Indianapolis, IN); Pacala, Theodore (Indianapolis, IN); Sippel, George R. (Indianapolis, IN)

    1981-01-01T23:59:59.000Z

    A method for manufacturing a hot side regenerator cross arm seal assembly having a thermally stablilized wear coating with a substantially flat wear surface thereon to seal between low pressure and high pressure passages to and from the hot inboard side of a rotary regenerator matrix includes the steps of forming a flat cross arm substrate member of high nickel alloy steel; fixedly securing the side edges of the substrate member to a holding fixture with a concave surface thereacross to maintain the substrate member to a slightly bent configuration on the fixture surface between the opposite ends of the substrate member to produce prestress therein; applying coating layers on the substrate member including a wear coating of plasma sprayed nickel oxide/calcium flouride material to define a wear surface of slightly concave form across the restrained substrate member between the free ends thereon; and thereafter subjecting the substrate member and the coating thereon to a heat treatment of 1600.degree. F. for sixteen hours to produce heat stabilizing growth in the coating layers on the substrate member and to produce a thermally induced growth stress in the wear surface that substantially equalizes the prestress in the substrate whereby when the cross arm is removed from the fixture surface following the heat treatment step a wear face is formed on the cross arm assembly that will be substantially flat between the ends.

  8. WM'05 Conference, February 27 -March 3, 2005, Tucson, AZ TRACKING RADIOACTIVE SOURCES IN COMMERCE

    E-Print Network [OSTI]

    Identification [RFID] tags). Preliminary pseudo-random testing results have been very positive. Once we have radiological and nuclear material tracking and monitoring in commerce and is part of a larger program entitled in proximity to radioactive materials. Current candidate technologies include, (1) Satellite, (2) Radio

  9. Cask systems development program seal technology

    SciTech Connect (OSTI)

    Madsen, M.M.; Edwards, K.R.; Humphreys, D.L.

    1991-01-01T23:59:59.000Z

    General design or test performance requirements for radioactive materials (RAM) packages are specified in Title 10 of the US Code of Federal Regulations Part 71 (10 CFR 71). Seals that provide the containment system interface between the packaging body and the closure must function in both high- and low-temperature environments under dynamic and static conditions. Experiments were performed to characterize the performance of several seal materials at low temperatures. Helium leak tests on face seals were used to compare the materials. Materials tested include butyl, neoprene, ethylene propylene, fuorosilicone, silicone, Eypel, Kalrez, Teflon, fluorocarbon, and Teflon/silicone composites. Results show that the seal materials tested, with the exception of silicone S613-60, are not leak tight at manufacturer low-temperature ratings. This paper documents the initial series of experiments developed to characterize the performance of several static seals under conditions representative of RAM transport container environments. Helium leak rates of face seals were measured at low and ambient temperatures to compare seal materials. As scaling laws have not been developed for seals, the leakage rates measured in this program are intended to be used in a qualitative rather than quantitative manner. 5 refs., 7 figs., 2 tabs.

  10. Turbine disc sealing assembly

    DOE Patents [OSTI]

    Diakunchak, Ihor S.

    2013-03-05T23:59:59.000Z

    A disc seal assembly for use in a turbine engine. The disc seal assembly includes a plurality of outwardly extending sealing flange members that define a plurality of fluid pockets. The sealing flange members define a labyrinth flow path therebetween to limit leakage between a hot gas path and a disc cavity in the turbine engine.

  11. 10 years and 20,000 sources: the offsite source recovery project

    SciTech Connect (OSTI)

    Whitworth, Julia R [Los Alamos National Laboratory; Abeyta, Cristy L [Los Alamos National Laboratory; Pearson, Michael W [Los Alamos National Laboratory

    2009-01-01T23:59:59.000Z

    The Global Threat Reduction Initiative's (GTRI) Offsite Source Recovery Project (OSRP) has been recovering excess and unwanted sealed sources for ten years. In January 2009, GTRI announced that the project had recovered 20,000 sealed radioactive sources. This project grew out of early efforts at Los Alamos National Laboratory (LANL) to recover and disposition excess Plutonium-239 (Pu-239) sealed sources that were distributed in the 1960s and 1970s under the Atoms for Peace Program. Sealed source recovery was initially considered a waste management activity, as evidenced by its initial organization under the Department of Energy's (DOE's) Environmental Management (EM) program. After the terrorist attacks of 2001, however, the interagency community began to recognize the threat posed by excess and unwanted radiological material, particularly those that could not be disposed at the end of their useful life. After being transferred to the National Nuclear Security Administration (NNSA) to be part of GTRI, OSRP's mission was expanded to include not only material that would be classified as Greater-than-Class-C (GTCC) when it became waste, but also any other materials that might be a 'national security consideration.' This paper discusses OSRP's history, recovery operations, expansion to accept high-activity beta-gamma-emitting sealed sources and devices and foreign-possessed sources, and more recent efforts such as cooperative projects with the Council on Radiation Control Program Directors (CRCPD) and involvement in GTRI's Search and Secure project. Current challenges and future work will also be discussed.

  12. Mechanical seal assembly

    DOE Patents [OSTI]

    Kotlyar, Oleg M. (Salt Lake City, UT)

    2001-01-01T23:59:59.000Z

    An improved mechanical seal assembly is provided for sealing rotating shafts with respect to their shaft housings, wherein the rotating shafts are subject to substantial axial vibrations. The mechanical seal assembly generally includes a rotating sealing ring fixed to the shaft, a non-rotating sealing ring adjacent to and in close contact with the rotating sealing ring for forming an annular seal about the shaft, and a mechanical diode element that applies a biasing force to the non-rotating sealing ring by means of hemispherical joint. The alignment of the mechanical diode with respect to the sealing rings is maintained by a series of linear bearings positioned axially along a desired length of the mechanical diode. Alternative embodiments include mechanical or hydraulic amplification components for amplifying axial displacement of the non-rotating sealing ring and transferring it to the mechanical diode.

  13. Mechanical seal assembly

    DOE Patents [OSTI]

    Kotlyar, Oleg M. (Salt Lake City, UT)

    2002-01-01T23:59:59.000Z

    An improved mechanical seal assembly is provided for sealing rotating shafts with respect to their shaft housings, wherein the rotating shafts are subject to substantial axial vibrations. The mechanical seal assembly generally includes a rotating sealing ring fixed to the shaft, a non-rotating sealing ring adjacent to and in close contact with the rotating sealing ring for forming an annular seal about the shaft, and a mechanical diode element that applies a biasing force to the non-rotating sealing ring by means of hemispherical joint. The alignment of the mechanical diode with respect to the sealing rings is maintained by a series of linear bearings positioned axially along a desired length of the mechanical diode. Alternative embodiments include mechanical or hydraulic amplification components for amplifying axial displacement of the non-rotating sealing ring and transfering it to the mechanical diode.

  14. Turbine blade platform seal

    DOE Patents [OSTI]

    Zagar, Thomas W. (Winter Springs, FL); Schiavo, Anthony L. (Oviedo, FL)

    2001-01-01T23:59:59.000Z

    A rotating blade group 90 for a turbo-machine having an improved device for sealing the gap 110 between the edges 112,114 of adjacent blade platforms 96,104. The gap 110 between adjacent blades 92,100 is sealed by a seal pin 20 its central portion 110 and by a seal plate 58,60 at each of the front 54 and rear 56 portions. The seal plates 58,60 are inserted into corresponding grooves 62,64 formed in the adjacent edges 112,114 of adjoining blades 92,100 and held in place by end plates 40,42. The end of the seal plates 58,60 may be chamfered 78,80 to improve the seal against the end plate 40,42. The seal pin 20 provides the required damping between the blades 92,100 and the seal plates 58,60 provide improved sealing effectiveness.

  15. The development of radioactive sample surrogates for training and exercises

    SciTech Connect (OSTI)

    Martha Finck; Bevin Brush; Dick Jansen; David Chamberlain; Don Dry; George Brooks; Margaret Goldberg

    2012-03-01T23:59:59.000Z

    The development of radioactive sample surrogates for training and exercises Source term information is required for to reconstruct a device used in a dispersed radiological dispersal device. Simulating a radioactive environment to train and exercise sampling and sample characterization methods with suitable sample materials is a continued challenge. The Idaho National Laboratory has developed and permitted a Radioactive Response Training Range (RRTR), an 800 acre test range that is approved for open air dispersal of activated KBr, for training first responders in the entry and exit from radioactively contaminated areas, and testing protocols for environmental sampling and field characterization. Members from the Department of Defense, Law Enforcement, and the Department of Energy participated in the first contamination exercise that was conducted at the RRTR in the July 2011. The range was contaminated using a short lived radioactive Br-82 isotope (activated KBr). Soil samples contaminated with KBr (dispersed as a solution) and glass particles containing activated potassium bromide that emulated dispersed radioactive materials (such as ceramic-based sealed source materials) were collected to assess environmental sampling and characterization techniques. This presentation summarizes the performance of a radioactive materials surrogate for use as a training aide for nuclear forensics.

  16. Radioactive Waste Radioactive Waste

    E-Print Network [OSTI]

    Slatton, Clint

    form · Separate liquid from solid · Radionuclide · Separate all but H3/C14 #12;#12;Radioactive Waste;Radioactive Waste H3/C14 solids Type B (non-incinerable) metal glass hazardous materials #12;#12;Radioactive#12;Radioactive Waste at UF Bldg 831 392-8400 #12;Radioactive Waste · Program is designed to

  17. Rotary shaft sealing assembly

    DOE Patents [OSTI]

    Dietle, Lannie L. (Houston, TX); Schroeder, John E. (Richmond, TX); Kalsi, Manmohan S. (Houston, TX); Alvarez, Patricio D. (Richmond, TX)

    2010-09-21T23:59:59.000Z

    A rotary shaft sealing assembly in which a first fluid is partitioned from a second fluid in a housing assembly having a rotary shaft located at least partially within. In one embodiment a lip seal is lubricated and flushed with a pressure-generating seal ring preferably having an angled diverting feature. The pressure-generating seal ring and a hydrodynamic seal may be used to define a lubricant-filled region with each of the seals having hydrodynamic inlets facing the lubricant-filled region. Another aspect of the sealing assembly is having a seal to contain pressurized lubricant while withstanding high rotary speeds. Another rotary shaft sealing assembly embodiment includes a lubricant supply providing a lubricant at an elevated pressure to a region between a lip seal and a hydrodynamic seal with a flow control regulating the flow of lubricant past the lip seal. The hydrodynamic seal may include an energizer element having a modulus of elasticity greater than the modulus of elasticity of a sealing lip of the hydrodynamic seal.

  18. Rotary shaft sealing assembly

    DOE Patents [OSTI]

    Dietle, Lannie L; Schroeder, John E; Kalsi, Manmohan S; Alvarez, Patricio D

    2013-08-13T23:59:59.000Z

    A rotary shaft sealing assembly in which a first fluid is partitioned from a second fluid in a housing assembly having a rotary shaft located at least partially within. In one embodiment a lip seal is lubricated and flushed with a pressure-generating seal ring preferably having an angled diverting feature. The pressure-generating seal ring and a hydrodynamic seal may be used to define a lubricant-filled region with each of the seals having hydrodynamic inlets facing the lubricant-filled region. Another aspect of the sealing assembly is having a seal to contain pressurized lubricant while withstanding high rotary speeds. Another rotary shaft sealing assembly embodiment includes a lubricant supply providing a lubricant at an elevated pressure to a region between a lip seal and a hydrodynamic seal with a flow control regulating the flow of lubricant past the lip seal. The hydrodynamic seal may include an energizer element having a modulus of elasticity greater than the modulus of elasticity of a sealing lip of the hydrodynamic seal.

  19. Inboard seal mounting

    DOE Patents [OSTI]

    Hayes, John R. (Indianapolis, IN)

    1983-01-01T23:59:59.000Z

    A regenerator assembly for a gas turbine engine has a hot side seal assembly formed in part by a cast metal engine block having a seal recess formed therein that is configured to supportingly receive ceramic support blocks including an inboard face thereon having a regenerator seal face bonded thereto. A pressurized leaf seal is interposed between the ceramic support block and the cast metal engine block to bias the seal wear face into sealing engagement with a hot side surface of a rotary regenerator matrix.

  20. Radioactive materials shipping cask anticontamination enclosure

    DOE Patents [OSTI]

    Belmonte, Mark S. (Irwin, PA); Davis, James H. (Pittsburgh, PA); Williams, David A. (Pittsburgh, PA)

    1982-01-01T23:59:59.000Z

    An anticontamination device for use in storing shipping casks for radioactive materials comprising (1) a seal plate assembly; (2) a double-layer plastic bag; and (3) a water management system or means for water management.

  1. Labyrinth Seal Leakage Equation

    E-Print Network [OSTI]

    Suryanarayanan, Saikishan

    2010-07-14T23:59:59.000Z

    A seal is a component used in a turbomachine to reduce internal leakage of the working fluid and to increase the machine's efficiency. The stability of a turbomachine partially depends upon the rotodynamic coefficients of the seal. The integral...

  2. Labyrinth Seal Leakage Analysis

    E-Print Network [OSTI]

    Chaudhary, Gaurav

    2012-10-19T23:59:59.000Z

    Seals are basic mechanical devices commonly used in machinery to avoid undesired flow losses of working fluids. To understand the working of these seals specifically those placed between relatively moving parts is still one of the major engineering...

  3. Security seal. [Patent application

    DOE Patents [OSTI]

    Gobeli, G.W.

    1981-11-17T23:59:59.000Z

    Security for a package or verifying seal in plastic material is provided by a print seal with unique thermally produced imprints in the plastic. If tampering is attempted, the material is irreparably damaged and thus detectable. The pattern of the imprints, similar to fingerprints are recorded as a positive identification for the seal, and corresponding recordings made to allow comparison. The integrity of the seal is proved by the comparison of imprint identification records made by laser beam projection.

  4. Titanium sealing glasses and seals formed therefrom

    DOE Patents [OSTI]

    Brow, Richard K. (Albuquerque, NM); McCollister, Howard L. (Albuquerque, NM); Phifer, Carol C. (Albuquerque, NM); Day, Delbert E. (Rolla, MO)

    1997-01-01T23:59:59.000Z

    Alkaline-earth lanthanoborate sealing-glass compositions containing CaO, La.sub.2 O.sub.3, B.sub.2 O.sub.3, TiO.sub.2 and Al.sub.2 O.sub.3 in various combinations of mole-% are provided. These sealing-glass compositions are useful for forming hermetic glass-to-metal seals with titanium and titanium alloys that have a high aqueous durability for component or device applications requiring exposure to moisture, water or body fluids. Particular applications of the titanium sealing-glass compositions include forming glass-to-metal seals for lithium batteries and implanted biomedical devices (e.g. batteries, pacemakers, defibrillators, pumps).

  5. Titanium sealing glasses and seals formed therefrom

    DOE Patents [OSTI]

    Brow, R.K.; McCollister, H.L.; Phifer, C.C.; Day, D.E.

    1997-12-02T23:59:59.000Z

    Alkaline-earth lanthanoborate sealing-glass compositions containing CaO, La{sub 2}O{sub 3}, B{sub 2}O{sub 3}, TiO{sub 2} and Al{sub 2}O{sub 3} in various combinations of mole-% are provided. These sealing-glass compositions are useful for forming hermetic glass-to-metal seals with titanium and titanium alloys that have a high aqueous durability for component or device applications requiring exposure to moisture, water or body fluids. Particular applications of the titanium sealing-glass compositions include forming glass-to-metal seals for lithium batteries and implanted biomedical devices (e.g. batteries, pacemakers, defibrillators, pumps). 2 figs.

  6. Skew resisting hydrodynamic seal

    DOE Patents [OSTI]

    Conroy, William T. (Pearland, TX); Dietle, Lannie L. (Sugar Land, TX); Gobeli, Jeffrey D. (Houston, TX); Kalsi, Manmohan S. (Houston, TX)

    2001-01-01T23:59:59.000Z

    A novel hydrodynamically lubricated compression type rotary seal that is suitable for lubricant retention and environmental exclusion. Particularly, the seal geometry ensures constraint of a hydrodynamic seal in a manner preventing skew-induced wear and provides adequate room within the seal gland to accommodate thermal expansion. The seal accommodates large as-manufactured variations in the coefficient of thermal expansion of the sealing material, provides a relatively stiff integral spring effect to minimize pressure-induced shuttling of the seal within the gland, and also maintains interfacial contact pressure within the dynamic sealing interface in an optimum range for efficient hydrodynamic lubrication and environment exclusion. The seal geometry also provides for complete support about the circumference of the seal to receive environmental pressure, as compared the interrupted character of seal support set forth in U.S. Pat. Nos. 5,873,576 and 6,036,192 and provides a hydrodynamic seal which is suitable for use with non-Newtonian lubricants.

  7. Burnup estimation of fuel sourcing radioactive material based on monitored Cs and Pu isotopic activity ratios in Fukushima N. P. S. accident

    SciTech Connect (OSTI)

    Yamamoto, T.; Suzuki, M.; Ando, Y. [Japan Nuclear Energy Safety Organization, Toranomon Towers Office, 14F, 4-1-28, Toranomon, Minato-ku, Tokyo 105-0001 (Japan)

    2012-07-01T23:59:59.000Z

    After the severe core damage of Fukushima Dai-Ichi Nuclear Power Station, radioactive material leaked from the reactor buildings. As part of monitoring of radioactivity in the site, measurements of radioactivity in soils at three fixed points have been performed for {sup 134}Cs and {sup 137}Cs with gamma-ray spectrometry and for Pu, Pu, and {sup 240}Pu with {alpha}-ray spectrometry. Correlations of radioactivity ratios of {sup 134}Cs to {sup 137}Cs, and {sup 238}Pu to the sum of {sup 239}Pu and {sup 240}Pu with fuel burnup were studied by using theoretical burnup calculations and measurements on isotopic inventories, and compared with the Cs and Pu radioactivity rations in the soils. The comparison indicated that the burnup of the fuel sourcing the radioactivity was from 18 to 38 GWd/t, which corresponded to that of the fuel in the highest power and, therefore, the highest decay heat in operating high-burnup fueled BWR cores. (authors)

  8. Low Cost, Durable Seal

    SciTech Connect (OSTI)

    Roberts, George; Parsons, Jason; Friedman, Jake

    2010-12-17T23:59:59.000Z

    Seal durability is critical to achieving the 2010 DOE operational life goals for both stationary and transportation PEM fuel cell stacks. The seal material must be chemically and mechanically stable in an environment consisting of aggressive operating temperatures, humidified gases, and acidic membranes. The seal must also be producible at low cost. Currentlyused seal materials do not meet all these requirements. This project developed and demonstrated a high consistency hydrocarbon rubber seal material that was able to meet the DOE technical and cost targets. Significant emphasis was placed on characterization of the material and full scale molding demonstrations.

  9. A Comparison of Simple Algorithms for Gamma-ray Spectrometers in Radioactive Source Search Applications

    SciTech Connect (OSTI)

    Jarman, Kenneth D.; Runkle, Robert C.; Anderson, Kevin K.; Pfund, David M.

    2008-03-01T23:59:59.000Z

    Large variation in time-dependent ambient gamma-ray radiation challenges the search for radiation sources. A common strategy to reduce the effects of background variation is to raise detection thresholds, but at the price of reduced detection sensitivity. We present simple algorithms that both reduce background variation and maintain trip-wire detection sensitivity with gamma-ray spectrometry. The best-performing algorithms focus on the spectral shape over several energy bins using Spectral Comparison Ratios and dynamically predict background with the Kalman Filter.

  10. Storage containers for radioactive material

    DOE Patents [OSTI]

    Groh, E.F.; Cassidy, D.A.; Dates, L.R.

    1980-07-31T23:59:59.000Z

    A radioactive material storage system is claimed for use in the laboratory having a flat base plate with a groove in one surface thereof and a hollow pedestal extending perpendicularly away from the other surface thereof, a sealing gasket in the groove, a cover having a filter therein and an outwardly extending flange which fits over the plate, the groove and the gasket, and a clamp for maintaining the cover and the plate sealed together. The plate and the cover and the clamp cooperate to provide a storage area for radioactive material readily accessible for use or inventory. Wall mounts are provided to prevent accidental formation of critical masses during storage.

  11. Rotary kiln seal

    DOE Patents [OSTI]

    Drexler, Robert L. (Idaho Falls, ID)

    1992-01-01T23:59:59.000Z

    A rotary seal used to prevent the escape of contaminates from a rotating kiln incinerator. The rotating seal combines a rotating disc plate which is attached to the rotating kiln shell and four sets of non-rotating carbon seal bars housed in a primary and secondary housing and which rub on the sides of the disc. A seal air system is used to create a positive pressure in a chamber between the primary and secondary seals to create a positive air flow into the contaminated gas chamber. The seal air system also employs an air inlet located between the secondary and tertiary seals to further insure that no contaminates pass the seal and enter the external environment and to provide makeup air for the air which flows into the contaminated gas chamber. The pressure exerted by the seal bars on the rotating disc is controlled by means of a preload spring. The seal is capable of operating in a thermally changing environment where the both radial expansion and axial movement of the rotating kiln do not result in the failure of the seal.

  12. Packer sealing assembly

    SciTech Connect (OSTI)

    Buckner, R.K.

    1984-06-05T23:59:59.000Z

    A sealing assembly for a packer includes a generally cylindrical elastomeric sealing element telescoped onto a mandrel between upper and lower expander heads. A sealing ring is disposed between each expander head and the sealing element at each end thereof for expanding radially outward toward engagement with the inside wall of a casing to keep the element from extruding between the expander heads and casing when setting the packer. A substantially non-expandable retaining ring surrounds the mandrel adjacent each of said sealing rings and an annular receptacle surrounds the mandrel and is located between each of the expander heads and the opposite ends of the sealing element. The receptacle has inner and outer malleable annular walls which are normally spaced radially outward from the mandrel and an end wall is integrally connected between these inner and outer walls so as to define an annular trough opening toward the sealing element. Extending into the trough is an annular protrusion which is integrally formed with the sealing element in each of the ends thereof so as to deform the inner walls radially inward into sealing engagement with the mandrel against elastomeric extrusion therebetween and so as to deform the outer walls radially outward into sealing engagement with the retaining ring against elastomeric extrusion therebetween when setting the packer.

  13. Damped flexible seal

    DOE Patents [OSTI]

    DuBois, Neil J. (Cranston, RI); Amaral, Antonio M. (Barrington, RI)

    1992-10-27T23:59:59.000Z

    A damped flexible seal assembly for a torpedo isolates the tailcone thereof rom vibrational energy present in the drive shaft assembly. A pair of outside flanges, each of which include an inwardly facing groove and an O-ring constrained therein, provide a watertight seal against the outer non-rotating surface of the drive shaft assembly. An inside flange includes an outwardly-facing groove and an O-ring constrained therein, and provides a watertight seal against the inner surface of the tail cone. Two cast-in-place elastomeric seals provide a watertight seal between the flanges and further provide a damping barrier between the outside flanges and the inside flanges for damping vibrational energy present in the drive shaft assembly before the energy can reach the tailcone through the seal assembly.

  14. Liquid zone seal

    DOE Patents [OSTI]

    Klebanoff, Leonard E. (Dublin, CA)

    2001-01-01T23:59:59.000Z

    A seal assembly that provides a means for establishing multiple pressure zones within a system. The seal assembly combines a plate extending from the inner wall of a housing or inner enclosure that intersects with and is immersed in the fluid contained in a well formed in a tray contained within the enclosure. The fluid is a low vapor pressure oil, chemically inert and oxidation resistant. The use of a fluid as the sealing component provides a seal that is self-healing and mechanically robust not subject to normal mechanical wear, breakage, and formation of cracks or pinholes and decouples external mechanical vibrations from internal structural members.

  15. Sealing the Deal

    SciTech Connect (OSTI)

    Jones, Anthony M.

    2014-06-01T23:59:59.000Z

    Pacific Northwest National Laboratory leveraged simulation to develop an optimized method for inspecting sealed containers in verifying nuclear arms control treaties.

  16. Geopolymer Sealing Materials

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

    Geopolymer Sealing Materials PI : Dr. Tomas Butcher Presenter: Dr. Toshi Sugama Brookhaven National Laboratory May 18, 2010 This presentation does not contain any proprietary...

  17. A Computational Study on the Leakage of Supercritical Carbon Dioxide through Labyrinth Seals

    E-Print Network [OSTI]

    Pidaparti, Sandeep R

    2013-11-26T23:59:59.000Z

    of turbomachinery equipment it is important to reduce internal leakage through seals. A computational study was performed to understand the leakage through seals subject to large pressure differential using Open source CFD software OpenFOAM. FIT (Fluid Property...

  18. Better Bearing Housing Seals Prevent Costly Machinery Failures

    E-Print Network [OSTI]

    Bloch, H. P.

    similar in principle to attraction-type Figure 8: Repulsion-type Magnetic Seal Cartridge in Shipping position (L) and operating posiLion (K). Source: Inpro Companies. Inc., Rock Island, IL magnetic face seals, the design shown in Figure 8 utilizes..., Inc., Rock Island, IL Magnetic seals are not a new invention. For years they have served with distinction in aerospace applications. More recently, they have been quite successfully introduced to centrifugal pumps by process plant maintenance...

  19. Rotordynamic and leakage characteristics of a 4-stage brush seal

    E-Print Network [OSTI]

    Conner, Kelly James

    1990-01-01T23:59:59.000Z

    is the source of destabilizing forces in labyrinth annular seals and arises due to fluid rotation within the seaL This destabilizing effect is aggravated when the fluid enters the seal with a "swirl" or tangential velocity component in the direction...-USAF funded research program for annular gas seal research. J. B. Dressman of the University of Louisville completed the original design of the test rig in 1982. Several modifications to both the test apparatus and the supporting facilities have been made...

  20. A gas-jet transport and catcher technique for on-line production of radioactive ion beams using an electron cyclotron resonance ion-source

    SciTech Connect (OSTI)

    Naik, V.; Chakrabarti, A.; Bhattacharjee, M.; Karmakar, P.; Bandyopadhyay, A.; Dechoudhury, S.; Mondal, M.; Pandey, H. K.; Lavanyakumar, D.; Mandi, T. K.; Dutta, D. P.; Kundu Roy, T.; Bhowmick, D.; Sanyal, D.; Srivastava, S. C. L.; Ray, A.; Ali, Md. S. [Variable Energy Cyclotron Centre (VECC), Sector-1, Block-AF, Bidhan Nagar, Kolkata 700064 (India); Bhattacharjee, S. [UGC-DAE CSR, Kolkata Centre, III/LB-8, Bidhan Nagar, Kolkata 700098 (India)

    2013-03-15T23:59:59.000Z

    Radioactive ion beams (RIB) have been produced on-line, using a gas-jet recoil transport coupled Electron Cyclotron Resonance (ECR) ion-source at the VECC-RIB facility. Radioactive atoms/molecules carried through the gas-jet were stopped in a catcher placed inside the ECR plasma chamber. A skimmer has been used to remove bulk of the carrier gas at the ECR entrance. The diffusion of atoms/molecules through the catcher has been verified off-line using stable isotopes and on-line through transmission of radioactive reaction products. Beams of {sup 14}O (71 s), {sup 42}K (12.4 h), {sup 43}K (22.2 h), and {sup 41}Ar (1.8 h) have been produced by bombarding nitrogen and argon gas targets with proton and alpha particle beams from the K130 cyclotron at VECC. Typical measured intensity of RIB at the separator focal plane is found to be a few times 10{sup 3} particles per second (pps). About 3.2 Multiplication-Sign 10{sup 3} pps of 1.4 MeV {sup 14}O RIB has been measured after acceleration through a radiofrequency quadrupole linac. The details of the gas-jet coupled ECR ion-source and RIB production experiments are presented along with the plans for the future.

  1. RSSC RADIOACTIVE WASTE DISPOSAL 08/2011 7-1 RADIOACTIVE WASTE DISPOSAL

    E-Print Network [OSTI]

    Slatton, Clint

    . Properly labeled containers with lids, covers, or seals. B. Labels, tape, plastic bags, plastic jugs or suitable liquid containers, corrugated cardboard boxes. C. Note: Liquid Waste containers are provided radioactive waste containing different radionuclides. C. Minimize radioactive waste by preventing unnecessary

  2. Multilayer compressive seal for sealing in high temperature devices

    DOE Patents [OSTI]

    Chou, Yeong-Shyung (Richland, WA); Stevenson, Jeffry W. (Richland, WA)

    2007-08-21T23:59:59.000Z

    A mica based compressive seal has been developed exhibiting superior thermal cycle stability when compared to other compressive seals known in the art. The seal is composed of compliant glass or metal interlayers and a sealing (gasket) member layer composed of mica that is infiltrated with a glass forming material, which effectively reduces leaks within the seal. The compressive seal shows approximately a 100-fold reduction in leak rates compared with previously developed hybrid seals after from 10 to about 40 thermal cycles under a compressive stress of from 50 psi to 100 psi at temperatures in the range from 600.degree. C. to about 850.degree. C.

  3. Tamper indicating seal

    DOE Patents [OSTI]

    Romero, Juan A. (Albuquerque, NM); Walker, Charles A. (Albuquerque, NM); Blair, Dianna S. (Albuquerque, NM); Bodmer, Connie C. (Albuquerque, NM)

    2012-05-29T23:59:59.000Z

    Seals have a flexible wire that can be looped through a hasp-like device. The seals include a body having a recess, a plug insertable into the recess and a snap ring for fastening the plug to the body. The plug and/or body can have access holes for inserting the wire into the recess. "Teeth" on the outer diameter and through-holes through the thickness of the snap ring allow for passing the ends of the flexible wire from the recess through the snap ring. The ends of the wire can be folded back over the snap ring and into engagement with the teeth. Assembly of the seal causes the ends of the wire to be securely fastened between the teeth of the snap ring and the sidewall of the recess. Seals can include a plug and/or body made of a frangible material such as glass, ceramic, glass-ceramic or brittle polymer.

  4. Labyrinth Seal Leakage Analysis

    E-Print Network [OSTI]

    Inam, Orcun

    2012-10-19T23:59:59.000Z

    . The effect of seal geometry is studied by varying clearance, pitch, tooth height, tooth width and upstream side angle. It was found that, amongst other geometrical parameters, tooth clearance and pitch has a strong influence on carryover coefficient. Smaller...

  5. Flexible cloth seal assembly

    DOE Patents [OSTI]

    Bagepalli, B.S.; Taura, J.C.; Aksit, M.F.; Demiroglu, M.; Predmore, D.R.

    1999-06-29T23:59:59.000Z

    A seal assembly is described having a flexible cloth seal which includes a shim assemblage surrounded by a cloth assemblage. A first tubular end portion, such as a gas turbine combustor, includes a longitudinal axis and has smooth and spaced-apart first and second surface portions defining a notch there between which is wider at its top than at its bottom and which extends outward from the axis. The second surface portion is outside curved, and a first edge of the cloth seal is positioned in the bottom of the notch. A second tubular end portion, such as a first stage nozzle, is located near, spaced apart from, and coaxially aligned with, the first tubular end portion. The second tubular end portion has a smooth third surface portion which surrounds at least a portion of the first tubular end portion and which is contacted by the cloth seal. 7 figs.

  6. Geopolymer Sealing Materials

    Broader source: Energy.gov [DOE]

    DOE Geothermal Peer Review 2010 - Presentation. Project objectives: Develop and characterize field-applicable geopolymer temporary sealing materials in the laboratory and to transfer this developed material technology to geothermal drilling service companies as collaborators for field validation tests.

  7. Gas turbine sealing apparatus

    DOE Patents [OSTI]

    Marra, John Joseph; Wessell, Brian J.; Liang, George

    2013-03-05T23:59:59.000Z

    A sealing apparatus in a gas turbine. The sealing apparatus includes a seal housing apparatus coupled to a disc/rotor assembly so as to be rotatable therewith during operation of the gas turbine. The seal housing apparatus comprises a base member, a first leg portion, a second leg portion, and spanning structure. The base member extends generally axially between forward and aft rows of rotatable blades and is positioned adjacent to a row of stationary vanes. The first leg portion extends radially inwardly from the base member and is coupled to the disc/rotor assembly. The second leg portion is axially spaced from the first leg portion, extends radially inwardly from the base member, and is coupled to the disc/rotor assembly. The spanning structure extends between and is rigidly coupled to each of the base member, the first leg portion, and the second leg portion.

  8. Turbine seal assembly

    DOE Patents [OSTI]

    Little, David A.

    2013-04-16T23:59:59.000Z

    A seal assembly that limits gas leakage from a hot gas path to one or more disc cavities in a turbine engine. The seal assembly includes a seal apparatus that limits gas leakage from the hot gas path to a respective one of the disc cavities. The seal apparatus comprises a plurality of blade members rotatable with a blade structure. The blade members are associated with the blade structure and extend toward adjacent stationary components. Each blade member includes a leading edge and a trailing edge, the leading edge of each blade member being located circumferentially in front of the blade member's corresponding trailing edge in a direction of rotation of the turbine rotor. The blade members are arranged such that a space having a component in a circumferential direction is defined between adjacent circumferentially spaced blade members.

  9. Ingestion resistant seal assembly

    DOE Patents [OSTI]

    Little, David A. (Chuluota, FL)

    2011-12-13T23:59:59.000Z

    A seal assembly limits gas leakage from a hot gas path to one or more disc cavities in a gas turbine engine. The seal assembly includes a seal apparatus associated with a blade structure including a row of airfoils. The seal apparatus includes an annular inner shroud associated with adjacent stationary components, a wing member, and a first wing flange. The wing member extends axially from the blade structure toward the annular inner shroud. The first wing flange extends radially outwardly from the wing member toward the annular inner shroud. A plurality of regions including one or more recirculation zones are defined between the blade structure and the annular inner shroud that recirculate working gas therein back toward the hot gas path.

  10. Titanium hermetic seals

    DOE Patents [OSTI]

    Brow, Richard K. (Albuquerque, NM); Watkins, Randall D. (Tijeras, NM)

    1995-01-01T23:59:59.000Z

    Titanium is prenitrided by being heated in a nitrogen environment under conditions which give rise to the formation of a titanium-nitride surface layer on the titanium. Titanium thus prenitrided may be used in electrical components which are hermetically sealed using silicate glasses and standard glass sealing techniques. According to the method of the invention, alkali volatilization and formation of deleterious interfacial silicide are inhibited.

  11. Titanium hermetic seals

    DOE Patents [OSTI]

    Brow, Richard K.; Watkins, Randall D.

    1995-07-04T23:59:59.000Z

    Titanium is prenitrided by being heated in a nitrogen environment under conditions which give rise to the formation of a titanium-nitride surface layer on the titanium. Titanium thus prenitrided may be used in electrical components which are hermetically sealed using silicate glasses and standard glass sealing techniques. According to the method of the invention, alkali volatilization and formation of deleterious interfacial silicide are inhibited.

  12. Bagless transfer process and apparatus for radioactive waste confinement

    DOE Patents [OSTI]

    Maxwell, D.N.; Hones, R.H.; Rogers, M.L.

    1998-04-14T23:59:59.000Z

    A process and apparatus are provided for removing radioactive material from a glovebox, placing the material in a stainless steel storage vessel in communication with the glovebox, and sealing the vessel with a welded plug. The vessel is then severed along the weld, a lower half of the plug forming a closure for the vessel. The remaining welded plug half provides a seal for the remnant portion of the vessel and thereby maintains the sealed integrity of the glovebox. 7 figs.

  13. Bagless transfer process and apparatus for radioactive waste confinement

    DOE Patents [OSTI]

    Maxwell, David N. (Aiken, SC); Hones, Robert H. (Evans, GA); Rogers, M. Lane (Aiken, SC)

    1998-01-01T23:59:59.000Z

    A process and apparatus is provided for removing radioactive material from a glovebox, placing the material in a stainless steel storage vessel in communication with the glovebox, and sealing the vessel with a welded plug. The vessel is then severed along the weld, a lower half of the plug forming a closure for the vessel. The remaining welded plug half provides a seal for the remnant portion of the vessel and thereby maintains the sealed integrity of the glovebox.

  14. Performance testing of elastomeric seal materials under low and high temperature conditions: Final report

    SciTech Connect (OSTI)

    BRONOWSKI,DAVID R.

    2000-06-01T23:59:59.000Z

    The US Department of Energy Offices of Defense Programs and Civilian Radioactive Waste Management jointly sponsored a program to evaluate elastomeric O-ring seal materials for radioactive material shipping containers. The report presents the results of low- and high-temperature tests conducted on 27 common elastomeric compounds.

  15. Experimental demonstration of differing impacts of pulsed and continuous operation of a deuterium-tritium neutron source on induced radioactivity in the context of ITER

    SciTech Connect (OSTI)

    Kumar, A.; Youssef, M.Z.; Abdou, M.A. [Univ. of California, Los Angeles, CA (United States); Ikeda, Yujiro; Uno, Yoshitomo; Maekawa, Hiroshi [Japan Atomic Energy Research Inst., Ibaraki (Japan)

    1996-12-31T23:59:59.000Z

    The work reported herein was conducted in response to an ITER Task to demonstrate experimentally that pulsed and continous operations of a D-T neutron source lead, in general, to differing impacts on inventory of induced radioactivity, on one hand, and to verify calculational methods, on the other. In a series of experiments conducted for the purpose, half lives of observed radioisotopes varied from 1 minute ({sup 25}Na) to 271 days ({sup 57}Co). Relatively short pulse lengths, 1 minute to 3 minute duration, were chosen. A pneumatic transport system was employed to transport foils of niobium, iron, aluminum, vanadium, nickel, and magnesium for irradiation close to the D-T neutron source. Three duty factors and two kinds of power levels were used for various neutron pulse trains. The experimental data was processed to obtain ratio of inventories in pulsed to continuous operation scenarios for each of the observed radioisotope. We observe a large reduction in radioactive inventories for values of t{sub 1/2}/p (half life/pulse duration) lying in the range of 1 to 10. Interestingly, random power pulse trains show even larger reduction in radioactive inventory: the ratio of inventories drops to approx.0.14 for t{sub 1/2}/p = 3.15 ({sup 27}Mg) for a duty factor of 20% and a train of 10 pulses, whereas it would have hit a minimum of 0.33 for t{sub 1/2}/p = 3.53 for constant power level. 14 refs., 10 figs., 1 tab.

  16. Sealing coupling. [LMFBR

    DOE Patents [OSTI]

    Pardini, J.A.; Brubaker, R.C.; Rusnak, J.J.

    1982-09-20T23:59:59.000Z

    Disclosed is a remotely operable releasable sealing coupling which provides fluid-tight joinder of upper and a lower conduit sections. Each conduit section has a concave conical sealing surface adjacent its end portion. A tubular sleeve having convex spherical ends is inserted between the conduit ends to form line contact with the concave conical end portions. An inwardly projecting lip located at one end of the sleeve cooperates with a retaining collar formed on the upper pipe end to provide swivel capture for the sleeve. The upper conduit section also includes a tapered lower end portion which engages the inside surface of the sleeve to limit misalignment of the connected conduit sections.

  17. Notes 11. High pressure floating ring seals

    E-Print Network [OSTI]

    San Andres, Luis

    2009-01-01T23:59:59.000Z

    Floating ring seals for compressors: leakage and force coefficients, seal lock up and effect on rotor stability, recommendations to reduce seal cross-coupled effects. Long oil seals as pressure barriers in industrial mixers: leakage and force...

  18. Static seal for turbine engine

    DOE Patents [OSTI]

    Salazar, Santiago; Gisch, Andrew

    2014-04-01T23:59:59.000Z

    A seal structure for a gas turbine engine, the seal structure including first and second components located adjacent to each other and forming a barrier between high and low pressure zones. A seal cavity is defined in the first and second components, the seal cavity extending to either side of an elongated gap extending generally in a first direction between the first and second components. A seal member is positioned within the seal cavity and spans across the elongated gap. The seal member includes first and second side edges extending into each of the components in a second direction transverse to the first direction, and opposing longitudinal edges extending between the side edges generally parallel to the first direction. The side edges include a groove formed therein for effecting a reduction of gas flow around the seal member at the side edges.

  19. Department Seal and Flag

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

    1992-05-18T23:59:59.000Z

    This directive sets forth the policy governing the use of the official seal and distinguishing flag of the Department of Energy (DOE) as described in Title 10, Code of Federal Regulations (CFR), Part 1002. Cancels DOE O 10002.A dated 1-8-90.

  20. Sealing an ultracapacitor

    DOE Patents [OSTI]

    Irwin, Patricia Chapman (Altamont, NY); Feist, Thomas Paul (Clifton Park, NY)

    2001-10-16T23:59:59.000Z

    An ultracapacitor comprises at least one cell comprising two solid, nonporous current collectors, two porous electrodes separating the current collectors, a porous separator between the electrodes and an electrolyte occupying pores in the electrodes and separator. The cell is sealed with a reclosable hermetic closure.

  1. Bellows sealed plug valve

    DOE Patents [OSTI]

    Dukas, Jr., Stephen J. (Idaho Falls, ID)

    1990-01-01T23:59:59.000Z

    A bellows sealed plug valve includes a valve body having an inlet passage and an outlet passage, a valve chamber between the inlet and outlet passages. A valve plug has substantially the same shape as the valve chamber and is rotatably disposed therein. A shaft is movable linearly in response to a signal from a valve actuator. A bellows is sealingly disposed between the valve chamber and the valve actuator and means are located between the bellows and the valve plug for converting linear movement of the shaft connected to the valve actuator to rotational movement of the plug. Various means are disclosed including helical thread mechanism, clevis mechanism and rack and pinion mechanism, all for converting linear motion to rotational motion.

  2. Gas turbine sealing apparatus

    DOE Patents [OSTI]

    Wiebe, David J; Wessell, Brian J; Ebert, Todd; Beeck, Alexander; Liang, George; Marussich, Walter H

    2013-02-19T23:59:59.000Z

    A gas turbine includes forward and aft rows of rotatable blades, a row of stationary vanes between the forward and aft rows of rotatable blades, an annular intermediate disc, and a seal housing apparatus. The forward and aft rows of rotatable blades are coupled to respective first and second portions of a disc/rotor assembly. The annular intermediate disc is coupled to the disc/rotor assembly so as to be rotatable with the disc/rotor assembly during operation of the gas turbine. The annular intermediate disc includes a forward side coupled to the first portion of the disc/rotor assembly and an aft side coupled to the second portion of the disc/rotor assembly. The seal housing apparatus is coupled to the annular intermediate disc so as to be rotatable with the annular intermediate disc and the disc/rotor assembly during operation of the gas turbine.

  3. Canister, Sealing Method And Composition For Sealing A Borehole

    DOE Patents [OSTI]

    Brown, Donald W. (Los Alamos, NM); Wagh, Arun S. (Orland Park, IL)

    2005-06-28T23:59:59.000Z

    Method and composition for sealing a borehole. A chemically bonded phosphate ceramic sealant for sealing, stabilizing, or plugging boreholes is prepared by combining an oxide or hydroxide and a phosphate with water to form slurry. The slurry is introduced into the borehole where the seal, stabilization or plug is desired, and then allowed to set up to form the high strength, minimally porous sealant, which binds strongly to itself and to underground formations, steel and ceramics.

  4. Process Knowledge Characterization of Radioactive Waste at the Classified Waste Landfill Remediation Project Sandia National Laboratories, Albuquerque, New Mexico

    SciTech Connect (OSTI)

    DOTSON,PATRICK WELLS; GALLOWAY,ROBERT B.; JOHNSON JR,CARL EDWARD

    1999-11-03T23:59:59.000Z

    This paper discusses the development and application of process knowledge (PK) to the characterization of radioactive wastes generated during the excavation of buried materials at the Sandia National Laboratories/New Mexico (SNL/NM) Classified Waste Landfill (CWLF). The CWLF, located in SNL/NM Technical Area II, is a 1.5-acre site that received nuclear weapon components and related materials from about 1950 through 1987. These materials were used in the development and testing of nuclear weapon designs. The CWLF is being remediated by the SNL/NM Environmental Restoration (ER) Project pursuant to regulations of the New Mexico Environment Department. A goal of the CWLF project is to maximize the amount of excavated materials that can be demilitarized and recycled. However, some of these materials are radioactively contaminated and, if they cannot be decontaminated, are destined to require disposal as radioactive waste. Five major radioactive waste streams have been designated on the CWLF project, including: unclassified soft radioactive waste--consists of soft, compatible trash such as paper, plastic, and plywood; unclassified solid radioactive waste--includes scrap metal, other unclassified hardware items, and soil; unclassified mixed waste--contains the same materials as unclassified soft or solid radioactive waste, but also contains one or more Resource Conservation and Recovery Act (RCRA) constituents; classified radioactive waste--consists of classified artifacts, usually weapons components, that contain only radioactive contaminants; and classified mixed waste--comprises radioactive classified material that also contains RCRA constituents. These waste streams contain a variety of radionuclides that exist both as surface contamination and as sealed sources. To characterize these wastes, the CWLF project's waste management team is relying on data obtained from direct measurement of radionuclide activity content to the maximum extent possible and, in cases where direct measurement is not technically feasible, from accumulated PK of the excavated materials.

  5. Metal to ceramic sealed joint

    DOE Patents [OSTI]

    Lasecki, John V. (Livonia, MI); Novak, Robert F. (Farmington Hills, MI); McBride, James R. (Ypsilanti, MI)

    1991-01-01T23:59:59.000Z

    A metal to ceramic sealed joint which can withstand wide variations in temperature and maintain a good seal is provided for use in a device adapted to withstand thermal cycling from about 20 to about 1000 degrees C. The sealed joint includes a metal member, a ceramic member having an end portion, and an active metal braze forming a joint to seal the metal member to the ceramic member. The joint is positioned remote from the end portion of the ceramic member to avoid stresses at the ends or edges of the ceramic member. The sealed joint is particularly suited for use to form sealed metal to ceramic joints in a thermoelectric generator such as a sodium heat engine where a solid ceramic electrolyte is joined to metal parts in the system.

  6. Metal to ceramic sealed joint

    DOE Patents [OSTI]

    Lasecki, J.V.; Novak, R.F.; McBride, J.R.

    1991-08-27T23:59:59.000Z

    A metal to ceramic sealed joint which can withstand wide variations in temperature and maintain a good seal is provided for use in a device adapted to withstand thermal cycling from about 20 to about 1000 degrees C. The sealed joint includes a metal member, a ceramic member having an end portion, and an active metal braze forming a joint to seal the metal member to the ceramic member. The joint is positioned remote from the end portion of the ceramic member to avoid stresses at the ends or edges of the ceramic member. The sealed joint is particularly suited for use to form sealed metal to ceramic joints in a thermoelectric generator such as a sodium heat engine where a solid ceramic electrolyte is joined to metal parts in the system. 11 figures.

  7. Experience of Consolidation Of Disused Sources In Developing Countries, An African Perspective

    SciTech Connect (OSTI)

    Kifanga, L.D.; Mompome, W.K.; Shao, D. [Tanzania Atomic Energy Commission, Arusha (Tanzania, United Republic of)

    2008-07-01T23:59:59.000Z

    Application of sealed sources in agriculture, medicine and industry was used in many African countries without having any arrangements in place for managing the sources when their useful life was over. In Tanzania a substantial use of such sources was utilized. In the early days source management was not an area that was given the required attention hence a legacy associated with sealed sources became evident in many African countries and Tanzania was one of them. In the 90's Tanzania Atomic Energy Commission (TAEC), realized the scope of the waste problem and began to participate in an International Atomic Energy Agency Regional (IAEA) project on waste management. Tanzania in cooperation with IAEA initiated activities under the IAEA Technical Cooperation and the Regional projects 'Strengthening Waste Management Infrastructure, RAF/4/015'; and 'Sustaining the Waste Management Infrastructure RAF/3/005' which played a significant role. The first outcome of the project was realized in 1999, as the first 'Temporary Radioactive Waste Storage Facility' began to operate. This particular Storage facility gave the first impact as well as the need to develop this particular infrastructure further. As the project carried on, more and more orphan sources were recovered, collected and safely stored at the facility. As the use of nuclear technology was expanding and the identification of the extent of sealed sources in the countries became more defined, the need to develop a 'Central Radioactive Waste Management Facility' (CRWMF) was becoming more desired. The central radioactive waste storage facility was constructed and commissioned in 2005. The facility was more advanced and could be used for much longer periods of time, as one of the most advanced storage facility in the Region. At present a large number of disused sources from various industries as well as from different activities are being stored at the facility. Tanzanian authorities are also planning to initiate a nationwide mission to recover and properly store as well as dispose of abandoned sources. Cooperation among the AFRA Member states has been very rewarding in terms of experience and its importance. Skills that have been gained during the past years of existence of the AFRA project will be a vital contribution for years to come. This paper discusses the experiences of United Republic of Tanzania on management of orphan radioactive sources. The need to develop its own radioactive waste management infrastructure was required due to the fact, that many disused radioactive sources have been found abandoned and needed to be properly disposed of. The paper will also discuss some of these experiences. (authors)

  8. Rim seal for turbine wheel

    DOE Patents [OSTI]

    Glezer, Boris (Del Mar, CA); Boyd, Gary L. (Alpine, CA); Norton, Paul F. (San Diego, CA)

    1996-01-01T23:59:59.000Z

    A turbine wheel assembly includes a disk having a plurality of blades therearound. A ceramic ring is mounted to the housing of the turbine wheel assembly. A labyrinth rim seal mounted on the disk cooperates with the ceramic ring to seal the hot gases acting on the blades from the disk. The ceramic ring permits a tighter clearance between the labyrinth rim seal and the ceramic ring.

  9. Pressure sensor for sealed containers

    DOE Patents [OSTI]

    Hodges, Franklin R. (Loudon, TN)

    2001-01-01T23:59:59.000Z

    A magnetic pressure sensor for sensing a pressure change inside a sealed container. The sensor includes a sealed deformable vessel having a first end attachable to an interior surface of the sealed container, and a second end. A magnet mounted to the vessel second end defining a distance away from the container surface provides an externally detectable magnetic field. A pressure change inside the sealed container causes deformation of the vessel changing the distance of the magnet away from the container surface, and thus the detectable intensity of the magnetic field.

  10. Storage depot for radioactive material

    DOE Patents [OSTI]

    Szulinski, Milton J. (Richland, WA)

    1983-01-01T23:59:59.000Z

    Vertical drilling of cylindrical holes in the soil, and the lining of such holes, provides storage vaults called caissons. A guarded depot is provided with a plurality of such caissons covered by shielded closures preventing radiation from penetrating through any linear gap to the atmosphere. The heat generated by the radioactive material is dissipated through the vertical liner of the well into the adjacent soil and thus to the ground surface so that most of the heat from the radioactive material is dissipated into the atmosphere in a manner involving no significant amount of biologically harmful radiation. The passive cooling of the radioactive material without reliance upon pumps, personnel, or other factor which might fail, constitutes one of the most advantageous features of this system. Moreover this system is resistant to damage from tornadoes or earthquakes. Hermetically sealed containers of radioactive material may be positioned in the caissons. Loading vehicles can travel throughout the depot to permit great flexibility of loading and unloading radioactive materials. Radioactive material can be shifted to a more closely spaced caisson after ageing sufficiently to generate much less heat. The quantity of material stored in a caisson is restricted by the average capacity for heat dissipation of the soil adjacent such caisson.

  11. AIR SEALING Seal air leaks and save energy!

    E-Print Network [OSTI]

    Oak Ridge National Laboratory

    AIR SEALING Seal air leaks and save energy! W H A T I S A I R L E A K A G E ? Ventilation is fresh air that enters a house in a controlled manner to exhaust excess moisture and reduce odors and stuffiness. Air leakage, or infiltration, is outside air that enters a house uncontrollably through cracks

  12. Operational Strategies for Low-Level Radioactive Waste Disposal Site in Egypt - 13513

    SciTech Connect (OSTI)

    Mohamed, Yasser T. [Hot Laboratories and Waste Management Center, Atomic Energy Authority, 3 Ahmed El-Zomor St., El-Zohour District, Naser City, 11787, Cairo (Egypt)] [Hot Laboratories and Waste Management Center, Atomic Energy Authority, 3 Ahmed El-Zomor St., El-Zohour District, Naser City, 11787, Cairo (Egypt)

    2013-07-01T23:59:59.000Z

    The ultimate aims of treatment and conditioning is to prepare waste for disposal by ensuring that the waste will meet the waste acceptance criteria of a disposal facility. Hence the purpose of low-level waste disposal is to isolate the waste from both people and the environment. The radioactive particles in low-level waste emit the same types of radiation that everyone receives from nature. Most low-level waste fades away to natural background levels of radioactivity in months or years. Virtually all of it diminishes to natural levels in less than 300 years. In Egypt, The Hot Laboratories and Waste Management Center has been established since 1983, as a waste management facility for LLW and ILW and the disposal site licensed for preoperational in 2005. The site accepts the low level waste generated on site and off site and unwanted radioactive sealed sources with half-life less than 30 years for disposal and all types of sources for interim storage prior to the final disposal. Operational requirements at the low-level (LLRW) disposal site are listed in the National Center for Nuclear Safety and Radiation Control NCNSRC guidelines. Additional procedures are listed in the Low-Level Radioactive Waste Disposal Facility Standards Manual. The following describes the current operations at the LLRW disposal site. (authors)

  13. Airfoil seal system for gas turbine engine

    DOE Patents [OSTI]

    Diakunchak, Ihor S.

    2013-06-25T23:59:59.000Z

    A turbine airfoil seal system of a turbine engine having a seal base with a plurality of seal strips extending therefrom for sealing gaps between rotational airfoils and adjacent stationary components. The seal strips may overlap each other and may be generally aligned with each other. The seal strips may flex during operation to further reduce the gap between the rotational airfoils and adjacent stationary components.

  14. Memorandum, Reporting of Radiological Sealed Sources Transactions |

    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 ChinaofSchaeferApril 1,(EAC) Richard2015 RD WorkshopEnergy OnMemorandum2006 |Department of

  15. Memorandum, Reporting of Radiological Sealed Sources Transactions |

    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 offOCHCO2:Introduction to EnergyDepartment ofMarginalPaul D.Department of Energy

  16. Refractory Glass Seals for SOFC

    SciTech Connect (OSTI)

    Chou, Y. S.; Stevenson, Jeffry W.

    2011-07-01T23:59:59.000Z

    One of the critical challenges facing planar solid oxide fuel cell (SOFC) technology is the need for reliable sealing technology. Seals must exhibit long-term stability and mechanical integrity in the high temperature SOFC environment during normal and transient operation. Several different approaches for sealing SOFC stacks are under development, including glass or glass-ceramic seals, metallic brazes, and compressive seals. Among glass seals, rigid glass-ceramics, self-healing glass, and composite glass approaches have been investigated under the SECA Core Technology Program. The U.S. Department of Energy's Pacific Northwest National Laboratory (PNNL) has developed the refractory glass approach in light of the fact that higher sealing temperatures (e.g., 930-1000 degrees C) may enhance the ultimate in-service bulk strength and electrical conductivity of contact materials, as well as the bonding strength between contact materials and adjacent SOFC components, such as interconnect coatings and electrodes. This report summarizes the thermal, chemical, mechanical, and electrical properties of the refractory sealing glass.

  17. Glassy composition for hermetic seals

    DOE Patents [OSTI]

    Wilder, Jr., James A. (Albuquerque, NM)

    1980-01-01T23:59:59.000Z

    The invention relates to a glassy composition adaptable for sealing to aluminum-based alloys to form a hermetically-sealed insulator body. The composition may either be employed as a glass or, after devitrifying heat treatment, as a glass-ceramic.

  18. Penetration seals for TFTR shielding

    SciTech Connect (OSTI)

    Hondorp, H.L.

    1980-12-01T23:59:59.000Z

    The penetrations of the shielding provided for TFTR are required to be sealed to avoid radiation streaming. This report provides a discussion of the properties required for these penetration seals. Several alternate designs are discussed and evaluated and designs recommended for specific applications.

  19. Greater-than-Class C low-level radioactive waste characterization. Appendix E-5: Impact of the 1993 NRC draft Branch Technical Position on concentration averaging of greater-than-Class C low-level radioactive waste

    SciTech Connect (OSTI)

    Tuite, P.; Tuite, K.; Harris, G. [Waste Management Group, Inc., Peekskill, NY (United States)

    1994-09-01T23:59:59.000Z

    This report evaluates the effects of concentration averaging practices on the disposal of greater-than-Class C low-level radioactive waste (GTCC LLW) generated by the nuclear utility industry and sealed sources. Using estimates of the number of waste components that individually exceed Class C limits, this report calculates the proportion that would be classified as GTCC LLW after applying concentration averaging; this proportion is called the concentration averaging factor. The report uses the guidance outlined in the 1993 Nuclear Regulatory Commission (NRC) draft Branch Technical Position on concentration averaging, as well as waste disposal experience at nuclear utilities, to calculate the concentration averaging factors for nuclear utility wastes. The report uses the 1993 NRC draft Branch Technical Position and the criteria from the Barnwell, South Carolina, LLW disposal site to calculate concentration averaging factors for sealed sources. The report addresses three waste groups: activated metals from light water reactors, process wastes from light-water reactors, and sealed sources. For each waste group, three concentration averaging cases are considered: high, base, and low. The base case, which is the most likely case to occur, assumes using the specific guidance given in the 1993 NRC draft Branch Technical Position on concentration averaging. To project future GTCC LLW generation, each waste category is assigned a concentration averaging factor for the high, base, and low cases.

  20. Radioactive Waste Management and Nuclear Facility Decommissioning Progress in Iraq - 13216

    SciTech Connect (OSTI)

    Al-Musawi, Fouad; Shamsaldin, Emad S.; Jasim, Hadi [Ministry of Science and Technology (MoST), Al-Jadraya, P.O. Box 0765, Baghdad (Iraq)] [Ministry of Science and Technology (MoST), Al-Jadraya, P.O. Box 0765, Baghdad (Iraq); Cochran, John R. [Sandia National Laboratories1, New Mexico, Albuquerque New Mexico 87185 (United States)] [Sandia National Laboratories1, New Mexico, Albuquerque New Mexico 87185 (United States)

    2013-07-01T23:59:59.000Z

    Management of Iraq's radioactive wastes and decommissioning of Iraq's former nuclear facilities are the responsibility of Iraq's Ministry of Science and Technology (MoST). The majority of Iraq's former nuclear facilities are in the Al-Tuwaitha Nuclear Research Center located a few kilometers from the edge of Baghdad. These facilities include bombed and partially destroyed research reactors, a fuel fabrication facility and radioisotope production facilities. Within these facilities are large numbers of silos, approximately 30 process or waste storage tanks and thousands of drums of uncharacterised radioactive waste. There are also former nuclear facilities/sites that are outside of Al-Tuwaitha and these include the former uranium processing and waste storage facility at Jesira, the dump site near Adaya, the former centrifuge facility at Rashdiya and the former enrichment plant at Tarmiya. In 2005, Iraq lacked the infrastructure needed to decommission its nuclear facilities and manage its radioactive wastes. The lack of infrastructure included: (1) the lack of an organization responsible for decommissioning and radioactive waste management, (2) the lack of a storage facility for radioactive wastes, (3) the lack of professionals with experience in decommissioning and modern waste management practices, (4) the lack of laws and regulations governing decommissioning or radioactive waste management, (5) ongoing security concerns, and (6) limited availability of electricity and internet. Since its creation eight years ago, the MoST has worked with the international community and developed an organizational structure, trained staff, and made great progress in managing radioactive wastes and decommissioning Iraq's former nuclear facilities. This progress has been made, despite the very difficult implementing conditions in Iraq. Within MoST, the Radioactive Waste Treatment and Management Directorate (RWTMD) is responsible for waste management and the Iraqi Decommissioning Directorate (IDD) is responsible for decommissioning activities. The IDD and the RWTMD work together on decommissioning projects. The IDD has developed plans and has completed decommissioning of the GeoPilot Facility in Baghdad and the Active Metallurgical Testing Laboratory (LAMA) in Al-Tuwaitha. Given this experience, the IDD has initiated work on more dangerous facilities. Plans are being developed to characterize, decontaminate and decommission the Tamuz II Research Reactor. The Tammuz Reactor was destroyed by an Israeli air-strike in 1981 and the Tammuz II Reactor was destroyed during the First Gulf War in 1991. In addition to being responsible for managing the decommissioning wastes, the RWTMD is responsible for more than 950 disused sealed radioactive sources, contaminated debris from the first Gulf War and (approximately 900 tons) of naturally-occurring radioactive materials wastes from oil production in Iraq. The RWTMD has trained staff, rehabilitated the Building 39 Radioactive Waste Storage building, rehabilitated portions of the French-built Radioactive Waste Treatment Station, organized and secured thousands of drums of radioactive waste organized and secured the stores of disused sealed radioactive sources. Currently, the IDD and the RWTMD are finalizing plans for the decommissioning of the Tammuz II Research Reactor. (authors)

  1. Tamper tape seals

    SciTech Connect (OSTI)

    Wright, B.W.; Undem, H.A.

    1994-07-01T23:59:59.000Z

    Tamper tapes are appealing for many applications due to their ease of use and relative robustness. Applications include seals for temporary area denial, protection of sensitive equipment, chain-of-custody audit trails, and inventory control practices. A next generation of adhesive tamper tapes is being developed that combines the best features of commercially available devices with additional state-of-the-art features in tamper indication, tamper-resistance, and counterfeit-resistance. The additional features are based on U.S. Department of Energy (DOE) research and development (R&D) activities that were originally associated with preparations for the Strategic Arms Reduction Treaty (START). New features include rapid-set, chemical-cure adhesive systems that allow user-friendly application and layered levels of counterfeit-resistance based on unique {open_quotes}fingerprint{close_quotes} characteristics that can be accessed as desired.

  2. Uranium Compounds and Other Natural Radioactivities

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

    for application of radioactive sources requirements. However, soil samples from the Chernobyl or Fukushima exclusion areas, mined ores or tailings from mining operations, and...

  3. Investigating Low Temperature Properties of Rubber Seals - 13020

    SciTech Connect (OSTI)

    Jaunich, M.; Wolff, D.; Stark, W. [BAM Federal Institute for Materials Research and Testing, Unter den Eichen 87, 12203 Berlin (Germany)] [BAM Federal Institute for Materials Research and Testing, Unter den Eichen 87, 12203 Berlin (Germany)

    2013-07-01T23:59:59.000Z

    To achieve the required tightness levels of containers for low and intermediate level radioactive wastes rubbers are widely applied as main sealing materials. The save encapsulation of the radioactive container contents has to be guaranteed according to legislation and appropriate guidelines for long storage periods as well as down to temperatures of -40 deg. C during transportation. Therefore the understanding of failure mechanisms that lead to leakage at low temperatures is of high importance. It is known that the material properties of rubbers are strongly influenced by temperature. At low temperatures this is caused by the rubber-glass transition (abbr. glass transition). During continuous cooling the material changes from rubber-like entropy-elastic to stiff energy-elastic behaviour, that allows nearly no strain or retraction. Therefore, rubbers are normally used above their glass transition but the minimum working temperature limit is not defined precisely, what can cause problems during application. The temperature range where full functionality is possible is strongly dependent on the application conditions and the material. For this investigation mainly ethylene propylene diene (EPDM) and fluorocarbon rubbers (FKM) were selected as they are often used for radioactive waste containers. Differential Scanning Calorimetry (DSC) and Dynamic Mechanical Analysis (DMA) are typically used for the determination of the temperature range of the glass transition process. The standardized compression set measurement according to ISO 815 is common for investigation of rubber sealing materials as the test simulates the seal behaviour after release. To reduce the test time of the standard tests a faster technique giving the same information was developed. Additionally, the breakdown temperature of the sealing function of complete O-ring seals is measured in a component test setup to compare it with the results of the other tests. The experimental setup is capable of measuring the leakage rate at low temperatures by the pressure rise method. A model was developed that allows calculating the minimum working temperature limit of a seal by combining the results of the applied methods. (authors)

  4. Radioactive waste processing apparatus

    DOE Patents [OSTI]

    Nelson, Robert E. (Lombard, IL); Ziegler, Anton A. (Darien, IL); Serino, David F. (Maplewood, MN); Basnar, Paul J. (Western Springs, IL)

    1987-01-01T23:59:59.000Z

    Apparatus for use in processing radioactive waste materials for shipment and storage in solid form in a container is disclosed. The container includes a top, and an opening in the top which is smaller than the outer circumference of the container. The apparatus includes an enclosure into which the container is placed, solution feed apparatus for adding a solution containing radioactive waste materials into the container through the container opening, and at least one rotatable blade for blending the solution with a fixing agent such as cement or the like as the solution is added into the container. The blade is constructed so that it can pass through the opening in the top of the container. The rotational axis of the blade is displaced from the center of the blade so that after the blade passes through the opening, the blade and container can be adjusted so that one edge of the blade is adjacent the cylindrical wall of the container, to insure thorough mixing. When the blade is inside the container, a substantially sealed chamber is formed to contain vapors created by the chemical action of the waste solution and fixant, and vapors emanating through the opening in the container.

  5. Seal device for ferromagnetic containers

    DOE Patents [OSTI]

    Meyer, Ross E. (Los Alamos, NM); Jason, Andrew J. (Los Alamos, NM)

    1994-01-01T23:59:59.000Z

    A temporary seal or patch assembly prevents the escape of contents, e.g., fluids and the like, from within a container having a breach therethrough until the contents can be removed and/or a repair effected. A frame that supports a sealing bladder can be positioned over the breach and the frame is then attached to the container surface, which must be of a ferromagnet material, by using switchable permanent magnets. The permanent magnets are designed to have a first condition that is not attracted to the ferromagnetic surface and a second conditions whereby the magnets are attracted to the surface with sufficient force to support the seal assembly on the surface. Latching devices may be attached to the frame and engage the container surface with hardened pins to prevent the lateral movement of the seal assembly along the container surface from external forces such as fluid drag or gravity.

  6. Seal device for ferromagnetic containers

    DOE Patents [OSTI]

    Meyer, R.E.; Jason, A.J.

    1994-10-18T23:59:59.000Z

    A temporary seal or patch assembly prevents the escape of contents, e.g., fluids and the like, from within a container having a breach there through until the contents can be removed and/or a repair effected. A frame that supports a sealing bladder can be positioned over the breach and the frame is then attached to the container surface, which must be of a ferromagnet material, by using switchable permanent magnets. The permanent magnets are designed to have a first condition that is not attracted to the ferromagnetic surface and a second conditions whereby the magnets are attracted to the surface with sufficient force to support the seal assembly on the surface. Latching devices may be attached to the frame and engage the container surface with hardened pins to prevent the lateral movement of the seal assembly along the container surface from external forces such as fluid drag or gravity. 10 figs.

  7. Switchable radioactive neutron source device

    DOE Patents [OSTI]

    Stanford, G.S.; Rhodes, E.A.; Devolpi, A.; Boyar, R.E.

    1987-11-06T23:59:59.000Z

    This invention is a switchable neutron generating apparatus comprised of a pair of plates, the first plate having an alpha emitter section on it and the second plate having a target material portion on it which generates neutrons when its nuclei absorb an alpha particle. In operation, the alpha portion of the first plate is aligned with the neutron portion of the second plate to produce neutrons and brought out of alignment to cease production of neutrons. 3 figs.

  8. Switchable radioactive neutron source device

    DOE Patents [OSTI]

    Boyar, Robert E. (La Grange, IL); DeVolpi, Alexander (Bolingbrook, IL); Stanford, George S. (Downers Grove, IL); Rhodes, Edgar A. (Woodridge, IL)

    1989-01-01T23:59:59.000Z

    This invention is a switchable neutron generating apparatus comprised of a pair of plates, the first plate having an alpha emitter section on it and the second plate having a target material portion on it which generates neutrons when its nuclei absorb an alpha particle. In operation, the alpha portion of the first plate is aligned with the neutron portion of the second plate to produce neutrons and brought out of alignment to cease production of neutrons.

  9. Findings in seal coat design

    E-Print Network [OSTI]

    Gonzalez Palmer, Miguel Angel

    1988-01-01T23:59:59.000Z

    FINDINGS IN SEAL COAT DESIGN A Thesis by MIGUEL ANGEL GONZALEZ PALMER Submitted to the Graduate College of Texas A&M University in partial fulfillment of the requirements for the degree of MASTER OF SCIENCE May 1988 Major Subject : Civil... Engineering FINDINGS IN SEAL COAT DESIGN A Thesis by MIGUEL ANGEL GONZALEZ PALMER Approved as to style and content by: Michael P. J. Olsen (Chairman of Committee) Dallas N. Little (Member) ne D. Tiner (Member) James T. P. Yao (Head of Departme...

  10. Greater-than-Class C low-level radioactive waste characterization: Estimated volumes, radionuclide activities, and other characteristics. Revision 1

    SciTech Connect (OSTI)

    Not Available

    1994-09-01T23:59:59.000Z

    The Department of Energy`s (DOE`s) planning for the disposal of greater-than-Class C low-level radioactive waste (GTCC LLW) requires characterization of the waste. This report estimates volumes, radionuclide activities, and waste forms of GTCC LLW to the year 2035. It groups the waste into four categories, representative of the type of generator or holder of the waste: Nuclear Utilities, Sealed Sources, DOE-Held, and Other Generator. GTCC LLW includes activated metals (activation hardware from reactor operation and decommissioning), process wastes (i.e., resins, filters, etc.), sealed sources, and other wastes routinely generated by users of radioactive material. Estimates reflect the possible effect that packaging and concentration averaging may have on the total volume of GTCC LLW. Possible GTCC mixed LLW is also addressed. Nuclear utilities will probably generate the largest future volume of GTCC LLW with 65--83% of the total volume. The other generators will generate 17--23% of the waste volume, while GTCC sealed sources are expected to contribute 1--12%. A legal review of DOE`s obligations indicates that the current DOE-Held wastes described in this report will not require management as GTCC LLW because of the contractual circumstances under which they were accepted for storage. This report concludes that the volume of GTCC LLW should not pose a significant management problem from a scientific or technical standpoint. The projected volume is small enough to indicate that a dedicated GTCC LLW disposal facility may not be justified. Instead, co-disposal with other waste types is being considered as an option.

  11. Greater-than-Class C low-level radioactive waste characterization. Appendix E-4: Packaging factors for greater-than-Class C low-level radioactive waste

    SciTech Connect (OSTI)

    Quinn, G.; Grant, P.; Winberg, M.; Williams, K.

    1994-09-01T23:59:59.000Z

    This report estimates packaging factors for several waste types that are potential greater-than-Class C (GTCC) low-level radioactive waste (LLW). The packaging factor is defined as the volume of a GTCC LLW disposal container divided by the as-generated or ``unpackaged`` volume of the waste loaded into the disposal container. Packaging factors reflect any processes that reduce or increase an original unpackaged volume of GTCC LLW, the volume inside a waste container not occupied by the waste, and the volume of the waste container itself. Three values are developed that represent (a) the base case or most likely value for a packaging factor, (b) a high case packaging factor that corresponds to the largest anticipated disposal volume of waste, and (c) a low case packaging factor for the smallest volume expected. GTCC LLW is placed in three categories for evaluation in this report: activated metals, sealed sources, and all other waste.

  12. Laser sealed vacuum insulation window

    DOE Patents [OSTI]

    Benson, David K. (Golden, CO); Tracy, C. Edwin (Golden, CO)

    1987-01-01T23:59:59.000Z

    A laser sealed evacuated window panel is comprised of two glass panes held spaced apart in relation to each other by a plurality of spherical glass beads and glass welded around the edges to provide an evacuated space between the glass panes that is completely glass sealed from the exterior. The glass welded edge seal is obtained by welding the edges of the glass panes together with a laser beam while the glass panes and bead spacers are positioned in a vacuum furnace and heated to the annealing point of the glass to avoid stress fracture in the area of the glass weld. The laser welding in the furnace can be directed around the perimeter of the glass panel by a combination of rotating the glass panel and linearly translating or aiming the laser with a relay mirror.

  13. Laser sealed vacuum insulating window

    DOE Patents [OSTI]

    Benson, D.K.; Tracy, C.E.

    1985-08-19T23:59:59.000Z

    A laser sealed evacuated window panel is comprised of two glass panes held spaced apart in relation to each other by a plurality of spherical glass beads and glass welded around the edges to provide an evacuated space between the glass panes that is completely glass sealed from the exterior. The glass welded edge seal is obtained by welding the edges of the glass panes together with a laser beam while the glass panes and bead spacers are positioned in a vacuum furnace and heated to the annealing point of the glass to avoid stress fracture in the area of the glass weld. The laser welding in the furnace can be directed around the perimeter of the galss panel by a combination of rotating the glass panel and linearly translating or aiming the laser with a relay mirror.

  14. Stabilizing geometry for hydrodynamic rotary seals

    DOE Patents [OSTI]

    Dietle, Lannie L. (Houston, TX); Schroeder, John E. (Richmond, TX)

    2010-08-10T23:59:59.000Z

    A hydrodynamic sealing assembly including a first component having first and second walls and a peripheral wall defining a seal groove, a second component having a rotatable surface relative to said first component, and a hydrodynamic seal comprising a seal body of generally ring-shaped configuration having a circumference. The seal body includes hydrodynamic and static sealing lips each having a cross-sectional area that substantially vary in time with each other about the circumference. In an uninstalled condition, the seal body has a length defined between first and second seal body ends which varies in time with the hydrodynamic sealing lip cross-sectional area. The first and second ends generally face the first and second walls, respectively. In the uninstalled condition, the first end is angulated relative to the first wall and the second end is angulated relative to the second wall. The seal body has a twist-limiting surface adjacent the static sealing lip. In the uninstalled condition, the twist-limiting surface is angulated relative to the peripheral wall and varies along the circumference. A seal body discontinuity and a first component discontinuity mate to prevent rotation of the seal body relative to the first component.

  15. SOURCE?

    Energy Savers [EERE]

    Department of Energy (DOE) in partnership with Lawrence Berkeley National Laboratory (LBNL), is an open-source code package designed to be a common, low-cost, standardized tool...

  16. Dual rotating shaft seal apparatus

    DOE Patents [OSTI]

    Griggs, J.E.; Newman, H.J.

    1983-06-16T23:59:59.000Z

    The report is directed to apparatus suitable for transferring torque and rotary motion through a wall in a manner which is essentially gas impermeable. The apparatus can be used for pressurizing, agitating, and mixing fluids and features two ferrofluidic, i.e., ferrometic seals. Each seal is disposed on one of two supported shafts and each shaft is operably connected at one end to a gear mechanism and at its other end to an adjustable coupling means which is to be connected to a rotatable shaft extending through a wall through which torque and rotary motion are to be transferred.

  17. Radioactive waste processing apparatus

    DOE Patents [OSTI]

    Nelson, R.E.; Ziegler, A.A.; Serino, D.F.; Basnar, P.J.

    1985-08-30T23:59:59.000Z

    Apparatus for use in processing radioactive waste materials for shipment and storage in solid form in a container is disclosed. The container includes a top, and an opening in the top which is smaller than the outer circumference of the container. The apparatus includes an enclosure into which the container is placed, solution feed apparatus for adding a solution containing radioactive waste materials into the container through the container opening, and at least one rotatable blade for blending the solution with a fixing agent such as cement or the like as the solution is added into the container. The blade is constructed so that it can pass through the opening in the top of the container. The rotational axis of the blade is displaced from the center of the blade so that after the blade passes through the opening, the blade and container can be adjusted so that one edge of the blade is adjacent the cylindrical wall of the container, to insure thorough mixing. When the blade is inside the container, a substantially sealed chamber is formed to contain vapors created by the chemical action of the waste solution and fixant, and vapors emanating through the opening in the container. The chamber may be formed by placing a removable extension over the top of the container. The extension communicates with the apparatus so that such vapors are contained within the container, extension and solution feed apparatus. A portion of the chamber includes coolant which condenses the vapors. The resulting condensate is returned to the container by the force of gravity.

  18. Seal strength models for medical device trays

    E-Print Network [OSTI]

    Mays, Patricia Faye

    2009-05-15T23:59:59.000Z

    nine package configurations. Packages for burst testing were sealed under a fractional factorial design with 27 treatments. Packages for peel testing were sealed under a 17-point face-centered central composite design. Packages were tested using peel...

  19. Investigation of stepped labyrinth seal leakage performance

    E-Print Network [OSTI]

    Reed, Thomas Stanley

    1993-01-01T23:59:59.000Z

    Leakage resistance of advanced design, stepped labyrinth seals has been examined based on geometric considerations. Leakage measurements were obtained in an attempt to identify geometric and flow characteristics contributing to a desired seal...

  20. Leakage and rotordynamic effects of pocket damper seals and see-through labyrinth seals

    E-Print Network [OSTI]

    Gamal Eldin, Ahmed Mohamed

    2009-05-15T23:59:59.000Z

    Tests ........................................................................... 73 VIII LEAKAGE TESTS: EFFECTS OF SEAL DESIGN PARAMETERS ............. 79 Review of Earlier Tests...

  1. Leakage and rotordynamic effects of pocket damper seals and see-through labyrinth seals

    E-Print Network [OSTI]

    Gamal Eldin, Ahmed Mohamed

    2008-10-10T23:59:59.000Z

    Tests ........................................................................... 73 VIII LEAKAGE TESTS: EFFECTS OF SEAL DESIGN PARAMETERS ............. 79 Review of Earlier Tests...

  2. Rotordynamic force coefficients of pocket damper seals

    E-Print Network [OSTI]

    Ertas, Bugra Han

    2005-11-01T23:59:59.000Z

    (Back Cap) Lubrication and Cooling Air Piston Cylinder Piston Pressurized Air (115 psi) Pedestal Misaligned Slave Bearing Carrier Slave Bearing Lock Washer Tie Bolt Teflon Ring Seals Spacer Damper Seal Housing Pocket Damper Seal O-Ring Seal Figure 6... by providing engineers with experimental results of PDS that are applicable to the operating conditions observed in the industry. Therefore, unlike previous tests conducted on PDS, the present tests are performed at high inlet pressures (1,000 psi), adequate...

  3. Piston rod seal for a Stirling engine

    DOE Patents [OSTI]

    Shapiro, Wilbur (Schenectady, NY)

    1984-01-01T23:59:59.000Z

    In a piston rod seal for a Stirling engine, a hydrostatic bearing and differential pressure regulating valve are utilized to provide for a low pressure differential across a rubbing seal between the hydrogen and oil so as to reduce wear on the seal.

  4. Acoustic resonance spectroscopy intrinsic seals

    SciTech Connect (OSTI)

    Olinger, C.T.; Burr, T.; Vnuk, D.R.

    1994-08-01T23:59:59.000Z

    We have begun to quantify the ability of acoustic resonance spectroscopy (ARS) to detect the removal and replacement of the lid of a simulated special nuclear materials drum. Conceptually, the acoustic spectrum of a container establishcs a baseline fingerprint, which we refer to as an intrinsic seal, for the container. Simply removing and replacing the lid changes some of the resonant frequencies because it is impossible to exactly duplicate all of the stress patterns between the lid and container. Preliminary qualitative results suggested that the ARS intrinsic seal could discriminate between cases where a lid has or has not been removed. The present work is directed at quantifying the utility of the ARS intrinsic seal technique, including the technique`s sensitivity to ``nuisance`` effects, such as temperature swings, movement of the container, and placement of the transducers. These early quantitative tests support the potential of the ARS intrinsic seal application, but also reveal a possible sensitivity to nuisance effects that could limit environments or conditions under which the technique is effective.

  5. Energy conversion device with improved seal

    DOE Patents [OSTI]

    Miller, Gerald R. (Salt Lake City, UT); Virkar, Anil V. (Midvale, UT)

    1980-01-01T23:59:59.000Z

    An energy conversion device comprising an improved sealing member adapted to seal a cation-permeable casing to the remainder of the device. The sealing member comprises a metal substrate which (i) bears a nonconductive and corrosion resistant coating on the major surface to which said casing is sealed, and (ii) is corrugated so as to render it flexible, thereby allowing said member to move relative to said casing without cracking the seal therebetween. Corrugations may be circumferential, radial, or both radial and circumferential so as to form dimples. The corrugated member may be in form of a bellows or in a substantially flat form, such as a disc.

  6. Greater-than-Class C low-level radioactive waste characterization. Appendix E-2: Mixed GTCC LLW assessment

    SciTech Connect (OSTI)

    Kirner, N.P. [Ebasco Environmental, Idaho Falls, ID (United States)

    1994-09-01T23:59:59.000Z

    Mixed greater-than-Class C low-level radioactive waste (mixed GTCC LLW) is waste that combines two characteristics: it is radioactive, and it is hazardous. This report uses information compiled from Greater-Than-Class C Low-Level Radioactive Waste Characterization: Estimated Volumes, Radionuclide Activities, and Other Characteristics (DOE/LLW 1 14, Revision 1), and applies it to the question of how much and what types of mixed GTCC LLW are generated and are likely to require disposal in facilities jointly regulated by the DOE and the NRC. The report describes how to classify a RCRA hazardous waste, and then applies that classification process to the 41 GTCC LLW waste types identified in the DOE/LLW-114 (Revision 1). Of the 41 GTCC LLW categories identified, only six were identified in this study as potentially requiring regulation as hazardous waste under RCRA. These wastes can be combined into the following three groups: fuel-in decontamination resins, organic liquids, and process waste consisting of lead scrap/shielding from a sealed source manufacturer. For the base case, no mixed GTCC LLW is expected from nuclear utilities or sealed source licensees, whereas only 177 ml of mixed GTCC LLW are expected to be produced by other generators through the year 2035. This relatively small volume represents approximately 40% of the base case estimate for GTCC wastes from other generators. For these other generators, volume estimates for mixed GTCC LLW ranged from less than 1 m{sup 3} to 187 m{sup 3}, depending on assumptions and treatments applied to the wastes.

  7. Double angle seal forming lubricant film

    DOE Patents [OSTI]

    Ernst, William D. (Troy, NY)

    1984-01-01T23:59:59.000Z

    A lubricated piston rod seal which inhibits gas leaking from a high pressure chamber on one side of the seal to a low pressure chamber on the other side of the seal. A liquid is supplied to the surface of the piston rod on the low pressure side of the seal. This liquid acts as lubricant for the seal and provides cooling for the rod. The seal, which can be a plastic, elastomer or other material with low elastic modulus, is designed to positively pump lubricant through the piston rod/seal interface in both directions when the piston rod is reciprocating. The capacity of the seal to pump lubricant from the low pressure side to the high pressure side is less than its capacity to pump lubricant from the high pressure side to the low pressure side which ensures that there is zero net flow of lubricant to the high pressure side of the seal. The film of lubricant between the seal and the rod minimizes any sliding contact and prevents the leakage of gas. Under static conditions gas leakage is prevented by direct contact between the seal and the rod.

  8. Rotary seal with improved film distribution

    DOE Patents [OSTI]

    Dietle, Lannie Laroy; Schroeder, John Erick

    2013-10-08T23:59:59.000Z

    The present invention is a generally circular rotary seal that establishes sealing between relatively rotatable machine components for lubricant retention and environmental exclusion, and incorporates seal geometry that interacts with the lubricant during relative rotation to distribute a lubricant film within the dynamic sealing interface. The features of a variable inlet size, a variable dynamic lip flank slope, and a reduction in the magnitude and circumferentially oriented portion of the lubricant side interfacial contact pressure zone at the narrowest part of the lip, individually or in combination thereof, serve to maximize interfacial lubrication in severe operating conditions, and also serve to minimize lubricant shear area, seal torque, seal volume, and wear, while ensuring retrofitability into the seal grooves of existing equipment.

  9. Experimental evaluation of pocket damper seals with brush seal elements

    E-Print Network [OSTI]

    Buchanan, Steven Eugene

    2000-01-01T23:59:59.000Z

    . ACKNOWLEDGEMENTS . . tv TABLE OF CONTENTS. . LIST OF FIGURES. . Vu1 LIST OF TABLES. LIST OF EQUATIONS . . CHAPTER I INTRODUCTION . Background. . Objectives. Literature Review. . Experimental Apparatus. II LEAKAGE TESTS . . 1 3 4 6 10 Objective...Q) 0 20 30 40 50 60 70 80 90 10 CHAPTER II LEAKAGE TESTS Objective Since the primary objective of this project is to reduce the leakage of gases Rom the high pressure side to the low pressure side of the seal while retaining the damping...

  10. Seal for fluid forming tools

    DOE Patents [OSTI]

    Golovashchenko, Sergey Fedorovich (Beverly Hills, MI); Bonnen, John Joseph Francis (Milford, MI)

    2012-03-20T23:59:59.000Z

    An electro-hydraulic forming tool for forming a sheet metal blank in a one-sided die has first and second rigid rings that engage opposite sides of a sheet metal blank. The rigid rings are contained within slots on a die portion and a hydraulic force applicator portion of the forming tool. The seals are either resiliently biased by an elastomeric member or inherently resiliently biased into contact with the blank.

  11. Wet powder seal for gas containment

    DOE Patents [OSTI]

    Stang, Louis G. (Sayville, NY)

    1982-01-01T23:59:59.000Z

    A gas seal is formed by a compact layer of an insoluble powder and liquid filling the fine interstices of that layer. The smaller the particle size of the selected powder, such as sand or talc, the finer will be the interstices or capillary spaces in the layer and the greater will be the resulting sealing capacity, i.e., the gas pressure differential which the wet powder layer can withstand. Such wet powder seal is useful in constructing underground gas reservoirs or storage cavities for nuclear wastes as well as stopping leaks in gas mains buried under ground or situated under water. The sealing capacity of the wet powder seal can be augmented by the hydrostatic head of a liquid body established over the seal.

  12. An Internal Coaxil Cable Seal System

    DOE Patents [OSTI]

    Hall, David R. (Provo, UT); Hall, Jr., H. Tracy (Provo, UT); Pixton, David (Lehi, UT); Dahlgren, Scott (Provo, UT); Sneddon, Cameron (Provo, UT); Briscoe, Michael (Lehi, UT); Fox, Joe (Spanish Fork, UT)

    2004-12-23T23:59:59.000Z

    The invention is a seal system for a coaxial cable more specifically an internal seal system placed within the coaxial cable and its constituent components. A series of seal stacks including flexible rigid rings and elastomeric rings are placed on load bearing members within the coaxial cable. The current invention is adapted to seal the annular space between the coaxial cable and an electrical contact passing there through. The coaxial cable is disposed within drilling components to transmit electrical signals between drilling components within a drill string. During oil and gas exploration, a drill string can see a range of pressures and temperatures thus resulting in multiple combinations of temperature and pressure and increasing the difficulty of creating a robust seal for all combinations. The seal system can be used in a plurality of downhole components, such as sections of pipe in a drill string, drill collars, heavy weight drill pipe, and jars.

  13. Cure-in-place process for seals

    DOE Patents [OSTI]

    Hirasuna, Alan R. (Corona Del Mar, CA)

    1981-01-01T23:59:59.000Z

    A cure-in-place process which allows a rubber seal element to be deformed to its service configuration before it is cross-linked and, hence, is a plastic and does not build up internal stress as a result of the deformation. This provides maximum residual strength to resist the differential pressure. Furthermore, the process allows use of high modulus formulations of the rubber seal element which would otherwise crack if cured and then deformed to its service configuration, resulting in a seal which has better gap bridging capability. Basically, the process involves positioning an uncured seal element in place, deforming it to its service configuration, heating the seal element, curing it in place, and then fully seating the seal.

  14. Radioactive Material Transportation Practices

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

    2002-09-23T23:59:59.000Z

    Establishes standard transportation practices for Departmental programs to use in planning and executing offsite shipments of radioactive materials including radioactive waste. Does not cancel other directives.

  15. Radioactive Waste Management

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

    1984-02-06T23:59:59.000Z

    To establish policies and guidelines by which the Department of Energy (DOE) manages tis radioactive waste, waste byproducts, and radioactively contaminated surplus facilities.

  16. DOE/NNSA Recovers One Millionth Curie of Radioactive Material...

    National Nuclear Security Administration (NNSA)

    were part of DOENNSA's global campaign to prevent terrorists from acquiring nuclear and radiological material. The radioactive source that achieved the millionth curie milestone...

  17. annual radioactive waste: Topics by E-print Network

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

    is: not high-level radioactive waste or irradiated nuclear fuel not uranium, thorium or other ore tailings or waste from extraction and concentration for source material...

  18. activity radioactive waste: Topics by E-print Network

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

    is: not high-level radioactive waste or irradiated nuclear fuel not uranium, thorium or other ore tailings or waste from extraction and concentration for source material...

  19. aqueous radioactive waste: Topics by E-print Network

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

    is: not high-level radioactive waste or irradiated nuclear fuel not uranium, thorium or other ore tailings or waste from extraction and concentration for source material...

  20. artificial radioactivity levels: Topics by E-print Network

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

    is: not high-level radioactive waste or irradiated nuclear fuel not uranium, thorium or other ore tailings or waste from extraction and concentration for source material...

  1. acidic radioactive waste: Topics by E-print Network

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

    is: not high-level radioactive waste or irradiated nuclear fuel not uranium, thorium or other ore tailings or waste from extraction and concentration for source material...

  2. ambient radioactivity levels: Topics by E-print Network

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

    is: not high-level radioactive waste or irradiated nuclear fuel not uranium, thorium or other ore tailings or waste from extraction and concentration for source material...

  3. activities radioactive waste: Topics by E-print Network

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

    is: not high-level radioactive waste or irradiated nuclear fuel not uranium, thorium or other ore tailings or waste from extraction and concentration for source material...

  4. activity radioactive wastes: Topics by E-print Network

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

    is: not high-level radioactive waste or irradiated nuclear fuel not uranium, thorium or other ore tailings or waste from extraction and concentration for source material...

  5. alkaline radioactive waste: Topics by E-print Network

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

    is: not high-level radioactive waste or irradiated nuclear fuel not uranium, thorium or other ore tailings or waste from extraction and concentration for source material...

  6. A NUMERICAL AND EXPERIMENTAL STUDY OF WINDBACK SEALS

    E-Print Network [OSTI]

    Lim, Chae H.

    2010-01-16T23:59:59.000Z

    Windback seals work similarly to labyrinth seals except for the effect of helical groove. These seals are essentially a tooth on stator or tooth on rotor labyrinth seal where the grooves are a continuous helical cut like a thread. Windback seals...

  7. Corrosion resistant storage container for radioactive material

    DOE Patents [OSTI]

    Schweitzer, Donald G. (Bayport, NY); Davis, Mary S. (Wading River, NY)

    1990-01-01T23:59:59.000Z

    A corrosion resistant long-term storage container for isolating radioactive waste material in a repository. The container is formed of a plurality of sealed corrosion resistant canisters of different relative sizes, with the smaller canisters housed within the larger canisters, and with spacer means disposed between judxtaposed pairs of canisters to maintain a predetermined spacing between each of the canisters. The combination of the plural surfaces of the canisters and the associated spacer means is effective to make the container capable of resisting corrosion, and thereby of preventing waste material from leaking from the innermost canister into the ambient atmosphere.

  8. Corrosion resistant storage container for radioactive material

    DOE Patents [OSTI]

    Schweitzer, D.G.; Davis, M.S.

    1984-08-30T23:59:59.000Z

    A corrosion resistant long-term storage container for isolating high-level radioactive waste material in a repository is claimed. The container is formed of a plurality of sealed corrosion resistant canisters of different relative sizes, with the smaller canisters housed within the larger canisters, and with spacer means disposed between juxtaposed pairs of canisters to maintain a predetermined spacing between each of the canisters. The combination of the plural surfaces of the canisters and the associated spacer means is effective to make the container capable of resisting corrosion, and thereby of preventing waste material from leaking from the innermost canister into the ambient atmosphere.

  9. Greater-than-Class C low-level radioactive waste characterization. Appendix H: Packaging factors for greater-than-Class C low-level radioactive waste

    SciTech Connect (OSTI)

    Quinn, G.; Grant, P.

    1991-08-01T23:59:59.000Z

    This report develops and presents estimates for a set of three values that represent a reasonable range for the packaging factors for several waste streams that are potential greater-than-Class C low-level radioactive waste. The packaging factor is defined as the volume of a greater-than-Class C low-level waste disposal container divided by the original, as-generated or ``unpackaged,`` volume of the wastes loaded into the disposal container. Packaging factors take into account any processes that reduce or increase an original unpackaged volume of a greater-than-Class C low-level radioactive waste, the volume inside a waste container not occupied by the waste, and the volume of the waste container itself. The three values developed represent (a) the base case or most likely value for a packaging factor, (b) a high case packaging factor that corresponds to the largest anticipated volume of waste for disposal, and (c) a low case packaging factor for the smallest volume expected. Three categories of greater-than-Class C low-level waste are evaluated in this report: activated metals, sealed sources, and all other wastes. Estimates of reasonable packaging factors for the low, base, and high cases for the specific waste streams in each category are shown in Table H-1.

  10. Ceramic blade with tip seal

    DOE Patents [OSTI]

    Glezer, B.; Bhardwaj, N.K.; Jones, R.B.

    1997-08-05T23:59:59.000Z

    The present gas turbine engine includes a disc assembly defining a disc having a plurality of blades attached thereto. The disc has a preestablished rate of thermal expansion and the plurality of blades have a preestablished rate of thermal expansion being less than the preestablished rate of thermal expansion of the disc. A shroud assembly is attached to the gas turbine engine and is spaced from the plurality of blades a preestablished distance forming an interface there between. Positioned in the interface is a seal having a preestablished rate of thermal expansion being generally equal to the rate of thermal expansion of the plurality of blades. 4 figs.

  11. Shim for sealing transition pieces

    DOE Patents [OSTI]

    Lacy, Benjamin Paul (Greer, SC); Demiroglu, Mehmet (Troy, NY); Sarawate, Neelesh Nandkumar (Niskayuna, NY)

    2012-07-24T23:59:59.000Z

    According to one aspect of the invention, a shim for sealing two adjacent turbine transition pieces is disclosed. The shim includes a circumferential member that includes a first lateral flange and a second lateral flange. Further, the first and second lateral flanges each comprise a tab configured to mate to a first surface plane and the first and second lateral flanges are configured to mate to a second surface plane, wherein the first and second surface planes are substantially parallel. In addition, the shim includes a first flange extending substantially perpendicular from the circumferential member.

  12. Magnetohydrodynamic (MHD) channel corner seal

    DOE Patents [OSTI]

    Spurrier, Francis R. (Pittsburgh, PA)

    1980-01-01T23:59:59.000Z

    A corner seal for an MHD duct includes a compressible portion which contacts the duct walls and an insulating portion which contacts the electrodes, sidewall bars and insulators. The compressible portion may be a pneumatic or hydraulic gasket or an open-cell foam rubber. The insulating portion is segmented into a plurality of pieces of the same thickness as the electrodes, insulators and sidewall bars and aligned therewith, the pieces aligned with the insulator being of a different size from the pieces aligned with the electrodes and sidewall bars to create a stepped configuration along the corners of the MHD channel.

  13. Greater-than-Class C low-level radioactive waste characterization: Estimated volumes, radionuclide activities, and other characteristics

    SciTech Connect (OSTI)

    Hulse, R.A.

    1991-08-01T23:59:59.000Z

    Planning for storage or disposal of greater-than-Class C low-level radioactive waste (GTCC LLW) requires characterization of that waste to estimate volumes, radionuclide activities, and waste forms. Data from existing literature, disposal records, and original research were used to estimate the characteristics and project volumes and radionuclide activities to the year 2035. GTCC LLW is categorized as: nuclear utilities waste, sealed sources waste, DOE-held potential GTCC LLW; and, other generator waste. It has been determined that the largest volume of those wastes, approximately 57%, is generated by nuclear power plants. The Other Generator waste category contributes approximately 10% of the total GTCC LLW volume projected to the year 2035. Waste held by the Department of Energy, which is potential GTCC LLW, accounts for nearly 33% of all waste projected to the year 2035; however, no disposal determination has been made for that waste. Sealed sources are less than 0.2% of the total projected volume of GTCC LLW.

  14. High thermal expansion, sealing glass

    DOE Patents [OSTI]

    Brow, Richard K. (Albuquerque, NM); Kovacic, Larry (Albuquerque, NM)

    1993-01-01T23:59:59.000Z

    A glass composition for hermetically sealing to high thermal expansion materials such as aluminum alloys, stainless steels, copper, and copper/beryllium alloys, which includes between about 10 and about 25 mole percent Na.sub.2 O, between about 10 and about 25 mole percent K.sub.2 O, between about 5 and about 15 mole percent Al.sub.2 O.sub.3, between about 35 and about 50 mole percent P.sub.2 O.sub.5 and between about 5 and about 15 mole percent of one of PbO, BaO, and mixtures thereof. The composition, which may also include between 0 and about 5 mole percent Fe.sub.2 O.sub.3 and between 0 and about 10 mole percent B.sub.2 O.sub.3, has a thermal expansion coefficient in a range of between about 160 and 210.times.10-7/.degree.C. and a dissolution rate in a range of between about 2.times.10.sup.- 7 and 2.times.10.sup.-9 g/cm.sup.2 -min. This composition is suitable to hermetically seal to metallic electrical components which will be subjected to humid environments over an extended period of time.

  15. High thermal expansion, sealing glass

    DOE Patents [OSTI]

    Brow, R.K.; Kovacic, L.

    1993-11-16T23:59:59.000Z

    A glass composition is described for hermetically sealing to high thermal expansion materials such as aluminum alloys, stainless steels, copper, and copper/beryllium alloys, which includes between about 10 and about 25 mole percent Na[sub 2]O, between about 10 and about 25 mole percent K[sub 2]O, between about 5 and about 15 mole percent Al[sub 2]O[sub 3], between about 35 and about 50 mole percent P[sub 2]O[sub 5] and between about 5 and about 15 mole percent of one of PbO, BaO, and mixtures thereof. The composition, which may also include between 0 and about 5 mole percent Fe[sub 2]O[sub 3] and between 0 and about 10 mole percent B[sub 2]O[sub 3], has a thermal expansion coefficient in a range of between about 160 and 210[times]10[sup [minus]7]/C and a dissolution rate in a range of between about 2[times]10[sup [minus]7] and 2[times]10[sup [minus]9]g/cm[sup 2]-min. This composition is suitable to hermetically seal to metallic electrical components which will be subjected to humid environments over an extended period of time.

  16. Greater-than-Class C low-level radioactive waste characterization. Appendix D-3: Characterization of greater-than-Class C low-level radioactive waste from other generators

    SciTech Connect (OSTI)

    Fish, L.W.

    1994-09-01T23:59:59.000Z

    The Other Generators category includes all greater-than-Class C low-level radioactive waste (GTCC LLW) that is not generated or held by nuclear utilities or sealed sources licensees or that is not stored at Department of Energy facilities. To determine the amount of waste within this category, 90 LLW generators were contacted; 13 fit the Other Generators category. Based on information received from the 13 identified Other Generators, the GTCC LLW Management Program was able to (a) characterize the nature of industries in this category, (b) estimate the 1993 inventory of Other Generator waste for high, base, and low cases, and (c) project inventories to the year 2035 for high, base, and low cases. Assumptions were applied to each of the case estimates to account for generators who may not have been identified in this study.

  17. Finite difference model of eccentric labyrinth seals

    E-Print Network [OSTI]

    Davis, Fredrick Michael

    1993-01-01T23:59:59.000Z

    shaft of a turbomachine, such as a gas turbine engine. To achieve the desired pressure drop between sections, the seal is constructed to convert the pressure energy between sections to kinetic energy in the seal where it is dissipated. When the rotor.... . . . . Finite Difference Method. Generating Eccentric Grids. . . . . . . . . . . . . . . . . . . . . . . . . . Generalizing Finite Difference Relations. . . . Accounting for Rotor Whirl. . . . . . Turbulence Model. . Enthalpy Model. . Boundary Conditions...

  18. Floating seal system for rotary devices

    DOE Patents [OSTI]

    Banasiuk, H.A.

    1983-08-23T23:59:59.000Z

    This invention relates to a floating seal system for rotary devices to reduce gas leakage around the rotary device in a duct and across the face of the rotary device to an adjacent duct. The peripheral seal bodies are made of resilient material having a generally U-shaped cross section wherein one of the legs is secured to a support member and the other of the legs forms a contacting seal against the rotary device. The legs of the peripheral seal form an extended angle of intersection of about 10[degree] to about 30[degree] in the unloaded condition to provide even sealing forces around the periphery of the rotary device. The peripheral seal extends around the periphery of the support member except where intersected by radial seals which reduce gas leakage across the face of the rotary device and between adjacent duct portions. The radial seal assembly is fabricated from channel bars, the smaller channel bar being secured to the divider of the support member and a larger inverted rigid floating channel bar having its legs freely movable over the legs of the smaller channel bar forming therewith a tubular channel. A resilient flexible tube is positioned within the tubular channel for substantially its full length to reduce gas leakage across the tubular channel. A spacer extends beyond the face of the floating channel near each end of the floating channel a distance to provide desired clearance between the floating channel and the face of the rotary device. 5 figs.

  19. Wide temperature range seal for demountable joints

    DOE Patents [OSTI]

    Sixsmith, H.; Valenzuela, J.A.; Nutt, W.E.

    1991-07-23T23:59:59.000Z

    The present invention is directed to a seal for demountable joints operating over a wide temperature range down to liquid helium temperatures. The seal has anti-extrusion guards which prevent extrusion of the soft ductile sealant material, which may be indium or an alloy thereof. 6 figures.

  20. Wide temperature range seal for demountable joints

    DOE Patents [OSTI]

    Sixsmith, Herbert (Norwich, VT); Valenzuela, Javier A. (Grantham, NH); Nutt, William E. (Enfield, NH)

    1991-07-23T23:59:59.000Z

    The present invention is directed to a seal for demountable joints operating over a wide temperature range down to liquid helium temperatures. The seal has anti-extrusion guards which prevent extrusion of the soft ductile sealant material, which may be indium or an alloy thereof.

  1. Sealing glasses for titanium and titanium alloys

    DOE Patents [OSTI]

    Brow, Richard K. (Albuquerque, NM); Watkins, Randall D. (Albuquerque, NM)

    1992-01-01T23:59:59.000Z

    Glass compositions containing CaO, Al.sub.2 O.sub.3, B.sub.2 O.sub.3, SrO and BaO of various combinations of mole % are provided. These compositions are capable of forming stable glass-to-metal seals with titanium and titanium alloys, for use in components such as seals for battery headers.

  2. Sealing glasses for titanium and titanium alloys

    DOE Patents [OSTI]

    Brow, R.K.; Watkins, R.D.

    1988-01-21T23:59:59.000Z

    Glass compositions containing CaO, Al/sub 2/O/sub 3/, B/sub 2/O/sub 3/, SrO and BaO of various combinations of mole % are provided. These compositions are capable of forming stable glass-to-metal seals with titanium and titanium alloys, for use in components such as seals for battery headers.

  3. Building America Webinar: Sealing of Home Enclosures with Aerosol...

    Energy Savers [EERE]

    Sealing of Home Enclosures with Aerosol Particles Building America Webinar: Sealing of Home Enclosures with Aerosol Particles This webinar was presented by research team Building...

  4. Spring loaded compliant seal for high temperature use

    DOE Patents [OSTI]

    Memmen, Robert L; Fedock, John A; Downs, James P

    2013-10-15T23:59:59.000Z

    A flexible seal having an X-shaped cross section that forms four contact points on four contact surfaces of two opposed seal slots. The flexible seal is used for a component in which the two seal slots undergo a large deflection such that the opposed slots are not aligned and a rigid seal will not form an adequate seal. The flexible seal can be used in a component of a combustor or a turbine in a gas turbine engine where opposed seal slots undergo the large deflection during operation.

  5. Integrated seal for high-temperature electrochemical device

    DOE Patents [OSTI]

    Tucker, Michael C; Jacobson, Craig P

    2013-07-16T23:59:59.000Z

    The present invention provides electrochemical device structures having integrated seals, and methods of fabricating them. According to various embodiments the structures include a thin, supported electrolyte film with the electrolyte sealed to the support. The perimeter of the support is self-sealed during fabrication. The perimeter can then be independently sealed to a manifold or other device, e.g., via an external seal. According to various embodiments, the external seal does not contact the electrolyte, thereby eliminating the restrictions on the sealing method and materials imposed by sealing against the electrolyte.

  6. Refrigerator with a clearance seal compressor

    SciTech Connect (OSTI)

    Holland, N. J.

    1985-09-10T23:59:59.000Z

    In a Stirling refrigeration system in which a displacer is driven in a reciprocating motion within a cold finger by a pressure differential between helium gas in the cold finger and helium gas in a gas spring volume, the reciprocating piston compressor for the working volume has a clearance seal between the working volume and a control volume. The only lubricant in that seal is the helium gas. The mean pressure of the working volume relative to the control volume can be controlled by varying the length of the clearance seal throughout the stroke of the piston. Preferably, the seal is between alumina ceramic sleeves. The clearance seal compressor may also be used in a Gifford-McMahon cycle.

  7. Low thermal expansion seal ring support

    DOE Patents [OSTI]

    Dewis, David W. (San Diego, CA); Glezer, Boris (Del Mar, CA)

    2000-01-01T23:59:59.000Z

    Today, the trend is to increase the temperature of operation of gas turbine engines. To cool the components with compressor discharge air, robs air which could otherwise be used for combustion and creates a less efficient gas turbine engine. The present low thermal expansion sealing ring support system reduces the quantity of cooling air required while maintaining life and longevity of the components. Additionally, the low thermal expansion sealing ring reduces the clearance "C","C'" demanded between the interface between the sealing surface and the tip of the plurality of turbine blades. The sealing ring is supported by a plurality of support members in a manner in which the sealing ring and the plurality of support members independently expand and contract relative to each other and to other gas turbine engine components.

  8. Zero dead volume tube to surface seal

    DOE Patents [OSTI]

    Benett, William J. (Livermore, CA); Folta, James A. (Livermore, CA)

    2000-01-01T23:59:59.000Z

    A method and apparatus for connecting a tube to a surface that creates a dead volume seal. The apparatus is composed of three components, a body, a ferrule, and a threaded fitting. The ferrule is compressed onto a tube and a seal is formed between the tube and a device retained in the body by threading the fitting into the body which provides pressure that seals the face of the ferrule to a mating surface on the device. This seal can be used at elevated temperatures depending on the materials used. While the invention has been developed for use with micro-machined silicon wafers used in Capillary Gas Chromatograph (GC), it can be utilized anywhere for making a gas or fluid face seal to the surface of a device that has near zero dead volume.

  9. Ceramic blade with tip seal

    DOE Patents [OSTI]

    Glezer, Boris (Del Mar, CA); Bhardwaj, Narender K. (San Diego, CA); Jones, Russell B. (San Diego, CA)

    1997-01-01T23:59:59.000Z

    The present gas turbine engine (10) includes a disc assembly (64) defining a disc (66) having a plurality of blades (70) attached thereto. The disc (66) has a preestablished rate of thermal expansion and the plurality of blades have a preestablished rate of thermal expansion being less than the preestablished rate of thermal expansion of the disc (66). A shroud assembly (100) is attached to the gas turbine engine (10) and is spaced from the plurality of blades (70) a preestablished distance forming an interface (108) therebetween. Positioned in the interface is a seal (110) having a preestablished rate of thermal expansion being generally equal to the rate of thermal expansion of the plurality of blades (70).

  10. Case Study of Envelope Sealing in Existing Multiunit Structures

    SciTech Connect (OSTI)

    Dentz, J.; Conlin, F.; Podorson, D.

    2012-10-01T23:59:59.000Z

    Envelope air sealing was included in the retrofit of a 244 unit low-rise multifamily housing complex in Durham, N.C. Pre- and post-retrofit enclosure leakage tests were conducted on 51 units and detailed diagnostics were performed on 16. On average, total leakage was reduced by nearly half, from 19.7 ACH50 to 9.4 ACH50. Costs for air sealing were $0.31 per square foot of conditioned floor area, lower than estimates found in the National Residential Efficiency Measures Database (NREMD) and other sources, perhaps due in part to the large-scale production nature of the project. Modeling with BEopt software -- using an estimate of 85% of the envelope air leakage going to the outside (based on guarded tests performed at the site) -- calculated a space conditioning energy cost savings of 15% to 21% due to the air sealing retrofit. Important air leakage locations identified included plumbing and electrical penetrations, dropped ceilings/soffits, windows, ducts and wall-to-floor intersections. Previous repair activity had created significant leakage locations as well. Specifications and a pictorial guide were developed for contractors performing the work.

  11. Sealing glasses for titanium and titanium alloys

    DOE Patents [OSTI]

    Brow, Richard K. (Albuquerque, NM); McCollister, Howard L. (Albuquerque, NM); Phifer, Carol C. (Albuquerque, NM); Day, Delbert E. (Rolla, MO)

    1997-01-01T23:59:59.000Z

    Barium lanthanoborate sealing-glass compositions are provided comprising various combinations (in terms of mole-%) of boron oxide (B.sub.2 O.sub.3), barium oxide (BaO), lanthanum oxide (La.sub.2 O.sub.3), and at least one other oxide selected from the group consisting of aluminum oxide (Al.sub.2 O.sub.3), calcium oxide (CaO), lithium oxide (Li.sub.2 O), sodium oxide (Na.sub.2 O), silicon dioxide (SiO.sub.2), or titanium dioxide (TiO.sub.2). These sealing-glass compositions are useful for forming hermetic glass-to-metal seals with titanium and titanium alloys having an improved aqueous durability and favorable sealing characteristics. Examples of the sealing-glass compositions are provided having coefficients of thermal expansion about that of titanium or titanium alloys, and with sealing temperatures less than about 900.degree. C., and generally about 700.degree.-800.degree. C. The barium lanthanoborate sealing-glass compositions are useful for components and devices requiring prolonged exposure to moisture or water, and for implanted biomedical devices (e.g. batteries, pacemakers, defibrillators, pumps).

  12. Sealing glasses for titanium and titanium alloys

    DOE Patents [OSTI]

    Brow, R.K.; McCollister, H.L.; Phifer, C.C.; Day, D.E.

    1997-07-15T23:59:59.000Z

    Barium lanthanoborate sealing-glass compositions are provided comprising various combinations (in terms of mole-%) of boron oxide (B{sub 2}O{sub 3}), barium oxide (BaO), lanthanum oxide (La{sub 2}O{sub 3}), and at least one other oxide selected from the group consisting of aluminum oxide (Al{sub 2}O{sub 3}), calcium oxide (CaO), lithium oxide (Li{sub 2}O), sodium oxide (Na{sub 2}O), silicon dioxide (SiO{sub 2}), or titanium dioxide (TiO{sub 2}). These sealing-glass compositions are useful for forming hermetic glass-to-metal seals with titanium and titanium alloys having an improved aqueous durability and favorable sealing characteristics. Examples of the sealing-glass compositions are provided having coefficients of thermal expansion about that of titanium or titanium alloys, and with sealing temperatures less than about 900 C, and generally about 700--800 C. The barium lanthanoborate sealing-glass compositions are useful for components and devices requiring prolonged exposure to moisture or water, and for implanted biomedical devices (e.g. batteries, pacemakers, defibrillators, pumps). 1 fig.

  13. Compliant Glass Seals for SOFC Stacks

    SciTech Connect (OSTI)

    Chou, Y. S.; Choi, Jung-Pyung; Xu, Wei; Stephens, Elizabeth V.; Koeppel, Brian J.; Stevenson, Jeffry W.; Lara-Curzio, Edgar

    2014-04-01T23:59:59.000Z

    This report summarizes results from experimental and modeling studies performed by participants in the Solid-State Energy Conversion Alliance (SECA) Core Technology Program, which indicate that compliant glass-based seals offer a number of potential advantages over conventional seals based on de-vitrifying glasses, including reduced stresses during stack operation and thermal cycling, and the ability to heal micro-damage induced during thermal cycling. The properties and composition of glasses developed and/or investigated in these studies are reported, along with results from long-term (up to 5,800h) evaluations of seals based on a compliant glass containing ceramic particles or ceramic fibers.

  14. Sealing apparatus for airfoils of gas turbine engines

    DOE Patents [OSTI]

    Jones, Russell B. (San Diego, CA)

    1998-01-01T23:59:59.000Z

    An improved airfoil tip sealing apparatus is disclosed wherein brush seals are attached to airfoil tips with the distal ends of the brush seal fibers sealingly contacting opposing wall surfaces. Embodiments for variable vanes, stators and both cooled and uncooled turbine blade applications are disclosed.

  15. Sealing apparatus for airfoils of gas turbine engines

    DOE Patents [OSTI]

    Jones, R.B.

    1998-05-19T23:59:59.000Z

    An improved airfoil tip sealing apparatus is disclosed wherein brush seals are attached to airfoil tips with the distal ends of the brush seal fibers sealingly contacting opposing wall surfaces. Embodiments for variable vanes, stators and both cooled and uncooled turbine blade applications are disclosed. 17 figs.

  16. Radioactive Waste Management (Minnesota)

    Broader source: Energy.gov [DOE]

    This section regulates the transportation and disposal of high-level radioactive waste in Minnesota, and establishes a Nuclear Waste Council to monitor the federal high-level radioactive waste...

  17. Testing of ethylene propylene seals for the GA-4/GA-9 casks

    SciTech Connect (OSTI)

    Boonstra, R.H.

    1993-08-01T23:59:59.000Z

    The primary O-ring seal of the GA-4 and GA-9 casks was tested for leakage with a full-scale mockup of the cask lid and flange. Tests were performed at temperatures of ambient, {minus}41{degrees}, 121{degrees}, and 193{degrees}C. Shim plates between the lid and flange simulated gaps caused by thermal distortion. The testing used a helium mass spectrometer leak detector (MSLD). Results showed that the primary seal was leaktight for all test conditions. Helium permeation through the seal began in 13--23 minutes for the ambient tests and in 1--2 minutes for the tests at elevated temperatures. After each test several hours of the pumping were typically required to reduce the MSLD background reading to an acceptable level for the next test, indicating that the seal had become saturated with helium. To verify that the test results showed permeation and not real leakage, several response checks were conducted in which a calibrated leak source was inserted in the detector line near the seal. When the leak source was activated the detector responded within seconds.

  18. Emergency sacrificial sealing method in filters, equipment, or systems

    DOE Patents [OSTI]

    Brown, Erik P

    2014-09-30T23:59:59.000Z

    A system seals a filter or equipment component to a base and will continue to seal the filter or equipment component to the base in the event of hot air or fire. The system includes a first sealing material between the filter or equipment component and the base; and a second sealing material between the filter or equipment component and the base and proximate the first sealing material. The first sealing material and the second seal material are positioned relative to each other and relative to the filter or equipment component and the base to seal the filter or equipment component to the base and upon the event of fire the second sealing material will be activated and expand to continue to seal the filter or equipment component to the base in the event of hot air or fire.

  19. Volume III, Chapter 18 Harbor Seals

    E-Print Network [OSTI]

    sand bars and mudflats in estuaries, intertidal rocks and reefs, sandy, cobble, and rocky beaches in Washington and Oregon by a state-financed population control programs that considered harbor seals

  20. Radioactive Materials License Commitments

    E-Print Network [OSTI]

    Radioactive Materials License Commitments for The University of Texas at Austin May 2009 July 2009 in the use of radioactive materials. In July 1963, the State of Texas granted The University of Texas at Austin a broad radioactive materials license for research, development and instruction. While this means

  1. Calculation of rotordynamic forces on labyrinth seals

    E-Print Network [OSTI]

    Hensel, Steve John

    1986-01-01T23:59:59.000Z

    CALCULATION OF ROTORDYNAMIC FORCES ON LABYRINTH SEALS A Thesis STEVE JOHN HENSEL Submitted to the Graduate College of Texas AkM University in partial fulfillment of the requirement for the degree of MASTER OF SCIENCE December 1986 Major... Subject: Mechanical Engineering CALCULATION OF ROTORDYNAMIC FORCES ON LABYRINTH SEALS A Thesis by STEVE JOHN HENSEL Approved as to style snd content by: David Rhode (Chairman of Committee) Erian Baskharone Leel and Garison (Member) +, gg, W. D...

  2. DEVELOPMENT OF A CERAMIC TAMPER INDICATING SEAL: SRNL CONTRIBUTIONS

    SciTech Connect (OSTI)

    Krementz, D.; Brinkman, K.; Martinez-Rodriguez, M.; Mendez-Torres, A.; Weeks, G.

    2013-06-03T23:59:59.000Z

    Savannah River National Laboratory (SRNL) and Sandia National Laboratories (SNL) are collaborating on development of a Ceramic Seal, also sometimes designated the Intrinsically Tamper Indicating Ceramic Seal (ITICS), which is a tamper indicating seal for international safeguards applications. The Ceramic Seal is designed to be a replacement for metal loop seals that are currently used by the IAEA and other safeguards organizations. The Ceramic Seal has numerous features that enhance the security of the seal, including a frangible ceramic body, protective and tamper indicating coatings, an intrinsic unique identifier using Laser Surface Authentication, electronics incorporated into the seal that provide cryptographic seal authentication, and user-friendly seal wire capture. A second generation prototype of the seal is currently under development whose seal body is of Low Temperature Co-fired Ceramic (LTCC) construction. SRNL has developed the mechanical design of the seal in an iterative process incorporating comments from the SNL vulnerability review team. SRNL is developing fluorescent tamper indicating coatings, with recent development focusing on optimizing the durability of the coatings and working with a vendor to develop a method to apply coatings on a 3-D surface. SRNL performed a study on the effects of radiation on the electronics of the seal and possible radiation shielding techniques to minimize the effects. SRNL is also investigating implementation of Laser Surface Authentication (LSA) as a means of unique identification of each seal and the effects of the surface coatings on the LSA signature.

  3. A numerical study of compressible flow in labyrinth seals with rub grooves

    E-Print Network [OSTI]

    Adams, Richard Gordon

    1997-01-01T23:59:59.000Z

    control volume, m 2 convection-diffusion coefficient mass source, kg/s seal clearance, mm turbulence model constant discharge coefficient coefficient of (hc pressurc-difference term rub groove depth, mm constant used in the law of the wall i9. 973...) rub groove width, mm stagnation enthalpy, specific turbulence kinetic energy, m /s 2 2 defined as 1/RT, characteristic length scale mass flow rate, kg/s number of teeth in a labyrinth seal pressure, MPa production of turbulence kmetic energy, m...

  4. Gas-lubricated seal for sealing between a piston and a cylinder wall

    DOE Patents [OSTI]

    Hoult, D.P.

    1985-09-10T23:59:59.000Z

    A piston-cylinder seal uses gas for a lubricant and has a runner supported on a gapless structure and placed in the space between the piston and the cylinder wall. The runner is deformed elastically under the influence of the operating pressures to follow and compensate for variations in the piston-cylinder fit and maintain a seal. 4 figs.

  5. Radioactive and chemotoxic wastes: Only radioactive wastes?

    SciTech Connect (OSTI)

    Eletti, G.F.; Tocci, M. [ENEA DISP, Rome (Italy)

    1993-12-31T23:59:59.000Z

    Radioactive waste arising from Italian Nuclear Power Plants and Research Centers, classified as 1st and 2nd Category wastes, are managed only as radioactive wastes following the Technical Guide No. 26 issued by the Italian Regulatory Body: ENEA DISP on 1987. A very important Regulatory Regime revision for Italian Nuclear Activities started at the end of 1991. This paper considers the need to develop a new strategy dedicated to mixed waste in line with current international trends.

  6. Rod seal device for Stirling engines

    SciTech Connect (OSTI)

    Kobayashi, D.; Itaba, T.; Momose, Y.

    1987-09-22T23:59:59.000Z

    A rod seal device for a Stirling engine is described which consists of: a piston rod having a first end connected to an operating piston for the engine and a second end connected to a guide piston disposed in a crank case; a compression chamber defined by the operating piston and a cylinder of the engine and including a working gas for the engine; a first intermediate chamber surrounding an outer periphery of the piston rod and being connected to the compression chamber and kept to maintain a minimum level of pressure of the working gas; a high pressure oil chamber disposed next to the first intermediate chamber and surrounding the outer periphery of the piston rod. A first low pressure oil chamber disposed next to the high pressure oil chamber via an oil seal member and surrounding the outer periphery of the piston rod. A first scraper seal disposed next to the first low pressure oil chamber and surrounding the outer periphery of the piston rod; a second intermediate chamber disposed next to the first low pressure oil chamber via the first scraper seal and surrounding the outer periphery of the piston rod; a second scraper seal disposed next to the second intermediate chamber and surrounding the outer periphery of the piston rod; a second low pressure oil chamber disposed next to the second intermediate chamber via the second scraper seal and surrounding the outer periphery of the piston rod, a second oil pump disposed between the second low pressure oil chamber and the second low pressure oil reservoir to positively discharge any gas introduced into the second low pressure oil chamber to the atmosphere; and a further oil seal disposed between the second low pressure oil chamber and a working gas chamber in the crank use for a power take-off device.

  7. Development of a Whole Container Seal

    SciTech Connect (OSTI)

    Kuhn, Michael J [ORNL] [ORNL; Pickett, Chris A [ORNL] [ORNL; Stinson, Brad J [ORNL] [ORNL; Rowe, Nathan C [ORNL] [ORNL

    2014-01-01T23:59:59.000Z

    This paper outlines a technique for utilizing electrically conductive textiles as a whole container seal. This method has the potential to provide more robustness for ensuring that the container has not been breached versus conventional sealing methods that only provide tamper indication at the area used for normal access. The conductive textile is used as a distributed sensor for detecting and localizing container tamper or breach. For sealing purposes, the conductive fabric represents a bounded, near-infinite grid of resistors. The well-known infinite resistance grid problem was used to model and confirm the expected accuracy and validity of this approach. An experimental setup was built that uses a multiplexed Wheatstone bridge measurement to determine the resistances of a coarse electrode grid across the conductive fabric. Non-uniform resistance values of the grid infer the presence of damage or tears in the fabric. Results suggest accuracy proportional to the electrode spacing in determining the presence and location of disturbances in conductive fabric samples. Current work is focused on constructing experimental prototypes for field and environmental testing to gauge the performance of these whole container seals in real world conditions. We are also developing software and hardware to interface with the whole container seals. The latest prototypes are expected to provide more accuracy in detecting and localizing events, although detection of a penetration should be adequate for most sealing applications. We are also developing smart sensing nodes that integrate digital hardware and additional sensors (e.g., motion, humidity) into the electrode nodes within the whole container seal.

  8. Solid oxide fuel cell having a glass composite seal

    DOE Patents [OSTI]

    De Rose, Anthony J.; Mukerjee, Subhasish; Haltiner, Jr., Karl Jacob

    2013-04-16T23:59:59.000Z

    A solid oxide fuel cell stack having a plurality of cassettes and a glass composite seal disposed between the sealing surfaces of adjacent cassettes, thereby joining the cassettes and providing a hermetic seal therebetween. The glass composite seal includes an alkaline earth aluminosilicate (AEAS) glass disposed about a viscous glass such that the AEAS glass retains the viscous glass in a predetermined position between the first and second sealing surfaces. The AEAS glass provides geometric stability to the glass composite seal to maintain the proper distance between the adjacent cassettes while the viscous glass provides for a compliant and self-healing seal. The glass composite seal may include fibers, powders, and/or beads of zirconium oxide, aluminum oxide, yttria-stabilized zirconia (YSZ), or mixtures thereof, to enhance the desirable properties of the glass composite seal.

  9. Mechanical seal having a single-piece, perforated mating ring

    DOE Patents [OSTI]

    Khonsari, Michael M. (Baton Rouge, LA); Somanchi, Anoop K. (Fremont, CA)

    2007-08-07T23:59:59.000Z

    A mechanical seal (e.g., single mechanical seals, double mechanical seals, tandem mechanical seals, bellows, pusher mechanical seals, and all types of rotating and reciprocating machines) with reduced contact surface temperature, reduced contact surface wear, or increased life span. The mechanical seal comprises a rotating ring and a single-piece, perforated mating ring, which improves heat transfer by controllably channeling coolant flow through the single-piece mating ring such that the coolant is in substantially uniform thermal contact with a substantial portion of the interior surface area of the seal face, while maintaining the structural integrity of the mechanical seal and minimizing the potential for coolant flow interruptions to the seal face caused by debris or contaminants (e.g., small solids and trash) in the coolant.

  10. Repatriation of US sources from Brazil

    SciTech Connect (OSTI)

    Tompkins, Andrew J [Los Alamos National Laboratory

    2008-01-01T23:59:59.000Z

    IAEA's interest in excess and unwanted sealed sources extends back to when radium sources were a problem throughout the world. Sta11ing in 1994, world wide IAEA member states inventoried and consolidated radium (Ra)-226 sources. IAEA then trained Regional Teams in the conditioning of Ra-226 sealed sources for long term storage, which resulted in the Regional Teams conditioning about 14,000 radium sources. These sources remained in their respective IAEA member state locations. Regional teams were seen as a way to encourage member state (local) management of a world wide problem, as well as a more cost effective solution.

  11. Seal assembly with anti-rotation pin for high pressure supercritical fluids

    DOE Patents [OSTI]

    Wright, Steven A.; Fuller, Robert L.

    2014-08-05T23:59:59.000Z

    A seal assembly for sealing a machine with a first chamber and a second chamber is provided. A rotating shaft extends through the first and second chambers, and rotates therein. The seal assembly has a seal housing, a seal ring and a seal pin. The seal housing is positionable in the machine housing. The seal housing has a seal pocket extending into a fluid side thereof, and a housing receptacle extending into an inner diameter thereof at the seal pocket. The seal ring is positionable in the seal pocket of the seal housing for forming a seal therewith. The seal ring has a ring receptacle extending into an outer diameter thereof. The ring receptacle is positionable adjacent to the housing receptacle for defining a pin hole therebetween. The seal pin is loosely positionable in the pin hole whereby movement about the seal ring is accommodated while preventing rotation thereof.

  12. Magnetron sputtering source

    DOE Patents [OSTI]

    Makowiecki, Daniel M. (Livermore, WA); McKernan, Mark A. (Livermore, CA); Grabner, R. Fred (Brentwood, CA); Ramsey, Philip B. (Livermore, CA)

    1994-01-01T23:59:59.000Z

    A magnetron sputtering source for sputtering coating substrates includes a high thermal conductivity electrically insulating ceramic and magnetically attached sputter target which can eliminate vacuum sealing and direct fluid cooling of the cathode assembly. The magnetron sputtering source design results in greater compactness, improved operating characteristics, greater versatility, and low fabrication cost. The design easily retrofits most sputtering apparatuses and provides for safe, easy, and cost effective target replacement, installation, and removal.

  13. Magnetron sputtering source

    DOE Patents [OSTI]

    Makowiecki, D.M.; McKernan, M.A.; Grabner, R.F.; Ramsey, P.B.

    1994-08-02T23:59:59.000Z

    A magnetron sputtering source for sputtering coating substrates includes a high thermal conductivity electrically insulating ceramic and magnetically attached sputter target which can eliminate vacuum sealing and direct fluid cooling of the cathode assembly. The magnetron sputtering source design results in greater compactness, improved operating characteristics, greater versatility, and low fabrication cost. The design easily retrofits most sputtering apparatuses and provides for safe, easy, and cost effective target replacement, installation, and removal. 12 figs.

  14. Radioactive Waste Management Basis

    SciTech Connect (OSTI)

    Perkins, B K

    2009-06-03T23:59:59.000Z

    The purpose of this Radioactive Waste Management Basis is to describe the systematic approach for planning, executing, and evaluating the management of radioactive waste at LLNL. The implementation of this document will ensure that waste management activities at LLNL are conducted in compliance with the requirements of DOE Order 435.1, Radioactive Waste Management, and the Implementation Guide for DOE Manual 435.1-1, Radioactive Waste Management Manual. Technical justification is provided where methods for meeting the requirements of DOE Order 435.1 deviate from the DOE Manual 435.1-1 and Implementation Guide.

  15. Thin californium-containing radioactive source wires

    DOE Patents [OSTI]

    Gross, Ian G (Clinton, TN); Pierce, Larry A (Kingston, TN)

    2012-01-03T23:59:59.000Z

    A cermet wire includes at least 1% californium-252 and is characterized by a diameter of no more than 0.0225 inch.

  16. Naturally Occurring Radioactive Materials in Cargo at US Borders

    SciTech Connect (OSTI)

    Kouzes, Richard T.; Ely, James H.; Evans, John C.; Hensley, Walter K.; Lepel, Elwood A.; McDonald, Joseph C.; Schweppe, John E.; Siciliano, Edward R.; Strom, Daniel J.; Woodring, Mitchell L.

    2006-01-01T23:59:59.000Z

    In the U.S. and other countries, large numbers of vehicles pass through border crossings each day. The illicit movement of radioactive sources is a concern that has resulted in the installation of radiation detection and identification instruments at border crossing points. This activity is judged to be necessary because of the possibility of an act of terrorism involving a radioactive source that may include any number of dangerous radionuclides. The problem of detecting, identifying, and interdicting illicit radioactive sources is complicated by the fact that many materials present in cargo are somewhat radioactive. Some cargo contains naturally occurring radioactive material or technologically-enhanced naturally occurring radioactive material that may trigger radiation portal monitor alarms. Man-made radioactive sources, especially medical isotopes, are also frequently observed and produce alarms. Such nuisance alarms can be an operational limiting factor for screening of cargo at border crossings. Information about the nature of the radioactive materials in cargo that can interfere with the detection of radionuclides of concern is necessary. This paper provides such information for North American cargo, but the information may also be of use to border control officials in other countries. (PIET-43741-TM-361)

  17. Microsoft Word - SealedSources - Cover.doc

    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 offOCHCO2:Introduction toManagement of the National NuclearRegulation;I I4-15Follow-upFORASU.S.

  18. A comparison of experimental and theoretical results for labyrinth gas seals with honeycomb stators

    E-Print Network [OSTI]

    Hawkins, Lawrence Allen

    1988-01-01T23:59:59.000Z

    stator seal correctly within 25% of measured values. The model provides accurate predictions of direct damping for large clearance seals. Overall, the model does not perform as well for low clearance seals as for high clearance seals. lv TABLE...

  19. Cosmic radioactivity and INTEGRAL results

    SciTech Connect (OSTI)

    Diehl, Roland [Max Planck Institut für Extraterrestrische Physik, D-85748 Garching, Germany and Excellence Cluster Origin and Evolution of the Universe', D-85748 Garching (Germany)

    2014-05-02T23:59:59.000Z

    Gamma-ray lines from radioactive decay of unstable isotopes co-produced by nucleosynthesis in massive stars and supernova have been measured since more than thirty years. Over the past ten years, INTEGRAL complemented the first sky survey made by COMPTEL. The {sup 26}A1 isotope with 1 My decay time had been first direct proof of currently-ongoing nucleosynthesis in our Galaxy. This has now become a tool to study the ?My history of specific source regions, such as massive-star groups and associations in nearby regions which can be discriminated from the galactic-plane background, and the inner Galaxy, where Doppler shifted lines add to the astronomical information about bar and spiral structure. Recent findings suggest that superbubbles show a remarkable asymmetry, on average, in the spiral arms of our galaxy. {sup 60}Fe is co-produced by the sources of {sup 26}A1, and the isotopic ratio from their nucleosynthesis encodes stellar-structure information. Annihilation gamma-rays from positrons in interstellar space show a puzzling bright and extended source region central to our Galaxy, but also may be partly related to nucleosynthesis. {sup 56}Ni and {sup 44}Ti isotope gamma-rays have been used to constrain supernova explosion mechanisms. Here we report latest results using the accumulated multi-year database of INTEGRAL observations, and discuss their astrophysical interpretations, connecting to other traces of cosmic radioactivity and to other cosmic messengers.

  20. Bentonite as a waste isolation pilot plant shaft sealing material

    SciTech Connect (OSTI)

    Daemen, J.; Ran, Chongwei [Univ. of Nevada, Reno, NV (United States)

    1996-12-01T23:59:59.000Z

    Current designs of the shaft sealing system for the Waste Isolation Pilot Plant (WIPP) propose using bentonite as a primary sealing component. The shaft sealing designs anticipate that compacted bentonite sealing components can perform through the 10,000-year regulatory period and beyond. To evaluate the acceptability of bentonite as a sealing material for the WIPP, this report identifies references that deal with the properties and characteristics of bentonite that may affect its behavior in the WIPP environment. This report reviews published studies that discuss using bentonite as sealing material for nuclear waste disposal, environmental restoration, toxic and chemical waste disposal, landfill liners, and applications in the petroleum industry. This report identifies the physical and chemical properties, stability and seal construction technologies of bentonite seals in shafts, especially in a saline brine environment. This report focuses on permeability, swelling pressure, strength, stiffness, longevity, and densification properties of bentonites.

  1. Leakage Prediction of Labyrinth Seals Having Advanced Cavity Shapes

    E-Print Network [OSTI]

    Panicker, Sunil M.

    2011-02-22T23:59:59.000Z

    Labyrinth seals are widely used in various turbo machines including turbines, compressors and pumps. Their purpose is to prevent the backflow of the working fluid. This backflow is due to the leakage of the seal. This loss affects the efficiency...

  2. Flow visualization and leakage measurements of worn labyrinth seals

    E-Print Network [OSTI]

    Allen, Brian Frank

    1997-01-01T23:59:59.000Z

    A large-scale flow visualization test facility is used to conduct an experimental investigation into the leakage resistance and flow characteristics of worn labyrinth seals. Wear in labyrinth seals is a consequence of contact between the rotating...

  3. High Temperature Leakage Performance of a Hybrid Brush Seal Compared to a Standard Brush Seal and a Labyrinth Seal

    E-Print Network [OSTI]

    Ashton, Zachary

    2010-01-14T23:59:59.000Z

    design that adds to the bristle brush matrix a number of cantilever pads that rest on the rotor surface. Upon shaft rotation the pads lift due to the generation of a hydrodynamic gas film while the brushes effectively seal an upstream pressure. Hence...

  4. AGING PERFORMANCE OF VITON GLT O-RINGS IN RADIOACTIVE MATERIAL PACKAGES

    SciTech Connect (OSTI)

    Skidmore, E; Kerry Dunn, K; Elizabeth Hoffman, E; Elise Fox, E; Kathryn Counts, K

    2007-05-07T23:59:59.000Z

    Radioactive material packages used for transportation of plutonium-bearing materials often contain multiple O-ring seals for containment. Packages such as the Model 9975 are also being used for interim storage of Pu-bearing materials at the Savannah River Site (SRS). One of the seal materials used in such packages is Viton{reg_sign} GLT fluoroelastomer. The aging behavior of containment vessel O-rings based on Viton{reg_sign} GLT at long-term containment term storage conditions is being characterized to assess its performance in such applications. This paper summarizes the program and test results to date.

  5. Rotordynamic characteritics of incompressible-flow labyrinth seals

    E-Print Network [OSTI]

    Ghali, Anupama

    1993-01-01T23:59:59.000Z

    ) . Parsons (1938) was apparently the first to introduce the labyrinth seal in his development of a steam turbine near the turn of the century The objective of the seal is to create a highly frictional flow path between high-pressure and low... to point out the unstable vibrations due to labyrinth seals. He discovered that the circumferential variation of pressure in the labyrinth seal caused excitation forces, which in turn were responsible for the rotor whirl in axial compressors...

  6. Type B package for the transport of large medical and industrial sources

    SciTech Connect (OSTI)

    Brown, Darrell Dwaine [Los Alamos National Laboratory; Noss, Philip W [AREVA FEDERAL SERVICES

    2010-09-14T23:59:59.000Z

    AREVA Federal Services LLC, under contract to the Los Alamos National Laboratory's Offsite Source Recovery Project, is developing a new Type B(U)-96 package for the transport of unwanted or abandoned high activity gamma and neutron radioactive sealed sources (sources). The sources were used primarily in medical or industrial devices, and are of domestic (USA) or foreign origin. To promote public safety and mitigate the possibility of loss or misuse, the Offsite Source Recovery Project is recovering and managing sources worldwide. The package, denoted the LANL-B, is designed to accommodate the sources within an internal gamma shield. The sources are located either in the IAEA's Long Term Storage Shield (LTSS), or within intact medical or industrial irradiation devices. As the sources are already shielded separately, the package does not include any shielding of its own. A particular challenge in the design of the LANL-B has been weight. Since the LTSS shield weighs approximately 5,000 lb [2,270 kg], and the total package gross weight must be limited to 10,000 lb [4,540 kg], the net weight of the package was limited to 5,000 lb, for an efficiency of 50% (i.e., the payload weight is 50% of the gross weight of the package). This required implementation of a light-weight bell-jar concept, in which the containment takes the form of a vertical bell which is bolted to a base. A single impact limiter is used on the bottom, to protect the elastomer seals and bolted joint. A top-end impact is mitigated by the deformation of a tori spherically-shaped head. Impacts in various orientations on the bottom end are mitigated by a cylindrical, polyurethane foam-filled impact limiter. Internally, energy is absorbed using honeycomb blocks at each end, which fill the torispherical head volumes. As many of the sources are considered to be in normal form, the LANL-B package offers leak-tight containment using an elastomer seal at the joint between the bell and the base, as well as on the single vent port. Leak testing prior to transport may be either using helium mass spectrometry or the pressure-rise concept.

  7. Welding/sealing glass-enclosed space in a vacuum

    DOE Patents [OSTI]

    Tracy, C. Edwin (Golden, CO); Benson, David K. (Golden, CO)

    1996-01-01T23:59:59.000Z

    A method of welding and sealing the edges of two juxtaposed glass sheets together to seal a vacuum space between the sheets comprises the steps of positioning a radiation absorbant material, such as FeO, VO.sub.2, or NiO, between the radiation transmissive glass sheets adjacent the edges and then irradiating the absorbant material, preferably with a laser beam, through at least one of the glass sheets. Heat produced by the absorbed radiation in the absorbant material melts glass in the portions of both glass sheets that are adjacent the absorbant material, and the melted glass from both sheets flows together to create the weld when the melted glass cools and hardens. The absorbant material can be dissolved and diffused into the melted glass to the extent that it no longer absorbs enough energy to keep the glass melted, thus, with appropriate proportioning of absorbant material to source energy power and welding heat needed, the process can be made self-stopping.

  8. Welding/sealing glass-enclosed space in a vacuum

    DOE Patents [OSTI]

    Tracy, C.E.; Benson, D.K.

    1996-02-06T23:59:59.000Z

    A method of welding and sealing the edges of two juxtaposed glass sheets together to seal a vacuum space between the sheets comprises the steps of positioning a radiation absorbent material, such as FeO, VO{sub 2}, or NiO, between the radiation transmissive glass sheets adjacent the edges and then irradiating the absorbent material, preferably with a laser beam, through at least one of the glass sheets. Heat produced by the absorbed radiation in the absorbent material melts glass in the portions of both glass sheets that are adjacent the absorbent material, and the melted glass from both sheets flows together to create the weld when the melted glass cools and hardens. The absorbent material can be dissolved and diffused into the melted glass to the extent that it no longer absorbs enough energy to keep the glass melted, thus, with appropriate proportioning of absorbent material to source energy power and welding heat needed, the process can be made self-stopping. 8 figs.

  9. High-level radioactive wastes. Supplement 1

    SciTech Connect (OSTI)

    McLaren, L.H. (ed.)

    1984-09-01T23:59:59.000Z

    This bibliography contains information on high-level radioactive wastes included in the Department of Energy's Energy Data Base from August 1982 through December 1983. These citations are to research reports, journal articles, books, patents, theses, and conference papers from worldwide sources. Five indexes, each preceded by a brief description, are provided: Corporate Author, Personal Author, Subject, Contract Number, and Report Number. 1452 citations.

  10. Flat-to-Flat Solder Seal Andrey Elagin1

    E-Print Network [OSTI]

    To practice 8x8" seals we start from good parts with no scavenging Cu Scavenging Problem #12;11 Seal #1 A complete LAPPD glass tile except for an aluminum photo-cathode top seal by compression on a viton o Recipe for Ceramic Package Copper well is brazed into the ceramic body and filled with indium alloy (In

  11. Experimental rotordynamic coefficient results for: (a) a labyrinth seal with and without shunt injection and (b) a honeycomb seal

    E-Print Network [OSTI]

    Soto Azuaje, Elias Antonio

    1997-01-01T23:59:59.000Z

    the best flow control, and the labyrinth seals with shunt injection the worst. For low and medium running speed, and most conditions, the labyrinth seal with injection against rotation has the best rotordynamic stability followed in order by the honeycomb...

  12. Analytical and experimental investigations of a labyrinth seal test rig and damper seals for turbomachinery

    E-Print Network [OSTI]

    Shultz, Richard Raymond

    1997-01-01T23:59:59.000Z

    applications is discussed. The direct damping coefficients of the shaft seals are determined experimentally by processing measured displacement vibration impact response data with an equivalent single degree of freedom model of the cantilever beam test rig...

  13. Seals and Sealing Practices: The Ancient Near East and Bronze Age Aegean

    E-Print Network [OSTI]

    Younger, John G.

    1996-01-01T23:59:59.000Z

    This review article summarizes first the achievements of the Corpus der minoischen und mykenischen Siegel, and then what is known about early administration and sealing practices in the prehistoric Aegean and Near East....

  14. Measure Guideline: Guide to Attic Air Sealing

    SciTech Connect (OSTI)

    Lstiburek, J.

    2014-09-01T23:59:59.000Z

    The Guide to Attic Air Sealing was completed in 2010 and although not in the standard Measure Guideline format, is intended to be a Measure Guideline on Attic Air Sealing. The guide was reviewed during two industry stakeholders meetings held on December 18th, 2009 and January 15th, 2010, and modified based on the comments received. Please do not make comments on the Building America format of this document. The purpose of the Guide to Attic Air Sealing is to provide information and recommendations for the preparation work necessary prior to adding attic insulation. Even though the purpose of this guide is to save energy - health, safety and durability should not be compromised by energy efficiency. Accordingly, combustion safety and ventilation for indoor air quality are addressed first. Durability and attic ventilation then follow. Finally, to maximize energy savings, air sealing is completed prior to insulating. The guide is intended for home remodelers, builders, insulation contractors, mechanical contractors, general contractors who have previously done remodeling and homeowners as a guide to the work that needs to be done.

  15. Positive contact, self retaining bearing seals

    DOE Patents [OSTI]

    Johnson, Bruce H. (Kansas City, MO); Larsen, Lawrence E. (Kansas City, MO); Welch, Edmund F. (Kansas City, MO)

    1992-05-05T23:59:59.000Z

    An ultra-low friction bearing including an inner race, an outer race, bearing elements engaged between the inner and outer races and a seal between the inner and outer races is disclosed. The seal includes first and second sealing washers. The first washer has an outer diameter greater than an inner diameter of the outer race and an inner diameter greater than the outer diameter of the inner race. The second washer has an inner diameter less than the outer diameter of the inner race and an outer diameter less than the inner diameter of the outer race. The first washer slidably engages the outer race, the second washer slidably engages the inner race and the washers overlap and slidably engage one another. One of the washers snap fits into its respective inner or outer race while the other washer engages a stepped surface of the other of the inner and outer races. The grooved and stepped surface are offset from one another in a longitudinal direction of the races such that the washers are conically loaded thus providing a seal between the inner and outer races sufficient to prevent lubricant and contaminating particles from passing therethrough. The washers are made from a non-metallic semi-flexible low-modulus material.

  16. Managing an Effective Leak Sealing Program

    E-Print Network [OSTI]

    Rinz, W. H.

    1980-01-01T23:59:59.000Z

    An on-line leak sealing program is an extremely effective method of cost savings to industrial plants. The dollars a plant saves can be direct and dramatic as in an avoided system shut-down or subtle and analytical as in a long term maintenance...

  17. Angel wing seals for blades of a gas turbine and methods for determining angel wing seal profiles

    DOE Patents [OSTI]

    Wang, John Zhiqiang (Greenville, SC)

    2003-01-01T23:59:59.000Z

    A gas turbine has buckets rotatable about an axis, the buckets having angel wing seals. The seals have outer and inner surfaces, at least one of which, and preferably both, extend non-linearly between root radii and the tip of the seal body. The profiles are determined in a manner to minimize the weight of the seal bodies, while maintaining the stresses below predetermined maximum or allowable stresses.

  18. RADIOACTIVE WASTE DISPOSAL IN GRANITE

    E-Print Network [OSTI]

    Witherspoon, P.A.

    2010-01-01T23:59:59.000Z

    RADIOACTIVE WASTE DISPOSAL IN GRANITE Paul A. WitherspoonRADIOACTIVE WASTE DISPOSAL IN GRANITE Paul A. Wither spoona repository site in granite are to evaluate the suitability

  19. Sealed vacuum canister and method for pick-up and containment of material

    DOE Patents [OSTI]

    Stoutenburgh, R.R.

    1996-02-13T23:59:59.000Z

    A vacuum canister is described including a housing with a sealed vacuum chamber having a predetermined vacuum pressure therein and a valve having a first port for fluid communication with the vacuum chamber and a second port for receiving at least one of a fluid and a particulate material. The valve is operable between a first position to seal the vacuum chamber and retain the predetermined vacuum within the vacuum chamber, and a second position to access the vacuum chamber to permit vacuum fluid flow through the valve from the second port into the vacuum chamber. The vacuum canister, in the operation to pick up material with the valve in the second position, when the second port is located adjacent at least one of a fluid and a particulate material, is effective to displace through the valve at least one of a fluid and a particulate material into the housing. The vacuum canister is desirably suitable for picking up and containing hazardous material such as radioactive material, in which the vacuum canister includes a protective layer of lead having a predetermined thickness that is effective to shield radiation emitted from the radioactive material contained within the housing. Advantageously, the vacuum canister includes a vacuum means for establishing a predetermined vacuum pressure within the vacuum chamber. 6 figs.

  20. Sealed vacuum canister and method for pick-up and containment of material

    DOE Patents [OSTI]

    Stoutenburgh, Roger R. (Cutchogue, NY)

    1996-01-01T23:59:59.000Z

    A vacuum canister including a housing with a sealed vacuum chamber having a predetermined vacuum pressure therein and a valve having a first port for fluid communication with the vacuum chamber and a second port for receiving at least one of a fluid and a particulate material. The valve is operable between a first position to seal the vacuum chamber and retain the predetermined vacuum within the vacuum chamber, and a second position to access the vacuum chamber to permit vacuum fluid flow through the valve from the second port into the vacuum chamber. In operation of the vacuum canister to pick up material with the valve in the second position, when the second port is located adjacent at least one of a fluid and a particulate material, is effective to displace through the valve at least one of a fluid and a particulate material into the housing. The vacuum canister is desirably suitable for picking up and containing hazardous material such as radioactive material, in which the vacuum canister includes a protective layer of lead having a predetermined thickness that is effective to shield radiation emitted from the radioactive material contained within the housing. Advantageously, the vacuum canister includes a vacuum means for establishing a predetermined vacuum pressure within the vacuum chamber.

  1. DEVELOPMENT OF A ROTARY MICROFILTER FOR RADIOACTIVE WASTE APPLICATIONS

    SciTech Connect (OSTI)

    Poirier, M; David Herman, D; Samuel Fink, S

    2008-02-25T23:59:59.000Z

    The processing rate of Savannah River Site (SRS) high-level waste decontamination processes are limited by the flow rate of the solid-liquid separation. The baseline process, using a 0.1 micron cross-flow filter, produces {approx}0.02 gpm/sq. ft. of filtrate under expected operating conditions. Savannah River National Laboratory (SRNL) demonstrated significantly higher filter flux for actual waste samples using a small-scale rotary filter. With funding from the U. S. Department of Energy Office of Cleanup Technology, SRNL personnel are evaluating and developing the rotary microfilter for radioactive service at SRS. The authors improved the design for the disks and filter unit to make them suitable for high-level radioactive service. They procured two units using the new design, tested them with simulated SRS wastes, and evaluated the operation of the units. Work to date provides the following conclusions and program status: (1) The authors modified the design of the filter disks to remove epoxy and Ryton{reg_sign}. The new design includes welding both stainless steel and ceramic coated stainless steel filter media to a stainless steel support plate. The welded disks were tested in the full-scale unit. They showed good reliability and met filtrate quality requirements. (2) The authors modified the design of the unit, making installation and removal easier. The new design uses a modular, one-piece filter stack that is removed simply by disassembly of a flange on the upper (inlet) side of the filter housing. All seals and rotary unions are contained within the removable stack. (3) While it is extremely difficult to predict the life of the seal, the vendor representative indicates a minimum of one year in present service conditions is reasonable. Changing the seal face material from silicon-carbide to a graphite-impregnated silicon-carbide is expected to double the life of the seal. Replacement of the current seal with an air seal could increase the lifetime to 5 years and is undergoing testing in the current work. (4) The bottom bushing showed wear due to a misalignment during the manufacture of the filter tank. Replacing the graphite bushing with a more wear resistant material such as a carbide material will increase the lifetime of the bushing. This replacement requires a more wear resistant part or coating to prevent excessive wear of the shaft. The authors are currently conducting testing with the more wear resistant bushing. (5) The project team plans to use the rotary microfilter as a filter in advance of an ion exchange process under development for potential deployment in SRS waste tank risers.

  2. Skew And Twist Resistant Hydrodynamic Rotary Shaft Seal

    DOE Patents [OSTI]

    Dietle, Lannie (Sugar Land, TX); Kalsi, Manmohan Singh (Houston, TX)

    2000-03-14T23:59:59.000Z

    A hydrodynamically lubricated squeeze packing type rotary shaft seal suitable for lubricant retention and environmental exclusion which incorporates one or more resilient protuberances which and cooperate with the gland walls to hold the seal straight in its installation groove in unpressurized and low pressure lubricant retention applications thereby preventing skew-induced wear caused by impingement of abrasive contaminants present in the environment, and which also serve as radial bearings to prevent tipping of the seal within its installation gland. Compared to prior art, this invention provides a dramatic reduction of seal and shaft wear in abrasive environments and provides a significant increase in seal life.

  3. Radioactive Waste Management Manual

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

    1999-07-09T23:59:59.000Z

    This Manual further describes the requirements and establishes specific responsibilities for implementing DOE O 435.1, Radioactive Waste Management, for the management of DOE high-level waste, transuranic waste, low-level waste, and the radioactive component of mixed waste. The purpose of the Manual is to catalog those procedural requirements and existing practices that ensure that all DOE elements and contractors continue to manage DOE's radioactive waste in a manner that is protective of worker and public health and safety, and the environment. Does not cancel other directives.

  4. Pressure seals - Implications for deep gas exploration in Anadarko basin

    SciTech Connect (OSTI)

    Tigert, V.A.; Al-Shaieb, Z. (Oklahoma State Univ., Stillwater (USA))

    1989-08-01T23:59:59.000Z

    Pressure seals are economically significant geological phenomena because they play an important role in deep natural gas entrapment. Pressure seals identified in basins worldwide may offer a new frontier for exploring natural gas reservoirs below {minus} 10,000 ft. Pressure seals are low-permeability envelopes that enclose abnormally pressured internal reservoirs. There are three different types of seals: basal, lateral, and top planar. Basal seals define the bottom of abnormal pressure compartments and usually follow a stratigraphic horizon. Lateral seals are usually associated with fault patterns. Top planar seals may cut across time-stratigraphic boundaries, different lithologies, and structures, and are by far the most significant type. The southeastern portion of the Anadarko basin in the Mill Creek graben area displays a layered sequence of abnormally pressured fluid compartments between {minus} 3,000 and {minus} minus 16,000 ft. These compartments are separated from each other as well as from overlying and underlying normal pressure zones by pressure seals. In McClain County, a top planar pressure seal separating two abnormal pressured compartments is located between {minus} 11,000 and {minus} 12,000 ft within the Simpson Group. Diagenetic signatures identified in the seal zone are characterized by carbonate and/or silica cemented intervals alternating with more porous and permeable units generating distinctive banded and/or laminated structures, coined zebra structures. The resulting compositional and textural heterogeneity of the Simpson sandstones may be related to diagenetic modification that occurred during the seal evolution.

  5. Method of assembling and sealing an alkali metal battery

    DOE Patents [OSTI]

    Elkins, P.E.; Bell, J.E.; Harlow, R.A.; Chase, G.G.

    1983-03-01T23:59:59.000Z

    A method of initially assembling and then subsequently hermetically sealing a container portion of an alkali metal battery to a ceramic portion of such a battery is disclosed. Sealing surfaces are formed respectively on a container portion and a ceramic portion of an alkali metal battery. These sealing surfaces are brought into juxtaposition and a material is interposed there between. This interposed material is one which will diffuse into sealing relationship with both the container portion and the ceramic portion of the alkali metal battery at operational temperatures of such a battery. A pressure is applied between these sealing surfaces to cause the interposed material to be brought into intimate physical contact with such juxtaposed surfaces. A temporary sealing material which will provide a seal against a flow of alkali metal battery reactants there through at room temperatures and is applied over the juxtaposed sealing surfaces and material interposed there between. The entire assembly is heated to an operational temperature so that the interposed material diffuses into the container portion and the ceramic portion to form a hermetic seal there between. The pressure applied to the juxtaposed sealing surfaces is maintained in order to ensure the continuation of the hermetic seal. 4 figs.

  6. Method of making hermetic seals for hermetic terminal assemblies

    DOE Patents [OSTI]

    Hsu, John S.; Marlino, Laura D.; Ayers, Curtis W.

    2010-04-13T23:59:59.000Z

    This invention teaches methods of making a hermetic terminal assembly comprising the steps of: inserting temporary stops, shims and jigs on the bottom face of a terminal assembly thereby blocking assembly core open passageways; mounting the terminal assembly inside a vacuum chamber using a temporary assembly perimeter seal and flange or threaded assembly interfaces; mixing a seal admixture and hardener in a mixer conveyor to form a polymer seal material; conveying the polymer seal material into a polymer reservoir; feeding the polymer seal material from the reservoir through a polymer outlet valve and at least one polymer outlet tube into the terminal assembly core thereby filling interstitial spaces in the core adjacent to service conduits, temporary stop, and the terminal assembly casing; drying the polymer seal material at room temperature thereby hermetically sealing the core of the terminal assembly; removing the terminal assembly from the vacuum chamber, and; removing the temporary stops, shims.

  7. Gas Seal Leakage at High Temperature: A Labyrinth Seal and an All-Metal Complaint Seal of Similar Clearance

    E-Print Network [OSTI]

    Anderson, Alain

    2013-07-31T23:59:59.000Z

    ] D Rotor diameter [m] F Axial load [N] HID Housing inner diameter [m] i Current [A] kV? V/ ?. Motor constant [V/(rad/s)] l Seal axial length [m] ? Mass flow rate [kg/s] ? iV. Motor electrical power [W] Pa Air absolute ambient pressure [Pa... function [(J/(kg-K))0.5] ? ? . Density [kg/m 3] ? Rotor angular speed [rad/s] vi TABLE OF CONTENTS...

  8. Understanding radioactive waste

    SciTech Connect (OSTI)

    Murray, R.L.

    1981-12-01T23:59:59.000Z

    This document contains information on all aspects of radioactive wastes. Facts are presented about radioactive wastes simply, clearly and in an unbiased manner which makes the information readily accessible to the interested public. The contents are as follows: questions and concerns about wastes; atoms and chemistry; radioactivity; kinds of radiation; biological effects of radiation; radiation standards and protection; fission and fission products; the Manhattan Project; defense and development; uses of isotopes and radiation; classification of wastes; spent fuels from nuclear reactors; storage of spent fuel; reprocessing, recycling, and resources; uranium mill tailings; low-level wastes; transportation; methods of handling high-level nuclear wastes; project salt vault; multiple barrier approach; research on waste isolation; legal requiremnts; the national waste management program; societal aspects of radioactive wastes; perspectives; glossary; appendix A (scientific American articles); appendix B (reference material on wastes). (ATT)

  9. Apparatus for safeguarding a radiological source

    DOE Patents [OSTI]

    Bzorgi, Fariborz M

    2014-10-07T23:59:59.000Z

    A tamper detector is provided for safeguarding a radiological source that is moved into and out of a storage location through an access porthole for storage and use. The radiological source is presumed to have an associated shipping container approved by the U.S. Nuclear Regulatory Commission for transporting the radiological source. The tamper detector typically includes a network of sealed tubing that spans at least a portion of the access porthole. There is an opening in the network of sealed tubing that is large enough for passage therethrough of the radiological source and small enough to prevent passage therethrough of the associated shipping cask. Generally a gas source connector is provided for establishing a gas pressure in the network of sealed tubing, and a pressure drop sensor is provided for detecting a drop in the gas pressure below a preset value.

  10. Radioactive Waste Management Manual

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

    1999-07-09T23:59:59.000Z

    This Manual further describes the requirements and establishes specific responsibilities for implementing DOE O 435.1, Radioactive Waste Management, for the management of DOE high-level waste, transuranic waste, low-level waste, and the radioactive component of mixed waste. Change 1 dated 6/19/01 removes the requirement that Headquarters is to be notified and the Office of Environment, Safety and Health consulted for exemptions for use of non-DOE treatment facilities. Certified 1-9-07.

  11. High expansion, lithium corrosion resistant sealing glasses

    DOE Patents [OSTI]

    Brow, Richard K. (Albuquerque, NM); Watkins, Randall D. (Albuquerque, NM)

    1991-01-01T23:59:59.000Z

    Glass compositions containing CaO, Al.sub.2 O.sub.3, B.sub.2 O.sub.3, SrO and BaO in various combinations of mole % are provided. These compositions are capable of forming stable glass-to-metal seals with pin materials of 446 Stainless Steel and Alloy-52 rather than molybdenum, for use in harsh chemical environments, specifically in lithium batteries.

  12. High expansion, lithium corrosion resistant sealing glasses

    DOE Patents [OSTI]

    Brow, R.K.; Watkins, R.D.

    1991-06-04T23:59:59.000Z

    Glass compositions containing CaO, Al[sub 2]O[sub 3], B[sub 2]O[sub 3], SrO and BaO in various combinations of mole % are provided. These compositions are capable of forming stable glass-to-metal seals with pin materials of 446 Stainless Steel and Alloy-52 rather than molybdenum, for use in harsh chemical environments, specifically in lithium batteries.

  13. Innovative Seals for Solid Oxide Fuel Cells (SOFC)

    SciTech Connect (OSTI)

    Singh, Raj

    2008-06-30T23:59:59.000Z

    A functioning SOFC requires different type of seals such as metal-metal, metal-ceramic, and ceramic-ceramic. These seals must function at high temperatures between 600--900{sup o}C and in oxidizing and reducing environments of the fuels and air. Among the different type of seals, the metal-metal seals can be readily fabricated using metal joining, soldering, and brazing techniques. However, the metal-ceramic and ceramic-ceramic seals require significant research and development because the brittle nature of ceramics/glasses can lead to fracture and loss of seal integrity and functionality. Consequently, any seals involving ceramics/glasses require a significant attention and technology development for reliable SOFC operation. This final report is prepared to describe the progress made in the program on the needs, approaches, and performance of high temperature seals for SOFC. In particular, a new concept of self-healing glass seals is pursued for making seals between metal-ceramic material combinations, including some with a significant expansion mismatch.

  14. Dealing with a fast changing environment: the trophic ecology of the southern elephant seal (Mirounga leonina) and crabeater seal (Lobodon carcinophaga) in the western Antarctica Peninsula

    E-Print Network [OSTI]

    Huckstadt, Luis Alfredo

    2012-01-01T23:59:59.000Z

    elephant seals from Patagonia. Marine Mammal Science 26:430-juvenile elephant seals from Patagonia. Mar Mamm Sci 26:430-

  15. Skew and twist resistant hydrodynamic rotary shaft seal

    DOE Patents [OSTI]

    Dietle, Lannie (Sugar Land, TX); Kalsi, Manmohan Singh (Houston, TX)

    1999-01-01T23:59:59.000Z

    A hydrodynamically lubricated squeeze packing type rotary shaft seal suitable for lubricant retention and environmental exclusion which incorporates one or more resilient protuberances which and cooperate with the gland walls to hold the seal straight in its installation groove in unpressurized and low pressure lubricant retention applications thereby preventing skew-induced wear caused by impingement of abrasive contaminants present in the environment, and which also serve as radial bearings to prevent tipping of the seal within its installation gland.

  16. Analysis of floating multi-ring oil seals

    E-Print Network [OSTI]

    Semanate Negrete, Julio Enrique

    1992-01-01T23:59:59.000Z

    -UP CONDITIONS IN FLOATING RING OIL SEALS . . . . Quasi-static analysis for a compressor rotor mounted on tilt-pad bearings and floating ring oil seals . . . . . . . . . . . . . . . . . . . . . The numerical solution procedure Results and discussion Closure... parameters for lock-up calculation. Table 10 Modified Sommerfeld Number, attitude angle and eccentricity ratio for the floating ring oil seals. Table 11 Modified Sommerfeld Number, attitude angle and eccentricity ratio for the tilt-pad bearings. 66 99...

  17. Skew and twist resistant hydrodynamic rotary shaft seal

    DOE Patents [OSTI]

    Dietle, L.; Kalsi, M.S.

    1999-02-23T23:59:59.000Z

    A hydrodynamically lubricated squeeze packing type rotary shaft seal suitable for lubricant retention and environmental exclusion which incorporates one or more resilient protuberances which cooperate with the gland walls to hold the seal straight in its installation groove in unpressurized and low pressure lubricant retention applications thereby preventing skew-induced wear caused by impingement of abrasive contaminants present in the environment, and which also serve as radial bearings to prevent tipping of the seal within its installation gland. 14 figs.

  18. HEAVY METALS IN THE NORTHERN FUR SEAL, CALLORHINUS URSIN US, AND

    E-Print Network [OSTI]

    HEAVY METALS IN THE NORTHERN FUR SEAL, CALLORHINUS URSIN US, AND HARBOR SEAL, PHOCA VITULINA Calillnnia harbor seal and 170 ppm in a fur seal taken oil the Washington coast. Concentrations of cadmium of mercury were from southern California seals. Heavy metals are persistent contaminants that ultimately end

  19. Radioactive mixed waste disposal

    SciTech Connect (OSTI)

    Jasen, W.G.; Erpenbeck, E.G.

    1993-02-01T23:59:59.000Z

    Various types of waste have been generated during the 50-year history of the Hanford Site. Regulatory changes in the last 20 years have provided the emphasis for better management of these wastes. Interpretations of the Atomic Energy Act of 1954 (AEA), the Resource Conservation and Recovery Act of 1976 (RCRA), and the Hazardous and Solid Waste Amendments (HSWA) have led to the definition of radioactive mixed wastes (RMW). The radioactive and hazardous properties of these wastes have resulted in the initiation of special projects for the management of these wastes. Other solid wastes at the Hanford Site include low-level wastes, transuranic (TRU), and nonradioactive hazardous wastes. This paper describes a system for the treatment, storage, and disposal (TSD) of solid radioactive waste.

  20. Attic Air Sealing Guide - Building America Top Innovation | Department...

    Energy Savers [EERE]

    United States. Read the Top Innovation profile on the Guide to Attic Air Sealing. Find case studies of Building America projects across the country that utilize effective attic...

  1. Sealed One Piece Battery Having A Prism Shape Container

    DOE Patents [OSTI]

    Verhoog, Roelof (Bordeaux, FR); Barbotin, Jean-Loup (Pompignac, FR)

    2000-03-28T23:59:59.000Z

    A sealed one-piece battery having a prism-shaped container including: a tank consisting of a single plastic material, a member fixed and sealed to the tank and to partitions on the side of the tank opposite the transverse wall to seal the tank, two flanges fixed and sealed to longitudinal walls defining flow compartments for a heat-conducting fluid, and two tubes on the transverse wall of the tank forming an inlet and an outlet for fluid common to the compartments.

  2. Ceramic-glass-metal seal by microwave heating

    DOE Patents [OSTI]

    Meek, T.T.; Blake, R.D.

    1983-10-04T23:59:59.000Z

    A method for producing a ceramic-glass-metal seal by microwaving, mixes a slurry of glass sealing material and coupling agent and applies same to ceramic and metal workpieces. The slurry and workpieces are then insulated and microwaved at a power, time and frequency sufficient to cause a liquid-phase reaction in the slurry. The reaction of the glass sealing material forms a chemically different seal than that which would be formed by conventional heating because it is formed by diffusion rather than by wetting of the reactants.

  3. International Data on Radiological Sources

    SciTech Connect (OSTI)

    Martha Finck; Margaret Goldberg

    2010-07-01T23:59:59.000Z

    ABSTRACT The mission of radiological dispersal device (RDD) nuclear forensics is to identify the provenance of nuclear and radiological materials used in RDDs and to aid law enforcement in tracking nuclear materials and routes. The application of databases to radiological forensics is to match RDD source material to a source model in the database, provide guidance regarding a possible second device, and aid the FBI by providing a short list of manufacturers and distributors, and ultimately to the last legal owner of the source. The Argonne/Idaho National Laboratory RDD attribution database is a powerful technical tool in radiological forensics. The database (1267 unique vendors) includes all sealed sources and a device registered in the U.S., is complemented by data from the IAEA Catalogue, and is supported by rigorous in-lab characterization of selected sealed sources regarding physical form, radiochemical composition, and age-dating profiles. Close working relationships with global partners in the commercial sealed sources industry provide invaluable technical information and expertise in the development of signature profiles. These profiles are critical to the down-selection of potential candidates in either pre- or post- event RDD attribution. The down-selection process includes a match between an interdicted (or detonated) source and a model in the database linked to one or more manufacturers and distributors.

  4. Radioactive Waste Management Manual

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

    1999-07-09T23:59:59.000Z

    This Manual further describes the requirements and establishes specific responsibilities for implementing DOE O 435.1, Radioactive Waste Management, for the management of DOE high-level waste, transuranic waste, low-level waste, and the radioactive component of mixed waste. Change 1 dated 6/19/01 removes the requirement that Headquarters is to be notified and the Office of Environment, Safety and Health consulted for exemptions for use of non-DOE treatment facilities. Certified 1-9-07. Admin Chg 2, dated 6-8-11, cancels DOE M 435.1-1 Chg 1.

  5. Development of the Holifield Radioactive Ion Beam Facility

    SciTech Connect (OSTI)

    Tatum, B.A.

    1997-08-01T23:59:59.000Z

    The Holifield Radioactive Ion Beam Facility (HRIBF) construction project has been completed and the first radioactive ion beam has been successfully accelerated. The project, which began in 1992, has involved numerous facility modifications. The Oak Ridge Isochronous Cyclotron has been converted from an energy booster for heavy ion beams to a light ion accelerator with internal ion source. A target-ion source and mass analysis system have been commissioned as key components of the facility`s radioactive ion beam injector to the 25MV tandem electrostatic accelerator. Beam transport lines have been completed, and new diagnostics for very low intensity beams have been developed. Work continues on a unified control system. Development of research quality radioactive beams for the nuclear structure and nuclear astrophysics communities continues. This paper details facility development to date.

  6. Gradient Meshed and Toughened SOEC (Solid Oxide Electrolyzer Cell) Composite Seal with Self-Healing Capabilities

    SciTech Connect (OSTI)

    Kathy Lu; W. T. Reynolds, Jr.

    2010-06-08T23:59:59.000Z

    High-temperature electrolysis of water steam is a promising approach for hydrogen production. The potential is even more promising when abundant heat source from nuclear power reactors can be efficiently utilized. Hydrogen production through the above approach also allows for low electric consumption. Overall energy conversion efficiencies for high temperature electrolysis are in the 45-50% range compared to ~30% for the conventional electrolysis. Under such motivation, this research is focused on increasing the operation time and high temperature stability of solid oxide electrolyzer cells (SOEC) for splitting water into hydrogen. Specifically, our focus is to improve the SOEC seal thermal stability and performances by alleviating thermal stress and seal cracking issues.

  7. Transporting radioactive materials: Q & A to your questions

    SciTech Connect (OSTI)

    Not Available

    1993-04-01T23:59:59.000Z

    Over 2 million packages of radioactive materials are shipped each year in the United States. These shipments are carried by trucks, trains, ships, and airplanes every day just like other commodities. Compliance with Federal regulations ensures that radioactive materials are transported safely. Proper packaging is the key to safe shipment. Package designs for radioactive materials must protect the public and the environment even in case of an accident. As the level of radioactivity increases, packaging design requirements become more stringent. Radioactive materials have been shipped in this country for more than 40 years. As with other commodities, vehicles carrying these materials have been involved in accidents. However, no deaths or serious injuries have resulted from exposure to the radioactive contents of these shipments. People are concerned about how radioactive shipments might affect them and the environment. This booklet briefly answers some of the commonly asked questions about the transport of radioactive materials. More detailed information is available from the sources listed at the end of this booklet.

  8. The Full Scale Seal Experiment - A Seal Industrial Prototype for Cigeo - 13106

    SciTech Connect (OSTI)

    Lebon, P.; Bosgiraud, J.M.; Foin, R.; Armand, G. [Andra, 1 rue Jean-Monnet, 92 298 Chatenay-Malabry Cedex (France)] [Andra, 1 rue Jean-Monnet, 92 298 Chatenay-Malabry Cedex (France)

    2013-07-01T23:59:59.000Z

    The Full Scale Seal (FSS) Experiment is one of various experiments implemented by Andra, within the frame of the Cigeo (the French Deep Geological Repository) Project development, to demonstrate the technical construction feasibility and performance of seals to be constructed, at time of Repository components (shafts, ramps, drifts, disposal vaults) progressive closure. FSS is built inside a drift model fabricated on surface for the purpose. Prior to the scale 1:1 seal construction test, various design tasks are scheduled. They include the engineering work on the drift model to make it fit with the experimental needs, on the various work sequences anticipated for the swelling clay core emplacement and the concrete containment plugs construction, on the specialized handling tools (and installation equipment) manufactured and delivered for the purpose, and of course on the various swelling clay materials and low pH (below 11) concrete formulations developed for the application. The engineering of the 'seal-as-built' commissioning means (tools and methodology) must also be dealt with. The FSS construction experiment is a technological demonstrator, thus it is not focused on the phenomenological survey (and by consequence, on the performance and behaviour forecast). As such, no hydration (forced or natural) is planned. However, the FSS implementation (in particular via the construction and commissioning activities carried out) is a key milestone in view of comforting phenomenological extrapolation in time and scale. The FSS experiment also allows for qualifying the commissioning methods of a real sealing system in the Repository, as built, at time of industrial operations. (authors)

  9. Method and apparatus for dispensing small quantities of mercury from evacuated and sealed glass capsules

    DOE Patents [OSTI]

    Grossman, M.W.; George, W.A.; Pai, R.Y.

    1985-08-13T23:59:59.000Z

    A technique is disclosed for opening an evacuated and sealed glass capsule containing a material that is to be dispensed which has a relatively high vapor pressure such as mercury. The capsule is typically disposed in a discharge tube envelope. The technique involves the use of a first light source imaged along the capsule and a second light source imaged across the capsule substantially transversely to the imaging of the first light source. Means are provided for constraining a segment of the capsule along its length with the constraining means being positioned to correspond with the imaging of the second light source. These light sources are preferably incandescent projection lamps. The constraining means is preferably a multiple looped wire support. 6 figs.

  10. Radioactive Waste Management

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

    1999-07-09T23:59:59.000Z

    The objective of this Order is to ensure that all Department of Energy (DOE) radioactive waste is managed in a manner that is protective of worker and public health and safety and the environment. Cancels DOE O 5820.2A. Chg 1 dated 8-28-01. Certified 1-9-07.

  11. Radioactive Waste Management

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

    1999-07-09T23:59:59.000Z

    The objective of this Order is to ensure that all Department of Energy (DOE) radioactive waste is managed in a manner that is protective of worker and public health and safety and the environment. Cancels DOE O 5820.2A

  12. New Proton Radioactivity Measurements

    E-Print Network [OSTI]

    Edinburgh, University of

    New Proton Radioactivity Measurements Richard J. Irvine Thesis submitted for the degree of Doctor to search for examples of proton emission from ground and low­lying states in odd­Z nuclei at the proton into a double­sided silicon strip detector system, where their subsequent particle decays (proton or alpha) were

  13. RedSeal Comments on "Smart Grid RFI: Addressing Policy and Logistical...

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

    RedSeal Comments on "Smart Grid RFI: Addressing Policy and Logistical Challenges. RedSeal Comments on "Smart Grid RFI: Addressing Policy and Logistical Challenges. RedSeal Comments...

  14. Notes 12. (a) Annular pressure (damper) seals, and (b) Hydrostatic journal bearings

    E-Print Network [OSTI]

    San Andres, Luis

    2009-01-01T23:59:59.000Z

    The mechanism of centering stiffness in seals. Force coefficients for short-length pressure seals. Design of annular seals: swirl brakes, impact on rotordynamics. Hydrostatic bearings in modern applications. The principle of hydrostatic lubrication...

  15. A study of the effects of eccentricity on honeycomb annular gas seals

    E-Print Network [OSTI]

    Weatherwax, Mark

    2001-01-01T23:59:59.000Z

    Results are presented which show the effects of eccentricity on high pressure honeycomb and smooth annular gas seals. The results of the experiments indicate the ability to utilize centered seal solutions for rotordynamic coefficients and seal...

  16. Identification of dynamic force coefficients of a labyrinth and gas damper seal using impact load excitations

    E-Print Network [OSTI]

    Ransom, David Lawrence

    1997-01-01T23:59:59.000Z

    Experiments to identify stiffness and damping force coefficients of a two bladed teeth-on-stator labyrinth seal and a gas damper seal, both of diverging clearance, are presented. Calibrated impact guns excite a housing holding the test seal...

  17. CRUCIBLE TESTING OF TANK 48 RADIOACTIVE WASTE SAMPLE USING FBSR TECHNOLOGY FOR ORGANIC DESTRUCTION

    SciTech Connect (OSTI)

    Hammond, C; William Pepper, W

    2008-09-19T23:59:59.000Z

    The purpose of crucible scale testing with actual radioactive Tank 48H material was to duplicate the test results that had been previously performed on simulant Tank 48H material. The earlier crucible scale testing using simulants was successful in demonstrating that bench scale crucible tests produce results that are indicative of actual Fluidized Bed Steam Reforming (FBSR) pilot scale tests. Thus, comparison of the results using radioactive Tank 48H feed to those reported earlier with simulants would then provide proof that the radioactive tank waste behaves in a similar manner to the simulant. Demonstration of similar behavior for the actual radioactive Tank 48H slurry to the simulant is important as a preliminary or preparation step for the more complex bench-scale steam reformer unit that is planned for radioactive application in the Savannah River National Laboratory (SRNL) Shielded Cells Facility (SCF) later in 2008. The goals of this crucible-scale testing were to show 99% destruction of tetraphenylborate and to demonstrate that the final solid product produced is sodium carbonate. Testing protocol was repeated using the specifications of earlier simulant crucible scale testing, that is sealed high purity alumina crucibles containing a pre-carbonated and evaporated Tank 48H material. Sealing of the crucibles was accomplished by using an inorganic 'nepheline' sealant. The sealed crucibles were heat-treated at 650 C under constant argon flow to inert the system. Final product REDOX measurements were performed to establish the REDuction/OXidation (REDOX) state of known amounts of added iron species in the final product. These REDOX measurements confirm the processing conditions (pyrolysis occurring at low oxygen fugacity) of the sealed crucible environment which is the environment actually achieved in the fluidized bed steam reformer process. Solid product dissolution in water was used to measure soluble cations and anions, and to investigate insoluble fractions of the product solids. Radioanalytical measurements were performed on the Tank 48H feed material and on the dissolved products in order to estimate retention of Cs-137 in the process. All aspects of prior crucible scale testing with simulant Tank 48H slurry were demonstrated to be repeatable with the actual radioactive feed. Tetraphenylborate destruction was shown to be >99% and the final solid product is sodium carbonate crystalline material. Less than 10 wt% of the final solid products are insoluble components comprised of Fe/Ni/Cr/Mn containing sludge components and Ti from monosodium titanate present in Tank 48H. REDOX measurements on the radioactive solid products indicate a reducing atmosphere with extremely low oxygen fugacity--evidence that the sealed crucible tests performed in the presence of a reductant (sugar) under constant argon purge were successful in duplicating the pyrolysis reactions occurring with the Tank 48H feed. Soluble anion measurements confirm that using sugar as reductant at 1X stoichiometry was successful in destroying nitrate/nitrite in the Tank 48H feed. Radioanalytical measurements indicate that {approx}75% of the starting Cs-137 is retained in the solid product. No attempts were made to analyze/measure other potential Cs-137 in the process, i.e., as possible volatile components on the inner surface of the alumina crucible/lid or as offgas escaping the sealed crucible. The collective results from these crucible scale tests on radioactive material are in good agreement with simulant testing. Crucible scale processing has been shown to duplicate the complex reactions of an actual fluidized bed steam reformer. Thus this current testing should provide a high degree of confidence that upcoming bench-scale steam reforming with radioactive Tank 48H slurry will be successful in tetraphenylborate destruction and production of sodium carbonate product.

  18. Sealed joint structure for electrochemical device

    DOE Patents [OSTI]

    Tucker, Michael C; Jacobson, Craig P; De Jonghe, Lutgard C; Visco, Steven J

    2013-05-21T23:59:59.000Z

    Several members make up a joint in a high-temperature electrochemical device, wherein the various members perform different functions. The joint is useful for joining multiple cells (generally tubular modules) of an electrochemical device to produce a multi-cell segment-in-series stack for a solid oxide fuel cell, for instance. The joint includes sections that bond the joining members to each other; one or more seal sections that provide gas-tightness, and sections providing electrical connection and/or electrical insulation between the various joining members. A suitable joint configuration for an electrochemical device has a metal joint housing, a first porous electrode, a second porous electrode, separated from the first porous electrode by a solid electrolyte, and an insulating member disposed between the metal joint housing and the electrolyte and second electrode. One or more brazes structurally and electrically connects the first electrode to the metal joint housing and forms a gas tight seal between the first electrode and the second electrode.

  19. Bipolar battery with array of sealed cells

    DOE Patents [OSTI]

    Kaun, Thomas D. (New Lenox, IL); Smaga, John A. (Lemont, IL)

    1987-01-01T23:59:59.000Z

    A lithium alloy/metal sulfide battery as a dipolar battery is disclosed with an array of stacked cells with the anode and cathode electrode materials in each cell sealed in a confining structure and separated from one another except across separator material interposed therebetween. The separator material is contained in a module having separate perforated metallic sheets that sandwich opposite sides of the separator material for the cell and an annular insulating spacer that surrounds the separator material beyond the perforations and is also sandwiched between and sealed to the sheets. The peripheral edges of the sheets project outwardly beyond the spacer, traverse the side edges of the adjacent electrode material to form cup-like electrode holders, and are fused to the adjacent current collector or end face members of the array. Electrolyte is infused into the electrolyte cavity through the perforations of one of the metallic sheets with the perforations also functioning to allow ionic conductance across the separator material between the adjacent electrodes. A gas-tight housing provides an enclosure of the array.

  20. Radioactive Contamination of Danish Territory

    E-Print Network [OSTI]

    Risø-R-462 Radioactive Contamination of Danish Territory after Core-melt Accidents at the Barsebäck;#12;RIS0-R-462 RADIOACTIVE CONTAMINATION OF DANISH TERRITORY AFTER CORE-MELT ACCIDENTS AT THE BARSEBACK. An assessment is made of the radioactive contamination of Danish territory in the event of a core-melt accident

  1. Fuel cell generator containing a gas sealing means

    DOE Patents [OSTI]

    Makiel, Joseph M. (Monroeville, PA)

    1987-01-01T23:59:59.000Z

    A high temperature solid electrolyte electrochemical generator is made, operating with flowing fuel gas and oxidant gas, the generator having a thermal insulation layer, and a sealing means contacting or contained within the insulation, where the sealing means is effective to control the contact of the various gases utilized in the generator.

  2. Projecting the effects of environmental change on Antarctic seals

    E-Print Network [OSTI]

    will be the least negatively influenced by changes in pack ice characteristics, although, as may be the case, and 3) southern elephant and fur seals will respond in ways opposite to the pack ice species, but could) and, as we argue here, pinnipeds in the Antarctic. The four species of pack ice seals (crabeater

  3. Field Manual for Crack Sealing in Asphalt Pavements

    E-Print Network [OSTI]

    Texas at Austin, University of

    Field Manual for Crack Sealing in Asphalt Pavements Yetkin Yildirim, Ahmed Qatan, and Jorge Prozzi January 2006 3208RedRiver Austin,TX78705 #12;Dr. Yetkin Yildirim, P.E. Director Texas Pavement for Crack Sealing in Asphalt Pavements #12;Performing Organization: Center for Transportation Research

  4. Analog Video Authentication and Seal Verification Equipment Development

    SciTech Connect (OSTI)

    Gregory Lancaster

    2012-09-01T23:59:59.000Z

    Under contract to the US Department of Energy in support of arms control treaty verification activities, the Savannah River National Laboratory in conjunction with the Pacific Northwest National Laboratory, the Idaho National Laboratory and Milagro Consulting, LLC developed equipment for use within a chain of custody regime. This paper discussed two specific devices, the Authentication Through the Lens (ATL) analog video authentication system and a photographic multi-seal reader. Both of these devices have been demonstrated in a field trial, and the experience gained throughout will also be discussed. Typically, cryptographic methods are used to prove the authenticity of digital images and video used in arms control chain of custody applications. However, in some applications analog cameras are used. Since cryptographic authentication methods will not work on analog video streams, a simple method of authenticating analog video was developed and tested. A photographic multi-seal reader was developed to image different types of visual unique identifiers for use in chain of custody and authentication activities. This seal reader is unique in its ability to image various types of seals including the Cobra Seal, Reflective Particle Tags, and adhesive seals. Flicker comparison is used to compare before and after images collected with the seal reader in order to detect tampering and verify the integrity of the seal.

  5. Stirling engine or heat pump having an improved seal

    DOE Patents [OSTI]

    White, Maurice A. (2802 S. Everett Pl., Kennewick, WA 99337); Riggle, Peter (616 Fuller, Richland, WA 99352); Emigh, Stuart G. (67 Park St., Richland, WA 99352)

    1985-01-01T23:59:59.000Z

    A Stirling Engine or Heat Pump having two relatively movable machine elements for power transmission purposes includes a hermetic seal bellows interposed between the elements for separating a working gas from a pressure compensating liquid that balances pressure across the bellows to reduce bellows stress and to assure long bellows life. The volume of pressure compensating liquid displaced due to relative movement between the machine elements is minimized by enclosing the compensating liquid within a region exposed to portions of both machine elements at one axial end of a slidable interface presented between them by a clearance seal having an effective diameter of the seal bellows. Pressure equalization across the bellows is achieved by a separate hermetically sealed compensator including a movable enclosed bellows. The interior of the compensator bellows is in communication with one side of the seal bellows, and its exterior is in communication with the remaining side of the seal bellows. A buffer gas or additional liquid region can be provided at the remaining axial end of the clearnace seal, along with valved arrangements for makeup of liquid leakage through the clearance seal.

  6. High-Temperature Zirconia Oxygen Sensor with Sealed Metal/Metal...

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

    High-Temperature Zirconia Oxygen Sensor with Sealed MetalMetal Oxide Internal Reference High-Temperature Zirconia Oxygen Sensor with Sealed MetalMetal Oxide Internal Reference...

  7. Reference design and operations for deep borehole disposal of high-level radioactive waste.

    SciTech Connect (OSTI)

    Herrick, Courtney Grant; Brady, Patrick Vane; Pye, Steven; Arnold, Bill Walter; Finger, John Travis; Bauer, Stephen J.

    2011-10-01T23:59:59.000Z

    A reference design and operational procedures for the disposal of high-level radioactive waste in deep boreholes have been developed and documented. The design and operations are feasible with currently available technology and meet existing safety and anticipated regulatory requirements. Objectives of the reference design include providing a baseline for more detailed technical analyses of system performance and serving as a basis for comparing design alternatives. Numerous factors suggest that deep borehole disposal of high-level radioactive waste is inherently safe. Several lines of evidence indicate that groundwater at depths of several kilometers in continental crystalline basement rocks has long residence times and low velocity. High salinity fluids have limited potential for vertical flow because of density stratification and prevent colloidal transport of radionuclides. Geochemically reducing conditions in the deep subsurface limit the solubility and enhance the retardation of key radionuclides. A non-technical advantage that the deep borehole concept may offer over a repository concept is that of facilitating incremental construction and loading at multiple perhaps regional locations. The disposal borehole would be drilled to a depth of 5,000 m using a telescoping design and would be logged and tested prior to waste emplacement. Waste canisters would be constructed of carbon steel, sealed by welds, and connected into canister strings with high-strength connections. Waste canister strings of about 200 m length would be emplaced in the lower 2,000 m of the fully cased borehole and be separated by bridge and cement plugs. Sealing of the upper part of the borehole would be done with a series of compacted bentonite seals, cement plugs, cement seals, cement plus crushed rock backfill, and bridge plugs. Elements of the reference design meet technical requirements defined in the study. Testing and operational safety assurance requirements are also defined. Overall, the results of the reference design development and the cost analysis support the technical feasibility of the deep borehole disposal concept for high-level radioactive waste.

  8. Photogrammetry as a tool for estimating size and condition in the Hawaiian monk seal (Monachus schauinslandi), the harbor seal (Phoca vitulina), and the northern elephant seal (Mirounga anguistirosis)

    E-Print Network [OSTI]

    McFadden, Katherine Walton

    1999-01-01T23:59:59.000Z

    A photographic technique was developed to indirectly estimate mass and body condition of the endangered Hawaiian monk seal (Monachus schauinslandi). This project differs from other photogrammetric studies because subjects were photographed under...

  9. Capillary exit pressure as a basin sealing mechanism

    SciTech Connect (OSTI)

    Shosa, J.; Cathles, L. [Cornell Univ., Ithaca, NY (United States)

    1996-12-31T23:59:59.000Z

    Abnormally pressured compartments in sedimentary basins require an efficient sealing mechanism. Most sealing mechanisms rely on either intrinsically low formation permeabilities or on the entry pressure of a non-aqueous phase into a fine-grained unit. However, the nanodarcy permeabilities required to maintain overpressures over significant geologic time are not plausible over wide areas. Entry pressures, while effective in trapping a non-aqueous phase in a local reservoir, can not prevent leakage where the non-aqueous phase is not ponded against the seal. The capillary exit pressure required to displace water from a fine-grained formation into a coarse-grained formation which contains a non-aqueous phase provides an alternative sealing mechanism. Capillary exit pressure seals require contrasts in grain size and the presence of two phases in the coarse-grained unit, but do not require 100% saturation of the non-aqueous phase. These conditions can exist on all sides of a pressure compartment, and can account for sealing on the top, bottom, and sides of a compartment. We have shown in the laboratory that capillary exit pressure seals under reservoir conditions allow no fluid flow across the seal until a threshold pressure is exceeded (e.g., the seat is not a relative permeability effect) and that exit pressures are additive over a series of fine/coarse interfaces. Capillary exit pressure seals can maintain the abnormal pressures observed in the South Eugene Island Block 330 field. Both a sufficient number of sand/shale layers and a gas phase are present in the pressure transition zone there. We believe capillary exit pressure seals are a general feature of sedimentary basins and are important in controlling large scale fluid flow.

  10. Fault seal analysis of Okan and Meren fields, Nigeria

    SciTech Connect (OSTI)

    Eisenberg, R.A. [Chevron Petroleum Technology Co., La Habra, CA (United States); Brenneman, R.J. [Chevron Overseas Petroleum Co., San Ramon, CA (United States); Adeogba, A.A. [Chevron Nigeria Ltd., Lagos (Nigeria)

    1995-08-01T23:59:59.000Z

    The sealing capacity and the dynamic seal behavior of faults between juxtaposed reservoirs were analyzed for Okan and Meren fields, offshore Nigeria. In both fields correlations were found between reservoir performance, juxtaposed fluid types, oil geochemistry, interpreted fluid contact relationships, fault sealing/leaking condition, and calculated smear gouge ratios. Integration of these data has been invaluable in quantifying fault seal risk and may effect depletion strategies for fault-juxtaposed reservoirs within these fields. Fault plane sections defined reservoir juxtapositions and aided visualization of potential cross-fault spill points. Smear gouge ratios calculated from E-logs were used to estimate the composition of fault-gouge materials between the juxtaposed reservoirs. These tools augmented interpretation of seal/nonseal character based on fluid contact relationships in proved reservoirs and, in addition, were used to quantify fault seal risk of untested fault-dependent closures in Okan. The results of these analyses were then used to interpret production-induced fault seal breakdown within the G-sands and also to risk seal integrity of fault dependent closures within the untested O-sands in an adjacent, upthrown fault block. Within this fault block the presence of potential fault intersection leak points and large areas of sand/sand juxtaposition with high smear gouge ratios (low sealing potential) limits potential reserves within the O-sand package. In Meren Field the E- and G-sands are juxtaposed, on different pressure decline, geochemically distinct, and are characterized by low smear gouge ratios. In contrast, specific G- and H-sands, juxtaposed across the same fault, contain similar OOWCs and are characterized by high smear gouge ratios. The cross-sealing and/or cross-leaking nature of compartment boundaries at Meren is related to fault displacement variation and the composition of displaced stratigraphy.

  11. Capillary exit pressure as a basin sealing mechanism

    SciTech Connect (OSTI)

    Shosa, J.; Cathles, L. (Cornell Univ., Ithaca, NY (United States))

    1996-01-01T23:59:59.000Z

    Abnormally pressured compartments in sedimentary basins require an efficient sealing mechanism. Most sealing mechanisms rely on either intrinsically low formation permeabilities or on the entry pressure of a non-aqueous phase into a fine-grained unit. However, the nanodarcy permeabilities required to maintain overpressures over significant geologic time are not plausible over wide areas. Entry pressures, while effective in trapping a non-aqueous phase in a local reservoir, can not prevent leakage where the non-aqueous phase is not ponded against the seal. The capillary exit pressure required to displace water from a fine-grained formation into a coarse-grained formation which contains a non-aqueous phase provides an alternative sealing mechanism. Capillary exit pressure seals require contrasts in grain size and the presence of two phases in the coarse-grained unit, but do not require 100% saturation of the non-aqueous phase. These conditions can exist on all sides of a pressure compartment, and can account for sealing on the top, bottom, and sides of a compartment. We have shown in the laboratory that capillary exit pressure seals under reservoir conditions allow no fluid flow across the seal until a threshold pressure is exceeded (e.g., the seat is not a relative permeability effect) and that exit pressures are additive over a series of fine/coarse interfaces. Capillary exit pressure seals can maintain the abnormal pressures observed in the South Eugene Island Block 330 field. Both a sufficient number of sand/shale layers and a gas phase are present in the pressure transition zone there. We believe capillary exit pressure seals are a general feature of sedimentary basins and are important in controlling large scale fluid flow.

  12. Radioactive ion detector

    DOE Patents [OSTI]

    Bower, K.E.; Weeks, D.R.

    1997-08-12T23:59:59.000Z

    Apparatus for detecting the presence, in aqueous media, of substances which emit alpha and/or beta radiation and determining the oxidation state of these radioactive substances, that is, whether they are in cationic or anionic form. In one embodiment, a sensor assembly has two elements, one comprised of an ion-exchange material which binds cations and the other comprised of an ion-exchange material which binds anions. Each ion-exchange element is further comprised of a scintillation plastic and a photocurrent generator. When a radioactive substance to which the sensor is exposed binds to either element and emits alpha or beta particles, photons produced in the scintillation plastic illuminate the photocurrent generator of that element. Sensing apparatus senses generator output and thereby indicates whether cationic species or anionic species or both are present and also provides an indication of species quantity. 2 figs.

  13. Carbon Dioxide Sealing Capacity: Textural or Compositional Controls?

    SciTech Connect (OSTI)

    Cranganu, Constantin; Soleymani, Hamidreza; Sadiqua, Soleymani; Watson, Kieva

    2013-11-30T23:59:59.000Z

    This research project is aiming to assess the carbon dioxide sealing capacity of most common seal-rocks, such as shales and non-fractured limestones, by analyzing the role of textural and compositional parameters of those rocks. We hypothesize that sealing capacity is controlled by textural and/or compositional pa-rameters of caprocks. In this research, we seek to evaluate the importance of textural and compositional parameters affecting the sealing capacity of caprocks. The conceptu-al framework involves two testable end-member hypotheses concerning the sealing ca-pacity of carbon dioxide reservoir caprocks. Better understanding of the elements controlling sealing quality will advance our knowledge regarding the sealing capacity of shales and carbonates. Due to relatively low permeability, shale and non-fractured carbonate units are considered relatively imper-meable formations which can retard reservoir fluid flow by forming high capillary pres-sure. Similarly, these unites can constitute reliable seals for carbon dioxide capture and sequestration purposes. This project is a part of the comprehensive project with the final aim of studying the caprock sealing properties and the relationship between microscopic and macroscopic characteristics of seal rocks in depleted gas fields of Oklahoma Pan-handle. Through this study we examined various seal rock characteristics to infer about their respective effects on sealing capacity in special case of replacing reservoir fluid with super critical carbon dioxide (scCO{sub 2}). To assess the effect of textural and compositional properties on scCO{sub 2} maximum reten-tion column height we collected 30 representative core samples in caprock formations in three counties (Cimarron, Texas, Beaver) in Oklahoma Panhandle. Core samples were collected from various seal formations (e.g., Cherokee, Keys, Morrowan) at different depths. We studied the compositional and textural properties of the core samples using several techniques. Mercury Injection Porosimetry (MIP), Scanning Electron Microsco-py SEM, and Sedigraph measurements are used to assess the pore-throat-size distribu-tion, sorting, texture, and grain size of the samples. Also, displacement pressure at 10% mercury saturation (Pd) and graphically derived threshold pressure (Pc) were deter-mined by MIP technique. SEM images were used for qualitative study of the minerals and pores texture of the core samples. Moreover, EDS (Energy Dispersive X-Ray Spec-trometer), BET specific surface area, and Total Organic Carbon (TOC) measurements were performed to study various parameters and their possible effects on sealing capaci-ty of the samples. We found that shales have the relatively higher average sealing threshold pressure (Pc) than carbonate and sandstone samples. Based on these observations, shale formations could be considered as a promising caprock in terms of retarding scCO{sub 2} flow and leak-age into above formations. We hypothesized that certain characteristics of shales (e.g., 3 fine pore size, pore size distribution, high specific surface area, and strong physical chemical interaction between wetting phase and mineral surface) make them an effi-cient caprock for sealing super critical CO{sub 2}. We found that the displacement pressure at 10% mercury saturation could not be the ultimate representative of the sealing capacity of the rock sample. On the other hand, we believe that graphical method, introduced by Cranganu (2004) is a better indicator of the true sealing capacity. Based on statistical analysis of our samples from Oklahoma Panhandle we assessed the effects of each group of properties (textural and compositional) on maximum supercriti-cal CO{sub 2} height that can be hold by the caprock. We conclude that there is a relatively strong positive relationship (+.40 to +.69) between supercritical CO{sub 2} column height based on Pc and hard/ soft mineral content index (ratio of minerals with Mohs hardness more than 5 over minerals with Mohs hardness less than 5) in both shales and limestone samples. Average median pore rad

  14. MECHANICAL PROPERTY CHARACTERIZATIONS AND PERFORMANCE MODELING OF SOFC SEALS

    SciTech Connect (OSTI)

    Koeppel, Brian J.; Vetrano, John S.; Nguyen, Ba Nghiep; Sun, Xin; Khaleel, Mohammad A.

    2008-03-26T23:59:59.000Z

    This study provides modeling tools for the design of reliable seals for SOFC stacks. The work consists of 1) experimental testing to determine fundamental properties of SOFC sealing materials, and 2) numerical modeling of stacks and sealing systems. The material tests capture relevant temperature-dependent physical and mechanical data needed by the analytical models such as thermal expansion, strength, fracture toughness, and relaxation behavior for glass-ceramic seals and other materials. Testing has been performed on both homogenous specimens and multiple material assemblies to investigate the effect of interfacial reactions. A viscoelastic continuum damage model for a glass-ceramic seal was developed to capture the nonlinear behavior of this material at high temperatures. This model was implemented in the MSC MARC finite element code and was used for a detailed analysis of a planar SOFC stack under thermal cycling conditions. Realistic thermal loads for the stack were obtained using PNNL’s in-house multiphysics solver. The accumulated seal damage and component stresses were evaluated for multiple thermal loading cycles, and regions of high seal damage susceptible to cracking were identified. Selected test results, numerical model development, and analysis results will be presented.

  15. Tamper-indicating seals : practices, problems, and standards

    SciTech Connect (OSTI)

    Johnston, R. G. (Roger G.)

    2003-01-01T23:59:59.000Z

    Tamper-indicating seals have been used by customs officials for over 7,000 years. Today, seals are widely used to help counter theft, smuggling, sabotage, vandalism, terrorism, and espionage. Despite their antiquity and modern widespread use, however, there remains considerable confusion about seals, as well as a lot of misconceptions, wishful thinking, sloppy terminology, and poor practice. The absence of meaningful norms and standards, together with the surprisingly limited amount of research and development (R&D) in the field of tamper detection, has also hindered the effective use of seals. The Vulnerability Assessment Team (VAT) at Los Alamos National Laboratory has intensively studied tamper-indicating seals for the last 12 years. We have engaged in vulnerability assessments, R&D, consulting, and training for over two dozen United States government agencies and private companies, as well as for the International Atomic Energy Agency (IAEA) and Euratom. The VAT has also analyzed over 200 different types of seals in detail. This paper summarizes some of our conclusions, recommendations, and warnings regarding seals and tamper detection.

  16. alloy ion source: Topics by E-print Network

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

    ions at radioactive ion beam facilities is discussed. The ability to combine high efficiency and element selectivity makes a resonance ionization laser ion source (RILIS) an...

  17. ambient ion sources: Topics by E-print Network

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

    ions at radioactive ion beam facilities is discussed. The ability to combine high efficiency and element selectivity makes a resonance ionization laser ion source (RILIS) an...

  18. Sealing system for piston rod of hot gas engine

    SciTech Connect (OSTI)

    Lundholm, S.G.; Ringqvist, S.A.

    1980-11-25T23:59:59.000Z

    An improvement to a sealing system for restricting fluid flow around a piston rod between a piston cylinder and crankshaft space in a hot gas engine where a seal element is secured around the piston rod in an intermediate chamber, the improvement including a link in the crankshaft space connecting, and permitting relative radial motion between, the piston rod and the crosshead and an o-ring having a diameter substantially greater than that of the piston rod and being secured between a lower ring securing the seal element in place around the piston rod and a wall of the intermediate chamber for frictionally restricting radial movement of the lower ring.

  19. Evaluation of Steam Turbines Triangular Tooth on Stator Labyrinth Seal 

    E-Print Network [OSTI]

    Tanvir, Hossain Ahmed

    2012-07-16T23:59:59.000Z

    . ........................................................................... 9? Fig. 1.8. Flow pattern inside the labyrinth seal cavities for incompressible flow (case 1, c=0.05, s=3, B=7?, w=0, cavity 1). ............ 12? Fig. 1.9. Flow pattern inside the labyrinth seal cavities for compressible flow... ( case 1, c=0.05, s=3, b=7?, w=0, cavity 1). ............................................. 13? Fig. 1.10. Stream traces inside the labyrinth seal cavities for compressible flow (case 3, c=0.05, s=3, b=7?, cavity 1...

  20. Trap seal for open circuit liquid cooled turbines

    DOE Patents [OSTI]

    Grondahl, Clayton M. (Clifton Park, NY); Germain, Malcolm R. (Ballston Lake, NY)

    1980-01-01T23:59:59.000Z

    An improved trap seal for open circuit liquid cooled turbines is disclosed. The trap seal of the present invention includes an annular recess formed in the supply conduit of cooling channels formed in the airfoil of the turbine buckets. A cylindrical insert is located in the annular recesses and has a plurality of axial grooves formed along the outer periphery thereof and a central recess formed in one end thereof. The axial grooves and central recess formed in the cylindrical insert cooperate with the annular recess to define a plurality of S-shaped trap seals which permit the passage of liquid coolant but prohibit passage of gaseous coolant.

  1. Method of sealing an ultracapacitor substantially free of water

    DOE Patents [OSTI]

    Chapman-Irwin, Patricia (Altamont, NY); Feist, Thomas Paul (Clifton Park, NY)

    2002-04-02T23:59:59.000Z

    A method of sealing an ultracapacitor substantially free of water is disclosed. The method includes providing a multilayer cell comprising two solid, non porous current collectors, separated by two porous electrodes with a separator between the two electrodes, sealing the cell with a reclosable hermetic closure. Water inside the closure is dissociated by an applied voltage to the cell and escapes in the form of hydrogen and oxygen when the closure is unmated, the closure is then mated to hermetically seal the cell which is substantially free of water.

  2. Flexible edge seal for vacuum insulating glazing units

    DOE Patents [OSTI]

    Bettger, Kenneth J.; Stark, David H.

    2012-12-11T23:59:59.000Z

    A flexible edge seal is provided for a vacuum insulating glazing unit having a first glass pane and a second glass pane spaced-apart from the first. The edge seal comprises a seal member formed of a hermetically bondable material and having a first end, a second end and a center section disposed therebetween. The first end is hermetically bondable to a first glass pane. The second end is hermetically bondable to a second glass pane. The center section comprises a plurality of convolutes.

  3. Method for producing ceramic-glass-ceramic seals by microwave heating

    DOE Patents [OSTI]

    Blake, Rodger D. (Santa Fe, NM); Meek, Thomas T. (Los Alamos, NM)

    1986-01-01T23:59:59.000Z

    Method for producing a ceramic-glass-ceramic seal by the use of microwave energy, and a sealing mixture which comprises a glass sealing material, a coupling agent, and an oxidizer. The seal produced exhibits greater strength due to its different microstructure. Sodium nitrate is the most preferred oxidizer.

  4. Rotordynamic evaluation of frequency dependent impedances of hole-pattern gas damper seals

    E-Print Network [OSTI]

    Holt, Christopher George

    2000-01-01T23:59:59.000Z

    Two hole-pattern seals are compared with one smooth bore seal. The two hole-pattern seals have cell depths of 2.03 mm and 3.18 mm with a cell diameter of 1.59 mm. The hole area density factor for both hole-pattern seals is 43%. The L/D ratio...

  5. 3-D laser doppler velocimeter measurements of eccentric annular and labyrinth seals

    E-Print Network [OSTI]

    Das, Purandar Gururaj

    1993-01-01T23:59:59.000Z

    .27 mm. The eccentricity ratios of the annular and labyrinth seals were 0.10 and 0.50 respectively. The whirl ratio for both seals were 1.00. For both seals the maximum axial velocity is not located at the maximum clearance over the length of the seals...

  6. Creating a Sealstone: A Study of Seals in the Greek Late Bronze Age

    E-Print Network [OSTI]

    Younger, John G.

    1981-01-01T23:59:59.000Z

    This study describes how Minoan-Mycenaean sealstones were created, using evidence of unfinished seals....

  7. Radioactive waste material disposal

    DOE Patents [OSTI]

    Forsberg, C.W.; Beahm, E.C.; Parker, G.W.

    1995-10-24T23:59:59.000Z

    The invention is a process for direct conversion of solid radioactive waste, particularly spent nuclear fuel and its cladding, if any, into a solidified waste glass. A sacrificial metal oxide, dissolved in a glass bath, is used to oxidize elemental metal and any carbon values present in the waste as they are fed to the bath. Two different modes of operation are possible, depending on the sacrificial metal oxide employed. In the first mode, a regenerable sacrificial oxide, e.g., PbO, is employed, while the second mode features use of disposable oxides such as ferric oxide. 3 figs.

  8. Radioactive waste material disposal

    DOE Patents [OSTI]

    Forsberg, Charles W. (155 Newport Dr., Oak Ridge, TN 37830); Beahm, Edward C. (106 Cooper Cir., Oak Ridge, TN 37830); Parker, George W. (321 Dominion Cir., Knoxville, TN 37922)

    1995-01-01T23:59:59.000Z

    The invention is a process for direct conversion of solid radioactive waste, particularly spent nuclear fuel and its cladding, if any, into a solidified waste glass. A sacrificial metal oxide, dissolved in a glass bath, is used to oxidize elemental metal and any carbon values present in the waste as they are fed to the bath. Two different modes of operation are possible, depending on the sacrificial metal oxide employed. In the first mode, a regenerable sacrificial oxide, e.g., PbO, is employed, while the second mode features use of disposable oxides such as ferric oxide.

  9. RADIOACTIVE MATERIALS SENSORS

    SciTech Connect (OSTI)

    Mayo, Robert M.; Stephens, Daniel L.

    2009-09-15T23:59:59.000Z

    Providing technical means to detect, prevent, and reverse the threat of potential illicit use of radiological or nuclear materials is among the greatest challenges facing contemporary science and technology. In this short article, we provide brief description and overview of the state-of-the-art in sensor development for the detection of radioactive materials, as well as an identification of the technical needs and challenges faced by the detection community. We begin with a discussion of gamma-ray and neutron detectors and spectrometers, followed by a description of imaging sensors, active interrogation, and materials development, before closing with a brief discussion of the unique challenges posed in fielding sensor systems.

  10. Dynamically Movable Exhausting Emc Sealing System

    DOE Patents [OSTI]

    Barringer, Dennis R. (Wallkill, NY); Seminaro, Edward J. (Milton, NY); Toffler, Harold M. (Newburgh, NY)

    2003-12-09T23:59:59.000Z

    A docking apparatus for printed circuit boards including a cassette housing, having a housing base, a housing cover and a housing wall, wherein the housing base and the housing wall are disposed relative to each other so as to define a housing cavity for containing a printed circuit card and wherein the housing wall includes a cable opening disposed so as to be communicated with the housing cavity, a housing bezel, disposed relative to the cassette housing so as to be associated with the cable opening, the housing bezel includes an outer bezel having a first plurality of openings and an inner bezel having a second plurality of apertures, the inner bezel in electrical communication with the printed circuit card, wherein said housing bezel is removable, and an EMC gasket disposed between the outer and inner bezels of said housing bezel, the EMC gasket configured to provide a removable EMC seal proximate the cable opening while still allowing airflow through the first and second plurality of apertures having the EMC gasket therebetween. A docking apparatus for printed circuit boards including a cassette housing, having a housing base, a housing cover and a housing wall, wherein the housing base and the housing wall are disposed relative to each other so as to define a housing cavity for containing a printed circuit card and wherein the housing wall includes a cable opening disposed so as to be communicated with the housing cavity, a housing bezel, disposed relative to the cassette housing so as to be associated with the cable opening, the housing bezel includes an outer bezel having a first plurality of openings and an inner bezel having a second plurality of apertures, the inner bezel in electrical communication with the printed circuit card, wherein said housing bezel is removable, and an EMC gasket disposed between the outer and inner bezels of said housing bezel, the EMC gasket configured to provide a removable EMC seal proximate the cable opening while still allowing airflow through the first and second plurality of apertures having the EMC gasket therebetween.

  11. Computational analysis of spiral groove thrust bearings and face seals

    E-Print Network [OSTI]

    Zirkelback, Nicole Lisa

    1997-01-01T23:59:59.000Z

    Analyses for incompressible and compressible spiral groove thrust bearings (SGTBS) and face seals (SGFSS) are presented. A successive approximation linearizes the partial differential equation of pressure that arises in the compressible fluid...

  12. Design and vibration testing of a flexible seal whisker model

    E-Print Network [OSTI]

    Gerber, Christopher D

    2013-01-01T23:59:59.000Z

    Harbor seal whiskers have a unique surface structure that dramatically reduces vortex induced vibrations as they move through the water. Concurrently with rigid whisker experiments, this project focuses on the design and ...

  13. Measure Guideline: Sealing and Insulating of Ducts in Existing Homes

    SciTech Connect (OSTI)

    Aldrich, R.; Puttagunta, S.

    2011-12-01T23:59:59.000Z

    This document begins with a discussion on potential cost and performance benefits of duct sealing and insulating. It continues with a review of typical duct materials and components and the overall procedures for assessing and improving the duct system.

  14. Recovery Act Workers Add Time Capsule Before Sealing Reactor...

    Office of Environmental Management (EM)

    (SRS) placed a time capsule with a cache of timely news items inside a former nuclear reactor this week before sealing the 300,000-square foot facility shut for hundreds of years...

  15. Flow visualization and leakage measurements of labyrinth seals

    E-Print Network [OSTI]

    Johnson, James Wayne

    1996-01-01T23:59:59.000Z

    A large scale test rig is used to conduct an experimental investigation into the leakage resistance properties and flow characteristics of labyrinth seals. A novel test facility with multiple cavities that provides 2D, planar flow at a scale...

  16. C-1 1999 SITE ENVIRONMENTAL REPORT APPENDIX C: CONCEPTS OF RADIOACTIVITY

    E-Print Network [OSTI]

    Man-made Medical, 39 Nuclear Medicine, 14 Consumer Products, 10 SOURCES OF RADIATION Radioactivity as radiation. The three most important types of radiation are described below. COMMON TYPES OF RADIATION ALPHA occurring radioactive elements such as radon emit alpha radiation. BETA Beta radiation is composed

  17. Filled glass composites for sealing of solid oxide fuel cells.

    SciTech Connect (OSTI)

    Tandon, Rajan; Widgeon, Scarlett Joyce; Garino, Terry J.; Brochu, Mathieu; Gauntt, Bryan D.; Corral, Erica L.; Loehman, Ronald E.

    2009-04-01T23:59:59.000Z

    Glasses filled with ceramic or metallic powders have been developed for use as seals for solid oxide fuel cells (SOFC's) as part of the U.S. Department of Energy's Solid State Energy Conversion Alliance (SECA) Program. The composites of glass (alkaline earth-alumina-borate) and powders ({approx}20 vol% of yttria-stabilized zirconia or silver) were shown to form seals with SOFC materials at or below 900 C. The type and amount of powder were adjusted to optimize thermal expansion to match the SOFC materials and viscosity. Wetting studies indicated good wetting was achieved on the micro-scale and reaction studies indicated that the degree of reaction between the filled glasses and SOFC materials, including spinel-coated 441 stainless steel, at 750 C is acceptable. A test rig was developed for measuring strengths of seals cycled between room temperature and typical SOFC operating temperatures. Our measurements showed that many of the 410 SS to 410 SS seals, made using silver-filled glass composites, were hermetic at 0.2 MPa (2 atm.) of pressure and that seals that leaked could be resealed by briefly heating them to 900 C. Seal strength measurements at elevated temperature (up to 950 C), measured using a second apparatus that we developed, indicated that seals maintained 0.02 MPa (0.2 atm.) overpressures for 30 min at 750 C with no leakage. Finally, the volatility of the borate component of sealing glasses under SOFC operational conditions was studied using weight loss measurements and found by extrapolation to be less than 5% for the projected SOFC lifetime.

  18. Measure Guideline: Air Sealing Attics in Multifamily Buildings

    SciTech Connect (OSTI)

    Otis, C.; Maxwell, S.

    2012-06-01T23:59:59.000Z

    This Building America Measure Guideline is intended for owners, builders, contractors, homeowners, and other stakeholders in the multifamily building industry, and focuses on challenges found in existing buildings for a variety of housing types. It explains why air sealing is desirable, explores related health and safety issues, and identifies common air leakage points in multifamily building attics. In addition, it also gives an overview of materials and techniques typically used to perform air sealing work.

  19. Inflatable containment diaphragm for sealing and removing stacks

    DOE Patents [OSTI]

    Meskanick, G.R.; Rosso, D.T.

    1993-04-13T23:59:59.000Z

    A diaphragm with an inflatable torus-shaped perimeter is used to seal at least one end of a stack so that debris that might be hazardous will not be released during removal of the stack. A diaphragm is inserted and inflated in the lower portion of a stack just above where the stack is to be cut such that the perimeter of the diaphragm expands and forms a seal against the interior surface of the stack.

  20. Experimental study of ceramic coated tip seals for turbojet engines

    SciTech Connect (OSTI)

    Biesiadny, T.J.; Klann, G.A.; Lassow, E.S.; Mchenry, M.

    1985-01-01T23:59:59.000Z

    Ceramic gas-path seals were fabricated and successfully operated over 1000 cycles from flight idle to maximum power in a small turboshaft engine. The seals were fabricated by plasma spraying zirconia over a NiCoCrAlX bond boat on the Haynes 25 substrate. Coolant-side substrate temperatures and related engine parameters were recorded. Post-test inspection revealed mudflat surface cracking with penetration to the ceramic bond-coat interface.

  1. Performance and reliability enhancement of turbo-pump labyrinth seals

    E-Print Network [OSTI]

    Guidry, Michael James

    1991-01-01T23:59:59.000Z

    PERFORMANCE AND RELIABILITY ENHANCEMENT OF TURBO-PUMP LABYRINTH SEALS A Thesis by MICHAEL JAMES GUIDRY, JR. Submitted to the Office of Graduate Studies of Texas A&M University in partial fulfillment of the requirement for the degree... of MASTER OF SCIENCE August 1991 Major Subject: Mechanical Engineering PERFORMANCE AND RELIABILITY ENHANCEMENT OF TURBO-PUMP LABYRINTH SEALS A Thesis by Michael Ja. mes Guidry, Jr. Approved as to style and content by: D. L. Rhode (Chair...

  2. Advanced configurations for leakage reduction in a labyrinth seal

    E-Print Network [OSTI]

    Veldanda, Sharath B.

    1992-01-01T23:59:59.000Z

    ADVANCED CONFIGURATIONS FOR LEAKAGE REDUCTION IN A LABYRINTH SEAL A Thesis by SHARATH B. VELDANDA Submitted to the Office of Graduate Studies of Texas ARM University in partial fulfillment of the requirements for the degree of MASTER... OF SCIENCE December 1992 Major Subject: Mechanical Engineering ADVANCED CONFIGURATION FOR LEAKAGE REDUCTION IN A LABYRINTH SEAL A Thesis by SHARATH B. VELDANDA Approved as to style and content by: David L. Rhode y~~ (Member) K. D. Korkan (Member...

  3. Deep borehole disposal of high-level radioactive waste.

    SciTech Connect (OSTI)

    Stein, Joshua S.; Freeze, Geoffrey A.; Brady, Patrick Vane; Swift, Peter N.; Rechard, Robert Paul; Arnold, Bill Walter; Kanney, Joseph F.; Bauer, Stephen J.

    2009-07-01T23:59:59.000Z

    Preliminary evaluation of deep borehole disposal of high-level radioactive waste and spent nuclear fuel indicates the potential for excellent long-term safety performance at costs competitive with mined repositories. Significant fluid flow through basement rock is prevented, in part, by low permeabilities, poorly connected transport pathways, and overburden self-sealing. Deep fluids also resist vertical movement because they are density stratified. Thermal hydrologic calculations estimate the thermal pulse from emplaced waste to be small (less than 20 C at 10 meters from the borehole, for less than a few hundred years), and to result in maximum total vertical fluid movement of {approx}100 m. Reducing conditions will sharply limit solubilities of most dose-critical radionuclides at depth, and high ionic strengths of deep fluids will prevent colloidal transport. For the bounding analysis of this report, waste is envisioned to be emplaced as fuel assemblies stacked inside drill casing that are lowered, and emplaced using off-the-shelf oilfield and geothermal drilling techniques, into the lower 1-2 km portion of a vertical borehole {approx}45 cm in diameter and 3-5 km deep, followed by borehole sealing. Deep borehole disposal of radioactive waste in the United States would require modifications to the Nuclear Waste Policy Act and to applicable regulatory standards for long-term performance set by the US Environmental Protection Agency (40 CFR part 191) and US Nuclear Regulatory Commission (10 CFR part 60). The performance analysis described here is based on the assumption that long-term standards for deep borehole disposal would be identical in the key regards to those prescribed for existing repositories (40 CFR part 197 and 10 CFR part 63).

  4. Gas-path leakage seal for a gas turbine

    DOE Patents [OSTI]

    Wolfe, Christopher E. (Schenectady, NY); Dinc, Osman S. (Troy, NY); Bagepalli, Bharat S. (Schenectady, NY); Correia, Victor H. (New Lebanon, NY); Aksit, Mahmut F. (Troy, NY)

    1996-01-01T23:59:59.000Z

    A gas-path leakage seal for generally sealing a gas-path leakage-gap between spaced-apart first and second members of a gas turbine (such as combustor casing segments). The seal includes a generally imperforate foil-layer assemblage which is generally impervious to gas and is located in the leakage-gap. The seal also includes a cloth-layer assemblage generally enclosingly contacting the foil-layer assemblage. In one seal, the first edge of the foil-layer assemblage is left exposed, and the foil-layer assemblage resiliently contacts the first member near the first edge to reduce leakage in the "plane" of the cloth-layer assemblage under conditions which include differential thermal growth of the two members. In another seal, such leakage is reduced by having a first weld-bead which permeates the cloth-layer assemblage, is attached to the metal-foil-layer assemblage near the first edge, and unattachedly contacts the first member.

  5. Hermetically sealed electrical feedthrough for high temperature secondary cells

    DOE Patents [OSTI]

    Knoedler, Reinhard (Nussloch, DE); Nelson, Paul A. (Wheaton, IL); Shimotake, Hiroshi (Hinsdale, IL); Battles, James E. (Oak Forest, IL)

    1985-01-01T23:59:59.000Z

    A passthrough seal is disclosed for electrically isolating the terminal in a lithium/metal sulfide cell from the structural cell housing. The seal has spaced upper and lower insulator rings fitted snuggly between the terminal and an annularly disposed upstanding wall, and outwardly of a powdered insulator also confined between the upstanding wall and terminal. The adjacent surfaces of the upper insulator ring and the respective upstanding wall and terminal are conically tapered, diverging in the axial direction away from the cell interior, and a sealing ring is located between each pair of the adjacent surfaces. The components are sized so that upon appropriate movement of the upper insulator ring toward the lower insulator ring the powdered insulator and sealing rings are each compressed to a high degree. This compacts the powdered insulator thereby rendering the same highly impervious and moreover fuses the sealing rings to and between the adjacent surfaces. The upper and lower insulator rings might be formed of beryllium oxide and/or alumina, the powdered insulator might be formed of boron nitride, and the sealing rings might be formed of aluminum.

  6. Hermetically sealed electrical feedthrough for high temperature secondary cells

    DOE Patents [OSTI]

    Knoedler, R.; Nelson, P.A.; Shimotake, H.; Battles, J.E.

    1983-07-26T23:59:59.000Z

    A passthrough seal is disclosed for electrically isolating the terminal in a lithium/metal sulfide cell from the structural cell housing. The seal has spaced upper and lower insulator rings fitted snuggly between the terminal and an annularly disposed upstanding wall, and outwardly of a powdered insulator also confined between the upstanding wall and terminal. The adjacent surfaces of the upper insulator ring and the respective upstanding wall and terminal are conically tapered, diverging in the axial direction away from the cell interior, and a sealing ring is located between each pair of the adjacent surfaces. The components are sized so that upon appropriate movement of the upper insulator ring toward the lower insulator ring the powdered insulator and sealing rings are each compressed to a high degree. This compacts the powdered insulator thereby rendering the same highly impervious and moreover fuses the sealing rings to and between the adjacent surfaces. The upper and lower insulator rings might be formed of beryllium oxide and/or alumina, the powdered insulator might be formed of boron nitride, and the sealing rings might be formed of aluminum.

  7. Gas-path leakage seal for a gas turbine

    DOE Patents [OSTI]

    Wolfe, C.E.; Dinc, O.S.; Bagepalli, B.S.; Correia, V.H.; Aksit, M.F.

    1996-04-23T23:59:59.000Z

    A gas-path leakage seal is described for generally sealing a gas-path leakage-gap between spaced-apart first and second members of a gas turbine (such as combustor casing segments). The seal includes a generally imperforate foil-layer assemblage which is generally impervious to gas and is located in the leakage-gap. The seal also includes a cloth-layer assemblage generally enclosingly contacting the foil-layer assemblage. In one seal, the first edge of the foil-layer assemblage is left exposed, and the foil-layer assemblage resiliently contacts the first member near the first edge to reduce leakage in the ``plane`` of the cloth-layer assemblage under conditions which include differential thermal growth of the two members. In another seal, such leakage is reduced by having a first weld-bead which permeates the cloth-layer assemblage, is attached to the metal-foil-layer assemblage near the first edge, and unattachedly contacts the first member. 4 figs.

  8. Radioactive waste management in the former USSR

    SciTech Connect (OSTI)

    Bradley, D.J.

    1992-06-01T23:59:59.000Z

    Radioactive waste materials--and the methods being used to treat, process, store, transport, and dispose of them--have come under increased scrutiny over last decade, both nationally and internationally. Nuclear waste practices in the former Soviet Union, arguably the world's largest nuclear waste management system, are of obvious interest and may affect practices in other countries. In addition, poor waste management practices are causing increasing technical, political, and economic problems for the Soviet Union, and this will undoubtedly influence future strategies. this report was prepared as part of a continuing effort to gain a better understanding of the radioactive waste management program in the former Soviet Union. the scope of this study covers all publicly known radioactive waste management activities in the former Soviet Union as of April 1992, and is based on a review of a wide variety of literature sources, including documents, meeting presentations, and data base searches of worldwide press releases. The study focuses primarily on nuclear waste management activities in the former Soviet Union, but relevant background information on nuclear reactors is also provided in appendixes.

  9. Radioactive Contamination of Danish Territory

    E-Print Network [OSTI]

    » & Risø-R-462 Radioactive Contamination of Danish Territory after Core-melt Accidents 1982 Risø National Laboratory, DK-4000 Roskilde, Denmark #12;RISØ-R-462 RADIOACTIVE CONTAMINATION contamination of Danish territory in the event of a core-melt accident at the Barseback nuclear power plant

  10. Radioactive Material Transportation Practices Manual

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

    2008-06-04T23:59:59.000Z

    This Manual establishes standard transportation practices for the Department of Energy, including National Nuclear Security Administration to use in planning and executing offsite shipments of radioactive materials and waste. The revision reflects ongoing collaboration of DOE and outside organizations on the transportation of radioactive material and waste. Cancels DOE M 460.2-1.

  11. CHERNOBYL DATA BASE ENVIRONMENTAL RADIOACTIVITY

    E-Print Network [OSTI]

    MAY 1990 THE NORDIC CHERNOBYL DATA BASE ENVIRONMENTAL RADIOACTIVITY MEASUREMENTS Nordic liaison CHERNOBYL DATA BASE ENVIRONMENTAL RADIOACTIVITY MEASUREMENTS Final Report of the NKA Project AKT 242 Edited the members of the working group. Graphic Systems AB, Malmo 1990 #12;111 ABSTRACT. The NORDIC CHERNOBYL DATA

  12. Radioactive Samples / Materials at the APS

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

    Using Radioactive Samples Materials at the APS The use of radioactive samples requires additional information for review and approval. All proposed experiments involving...

  13. Casingless down-hole for sealing an ablation volume and obtaining a sample for analysis

    DOE Patents [OSTI]

    Noble, Donald T. (Ames, IA); Braymen, Steven D. (Ames, IA); Anderson, Marvin S. (Ames, IA)

    1996-10-01T23:59:59.000Z

    A casing-less down hole sampling system for acquiring a subsurface sample for analysis using an inductively coupled plasma system is disclosed. The system includes a probe which is pushed into the formation to be analyzed using a hydraulic ram system. The probe includes a detachable tip member which has a soil point mad a barb, with the soil point aiding the penetration of the earth, and the barb causing the tip member to disengage from the probe and remain in the formation when the probe is pulled up. The probe is forced into the formation to be tested, and then pulled up slightly, to disengage the tip member and expose a column of the subsurface formation to be tested. An instrumentation tube mounted in the probe is then extended outward from the probe to longitudinally extend into the exposed column. A balloon seal mounted on the end of the instrumentation tube allows the bottom of the column to be sealed. A source of laser radiation is emitted from the instrumentation tube to ablate a sample from the exposed column. The instrumentation tube can be rotated in the probe to sweep the laser source across the surface of the exposed column. An aerosol transport system carries the ablated sample from the probe to the surface for testing in an inductively coupled plasma system. By testing at various levels in the down-hole as the probe is extracted from the soil, a profile of the subsurface formation may be obtained.

  14. Casingless down-hole for sealing an ablation volume and obtaining a sample for analysis

    DOE Patents [OSTI]

    Noble, D.T.; Braymen, S.D.; Anderson, M.S.

    1996-10-01T23:59:59.000Z

    A casing-less down hole sampling system for acquiring a subsurface sample for analysis using an inductively coupled plasma system is disclosed. The system includes a probe which is pushed into the formation to be analyzed using a hydraulic ram system. The probe includes a detachable tip member which has a soil point and a barb, with the soil point aiding the penetration of the earth, and the barb causing the tip member to disengage from the probe and remain in the formation when the probe is pulled up. The probe is forced into the formation to be tested, and then pulled up slightly, to disengage the tip member and expose a column of the subsurface formation to be tested. An instrumentation tube mounted in the probe is then extended outward from the probe to longitudinally extend into the exposed column. A balloon seal mounted on the end of the instrumentation tube allows the bottom of the column to be sealed. A source of laser radiation is emitted from the instrumentation tube to ablate a sample from the exposed column. The instrumentation tube can be rotated in the probe to sweep the laser source across the surface of the exposed column. An aerosol transport system carries the ablated sample from the probe to the surface for testing in an inductively coupled plasma system. By testing at various levels in the down-hole as the probe is extracted from the soil, a profile of the subsurface formation may be obtained. 9 figs.

  15. Journal of Power Sources 196 (2011) 12161221 Contents lists available at ScienceDirect

    E-Print Network [OSTI]

    Van Zee, John W.

    2011-01-01T23:59:59.000Z

    , USA a r t i c l e i n f o Article history: Received 15 July 2010 Received in revised form 25 August membrane fuel cell (PEMFC) is a promising power source for many applications such as automobiles. Sealing

  16. Comparison of a Slanted-Tooth See-Through Labyrinth Seal to a Straight-Tooth See-Through Labyrinth Seal for Rotordynamic Coefficients and Leakage

    E-Print Network [OSTI]

    Mehta, Naitik

    2012-07-16T23:59:59.000Z

    .... 62 Table 41. Raw data for straight-tooth labyrinth seal at 10,200 rpm, 0.4 PR, medium preswirl ... 62 Table 42. Raw data for straight-tooth labyrinth seal at 15,350 rpm, 0.4 PR, medium preswirl ... 63 Table 43. Raw data for straight-tooth labyrinth... seal at 20,200 rpm, 0.4 PR, medium preswirl ... 63 Table 44. Raw data for straight-tooth labyrinth seal at 10,200 rpm, 0.5 PR, medium preswirl ... 64 Table 45. Raw data for straight-tooth labyrinth seal at 15,350 rpm, 0.5 PR, medium preswirl ... 64...

  17. Down hole drilling motor with pressure balanced bearing seals

    SciTech Connect (OSTI)

    McDonald, W.J.

    1981-01-27T23:59:59.000Z

    A down hole drilling motor, e.g., A turbodrill, which is connected to a string of drill pipe has a rotating shaft for driving a drill bit which may be a rotary bit or a high speed solid head diamond bit. The turbine section has rotor and stator blades which are crescent shaped in cross section with each blade having an exit angle of 14*-23* for maximum turbine efficiency. The bearing shaft is provided with chevron rotary seals positioned below the rotary bearings carrying both radial and vertical thrust. Fluid lubricant fills the space from the rotary seals to a predetermined level above the bearings. A piston seals the lubricant chamber and is pressurized by drilling fluid (I.E. Mud) flowing through the tool. A layer of lubricant fluid overlies the first piston and has a second piston covering said fluid and transmitting pressure from the drilling fluid to the lubricant fluid surrounding the bearings. The drilling mud that causes the turbodrill to rotate is pumped away from the bearing seals by pump means operated by the drilling motor to balance the pressure on the upper and lower bearing seals.

  18. Rotordynamic coefficients and leakage flow of parallel-grooved liquid-seals

    E-Print Network [OSTI]

    Kilgore, James Joseph

    1988-01-01T23:59:59.000Z

    versus AP and running speed for seals 1 and 2 s Measured and predicted Cq s x 1000 versus AP and running speed for seals 3 and 4 1 Measured and predicted Cg ' x 1000 versus DP and running speed for seals 5 and 6 1 Measured and predicted Cq ' x 1000... versus DP and running speed for seals 7 a. nd 8 1 Measured and predicted Cg s x 1000 versus AP and running speed for seal 9 t Typical speed dependency for experimental values of Cs ' x 1000 versus DP and running speed, shown for seal 2 Measured...

  19. Program for the improvement of downhole drilling motor bearings and seals. Phase V. Final report

    SciTech Connect (OSTI)

    DeLafosse, P.H.; Tibbitts, G.A.; Black, A.D.; DiBona, B.G.

    1983-08-01T23:59:59.000Z

    The work done during the fifth and final phase of a program to improve downhole drilling motor bearing and seals is described. The principal activities in this phase were: (a) testing seals with abrasive-laden mud on the low-pressure side; (b) test second and third generation designs of both elastomeric chevron seals and Teflon U-seals; and (c) testing a full-scale bearing/seal package. Several operating parameters which have a radical effect on seal life were identified, and some promising designs and materials were tested.

  20. Geological problems in radioactive waste isolation - A world wide review

    SciTech Connect (OSTI)

    Witherspoon, P.A. [Lawrence Berkeley Lab., CA (United States)

    1991-06-01T23:59:59.000Z

    The problem of isolating radioactive wastes from the biosphere presents specialists in the earth sciences with some of the most complicated problems they have ever encountered. This is especially true for high-level waste (HLW), which must be isolated in the underground and away from the biosphere for thousands of years. The most widely accepted method of doing this is to seal the radioactive materials in metal canisters that are enclosed by a protective sheath and placed underground in a repository that has been carefully constructed in an appropriate rock formation. Much new technology is being developed to solve the problems that have been raised, and there is a continuing need to publish the results of new developments for the benefit of all concerned. Table 1 presents a summary of the various formations under investigation according to the reports submitted for this world wide review. It can be seen that in those countries that are searching for repository sites, granitic and metamorphic rocks are the prevalent rock type under investigation. Six countries have developed underground research facilities that are currently in use. All of these investigations are in saturated systems below the water table, except the United States project, which is in the unsaturated zone of a fractured tuff.

  1. PCBs have declined more than DDT-group residues in Arctic ringed seals (Phoca hispida) between 1972 and 1981

    SciTech Connect (OSTI)

    Addison, R.F.; Zinck, M.E.; Smith, T.G.

    1986-03-01T23:59:59.000Z

    Mean DDT-group concentrations in the blubber of western Arctic ringed seals (Phoca hispida) sampled in 1981 were less than 1..mu..g.g/sup -1/ wet weight. Male seals had higher concentrations than did females. PCB concentrations were about half of those in a sample of the same population taken in 1972, when allowance was made for the variation of residue concentrations with age, sex, and condition. This decline probably results from the ban on PCB manufacture and use imposed in the early 1970s. Concentrations of DDT-group residues did not show any clear decline over the same interval, and the relative proportions of p,p'-DDT and p,p'-DDE suggested that there is a continuing supply of DDT to the western Arctic. The most probable source of this is by atmospheric or water transport from the Far East, where DDT was used until at least the late 1970s.

  2. Greater-than-Class C low-level radioactive waste shipping package/container identification and requirements study. National Low-Level Waste Management Program

    SciTech Connect (OSTI)

    Tyacke, M.

    1993-08-01T23:59:59.000Z

    This report identifies a variety of shipping packages (also referred to as casks) and waste containers currently available or being developed that could be used for greater-than-Class C (GTCC) low-level waste (LLW). Since GTCC LLW varies greatly in size, shape, and activity levels, the casks and waste containers that could be used range in size from small, to accommodate a single sealed radiation source, to very large-capacity casks/canisters used to transport or dry-store highly radioactive spent fuel. In some cases, the waste containers may serve directly as shipping packages, while in other cases, the containers would need to be placed in a transport cask. For the purpose of this report, it is assumed that the generator is responsible for transporting the waste to a Department of Energy (DOE) storage, treatment, or disposal facility. Unless DOE establishes specific acceptance criteria, the receiving facility would need the capability to accept any of the casks and waste containers identified in this report. In identifying potential casks and waste containers, no consideration was given to their adequacy relative to handling, storage, treatment, and disposal. Those considerations must be addressed separately as the capabilities of the receiving facility and the handling requirements and operations are better understood.

  3. Seal inlet disturbance boundary conditions for rotordynamic models and influence of some off-design conditions on labyrinth rotordynamic instability

    E-Print Network [OSTI]

    Xi, Jinxiang

    2007-04-25T23:59:59.000Z

    Systematic parametric studies were performed to better understand seal-inlet rotordynamics. A CFD-perturbation model was employed to compute the seal-inlet flow disturbance quantities. Seal inlet disturbance boundary condition correlations were...

  4. The Effect of High Rotational Speed on the Performance of Straight-through Labyrinth Seals for Compressible and Incompressible Flow

    E-Print Network [OSTI]

    Obidigbo, Ekene R.

    2012-07-16T23:59:59.000Z

    The leakage flow through straight through labyrinth seals with tooth on stator was investigated by performing CFD simulations .ANSYS Fluent is used to simulate the fluid flow through straight through Labyrinth seals. The effect of seal geometry...

  5. Gas-path leakage seal for a turbine

    DOE Patents [OSTI]

    Bagepalli, B.S.; Aksit, M.F.; Farrell, T.R.

    1999-08-10T23:59:59.000Z

    A gas-path leakage seal for generally sealing a gas-path leakage-gap between spaced-apart first and second members of a turbine (such as combustor casing segments of a gas turbine). The seal includes a flexible and generally imperforate metal sheet assemblage having opposing first and second surfaces and two opposing raised edges extending a generally identical distance above and below the surfaces. A first cloth layer assemblage has a thickness generally equal to the previously-defined identical distance and is superimposed on the first surface between the raised edges. A second cloth layer assemblage is generally identical to the first cloth layer assemblage and is superimposed on the second surface between the raised edges. 5 figs.

  6. Resilient Sealing Materials for Solid Oxide Fuel Cells

    SciTech Connect (OSTI)

    Signo T. Reis; Richard K. Brow

    2006-09-30T23:59:59.000Z

    This report describes the development of ''invert'' glass compositions designed for hermetic seals in solid oxide fuel cells (SOFC). Upon sealing at temperatures compatible with other SOFC materials (generally {le}900 C), these glasses transform to glass-ceramics with desirable thermo-mechanical properties, including coefficients of thermal expansion (CTE) over 11 x 10{sup -6}/C. The long-term (>four months) stability of CTE under SOFC operational conditions (e.g., 800 C in wet forming gas or in air) has been evaluated, as have weight losses under similar conditions. The dependence of sealant properties on glass composition are described in this report, as are experiments to develop glass-matrix composites by adding second phases, including Ni and YSZ. This information provides design-guidance to produce desirable sealing materials.

  7. Theory of the leak-rate of seals

    E-Print Network [OSTI]

    B. N. J. Persson; C. Yang

    2008-05-06T23:59:59.000Z

    Seals are extremely useful devices to prevent fluid leakage. However, the exact mechanism of roughness induced leakage is not well understood. We present a theory of the leak-rate of seals, which is based on percolation theory and a recently developed contact mechanics theory. We study both static and dynamics seals. We present molecular dynamics results which show that when two elastic solids with randomly rough surfaces are squeezed together, as a function of increasing magnification or decreasing squeezing pressure, a non-contact channel will percolate when the (relative) projected contact area, A/A_0, is of order 0.4, in accor dance with percolation theory. We suggest a simple experiment which can be used to test the theory.

  8. Radioactive waste material melter apparatus

    DOE Patents [OSTI]

    Newman, Darrell F. (Richland, WA); Ross, Wayne A. (Richland, WA)

    1990-01-01T23:59:59.000Z

    An apparatus for preparing metallic radioactive waste material for storage is disclosed. The radioactive waste material is placed in a radiation shielded enclosure. The waste material is then melted with a plasma torch and cast into a plurality of successive horizontal layers in a mold to form a radioactive ingot in the shape of a spent nuclear fuel rod storage canister. The apparatus comprises a radiation shielded enclosure having an opening adapted for receiving a conventional transfer cask within which radioactive waste material is transferred to the apparatus. A plasma torch is mounted within the enclosure. A mold is also received within the enclosure for receiving the melted waste material and cooling it to form an ingot. The enclosure is preferably constructed in at least two parts to enable easy transport of the apparatus from one nuclear site to another.

  9. Radioactive waste material melter apparatus

    DOE Patents [OSTI]

    Newman, D.F.; Ross, W.A.

    1990-04-24T23:59:59.000Z

    An apparatus for preparing metallic radioactive waste material for storage is disclosed. The radioactive waste material is placed in a radiation shielded enclosure. The waste material is then melted with a plasma torch and cast into a plurality of successive horizontal layers in a mold to form a radioactive ingot in the shape of a spent nuclear fuel rod storage canister. The apparatus comprises a radiation shielded enclosure having an opening adapted for receiving a conventional transfer cask within which radioactive waste material is transferred to the apparatus. A plasma torch is mounted within the enclosure. A mold is also received within the enclosure for receiving the melted waste material and cooling it to form an ingot. The enclosure is preferably constructed in at least two parts to enable easy transport of the apparatus from one nuclear site to another. 8 figs.

  10. Borehole sounding device with sealed depth and water level sensors

    DOE Patents [OSTI]

    Skalski, Joseph C.; Henke, Michael D.

    2005-08-02T23:59:59.000Z

    A borehole device having proximal and distal ends comprises an enclosure at the proximal end for accepting an aircraft cable containing a plurality of insulated conductors from a remote position. A water sensing enclosure is sealingly attached to the enclosure and contains means for detecting water, and sending a signal on the cable to the remote position indicating water has been detected. A bottom sensing enclosure is sealingly attached to the water sensing enclosure for determining when the borehole device encounters borehole bottom and sends a signal on the cable to the remote position indicating that borehole bottom has been encountered.

  11. High pressure testing of see-through labyrinth seals

    E-Print Network [OSTI]

    Picardo, Arthur Michael

    2003-01-01T23:59:59.000Z

    of labyrinth tooth Impedance Inches of water [UT'] [L) [L) [FT/L] [FT/L] [FT/L] [FT/L] [L] [L] [F] [F] [UT ] [L] [F/L] [L] K;; m, N NT pe PR PS R Direct stiffness Cross-coupled stiffness Stiffness Coefficient Seal Length Stator... the exit-labyrinth seals. Section A-A in Figure 4 gives the location of swirl brakes. Btmor Inlet Annulus Back Pr'asnua Anfsrlur Shaker Btmgars (2 (9 90 ) Thmmomuple Pressure Traraduccfs (2 e sf ) et Prrmnlrf Btrg Pmmum Therm ocormles Transducers...

  12. Leaf seal for transition duct in turbine system

    DOE Patents [OSTI]

    Flanagan, James Scott; LeBegue, Jeffrey Scott; McMahan, Kevin Weston; Dillard, Daniel Jackson; Pentecost, Ronnie Ray

    2013-06-11T23:59:59.000Z

    A turbine system is disclosed. In one embodiment, the turbine system includes a transition duct. The transition duct includes an inlet, an outlet, and a passage extending between the inlet and the outlet and defining a longitudinal axis, a radial axis, and a tangential axis. The outlet of the transition duct is offset from the inlet along the longitudinal axis and the tangential axis. The transition duct further includes an interface member for interfacing with a turbine section. The turbine system further includes a leaf seal contacting the interface member to provide a seal between the interface member and the turbine section.

  13. Flexible metallic seal for transition duct in turbine system

    DOE Patents [OSTI]

    Flanagan, James Scott; LeBegue, Jeffrey Scott; McMahan, Kevin Weston; Dillard, Daniel Jackson; Pentecost, Ronnie Ray

    2014-04-22T23:59:59.000Z

    A turbine system is disclosed. In one embodiment, the turbine system includes a transition duct. The transition duct includes an inlet, an outlet, and a passage extending between the inlet and the outlet and defining a longitudinal axis, a radial axis, and a tangential axis. The outlet of the transition duct is offset from the inlet along the longitudinal axis and the tangential axis. The transition duct further includes an interface member for interfacing with a turbine section. The turbine system further includes a flexible metallic seal contacting the interface member to provide a seal between the interface member and the turbine section.

  14. Predicting the Performance of Edge Seal Materials for PV (Presentation)

    SciTech Connect (OSTI)

    Kempe, M.; Panchagade, D.; Dameron, A.; Reese, M.

    2012-03-01T23:59:59.000Z

    Edge seal materials were evaluated using a 100-nm film of Ca deposited on glass and laminated to another glass substrate. As moisture penetrates the package it converts the Ca metal to transparent CaOH2 giving a clear indication of the depth to which moisture has entered. Using this method, we have exposed test samples to a variety of temperature and humidity conditions ranging from 45C and 10% RH up to 85C and 85% RH, to ultraviolet radiation and to mechanical stress. We are able to show that edge seal materials are capable of keeping moisture away from sensitive cell materials for the life of a module.

  15. Dismantlement and Radioactive Waste Management of DPRK Nuclear Facilities

    SciTech Connect (OSTI)

    Jooho, W.; Baldwin, G. T.

    2005-04-01T23:59:59.000Z

    One critical aspect of any denuclearization of the Democratic People’s Republic of Korea (DPRK) involves dismantlement of its nuclear facilities and management of their associated radioactive wastes. The decommissioning problem for its two principal operational plutonium facilities at Yongbyun, the 5MWe nuclear reactor and the Radiochemical Laboratory reprocessing facility, alone present a formidable challenge. Dismantling those facilities will create radioactive waste in addition to existing inventories of spent fuel and reprocessing wastes. Negotiations with the DPRK, such as the Six Party Talks, need to appreciate the enormous scale of the radioactive waste management problem resulting from dismantlement. The two operating plutonium facilities, along with their legacy wastes, will result in anywhere from 50 to 100 metric tons of uranium spent fuel, as much as 500,000 liters of liquid high-level waste, as well as miscellaneous high-level waste sources from the Radiochemical Laboratory. A substantial quantity of intermediate-level waste will result from disposing 600 metric tons of graphite from the reactor, an undetermined quantity of chemical decladding liquid waste from reprocessing, and hundreds of tons of contaminated concrete and metal from facility dismantlement. Various facilities for dismantlement, decontamination, waste treatment and packaging, and storage will be needed. The shipment of spent fuel and liquid high level waste out of the DPRK is also likely to be required. Nuclear facility dismantlement and radioactive waste management in the DPRK are all the more difficult because of nuclear nonproliferation constraints, including the call by the United States for “complete, verifiable and irreversible dismantlement,” or “CVID.” It is desirable to accomplish dismantlement quickly, but many aspects of the radioactive waste management cannot be achieved without careful assessment, planning and preparation, sustained commitment, and long completion times. The radioactive waste management problem in fact offers a prospect for international participation to engage the DPRK constructively. DPRK nuclear dismantlement, when accompanied with a concerted effort for effective radioactive waste management, can be a mutually beneficial goal.

  16. A new three-control-volume theory for circumferentially-grooved liquid seals

    E-Print Network [OSTI]

    Marquette, Olivier Robert

    1994-01-01T23:59:59.000Z

    Circumferentially-grooved seals are used in centrifugal pumps to reduce leakage flow. Florjancic (1990) developed an analysis using a partition of the seal into three control volumes, bulk-flow theory and Hirs' lubrication equations. This thesis...

  17. Chip Seals for Asphalt Concrete Pavements: A Proposed Emulsion Residue Specification and Existing Pavement Texture Evaluation

    E-Print Network [OSTI]

    Hoyt, Denise

    2012-07-16T23:59:59.000Z

    Chip seals are a pavement surface treatment used for maintaining asphalt concrete pavements. National Cooperative Highway Research Program (NCHRP) Project 14-17 was performed to produce a national Chip Seal Manual which would consolidate the best...

  18. Manufacturing of lab-on-a-chip devices : characterizing seals for on-board reagent delivery

    E-Print Network [OSTI]

    Inamdar, Tejas Satish

    2013-01-01T23:59:59.000Z

    The reagent delivery mechanism in a point-of-care, HIV diagnostic, microfluidic device is studied. Reagents held in an aluminum pack are released on the opening of a fluidic seal. Fluidic seals, controlling the flow of ...

  19. Program for the improvement of downhole drilling motor bearings and seals. Phase IV. Final report

    SciTech Connect (OSTI)

    Tibbets, G.A.; DeLafosse, P.H.; Black, A.; Green, S.J.

    1981-04-01T23:59:59.000Z

    Test results are presented from the seal test machine and bearing-seal package. An overal program summary is given and the major milestones of this phase of the program are shown. (MHR)

  20. Exploring the mechanisms critical to the operation of metal face seals through modeling and experiments

    E-Print Network [OSTI]

    Wang, Yong, Ph. D. Massachusetts Institute of Technology, Dept. of Aeronautics and Astronautics

    2008-01-01T23:59:59.000Z

    This thesis aims to explore operation mechanisms of a special type of mechanical face seals: the flexible metal-to-metal face seal (FMMFS). Unique features of the FMMFS include much more flexibility in the circumferential ...

  1. Experimental measurement and analysis of wall pressure distribution for a 50% eccentric whirling annular seal 

    E-Print Network [OSTI]

    Suryanarayanan, Arun

    2004-11-15T23:59:59.000Z

    In any rotating machinery, the geometry of the seal influences the extent of systemleakage. The path taken by the flow in the clearance volume is dependent on the seal and rotor profile. The clearance between a new ...

  2. The Global Threat Reduction Initiative's Orphan Source Recovery Project in the Russian Federation

    SciTech Connect (OSTI)

    Russell, J. W. [NSTec; Ahumada, A. D. [NSTec; Blanchard, T. A. [NNSA

    2012-06-04T23:59:59.000Z

    After 9/11, officials at the United States Department of Energy (DOE), National Nuclear Security Administration (NNSA) grew more concerned about radiological materials that were vulnerable to theft and illicit use around the world. The concern was that terrorists could combine stolen radiological materials with explosives to build and detonate a radiological dispersal device (RDD), more commonly known as a “dirty bomb.” In response to this and other terrorist threats, the DOE/NNSA formed what is now known as the Global Threat Reduction Initiative (GTRI) to consolidate and accelerate efforts to reduce and protect vulnerable nuclear and radiological materials located at civilian sites worldwide. Although a cooperative program was already underway in the Russian Federation to secure nuclear materials at a range of different facilities, thousands of sealed radioactive sources remained vulnerable at medical, research, and industrial sites. In response, GTRI began to focus efforts on addressing these materials. GTRI’s Russia Orphan Source Recovery Project, managed at the Nevada National Security Site’s North Las Vegas facility, was initiated in 2002. Throughout the life of the project, Joint Stock Company “Isotope” has served as the primary Russian subcontractor, and the organization has proven to be a successful partner. Since the first orphan source recovery of an industrial cobalt-60 irradiator with 647 curies (Ci) at an abandoned facility in Moscow in 2003, the GTRI Orphan Source Recovery Project in the Russian Federation has accomplished substantial levels of threat reduction. To date, GTRI has recovered and securely disposed of more than 5,100 sources totaling more that 628,000 Ci. This project serves as an extraordinary example of how international cooperation can be implemented by partners with mutual interests to achieve significant goals.

  3. Method for making radioactive metal articles having small dimensions

    DOE Patents [OSTI]

    Ohriner, Evan K. (Knoxville, TN)

    2000-01-01T23:59:59.000Z

    A method for making a radioactive article such as wire, includes the steps of providing a metal article having a first shape, such a cylinder, that is either radioactive itself or can be converted to a second, radioactive isotope by irradiation; melting the metal article one or more times; optionally adding an alloying metal to the molten metal in order to enhance ductility or other properties; placing the metal article having the first shape (e.g., cylindrical) into a cavity in the interior of an extrusion body (e.g., a cylinder having a cylindrical cavity therein); extruding the extrusion body and the article having the first shape located in the cavity therein, resulting in an elongated extrusion body and an article having a second shape; removing the elongated extrusion body, for example by chemical means, leaving the elongated inner article substantially intact; optionally repeating the extrusion procedure one or more times; and then drawing the elongated article to still further elongate it, into wire, foil, or another desired shape. If the starting metal is enriched in a radioactive isotope or a precursor thereof, the end product can provide a more intense radiation source than conventionally manufactured radioactive wire, foil, or the like.

  4. Department of Mechanical Engineering Fall 2012 Dresser-Rand 3 Adjustable Impeller Eye Labyrinth Seal

    E-Print Network [OSTI]

    Demirel, Melik C.

    was constructed with 3D print models of the segmented seal and actuating ring. Outcomes · The sponsor will save

  5. Controlled-force end seal arrangement for an air press of a papermaking machine

    DOE Patents [OSTI]

    Beck, David A.

    2003-07-08T23:59:59.000Z

    An air press for pressing a fiber web includes a plurality of rolls and a pair of end seal arrangements. Of the plurality of rolls, each pair of adjacent rolls forms a nip therebetween. Further, each roll has a pair of roll ends, the plurality of rolls together forming two sets of roll ends. Each end seal arrangement coacts with one set of roll ends, the plurality of rolls and the pair of end seal arrangements together defining an air press chamber having an air chamber pressure. Each end seal arrangement is composed of at least one roll seal, including a first roll seal, and an adjustable bias mechanism. Each roll seal forms a seal with at least one roll end, and one side of the first roll seal being exposed to the air chamber pressure. The adjustable bias mechanism is configured for controlling a position of each roll seal relative to a respective at least one roll end and for adjusting a seal force between the roll seal and the respective at least one roll end.

  6. `Might is Right'. A study of the Cape Town/Crozets elephant seal oil trade (18321869).

    E-Print Network [OSTI]

    de Villiers, Marienne

    `Might is Right'. A study of the Cape Town/Crozets elephant seal oil trade (1832­1869). BY Thierry involvement in the elephant seal oil trade on the Prince Edward Islands and Crozet Islands between the years 1832­1869. The Cape Town/Crozets elephant seal oil trade was a lucrative branch of the Cape Colony

  7. Comparison of the Leakage Characteristics of the Straight Annular and Convergent Seals

    E-Print Network [OSTI]

    Ustun, Serafettin

    2012-10-19T23:59:59.000Z

    independent analysis) ........ 17 Fig. 7 Comparison of the standard k-? and enhanced wall treatment models (convergent seal, Cex=0.1 mm) ..................................................................... 19 Fig. 8 Comparison of the standard k...-? and enhanced wall treatment models (straight annular seal, Cex=0.1 mm) ............................................................... 20 Fig. 9 Pressure contours for the convergent and straight annular seals (rotor wall, 20,200 rpm...

  8. Large-scale experimental investigation of flow characteristics in labyrinth seal geometries

    E-Print Network [OSTI]

    Younger, James Stanton

    1994-01-01T23:59:59.000Z

    density and absolute viscosity must be taken into account when ca)culating the corresponding flow Reynolds number for a particular seal leakage test. Labyrinth Seal Test-section The labyrinth seal test-section is comprised of a 0. 914 m x 0. 914 m x 2...

  9. Method of processing "BPS" glass ceramic and seals made therewith

    DOE Patents [OSTI]

    Reed, Scott T. (Albuquerque, NM); Stone, Ronald G. (Albuquerque, NM); McCollister, Howard L. (Albuquerque, NM); Wengert, deceased, Paul R. (late of Albuquerque, NM)

    1998-01-01T23:59:59.000Z

    A glass ceramic composition, a glass ceramic-to-metal seal, and more specifically a hermetic glass ceramic-to-metal seal prepared by subjecting a glass composition comprising, by weight percent, SiO.sub.2 (65-80%), LiO.sub.2 (8-16%), Al.sub.2 O.sub.3 (2-8%), K.sub.2 O (1-8%), P.sub.2 O.sub.5 (1-5%), B.sub.2 O.sub.3 (0.5-7%), and ZnO (0-5%) to the following processing steps: 1) heating the glass composition in a belt furnace to a temperature sufficient to melt the glass and crystallize lithium phosphate, 2) holding at a temperature and for a time sufficient to create cristobalite nuclei, 3) cooling at a controlled rate and to a temperature to cause crystallization of lithium silicates and growth of cristobalite, and 4) still further cooling in stages to ambient temperature. This process produces a glass ceramic whose high coefficient of thermal expansion (up to 200.times.10.sup.-7 in/in/.degree.C.) permits the fabrication of glass ceramic-to-metal seals, and particularly hermetic glass ceramic seals to nickel-based and stainless steel alloys and copper.

  10. Exploration of Ion-Exchanged Glass for Seals Applications 

    E-Print Network [OSTI]

    Ghanbari, Roushan

    2012-10-19T23:59:59.000Z

    to the same point load, the fracture patterns produced can be compared and used as a verification measure. This technology has the potential to be used in passive seal applications. Each image was categorized depending on its fracture as a "3 leaf" or "4 leaf...

  11. Preparation of Samples for Light Microscopy Simple Wax Seal

    E-Print Network [OSTI]

    Fygenson, Deborah Kuchnir

    Preparation of Samples for Light Microscopy Simple Wax Seal Materials - Slide - Cover Slip - Paraffin Wax Candle - Pasteur Pipette (suggested size 5 3/4 inch) - Matches Preparation of the Slide - You may want to protect the work surface from melted wax. We use a sheet of aluminum foil taped

  12. Down hole drilling motor with pressure balanced bearing seals

    SciTech Connect (OSTI)

    Maurer, W.C.

    1980-09-30T23:59:59.000Z

    A downhole drilling motor, e.g., a turbodrill is described, which is connected to a string of drill pipe has a rotating shaft for driving a drill bit which may be a rotary bit or a high speed solid head diamond bit. The turbine section has rotor and stator blades which are crescent shaped in cross section with each blade having an exit angle of 14-23/sup 0/ for maximum turbine efficiency. The drilling motor may alternatively be a positive displacement motor. The bearing shaft is provided with chevron rotary seals positioned below the rotary bearings carrying both radial and vertical thrust. Fluid lubricant fills the space from the rotary seals to a predetermined level above the bearings. A piston seals the lubricant chamber and is pressurized by drilling fluid (i.e. mud) flowing through the tool. A layer of lubricant fluid overlies the first piston and has a second piston covering said fluid and transmitting pressure from the drilling fluid to the lubricant fluid surrounding the bearings. The drilling mud is divided into two streams, one of which rotates the drill bit, and the other of which passes through the drill bit. The pressure drop across the drilling motor equals the pressure drop across the drill bit, thus balancing the pressure on the bearing seals.

  13. 1 INTRODUCTION Geosynthetic Clay Liners (GCLs) are sealing ele-

    E-Print Network [OSTI]

    Boyer, Edmond

    1 INTRODUCTION Geosynthetic Clay Liners (GCLs) are sealing ele- ments which contain bentonite: A significant number of studies have been published on the field performance of Geosynthetic Clay Liners (GCLs encapsulated between geotextile components. They have been mostly em- ployed to replace clay liners in landfill

  14. Advances in associated-particle sealed-tube neutron probe diagnostics for substance detection

    SciTech Connect (OSTI)

    Rhodes, E.; Dickerman, C.E. [Argonne National Lab., IL (United States); Frey, M. [MF Physics Corp., Colorado Springs, CO (United States)

    1995-07-01T23:59:59.000Z

    The development and investigation of a small associated-particle sealed-tube neutron generator (APSTNG) shows potential to allow the associated-particle diagnostic method to be moved out of the laboratory into field applications. The APSTNG interrogates the inspected object with 14-MeV neutrons generated from the deuterium-tritium reaction and detects the alpha-particle associated with each neutron inside a cone encompassing the region of interest. Gamma-ray spectra of resulting neutron reactions identify many nuclides. Flight-times determined from detection times of the gamma-rays and alpha-particles can yield a separate coarse tomographic image of each identified nuclide, from a single orientation. Chemical substances are identified by comparing relative spectral line intensities with ratios of elements in reference compounds. The high-energy neutrons and gamma-rays penetrate large objects and dense materials. Generally no collimators or radiation shielding are needed. Proof-of-concept laboratory experiments have been successfully performed for simulated nuclear, chemical warfare, and conventional munitions. Most recently, inspection applications have been investigated for radioactive waste characterization, presence of cocaine in propane tanks, and uranium and plutonium smuggling. Based on lessons learned with the present APSTNG system, an advanced APSTNG tube (along with improved high voltage supply and control units) is being designed and fabricated that will be transportable and rugged, yield a substantial neutron output increase, and provide sufficiently improved lifetime to allow operation at more than an order of magnitude increase in neutron flux.

  15. 96 RADIATION SAFETY MANUAL (REVISED MARCH 2010) STATEMENT OF TRAINING AND EXPERIENCE FOR USE OF

    E-Print Network [OSTI]

    sealed radioactive sources XRD irradiator XRF medical xray nonmedical EMITTERS WHAT DEVICES HAVE YOU USED: XRD selfshielded irradiator XRF medical xray

  16. 1

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

    Removal Program and OSRP mission includes removal and disposal of excess, unwanted, abandoned, or orphan radioactive sealed sources that pose a potential risk to national...

  17. Rotary seal with enhanced lubrication and contaminant flushing

    DOE Patents [OSTI]

    Dietle, Lannie L. (Sugar Land, TX)

    2000-01-01T23:59:59.000Z

    A resilient, ring shaped interference-type hydrodynamic rotary seal having waves on the lubricant side which provide increased film thickness and flushing action by creating contact pressure induced angulated restrictions formed by abrupt restrictive diverters. The angulated restrictions are defined by projecting ridges, corners at the trailing edge of the waves, or simply by use of a converging shape at the trailing edge of the waves which is more abrupt than the gently converging hydrodynamic inlet shape at the leading edge of the waves. The abrupt restrictive diverter performs two functions; a restricting function and a diverting function. The angulated restrictions cause a local film thickness restriction which produces a damming effect preventing a portion of the lubricant from leaking out of the dynamic sealing interface at the trailing edge of the wave, and results in a much thicker lubricant film thickness under the waves. This contributes to more film thickness in the remainder of the dynamic sealing interface toward the environment because film thickness tends to decay gradually rather than abruptly due to the relative stiffness of the seal material. Because of the angle of the abrupt restrictive diverter relative to the relative rotation direction, in conjunction with the restriction or damming effect, a strong diverting action is produced which pumps lubricant across the dynamic sealing interface toward the environment. The lubricant diversion is caused by the component of the rotational velocity tangent to the abrupt restrictive diverter. The component of rotational velocity normal to the abrupt restrictive diverter causes a portion of the lubricant film to be pumped past the abrupt restrictive diverter, thereby assuring adequate lubrication thereof.

  18. ACCELERATION OF CHARGE BRED RADIOACTIVE IONS AT TRIUMF F. Ames, R. Baartman, P. Bricault, K. Jayamanna, M. McDonald, P. Schmor,

    E-Print Network [OSTI]

    Paris-Sud XI, Université de

    operation and an Electron Cyclotron Resonance Ion Source (ECRIS) for continuous beam operation. With nearly facility. Mass separated beams of radioactive ions from the on-line ion sources can be directed and from the on-line commissioning. INTRODUCTION At the radioactive beam facility ISAC at TRIUMF

  19. Maine State Briefing Book on low-level radioactive waste management

    SciTech Connect (OSTI)

    Not Available

    1981-08-01T23:59:59.000Z

    The Maine State Briefing Book is one of a series of state briefing books on low-level radioactive waste management practices. It has been prepared to assist state and Federal agency officials in planning for safe low-level radioactive waste disposal. The report contains a profile of low-level radioactive waste generators in Maine. The profile is the result of a survey of radioactive material licensees in Maine. The briefing book also contains a comprehensive assessment of low-level radioactive waste management issues and concerns as defined by all major interested partices including industry, government, the media, and interest groups. The assessment was developed through personal communications with representatives of interested parties, and through a review of media sources. Lastly, the briefing book provides demographic and socioeconomic data and a discussion of relevant goverment agencies and activities, all of which may impact management practices in Maine.

  20. Introduction to naturally occurring radioactive material

    SciTech Connect (OSTI)

    Egidi, P.

    1997-08-01T23:59:59.000Z

    Naturally occurring radioactive material (NORM) is everywhere; we are exposed to it every day. It is found in our bodies, the food we eat, the places where we live and work, and in products we use. We are also bathed in a sea of natural radiation coming from the sun and deep space. Living systems have adapted to these levels of radiation and radioactivity. But some industrial practices involving natural resources concentrate these radionuclides to a degree that they may pose risk to humans and the environment if they are not controlled. Other activities, such as flying at high altitudes, expose us to elevated levels of NORM. This session will concentrate on diffuse sources of technologically-enhanced (TE) NORM, which are generally large-volume, low-activity waste streams produced by industries such as mineral mining, ore benefication, production of phosphate Fertilizers, water treatment and purification, and oil and gas production. The majority of radionuclides in TENORM are found in the uranium and thorium decay chains. Radium and its subsequent decay products (radon) are the principal radionuclides used in characterizing the redistribution of TENORM in the environment by human activity. We will briefly review other radionuclides occurring in nature (potassium and rubidium) that contribute primarily to background doses. TENORM is found in many waste streams; for example, scrap metal, sludges, slags, fluids, and is being discovered in industries traditionally not thought of as affected by radionuclide contamination. Not only the forms and volumes, but the levels of radioactivity in TENORM vary. Current discussions about the validity of the linear no dose threshold theory are central to the TENORM issue. TENORM is not regulated by the Atomic Energy Act or other Federal regulations. Control and regulation of TENORM is not consistent from industry to industry nor from state to state. Proposed regulations are moving from concentration-based standards to dose-based standards. So when is TENORM a problem? Where is it a problem? That depends on when, where, and whom you talk to! We will start by reviewing background radioactivity, then we will proceed to the geology, mobility, and variability of these radionuclides. We will then review some of the industrial sectors affected by TENORM, followed by a brief discussion on regulatory aspects of the issue.

  1. An Investigation of the Integrity of Cemented Casing Seals with Application to Salt Cavern Sealing and Abandonment

    SciTech Connect (OSTI)

    Pfeifle, T.W.; Mellegard, K.D.; Skaug, N.T.; Bruno, M.S.

    2001-04-19T23:59:59.000Z

    This research project was pursued in three key areas. (1) Salt permeability testing under complex stress states; (2) Hydraulic and mechanical integrity investigations of the well casing shoe through benchscale testing; and (3) Geomechanical modeling of the fluid/salt hydraulic and mechanical interaction of a sealed cavern.

  2. Electrostatics and radioactive aerosol behavior

    SciTech Connect (OSTI)

    Clement, C.F.

    1994-12-31T23:59:59.000Z

    Radioactive aerosols differ from their nonradioactive counterparts by their ability to charge themselves by emitting charged particles during the radioactive decay process. Evidence that electrostatics, including this charging process, can affect the transport of the aerosols was summarized previously. Charge distributions and the mean charge for a monodisperse radioactive aerosol have been considered in detail. The principal results of theory to calculate charge distributions on a aerosol with a size distribution, changes to Brownian coagulation rates for an aerosol in a reactor containment, and possible changes to aerosol deposition resulting from the charging will be presented. The main purpose of the work has been to improve calculations of aerosol behavior in reactor containments, but behavior in less ionizing environments will be affected more strongly, and some problems remain to be solved in performing reliable calculations.

  3. Evaluation of radioactive scrap metal recycling

    SciTech Connect (OSTI)

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

    1995-12-01T23:59:59.000Z

    This report evaluates the human health risks and environmental and socio-political impacts of options for recycling radioactive scrap metal (RSM) or disposing of and replacing it. Argonne National Laboratory (ANL) is assisting the US Department of Energy (DOE), Office of Environmental Restoration and Waste Management, Oak Ridge Programs Division, in assessing the implications of RSM management alternatives. This study is intended to support the DOE contribution to a study of metal recycling being conducted by the Task Group on Recycling and Reuse of the Organization for Economic Cooperation and Development. The focus is on evaluating the justification for the practice of recycling RSM, and the case of iron and steel scrap is used as an example in assessing the impacts. To conduct the evaluation, a considerable set of data was compiled and developed. Much of this information is included in this document to provide a source book of information.

  4. Incorporation and distribution of rhenium in a borosilicate glass melt heat treated in a sealed ampoule

    SciTech Connect (OSTI)

    Kim, Dong-Sang; Schweiger, Michael J.

    2013-07-25T23:59:59.000Z

    We investigated a mass balance of rhenium (used as a surrogate for technetium-99) in a borosilicate glass that was mixed with excess Re source (KReO4) beyond its solubility and heat treated in a vacuum-sealed fused silica ampoule. Distribution of Re in the bulk of the glass, in a salt phase formed on the melt surface, and in condensate material deposited on the ampoule wall was evaluated to understand the Re migration into different phases during the reaction between the molten glass and KReO4. The information gained from this study will contribute to an effort to understand the mechanism of technetium retention in or escape from glass melt during early stages of glass batch melting, which is a goal of the present series of studies.

  5. Low torque hydrodynamic lip geometry for bi-directional rotation seals

    DOE Patents [OSTI]

    Dietle, Lannie L. (Houston, TX); Schroeder, John E. (Richmond, TX)

    2011-11-15T23:59:59.000Z

    A hydrodynamically lubricating geometry for the generally circular dynamic sealing lip of rotary seals that are employed to partition a lubricant from an environment. The dynamic sealing lip is provided for establishing compressed sealing engagement with a relatively rotatable surface, and for wedging a film of lubricating fluid into the interface between the dynamic sealing lip and the relatively rotatable surface in response to relative rotation that may occur in the clockwise or the counter-clockwise direction. A wave form incorporating an elongated dimple provides the gradual convergence, efficient impingement angle, and gradual interfacial contact pressure rise that are conducive to efficient hydrodynamic wedging. Skewed elevated contact pressure zones produced by compression edge effects provide for controlled lubricant movement within the dynamic sealing interface between the seal and the relatively rotatable surface, producing enhanced lubrication and low running torque.

  6. Low torque hydrodynamic lip geometry for bi-directional rotation seals

    DOE Patents [OSTI]

    Dietle, Lannie L. (Houston, TX); Schroeder, John E. (Richmond, TX)

    2009-07-21T23:59:59.000Z

    A hydrodynamically lubricating geometry for the generally circular dynamic sealing lip of rotary seals that are employed to partition a lubricant from an environment. The dynamic sealing lip is provided for establishing compressed sealing engagement with a relatively rotatable surface, and for wedging a film of lubricating fluid into the interface between the dynamic sealing lip and the relatively rotatable surface in response to relative rotation that may occur in the clockwise or the counter-clockwise direction. A wave form incorporating an elongated dimple provides the gradual convergence, efficient impingement angle, and gradual interfacial contact pressure rise that are conducive to efficient hydrodynamic wedging. Skewed elevated contact pressure zones produced by compression edge effects provide for controlled lubricant movement within the dynamic sealing interface between the seal and the relatively rotatable surface, producing enhanced lubrication and low running torque.

  7. Remote vacuum or pressure sealing device and method for critical isolated systems

    DOE Patents [OSTI]

    Brock, James David (Newport News, VA); Keith, Christopher D. (Newport News, VA)

    2012-07-10T23:59:59.000Z

    A remote vacuum or pressure sealing apparatus and method for making a radiation tolerant, remotely prepared seal that maintains a vacuum or pressure tight seal throughout a wide temperature range. The remote sealing apparatus includes a fixed threaded sealing surface on an isolated system, a gasket, and an insert consisting of a plug with a protruding sample holder. An insert coupling device, provided for inserting samples within the isolated system, includes a threaded fastener for cooperating with the fixed threaded sealing surface on the isolated system. The insert coupling device includes a locating pin for azimuthal orientation, coupling pins, a tooted coaxial socket wrench, and an insert coupling actuator for actuating the coupling pins. The remote aspect of the sealing apparatus maintains the isolation of the system from the user's environment, safely preserving the user and the system from detrimental effect from each respectively.

  8. Axial seal system for a gas turbine steam-cooled rotor

    DOE Patents [OSTI]

    Mashey, Thomas Charles (Anderson, SC)

    2002-01-01T23:59:59.000Z

    An axial seal assembly is provided at the interface between adjacent wheels and spacers of a gas turbine rotor and disposed about tubes passing through openings in the rotor adjacent the rotor rim and carrying a thermal medium. Each seal assembly includes a support bushing for supporting a land of the thermal medium carrying tube, an axially registering seat bushing disposed in the opposed opening and a frustoconical seal between the seal bushing and seat. The seal bushing includes a radial flange having an annular recess for retaining the outer diameter edge of the seal, while the seat bushing has an axially facing annular surface forming a seat for engagement by the inner diameter edge of the seal.

  9. Gas Spring Losses in Linear Clearance Seal Compressors P.B. Bailey, M.W. Dadd, J.S. Reed*

    E-Print Network [OSTI]

    1 Gas Spring Losses in Linear Clearance Seal Compressors P.B. Bailey, M.W. Dadd, J.S. Reed* , C investigations on conventional crank driven reciprocating compressors, where the use of normal sliding seals would minimise seal losses. The widespread use of linear clearance seals in linear compressor has raised

  10. The influence of a central groove on static and dynamic characteristics of an annular liquid seal with laminar flow

    E-Print Network [OSTI]

    Graviss, Matthew Sheridan

    2005-08-29T23:59:59.000Z

    This thesis provides experimental static and dynamic results for four pairs of seals, including a pair of smooth seals and three pairs of centrally grooved seals. The grooved seals have groove depth to clearance ratios (Dg/C) of 5, 10, and 15...

  11. Thulium-170 heat source

    DOE Patents [OSTI]

    Walter, Carl E. (Pleasanton, CA); Van Konynenburg, Richard (Livermore, CA); VanSant, James H. (Tracy, CA)

    1992-01-01T23:59:59.000Z

    An isotopic heat source is formed using stacks of thin individual layers of a refractory isotopic fuel, preferably thulium oxide, alternating with layers of a low atomic weight diluent, preferably graphite. The graphite serves several functions: to act as a moderator during neutron irradiation, to minimize bremsstrahlung radiation, and to facilitate heat transfer. The fuel stacks are inserted into a heat block, which is encased in a sealed, insulated and shielded structural container. Heat pipes are inserted in the heat block and contain a working fluid. The heat pipe working fluid transfers heat from the heat block to a heat exchanger for power conversion. Single phase gas pressure controls the flow of the working fluid for maximum heat exchange and to provide passive cooling.

  12. The Radioactive Beam Program at Argonne

    E-Print Network [OSTI]

    B. B. Back

    2006-06-06T23:59:59.000Z

    In this talk I will present selected topics of the ongoing radioactive beam program at Argonne and discuss the capabilities of the CARIBU radioactive ion production facility as well as plans for construction of a novel superconducting solenoid spectrometer.

  13. Low Level Radioactive Waste Authority (Michigan)

    Broader source: Energy.gov [DOE]

    Federal laws passed in 1980 and 1985 made each state responsible for the low-level radioactive waste produced within its borders. Act 204 of 1987 created the Low-Level Radioactive Waste Authority ...

  14. Radioactivity in Food and the Environment, 2009

    E-Print Network [OSTI]

    ..............................................................................................................27 1.2.5 Solid radioactive waste disposal at sea Protection Agency. Printed on paper made from a minimum 75% deinked postconsumer waste. Front cover ............................................................................................................................22 1.2 Disposals of radioactive waste

  15. Internal and External Radioactive Backgrounds

    E-Print Network [OSTI]

    Chapter 3 Internal and External Radioactive Backgrounds New physics is often discovered by pushing energies. With the current large mixing angle-MSW oscillation parameters, Borexino expects to observe 0.35 neutrino events per day per ton from 7Be in the energy window. Because there are so few events

  16. Stabilization of scintillation detector by reference signal from radioactive source

    SciTech Connect (OSTI)

    Nedavnii, O.I.

    1985-05-01T23:59:59.000Z

    This paper examines the possibility of stabilization of a scintillation detector using an additional detector whose scintillator with respect to the former performs the function of a target, which generates secondary radiation. It is experimentally established that a regulation time constant of 10 sec ensures constancy of the transfer characteristic of the detector with an error of about 1.5% for disturbing effects that correspond to 20% of this characteristic.

  17. RISG-M-2482 COMPUTER MODELLING OF RADIOACTIVE SOURCE TERMS

    E-Print Network [OSTI]

    /INTOR workshops. INIS descriptors: M CODES; MATHEMATICAL MODELS; MONTE CARLO METHOD; NEUTRON TRANSPORT; TOKAMAK

  18. Armenia Secures Dangerous Radioactive Sources in Cooperation with NNSA |

    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 for4,645 3,625govInstrumentstdmadapInactiveVisiting the TWP TWPAlumni AlumniFederal FacilityAprilAre EarthsDecadeNational Nuclear

  19. Radioactive isotopes in Danish drinking water

    E-Print Network [OSTI]

    Radioactive isotopes in Danish drinking water Sven P. Nielsen Risø National Laboratory Working OF INVESTIGATION 11 3 DESCRIPTION OF INVESTIGATION 12 4 RADIOACTIVITY IN DRINKING WATER 13 5 SAMPLING 15 6 27 #12;4 #12;5 Preface This project for investigation of radioactivity in drinking water shall

  20. Environmental Radioactivity in Greenland in 1981

    E-Print Network [OSTI]

    Ris«-R-471 v Environmental Radioactivity in Greenland in 1981 A. Aarkrog, Henning Dahlgaard, Elis July 1962 #12;Risø-R-471 ENVIRONMENTAL RADIOACTIVITY IN GREENLAND IN 1981 A. Aarkrog, Henning Dahlgaard. Measurements of fallout radioactivity in Greenland in 1981 are reported. Strontium-90 (and Cesium-137 in most

  1. Environmental Radioactivity in Greenland in 1978

    E-Print Network [OSTI]

    ·ft I la 0 0 0 0 Risn-R-405 Environmental Radioactivity in Greenland in 1978 A. Aarkrog, Heinz ENVIRONMENTAL RADIOACTIVITY IN GREENLAND IN 1978 A. Aarkrog, Heinz Hansen and J. Lippert Abstract. Heasureaents of fallout radioactivity in Greenland in 1978 are reported. Strontium-90 (and Cesium-137 in most cases

  2. Turbocharger with variable nozzle having vane sealing surfaces

    SciTech Connect (OSTI)

    Arnold, Philippe (Hennecourt, FR); Petitjean, Dominique (Julienrupt, FR); Ruquart, Anthony (Thaon les Vosges, FR); Dupont, Guillaume (Thaon les Vosges, FR); Jeckel, Denis (Thaon les Vosges, FR)

    2011-11-15T23:59:59.000Z

    A variable nozzle for a turbocharger includes a plurality of vanes rotatably mounted on a nozzle ring and disposed in a nozzle flow path defined between the nozzle ring and an opposite nozzle wall. Either or both of the faces of the nozzle ring and nozzle wall include(s) at least one step that defines sealing surfaces positioned to be substantially abutted by airfoil surfaces of the vanes in the closed position of the vanes and to be spaced from the airfoil surfaces in positions other than the closed position. This substantial abutment between the airfoil surfaces and the sealing surfaces serves to substantially prevent exhaust gas from leaking past the ends of the airfoil portions. At the same time, clearances between the nozzle ring face and the end faces of the airfoil portions can be sufficiently large to prevent binding of the vanes under all operating conditions.

  3. Low pressure cooling seal system for a gas turbine engine

    DOE Patents [OSTI]

    Marra, John J

    2014-04-01T23:59:59.000Z

    A low pressure cooling system for a turbine engine for directing cooling fluids at low pressure, such as at ambient pressure, through at least one cooling fluid supply channel and into a cooling fluid mixing chamber positioned immediately downstream from a row of turbine blades extending radially outward from a rotor assembly to prevent ingestion of hot gases into internal aspects of the rotor assembly. The low pressure cooling system may also include at least one bleed channel that may extend through the rotor assembly and exhaust cooling fluids into the cooling fluid mixing chamber to seal a gap between rotational turbine blades and a downstream, stationary turbine component. Use of ambient pressure cooling fluids by the low pressure cooling system results in tremendous efficiencies by eliminating the need for pressurized cooling fluids for sealing this gap.

  4. The pumping ring as a Stirling Engine rod seal

    SciTech Connect (OSTI)

    Short, M.G.

    1983-08-01T23:59:59.000Z

    The rod seal performs a demanding role in a Stirling cycle machine having to restrict both gas and oil leakage to minimal levels whilst operating at high pressures and sliding speeds. This paper describes the continuation of a development programme carried out at the Royal Naval Engineering College, Manadon as part of the UK. Stirling Engine Consortium. The results of tests using a back to back pumping ring configuration are presented.

  5. SOFC Interconnect and Compressive Seal Development at PNNL

    SciTech Connect (OSTI)

    Chou, Y S.; Yang, Z Gary; Singh, Prabhakar; Stevenson, Jeffry W.; Xia, Gordon

    2005-11-01T23:59:59.000Z

    The development of solid oxide fuel cell (SOFC) technology represents an opportunity to achieve significant improvements in energy conversion efficiency and reduction of undesirable emissions. However, many technical challenges still need to be overcome before the utilization of the advantages of SOFC can take place. These challenges include the need for improved interconnects and seals for planar SOFC stacks. In this paper, we briefly summarize recent progress at PNNL in these two research areas.

  6. Believing Your Eyes: Strengthening the Reliability of Tags and Seals

    SciTech Connect (OSTI)

    Brim, Cornelia P.; Denlinger, Laura S.

    2013-07-01T23:59:59.000Z

    NNSA’s Office of Nonproliferation and International Security (NIS) is working together with scientific experts at the DOE national laboratories to develop the tools needed to safeguard and secure nuclear material from diversion, theft, and sabotage--tasks critical to support future arms control treaties that may involve the new challenge of monitoring nuclear weapons dismantlement. Use of optically stimulated luminescent material is one method to enhance the security and robustness of existing tamper indicating devices such as tags and seals.

  7. Rotordynamic evaluation of hybrid damper seals with metal mesh elements

    E-Print Network [OSTI]

    Bhamidipati, Laxmi Narasimha Kameswara Sarma

    2003-01-01T23:59:59.000Z

    . . CHAPTFR 1 INTRODUCTION Literature Review II RESEARCH OBJECTIVES AND METHOD. Obj ective Method . III LEAKAGE TESTS . . . . I 0 Experimental Apparatus and Instrumentation. . . Procedure Results IV ROTATING TESTS . . . . I 0 . . . . 10 . . . . I... metal mesh elements. Figure 1: The New MHS Figure 2: New Metal Mesh Elements Figure 3: Comparison between Old and New Metal Mesh Elements 10 CHAPTER III LEAKAGE TESTS Since the primary objective of a seal is to prevent leakage from the high...

  8. Effects of mineral fillers in slurry seal mixtures

    E-Print Network [OSTI]

    Harper, William Joe

    1964-01-01T23:59:59.000Z

    rather than a desi~. The current practice among engineers and contractors is to prepare a mixture in ac- cordance with these specifications using local materials. In many cases a mineral filler, usually portland cement, is added to "improve... applied to portland cement concrete pavements to improve the skid resistance and riding qualities of tbe surface. A slurry seal cost does not increase or improve the strength of the pavement structure . The City of Las Vagas, New Mexico, used slurry...

  9. The radioactive Substances (Uranium and Thorium) Exemption Order 1962 

    E-Print Network [OSTI]

    Joseph, Keith

    1962-01-01T23:59:59.000Z

    STATUTORY INSTRUMENTS 1962 No.2710 ATOMIC ENERGY AND RADIOACTIVE SUBSTANCES The Radioactive Substances (Uranium and Thorium) Exemption Order 1962...

  10. Status and conservation of Antarctic seals and seabirds: a review

    SciTech Connect (OSTI)

    Croxall, J.P.

    1987-01-01T23:59:59.000Z

    Present threats to Antarctic seabirds and seals when ashore include disturbance and habitat destruction and serious predation by introduced rats and cats at sub-Antarctic islands. In the marine environment threats are posed by pesticides (widespread but at low levels), pollution (mainly a potential problem associated with oil exploration), incidental takes and competition with commercial fisheries, which is reviewed in detail. Even in areas where harvesting of fish may be exceeding sustainable yield, predator-prey interaction data are inadequate to assess the level, or significance, of the effect on predators. Present krill harvests are small but likely to increase, especially in favored areas; species of potential vulnerability are noted. Existing legislation offers excellent protection for wildlife, but formally protected areas by no means cover the major breeding concentrations of seabirds and especially seals in all sectors and zones. There is a need for a comprehensive review, which in some areas will require extensive survey work. Programs for the control and elimination of alien predators need proper planning and major support. Marine reserves may be of limited benefit to pelagic seals and seabirds, and further research in some key areas is needed. Realistic environmental impact assessments will require more detailed information on predator distribution and movements than is available now; appropriate surveys and research need starting. Sensitive management of marine fisheries is difficult with the present level of quantitative data on predator-prey interactions. Difficulties in monitoring aspects of predator biology as indices of the state of prey stocks are reviewed.

  11. Performance characteristics of a self-sealing/self-healing barrier

    SciTech Connect (OSTI)

    McGregor, R.G. [Water Technology International Corp., Burlington, Ontario (Canada); [Canadian Clean Technology Centre, Burlington, Ontario (Canada); Stegemann, J.A. [Canadian Clean Technology Centre, Burlington, Ontario (Canada)

    1997-12-31T23:59:59.000Z

    Environment Canada and the Netherlands Energy Research Foundation are co-developers of a patented Self-Sealing/Self-Healing (SS/SH) Barrier system for containment of wastes which is licensed to Water Technology International Corporation. The SS/SH Barrier is intended for use as either a liner or cover for landfills, contaminated sites, secondary containment areas, etc., in the industrial, chemical, mining and municipal sectors, and also as a barrier to hydraulic flow for the transportation and construction industry. The SS/SH Barrier`s most significant feature is its capability for self-repair in the event of a breach. By contrast, conventional barrier systems, such as clay, geomembrane, or geosynthetic clay liners can not be repaired without laborious excavation and reconstruction. Laboratory investigations have shown that the SS/SH Barrier concept will function with a variety of reactive materials. Self-Sealing/Self-Healing Barriers are cost competitive and consistently exhibit hydraulic conductivities ranging from 10{sup -9} to 10{sup -13} m/s, which decrease with time. These measurements meet or exceed the recommended hydraulic conductivity required by EPA for clay liners (<1x10{sup -9} m/s) used in landfills and hazardous waste sites. Results of mineralogical examination of the seal, diffusion testing, hydraulic conductivity measurement, and durability testing, including wet/dry, freeze/thaw cycling and leachate compatibility are also presented.

  12. Comments on a paper tilted `The sea transport of vitrified high-level radioactive wastes: Unresolved safety issues`

    SciTech Connect (OSTI)

    Sprung, J.L.; McConnell, P.E.; Nigrey, P.J.; Ammerman, D.J. [and others

    1997-05-01T23:59:59.000Z

    The cited paper estimates the consequences that might occur should a purpose-built ship transporting Vitrified High Level Waste (VHLW) be involved in a severe collision that causes the VHLW canisters in one Type-B package to spill onto the floor of a major ocean fishing region. Release of radioactivity from VHLW glass logs, failure of elastomer cask seals, failure of VHLW canisters due to stress corrosion cracking (SCC), and the probabilities of the hypothesized accident scenario, of catastrophic cask failure, and of cask recovery from the sea are all discussed.

  13. Radioactive waste treatment technologies and environment

    SciTech Connect (OSTI)

    HORVATH, Jan; KRASNY, Dusan [JAVYS, PLc. - Nuclear and Decommisioning Company, PLc. (Slovakia)

    2007-07-01T23:59:59.000Z

    The radioactive waste treatment and conditioning are the most important steps in radioactive waste management. At the Slovak Electric, plc, a range of technologies are used for the processing of radioactive waste into a form suitable for disposal in near surface repository. These technologies operated by JAVYS, PLc. Nuclear and Decommissioning Company, PLc. Jaslovske Bohunice are described. Main accent is given to the Bohunice Radwaste Treatment and Conditioning Centre, Bituminization plant, Vitrification plant, and Near surface repository of radioactive waste in Mochovce and their operation. Conclusions to safe and effective management of radioactive waste in the Slovak Republic are presented. (authors)

  14. The Development of Low-Cost Integrated Composite Seal for SOFC: Materials and Design Methodologies

    SciTech Connect (OSTI)

    Xinyu Huang; Kristoffer Ridgeway; Srivatsan Narasimhan; Serg Timin; Wei Huang; Didem Ozevin; Ken Reifsnider

    2006-07-31T23:59:59.000Z

    This report summarizes the work conducted by UConn SOFC seal development team during the Phase I program and no cost extension. The work included composite seal sample fabrication, materials characterizations, leak testing, mechanical strength testing, chemical stability study and acoustic-based diagnostic methods. Materials characterization work revealed a set of attractive material properties including low bulk permeability, high electrical resistivity, good mechanical robustness. Composite seal samples made of a number of glasses and metallic fillers were tested for sealing performance under steady state and thermal cycling conditions. Mechanical testing included static strength (pull out) and interfacial fracture toughness measurements. Chemically stability study evaluated composite seal material stability after aging at 800 C for 168 hrs. Acoustic based diagnostic test was conducted to help detect and understand the micro-cracking processes during thermal cycling test. The composite seal concept was successfully demonstrated and a set of material (coating composition & fillers) were identified to have excellent thermal cycling performance.

  15. 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.

  16. Investigations of Near-Field Thermal-Hydrologic-Mechanical-Chemical Models for Radioactive Waste Disposal in Clay/Shale Rock

    SciTech Connect (OSTI)

    Liu, H.H.; Li, L.; Zheng, L.; Houseworth, J.E.; Rutqvist, J.

    2011-06-20T23:59:59.000Z

    Clay/shale has been considered as potential host rock for geological disposal of high-level radioactive waste throughout the world, because of its low permeability, low diffusion coefficient, high retention capacity for radionuclides, and capability to self-seal fractures. For example, Callovo-Oxfordian argillites at the Bure site, France (Fouche et al., 2004), Toarcian argillites at the Tournemire site, France (Patriarche et al., 2004), Opalinus Clay at the Mont Terri site, Switzerland (Meier et al., 2000), and Boom clay at the Mol site, Belgium (Barnichon and Volckaert, 2003) have all been under intensive scientific investigation (at both field and laboratory scales) for understanding a variety of rock properties and their relationships to flow and transport processes associated with geological disposal of radioactive waste. Figure 1-1 presents the distribution of clay/shale formations within the USA.

  17. Critically safe volume vacuum pickup for use in wet or dry cleanup of radioactive enclosures

    DOE Patents [OSTI]

    Zeren, J.D.

    1993-12-28T23:59:59.000Z

    A physical compact vacuum pickup device of critically safe volume and geometric shape is provided for use in radioactive enclosures, such as a small glove box, to facilitate manual cleanup of either wet or dry radioactive material. The device is constructed and arranged so as to remain safe when filled to capacity with plutonium-239 oxide. Two fine mesh filter bags are supported on the exterior of a rigid fine mesh stainless steel cup. This assembly is sealed within, and spaced from, the interior walls of a stainless steel canister. An air inlet communicates with the interior of the canister. A modified conventional vacuum head is physically connected to, and associated with, the interior of the mesh cup. The volume of the canister, as defined by the space between the mesh cup and the interior walls of the canister, forms a critically safe volume and geometric shape for dry radioactive particles that are gathered within the canister. A critically safe liquid volume is maintained by operation of a suction terminating float valve, and/or by operation of redundant vacuum check/liquid drain valves and placement of the air inlet. 5 figures.

  18. Critically safe volume vacuum pickup for use in wet or dry cleanup of radioactive enclosures

    DOE Patents [OSTI]

    Zeren, Joseph D. (390 Forest Ave., Boulder, CO 80304)

    1993-12-28T23:59:59.000Z

    A physical compact vacuum pickup device of critically safe volume and geometric shape is provided for use in radioactive enclosures, such as a small glove box, to facilitate manual cleanup of either wet or dry radioactive material. The device is constructed and arranged so as to remain safe when filled to capacity with plutonium-239 oxide. Two fine mesh filter bags are supported on the exterior of a rigid fine mesh stainless steel cup. This assembly is sealed within, and spaced from, the interior walls of a stainless steel canister. An air inlet communicates with the interior of the canister. A modified conventional vacuum head is physically connected to, and associated with, the interior of the mesh cup. The volume of the canister, as defined by the space between the mesh cup and the interior walls of the canister, forms a critically safe volume and geometric shape for dry radioactive particles that are gathered within the canister. A critically safe liquid volume is maintained by operation of a suction terminating float valve, and/or by operation of redundant vacuum check/liquid drain valves and placement of the air inlet.

  19. System design and implementation for the glass panel alignment and sealing tool for flat panel displays

    SciTech Connect (OSTI)

    Jordan, J.D.; Stromberg, P.G.; Kuszmaul, S.S.

    1996-10-16T23:59:59.000Z

    This report describes the system designed and fabricated for the National Center for Advanced Information Component Manufacturing (NCAICM) project number 9322-135. The system is a device capable of simultaneously aligning two glass plates and sealing them together with glass frit. The process development was divided into two phases. The first was thermal sealing in an ambient environment. The second was sealing a controlled environment in a vacuum.

  20. Measure Guideline: Air Sealing Mechanical Closets in Slab-On-Grade Homes

    SciTech Connect (OSTI)

    Dickson, B.

    2012-02-01T23:59:59.000Z

    This measure guideline describes covers two fundamental retrofit strategies for air sealing around air handling systems that are located within the living space in an enclosed closet: one in which all of the equipment is removed and being replaced, and a closet where the equipment is to remain and existing conditions are sealed. It includes the design and installation details necessary to effectively seal the air handler closet and central return system to maximize the efficiency and safety of the space conditioning system.

  1. Industrial Technology of Decontamination of Liquid Radioactive Waste in SUE MosSIA 'Radon' - 12371

    SciTech Connect (OSTI)

    Adamovich, Dmitry V.; Neveykin, Petr P.; Karlin, Yuri V.; Savkin, Alexander E. [SUE MosSIA 'Radon', 7th Rostovsky lane 2/14, Moscow 119121 (Russian Federation)

    2012-07-01T23:59:59.000Z

    SUE MosSIA 'RADON' - this enterprise was created more than 50 years ago, which deals with the recycling of radioactive waste and conditioning of spent sources of radiation in stationary and mobile systems in the own factory and operating organizations. Here is represented the experience SUE MosSIA 'Radon' in the field of the management with liquid radioactive waste. It's shown, that the activity of SUE MosSIA 'RADON' is developing in three directions - improvement of technical facilities for treatment of radioactive waters into SUE MosSIA 'RADON' development of mobile equipment for the decontamination of radioactive waters in other organizations, development of new technologies for decontamination of liquid radioactive wastes as part of various domestic Russian and international projects including those related to the operation of nuclear power and nuclear submarines. SUE MosSIA 'RADON' has processed more than 270 thousand m{sup 3} of radioactive water, at that more than 7000 m{sup 3} in other organizations for more than 50 years. It is shown that a number of directions, particularly, the development of mobile modular units for decontamination of liquid radioactive waste, SUE MosSIA 'RADON' is a leader in the world. (authors)

  2. INEL metal recycle radioactive scrap metal survey report

    SciTech Connect (OSTI)

    Funk, D.M.

    1994-09-01T23:59:59.000Z

    DOE requested that inventory and characterization of radioactive scrap metal (RSM) be conducted across the DOE complex. Past studies have estimated the metal available from unsubstantiated sources. In meetings held in FY-1993, with seven DOE sites represented and several DOE-HQ personnel present, INEL personnel discovered that these numbers were not reliable and that large stockpiles did not exist. INEL proposed doing in-field measurements to ascertain the amount of RSM actually available. This information was necessary to determine the economic viability of recycling and to identify feed stock that could be used to produce containers for radioactive waste. This inventory measured the amount of RSM available at the selected DOE sites. Information gathered included radionuclide content and chemical form, general radiation field, alloy type, and mass of metal.

  3. Iraq liquid radioactive waste tanks maintenance and monitoring program plan.

    SciTech Connect (OSTI)

    Dennis, Matthew L.; Cochran, John Russell; Sol Shamsaldin, Emad (Iraq Ministry of Science and Technology)

    2011-10-01T23:59:59.000Z

    The purpose of this report is to develop a project management plan for maintaining and monitoring liquid radioactive waste tanks at Iraq's Al-Tuwaitha Nuclear Research Center. Based on information from several sources, the Al-Tuwaitha site has approximately 30 waste tanks that contain varying amounts of liquid or sludge radioactive waste. All of the tanks have been non-operational for over 20 years and most have limited characterization. The program plan embodied in this document provides guidance on conducting radiological surveys, posting radiation control areas and controlling access, performing tank hazard assessments to remove debris and gain access, and conducting routine tank inspections. This program plan provides general advice on how to sample and characterize tank contents, and how to prioritize tanks for soil sampling and borehole monitoring.

  4. Review of Monte Carlo simulations for backgrounds from radioactivity

    SciTech Connect (OSTI)

    Selvi, Marco [INFN - Sezione di Bologna (Italy)] [INFN - Sezione di Bologna (Italy)

    2013-08-08T23:59:59.000Z

    For all experiments dealing with the rare event searches (neutrino, dark matter, neutrino-less double-beta decay), the reduction of the radioactive background is one of the most important and difficult tasks. There are basically two types of background, electron recoils and nuclear recoils. The electron recoil background is mostly from the gamma rays through the radioactive decay. The nuclear recoil background is from neutrons from spontaneous fission, (?, n) reactions and muoninduced interactions (spallations, photo-nuclear and hadronic interaction). The external gammas and neutrons from the muons and laboratory environment, can be reduced by operating the detector at deep underground laboratories and by placing active or passive shield materials around the detector. The radioactivity of the detector materials also contributes to the background; in order to reduce it a careful screening campaign is mandatory to select highly radio-pure materials. In this review I present the status of current Monte Carlo simulations aimed to estimate and reproduce the background induced by gamma and neutron radioactivity of the materials and the shield of rare event search experiment. For the electromagnetic background a good level of agreement between the data and the MC simulation has been reached by the XENON100 and EDELWEISS experiments, using the GEANT4 toolkit. For the neutron background, a comparison between the yield of neutrons from spontaneous fission and (?, n) obtained with two dedicated softwares, SOURCES-4A and the one developed by Mei-Zhang-Hime, show a good overall agreement, with total yields within a factor 2 difference. The energy spectra from SOURCES-4A are in general smoother, while those from MZH presents sharp peaks. The neutron propagation through various materials has been studied with two MC codes, GEANT4 and MCNPX, showing a reasonably good agreement, inside 50% discrepancy.

  5. New Jersey State Briefing Book for low-level radioactive waste management

    SciTech Connect (OSTI)

    Not Available

    1981-04-01T23:59:59.000Z

    The New Jersey state Briefing Book is one of a series of State briefing books on low-level radioactive waste management practices. It has been prepared to assist state and federal agency officials in planning for safe low-level radioactive waste disposal. The report contains a profile of low-level radioactive waste generators in New Jersey. The profile is the result of a survey of NRC licensees in New Jersey. The briefing book also contains a comprehensive assessment of low-level radioactive waste management issues and concerns as defined by all major interested parties including industry, government, the media, and interest groups. The assessment was developed through personal communications with representatives of interested parties, and through a review of media sources. Lastly, the briefing book provides demographic and socioeconomic data and a discussion of relevant government agencies and activities, all of which may impact waste management practices in New Jersey.

  6. Ohio State Briefing Book for low-level radioactive waste management

    SciTech Connect (OSTI)

    Not Available

    1981-04-01T23:59:59.000Z

    The Ohio State Briefing Book is one of a series of state briefing books on low-level radioactive waste management practices. It has been prepared to assist state and federal agency officials in planning for safe low-level radioactive waste disposal. The report contains a profile of low-level radioactive waste generators in Ohio. The profile is the result of a survey of NRC licensees in Ohio. The briefing book also contains a comprehensive assessment of low-level radioactive waste management issues and concerns as defined by all major interested parties including industry, government, the media, and interest groups. The assessment was developed through personal communications with representatives of interested parties, and through a review of media sources. Lastly, the briefing book provides demographic and socioeconomic data and a discussion of relevant government agencies and activities, all of which may impact waste management practices in Ohio.

  7. Oregon State Briefing Book for low-level radioactive waste management

    SciTech Connect (OSTI)

    Not Available

    1980-12-01T23:59:59.000Z

    The Oregon State Briefing Book is one of a series of state briefing books on low-level radioactive waste management practices. It has been prepared to assist state and federal agency officials in planning for safe low-level radioactive waste disposal. The report contains a profile of low-level radioactive waste generators in Oregon. The profile is a result of a survey of NRC licensees in Oregon. The briefing book also contains a comprehensive assessment of low-level radioactive waste management issues and concerns as defined by all major interested parties including industry, government, the media, and interest groups. The assessment was developed through personal communications with representatives of interested parties, and through a review of media sources. Lastly, the briefing book provides demographic and socioeconomic data and a discussion of relevant government agencies and activities, all of which may impact waste management practices in Oregon.

  8. Connecticut State Briefing Book for low-level radioactive-waste management

    SciTech Connect (OSTI)

    none,

    1981-06-01T23:59:59.000Z

    The Connecticut State Briefing Book is one of a series of state briefing books on low-level radioactive waste management practices. It has been prepared to assist state and federal agency officials in planning for safe low-level radioactive waste disposal. The report contains a profile of low-level radioactive waste generators in Connecticut. The profile is the result of a survey of Nuclear Regulatory Commission licensees in Connecticut. The briefing book also contains a comprehensive assessment of low-level radioactive waste management issues and concerns as defined by all major interested parties including industry, government, the media, and interest groups. The assessment was developed through personal communications with representatives of interested parties, and through a review of media sources. Lastly, the briefing book provides demographic and socioeconomic data and a discussion of relevant government agencies and activities, all of which may affect waste management practices in Connecticut.

  9. Puerto Rico State Briefing Book for low-level radioactive waste management

    SciTech Connect (OSTI)

    Not Available

    1981-10-01T23:59:59.000Z

    The Puerto Rico State Briefing Book is one of a series of state briefing books on low-level radioactive waste management practices. It has been prepared to assist state and federal agency officials in planning for safe low-level radioactive waste disposal. The report contains a profile of low-level radioactive waste generators in Puerto Rico. The profile is the result of a survey of NRC licensees in Puerto Rico. The briefing book also contains a comprehensive assessment of low-level radioactive waste management issues and concerns as defined by all major interested parties including industry, government, the media, and interest groups. The assessment was developed through personal communications with representatives of interested parties, and through a review of media sources. Lastly, the briefing book provides demographic and socioeconomic data and a discussion of relevant government agencies and activities, all of which may impact waste management practices in Puerto Rico.

  10. North Dakota State Briefing Book for low-level radioactive waste management

    SciTech Connect (OSTI)

    none,

    1981-10-01T23:59:59.000Z

    The North Dakota State Briefing Book is one of a series of state briefing books on low-level radioactive waste management practices. It has been prepared to assist state and federal agency officials in planning for safe low-level radioactive waste disposal. The report contains a profile of low-level radioactive waste generators in North Dakota. The profile is the result of a survey of NRC licensees in North Dakota. The briefing book also contains a comprehensive assessment of low-level radioactive waste management issues and concerns as defined by all major interested parties including industry, government, the media, and interest groups. The assessment was developed through personal communications with representatives of interested parties, and through a review of media sources. Lastly, the briefing book provides demographic and socioeconomic data and a discussion of relevant government agencies and activities, all of which may impact waste management practices in North Dakota.

  11. Florida State Briefing Book for low-level radioactive-waste management

    SciTech Connect (OSTI)

    none,

    1981-06-01T23:59:59.000Z

    The Florida State Briefing Book is one of a series of state briefing books on low-level radioactive waste management practices. It has been prepared to assist state and federal agency officials in planning for safe low-level radioactive waste disposal. The report contains a profile of low-level radioactive waste generators in Florida. The profile is the result of a survey of NRC licensees in Florida. The briefing book also contains a comprehensive assessment of low-level radioactive waste management issues and concerns as defined by all major interested parties including industry, government, the media, and interest groups. The assessment was developed through personal communications with representatives of interested parties, and through a review of media sources. Lastly, the briefing book provides demographic and socioeconomic data and a discussion of relevant government agencies and activities, all of which may impact waste management practices in Florida.

  12. Utah State Briefing Book for low-level radioactive waste management

    SciTech Connect (OSTI)

    Not Available

    1981-10-01T23:59:59.000Z

    The Utah State Briefing Book is one of a series of state briefing books on low-level radioactive waste management practices. It has been prepared to assist state and federal agency officials in planning for safe low-level radioactive waste disposal. The report contains a profile of low-level radioactive waste generators in Utah. The profile is the result of a survey of NRC licensees in Utah. The briefing book also contains a comprehensive assessment of low-level radioactive waste management issues and concerns as defined by all major interested parties including industry, government, the media, and interest groups. The assessment was developed through personal communications with representatives of interested parties, and through a review of media sources. Lastly, the briefing book provides demographic and socioeconomic data and a discussion of relevant government agencies and activities, all of which may impact waste management practices in Utah.

  13. Wyoming State Briefing Book for low-level radioactive waste management

    SciTech Connect (OSTI)

    Not Available

    1981-10-01T23:59:59.000Z

    The Wyoming State Briefing Book is one of a series of state briefing books on low-level radioactive waste management practices. It has been prepared to assist state and federal agency officials in planning for safe low-level radioactive waste disposal. The report contains a profile of low-level radioactive waste generators in Wyoming. The profile is the result of a survey of NRC licensees in Wyoming. The briefing book also contains a comprehensive assessment of low-level radioactive waste management issues and concerns as defined by all major interested parties including industry, government, the media, and interest groups. The assessment was developed through personal communications with representatives of interested parties, and through a review of media sources. Lastly, the briefing book provides demographic and socioeconomic data and a discussion of relevant government agencies and activities, all of which may impact waste management practices in Wyoming.

  14. North Carolina State Briefing Book for low-level radioactive waste management

    SciTech Connect (OSTI)

    Not Available

    1981-08-01T23:59:59.000Z

    The North Carolina State Briefing Book is one of a series of state briefing books on low-level radioactive waste management practices. It has been prepared to assist state and federal agency officials in planning for safe low-level radioactive waste disposal. The report contains a profile of low-level radioactive waste generators in North Carolina. The profile is the result of a survey of NRC licensees in North Carolina. The briefing book also contains a comprehensive assessment of low-level radioactive waste management issues and concerns as defined by all major interested parties including industry, government, the media, and interest groups. The assessment was developed through personal communications with representatives of interested parties, and through a review of media sources. Lastly, the briefing book provides demographic and socioeconomic data and a discussion of relevant government agencies and activities, all of which may impact waste management practices in North Carolina.

  15. Pennsylvania State Briefing Book for low-level radioactive waste management

    SciTech Connect (OSTI)

    Not Available

    1981-04-01T23:59:59.000Z

    The Pennsylvania State Briefing Book is one of a series of state briefing books on low-level radioactive waste management practices. It has been prepared to assist state and federal agency officials in planning for safe low-level radioactive waste disposal. The report contains a profile of low-level radioactive waste generators in Pennsylvania. The profile is the result of a survey of NRC licensees in Pennsylvania. The briefing book also contains a comprehensive assessment of low-level radioactive waste management issues and concerns as defined by all major interested parties including industry, government, the media, and interest groups. The assessment was developed through personal communications with representatives of interested parties, and through a review of media sources. Lastly, the briefing book provides demographic and socioeconomic data and a discussion of relevant government agencies and activities, all of which may impact waste management practices in Pennsylvania.

  16. South Carolina State Briefing Book for low-level radioactive waste management

    SciTech Connect (OSTI)

    Not Available

    1981-08-01T23:59:59.000Z

    The South Carolina State Briefing Book is one of a series of state briefing books on low-level radioactive waste management practices. It has been prepared to assist state and federal agency officials in planning for safe low-level radioactive waste disposal. The report contains a profile of low-level radioactive waste generators in South Carolina. The profile is the result of a survey of NRC licensees in South Carolina. The briefing book also contains a comprehensive assessment of low-level radioactive waste management issues and concerns as definied by all major interested parties including industry, government, the media, and interest groups. The assessment was developed through personal communications with representatives of interested parties, and through a review of media sources. Lastly, the briefing book provides demographic and socioeconomic data and a discussion of relevant government agencies and activities, all of which may impact waste management practices in South Carolina.

  17. Massachusetts State Briefing Book for low-level radioactive waste management

    SciTech Connect (OSTI)

    Not Available

    1981-03-12T23:59:59.000Z

    The Massachusetts State Briefing Book is one of a series of State briefing books on low-level radioactive waste management practices. It has been prepared to assist State and Federal agency officials in planning for safe low-level radioactive waste disposal. The report contains a profile of low-level radioactive waste generators in Massachusetts. The profile is the result of a survey of NRC licensees in Massachusetts. The briefing book also contains a comprehensive assessment of low-level radioactive waste management issues and concerns as defined by all major interested parties including industry, government, the media, and interest groups. The assessment was developed through personal communications with representatives of interested parties, and through a review of media sources. Lastly, the briefing book provides demographic and socioeconomic data and a discussion of relevant government agencies and activities, all of which may impact waste management practices in Massachusetts.

  18. Washington State Briefing Book for low-level radioactive waste management

    SciTech Connect (OSTI)

    Not Available

    1980-12-01T23:59:59.000Z

    The Washington State Briefing Book is one of a series of state briefing books on low-level radioactive waste management practices. It has been prepared to assist state and federal agency officials in planning for safe low-level radioactive waste disposal. The report contains a profile of low-level radioactive waste generators in Washington. The profile is the result of a survey of NRC licensees in Washington. The briefing book also contains a comprehensive assessment of low-level radioactive waste management issues and concerns as defined by all major interested parties including industry, government, the media, and interest groups. The assessment was developed through personal communications with representatives of interested parties, and through a review of media sources. Lastly, the briefing book provides demographic and socioeconomic data and a discussion of relevant government agencies and activities, all of which may impact waste management practices in Washington.

  19. Glass ceramics for sealing to high-thermal-expansion metals

    SciTech Connect (OSTI)

    Wilder, Jr., J. A.

    1980-10-01T23:59:59.000Z

    Glass ceramics were studied, formulated in the Na/sub 2/O CaO.P/sub 2/O/sub 5/, Na/sub 2/O.BaOP/sub 2/O/sub 5/, Na/sub 2/O.Al/sub 2/O/sub 3/.P/sub 2/O/sub 5/, and Li/sub 2/O.BaO.P/sub 2/O/sub 5/ systems to establish their suitability for sealing to high thermal expansion metals, e.g. aluminum, copper, and 300 series stainless steels. Glass ceramics in Na/sub 2/O.CaO.P/sub 2/O/sub 5/ and Na/sub 2/O.BaO.P/sub 2/O/sub 5/ systems have coefficients of thermal expansion in the range 140 x 10/sup -1/ per /sup 0/C less than or equal to ..cap alpha.. less than or equal to 225 x 10/sup -7/ per /sup 0/C and fracture toughness values generally greater than those of phosphate glasses; they are suitable for fabricating seals to high thermal expansion metals. Crystal phases include NaPo/sub 3/, (NaPO/sub 3/)/sub 3/, NaBa(PO/sub 3/)/sub 3/, and NaCa(PO/sub 3/)/sub 3/. Glass ceramics formed in the Na/sub 2/O.Al/sub 2/O/sub 3/.P/sub 2/O/sub 5/ systems have coefficients of thermal expansion greater than 240 x 10/sup -7/ per /sup 0/C, but they have extensive microcracking. Due to their low thermal expansion values (..cap alpha.. less than or equal to 120 x 10/sup -7/ per /sup 0/C), glass ceramics in the Li/sub 2/O.BaO.P/sub 2/O/sub 5/ system are unsuitable for sealing to high thermal expansion metals.

  20. Source Recertification, Refurbishment, and Transfer Logistics

    SciTech Connect (OSTI)

    Gastelum, Zoe N.; Duckworth, Leesa L.; Greenfield, Bryce A.; Doll, Stephanie R.

    2013-09-01T23:59:59.000Z

    The 2012 Gap Analysis of Department of Energy Radiological Sealed Sources, Standards, and Materials for Safeguards Technology Development [1] report, and the subsequent Reconciliation of Source Needs and Surpluses across the U.S. Department of Energy National Laboratory Complex [2] report, resulted in the identification of 33 requests for nuclear or radiological sealed sources for which there was potentially available, suitable material from within the U.S. Department of Energy (DOE) complex to fill the source need. Available, suitable material was defined by DOE laboratories as material slated for excess, or that required recertification or refurbishment before being used for safeguards technology development. This report begins by outlining the logistical considerations required for the shipment of nuclear and radiological materials between DOE laboratories. Then, because of the limited need for transfer of matching sources, the report also offers considerations for an alternative approach – the shipment of safeguards equipment between DOE laboratories or technology testing centers. Finally, this report addresses repackaging needs for the two source requests for which there was available, suitable material within the DOE complex.

  1. Evaluation of Steam Turbines Triangular Tooth on Stator Labyrinth Seal

    E-Print Network [OSTI]

    Tanvir, Hossain Ahmed

    2012-07-16T23:59:59.000Z

    the 0.5 ptation is u es, the pre ssure differe above plot, % when mo sed to refine ssure diffe nces are plo it is observe re than 1000 F the wall. A rences acro tted as a fu d that the c 00 nodes ar ig. 1.7. Gr fter several ss... the seal nction of Re hange in pre e employed id Independ thousand ite are record which is sh ssure differ . ence study rations and ed. Finally own in the ence ( Pin-Po . the number the record Fig. 1.7. Fr ut ) is less th 9...

  2. Mean flow and turbulence characteristics in whirling annular seals

    E-Print Network [OSTI]

    Thames, Howard Davis

    1992-01-01T23:59:59.000Z

    of the test rig with the annular seal installed 15: Dimensions of the Annular Rotor . 16: Components of the 3D Laser Doppler Velocimetry System 15 17 . . 19 Figure 17: Raw Doppler signal with high frequency noise and pedestal Figure 18: Doppler signal... 64: Figure 65: Figure 66: Figure 67: Figure 68: Figure 69: Figure 70: Figure 71: Figure 72: Figure 73: Figure 74: Figure 75: Figure 76: Figure 77: Case 2 Vector Plots at Constant Axial Positions 13-17 99 Case 2 Mean Velocity Contours...

  3. The effect of a new damper seal on rotordynamics

    E-Print Network [OSTI]

    Li, Qiming

    1995-01-01T23:59:59.000Z

    and vibration damping device developed from the teeth on stator labyrinth seal. It can be used in any turbomachine with compressible working fluids. There are two distinct features that are critical to provide damping. The first one is that the radial rotor... fields within the cavities are ignored. The existing computer code predicts that the optimal blade number is 2 from the viewpoint of vibration damping, and that a larger number of blades will decrease both leakage and damping. Figure 3 is a cross...

  4. Radioactive Waste Management BasisSept 2001

    SciTech Connect (OSTI)

    Goodwin, S S

    2011-08-31T23:59:59.000Z

    This Radioactive Waste Management Basis (RWMB) documents radioactive waste management practices adopted at Lawrence Livermore National Laboratory (LLNL) pursuant to Department of Energy (DOE) Order 435.1, Radioactive Waste Management. The purpose of this RWMB is to describe the systematic approach for planning, executing, and evaluating the management of radioactive waste at LLNL. The implementation of this document will ensure that waste management activities at LLNL are conducted in compliance with the requirements of DOE Order 435.1, Radioactive Waste Management, and the Implementation Guide for DOE manual 435.1-1, Radioactive Waste Management Manual. Technical justification is provided where methods for meeeting the requirements of DOE Order 435.1 deviate from the DOE Manual 435.1-1 and Implementation Guide.

  5. Radioactive Waste Management, Inspection Criteria; Approach,...

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

    except for storage for decay or otherwise authorized by the Field Element Manager? Are radioactive waste storage, treatment, and disposal activities performed in a manner that...

  6. Sandia National Laboratories: radioactive waste solution cleanup

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

    solution cleanup ECIS and UOP (a Honewell Company): CSTs Clean Radioactive Waste in Fukushima and Worldwide On February 14, 2013, in Energy, Materials Science, Nuclear Energy,...

  7. Sandia National Laboratories: removing the highly radioactive...

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

    elements ECIS and UOP (a Honewell Company): CSTs Clean Radioactive Waste in Fukushima and Worldwide On February 14, 2013, in Energy, Materials Science, Nuclear Energy,...

  8. Office of Civilian Radioactive Waste Management Transportation...

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

    Jay Jones Office of Civilian Radioactive Waste Management April 22, 2004 Albuquerque, New Mexico 2 Session Overview * Meeting objectives and expectations * Topic Group...

  9. Radiation Machines and Radioactive Materials (Iowa)

    Broader source: Energy.gov [DOE]

    These chapters describe general provisions and regulatory requirements; registration, licensure, and transportation of radioactive materials; and exposure standards for radiation protection.

  10. Blade platform seal for ceramic/metal rotor assembly

    DOE Patents [OSTI]

    Wertz, John L. (Indianapolis, IN)

    1982-01-01T23:59:59.000Z

    A combination ceramic and metal turbine rotor for use in high temperature gas turbine engines includes a metal rotor disc having a rim with a plurality of circumferentially spaced blade root retention slots therein to receive a plurality of ceramic blades, each including side platform segments thereon and a dovetail configured root slidably received in one of the slots. Adjacent ones of the platform segments including edge portions thereon closely spaced when the blades are assembled to form expansion gaps in an annular flow surface for gas passage through the blades and wherein the assembly further includes a plurality of unitary seal members on the rotor connected to its rim and each including a plurality of spaced, axially extending, flexible fingers that underlie and conform to the edge portions of the platform segments and which are operative at turbine operating temperatures and speeds to distribute loading on the platform segments as the fingers are seated against the underside of the blade platforms to seal the gaps without undesirably stressing thin web ceramic sections of the platform.

  11. Follow-up on the Management of Plutonium-239 Sealed Sources Recovery...

    Office of Environmental Management (EM)

    to colleges and universilies, commercial companies and other coiintries by the Atomic Energy Commission. Due to the fact that they are on loan, they remain the property of the...

  12. Follow-up on the Management of Plutonium-239 Sealed Sources Recovery

    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 offOCHCO2: FinalOffers3.pdf0-45.pdf Flash2010-45.pdfFlash2011-43andProperty ControlFollow-up on

  13. System and Method for Sealing a Vapor Deposition Source - Energy Innovation

    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'sis Taking Over Our InstagramStructureProposed Action(Insert DirectiveSynthetic

  14. THERMAL EVALUATION OF DRUM TYPE RADIOACTIVE MATERIAL PACKAGING ARRAYS IN STORAGE

    SciTech Connect (OSTI)

    Gupta, N

    2009-04-27T23:59:59.000Z

    Drum type packages are routinely used to transport radioactive material (RAM) in the U.S. Department of Energy (DOE) complex. These packages are designed to meet the federal regulations described in 10 CFR 71.[1] In recent years, there has been a greater need to use these packagings to store the excess fissile material, especially plutonium for long term storage. While the design requirements for safe transportation of these packagings are well defined, the requirements for safe long term storage are not well established. Since the RAM contents in the packagings produce decay heat, it is important that they are stored carefully to prevent overheating of the containment vessel (CV) seals to prevent any leakage and the impact limiter to maintain the package structural integrity. This paper analyzes different storage arrays for a typical 9977 packaging for thermal considerations and makes recommendations for their safe storage under normal operating conditions.

  15. Fall Protection Procedures for Sealing Bulk Waste Shipments by Rail Cars at Formerly Utilized Sites Remedial Action Program (FUSRAP) Sites - 13509

    SciTech Connect (OSTI)

    Boyle, J.D. [U.S. Army Corps of Engineers - Buffalo District, Buffalo, New York 14207 (United States)] [U.S. Army Corps of Engineers - Buffalo District, Buffalo, New York 14207 (United States); Fort, E. Joseph; Lorenz, William [Cabrera Services (Cabrera) East Harford, CT 06108 (United States)] [Cabrera Services (Cabrera) East Harford, CT 06108 (United States); Mills, Andy [Shaw Environmental and Infrastructure, Inc. (Shaw) Baton Rouge, LA 70809 (United States)] [Shaw Environmental and Infrastructure, Inc. (Shaw) Baton Rouge, LA 70809 (United States)

    2013-07-01T23:59:59.000Z

    Rail-cars loaded with radioactive materials must be closed and fastened to comply with United States Department of Transportation (DOT) requirements before they shipped. Securing waste shipments in a manner that meets these regulations typically results in the use of a sealable rail-car liner. Workers accessing the tops of the 2.74 m high rail-cars to seal and inspect liners for compliance prior to shipment may be exposed to a fall hazard. Relatively recent revisions to the Fall Protection requirements in the Safety and Health Requirements Manual (EM385-1-1, U.S. Army Corps of Engineers) have necessitated modifications to the fall protection systems previously employed for rail-car loading at Formerly Utilized Sites Remedial Action Program (FUSRAP) sites. In response these projects have developed site-specific procedures to protect workers and maintain compliance with the improved fall protection regulations. (authors)

  16. 30. Radioactivity and radiation protection 1 30. RADIOACTIVITY AND RADIATION PROTECTION

    E-Print Network [OSTI]

    30. Radioactivity and radiation protection 1 30. RADIOACTIVITY AND RADIATION PROTECTION Revised for the 2012 edition (pdg.lbl.gov) February 16, 2012 14:08 #12;2 30. Radioactivity and radiation protection radiation in a volume element of a specified material divided by the mass of this volume element. · Kerma, K

  17. 33. Radioactivity and radiation protection 1 33. RADIOACTIVITY AND RADIATION PROTECTION

    E-Print Network [OSTI]

    33. Radioactivity and radiation protection 1 33. RADIOACTIVITY AND RADIATION PROTECTION Revised://pdg.lbl.gov) June 18, 2012 16:20 #12;2 33. Radioactivity and radiation protection tissue caused by different radiation in a volume element of a specified material divided by the mass of this volume element. · Kerma, K

  18. 30. Radioactivity and radiation protection 1 30. RADIOACTIVITY AND RADIATION PROTECTION

    E-Print Network [OSTI]

    30. Radioactivity and radiation protection 1 30. RADIOACTIVITY AND RADIATION PROTECTION Revised;2 30. Radioactivity and radiation protection caused by different radiation types R weighted with so radiation in a volume element of a specified material divided by the mass of this volume element. · Kerma, K

  19. Use of seal-like robot PARO in sensory group therapy for older adults with dementia

    E-Print Network [OSTI]

    Sabanovic, Selma

    Use of seal-like robot PARO in sensory group therapy for older adults with dementia Wan-Ling Chang--This work presents the preliminary results of an eight- week study of the seal-like robot PARO being used adapted the concept of MSBT to the use of PARO as a multimodal sensory stimulus in a group activity

  20. Postdoctoral Research Associate (Stable Glass-Ceramic Nanocomposites as Compliant Seals for SOFCs)

    E-Print Network [OSTI]

    Azad, Abdul-Majeed

    Postdoctoral Research Associate (Stable Glass-Ceramic Nanocomposites as Compliant Seals for SOFCs with strong background in materials synthesis, processing and SOFC characterization together with exceptional and conducting sealing experiments with button SOFCs for extended period of time and, data analysis