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Sample records for nuclear filter technology

  1. Nuclear Filter Technology | Open Energy Information

    Open Energy Info (EERE)

    Filter Technology Jump to: navigation, search Name: Nuclear Filter Technology Place: Golden, CO Information About Partnership with NREL Partnership with NREL Yes Partnership Type...

  2. Advanced Particulate Filter Technologies for Direct Injection...

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

    Particulate Filter Technologies for Direct Injection Gasoline Engine Applications Advanced Particulate Filter Technologies for Direct Injection Gasoline Engine Applications Specific ...

  3. Nuclear Science & Technology

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

    Nuclear Science & Technology Nuclear Science & Technology1354608000000Nuclear Science & TechnologySome of these resources are LANL-only and will require Remote Access. No...

  4. Plasma Mass Filters For Nuclear Waste Reprocessing

    SciTech Connect (OSTI)

    Abraham J. Fetterman and Nathaniel J. Fisch

    2011-05-26

    Practical disposal of nuclear waste requires high-throughput separation techniques. The most dangerous part of nuclear waste is the fission product, which contains the most active and mobile radioisotopes and produces most of the heat. We suggest that the fission products could be separated as a group from nuclear waste using plasma mass filters. Plasmabased processes are well suited to separating nuclear waste, because mass rather than chemical properties are used for separation. A single plasma stage can replace several stages of chemical separation, producing separate streams of bulk elements, fission products, and actinoids. The plasma mass filters may have lower cost and produce less auxiliary waste than chemical processing plants. Three rotating plasma configurations are considered that act as mass filters: the plasma centrifuge, the Ohkawa filter, and the asymmetric centrifugal trap.

  5. Plasma Mass Filters For Nuclear Waste Reprocessing

    SciTech Connect (OSTI)

    Abraham J. Fetterman and Nathaniel J. Fisch

    2011-05-25

    Practical disposal of nuclear waste requires high-throughput separation techniques. The most dangerous part of nuclear waste is the fission product, which contains the most active and mobile radioisotopes and produces most of the heat. We suggest that the fission products could be separated as a group from nuclear waste using plasma mass filters. Plasmabased processes are well suited to separating nuclear waste, because mass rather than chemical properties are used for separation. A single plasma stage can replace several stages of chemical separation, producing separate streams of bulk elements, fission products, and actinoids. The plasma mass filters may have lower cost and produce less auxiliary waste than chemical processing plants. Three rotating plasma configurations are considered that act as mass filters: the plasma centrifuge, the Ohkawa filter, and the asymmetric centrifugal trap.

  6. Plasma filtering techniques for nuclear waste remediation

    DOE Public Access Gateway for Energy & Science Beta (PAGES Beta)

    Gueroult, Renaud; Hobbs, David T.; Fisch, Nathaniel J.

    2015-04-24

    Nuclear waste cleanup is challenged by the handling of feed stocks that are both unknown and complex. Plasma filtering, operating on dissociated elements, offers advantages over chemical methods in processing such wastes. The costs incurred by plasma mass filtering for nuclear waste pretreatment, before ultimate disposal, are similar to those for chemical pretreatment. However, significant savings might be achieved in minimizing the waste mass. As a result, this advantage may be realized over a large range of chemical waste compositions, thereby addressing the heterogeneity of legacy nuclear waste.

  7. Demonstrated Petroleum Reduction Using Oil Bypass Filter Technology...

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

    Demonstrated Petroleum Reduction Using Oil Bypass Filter Technology on Heavy and Light Vehicles Demonstrated Petroleum Reduction Using Oil Bypass Filter Technology on Heavy and ...

  8. Filter:Incentives by Eligible Technologies | Open Energy Information

    Open Energy Info (EERE)

    navigation, search This filter covers the property IncentiveTechDsc. Retrieved from "http:en.openei.orgwindex.php?titleFilter:IncentivesbyEligibleTechnologies&oldid267428...

  9. Nuclear Energy Enabling Technologies | Department of Energy

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

    Enabling Technologies Nuclear Energy Enabling Technologies Nuclear Energy Enabling Technologies The Nuclear Energy Enabling Technologies (NEET) Program will develop crosscutting ...

  10. Plasma filtering techniques for nuclear waste remediation

    DOE Public Access Gateway for Energy & Science Beta (PAGES Beta)

    Gueroult, Renaud; Hobbs, David T.; Fisch, Nathaniel J.

    2015-04-24

    The economical viability of nuclear waste cleanup e orts could, in some cases, be put at risk due to the difficulties faced in handling unknown and complex feedstocks. Plasma filtering, which operates on dissociated elements, offers advantages over chemical techniques for the processing of such wastes. In this context, the economic feasibility of plasma mass filtering for nuclear waste pretreatment before ultimate disposal is analyzed. Results indicate similar costs for chemical and plasma solid-waste pretreatment per unit mass of waste, but suggest significant savings potential as a result of a superior waste mass minimization. This performance improvement is observed overmore » a large range of waste chemical compositions, representative of legacy waste's heterogeneity. Although smaller, additional savings arise from the absence of a secondary liquid waste stream, as typically produced by chemical techniques.« less

  11. Plasma filtering techniques for nuclear waste remediation

    SciTech Connect (OSTI)

    Gueroult, Renaud; Hobbs, David T.; Fisch, Nathaniel J.

    2015-04-24

    The economical viability of nuclear waste cleanup e orts could, in some cases, be put at risk due to the difficulties faced in handling unknown and complex feedstocks. Plasma filtering, which operates on dissociated elements, offers advantages over chemical techniques for the processing of such wastes. In this context, the economic feasibility of plasma mass filtering for nuclear waste pretreatment before ultimate disposal is analyzed. Results indicate similar costs for chemical and plasma solid-waste pretreatment per unit mass of waste, but suggest significant savings potential as a result of a superior waste mass minimization. This performance improvement is observed over a large range of waste chemical compositions, representative of legacy waste's heterogeneity. Although smaller, additional savings arise from the absence of a secondary liquid waste stream, as typically produced by chemical techniques.

  12. Nuclear Safety R&D in the Waste Processing Technology Development...

    Office of Environmental Management (EM)

    & Technology 2 Outline Nuclear Safety Research & Development Overview Summary of EM- NSR&D Presentations from February 2009 Evaluating Performance of Nuclear Grade HEPA Filters ...

  13. Nuclear Reactors and Technology

    SciTech Connect (OSTI)

    Cason, D.L.; Hicks, S.C.

    1992-01-01

    This publication Nuclear Reactors and Technology (NRT) announces on a monthly basis the current worldwide information available from the open literature on nuclear reactors and technology, including all aspects of power reactors, components and accessories, fuel elements, control systems, and materials. This publication contains the abstracts of DOE reports, journal articles, conference papers, patents, theses, and monographs added to the Energy Science and Technology Database during the past month. Also included are US information obtained through acquisition programs or interagency agreements and international information obtained through the International Energy Agency`s Energy Technology Data Exchange or government-to-government agreements. The digests in NRT and other citations to information on nuclear reactors back to 1948 are available for online searching and retrieval on the Energy Science and Technology Database and Nuclear Science Abstracts (NSA) database. Current information, added daily to the Energy Science and Technology Database, is available to DOE and its contractors through the DOE Integrated Technical Information System. Customized profiles can be developed to provide current information to meet each user`s needs.

  14. Nuclear Energy Safety Technologies

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

    Safety Technologies - Sandia Energy Energy Search Icon Sandia Home Locations Contact Us Employee Locator Energy & Climate Secure & Sustainable Energy Future Stationary Power Energy Conversion Efficiency Solar Energy Wind Energy Water Power Supercritical CO2 Geothermal Natural Gas Safety, Security & Resilience of the Energy Infrastructure Energy Storage Nuclear Power & Engineering Grid Modernization Battery Testing Nuclear Fuel Cycle Defense Waste Management Programs Advanced

  15. Nuclear Technology Programs

    SciTech Connect (OSTI)

    Harmon, J.E.

    1990-10-01

    This document reports on the work done by the Nuclear Technology Programs of the Chemical Technology Division, Argonne National Laboratory, in the period April--September 1988. These programs involve R D in three areas: applied physical chemistry, separation science and technology, and nuclear waste management. The work in applied physical chemistry includes investigations into the processes that control the release and transport of fission products under accident-like conditions, the thermophysical properties of selected materials in environments simulating those of fusion energy systems. In the area of separation science and technology, the bulk of the effort is concerned with developing and implementing processes for the removal and concentration of actinides from waste streams contaminated by transuranic elements. Another effort is concerned with examining the feasibility of substituting low-enriched for high-enriched uranium in the production of fission-product {sup 99}Mo. In the area of waste management, investigations are underway on the performance of materials in projected nuclear repository conditions to provide input to the licensing of the nation's high-level waste repositories.

  16. NUCLEAR RADIATION DOSIMETER USING COMPOSITE FILTER AND A SINGLE ELEMENT FILTER

    DOE Patents [OSTI]

    Storm, E.; Shlaer, S.

    1964-04-21

    A nuclear radiation dosimeter is described that uses, in combination, a composite filter and a single element filter. The composite filter contains a plurality of comminuted metals having K-edges evenly distributed over the energy range of interest and the quantity of each of the metals is selected to result in filtering in an amount inversely proportional to the sensitivity of the film in the range over l00 kev. A copper filter is used that has a thickness to contribute the necessary additional correction in the interval between 40 and 100 kev. (AEC)

  17. Requirements from Particulate Filter Technology for Commercial...

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

    Hot Gas Filtration of Fine and Ultra fine Particles with Liquid Phase Sintered SiC Ceramic DPF Evaluation of Passive and Active Soot Filters for Removal of Particulate ...

  18. Nuclear Reactor Technologies | Department of Energy

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

    Reactor Technologies Nuclear Reactor Technologies TVA Watts Bar Nuclear Power Plant | Photo courtesy of Tennessee Valley Authority TVA Watts Bar Nuclear Power Plant | Photo ...

  19. Advanced Nuclear Technologies

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

    Advanced Nuclear Reactors Advanced Nuclear Reactors Turbulent Flow of Coolant in an Advanced Nuclear Reactor Visualizing Coolant Flow in Sodium Reactor Subassemblies Sodium-cooled Fast Reactor (SFR) Coolant Flow At the heart of a nuclear power plant is the reactor. The fuel assembly is placed inside a reactor vessel where all the nuclear reactions occur to produce the heat and steam used for power generation. Nonetheless, an entire power plant consists of many other support components and key

  20. Technology development: HEPA filter service life test plan

    SciTech Connect (OSTI)

    Kirchner, K.N.; Cummings, K.G.; Leck, W.C.; Fretthold, J.K.

    1995-05-31

    Rocky Flats Environmental Technology Site (the Site) has approximately 10,000 High Efficiency Particulate Air (HEPA) Filters installed in a variety of filter plenums. These ventilation/filtration plenum systems are used to control the release of airborne particulate contaminates to the environment during normal operations and also during potential design-based accidents. The operational integrity of the HEPA filter plenums is essential to maintaining the margins of safety as required by building specific Final Safety Analysis Reports (FSARS) for protection of the public and environment. An Unreviewed Safety Question Determination (USQD), USDQ-RFP94.0615-ARS, was conducted in 1994 addressing the potential inadequacy of the safety envelope for Protected Area building HEPA plenums. While conducting this USQD, questions were raised concerning the maximum service life criteria for HEPA filters. Accident scenarios in existing FSARs identify conditions that could potentially cause plugging or damage of down stream HEPA filters as a result of impaction from failed filters. Additionally, available data indicates that HEPA filters experience structural degradation due to the effects of age. The Unresolved Safety Question (USQ) compensatory measures thus require testing and analysis of used HEPA filters in order to determine and implement service life criteria.

  1. Nuclear Proliferation Technology Trends Analysis

    SciTech Connect (OSTI)

    Zentner, Michael D.; Coles, Garill A.; Talbert, Robert J.

    2005-10-04

    A process is underway to develop mature, integrated methodologies to address nonproliferation issues. A variety of methodologies (both qualitative and quantitative) are being considered. All have one thing in common, a need for a consistent set of proliferation related data that can be used as a basis for application. One approach to providing a basis for predicting and evaluating future proliferation events is to understand past proliferation events, that is, the different paths that have actually been taken to acquire or attempt to acquire special nuclear material. In order to provide this information, this report describing previous material acquisition activities (obtained from open source material) has been prepared. This report describes how, based on an evaluation of historical trends in nuclear technology development, conclusions can be reached concerning: (1) The length of time it takes to acquire a technology; (2) The length of time it takes for production of special nuclear material to begin; and (3) The type of approaches taken for acquiring the technology. In addition to examining time constants, the report is intended to provide information that could be used to support the use of the different non-proliferation analysis methodologies. Accordingly, each section includes: (1) Technology description; (2) Technology origin; (3) Basic theory; (4) Important components/materials; (5) Technology development; (6) Technological difficulties involved in use; (7) Changes/improvements in technology; (8) Countries that have used/attempted to use the technology; (9) Technology Information; (10) Acquisition approaches; (11) Time constants for technology development; and (12) Required Concurrent Technologies.

  2. Nuclear Reactors and Technology; (USA)

    SciTech Connect (OSTI)

    Cason, D.L.; Hicks, S.C.

    1991-01-01

    Nuclear Reactors and Technology (NRT) announces on a monthly basis the current worldwide information available from the open literature on nuclear reactors and technology, including all aspects of power reactors, components and accessories, fuel elements, control systems, and materials. This publication contains the abstracts of DOE reports, journal articles, conference papers, patents, theses, and monographs added to the Energy Science and Technology Database (EDB) during the past month. Also included are US information obtained through acquisition programs or interagency agreements and international information obtained through the International Energy Agency's Energy Technology Data Exchange or government-to-government agreements. The digests in NRT and other citations to information on nuclear reactors back to 1948 are available for online searching and retrieval on EDB and Nuclear Science Abstracts (NSA) database. Current information, added daily to EDB, is available to DOE and its contractors through the DOE integrated Technical Information System. Customized profiles can be developed to provide current information to meet each user's needs.

  3. Improved HEPA Filter Technology for Flexible and Rigid Containment Barriers

    SciTech Connect (OSTI)

    P. A. Pinson

    1998-07-01

    Safety and reliability in glovebox operations can be significantly improved and waste packaging efficiencies can be increased by inserting flexible, lightweight, high capacity HEPA filters into the walls of plastic sheet barriers. This HEPA filter/barrier technology can be adapted to a wide variety of applications: disposable waste bags, protective environmental barriers for electronic equipment, single or multiple use glovebag assemblies, flexible glovebox wall elements, and room partitions. These reliable and inexpensive filtered barriers have many uses in fields such as radioactive waste processing, HVAC filter changeout, vapor or grit blasting, asbestos cleanup, pharmaceutical, medical, biological, and electronic equipment containment. The applications can result in significant cost savings, improved operational reliability and safety, and total waste volume reduction. This technology was developed at the Argonne National Laboratory-West (ANL-W) in 1993 and has been used at ANL-W since then at the TRU Waste Characterization Chamber Gloveboxes. Another 1998 AGS Conference paper titled "TRU Waste Characterization Gloveboxes", presented by Mr. David Duncan of ANL-W, describes these boxes.

  4. The Governance of Nuclear Technology

    SciTech Connect (OSTI)

    Vergino, E S; May, M

    2003-09-22

    Eisenhower's Atoms for Peace speech in 1953 is remembered for engaging the world, and the Soviet Union in particular, in a dialogue about arms control and the formulation of a nuclear regime in which national and international security concerns growing from this unprecedented emerging and frightening new weapons capability would be addressed while tapping the civilian promise of nuclear applications for the good of mankind. Out of it came a series of initiatives, leading fifteen years later to the NPT, intended to allow the growth and spread of the beneficial uses of nuclear know-how while constraining the incentives and capabilities for nuclear weapons. The last 50 years has seen a gradual spread in nations with nuclear weapons, other nations with nuclear knowledge and capabilities, and still others with nuclear weapon intentions. Still most nations of the world have forgone weapon development, most have signed and abided by the NPT, and some that have had programs or even weapons, have turned these capabilities off. Yet despite this experience, and despite a relatively successful record up to a few years ago, there is today a clear and generally recognized crisis in nuclear governance, a crisis that affects the future of all the cross-cutting civilian/security issues we have cited. The crux of this crisis is a lack of consensus among the major powers whose support of international efforts is necessary for effective governance of nuclear activities. The lack of consensus focuses on three challenges: what to do about non-compliance, what to do about non-adherence, and what to do about the possible leakage of nuclear materials and technologies to terrorist groups. Short of regaining consensus on the priority to be given to nuclear material and technology controls, it is unlikely that any international regime to control nuclear materials and technologies, let alone oversee a growth in the nuclear power sector, will be successful in the tough cases where it needs to be successful. Regaining that consensus on the other hand means alleviating some fundamental insecurity on the part of states, and weakening the hold that terrorist groups have on some state governments. This in turn requires that some fundamental issues be addressed, with recognition that these are part of a suite of complex and dynamic interactions. Among these issues are: How will states provide for their own security and other central interests while preventing further proliferation, protecting against the use of nuclear weapons, and yet allowing for the possible expansion of nuclear power?; How best can states with limited resources to fight terrorist activities and safeguard nuclear materials be assisted in securing their materials and technologies?; What is the future role of international inspections? Does the IAEA remain the right organization to carry out these tasks? If not, what are the desired characteristics of a successor agency and can there be agreement on one?; How confident can we be of nonproliferation as latent nuclear weapon capabilities spread? The policies to address these and other issues must explicitly deal with NPT members who do not observe their obligations; NPT non-members; illicit trade in SNM and weapon technologies and the possibility of a regional nuclear war.

  5. Report of the Nuclear Reactor Technology Subcommittee

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

    Nuclear Reactor Technology Subcommittee November 18, 2014 Nuclear power competitiveness in ... test reactors worldwide (e.g., JHR in France, MYRRHA in Belgium and MBIR in Russia). ...

  6. Nuclear power high technology colloquium: proceedings

    SciTech Connect (OSTI)

    Not Available

    1984-12-10

    Reports presenting information on technology advancements in the nuclear industry and nuclear power plant functions have been abstracted and are available on the energy data base.

  7. NNSA Awards Information Technology Contract | National Nuclear...

    National Nuclear Security Administration (NNSA)

    Information Technology Contract | National Nuclear Security Administration Facebook Twitter Youtube Flickr RSS People Mission Managing the Stockpile Preventing Proliferation...

  8. nuclear technology | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    Nuclear Security Administration Facebook Twitter Youtube Flickr RSS People Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response ...

  9. History of nuclear technology development in Japan

    SciTech Connect (OSTI)

    Yamashita, Kiyonobu

    2015-04-29

    Nuclear technology development in Japan has been carried out based on the Atomic Energy Basic Act brought into effect in 1955. The nuclear technology development is limited to peaceful purposes and made in a principle to assure their safety. Now, the technologies for research reactors radiation application and nuclear power plants are delivered to developing countries. First of all, safety measures of nuclear power plants (NPPs) will be enhanced based on lesson learned from TEPCO Fukushima Daiichi NPS accident.

  10. Nuclear Facilities and Applied Technologies at Sandia

    SciTech Connect (OSTI)

    Wheeler, Dave; Kaiser, Krista; Martin, Lonnie; Hanson, Don; Harms, Gary; Quirk, Tom

    2014-11-28

    The Nuclear Facilities and Applied Technologies organization at Sandia National Laboratories Technical Area Five (TA-V) is the leader in advancing nuclear technologies through applied radiation science and unique nuclear environments. This video describes the organizations capabilities, facilities, and culture.

  11. Peaceful Uses of Nuclear Technology | National Nuclear Security

    National Nuclear Security Administration (NNSA)

    Administration Peaceful Uses of Nuclear Technology United States and China Mark 10th Anniversary of Peaceful Uses of Nuclear Technology Joint Coordination Meetings CHENGDU, CHINA - On May 6 and 7, the Department of Energy's National Nuclear Security Administration (NNSA) Deputy Administrator for Defense Nuclear Nonproliferation Anne Harrington and China National Energy Administration (NEA) Director General Liu Baohua co-chaired the 10th Peaceful Uses of

  12. Nuclear Reactor Technology Subcommittee of NEAC

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

    advanced technology deployment in nuclear power plants and more rapid commercialization ... be, commissioning new test reactors (France, China, Netherlands, and Russia). * The ...

  13. Preventing Proliferation of Nuclear Materials and Technology...

    National Nuclear Security Administration (NNSA)

    Preventing Proliferation of Nuclear Materials and Technology January 31, 2011 NNSA's ... Yearly reviewing thousands of export license requests for proliferation risks in ...

  14. Report of the ADVANCED NUCLEAR TRANSFORMATION TECHNOLOGY SUBCOMMITTEE...

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

    of the ADVANCED NUCLEAR TRANSFORMATION TECHNOLOGY SUBCOMMITTEE of the NUCLEAR ENERGY RESEARCH ADVISORY COMMITTEE Report of the ADVANCED NUCLEAR TRANSFORMATION TECHNOLOGY...

  15. NEAC Nuclear Reactor Technology Subcommittee Report for December...

    Office of Environmental Management (EM)

    Nuclear Reactor Technology Subcommittee Report for December 11, 2015 Meeting NEAC Nuclear Reactor Technology Subcommittee Report for December 11, 2015 Meeting PDF icon NEAC Nuclear...

  16. The nuclear materials control technology briefing book

    SciTech Connect (OSTI)

    Hartwell, J.K.; Fernandez, S.J.

    1992-03-01

    As national and international interests in nuclear arms control and non-proliferation of nuclear weapons, intensify, it becomes ever more important that contributors be aware of the technologies available for the measurement and control of the nuclear materials important to nuclear weapons development. This briefing book presents concise, nontechnical summaries of various special nuclear material (SNM) and tritium production monitoring technologies applicable to the control of nuclear materials and their production. Since the International Atomic Energy Agency (IAEA) operates a multinational, on-site-inspector-based safeguards program in support of the Treaty on the Non-Proliferation of Nuclear Weapons (NPT), many (but not all) of the technologies reported in this document are in routine use or under development for IAEA safeguards.

  17. Final Report: Part 1. In-Place Filter Testing Instrument for Nuclear Material Containers. Part 2. Canister Filter Test Standards for Aerosol Capture Rates.

    SciTech Connect (OSTI)

    Brown, Austin Douglas; Runnels, Joel T.; Moore, Murray E.; Reeves, Kirk Patrick

    2014-11-02

    A portable instrument has been developed to assess the functionality of filter sand o-rings on nuclear material storage canisters, without requiring removal of the canister lid. Additionally, a set of fifteen filter standards were procured for verifying aerosol leakage and pressure drop measurements in the Los Alamos Filter Test System. The US Department of Energy uses several thousand canisters for storing nuclear material in different chemical and physical forms. Specialized filters are installed into canister lids to allow gases to escape, and to maintain an internal ambient pressure while containing radioactive contaminants. Diagnosing the condition of container filters and canister integrity is important to ensure worker and public safety and for determining the handling requirements of legacy apparatus. This report describes the In-Place-Filter-Tester, the Instrument Development Plan and the Instrument Operating Method that were developed at the Los Alamos National Laboratory to determine the “as found” condition of unopened storage canisters. The Instrument Operating Method provides instructions for future evaluations of as-found canisters packaged with nuclear material. Customized stainless steel canister interfaces were developed for pressure-port access and to apply a suction clamping force for the interface. These are compatible with selected Hagan-style and SAVY-4000 storage canisters that were purchased from NFT (Nuclear Filter Technology, Golden, CO). Two instruments were developed for this effort: an initial Los Alamos POC (Proof-of-Concept) unit and the final Los Alamos IPFT system. The Los Alamos POC was used to create the Instrument Development Plan: (1) to determine the air flow and pressure characteristics associated with canister filter clogging, and (2) to test simulated configurations that mimicked canister leakage paths. The canister leakage scenarios included quantifying: (A) air leakage due to foreign material (i.e. dust and hair) fouling of o-rings, (B) leakage through simulated cracks in o-rings, and (C) air leakage due to inadequately tightened canister lids. The Los Alamos POC instrument determined pertinent air flow and pressure quantities, and this knowledge was used to specify a customized Isaac® (Z axis, Salt Lake City, UT) leak test module. The final Los Alamos IPFT (incorporating the Isaac® leak test module) was used to repeat the tests in the Instrument Development Plan (with simulated filter clogging tests and canister leak pathway tests). The Los Alamos IPFT instrument is capable of determining filter clogging and leak rate conditions, without requiring removal of the container lid. The IPFT measures pressure decay rate from 1.7E-03 in WC/sec to 1.7E-01 in WC/sec. On the same unit scale, helium leak testing of canisters has a range from 5.7E-07 in WC/sec to 1.9E-03 in WC/sec. For a 5-quart storage canister, the IPFT measures equivalent leak flow rates from 0.03 to 3.0 cc/sec. The IPFT does not provide the same sensitivity as helium leak testing, but is able to gauge the assembled condition of as-found and in-situ canisters.

  18. Requirements from Particulate Filter Technology for Commercial Vehicles:

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

    Sintered Metal Particulate Filter Opens a New Dimension of Performance | Department of Energy biddinger.pdf More Documents & Publications 12TH DIESEL ENGINE-EFFICIENCY AND EMISSIONS RESEARCH CONFERENCE (DEER 2006) PRESENTATIONS Hot Gas Filtration of Fine and Ultra fine Particles with Liquid Phase Sintered SiC Ceramic DPF Evaluation of Passive and Active Soot Filters for Removal of Particulate Emissions from Diesel Engines

  19. NEAC Nuclear Reactor Technology Subcommittee Report for December 11, 2015

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

    Meeting | Department of Energy Nuclear Reactor Technology Subcommittee Report for December 11, 2015 Meeting NEAC Nuclear Reactor Technology Subcommittee Report for December 11, 2015 Meeting PDF icon NEAC Nuclear Reactor Technology

  20. Production Technology | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    Production Technology NNSA continues to assure the safety, security, and reliability of the existing stockpile as it progresses towards a newly responsive nuclear weapons infrastructure as called for in the 2001 Nuclear Posture Review and described in the vision for Complex Transformation. The work is one of the key providers of design-to-manufacturing and technological readiness capabilities for this transformation effort. NNSA closely integrates planning and project selection prioritization

  1. Advanced Nuclear Technology: Advanced Light Water Reactors Utility...

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

    Nuclear Technology: Advanced Light Water Reactors Utility Requirements Document Small Modular Reactors Inclusion Summary Advanced Nuclear Technology: Advanced Light Water Reactors ...

  2. ENTECH European Nuclear Technologies Ltd | Open Energy Information

    Open Energy Info (EERE)

    ENTECH European Nuclear Technologies Ltd Jump to: navigation, search Name: ENTECH (European Nuclear Technologies Ltd.) Place: Bristol, United Kingdom Zip: BS99 7JT Product: Entech...

  3. Fusion Nuclear Science and Technology Program - Status and plans...

    Office of Environmental Management (EM)

    Fusion Nuclear Science and Technology Program - Status and plans for tritium research ... May 05-07, 2015. PDF icon Fusion Nuclear Science and Technology Program - Status and plans ...

  4. Fusion Nuclear Science and Technology Program - Status and Plans...

    Office of Environmental Management (EM)

    Plans for Tritium Research Fusion Nuclear Science and Technology Program - Status and ... 23-25, 2014. PDF icon Fusion Nuclear Science and Technology Program - Status and Plans ...

  5. Idaho Nuclear Technology and Engineering Center Tank Farm Facility...

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

    Idaho Nuclear Technology and Engineering Center Tank Farm Facility Idaho Nuclear Technology and Engineering Center Tank Farm Facility The Secretary of Energy signed Section 3116 of ...

  6. Advanced Particulate Filter Technologies for Direct Injection Gasoline Engine Applications

    Broader source: Energy.gov [DOE]

    Specific designs and material properties have to be developed for gasoline particulate filters based on the different engine and exhaust gas characteristic of gasoline engines compared to diesel engines, e.g., generally lower levels of engine-out particulate emissions or higher GDI exhaust gas temperatures

  7. Human factors in nuclear technology - a history

    SciTech Connect (OSTI)

    Jones, D.B. )

    1992-01-01

    Human factors, human factors engineering (HFE), or ergonomics did not receive much formal attention in nuclear technology prior to the Three Mile Island Unit 2 (TMI-2) incident. Three principal reasons exist for this lack of concern. First, emerging technologies show little concern with how people will use a new system. Making the new technology work is considered more important than the people who will use it. Second, the culture of the users of nuclear power did not recognize a need for human factors. Traditional utilities had well established and effective engineering designs for control of electric power generation, while medicine considered the use of nuclear isotopes another useful tool, not requiring special ergonomics. Finally, the nuclear industry owed much to Admiral Rickover. He was definitely opposed.

  8. Spent Nuclear Fuel Alternative Technology Decision Analysis

    SciTech Connect (OSTI)

    Shedrow, C.B.

    1999-11-29

    The Westinghouse Savannah River Company (WSRC) made a FY98 commitment to the Department of Energy (DOE) to recommend a technology for the disposal of aluminum-based spent nuclear fuel (SNF) at the Savannah River Site (SRS). The two technologies being considered, direct co-disposal and melt and dilute, had been previously selected from a group of eleven potential SNF management technologies by the Research Reactor Spent Nuclear Fuel Task Team chartered by the DOE''s Office of Spent Fuel Management. To meet this commitment, WSRC organized the SNF Alternative Technology Program to further develop the direct co-disposal and melt and dilute technologies and ultimately provide a WSRC recommendation to DOE on a preferred SNF alternative management technology.

  9. Effective citizen advocacy of beneficial nuclear technologies

    SciTech Connect (OSTI)

    McKibben, J. Malvyn; Wood, Susan

    2007-07-01

    In 1991, a small group of citizens from communities near the Savannah River Site (SRS) formed a pro-nuclear education and advocacy group, Citizens for Nuclear Technology Awareness (CNTA). Their purpose was to: (1) counter nuclear misinformation that dominated the nation's news outlets, (2) provide education on nuclear subjects to area citizens, students, elected officials, and (3) provide informed citizen support for potential new missions for SRS when needed. To effectively accomplish these objectives it is also essential to establish and maintain good relations with community leaders and reporters that cover energy and nuclear subjects. The organization has grown considerably since its inception and has expanded its sphere of influence. We believe that our experiences over these fifteen years are a good model for effectively communicating nuclear subjects with the public. This paper describes the structure, operation and some of the results of CNTA. (authors)

  10. Proliferation Persuasion. Coercive Bargaining with Nuclear Technology

    SciTech Connect (OSTI)

    Volpe, Tristan A.

    2015-08-31

    Why do states wait for prolonged periods of time with the technical capacity to produce nuclear weapons? Only a handful of countries have ever acquired the sensitive nuclear fuel cycle technology needed to produce fissile material for nuclear weapons. Yet the enduring trend over the last five decades is for these states to delay or forgo exercising the nuclear weapons option provided by uranium enrichment or plutonium reprocessing capabilities. I show that states pause at this threshold stage because they use nuclear technology to bargain for concessions from both allies and adversaries. But when does nuclear latency offer bargaining benefits? My central argument is that challengers must surmount a dilemma to make coercive diplomacy work: the more they threaten to proliferate, the harder it becomes to reassure others that compliance will be rewarded with nuclear restraint. I identify a range of mechanisms able to solve this credibility problem, from arms control over breakout capacity to third party mediation and confidence building measures. Since each step towards the bomb raises the costs of implementing these policies, a state hits a sweet spot when it first acquires enrichment and/or reprocessing (ENR) technology. Subsequent increases in proliferation capability generate diminishing returns at the bargaining table for two reasons: the state must go to greater lengths to make a credible nonproliferation promise, and nuclear programs exhibit considerable path dependency as they mature over time. Contrary to the conventional wisdom about power in world politics, less nuclear latency thereby yields more coercive threat advantages. I marshal new primary source evidence from archives and interviews to identify episodes in the historical record when states made clear decisions to use ENR technology as a bargaining chip, and employ this theory of proliferation persuasion to explain how Japan, North Korea, and Iran succeeded and failed to barter concessions from the United States. By clarifying when countries are able to leverage steps towards the bomb for international political gain, my work advances our understanding of proliferation and coercive diplomacy.

  11. Current Abstracts Nuclear Reactors and Technology

    SciTech Connect (OSTI)

    Bales, J.D.; Hicks, S.C.

    1993-01-01

    This publication Nuclear Reactors and Technology (NRT) announces on a monthly basis the current worldwide information available from the open literature on nuclear reactors and technology, including all aspects of power reactors, components and accessories, fuel elements, control systems, and materials. This publication contains the abstracts of DOE reports, journal articles, conference papers, patents, theses, and monographs added to the Energy Science and Technology Database during the past month. Also included are US information obtained through acquisition programs or interagency agreements and international information obtained through acquisition programs or interagency agreements and international information obtained through the International Energy Agency`s Energy Technology Data Exchange or government-to-government agreements. The digests in NRT and other citations to information on nuclear reactors back to 1948 are available for online searching and retrieval on the Energy Science and Technology Database and Nuclear Science Abstracts (NSA) database. Current information, added daily to the Energy Science and Technology Database, is available to DOE and its contractors through the DOE Integrated Technical Information System. Customized profiles can be developed to provide current information to meet each user`s needs.

  12. Nuclear technologies for Moon and Mars exploration

    SciTech Connect (OSTI)

    Buden, D.

    1991-01-01

    Nuclear technologies are essential to successful Moon and Mars exploration and settlements. Applications can take the form of nuclear propulsion for transport of crews and cargo to Mars and the Moon; surface power for habitats and base power; power for human spacecraft to Mars; shielding and life science understanding for protection against natural solar and cosmic radiations; radioisotopes for sterilization, medicine, testing, and power; and resources for the benefits of Earth. 5 refs., 9 figs., 3 tabs.

  13. Improved Technology To Prevent Nuclear Proliferation And Counter Nuclear Terrorism

    SciTech Connect (OSTI)

    Richardson, J; Yuldashev, B; Labov, S; Knapp, R

    2006-06-12

    As the world moves into the 21st century, the possibility of greater reliance on nuclear energy will impose additional technical requirements to prevent proliferation. In addition to proliferation resistant reactors, a careful examination of the various possible fuel cycles from cradle to grave will provide additional technical and nonproliferation challenges in the areas of conversion, enrichment, transportation, recycling and waste disposal. Radiation detection technology and information management have a prominent role in any future global regime for nonproliferation. As nuclear energy and hence nuclear materials become an increasingly global phenomenon, using local technologies and capabilities facilitate incorporation of enhanced monitoring and detection on the regional level. Radiation detection technologies are an important tool in the prevention of proliferation and countering radiological/nuclear terrorism. A variety of new developments have enabled enhanced performance in terms of energy resolution, spatial resolution, passive detection, predictive modeling and simulation, active interrogation, and ease of operation and deployment in the field. For example, various gamma ray imaging approaches are being explored to combine spatial resolution with background suppression in order to enhance sensitivity many-fold at reasonable standoff distances and acquisition times. New materials and approaches are being developed in order to provide adequate energy resolution in field use without the necessity for liquid nitrogen. Different detection algorithms enable fissile materials to be distinguished from other radioisotopes.

  14. Section 3116 Determination for Idaho Nuclear Technology and Engineerin...

    Office of Environmental Management (EM)

    3116 Determination for Idaho Nuclear Technology and Engineering Center Tank Farm Facility, signed by Secretary Samuel W. Bodman Section 3116 Determination for Idaho Nuclear...

  15. June 2015 Most Viewed Documents for Fission And Nuclear Technologies...

    Office of Scientific and Technical Information (OSTI)

    June 2015 Most Viewed Documents for Fission And Nuclear Technologies Estimation of gas ... MIGRATION IN SOILS OF THE CHERNOBYL NUCLEAR POWER PLANT EXCLUSION ZONE Farfan, E ...

  16. March 2016 Most Viewed Documents for Fission And Nuclear Technologies...

    Office of Scientific and Technical Information (OSTI)

    Fission And Nuclear Technologies Estimation of gas leak rates through very small orifices ... methods and test results utilized for nuclear core applications (LWBR Development ...

  17. December 2015 Most Viewed Documents for Fission And Nuclear Technologi...

    Office of Scientific and Technical Information (OSTI)

    December 2015 Most Viewed Documents for Fission And Nuclear Technologies Estimation of gas ... methods and test results utilized for nuclear core applications (LWBR Development ...

  18. Most Viewed Documents for Fission and Nuclear Technologies: December...

    Office of Scientific and Technical Information (OSTI)

    Most Viewed Documents for Fission and Nuclear Technologies: December 2014 Stress analysis ... States)) (1992) 67 Behavior of spent nuclear fuel in water pool storage Johnson, A.B. ...

  19. Development of Partial Filter Technology for HDD Retrofit | Department of

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

    Energy 2005 Diesel Engine Emissions Reduction (DEER) Conference Presentations and Posters PDF icon 2005_deer_chatterjee.pdf More Documents & Publications SCRT Technology for Retrofit of Heavy-Duty Diesel Applications 3-D Printed Molds Hold Promise for Enhanced Wind Energy Manufacturing 3-D Printed Molds Hold Promise for Enhanced Wind Energy Manufacturing The Energy Department is exploring the production of wind energy blade molds through 3-D printing, which could reduce production time

  20. Fostering the Next Generation of Nuclear Energy Technology |...

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

    this draft solicitation would support advanced nuclear energy technologies that will catalyze the deployment of future projects that replicate or extend a technological innovation. ...

  1. State Nuclear Power Technology Corporation SNPTC | Open Energy...

    Open Energy Info (EERE)

    Technology Corporation SNPTC Jump to: navigation, search Name: State Nuclear Power Technology Corporation (SNPTC) Place: Beijing, Beijing Municipality, China Zip: 100032 Product:...

  2. Nuclear Separations Technologies Workshop Report | Department of Energy

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

    Separations Technologies Workshop Report Nuclear Separations Technologies Workshop Report The Department of Energy (DOE) sponsored a workshop on nuclear separations technologies in Bethesda, Maryland, on July 27 and 28, 2011, to (1) identify common needs and potential requirements in separations technologies and opportunities for program partnerships, and (2) evaluate the need for a DOE nuclear separations center of knowledge to improve cross- program collaboration in separations technology. The

  3. Summary, Long-Term Nuclear Technology Research and Development Plan |

    Energy Savers [EERE]

    Department of Energy Summary, Long-Term Nuclear Technology Research and Development Plan Summary, Long-Term Nuclear Technology Research and Development Plan In 1998, DOE established the Nuclear Energy Research Advisory Committee (NERAC) to provide advice to the Secretary and to the Director, Office of Nuclear Energy, Science, and Technology (NE), on the broad range of non-defense DOE nuclear technology programs. The NERAC recommended development of a long-range R&D program. This R&D

  4. Space nuclear power, propulsion, and related technologies.

    SciTech Connect (OSTI)

    Berman, Marshall

    1992-01-01

    Sandia National Laboratories (Sandia) is one of the nation's largest research and development (R&D) facilities, with headquarters at Albuquerque, New Mexico; a laboratory at Livermore, California; and a test range near Tonopah, Nevada. Smaller testing facilities are also operated at other locations. Established in 1945, Sandia was operated by the University of California until 1949, when, at the request of President Truman, Sandia Corporation was formed as a subsidiary of Bell Lab's Western Electric Company to operate Sandia as a service to the U.S. Government without profit or fee. Sandia is currently operated for the U.S. Department of Energy (DOE) by AT&T Technologies, Inc., a wholly-owned subsidiary of AT&T. Sandia's responsibility is national security programs in defense and energy with primary emphasis on nuclear weapon research and development (R&D). However, Sandia also supports a wide variety of projects ranging from basic materials research to the design of specialized parachutes. Assets, owned by DOE and valued at more than $1.2 billion, include about 600 major buildings containing about 372,000 square meters (m2) (4 million square feet [ft2]) of floor space, located on land totalling approximately 1460 square kilometers (km2) (562 square miles [mi]). Sandia employs about 8500 people, the majority in Albuquerque, with about 1000 in Livermore. Approximately 60% of Sandia's employees are in technical and scientific positions, and the remainder are in crafts, skilled labor, and administrative positions. As a multiprogram national laboratory, Sandia has much to offer both industrial and government customers in pursuing space nuclear technologies. The purpose of this brochure is to provide the reader with a brief summary of Sandia's technical capabilities, test facilities, and example programs that relate to military and civilian objectives in space. Sandia is interested in forming partnerships with industry and government organizations, and has already formed several cooperative alliances and agreements. Because of the synergism of multiple governmental and industrial sponsors of many programs, Sandia is frequently able to provide complex technical solutions in a relatively short time, and often at lower cost to a particular customer. They have listed a few ongoing programs at Sandia related to space nuclear technology as examples of the possible synergisms that could result from forming teams and partnerships with related technologies and objectives.

  5. April 2013 Most Viewed Documents for Fission And Nuclear Technologies...

    Office of Scientific and Technical Information (OSTI)

    April 2013 Most Viewed Documents for Fission And Nuclear Technologies Science Subject Feed Behavior of spent nuclear fuel in water pool storage Johnson, A.B. Jr. (null) 298 > ...

  6. Most Viewed Documents for Fission And Nuclear Technologies: September...

    Office of Scientific and Technical Information (OSTI)

    for Fission And Nuclear Technologies: September 2014 Estimation of gas leak rates through ... H.J. (1977) 71 Behavior of spent nuclear fuel in water pool storage Johnson, A.B. ...

  7. SRNS signs on as industry partner for Nuclear Engineering Technology

    National Nuclear Security Administration (NNSA)

    Education | National Nuclear Security Administration SRNS signs on as industry partner for Nuclear Engineering Technology Education Tuesday, August 12, 2014 - 12:08pm Augusta Technical College recently announced a formal Agreement of Understanding with Georgia Power and Savannah River Site management and operating contractor Savannah River Nuclear Solutions (SRNS) in support of the College's Nuclear Engineering Technology Program. The agreement recognizes SRNS as an industry partner, which

  8. Fusion Nuclear Science and Technology Program - Status and plans for

    Office of Environmental Management (EM)

    tritium research | Department of Energy plans for tritium research Fusion Nuclear Science and Technology Program - Status and plans for tritium research Presentation from the 35th Tritium Focus Group Meeting held in Princeton, New Jersey on May 05-07, 2015. PDF icon Fusion Nuclear Science and Technology Program - Status and plans for tritium research More Documents & Publications Fusion Nuclear Science and Technology Program - Status and Plans for Tritium Research Overview of tritium

  9. Guidance for Deployment of Mobile Technologies for Nuclear Power...

    Energy Savers [EERE]

    Guidance for Deployment of Mobile Technologies for Nuclear Power Plant Field Workers Guidance ... Additional benefits in safety, efficiency, and productivity are highly probable given ...

  10. Vehicle Technologies Office Merit Review 2015: Development of Radio Frequency Diesel Particulate Filter Sensor and Controls for Advanced Low-Pressure Drop Systems to Reduce Engine Fuel Consumption

    Broader source: Energy.gov [DOE]

    Presentation given by Filter Sensing Technologies, Inc. at 2015 DOE Hydrogen and Fuel Cells Program and Vehicle Technologies Office Annual Merit Review and Peer Evaluation Meeting about development...

  11. Vehicle Technologies Office Merit Review 2014: Development of Radio Frequency Diesel Particulate Filter Sensor and Controls for Advanced Low-Pressure Drop Systems to Reduce Engine Fuel Consumption

    Broader source: Energy.gov [DOE]

    Presentation given by Filter Sensing Technologies, Inc. at 2014 DOE Hydrogen and Fuel Cells Program and Vehicle Technologies Office Annual Merit Review and Peer Evaluation Meeting about development...

  12. U.S. Department of Energy FreedomCAR & Vehicle Technologies Program Oil Bypass Filter Technology Evaluation Final Report

    SciTech Connect (OSTI)

    L. R. Zirker; J. E. Francfort; J. J. Fielding

    2006-03-01

    This Oil Bypass Filter Technology Evaluation final report documents the feasibility of using oil bypass filters on 17 vehicles in the Idaho National Laboratory (INL) fleet during a 3-year test period. Almost 1.3 million test miles were accumulated, with eleven 4-cycle diesel engine buses accumulating 982,548 test miles and six gasoline-engine Chevrolet Tahoes accumulating 303,172 test miles. Two hundred and forty oil samples, taken at each 12,000-mile bus servicing event and at 3,000 miles for the Tahoes, documented the condition of the engine oils for continued service. Twenty-eight variables were normally tested, including the presence of desired additives and undesired wear metals such as iron and chrome, as well as soot, water, glycol, and fuel. Depending on the assumptions employed, the INL found that oil bypass filter systems for diesel engine buses have a positive payback between 72,000 and 144,000 miles. For the Tahoes, the positive payback was between 66,000 and 69,000 miles.

  13. The Los Alamos nuclear safeguards and nonproliferation technology development program

    SciTech Connect (OSTI)

    Smith, H.A. Jr.; Menlove, H.O.; Reilly, T.D.; Bosler, G.E.; Hakkila, E.A.; Eccleston, G.W.

    1994-04-01

    For nearly three decades, Los Alamos National Laboratory has developed and implemented nuclear measurement technology and training in support of national and international nuclear safeguards. This paper outlines the major elements of those technologies and highlights some of the latest developments.

  14. technology transfer | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    technology transfer Y-12 honors its inventors with Technology Transfer awards OAK RIDGE, Tennessee - Twenty-nine Y-12 inventors were recognized for their technology and innovative accomplishments during the recent 12th annual Technology Transfer Awards Ceremony. The site has a long history of producing technologies initially used at Y-12 and later transferred to the... Y-12 honors its inventors with Technology Transfer awards , Twenty-nine Y-12 inventors were recognized for their technology and

  15. Energy Department Invests $67 Million to Advanced Nuclear Technology |

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

    Department of Energy 7 Million to Advanced Nuclear Technology Energy Department Invests $67 Million to Advanced Nuclear Technology August 20, 2014 - 12:00pm Addthis News Media Contact 202-586-4940 WASHINGTON - Building on President Obama's Climate Action Plan and the Administration's efforts to expand clean energy innovation, the Energy Department announced today nearly $67 million in nuclear energy research and infrastructure enhancement awards. 83 projects were selected from across the

  16. Technology Readiness Levels for Advanced Nuclear Fuels and Materials Development

    SciTech Connect (OSTI)

    Jon Carmack

    2014-01-01

    The Technology Readiness Level (TRL) process is used to quantitatively assess the maturity of a given technology. The TRL process has been developed and successfully used by the Department of Defense (DOD) for development and deployment of new technology and systems for defense applications. In addition, NASA has also successfully used the TRL process to develop and deploy new systems for space applications. Advanced nuclear fuels and materials development is a critical technology needed for closing the nuclear fuel cycle. Because the deployment of a new nuclear fuel forms requires a lengthy and expensive research, development, and demonstration program, applying the TRL concept to the advanced fuel development program is very useful as a management and tracking tool. This report provides definition of the technology readiness level assessment process as defined for use in assessing nuclear fuel technology development for the Advanced Fuel Campaign (AFC).

  17. Nuclear Physics Accelerator Technology Yields New Process for Producing

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

    Boron-Nitride Nanotubes | U.S. DOE Office of Science (SC) Nuclear Physics Accelerator Technology Yields New Process for Producing Boron-Nitride Nanotubes Nuclear Physics (NP) NP Home About Research Facilities Science Highlights Benefits of NP Funding Opportunities Nuclear Science Advisory Committee (NSAC) Community Resources Contact Information Nuclear Physics U.S. Department of Energy SC-26/Germantown Building 1000 Independence Ave., SW Washington, DC 20585 P: (301) 903-3613 F: (301)

  18. Filter Measurement System for Nuclear Material Storage Canisters. End of Year Report FY 2013

    SciTech Connect (OSTI)

    Moore, Murray E. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Reeves, Kirk P. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2014-02-03

    A test system has been developed at Los Alamos National Laboratory to measure the aerosol collection efficiency of filters in the lids of storage canisters for special nuclear materials. Two FTS (filter test system) devices have been constructed; one will be used in the LANL TA-55 facility with lids from canisters that have stored nuclear material. The other FTS device will be used in TA-3 at the Radiation Protection Divisions Aerosol Engineering Facility. The TA-3 system will have an expanded analytical capability, compared to the TA-55 system that will be used for operational performance testing. The LANL FTS is intended to be automatic in operation, with independent instrument checks for each system component. The FTS has been described in a complete P&ID (piping and instrumentation diagram) sketch, included in this report. The TA-3 FTS system is currently in a proof-of-concept status, and TA-55 FTS is a production-quality prototype. The LANL specification for (Hagan and SAVY) storage canisters requires the filter shall capture greater than 99.97% of 0.45-micron mean diameter dioctyl phthalate (DOP) aerosol at the rated flow with a DOP concentration of 6515 micrograms per liter. The percent penetration (PEN%) and pressure drop (DP) of fifteen (15) Hagan canister lids were measured by NFT Inc. (Golden, CO) over a period of time, starting in the year 2002. The Los Alamos FTS measured these quantities on June 21, 2013 and on Oct. 30, 2013. The LANL(6-21-2013) results did not statistically match the NFT Inc. data, and the LANL FTS system was re-evaluated, and the aerosol generator was replaced and the air flow measurement method was corrected. The subsequent LANL(10-30-2013) tests indicate that the PEN% results are statistically identical to the NFT Inc. results. The LANL(10-30-2013) pressure drop measurements are closer to the NFT Inc. data, but future work will be investigated. An operating procedure for the FTS (filter test system) was written, and future project milestones are on track for completion

  19. Configuration and technology implications of potential nuclear hydrogen system applications.

    SciTech Connect (OSTI)

    Conzelmann, G.; Petri, M.; Forsberg, C.; Yildiz, B.; ORNL

    2005-11-05

    Nuclear technologies have important distinctions and potential advantages for large-scale generation of hydrogen for U.S. energy services. Nuclear hydrogen requires no imported fossil fuels, results in lower greenhouse-gas emissions and other pollutants, lends itself to large-scale production, and is sustainable. The technical uncertainties in nuclear hydrogen processes and the reactor technologies needed to enable these processes, as well waste, proliferation, and economic issues must be successfully addressed before nuclear energy can be a major contributor to the nation's energy future. In order to address technical issues in the time frame needed to provide optimized hydrogen production choices, the Nuclear Hydrogen Initiative (NHI) must examine a wide range of new technologies, make the best use of research funding, and make early decisions on which technology options to pursue. For these reasons, it is important that system integration studies be performed to help guide the decisions made in the NHI. In framing the scope of system integration analyses, there is a hierarchy of questions that should be addressed: What hydrogen markets will exist and what are their characteristics? Which markets are most consistent with nuclear hydrogen? What nuclear power and production process configurations are optimal? What requirements are placed on the nuclear hydrogen system? The intent of the NHI system studies is to gain a better understanding of nuclear power's potential role in a hydrogen economy and what hydrogen production technologies show the most promise. This work couples with system studies sponsored by DOE-EE and other agencies that provide a basis for evaluating and selecting future hydrogen production technologies. This assessment includes identifying commercial hydrogen applications and their requirements, comparing the characteristics of nuclear hydrogen systems to those market requirements, evaluating nuclear hydrogen configuration options within a given market, and identifying the key drivers and thresholds for market viability of nuclear hydrogen options.

  20. Ground-based Nuclear Detonation Detection (GNDD) Technology Roadmap

    SciTech Connect (OSTI)

    Casey, Leslie A.

    2014-01-13

    This GNDD Technology Roadmap is intended to provide guidance to potential researchers and help management define research priorities to achieve technology advancements for ground-based nuclear explosion monitoring science being pursued by the Ground-based Nuclear Detonation Detection (GNDD) Team within the Office of Nuclear Detonation Detection in the National Nuclear Security Administration (NNSA) of the U.S. Department of Energy (DOE). Four science-based elements were selected to encompass the entire scope of nuclear monitoring research and development (R&D) necessary to facilitate breakthrough scientific results, as well as deliver impactful products. Promising future R&D is delineated including dual use associated with the Comprehensive Nuclear-Test-Ban Treaty (CTBT). Important research themes as well as associated metrics are identified along with a progression of accomplishments, represented by a selected bibliography, that are precursors to major improvements to nuclear explosion monitoring.

  1. Further development of the cleanable steel HEPA filter, cost/benefit analysis, and comparison with competing technologies

    SciTech Connect (OSTI)

    Bergman, W.; Larsen, G.; Lopez, R.; Wilson, K.; Witherell, C.; McGregor, M.

    1997-01-01

    We have made further progress in developing a cleanable steel fiber HEPA filter. We fabricated a pleated cylindrical cartridge using commercially available steel fiber media that is made with 1 {mu}m stainless steel fibers and sintered into a sheet form. Test results at the Department of Energy (DOE) Filter Test Station at Oak Ridge show the prototype filter cartridge has 99.99% efficiency for 0.3 {mu}m dioctyl phthalate (DOP) aerosols and a pressure drop of 1.5 inches. Filter loading and cleaning tests using AC Fine dust showed the filter could be repeatedly cleaned using reverse air pulses. Our analysis of commercially optimized filters suggest that cleanable steel HEPA filters need to be made from steel fibers less than 1 {mu}m, and preferably 0.5 {mu}m, to meet the standard HEPA filter requirements in production units. We have demonstrated that 0.5 {mu}m steel fibers can be produced using the fiber bundling and drawing process. The 0.5 {mu}m steel fibers are then sintered into small filter samples and tested for efficiency and pressure drop. Test results on the sample showed a penetration of 0.0015% at 0.3 {mu}m and a pressure drop of 1.15 inches at 6.9 ft/min (3.5 cm/s) velocity. Based on these results, steel fiber media can easily meet the requirements of 0.03% penetration and 1.0 inch of pressure drop by using less fibers in the media. A cost analysis of the cleanable steel HEPA filter shows that, although the steel HEPA filter costs much more than the standard glass fiber HEPA filter, it has the potential to be very cost effective because of the high disposal costs of contaminated HEPA filters. We estimate that the steel HEPA filter will save an average of $16,000 over its 30 year life. The additional savings from the clean-up costs resulting from ruptured glass HEPA filters during accidents was not included but makes the steel HEPA filter even more cost effective. We also present the results of our evaluation of competing technologies with metallic and ceramic powder filters, ceramic fiber falters, and reinforced glass fiber filters. In general, the metallic and ceramic powder filters have pressure drops in excess of 25 inches of water for HEPA grade efficiencies and are therefore not viable candidates. The ceramic fiber filters cannot meet the HEPA efficiency because the fiber diameters are too large. The reinforced glass fiber filter is a promising candidate for the cleanable HEPA filter but requires additional development and testing to confirm its potential to be repeatedly cleaned. This report is based upon material extracted from a DOE technical review of the Mixed Waste Integrated Program and from the final report of a systems analysis of cleanable steel HEPA filters.

  2. PPPL's MINDS Technology Takes Nuclear Detection to the Marketplace |

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

    Department of Energy PPPL's MINDS Technology Takes Nuclear Detection to the Marketplace PPPL's MINDS Technology Takes Nuclear Detection to the Marketplace October 20, 2011 - 5:25pm Addthis Charles Gentile (center) and other members of the MINDS team, including Ken Silber (right) and Bill Davis (left) work on new techniques to identify radionuclides. | Photo by Elle Starkman/Princeton Plasma Physics Laboratory Office of Communications Charles Gentile (center) and other members of the MINDS

  3. Define and Quantify the Physics of Air Flow, Pressure Drop and Aerosol Collection in Nuclear Grade HEPA Filters

    SciTech Connect (OSTI)

    Moore, Murray E.

    2015-02-23

    Objective: Develop a set of peer-review and verified analytical methods to adjust HEPA filter performance to different flow rates, temperatures and altitudes. Experimental testing will measure HEPA filter flow rate, pressure drop and efficiency to verify the analytical approach. Nuclear facilities utilize HEPA (High Efficiency Particulate Air) filters to purify air flow for workspace ventilation. However, the ASME AG-1 technical standard (Code on Nuclear Air and Gas Treatment) does not adequately describe air flow measurement units for HEPA filter systems. Specifically, the AG-1 standard does not differentiate between volumetric air flow in ACFM (actual cubic feet per minute)compared to mass flow measured in SCFM (standard cubic feet per minute). More importantly, the AG-1 standard has an overall deficiency for using HEPA filter devices at different air flow rates, temperatures, and altitudes. Technical Approach: The collection efficiency and pressure drops of 18 different HEPA filters will be measured over a range of flow rates, temperatures and altitudes. The experimental results will be compared to analytical scoping calculations. Three manufacturers have allocated six HEPA filters each for this effort. The 18 filters will be tested at two different flow rates, two different temperatures and two different altitudes. The 36 total tests will be conducted at two different facilities: the ATI Test facilities (Baltimore MD) and the Los Alamos National Laboratory (Los Alamos NM). The Radiation Protection RP-SVS group at Los Alamos has an aerosol wind tunnel that was originally designed to evaluate small air samplers. In 2010, modifications were started to convert the wind tunnel for HEPA filter testing. (Extensive changes were necessary for the required aerosol generators, HEPA test fixtures, temperature control devices and measurement capabilities.) To this date, none of these modification activities have been funded through a specific DOE or NNSA program. This is expected to require six months of time, after receipt of funding. Benefits: US DOE facilities that use HEPA filters will benefit from access to the new operational measurement methods. Uncertainty and guesswork will be removed from HEPA filter operations.

  4. Cost estimate guidelines for advanced nuclear power technologies

    SciTech Connect (OSTI)

    Delene, J.G.; Hudson, C.R. II.

    1990-03-01

    To make comparative assessments of competing technologies, consistent ground rules must be applied when developing cost estimates. This document provides a uniform set of assumptions, ground rules, and requirements that can be used in developing cost estimates for advanced nuclear power technologies. 10 refs., 8 figs., 32 tabs.

  5. Global Nuclear Energy Partnership Technology Development Plan

    SciTech Connect (OSTI)

    David J. Hill

    2007-07-01

    This plan describes the GNEP Technology Demonstration Program (GNEP-TDP). It has been prepared to guide the development of integrated plans and budgets for realizing the domestic portion of the GNEP vision as well as providing the basis for developing international cooperation. Beginning with the GNEP overall goals, it describes the basic technical objectives for each element of the program, summarizes the technology status and identifies the areas of greatest technical risk. On this basis a proposed technology demonstration program is described that can deliver the required information for a Secretarial decision in the summer of 2008 and support construction of facilities.

  6. Nuclear Physics Technology Saves Lives | Jefferson Lab

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

    Physics Technology Saves Lives January 11, 2006 Listen to this story Ribbon With early ... Group, headed by Stan Majewski, is part of the Physics Division here at Jefferson Lab. ...

  7. U.S. Department of Energy FreedomCAR & Vehicle Technologies Program Oil Bypass Filter Technology Evaluation - Sixth Quarterly Report, January - March 2004

    SciTech Connect (OSTI)

    U.S. Department of Energy; Larry Zirker

    2004-06-01

    This Oil Bypass Filter Technology Evaluation quarterly report (January-March 2004) details the ongoing fleet evaluation of an oil bypass filter technology by the Idaho National Engineering and Environmental Laboratory (INEEL) for the U.S. Department of Energy's FreedomCAR & Vehicle Technologies Program. Eight four-cycle diesel-engine buses used to transport INEEL employees on various routes have been equipped with oil bypass filter systems from the puraDYN Corporation. The bypass filters are reported to have engine oil filtering capability of <1 micron and a built-in additive package to facilitate extended oil-drain intervals. This quarter, the heavy-duty buses traveled 88,747 miles, and as of the end of March 2004, the eight buses have accumulated 412,838 total test miles without requiring an oil change. This represents an avoidance of 34 oil changes, which equates to 1,199 quarts (300 gallons) of new oil not consumed and, furthermore, 1,199 quarts of waste oil not generated.

  8. Analysis of nuclear proliferation resistance reprocessing and recycling technologies

    SciTech Connect (OSTI)

    Patricia Paviet-Hartmann; Gary Cerefice; Marcela Stacey; Steven Bakhtiar

    2011-05-01

    The PUREX process has been progressively and continuously improved during the past three decades, and these improvements account for successful commercialization of reprocessing in a few countries. The renewed interest in nuclear energy and the international growth of nuclear electricity generation do not equate and should not be equated -with increasing proliferation risks. Indeed, the nuclear renaissance presents a unique opportunity to enhance the culture of non-proliferation. With the recent revival of interest in nuclear technology, technical methods for prevention of nuclear proliferation are being revisited. Robust strategies to develop new advanced separation technologies are emerging worldwide for sustainability and advancement of nuclear energy with enhanced proliferation resistance. On the other hand, at this moment, there are no proliferation resistance advanced technologies. . Until now proliferation resistance as it applies to reprocessing has been focused on not separating a pure stream of weapons-usable plutonium. France, as an example, has proposed a variant of the PUREX process, the COEX TM process, which does not result on a pure plutonium product stream. A further step is to implement a process based on group extraction of actinides and fission products associated with a homogeneous recycling strategy (UNEX process in the US, GANEX process in France). Such scheme will most likely not be deployable on an industrial scale before 2030 or so because it requires intensive R&D and robust flowsheets. Finally, future generation recycling schemes will handle the used nuclear fuel in fast neutron reactors. This means that the plutonium throughput of the recycling process may increase. The need is obvious for advanced aqueous recycling technologies that are intrinsically more proliferation resistant than the commercial PUREX process. In this paper, we review the actual PUREX process along with the advanced recycling technologies that will enhance technical barriers, making plutonium diversion more difficult by not isolating plutonium or/and coexistence of fission products with plutonium.

  9. Most Viewed Documents for Fission And Nuclear Technologies: September 2014

    Office of Scientific and Technical Information (OSTI)

    | OSTI, US Dept of Energy, Office of Scientific and Technical Information for Fission And Nuclear Technologies: September 2014 Estimation of gas leak rates through very small orifices and channels. [From sealed PuO/sub 2/ containers under accident conditions] Bomelburg, H.J. (1977) 71 Behavior of spent nuclear fuel in water pool storage Johnson, A.B. Jr. (1977) 68 Stress analysis and evaluation of a rectangular pressure vessel. [For equipment for sampling Hanford tank radwaste] Rezvani,

  10. Most Viewed Documents for Fission and Nuclear Technologies: December 2014 |

    Office of Scientific and Technical Information (OSTI)

    OSTI, US Dept of Energy, Office of Scientific and Technical Information Most Viewed Documents for Fission and Nuclear Technologies: December 2014 Stress analysis and evaluation of a rectangular pressure vessel. [For equipment for sampling Hanford tank radwaste] Rezvani, M.A.; Ziada, H.H. (Westinghouse Hanford Co., Richland, WA (United States)); Shurrab, M.S. (Westinghouse Savannah River Co., Aiken, SC (United States)) (1992) 67 Behavior of spent nuclear fuel in water pool storage Johnson,

  11. Nuclear Symbiosis - A Means to Achieve Sustainable Nuclear Growth while Limiting the Spread of Sensititive Nuclear Technology

    SciTech Connect (OSTI)

    David Shropshire

    2009-09-01

    Global growth of nuclear energy in the 21st century is creating new challenges to limit the spread of nuclear technology without hindering adoption in countries now considering nuclear power. Independent nuclear states desire autonomy over energy choices and seek energy independence. However, this independence comes with high costs for development of new indigenous fuel cycle capabilities. Nuclear supplier states and expert groups have proposed fuel supply assurance mechanisms such as fuel take-back services, international enrichment services and fuel banks in exchange for recipient state concessions on the development of sensitive technologies. Nuclear states are slow to accept any concessions to their rights under the Non-Proliferation Treaty. To date, decisions not to develop indigenous fuel cycle capabilities have been driven primarily by economics. However, additional incentives may be required to offset a nuclear states perceived loss of energy independence. This paper proposes alternative economic development incentives that could help countries decide to forgo development of sensitive nuclear technologies. The incentives are created through a nuclear-centered industrial complex with symbiotic links to indigenous economic opportunities. This paper also describes a practical tool called the Nuclear Materials Exchange for identifying these opportunities.

  12. March 2014 Most Viewed Documents for Fission And Nuclear Technologies |

    Office of Scientific and Technical Information (OSTI)

    OSTI, US Dept of Energy, Office of Scientific and Technical Information 4 Most Viewed Documents for Fission And Nuclear Technologies Science Subject Feed Behavior of spent nuclear fuel in water pool storage Johnson, A.B. Jr. (1977) 72 /> Peer-review study of the draft handbook for human-reliability analysis with emphasis on nuclear-power-plant applications, NUREG/CR-1278 Brune, R.L.; Weinstein, M.; Fitzwater, M.E. (1983) 67 /> Stress analysis and evaluation of a rectangular pressure

  13. Current Status of Helium-3 Alternative Technologies for Nuclear Safeguards

    SciTech Connect (OSTI)

    Henzlova, Daniela; Kouzes, R.; McElroy, R.; Peerani, P.; Aspinall, M.; Baird, K.; Bakel, A.; Borella, M.; Bourne, M.; Bourva, L.; Cave, F.; Chandra, R.; Chernikova, D.; Croft, S.; Dermody, G.; Dougan, A.; Ely, J.; Fanchini, E.; Finocchiaro, P.; Gavron, Victor; Kureta, M.; Ianakiev, Kiril Dimitrov; Ishiyama, K.; Lee, T.; Martin, Ch.; McKinny, K.; Menlove, Howard Olsen; Orton, Ch.; Pappalardo, A.; Pedersen, B.; Peranteau, D.; Plenteda, R.; Pozzi, S.; Schear, M.; Seya, M.; Siciliano, E.; Stave, S.; Sun, L.; Swinhoe, Martyn Thomas; Tagziria, H.; Vaccaro, S.; Takamine, J.; Weber, A. -L.; Yamaguchi, T.; Zhu, H.

    2015-12-01

    International safeguards inspectorates (e.g., International Atomic Energy Agency {IAEA}, or Euratom) rely heavily on neutron assay techniques, and in particular, on coincidence counters for the verification of declared nuclear materials under safeguards and for monitoring purposes. While 3He was readily available, the reliability, safety, ease of use, gamma-ray insensitivity, and high intrinsic thermal neutron detection efficiency of 3He-based detectors obviated the need for alternative detector technologies. However, the recent decline of the 3He gas supply has triggered international efforts to develop and field neutron detectors that make use of alternative materials. In response to this global effort, the U.S. Department of Energy’s (DOE) National Nuclear Security Administration (NNSA) and Euratom launched a joint effort aimed at bringing together international experts, technology users and developers in the field of nuclear safeguards to discuss and evaluate the proposed 3He alternative materials and technologies. The effort involved a series of two workshops focused on detailed overviews and viability assessments of various 3He alternative technologies for use in nuclear safeguards applications. The key objective was to provide a platform for collaborative discussions and technical presentations organized in a compact, workshop-like format to stimulate interactions among the participants. The meetings culminated in a benchmark exercise providing a unique opportunity for the first inter-comparison of several available alternative technologies. This report provides an overview of the alternative technology efforts presented during the two workshops along with a summary of the benchmarking activities and results. The workshop recommendations and key consensus observations are discussed in the report, and used to outline a proposed path forward and future needs foreseeable in the area of 3He-alternative technologies.

  14. Current Development of Nuclear Thermal Propulsion technologies at the Center for Space Nuclear Research

    SciTech Connect (OSTI)

    Robert C. O'Brien; Steven K. Cook; Nathan D. Jerred; Steven D. Howe; Ronald Samborsky; Daniel Brasuell

    2012-09-01

    Nuclear power and propulsion has been considered for space applications since the 1950s. Between 1955 and 1972 the US built and tested over twenty nuclear reactors / rocket engines in the Rover/NERVA programs1. The Aerojet Corporation was the prime contractor for the NERVA program. Modern changes in environmental laws present challenges for the redevelopment of the nuclear rocket. Recent advances in fuel fabrication and testing options indicate that a nuclear rocket with a fuel composition that is significantly different from those of the NERVA project can be engineered; this may be needed to ensure public support and compliance with safety requirements. The Center for Space Nuclear Research (CSNR) is pursuing a number of technologies, modeling and testing processes to further the development of safe, practical and affordable nuclear thermal propulsion systems.

  15. Nuclear technology programs; Semiannual progress report, October 1989--March 1990

    SciTech Connect (OSTI)

    Harmon, J.E.

    1992-01-01

    This document reports on the work done by the Nuclear Technology Programs of the Chemical Technology Division, Argonne National Laboratory, in the period October 1989--March 1990. These programs involve R&D in three areas: applied physical chemistry, separation science and technology, and nuclear waste management. The work in applied physical chemistry includes investigations into the processes that control the release and transport of fission products under accident-like conditions, the thermophysical properties of metal fuel and blanket materials of the Integral Fast Reactor, and the properties of selected materials in environments simulating those of fusion energy systems. In the area of separation science and technology, the bulk of the effort is concerned with developing and implementing processes for the removal and concentration of actinides from waste streams contaminated by transuranic elements. Another effort is concerned water waste stream generated in production of 2,4,6-trinitrotoluene. In the area of waste management, investigations are underway on the performance of materials in projected nuclear repository conditions to provide input to the licensing of the nation`s high-level waste repositories.

  16. Nuclear Technology Programs semiannual progress report, October 1988--March 1989

    SciTech Connect (OSTI)

    Harmon, J.E.

    1990-12-01

    This document reports on the work done by the Nuclear Technology Programs of the Chemical Technology Division, Argonne National Laboratory, in the period October 1988--March 1989. These programs involve R&D in three areas: applied physical chemistry, separation science and technology, and nuclear waste management. The work in applied physical chemistry includes investigations into the processes that control the release and transport of fission products under accident-like conditions, the thermophysical properties of metal fuel and blanket materials of the Integral Fast Reactor, and the properties of selected materials in environments simulating those of fusion energy systems. In the area of separation science and technology, the bulk of the effort is concerned with developing and implementing processes for the removal and concentration of actinides from waste streams contaminated by transuranic elements. Another effort is concerned with examining the feasibility of substituting low-enriched for high-enriched uranium in the production of fission product {sup 99}Mo. In the area of waste management, investigations are underway on the performance of materials in projected nuclear repository conditions to provide input to the licensing of the nation`s high-level waste repositories. 127 refs., 76 figs., 103 tabs.

  17. Nuclear Technology Programs semiannual progress report, October 1990--March 1991

    SciTech Connect (OSTI)

    1992-12-01

    This document reports on the work done by the Nuclear Technology Programs of the Chemical Technology Division, Argonne National Laboratory, in the period October 1990--March 1991. These programs involve R&D in three areas: applied physical chemistry, separation science and technology, and nuclear waste management. The work in applied physical chemistry includes investigations into the processes that control the release and transpose of fission products under accident-like conditions in a light water reactor, the thermophysical properties of the metal fuel in the Integral Fast Reactor, and the properties of selected materials in environments simulating those of fusion energy systems. In the area of separation science and technology, the bulk of the effort is concerned with developing and implementing processes for the removal and concentration of actinides from waste streams contaminated by transuranic elements. In the area of waste management, investigations are underway on the performance of materials in projected nuclear repository conditions to provide input to the licensing of the nation`s high-level waste repositories.

  18. Nuclear Technology Programs semiannual progress report, April-- September 1990

    SciTech Connect (OSTI)

    Harmon, J.E.

    1992-06-01

    This document reports on the work done by the Nuclear Technology Programs of the Chemical Technology Division, Argonne National Laboratory, in the period April--September 1990. These programs involve R&D in three areas: applied physical chemistry, separation science and technology, and nuclear waste management. The work in applied physical chemistry includes investigations into the processes that control the release and transport of fission products under accident-like conditions in a light water reactor, the thermophysical properties of the metal fuel in the Integral Fast Reactor, and the properties of selected materials in environments simulating those of fusion energy systems. In the area of separation science and technology, the bulk of the effort is concerned with developing and implementing processes for the removal and concentration of actinides from waste streams contaminated by transuranic elements. In the area of waste management, investigations are underway on the performance of materials in projected nuclear repository conditions to provide input to the licensing of the nation`s high-level waste repositories.

  19. Nuclear Technology Programs semiannual progress report, April-- September 1990

    SciTech Connect (OSTI)

    Harmon, J.E.

    1992-06-01

    This document reports on the work done by the Nuclear Technology Programs of the Chemical Technology Division, Argonne National Laboratory, in the period April--September 1990. These programs involve R D in three areas: applied physical chemistry, separation science and technology, and nuclear waste management. The work in applied physical chemistry includes investigations into the processes that control the release and transport of fission products under accident-like conditions in a light water reactor, the thermophysical properties of the metal fuel in the Integral Fast Reactor, and the properties of selected materials in environments simulating those of fusion energy systems. In the area of separation science and technology, the bulk of the effort is concerned with developing and implementing processes for the removal and concentration of actinides from waste streams contaminated by transuranic elements. In the area of waste management, investigations are underway on the performance of materials in projected nuclear repository conditions to provide input to the licensing of the nation's high-level waste repositories.

  20. Nuclear technology programs. Semiannual progress report, April--September 1991

    SciTech Connect (OSTI)

    Not Available

    1993-07-01

    This document reports on the work done by the Nuclear Technology Programs of the Chemical Technology Division, Argonne National Laboratory, in the period April through September 1991. These programs involve R & D in three areas: applied physical chemistry, separation science and technology, and nuclear waste management. The work in applied physical chemistry includes investigations into the processes that control the release and transport of fission products under accident-like conditions in a light water reactor, the thermophysical properties of the metal fuel in the Integral Fast Reactor, and the properties of selected materials in environments simulating those of fusion energy systems. In the area of separation science and technology, the bulk of the effort is concerned with developing and implementing processes for the removal and concentration of actinides from waste streams contaminated by transuranic elements. In the area of waste management, investigations are underway on the performance of materials in projected nuclear repository conditions to provide input to the licensing of the nation`s high-level waste repositories.

  1. April 2013 Most Viewed Documents for Fission And Nuclear Technologies |

    Office of Scientific and Technical Information (OSTI)

    OSTI, US Dept of Energy, Office of Scientific and Technical Information April 2013 Most Viewed Documents for Fission And Nuclear Technologies Science Subject Feed Behavior of spent nuclear fuel in water pool storage Johnson, A.B. Jr. (null) 298 /> Estimation of gas leak rates through very small orifices and channels. [From sealed PuO/sub 2/ containers under accident conditions] Bomelburg, H.J. (null) 292 /> Graphite design handbook Ho, F.H. (1988) 216 /> System Definition and

  2. July 2013 Most Viewed Documents for Fission And Nuclear Technologies |

    Office of Scientific and Technical Information (OSTI)

    OSTI, US Dept of Energy, Office of Scientific and Technical Information July 2013 Most Viewed Documents for Fission And Nuclear Technologies Science Subject Feed Estimation of gas leak rates through very small orifices and channels. [From sealed PuO/sub 2/ containers under accident conditions] Bomelburg, H.J. (1977) 286 /> Graphite design handbook Ho, F.H. (1988) 136 /> Behavior of spent nuclear fuel in water pool storage Johnson, A.B. Jr. (1977) 123 /> Stress analysis and

  3. June 2014 Most Viewed Documents for Fission And Nuclear Technologies |

    Office of Scientific and Technical Information (OSTI)

    OSTI, US Dept of Energy, Office of Scientific and Technical Information June 2014 Most Viewed Documents for Fission And Nuclear Technologies Behavior of spent nuclear fuel in water pool storage Johnson, A.B. Jr. (1977) 78 Estimation of gas leak rates through very small orifices and channels. [From sealed PuO/sub 2/ containers under accident conditions] Bomelburg, H.J. (1977) 71 Review of thorium fuel reprocessing experience Brooksbank, R.E.; McDuffee, W.T.; Rainey, R.H. (1978) 70 Stress

  4. {alpha}-particle optical potentials for nuclear astrophysics (NA) and nuclear technology (NT)

    SciTech Connect (OSTI)

    Avrigeanu, V.; Avrigeanu, M.

    2012-11-20

    The high precision of recent measurements for low-energy {alpha}-particle elastic-scattering as well as induced-reaction data makes possible the understanding of actual limits and possible improvement of the global optical model potentials parameters. Involvement of recent optical potentials for reliable description of both the elastic scattering and emission of {alpha}-particles, of equal interest for nuclear astrophysics (NA) and nuclear technology (NT) for fusion devices, is discussed in the present work.

  5. Refractory alloy technology for space nuclear power applications

    SciTech Connect (OSTI)

    Cooper, R.H. Jr.; Hoffman, E.E.

    1984-01-01

    Purpose of this symposium is twofold: (1) to review and document the status of refractory alloy technology for structural and fuel-cladding applications in space nuclear power systems, and (2) to identify and document the refractory alloy research and development needs for the SP-100 Program in both the short and the long term. In this symposium, an effort was made to recapture the space reactor refractory alloy technology that was cut off in midstream around 1973 when the national space nuclear reactor program began in the early 1960s, was terminated. The six technical areas covered in the program are compatibility, processing and production, welding and component fabrication, mechanical and physical properties, effects of irradiation, and machinability. The refractory alloys considered are niobium, molybdenum, tantalum, and tungsten. Thirteen of the 14 pages have been abstracted separately. The remaining paper summarizes key needs for further R and D on refractory alloys. (DLC)

  6. Ceramic HEPA Filter Program

    SciTech Connect (OSTI)

    Mitchell, M A; Bergman, W; Haslam, J; Brown, E P; Sawyer, S; Beaulieu, R; Althouse, P; Meike, A

    2012-04-30

    Potential benefits of ceramic filters in nuclear facilities: (1) Short term benefit for DOE, NRC, and industry - (a) CalPoly HTTU provides unique testing capability to answer questions for DOE - High temperature testing of materials, components, filter, (b) Several DNFSB correspondences and presentations by DNFSB members have highlighted the need for HEPA filter R and D - DNFSB Recommendation 2009-2 highlighted a nuclear facility response to an evaluation basis earthquake followed by a fire (aka shake-n-bake) and CalPoly has capability for a shake-n-bake test; (2) Intermediate term benefit for DOE and industry - (a) Filtration for specialty applications, e.g., explosive applications at Nevada, (b) Spin-off technologies applicable to other commercial industries; and (3) Long term benefit for DOE, NRC, and industry - (a) Across industry, strong desire for better performance filter, (b) Engineering solution to safety problem will improve facility safety and decrease dependence on associated support systems, (c) Large potential life-cycle cost savings, and (d) Facilitates development and deployment of LLNL process innovations to allow continuous ventilation system operation during a fire.

  7. March 2016 Most Viewed Documents for Fission And Nuclear Technologies |

    Office of Scientific and Technical Information (OSTI)

    OSTI, US Dept of Energy, Office of Scientific and Technical Information Fission And Nuclear Technologies Estimation of gas leak rates through very small orifices and channels. [From sealed PuO/sub 2/ containers under accident conditions] Bomelburg, H.J. (1977) 648 System Definition and Analysis: Power Plant Design and Layout NONE (1996) 468 Stress analysis and evaluation of a rectangular pressure vessel. [For equipment for sampling Hanford tank radwaste] Rezvani, M.A.; Ziada, H.H.

  8. September 2013 Most Viewed Documents for Fission And Nuclear Technologies |

    Office of Scientific and Technical Information (OSTI)

    OSTI, US Dept of Energy, Office of Scientific and Technical Information September 2013 Most Viewed Documents for Fission And Nuclear Technologies Science Subject Feed Estimation of gas leak rates through very small orifices and channels. [From sealed PuO/sub 2/ containers under accident conditions] Bomelburg, H.J. (1977) 133 /> Stress analysis and evaluation of a rectangular pressure vessel. [For equipment for sampling Hanford tank radwaste] Rezvani, M.A.; Ziada, H.H. (Westinghouse

  9. September 2015 Most Viewed Documents for Fission And Nuclear Technologies |

    Office of Scientific and Technical Information (OSTI)

    OSTI, US Dept of Energy, Office of Scientific and Technical Information September 2015 Most Viewed Documents for Fission And Nuclear Technologies Estimation of gas leak rates through very small orifices and channels. [From sealed PuO/sub 2/ containers under accident conditions] Bomelburg, H.J. (1977) 444 System Definition and Analysis: Power Plant Design and Layout NONE (1996) 273 Stress analysis and evaluation of a rectangular pressure vessel. [For equipment for sampling Hanford tank

  10. June 2015 Most Viewed Documents for Fission And Nuclear Technologies |

    Office of Scientific and Technical Information (OSTI)

    OSTI, US Dept of Energy, Office of Scientific and Technical Information June 2015 Most Viewed Documents for Fission And Nuclear Technologies Estimation of gas leak rates through very small orifices and channels. [From sealed PuO/sub 2/ containers under accident conditions] Bomelburg, H.J. (1977) 305 System Definition and Analysis: Power Plant Design and Layout NONE (1996) 296 Stress analysis and evaluation of a rectangular pressure vessel. [For equipment for sampling Hanford tank radwaste]

  11. March 2015 Most Viewed Documents for Fission And Nuclear Technologies |

    Office of Scientific and Technical Information (OSTI)

    OSTI, US Dept of Energy, Office of Scientific and Technical Information 5 Most Viewed Documents for Fission And Nuclear Technologies Stress analysis and evaluation of a rectangular pressure vessel. [For equipment for sampling Hanford tank radwaste] Rezvani, M.A.; Ziada, H.H. (Westinghouse Hanford Co., Richland, WA (United States)); Shurrab, M.S. (Westinghouse Savannah River Co., Aiken, SC (United States)) (1992) 223 Estimation of gas leak rates through very small orifices and channels. [From

  12. December 2015 Most Viewed Documents for Fission And Nuclear Technologies |

    Office of Scientific and Technical Information (OSTI)

    OSTI, US Dept of Energy, Office of Scientific and Technical Information December 2015 Most Viewed Documents for Fission And Nuclear Technologies Estimation of gas leak rates through very small orifices and channels. [From sealed PuO/sub 2/ containers under accident conditions] Bomelburg, H.J. (1977) 432 System Definition and Analysis: Power Plant Design and Layout NONE (1996) 323 Stress analysis and evaluation of a rectangular pressure vessel. [For equipment for sampling Hanford tank

  13. Future Science & Technology Programs | National Nuclear Security

    National Nuclear Security Administration (NNSA)

    Administration Programs Future Science & Technology Programs NNSA has several major projects which are designed with future stockpile needs in mind. They are focused on the research and development efforts and the long-term vitality of science and engineering at NNSA. NNSA is focused on developing and maintaining the critical scientific and technical capabilities that are needed to maintain the nuclear weapons stockpile for the long term. Doing so is technically challenging, and involve

  14. Innovative applications of technology for nuclear power plant productivity improvements

    SciTech Connect (OSTI)

    Naser, J. A.

    2012-07-01

    The nuclear power industry in several countries is concerned about the ability to maintain high plant performance levels due to aging and obsolescence, knowledge drain, fewer plant staff, and new requirements and commitments. Current plant operations are labor-intensive due to the vast number of operational and support activities required by commonly used technology in most plants. These concerns increase as plants extend their operating life. In addition, there is the goal to further improve performance while reducing human errors and increasingly focus on reducing operations and maintenance costs. New plants are expected to perform more productively than current plants. In order to achieve and increase high productivity, it is necessary to look at innovative applications of modern technologies and new concepts of operation. The Electric Power Research Inst. is exploring and demonstrating modern technologies that enable cost-effectively maintaining current performance levels and shifts to even higher performance levels, as well as provide tools for high performance in new plants. Several modern technologies being explored can provide multiple benefits for a wide range of applications. Examples of these technologies include simulation, visualization, automation, human cognitive engineering, and information and communications technologies. Some applications using modern technologies are described. (authors)

  15. Advanced Nuclear Technology: Advanced Light Water Reactors Utility Requirements Document Small Modular Reactors Inclusion Summary

    Broader source: Energy.gov [DOE]

    Advanced Nuclear Technology: Advanced Light Water Reactors Utility Requirements Document Small Modular Reactors Inclusion Summary November 2014

  16. March 2006, Report of the ADVANCED NUCLEAR TRANSFORMATION TECHNOLOGY SUBCOMMITTEE of the NUCLEAR ENERGY RESEARCH ADVISORY COMMITTEE

    Broader source: Energy.gov [DOE]

    The Global Nuclear Energy Partnership (GNEP) marks a major change in the direction of the DOE’s nuclear energy R&D program. It is a coherent plan to test technologies that promise to markedly...

  17. Proceedings of the Nuclear Criticality Technology Safety Workshop

    SciTech Connect (OSTI)

    Rene G. Sanchez

    1998-04-01

    This document contains summaries of most of the papers presented at the 1995 Nuclear Criticality Technology Safety Project (NCTSP) meeting, which was held May 16 and 17 at San Diego, Ca. The meeting was broken up into seven sessions, which covered the following topics: (1) Criticality Safety of Project Sapphire; (2) Relevant Experiments For Criticality Safety; (3) Interactions with the Former Soviet Union; (4) Misapplications and Limitations of Monte Carlo Methods Directed Toward Criticality Safety Analyses; (5) Monte Carlo Vulnerabilities of Execution and Interpretation; (6) Monte Carlo Vulnerabilities of Representation; and (7) Benchmark Comparisons.

  18. January 2013 Most Viewed Documents for Fission And Nuclear Technologies |

    Office of Scientific and Technical Information (OSTI)

    OSTI, US Dept of Energy, Office of Scientific and Technical Information January 2013 Most Viewed Documents for Fission And Nuclear Technologies Laboratory studies of shear/leach processing of zircaloy clad metallic uranium reactor fuel Swanson, J.L.; Bray, L.A.; Kjarmo, H.E.; Ryan, J.L.; Matsuzaki, C.L.; Pitman, S.G.; Haberman, J.H. Working session 3: Tubing integrity Cueto-Felgueroso, C. [Tecnatom, S.A., San Sebastian de los Reyes, Madrid (Spain)]; Strosnider, J. [NRC, Washington, DC

  19. Secondary Waste Considerations for Vitrification of Sodium-Bearing Waste at the Idaho Nuclear Technology and Engineering Center FY-2001 Status Report

    SciTech Connect (OSTI)

    Herbst, A.K.; Kirkham, R.J.; Losinski, S.J.

    2002-09-26

    The Idaho Nuclear Technology and Engineering Center (INTEC) is considering vitrification to process liquid sodium-bearing waste. Preliminary studies were completed to evaluate the potential secondary wastes from the melter off-gas clean up systems. Projected secondary wastes comprise acidic and caustic scrubber solutions, HEPA filters, activated carbon, and ion exchange media. Possible treatment methods, waste forms, and disposal sites are evaluated from radiological and mercury contamination estimates.

  20. Technology Insights and Perspectives for Nuclear Fuel Cycle Concepts

    SciTech Connect (OSTI)

    S. Bays; S. Piet; N. Soelberg; M. Lineberry; B. Dixon

    2010-09-01

    The following report provides a rich resource of information for exploring fuel cycle characteristics. The most noteworthy trends can be traced back to the utilization efficiency of natural uranium resources. By definition, complete uranium utilization occurs only when all of the natural uranium resource can be introduced into the nuclear reactor long enough for all of it to undergo fission. Achieving near complete uranium utilization requires technologies that can achieve full recycle or at least nearly full recycle of the initial natural uranium consumed from the Earth. Greater than 99% of all natural uranium is fertile, and thus is not conducive to fission. This fact requires the fuel cycle to convert large quantities of non-fissile material into fissile transuranics. Step increases in waste benefits are closely related to the step increase in uranium utilization going from non-breeding fuel cycles to breeding fuel cycles. The amount of mass requiring a disposal path is tightly coupled to the quantity of actinides in the waste stream. Complete uranium utilization by definition means that zero (practically, near zero) actinide mass is present in the waste stream. Therefore, fuel cycles with complete (uranium and transuranic) recycle discharge predominately fission products with some actinide process losses. Fuel cycles without complete recycle discharge a much more massive waste stream because only a fraction of the initial actinide mass is burned prior to disposal. In a nuclear growth scenario, the relevant acceptable frequency for core damage events in nuclear reactors is inversely proportional to the number of reactors deployed in a fuel cycle. For ten times the reactors in a fleet, it should be expected that the fleet-average core damage frequency be decreased by a factor of ten. The relevant proliferation resistance of a fuel cycle system is enhanced with: decreasing reliance on domestic fuel cycle services, decreasing adaptability for technology misuse, enablement of material accountability, and decreasing material attractiveness.

  1. Moving granular-bed filter development program, Option III: Development of moving granular-bed filter technology for multi-contaminant control. Task 14: Test plan; Topical report

    SciTech Connect (OSTI)

    Haas, J.C.; Olivo, C.A.; Wilson, K.B.

    1994-04-01

    An experimental test plan has been prepared for DOE/METC review and approval to develop a filter media suitable for multi-contaminant control in granular-bed filter (GBF) applications. The plan includes identification, development, and demonstration of methods for enhanced media morphology, chemical reactivity, and mechanical strength. The test plan includes media preparation methods, physical and chemical characterization methods for fresh and reacted media, media evaluation criteria, details of test and analytical equipment, and test matrix of the proposed media testing. A filter media composed of agglomerated limestone and clay was determined to be the best candidate for multi-contaminate control in GBF operation. The combined limestone/clay agglomerate has the potential to remove sulfur and alkali species, in addition to particulate, and possibly halogens and trace heavy metals from coal process streams.

  2. Nuclear physics detector technology applied to plant biology research

    SciTech Connect (OSTI)

    Weisenberger, Andrew G.; Kross, Brian J.; Lee, Seung Joo; McKisson, John E.; Xi, Wenze; Zorn, Carl J.; Howell, Calvin; Crowell, A.S.; Reid, C.D.; Smith, Mark

    2013-08-01

    The ability to detect the emissions of radioactive isotopes through radioactive decay (e.g. beta particles, x-rays and gamma-rays) has been used for over 80 years as a tracer method for studying natural phenomena. More recently a positron emitting radioisotope of carbon: {sup 11}C has been utilized as a {sup 11}CO{sub 2} tracer for plant ecophysiology research. Because of its ease of incorporation into the plant via photosynthesis, the {sup 11}CO{sub 2} radiotracer is a powerful tool for use in plant biology research. Positron emission tomography (PET) imaging has been used to study carbon transport in live plants using {sup 11}CO{sub 2}. Presently there are several groups developing and using new PET instrumentation for plant based studies. Thomas Jefferson National Accelerator Facility (Jefferson Lab) in collaboration with the Duke University Phytotron and the Triangle Universities Nuclear Laboratory (TUNL) is involved in PET detector development for plant imaging utilizing technologies developed for nuclear physics research. The latest developments of the use of a LYSO scintillator based PET detector system for {sup 11}CO{sub 2} tracer studies in plants will be briefly outlined.

  3. Application of Telepresence Technologies to Nuclear Material Safeguards

    SciTech Connect (OSTI)

    Wright, M.C.; Rome, J.A.

    1999-09-20

    Implementation of remote monitoring systems has become a priority area for the International Atomic Energy Agency and other international inspection regimes. For the past three years, DOE2000 has been the US Department of Energy's (DOE's) initiative to develop innovative applications to exploit the capabilities of broadband networks and media integration. The aim is to enhance scientific collaboration by merging computing and communications technologies. These Internet-based telepresence technologies could be easily extended to provide remote monitoring and control for confidence building and transparency systems at nuclear facilities around the world. One of the original DOE2000 projects, the Materials Microcharacterization Collaboratory is an interactive virtual laboratory, linking seven DOE user facilities located across the US. At these facilities, external collaborators have access to scientists, data, and instrumentation, all of which are available to varying degrees using the Internet. Remote operation of the instruments varies between passive (observational) to active (direct control), in many cases requiring no software at the remote site beyond a Web browser. Live video streams are continuously available on the Web so that participants can see what is happening at a particular location. An X.509 certificate system provides strong authentication, The hardware and software are commercially available and are easily adaptable to safeguards applications.

  4. Design Features and Technology Uncertainties for the Next Generation Nuclear Plant

    SciTech Connect (OSTI)

    John M. Ryskamp; Phil Hildebrandt; Osamu Baba; Ron Ballinger; Robert Brodsky; Hans-Wolfgang Chi; Dennis Crutchfield; Herb Estrada; Jeane-Claude Garnier; Gerald Gordon; Richard Hobbins; Dan Keuter; Marilyn Kray; Philippe Martin; Steve Melancon; Christian Simon; Henry Stone; Robert Varrin; Werner von Lensa

    2004-06-01

    This report presents the conclusions, observations, and recommendations of the Independent Technology Review Group (ITRG) regarding design features and important technology uncertainties associated with very-high-temperature nuclear system concepts for the Next Generation Nuclear Plant (NGNP). The ITRG performed its reviews during the period November 2003 through April 2004.

  5. U.S. Department of Energy Office of Nuclear Energy, Science and Technology

    Energy Savers [EERE]

    One the cover: Albert Einstein (1879-1955) U.S. Department of Energy Office of Nuclear Energy, Science and Technology Washington, D.C. 20585 The History of Nuclear Energy Table of Contents Preface ................................................................... 1 Introduction .......................................................... 3 The Discovery of Fission ...................................... 4 The First Self-Sustaining Chain Reaction ............ 5 The Development of Nuclear Energy for

  6. Filtering reprecipitated slurry

    SciTech Connect (OSTI)

    Morrissey, M.F.

    1992-12-31

    As part of the Late Washing Demonstration at Savannah River Technology Center, Interim Waste Technology has filtered reprecipitated and non reprecipitated slurry with the Experimental Laboratory Filter (ELF) at TNX. Reprecipitated slurry generates higher permeate fluxes than non reprecipitated slurry. Washing reprecipitated slurry may require a defoamer because reprecipitation encourages foaming.

  7. Filtering reprecipitated slurry

    SciTech Connect (OSTI)

    Morrissey, M.F.

    1992-01-01

    As part of the Late Washing Demonstration at Savannah River Technology Center, Interim Waste Technology has filtered reprecipitated and non reprecipitated slurry with the Experimental Laboratory Filter (ELF) at TNX. Reprecipitated slurry generates higher permeate fluxes than non reprecipitated slurry. Washing reprecipitated slurry may require a defoamer because reprecipitation encourages foaming.

  8. Cordierite silicon nitride filters

    SciTech Connect (OSTI)

    Sawyer, J.; Buchan, B. ); Duiven, R.; Berger, M. ); Cleveland, J.; Ferri, J. )

    1992-02-01

    The objective of this project was to develop a silicon nitride based crossflow filter. This report summarizes the findings and results of the project. The project was phased with Phase I consisting of filter material development and crossflow filter design. Phase II involved filter manufacturing, filter testing under simulated conditions and reporting the results. In Phase I, Cordierite Silicon Nitride (CSN) was developed and tested for permeability and strength. Target values for each of these parameters were established early in the program. The values were met by the material development effort in Phase I. The crossflow filter design effort proceeded by developing a macroscopic design based on required surface area and estimated stresses. Then the thermal and pressure stresses were estimated using finite element analysis. In Phase II of this program, the filter manufacturing technique was developed, and the manufactured filters were tested. The technique developed involved press-bonding extruded tiles to form a filter, producing a monolithic filter after sintering. Filters manufactured using this technique were tested at Acurex and at the Westinghouse Science and Technology Center. The filters did not delaminate during testing and operated and high collection efficiency and good cleanability. Further development in areas of sintering and filter design is recommended.

  9. Technology Roadmap Instrumentation, Control, and Human-Machine Interface to Support DOE Advanced Nuclear Energy Programs

    SciTech Connect (OSTI)

    Donald D Dudenhoeffer; Burce P Hallbert

    2007-03-01

    Instrumentation, Controls, and Human-Machine Interface (ICHMI) technologies are essential to ensuring delivery and effective operation of optimized advanced Generation IV (Gen IV) nuclear energy systems. In 1996, the Watts Bar I nuclear power plant in Tennessee was the last U.S. nuclear power plant to go on line. It was, in fact, built based on pre-1990 technology. Since this last U.S. nuclear power plant was designed, there have been major advances in the field of ICHMI systems. Computer technology employed in other industries has advanced dramatically, and computing systems are now replaced every few years as they become functionally obsolete. Functional obsolescence occurs when newer, more functional technology replaces or supersedes an existing technology, even though an existing technology may well be in working order.Although ICHMI architectures are comprised of much of the same technology, they have not been updated nearly as often in the nuclear power industry. For example, some newer Personal Digital Assistants (PDAs) or handheld computers may, in fact, have more functionality than the 1996 computer control system at the Watts Bar I plant. This illustrates the need to transition and upgrade current nuclear power plant ICHMI technologies.

  10. Nuclear Materials Research and Technology/Los Alamos National Laboratory

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

    Energy Nuclear Fuels Storage & Transportation Planning Project Nuclear Fuels Storage & Transportation Planning Project Independent Spent Fuel Storage Installation (ISFSI) at the shutdown Connecticut Yankee site. The ISFSI includes 40 multi-purpose canisters, within vertical concrete storage casks, containing 1019 used nuclear fuel assemblies [412.3 metric ton heavy metal (MTHM)] and 3 canisters of greater-than-class-C (GTCC) low-level radioactive waste. Photo courtesy of Connecticut

  11. Development and Analysis of Advanced High-Temperature Technology for Nuclear Heat Transport and Power Conversion

    SciTech Connect (OSTI)

    Per F. Peterson

    2010-03-01

    This project by the Thermal Hydraulics Research Laboratory at U.C. Berkeley Studied advanced high-temperature heat transport and power conversion technology, in support of the Nuclear Hydrogen Initiative and Generation IV.

  12. DOE Initiates Environmental Impact Statement for Global Nuclear Energy Partnership Technology Demonstrations

    Broader source: Energy.gov [DOE]

    WASHINGTON , DC - The U.S. Department of Energy (DOE) today announced plans to prepare an environmental impact statement (EIS) for the technology demonstration program of the Global Nuclear Energy...

  13. Laboratory Licenses Hydrogen Sensor Technology - News Releases | NREL

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

    Laboratory Licenses Hydrogen Sensor Technology Nuclear Filter Technology Awarded Licenses for Fiber Optic Hydrogen Sensor February 23, 2006 Golden, Colo. - The U.S. Department of Energy's National Renewable Energy Laboratory (NREL) today announced that Nuclear Filter Technology (NucFil) has been awarded licenses to manufacture Fiber Optic Hydrogen Sensors. The licenses, together with a Cooperative Research and Development Agreement (CRADA), allow NucFil to work with scientists and engineers at

  14. Nuclear Energy: Policies and Technology for the 21st Century

    Broader source: Energy.gov [DOE]

    The Department of Energy (DOE) Nuclear Energy Advisory Committee (NEAC) formed two subcommittees to develop a report for the new Administration: a Policy Subcommittee chartered to evaluate U.S....

  15. NEAC Nuclear Reactor Technology (NRT) Subcommittee On the Planning Study of Future Test/Demonstration Reactors

    Energy Savers [EERE]

    Report and Recommendations of NEAC Nuclear Reactor Technology (NRT) Subcommittee On the Planning Study of Future Test/Demonstration Reactors March 2, 2015 Final Given direction from Congress and interest of several stakeholders, the Department of Energy's Office of Nuclear Energy (DOE-NE) requested that Nuclear Energy Advisory Committee (NEAC)-NRT Subcommittee help define the scope and process for conducting a planning study for an advanced test/demonstration reactor in the United States. The

  16. Calcined Waste Storage at the Idaho Nuclear Technology and Engineering Center

    SciTech Connect (OSTI)

    M. D. Staiger M. C. Swenson

    2007-06-01

    This report provides a quantitative inventory and composition (chemical and radioactivity) of calcined waste stored at the Idaho Nuclear Technology and Engineering Center. From December 1963 through May 2000, liquid radioactive wastes generated by spent nuclear fuel reprocessing were converted into a solid, granular form called calcine. This report also contains a description of the calcine storage bins.

  17. FY 2012 National Security Technologies, LLC, PER Summary | National Nuclear

    National Nuclear Security Administration (NNSA)

    Security Administration FY 2012 National Security Technologies, LLC, PER Summary SUMMARY OF FY 2012 NATIONAL SECURITY TECHNOLOGIES, LLC, AWARD FEE DETERMINATION Total Available Fee Total Fee Earned % $29,855,764 $28,020,923 93.85% National Security Technologies, LLC, the management and operating contractor for the Nevada National Security Site, earned an "Excellent" rating in Program, a "Very Good" in Operations and Institutional and Business Management, and 93.85 percent

  18. Advanced Technology Development and Mitigation | National Nuclear Security

    National Nuclear Security Administration (NNSA)

    Administration Advanced Technology Development and Mitigation The Advanced Technology Development and Mitigation (ATDM) subprogram includes laboratory code and computer engineering and science projects that pursue long-term simulation and computing goals relevant to the broad national security missions of the NNSA. It addresses the need to adapt current integrated design codes and build new codes that are attuned to emerging computing technologies. Performing this work within the scope of

  19. Nuclear Materials Technology Division/Los Alamos National Laboratory

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

    Los Alamos National Laboratory * A U.S. Department of Energy Laboratory The Actinide Research Fall 1995 Zircon Promises to be A Host Phase for the Immobilization of Excess Weapon Plutonium Quarterly o f t h e N u c l e a r M a t e r i a l s T e c h n o l o g y D i v i s i o n One of the new and daunting challenges in nuclear waste management is the disposition of plutonium recovered from dismantled nuclear weapons. Under the first and second Strategic Arms Reduction Treaties, as well as

  20. Nuclear Materials Technology Division/Los Alamos National Laboratory

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

    Spring 1996 Los Alamos National Laboratory o f t h e N u c l e a r M a t e r i a l s T e c h n o l o g y D i v i s i o n Quarterly In This Issue 1 NMT Studies Fuel Fabrication Methods to Advance Efforts in Plutonium Disposition 4 Neutron Source Recovery Reduces the Nuclear Danger, Responds to National Need 6 Division Director Discusses Plutonium Future 8 NMT Designs and Fabricates Standards for Nuclear Material Assay 10 Advisory Committee Rates NMT as "Outstanding/ Excellent" 11 Recent

  1. Chapter 4: Advancing Clean Electric Power Technologies | Nuclear...

    Energy Savers [EERE]

    ... A number of coolant types have been assessed for Fast Reactors, leading to technologies such as the sodium-cooled fast reactor (SFR), the lead or lead-bismuth cooled fast reactor ...

  2. Disk filter

    DOE Patents [OSTI]

    Bergman, Werner

    1986-01-01

    An electric disk filter provides a high efficiency at high temperature. A hollow outer filter of fibrous stainless steel forms the ground electrode. A refractory filter material is placed between the outer electrode and the inner electrically isolated high voltage electrode. Air flows through the outer filter surfaces through the electrified refractory filter media and between the high voltage electrodes and is removed from a space in the high voltage electrode.

  3. Disk filter

    DOE Patents [OSTI]

    Bergman, W.

    1985-01-09

    An electric disk filter provides a high efficiency at high temperature. A hollow outer filter of fibrous stainless steel forms the ground electrode. A refractory filter material is placed between the outer electrode and the inner electrically isolated high voltage electrode. Air flows through the outer filter surfaces through the electrified refractory filter media and between the high voltage electrodes and is removed from a space in the high voltage electrode.

  4. Proceedings of the 21st DOE/NRC Nuclear Air Cleaning Conference; Sessions 1--8

    SciTech Connect (OSTI)

    First, M.W.

    1991-02-01

    Separate abstracts have been prepared for the papers presented at the meeting on nuclear facility air cleaning technology in the following specific areas of interest: air cleaning technologies for the management and disposal of radioactive wastes; Canadian waste management program; radiological health effects models for nuclear power plant accident consequence analysis; filter testing; US standard codes on nuclear air and gas treatment; European community nuclear codes and standards; chemical processing off-gas cleaning; incineration and vitrification; adsorbents; nuclear codes and standards; mathematical modeling techniques; filter technology; safety; containment system venting; and nuclear air cleaning programs around the world. (MB)

  5. ULTRA-COMPACT ACCELERATOR TECHNOLOGIES FOR APPLICATION IN NUCLEAR TECHNIQUES

    SciTech Connect (OSTI)

    Sampayan, S; Caporaso, G; Chen, Y; Carazo, V; Falabella, S; Guethlein, G; Guse, S; Harris, J R; Hawkins, S; Holmes, C; Krogh, M; Nelson, S; Paul, A C; Pearson, D; Poole, B; Schmidt, R; Sanders, D; Selenes, K; Sitaraman, S; Sullivan, J; Wang, L; Watson, J

    2009-06-11

    We report on compact accelerator technology development for potential use as a pulsed neutron source quantitative post verifier. The technology is derived from our on-going compact accelerator technology development program for radiography under the US Department of Energy and for a clinic sized compact proton therapy systems under an industry sponsored Cooperative Research and Development Agreement. The accelerator technique relies on the synchronous discharge of a prompt pulse generating stacked transmission line structure with the beam transit. The goal of this technology is to achieve {approx}10 MV/m gradients for 10s of nanoseconds pulses and to {approx}100 MV/m gradients for {approx}1 ns systems. As a post verifier for supplementing existing x-ray equipment, this system can remain in a charged, stand-by state with little or no energy consumption. We detail the progress of our overall component development effort with the multilayer dielectric wall insulators (i.e., the accelerator wall), compact power supply technology, kHz repetition-rate surface flashover ion sources, and the prompt pulse generation system consisting of wide-bandgap switches and high performance dielectric materials.

  6. Nuclear Materials Technology Division/Los Alamos National Laboratory

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

    0 Publications Nuclear Fuels Ceramics Materials Charac- terization Synthesis Metallurgy Actinide Chemistry Separation Spectroscopy Thermochemistry Inorganic Chemistry Actinide Disposition Safeguards Review Articles NDA Measurements Calorimetry Chemical Systems Diagnostics Analytical Chemistry 5 10 15 20 25 30 Spring 1995 Los Alamos National Laboratory * A U.S. Department of Energy Laboratory Chief Scientist's Notes: Going Back to the Basics The Actinide Research o f t h e N u c l e a r M a t e r

  7. Fusion Nuclear Science and Technology Program - Status and Plans for

    Office of Environmental Management (EM)

    Fukushima: Looking Back, Looking Ahead Fukushima: Looking Back, Looking Ahead March 11, 2016 - 3:47pm Addthis John Kotek John Kotek Acting Assistant Secretary for the Office of Nuclear Energy On March 11, 2011, a magnitude 9.0 earthquake struck Japan. It was one of the most powerful earthquakes on record, unleashing a tsunami that ravaged 430 miles of coastline, destroying communities, and killing nearly 16,000 people. The combined effects of the earthquake and tsunami overwhelmed on and offsite

  8. Status of Fuel Development and Manufacturing for Space Nuclear Reactors at BWX Technologies

    SciTech Connect (OSTI)

    Carmack, W.J.; Husser, D.L.; Mohr, T.C.; Richardson, W.C.

    2004-02-04

    New advanced nuclear space propulsion systems will soon seek a high temperature, stable fuel form. BWX Technologies Inc (BWXT) has a long history of fuel manufacturing. UO2, UCO, and UCx have been fabricated at BWXT for various US and international programs. Recent efforts at BWXT have focused on establishing the manufacturing techniques and analysis capabilities needed to provide a high quality, high power, compact nuclear reactor for use in space nuclear powered missions. To support the production of a space nuclear reactor, uranium nitride has recently been manufactured by BWXT. In addition, analytical chemistry and analysis techniques have been developed to provide verification and qualification of the uranium nitride production process. The fabrication of a space nuclear reactor will require the ability to place an unclad fuel form into a clad structure for assembly into a reactor core configuration. To this end, BWX Technologies has reestablished its capability for machining, GTA welding, and EB welding of refractory metals. Specifically, BWX Technologies has demonstrated GTA welding of niobium flat plate and EB welding of niobium and Nb-1Zr tubing. In performing these demonstration activities, BWX Technologies has established the necessary infrastructure to manufacture UO2, UCx, or UNx fuel, components, and complete reactor assemblies in support of space nuclear programs.

  9. Fermilab Project X nuclear energy application: Accelerator, spallation target and transmutation technology demonstration

    SciTech Connect (OSTI)

    Gohar, Yousry; Johnson, David; Johnson, Todd; Mishra, Shekhar; /Fermilab

    2011-04-01

    The recent paper 'Accelerator and Target Technology for Accelerator Driven Transmutation and Energy Production' and report 'Accelerators for America's Future' have endorsed the idea that the next generation particle accelerators would enable technological breakthrough needed for nuclear energy applications, including transmutation of waste. In the Fall of 2009 Fermilab sponsored a workshop on Application of High Intensity Proton Accelerators to explore in detail the use of the Superconducting Radio Frequency (SRF) accelerator technology for Nuclear Energy Applications. High intensity Continuous Wave (CW) beam from the Superconducting Radio Frequency (SRF) Linac (Project-X) at beam energy between 1-2 GeV will provide an unprecedented experimental and demonstration facility in the United States for much needed nuclear energy Research and Development. We propose to carry out an experimental program to demonstrate the reliability of the accelerator technology, Lead-Bismuth spallation target technology and a transmutation experiment of spent nuclear fuel. We also suggest that this facility could be used for other Nuclear Energy applications.

  10. Nuclear Materials Research and Technology/Los Alamos National Laboratory

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

    Magnetic Levitation Results in High-Purity Plutonium Metal 4 Researchers Prepare and Characterize First Transuranic Crown Ether Complex 6 "Excess" Nuclear Materials Hold Keys to Medicine, Research, Space Power 8 LANL Develops TRU Waste Mobile Analysis Methods for RCRA-Listed Metals 10 Recent Publications 11 Secretary Richardson Dedicates ARIES 12 NewsMakers 3rd quarter 1998 N u c l e a r M a t e r i a l s R e s e a r c h a n d T e c h n o l o g y Magnetic Levitation Results in

  11. Nuclear Materials Technology/Los Alamos National Laboratory

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

    Los Alamos National Laboratory The Actinide Research In This Issue 4 Pit Manufacturing Project Presents Many Challenges 6 Can Los Alamos Meet Its Future Nuclear Challenges? 9 Detecting and Predicting Plutonium Aging are Crucial to Stockpile Stewardship 12 Pit Disassembly and Conversion Address a 'Clear and Present Danger' 14 Publications and Invited Talks Newsmakers 15 Energy Secretary Spencer Abraham Addresses Employees 1st quarter 2001 N u c l e a r M a t e r i a l s R e s e a r c h a n d T e

  12. Nuclear Materials Technology/Los Alamos National Laboratory

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

    Investigating a Viable Fuel Form for ATW Focus on Students: 6 Students are Vital to the Lab 8 Nuclear Engineer Steven Alferink 10 Social Scientist Andrew Koehler 12 Chemist Susan Oldham 14 Newsmakers a U.S. Department of Energy Laboratory Los Alamos National Laboratory 3rd quarter 2001 N u c l e a r M a t e r i a l s R e s e a r c h a n d T e c h n o l o g y Quarterly continued on page 2 The Actinide Research Researchers are using a technique called power- compensated differential scanning

  13. Idaho Nuclear Technology and Engineering Center Low-Activity Waste Process Technology Program FY-2000 Status Report

    SciTech Connect (OSTI)

    Herbst, Alan Keith; Mc Cray, John Alan; Kirkham, Robert John; Pao, Jenn Hai; Argyle, Mark Don; Lauerhass, Lance; Bendixsen, Carl Lee; Hinckley, Steve Harold

    2000-11-01

    The Low-Activity Waste Process Technology Program anticipated that grouting will be used for disposal of low-level and transuranic wastes generated at the Idaho Nuclear Technology Engineering Center (INTEC). During fiscal year 2000, grout formulations were studied for transuranic waste derived from INTEC liquid sodium-bearing waste and for projected newly generated low-level liquid waste. Additional studies were completed using silica gel and other absorbents to solidify sodium-bearing wastes. A feasibility study and conceptual design were completed for the construction of a grout pilot plant for simulated wastes and demonstration facility for actual wastes.

  14. Idaho Nuclear Technology and Engineering Center Low-Activity Waste Process Technology Program FY-2000 Status Report

    SciTech Connect (OSTI)

    Herbst, A.K.; McCray, J.A.; Kirkham, R.J.; Pao, J.; Argyle, M.D.; Lauerhass, L.; Bendixsen, C.L.; Hinckley, S.H.

    2000-10-31

    The Low-Activity Waste Process Technology Program anticipated that grouting will be used for disposal of low-level and transuranic wastes generated at the Idaho Nuclear Technology Engineering Center (INTEC). During fiscal year 2000, grout formulations were studied for transuranic waste derived from INTEC liquid sodium-bearing waste and for projected newly generated low-level liquid waste. Additional studies were completed using silica gel and other absorbents to solidify sodium-bearing wastes. A feasibility study and conceptual design were completed for the construction of a grout pilot plant for simulated wastes and demonstration facility for actual wastes.

  15. Nuclear Materials Technology Division/Los Alamos National Laboratory

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

    Winter 1994 Los Alamos National Laboratory * A U.S. Department of Energy Laboratory Introducing The Actinide Research Quarterly My first year as Division Director has been a challenging yet rewarding experience. Although the Division has faced many challenges, I am gratified by the "can do" attitude our personnel continually exhibit. The foundation of NMT Division's science and technology excellence is our capabilities of actinide process chemistry, plutonium metallurgy, surface and

  16. Energy Department Invests $60 Million to Train Next Generation Nuclear Energy Leaders, Pioneer Advanced Nuclear Technology

    Broader source: Energy.gov [DOE]

    Building on President Obama’s Climate Action Plan to continue America’s leadership in clean energy innovation, the Energy Department announced more than $60 million in nuclear energy research awards and improvements to university research reactors and infrastructure.

  17. Prognostics and Health Management in Nuclear Power Plants: A Review of Technologies and Applications

    SciTech Connect (OSTI)

    Coble, Jamie B.; Ramuhalli, Pradeep; Bond, Leonard J.; Hines, Wes; Upadhyaya, Belle

    2012-07-17

    This report reviews the current state of the art of prognostics and health management (PHM) for nuclear power systems and related technology currently applied in field or under development in other technological application areas, as well as key research needs and technical gaps for increased use of PHM in nuclear power systems. The historical approach to monitoring and maintenance in nuclear power plants (NPPs), including the Maintenance Rule for active components and Aging Management Plans for passive components, are reviewed. An outline is given for the technical and economic challenges that make PHM attractive for both legacy plants through Light Water Reactor Sustainability (LWRS) and new plant designs. There is a general introduction to PHM systems for monitoring, fault detection and diagnostics, and prognostics in other, non-nuclear fields. The state of the art for health monitoring in nuclear power systems is reviewed. A discussion of related technologies that support the application of PHM systems in NPPs, including digital instrumentation and control systems, wired and wireless sensor technology, and PHM software architectures is provided. Appropriate codes and standards for PHM are discussed, along with a description of the ongoing work in developing additional necessary standards. Finally, an outline of key research needs and opportunities that must be addressed in order to support the application of PHM in legacy and new NPPs is presented.

  18. Guidance for Deployment of Mobile Technologies for Nuclear Power Plant Field Workers

    SciTech Connect (OSTI)

    Heather D. Medema; Ronald K. Farris

    2012-09-01

    This report is a guidance document prepared for the benefit of commercial nuclear power plants (NPPs) supporting organizations and personnel who are considering or undertaking deployment of mobile technology for the purpose of improving human performance and plant status control (PSC) for field workers in an NPP setting. This document especially is directed at NPP business managers, Electric Power Research Institute, Institute of Nuclear Power Operations, and other non-Information Technology personnel. This information is not intended to replace basic project management practices or reiterate these processes, but is to support decision-making, planning, and preparation of a business case.

  19. NNSA issues Preliminary Notice of Violation to National Security Technologies, LLC, for Nuclear Safety Violations, Fact Sheet

    Broader source: Energy.gov [DOE]

    On August 22, 2011, the National Nuclear Security Administration (NNSA) issued a Preliminary Notice of Violation (PNOV) to National Security Technologies, LLC (NSTec) for violations of Department...

  20. FILTER TREATMENT

    DOE Patents [OSTI]

    Sutton, J.B.; Torrey, J.V.P.

    1958-08-26

    A process is described for reconditioning fused alumina filters which have become clogged by the accretion of bismuth phosphate in the filter pores, The method consists in contacting such filters with faming sulfuric acid, and maintaining such contact for a substantial period of time.

  1. NEAC Fuel Cycle Technologies Subcommittee Report Presentation to the Nuclear Energy Advisory Committee

    Energy Savers [EERE]

    NEAC Fuel Cycle Technologies Subcommittee Report Presentation to the Nuclear Energy Advisory Committee Al Sattelberger, Chair (Presented by Joy Rempe) Washington, DC June 26, 2015 Fuel Cycle Technologies Subcommittee Members  Carol J. Burns  Margaret Chu  Raymond Juzaitis  Chris Kouts  Sekazi K. Mtingwa  Ronald P. Omberg  Joy L. Rempe  Dominique Warin  Alfred P. Sattelberger (Chair) 2 FCT Subcommittee April 29 2015 Review Highlights  Separations R&D:

  2. MANAGEMENT OF RESEARCH AND TEST REACTOR ALUMINUM SPENT NUCLEAR FUEL - A TECHNOLOGY ASSESSMENT

    SciTech Connect (OSTI)

    Vinson, D.

    2010-07-11

    The Department of Energy's Environmental Management (DOE-EM) Program is responsible for the receipt and storage of aluminum research reactor spent nuclear fuel or used fuel until ultimate disposition. Aluminum research reactor used fuel is currently being stored or is anticipated to be returned to the U.S. and stored at DOE-EM storage facilities at the Savannah River Site and the Idaho Nuclear Technology and Engineering Center. This paper assesses the technologies and the options for safe transportation/receipt and interim storage of aluminum research reactor spent fuel and reviews the comprehensive strategy for its management. The U.S. Department of Energy uses the Appendix A, Spent Nuclear Fuel Acceptance Criteria, to identify the physical, chemical, and isotopic characteristics of spent nuclear fuel to be returned to the United States under the Foreign Research Reactor Spent Nuclear Fuel Acceptance Program. The fuel is further evaluated for acceptance through assessments of the fuel at the foreign sites that include corrosion damage and handleability. Transport involves use of commercial shipping casks with defined leakage rates that can provide containment of the fuel, some of which are breached. Options for safe storage include wet storage and dry storage. Both options must fully address potential degradation of the aluminum during the storage period. This paper focuses on the various options for safe transport and storage with respect to technology maturity and application.

  3. Development of Advanced Technologies to Reduce Design, Fabrication and Construction Costs for Future Nuclear Power Plants

    SciTech Connect (OSTI)

    DiNunzio, Camillo A.; Gupta, Abhinav; Golay, Michael; Luk, Vincent; Turk, Rich; Morrow, Charles; Jin, Geum-Taek

    2002-11-30

    This report presents a summation of the third and final year of a three-year investigation into methods and technologies for substantially reducing the capital costs and total schedule for future nuclear plants. In addition, this is the final technical report for the three-year period of studies.

  4. SOME RECENT TECHNOLOGY DEVELOPMENTS FROM THE UK'S NATIONAL NUCLEAR LABORATORY TO ENABLE HAZARD CHARACTERISATION FOR NUCLEAR DECOMMISSIONING APPLICATIONS

    SciTech Connect (OSTI)

    Farfan, E.; Foley, T.

    2010-02-11

    Under its programme of self investment Internal Research and Development (IR&D), the UK's National Nuclear Laboratory (NNL) is addressing the requirement for development in technology to enable hazard characterisation for nuclear decommissioning applications. Three such examples are described here: (1) RadBall developed by the NNL (patent pending) is a deployable baseball-sized radiation mapping device which can, from a single location, locate and quantify radiation hazards. RadBall offers a means to collect information regarding the magnitude and distribution of radiation in a given cell, glovebox or room to support the development of a safe, cost effective decontamination strategy. RadBall requires no electrical supplies and is relatively small, making it easy to be deployed and used to map radiation hazards in hard to reach areas. Recent work conducted in partnership with the Savannah River National Laboratory (SRNL) is presented. (2) HiRAD (patent pending) has been developed by the NNL in partnership with Tracerco Ltd (UK). HiRAD is a real-time, remotely deployed, radiation detection device designed to operate in elevated levels of radiation (i.e. thousands and tens of thousands of Gray) as seen in parts of the nuclear industry. Like the RadBall technology, the HiRAD system does not require any electrical components, the small dimensions and flexibility of the device allow it to be positioned in difficult to access areas (such as pipe work). HiRAD can be deployed as a single detector, a chain, or as an array giving the ability to monitor large process areas. Results during the development and deployment of the technology are presented. (3) Wireless Sensor Network is a NNL supported development project led by the University of Manchester (UK) in partnership with Oxford University (UK). The project is concerned with the development of wireless sensor network technology to enable the underwater deployment and communication of miniaturised probes allowing pond monitoring and mapping. The potential uses, within the nuclear sector alone, are both numerous and significant in terms of the proceeding effort to clean up the UK's nuclear waste legacy.

  5. Innovation in Nuclear Technology for the Least Product Price and Cost

    SciTech Connect (OSTI)

    Duffey, Romney

    2003-09-01

    In energy markets, costs dominate for all new technology introductions (pressure valves, gas turbines, reactors) both now and far into the future. Technology improves, and costs are reduced as markets are penetrated with the trend following a learning/experience curve (MCE) based on classic economic forces. The curve followed is governed by development costs and market targets, and nuclear systems follow such a curve in order to compete with other technologies and projected future cost for alternate energy initiatives. Funding impacts directly on market penetration and on the ''learning rate.'' The CANDU/AECL development path (experience curve) is a chosen balance between evolution and revolution for a competitive advantage.

  6. The Need for a Strong Science and Technology Program in the Nuclear Weapons Complex for the 21st Century

    SciTech Connect (OSTI)

    Garaizar, X

    2010-01-06

    In this paper I argue for the need for a strong Science and Technology program in the Nuclear Weapons Complex as the basis for maintaining a credible deterrence capability. The current Nuclear Posture Review establishes a New Triad as the basis for the United States deterrence strategy in a changing security environment. A predictive science capability is at the core of a credible National Nuclear Weapons program in the 21st Century. In absence of nuclear testing, the certification of our current Nuclear Weapons relies on predictive simulations and quantification of the associated simulation uncertainties. In addition, a robust nuclear infrastructure needs an active research and development program that considers all the required nuclear scenarios, including new configurations for which there is no nuclear test data. This paper also considers alternative positions to the need for a Science and Technology program in the Nuclear Weapons complex.

  7. New Technologies for Repairing Aging Cables in Nuclear Power Plants

    SciTech Connect (OSTI)

    Simmons, Kevin L. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Fifield, Leonard S. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Westman, Matthew P. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

    2013-09-11

    The goal of this project is to demonstrate a proof-of-concept for a technique to repair aging cables that have been subjected to degradation associated with long-term thermal and radiation exposure in nuclear power plants. The physical degradation of the aging cables manifests itself primarily as cracking and increased brittleness of the polymeric electrical insulation. Therefore, the proposed cable-repair concept comprises development of techniques to impart a softening agent within the deteriorated polymer insulation jacket so as to regain the ability of the insulation to stretch without failing and possibly to heal existing cracks in the insulation. Our approach is to use commercially available ethylene-propylene rubber (EPR) as the relevant test material, demonstrate the adsorption of chemical treatments in the EPR and quantify changes in resulting physical and mechanical properties. EPR cable samples have been thermally treated in air to produce specimens corresponding to the full range of cable age-performance points from new (>350% elongation at break) to end-of-life (<50% elongation at break). The current focus is on two chemical treatments selected as candidates for restoring age-related cable elasticity loss: a rubber plasticizer and a reactive silane molecule. EPR specimens of 200, 150, 100, and 50% elongation at break have been soaked in the candidate chemical treatments and the kinetics of chemical uptake, measured by change in mass of the samples, has been determined. Mechanical properties as a function of aging and chemical treatment have been measured including ultimate tensile strength, tensile modulus at 50% strain, elongation at break, and storage modulus. Dimensional changes with treatment and changes in glass transition temperature were also investigated. These ongoing experiments are expected to provide insight into the physical-chemical nature of the effect of thermal degradation on EPR rejuvenation limits and to advance novel methods for restoring the ability of degraded EPR to be compliant and resist fracture. The results of this research reveal that absorption of chemical treatments can lower the glass transition temperature and modulus of EPR. Chemical treatments pursued thus far have proven ineffective at restoring EPR strength and elongation at break. Future work will combine the plasticizer modalities found to successfully increase the volume of the EPR, reduce EPR glass transition temperature and reduce EPR modulus with promising chemistries that will repair the damage of the polymer, potentially using the plasticizer as a host for the new chemistry.

  8. METAL MEDIA FILTERS, AG-1 SECTION FI

    SciTech Connect (OSTI)

    Adamson, D.

    2012-05-23

    One application of metal media filters is in various nuclear air cleaning processes including applications for protecting workers, the public and the environment from hazardous and radioactive particles. To support this application the development of the ASME AG-1 FI Standard on Metal Media has been under way for more than ten years. Development of the proposed section has required resolving several difficult issues associated with operating conditions (media velocity, pressure drop, etc.), qualification testing, and quality acceptance testing. Performance characteristics of metal media are dramatically different than the glass fiber media with respect to parameters like differential pressures, operating temperatures, media strength, etc. These differences make existing data for a glass fiber media inadequate for qualifying a metal media filter for AG-1. In the past much work has been conducted on metal media filters at facilities such as Lawrence Livermore National Laboratory (LLNL) and Savannah River National Laboratory (SRNL) to qualify the media as High Efficiency Particulate Air (HEPA) Filters. Particle retention testing has been conducted at Oak Ridge Filter Test Facility and at Air Techniques International (ATI) to prove that the metal media meets or exceeds the 99.97% particle retention required for a HEPA Filter. Even with his testing, data was lacking to complete an AG-1 FI Standard on metal media. With funding secured by Mississippi State University (MSU) from National Nuclear Security Administration (NNSA), a research test stand is being designed and fabricated at MSU's Institute for Clean Energy Technology (ICET) Facility to obtain qualification data on metal media. This in turn will support required data needed for the FI Standard. The paper will discuss in detail how the test stand at MSU will obtain the necessary data to complete the FI Standard.

  9. High Temperature Electrolysis for Hydrogen Production from Nuclear Energy – TechnologySummary

    SciTech Connect (OSTI)

    J. E. O'Brien; C. M. Stoots; J. S. Herring; M. G. McKellar; E. A. Harvego; M. S. Sohal; K. G. Condie

    2010-02-01

    The Department of Energy, Office of Nuclear Energy, has requested that a Hydrogen Technology Down-Selection be performed to identify the hydrogen production technology that has the best potential for timely commercial demonstration and for ultimate deployment with the Next Generation Nuclear Plant (NGNP). An Independent Review Team has been assembled to execute the down-selection. This report has been prepared to provide the members of the Independent Review Team with detailed background information on the High Temperature Electrolysis (HTE) process, hardware, and state of the art. The Idaho National Laboratory has been serving as the lead lab for HTE research and development under the Nuclear Hydrogen Initiative. The INL HTE program has included small-scale experiments, detailed computational modeling, system modeling, and technology demonstration. Aspects of all of these activities are included in this report. In terms of technology demonstration, the INL successfully completed a 1000-hour test of the HTE Integrated Laboratory Scale (ILS) technology demonstration experiment during the fall of 2008. The HTE ILS achieved a hydrogen production rate in excess of 5.7 Nm3/hr, with a power consumption of 18 kW. This hydrogen production rate is far larger than has been demonstrated by any of the thermochemical or hybrid processes to date.

  10. Vehicle Technologies Office Merit Review 2014: Durability of Diesel Particulate Filters (Agreement ID:10461) Project ID:18519

    Broader source: Energy.gov [DOE]

    Presentation given by Oak Ridge National Laboratory at 2014 DOE Hydrogen and Fuel Cells Program and Vehicle Technologies Office Annual Merit Review and Peer Evaluation Meeting about durability of...

  11. Filtering apparatus

    DOE Patents [OSTI]

    Haldipur, G.B.; Dilmore, W.J.

    1992-09-01

    A vertical vessel is described having a lower inlet and an upper outlet enclosure separated by a main horizontal tube sheet. The inlet enclosure receives the flue gas from a boiler of a power system and the outlet enclosure supplies cleaned gas to the turbines. The inlet enclosure contains a plurality of particulate-removing clusters, each having a plurality of filter units. Each filter unit includes a filter clean-gas chamber defined by a plate and a perforated auxiliary tube sheet with filter tubes suspended from each tube sheet and a tube connected to each chamber for passing cleaned gas to the outlet enclosure. The clusters are suspended from the main tube sheet with their filter units extending vertically and the filter tubes passing through the tube sheet and opening in the outlet enclosure. The flue gas is circulated about the outside surfaces of the filter tubes and the particulate is absorbed in the pores of the filter tubes. Pulses to clean the filter tubes are passed through their inner holes through tubes free of bends which are aligned with the tubes that pass the clean gas. 18 figs.

  12. Filtering apparatus

    DOE Patents [OSTI]

    Haldipur, Gaurang B.; Dilmore, William J.

    1992-01-01

    A vertical vessel having a lower inlet and an upper outlet enclosure separated by a main horizontal tube sheet. The inlet enclosure receives the flue gas from a boiler of a power system and the outlet enclosure supplies cleaned gas to the turbines. The inlet enclosure contains a plurality of particulate-removing clusters, each having a plurality of filter units. Each filter unit includes a filter clean-gas chamber defined by a plate and a perforated auxiliary tube sheet with filter tubes suspended from each tube sheet and a tube connected to each chamber for passing cleaned gas to the outlet enclosure. The clusters are suspended from the main tube sheet with their filter units extending vertically and the filter tubes passing through the tube sheet and opening in the outlet enclosure. The flue gas is circulated about the outside surfaces of the filter tubes and the particulate is absorbed in the pores of the filter tubes. Pulses to clean the filter tubes are passed through their inner holes through tubes free of bends which are aligned with the tubes that pass the clean gas.

  13. Implementing Arrangement Between the U.S. Department of Energy and the Agency of Natural Resources and Energy of Japan Concerning Cooperation in the Joint Nuclear Energy Research Initiative on Advanced Nuclear Technologies

    Broader source: Energy.gov [DOE]

    Noting further that representatives of DOE's Office of Nuclear Energy, Science, and Technology and ANRE have identified common interests in innovative light water reactor technologies, including...

  14. Most Viewed Documents - Fission and Nuclear Technologies | OSTI, US Dept of

    Office of Scientific and Technical Information (OSTI)

    Energy, Office of Scientific and Technical Information - Fission and Nuclear Technologies Metals design handbook Betts, W.S. (1988) Estimation of gas leak rates through very small orifices and channels. [From sealed PuO/sub 2/ containers under accident conditions] Bomelburg, H.J. () Graphite design handbook Ho, F.H. (1988) Motor-operated valve (MOV) actuator motor and gearbox testing DeWall, K.; Watkins, J.C.; Bramwell, D. [Lockheed Idaho Technologies Co., Idaho Falls, ID (United States)]

  15. Calcine Waste Storage at the Idaho Nuclear Technology and Engineering Center

    SciTech Connect (OSTI)

    Staiger, Merle Daniel; M. C. Swenson

    2005-01-01

    This report documents an inventory of calcined waste produced at the Idaho Nuclear Technology and Engineering Center during the period from December 1963 to May 2000. The report was prepared based on calciner runs, operation of the calcined solids storage facilities, and miscellaneous operational information that establishes the range of chemical compositions of calcined waste stored at Idaho Nuclear Technology and Engineering Center. The report will be used to support obtaining permits for the calcined solids storage facilities, possible treatment of the calcined waste at the Idaho National Engineering and Environmental Laboratory, and to ship the waste to an off-site facility including a geologic repository. The information in this report was compiled from calciner operating data, waste solution analyses and volumes calcined, calciner operating schedules, calcine temperature monitoring records, and facility design of the calcined solids storage facilities. A compact disk copy of this report is provided to facilitate future data manipulations and analysis.

  16. Supercritical Fluid Extraction of Radionuclides - A Green Technology for Nuclear Waste Management

    SciTech Connect (OSTI)

    Wai, Chien M.

    2003-09-10

    Supercritical fluid carbon dioxide (SF-CO2) is capable of extracting radionuclides including cesium, strontium, uranium, plutonium and lanthanides directly from liquid and solid samples with proper complexing agents. Of particular interest is the ability of SF-CO2 to dissolve uranium dioxide directly using a CO2-soluble tri-nbutylphosphate- nitric acid (TBP-HNO3) extractant to form a highly soluble UO2(NO3)2(TBP)2 complex that can be transported and separated from Cs, Sr, and other transition metals. This method can also dissolve plutonium dioxide in SF-CO2. The SF-CO2 extraction technology offers several advantages over conventional solvent-based methods including ability to extract radionuclides directly from solids, easy separation of solutes from CO2, and minimization of liquid waste generation. Potential applications of the SF-CO2 extraction technology for nuclear waste treatment and for reprocessing of spent nuclear fuels will be discussed. Information on current demonstrations of the SF-CO2 technology by nuclear companies and research organizations in different countries will be reviewed.

  17. Evaluation of Non-Nuclear Techniques for Well Logging: Technology Evaluation

    SciTech Connect (OSTI)

    Bond, Leonard J.; Denslow, Kayte M.; Griffin, Jeffrey W.; Dale, Gregory E.; Harris, Robert V.; Moran, Traci L.; Sheen, David M.; Schenkel, Thomas

    2010-11-01

    This report presents an initial review of the state-of-the-art nuclear and non-nuclear well logging methods and seeks to understand the technical and economic issues if AmBe, and potentially other isotope sources, are reduced or even eliminated in the oil-field services industry. Prior to considering alternative logging technologies, there is a definite need to open up discussions with industry regarding the feasibility and acceptability of source replacement. Industry views appear to range from those who see AmBe as vital and irreplaceable to those who believe that, with research and investment, it may be possible to transition to electronic neutron sources and employ combinations of non-nuclear technologies to acquire the desired petro-physical parameters. In one sense, the simple answer to the question as to whether petro-physical parameters can be sensed with technologies other than AmBe is probably "Yes". The challenges come when attention turns to record interpretation. The many decades of existing records form a very valuable proprietary resource, and the interpretation of subtle features contained in these records are of significant value to the oil-gas exploration community to correctly characterize a well. The demonstration of equivalence and correspondence/correlation between established and any new sensing modality, and correlations with historic records is critical to ensuring accurate data interpretation. Establishing the technical basis for such a demonstration represents a significant effort.

  18. Proceedings of the 28th Seismic Research Review: Ground-Based Nuclear Explosion Monitoring Technologies

    SciTech Connect (OSTI)

    Wetovsky, Marvin A.; Benson, Jody; Patterson, Eileen F.

    2006-09-19

    These proceedings contain papers prepared for the 28th Seismic Research Review: Ground-Based Nuclear Explosion Monitoring Technologies, held 19-21 September, 2006 in Orlando, Florida. These papers represent the combined research related to ground-based nuclear explosion monitoring funded by the National Nuclear Security Administration (NNSA), Air Force Technical Applications Center (AFTAC), Air Force Research Laboratory (AFRL), US Army Space and Missile Defense Command, Comprehensive Nuclear-Test-Ban Treaty Organization (CTBTO), and other invited sponsors. The scientific objectives of the research are to improve the United States capability to detect, locate, and identify nuclear explosions. The purpose of the meeting is to provide the sponsoring agencies, as well as potential users, an opportunity to review research accomplished during the preceding year and to discuss areas of investigation for the coming year. For the researchers, it provides a forum for the exchange of scientific information toward achieving program goals, and an opportunity to discuss results and future plans. Paper topics include: seismic regionalization and calibration; detection and location of sources; wave propagation from source to receiver; the nature of seismic sources, including mining practices; hydroacoustic, infrasound, and radionuclide methods; on-site inspection; and data processing.

  19. Proceedings of the 2011 Monitoring Research Review: Ground-Based Nuclear Explosion Monitoring Technologies

    SciTech Connect (OSTI)

    Wetovsky, Marvin A.; Patterson, Eileen F.; Sandoval, Marisa N.

    2011-09-13

    These proceedings contain papers prepared for the Monitoring Research Review 2011: Ground-Based Nuclear Explosion Monitoring Technologies, held 13-15 September, 2011 in Tucson, Arizona. These papers represent the combined research related to ground-based nuclear explosion monitoring funded by the National Nuclear Security Administration (NNSA), Defense Threat Reduction Agency (DTRA), Air Force Research Laboratory (AFRL), US Army Space and Missile Defense Command, Comprehensive Nuclear-Test-Ban Treaty Organization (CTBTO), National Science Foundation (NSF), and other invited sponsors. The scientific objectives of the research are to improve the United States' capability to detect, locate, and identify nuclear explosions. The purpose of the meeting is to provide the sponsoring agencies, as well as potential users, an opportunity to review research accomplished during the preceding year and to discuss areas of investigation for the coming year. For the researchers, it provides a forum for the exchange of scientific information toward achieving program goals, and an opportunity to discuss results and future plans. Paper topics include: seismic regionalization and calibration; detection and location of sources; wave propagation from source to receiver; the nature of seismic sources, including mining practices; hydroacoustic, infrasound, and radionuclide methods; on-site inspection; and data processing.

  20. Proceedings of the 2010 Monitoring Research Review: Ground-Based Nuclear Explosion Monitoring Technologies

    SciTech Connect (OSTI)

    Wetovsky, Marvin A.; Patterson, Eileen F.

    2010-09-21

    These proceedings contain papers prepared for the Monitoring Research Review 2010: Ground-Based Nuclear Explosion Monitoring Technologies, held 21-23 September, 2010 in Orlando, Florida,. These papers represent the combined research related to ground-based nuclear explosion monitoring funded by the National Nuclear Security Administration (NNSA), Air Force Research Laboratory (AFRL), US Army Space and Missile Defense Command, National Science Foundation (NSF), Comprehensive Nuclear-Test-Ban Treaty Organization (CTBTO), and other invited sponsors. The scientific objectives of the research are to improve the United States capability to detect, locate, and identify nuclear explosions. The purpose of the meeting is to provide the sponsoring agencies, as well as potential users, an opportunity to review research accomplished during the preceding year and to discuss areas of investigation for the coming year. For the researchers, it provides a forum for the exchange of scientific information toward achieving program goals, and an opportunity to discuss results and future plans. Paper topics include: seismic regionalization and calibration; detection and location of sources; wave propagation from source to receiver; the nature of seismic sources, including mining practices; hydroacoustic, infrasound, and radionuclide methods; on-site inspection; and data processing.

  1. Proceedings of the 29th Monitoring Research Review: Ground-Based Nuclear Explosion Monitoring Technologies

    SciTech Connect (OSTI)

    Wetovsky, Marvin A.; Benson, Jody; Patterson, Eileen F.

    2007-09-25

    These proceedings contain papers prepared for the 29th Monitoring Research Review: Ground-Based Nuclear Explosion Monitoring Technologies, held 25-27 September, 2007 in Denver, Colorado. These papers represent the combined research related to ground-based nuclear explosion monitoring funded by the National Nuclear Security Administration (NNSA), Air Force Technical Applications Center (AFTAC), Air Force Research Laboratory (AFRL), US Army Space and Missile Defense Command, Comprehensive Nuclear-Test-Ban Treaty Organization (CTBTO), and other invited sponsors. The scientific objectives of the research are to improve the United States capability to detect, locate, and identify nuclear explosions. The purpose of the meeting is to provide the sponsoring agencies, as well as potential users, an opportunity to review research accomplished during the preceding year and to discuss areas of investigation for the coming year. For the researchers, it provides a forum for the exchange of scientific information toward achieving program goals, and an opportunity to discuss results and future plans. Paper topics include: seismic regionalization and calibration; detection and location of sources; wave propagation from source to receiver; the nature of seismic sources, including mining practices; hydroacoustic, infrasound, and radionuclide methods; on-site inspection; and data processing.

  2. CONTROL TESTING OF THE UK NATIONAL NUCLEAR LABORATORY'S RADBALL TECHNOLOGY AT SAVANNAH RIVER NATIONAL LABORATORY

    SciTech Connect (OSTI)

    Farfan, E.

    2009-11-23

    The UK National Nuclear Laboratory (NNL) has developed a remote, non-electrical, radiation-mapping device known as RadBall (patent pending), which offers a means to locate and quantify radiation hazards and sources within contaminated areas of the nuclear industry. To date, the RadBall has been deployed in a number of technology trials in nuclear waste reprocessing plants at Sellafield in the UK. The trials have demonstrated the successful ability of the RadBall technology to be deployed and retrieved from active areas. The positive results from these initial deployment trials and the anticipated future potential of RadBall have led to the NNL partnering with the Savannah River National Laboratory (SRNL) to further underpin and strengthen the technical performance of the technology. RadBall consists of a colander-like outer shell that houses a radiation-sensitive polymer sphere. It has no power requirements and can be positioned in tight or hard-to reach places. The outer shell works to collimate radiation sources and those areas of the polymer sphere that are exposed react, becoming increasingly less transparent, in proportion to the absorbed dose. The polymer sphere is imaged in an optical-CT scanner which produces a high resolution 3D map of optical attenuation coefficients. Subsequent analysis of the optical attenuation maps provides information on the spatial distribution and strength of the sources in a given area forming a 3D characterization of the area of interest. This study completed at SRNL addresses key aspects of the testing of the RadBall technology. The first set of tests was performed at Savannah River Nuclear Solutions Health Physics Instrument Calibration Laboratory (HPICL) using various gamma-ray sources and an x-ray machine with known radiological characteristics. The objective of these preliminary tests was to identify the optimal dose and collimator thickness. The second set of tests involved a highly contaminated hot cell. The objective of this part of the testing was to characterize a hot cell with unknown radiation sources. The RadBall calibration experiments and hot cell deployment completed at SRNL were successful in that for each trial, the technology was able to locate the radiation sources. The NNL believe that the ability of RadBall to be remotely deployed with no electrical supplies into difficult to access areas of plant and locate and quantify radiation hazards is a unique radiation mapping service. The NNL consider there to be significant business potential associated with this innovative technology.

  3. Precision X-Band Linac Technologies for Nuclear Photonics Gamma-Ray Sources

    SciTech Connect (OSTI)

    Hartemann, F V; Albert, F; Anderson, S G; Bayramian, A J; Cross, R R; Ebbers, C A; Gibson, D J; Houck, T L; Marsh, R A; Messerly, M J; Siders, C W; McNabb, D P; Barty, C J; Adolphsen, C E; Chu, T S; Jongewaard, E N; Tantawi, S G; Vlieks, A E; Wang, F; Wang, J W; Raubenheimer, T O; Ighigeanu, D; Toma, M; Cutoiu, D

    2011-08-31

    Nuclear photonics is an emerging field of research requiring new tools, including high spectral brightness, tunable gamma-ray sources; high photon energy, ultrahigh-resolution crystal spectrometers; and novel detectors. This presentation focuses on the precision linac technology required for Compton scattering gamma-ray light sources, and on the optimization of the laser and electron beam pulse format to achieve unprecedented spectral brightness. Within this context, high-gradient X-band technology will be shown to offer optimal performance in a compact package, when used in conjunction with the appropriate pulse format, and photocathode illumination and interaction laser technologies. The nascent field of nuclear photonics is enabled by the recent maturation of new technologies, including high-gradient X-band electron acceleration, robust fiber laser systems, and hyper-dispersion CPA. Recent work has been performed at LLNL to demonstrate isotope-specific detection of shielded materials via NRF using a tunable, quasi-monochromatic Compton scattering gamma-ray source operating between 0.2 MeV and 0.9 MeV photon energy. This technique is called Fluorescence Imaging in the Nuclear Domain with Energetic Radiation (or FINDER). This work has, among other things, demonstrated the detection of {sup 7}Li shielded by Pb, utilizing gamma rays generated by a linac-driven, laser-based Compton scattering gamma-ray source developed at LLNL. Within this context, a new facility is currently under construction at LLNL, with the goal of generating tunable {gamma}-rays in the 0.5-2.5 MeV photon energy range, at a repetition rate of 120 Hz, and with a peak brightness in the 10{sup 20} photons/(s x mm{sup 2} x mrad{sup 2} x 0.1% bw).

  4. ``White Land``...new Russian closed-cycle nuclear technology for global deployment

    SciTech Connect (OSTI)

    Bowman, C.D.

    1996-07-01

    A Russian technology called ``White Land`` is being pursued which is based on their heavy-metal-cooled fast spectrum reactor technology developed to power their super-fast Alpha Class submarines. These reactors have important safety advantages over the more conventional sodium-cooled fast breeder reactors but preserve some of the attractive operational features of the fast spectrum systems. Perhaps chief among these advantages in the current political milieu is their ability to generate energy from any nuclide heavier than thorium including HEU, weapons plutonium, commercial plutonium, neptunium, americium, and curium. While there are several scenarios for deployment of these systems, the most attractive perhaps is containment in submarine-like enclosures to be placed underwater near a coastal population center. A Russian organization named the Alphabet Company would build the reactors and maintain title to them. The company would be paid on the basis of kilowatt-hours delivered. The reactors would not require refueling for 10--15 years and no maintenance violating the radiation containment would be required or would be carried out at the deployment site. The host country need not develop any nuclear technology or accept any nuclear waste. When the fuel load has been burned, the entire unit would be towed to Archangel, Russia for refueling. The fission product would be removed from the fuel by ``dry`` molten salt technology to minimize the waste stream and the fissile material would be returned to the reactor for further burning. The fission product waste would be stored at New Land Island, their current nuclear test site in the Arctic. If concerns over fission product justify it, the long-lived species will be transmuted in an accelerator-driven system. Apparently this project is backed at the highest levels of MINATOM and the Alphabet Company has the funding to proceed.

  5. Proceedings of the 2009 Monitoring Research Review: Ground-Based Nuclear Explosion Monitoring Technologies

    SciTech Connect (OSTI)

    Wetovsky, Marv A; Aguilar - Chang, Julio; Anderson, Dale; Arrowsmith, Marie; Arrowsmith, Stephen; Baker, Diane; Begnaud, Michael; Harste, Hans; Maceira, Monica; Patton, Howard; Phillips, Scott; Randall, George; Rowe, Charlotte; Stead, Richard; Steck, Lee; Whitaker, Rod; Yang, Xiaoning

    2009-09-21

    These proceedings contain papers prepared for the Monitoring Research Review 2009: Ground -Based Nuclear Explosion Monitoring Technologies, held 21-23 September, 2009 in Tucson, Arizona,. These papers represent the combined research related to ground-based nuclear explosion monitoring funded by the National Nuclear Security Administration (NNSA), Air Force Research Laboratory (AFRL), US Army Space and Missile Defense Command, Comprehensive Test Ban Treaty Organization (CTBTO), and other invited sponsors. The scientific objectives of the research are to improve the United States’ capability to detect, locate, and identify nuclear explosions. The purpose of the meeting is to provide the sponsoring agencies, as well as potential users, an opportunity to review research accomplished during the preceding year and to discuss areas of investigation for the coming year. For the researchers, it provides a forum for the exchange of scientific information toward achieving program goals, and an opportunity to discuss results and future plans. Paper topics include: seismic regionalization and calibration; detection and location of sources; wave propagation from source to receiver; the nature of seismic sources, including mining practices; hydroacoustic, infrasound, and radionuclide methods; on-site inspection; and data processing.

  6. Proceedings of the 27th Seismic Research Review: Ground-Based Nuclear Explosion Monitoring Technologies

    SciTech Connect (OSTI)

    Wetovsky, Marvin A.; Benson, Jody; Patterson, Eileen F.

    2005-09-20

    These proceedings contain papers prepared for the 27th Seismic Research Review: Ground-Based Nuclear Explosion Monitoring Technologies, held 20-22 September, 2005 in Rancho Mirage, California. These papers represent the combined research related to ground-based nuclear explosion monitoring funded by the National Nuclear Security Administration (NNSA), Air Force Technical Applications Center (AFTAC), Air Force Research Laboratory (AFRL), US Army Space and Missile Defense Command, and other invited sponsors. The scientific objectives of the research are to improve the United States capability to detect, locate, and identify nuclear explosions. The purpose of the meeting is to provide the sponsoring agencies, as well as potential users, an opportunity to review research accomplished during the preceding year and to discuss areas of investigation for the coming year. For the researchers, it provides a forum for the exchange of scientific information toward achieving program goals, and an opportunity to discuss results and future plans. Paper topics include: seismic regionalization and calibration; detection and location of sources; wave propagation from source to receiver; the nature of seismic sources, including mining practices; hydroacoustic, infrasound, and radionuclide methods; on-site inspection; and data processing.

  7. New radiological material detection technologies for nuclear forensics: Remote optical imaging and graphene-based sensors.

    SciTech Connect (OSTI)

    Harrison, Richard Karl; Martin, Jeffrey B.; Wiemann, Dora K.; Choi, Junoh; Howell, Stephen W.

    2015-09-01

    We developed new detector technologies to identify the presence of radioactive materials for nuclear forensics applications. First, we investigated an optical radiation detection technique based on imaging nitrogen fluorescence excited by ionizing radiation. We demonstrated optical detection in air under indoor and outdoor conditions for alpha particles and gamma radiation at distances up to 75 meters. We also contributed to the development of next generation systems and concepts that could enable remote detection at distances greater than 1 km, and originated a concept that could enable daytime operation of the technique. A second area of research was the development of room-temperature graphene-based sensors for radiation detection and measurement. In this project, we observed tunable optical and charged particle detection, and developed improved devices. With further development, the advancements described in this report could enable new capabilities for nuclear forensics applications.

  8. Air filter

    SciTech Connect (OSTI)

    Jackson, R.E.; Sparks, J.E.

    1981-03-03

    An air filter is described that has a counter rotating drum, i.e., the rotation of the drum is opposite the tangential intake of air. The intake air has about 1 lb of rock wool fibers per 107 cu. ft. of air sometimes at about 100% relative humidity. The fibers are doffed from the drum by suction nozzle which are adjacent to the drum at the bottom of the filter housing. The drum screen is cleaned by periodically jetting hot dry air at 120 psig through the screen into the suction nozzles.

  9. Filter apparatus

    DOE Patents [OSTI]

    Kuban, Daniel P. (Oak Ridge, TN); Singletary, B. Huston (Oak Ridge, TN); Evans, John H. (Rockwood, TN)

    1984-01-01

    A plurality of holding tubes are respectively mounted in apertures in a partition plate fixed in a housing receiving gas contaminated with particulate material. A filter cartridge is removably held in each holding tube, and the cartridges and holding tubes are arranged so that gas passes through apertures therein and across the partition plate while particulate material is collected in the cartridges. Replacement filter cartridges are respectively held in holding canisters mounted on a support plate which can be secured to the aforesaid housing, and screws mounted on said canisters are arranged to push replacement cartridges into the cartridge holding tubes and thereby eject used cartridges therefrom.

  10. Idaho Nuclear Technology and Engineering Center Newly Generated Liquid Waste Demonstration Project Feasibility Study

    SciTech Connect (OSTI)

    Herbst, A.K.

    2000-02-01

    A research, development, and demonstration project for the grouting of newly generated liquid waste (NGLW) at the Idaho Nuclear Technology and Engineering Center is considered feasible. NGLW is expected from process equipment waste, decontamination waste, analytical laboratory waste, fuel storage basin waste water, and high-level liquid waste evaporator condensate. The potential grouted waste would be classed as mixed low-level waste, stabilized and immobilized to meet RCRA LDR disposal in a grouting process in the CPP-604 facility, and then transported to the state.

  11. Identification and Evaluation of Human Factors Issues Associated with Emerging Nuclear Plant Technology

    SciTech Connect (OSTI)

    O'Hara,J.M.; Higgins,J.; Brown, William S.

    2009-04-01

    This study has identified human performance research issues associated with the implementation of new technology in nuclear power plants (NPPs). To identify the research issues, current industry developments and trends were evaluated in the areas of reactor technology, instrumentation and control technology, human-system integration technology, and human factors engineering (HFE) methods and tools. The issues were prioritized into four categories based on evaluations provided by 14 independent subject matter experts representing vendors, utilities, research organizations and regulators. Twenty issues were categorized into the top priority category. The study also identifies the priority of each issue and the rationale for those in the top priority category. The top priority issues were then organized into research program areas of: New Concepts of Operation using Multi-agent Teams, Human-system Interface Design, Complexity Issues in Advanced Systems, Operating Experience of New and Modernized Plants, and HFE Methods and Tools. The results can serve as input to the development of a long-term strategy and plan for addressing human performance in these areas to support the safe operation of new NPPs.

  12. Environmental assessment report: Nuclear Test Technology Complex. [Construction and operation of proposed facility

    SciTech Connect (OSTI)

    Tonnessen, K.; Tewes, H.A.

    1982-08-01

    The US Department of Energy (USDOE) is planning to construct and operate a structure, designated the Nuclear Test Technology Complex (NTTC), on a site located west of and adjacent to the Lawrence Livermore National Laboratory. The NTTC is designed to house 350 nuclear test program personnel, and will accommodate the needs of the entire staff of the continuing Nuclear Test Program (NTP). The project has three phases: land acquisition, facility construction and facility operation. The purpose of this environmental assessment report is to describe the activities associated with the three phases of the NTTC project and to evaluate potential environmental disruptions. The project site is located in a rural area of southeastern Alameda County, California, where the primary land use is agriculture; however, the County has zoned the area for industrial development. The environmental impacts of the project include surface disturbance, high noise levels, possible increases in site erosion, and decreased air quality. These impacts will occur primarily during the construction phase of the NTTC project and can be mitigated in part by measures proposed in this report.

  13. Magnetic Filtration Process, Magnetic Filtering Material, and Method of

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

    Forming Magnetic Filtering Material - Energy Innovation Portal Industrial Technologies Industrial Technologies Find More Like This Return to Search Magnetic Filtration Process, Magnetic Filtering Material, and Method of Forming Magnetic Filtering Material Oak Ridge National Laboratory Contact ORNL About This Technology Technology Marketing SummaryORNL researchers developed a new method for filtering materials and managing wastewater. This invention offers an integrated, intensified process

  14. Review: Waste-Pretreatment Technologies for Remediation of Legacy Defense Nuclear Wastes

    SciTech Connect (OSTI)

    Wilmarth, William R.; Lumetta, Gregg J.; Johnson, Michael E.; Poirier, Micheal R.; Thompson, Major C.; Suggs, Patricia C.; Machara, N.

    2011-01-13

    The U.S. Department of Energy (DOE) is responsible for retrieving, immobilizing, and disposing of radioactive waste that has been generated during the production of nuclear weapons in the United States. The vast bulk of this waste material is stored in underground tanks at the Savannah River Site in South Carolina and the Hanford Site in Washington State. The general strategy for treating the radioactive tank waste consists of first separating the waste into high-level and low-activity fractions. This initial partitioning of the waste is referred to as pretreatment. Following pretreatment, the high-level fraction will be immobilized in a glass form suitable for disposal in a geologic repository. The low-activity waste will be immobilized in a waste form suitable for disposal at the respective site. This paper provides a review of recent developments in the application of pretreatment technologies to the processing of the Hanford and Savannah River radioactive tank wastes. Included in the review are discussions of 1) solid/liquid separations methods, 2) cesium separation technologies, and 3) other separations critical to the success of the DOE tank waste remediation effort. Also included is a brief discussion of the different requirements and circumstances at the two DOE sites that have in some cases led to different choices in pretreatment technologies.

  15. Considerations Associated with Reactor Technology Selection for the Next Generation Nuclear Plant Project

    SciTech Connect (OSTI)

    L.E. Demick

    2010-09-01

    At the inception of the Next Generation Nuclear Plant Project and during predecessor activities, alternative reactor technologies have been evaluated to determine the technology that best fulfills the functional and performance requirements of the targeted energy applications and market. Unlike the case of electric power generation where the reactor performance is primarily expressed in terms of economics, the targeted energy applications involve industrial applications that have specific needs in terms of acceptable heat transport fluids and the associated thermodynamic conditions. Hence, to be of interest to these industrial energy applications, the alternative reactor technologies are weighed in terms of the reactor coolant/heat transport fluid, achievable reactor outlet temperature, and practicality of operations to achieve the very high reliability demands associated with the petrochemical, petroleum, metals and related industries. These evaluations have concluded that the high temperature gas-cooled reactor (HTGR) can uniquely provide the required ranges of energy needs for these target applications, do so with promising economics, and can be commercialized with reasonable development risk in the time frames of current industry interest i.e., within the next 10-15 years.

  16. REVIEW OF INDUSTRIES AND GOVERNMENT AGENCIES FOR TECHNOLOGIES APPLICABLE TO DEACTIVATION AND DECOMMISSIONING OF NUCLEAR WEAPONS FACILITIES

    SciTech Connect (OSTI)

    Reilkoff, T. E.; Hetland, M. D.; O'Leary, E. M.

    2002-02-25

    The Deactivation and Decommissioning Focus Area's (DDFA's) mission is to develop, demonstrate, and deploy improved deactivation and decommissioning (D&D) technologies. This mission requires that emphasis be continually placed on identifying technologies currently employed or under development in other nuclear as well as nonnuclear industries and government agencies. In support of DDFA efforts to clean up the U.S. Department of Energy's (DOE's) radiologically contaminated surplus facilities using technologies that improve worker safety, reduce costs, and accelerate cleanup schedules, a study was conducted to identify innovative technologies developed for use in nonnuclear arenas that are appropriate for D&D applications.

  17. The Nuclear Energy Advanced Modeling and Simulation Enabling Computational Technologies FY09 Report

    SciTech Connect (OSTI)

    Diachin, L F; Garaizar, F X; Henson, V E; Pope, G

    2009-10-12

    In this document we report on the status of the Nuclear Energy Advanced Modeling and Simulation (NEAMS) Enabling Computational Technologies (ECT) effort. In particular, we provide the context for ECT In the broader NEAMS program and describe the three pillars of the ECT effort, namely, (1) tools and libraries, (2) software quality assurance, and (3) computational facility (computers, storage, etc) needs. We report on our FY09 deliverables to determine the needs of the integrated performance and safety codes (IPSCs) in these three areas and lay out the general plan for software quality assurance to meet the requirements of DOE and the DOE Advanced Fuel Cycle Initiative (AFCI). We conclude with a brief description of our interactions with the Idaho National Laboratory computer center to determine what is needed to expand their role as a NEAMS user facility.

  18. Calcine Waste Storage at the Idaho Nuclear Technology and Engineering Center

    SciTech Connect (OSTI)

    M. D. Staiger

    1999-06-01

    A potential option in the program for long-term management of high-level wastes at the Idaho Nuclear Technology and Engineering Center (INTEC), at the Idaho National Engineering and Environmental Laboratory, calls for retrieving calcine waste and converting it to a more stable and less dispersible form. An inventory of calcine produced during the period December 1963 to May 1999 has been prepared based on calciner run, solids storage facilities operating, and miscellaneous operational information, which gives the range of chemical compositions of calcine waste stored at INTEC. Information researched includes calciner startup data, waste solution analyses and volumes calcined, calciner operating schedules, solids storage bin capacities, calcine storage bin distributor systems, and solids storage bin design and temperature monitoring records. Unique information on calcine solids storage facilities design of potential interest to remote retrieval operators is given.

  19. Metrics For Comparing Plasma Mass Filters

    SciTech Connect (OSTI)

    Abraham J. Fetterman and Nathaniel J. Fisch

    2012-08-15

    High-throughput mass separation of nuclear waste may be useful for optimal storage, disposal, or environmental remediation. The most dangerous part of nuclear waste is the fission product, which produces most of the heat and medium-term radiation. Plasmas are well-suited to separating nuclear waste because they can separate many different species in a single step. A number of plasma devices have been designed for such mass separation, but there has been no standardized comparison between these devices. We define a standard metric, the separative power per unit volume, and derive it for three different plasma mass filters: the plasma centrifuge, Ohkawa filter, and the magnetic centrifugal mass filter. __________________________________________________

  20. Metrics for comparing plasma mass filters

    SciTech Connect (OSTI)

    Fetterman, Abraham J.; Fisch, Nathaniel J.

    2011-10-15

    High-throughput mass separation of nuclear waste may be useful for optimal storage, disposal, or environmental remediation. The most dangerous part of nuclear waste is the fission product, which produces most of the heat and medium-term radiation. Plasmas are well-suited to separating nuclear waste because they can separate many different species in a single step. A number of plasma devices have been designed for such mass separation, but there has been no standardized comparison between these devices. We define a standard metric, the separative power per unit volume, and derive it for three different plasma mass filters: the plasma centrifuge, Ohkawa filter, and the magnetic centrifugal mass filter.

  1. Research and Development Technology Development Roadmaps for the Next Generation Nuclear Plant Project

    SciTech Connect (OSTI)

    Ian McKirdy

    2011-07-01

    The U.S. Department of Energy (DOE) has selected the high temperature gas-cooled reactor (HTGR) design for the Next Generation Nuclear Plant (NGNP) Project. The NGNP will demonstrate the use of nuclear power for process heat, hydrogen and electricity production. The reactor will be graphite moderated with helium as the primary coolant and may be either prismatic or pebble-bed. Although, final design features have not yet been determined. Research and Development (R&D) activities are proceeding on those known plant systems to mature the technology, codify the materials for specific applications, and demonstrate the component and system viability in NGNP relevant and integrated environments. Collectively these R&D activities serve to reduce the project risk and enhance the probability of on-budget, on-schedule completion and NRC licensing. As the design progresses, in more detail, toward final design and approval for construction, selected components, which have not been used in a similar application, in a relevant environment nor integrated with other components and systems, must be tested to demonstrate viability at reduced scales and simulations prior to full scale operation. This report and its R&D TDRMs present the path forward and its significance in assuring technical readiness to perform the desired function by: Choreographing the integration between design and R&D activities; and proving selected design components in relevant applications.

  2. Evaluation of HEPA filter service life

    SciTech Connect (OSTI)

    Fretthold, J.K.; Stithem, A.R.

    1997-07-14

    Rocky Flats Environmental Technology Site (RFETS), has approximately 10,000 High Efficiency Particulate Air (HEPA) Filters installed in a variety of filter plenums. These ventilation/filtration plenum systems are used to control the release of airborne particulate contaminates to the environment during normal operations and potential accidents. This report summarizes the results of destructive and non-destructive tests on HEPA filters obtained from a wide variety of ages and service conditions. These tests were performed to determine an acceptable service life criteria for HEPA filters used at Rocky Flats Environmental Technology Site (RFETS). A total of 140 filters of various ages (1972 to 1996) and service history (new, aged unused, used) were tested. For the purpose of this report, filter age from manufacture date/initial test date to the current sample date was used, as opposed to the actual time a filter was installed in an operating system.

  3. Idaho Nuclear Technology and Engineering Center (INTEC) (formerly ICPP) ash reutilization study

    SciTech Connect (OSTI)

    Langenwalter, T.; Pettet, M.; Ochoa, R.; Jensen, S.

    1998-05-01

    Since 1984, the coal-fired plant at the Idaho Nuclear Technology and Engineering Center (INTEC, formerly Idaho Chemical Processing Plant) has been generating fly ash at a rate of approximately 1,000 tons per year. This ash is hydrated and placed in an ash bury pit near the coal-fired plant. The existing ash bury pit will be full in less than 1 year at its present rate of use. A conceptual design to build a new ash bury pit was completed, and the new pit is estimated to cost $1.7 million. This report evaluates ash reutilization alternatives that propose to eliminate this waste stream and save the $1.7 million required to build a new pit. The alternatives include using ash for landfill day cover, concrete admixture, flowable fill, soil stabilization, waste remediation, and carbon recovery technology. Both physical and chemical testing, under the guidance of the American Society for Testing and Materials, have been performed on ash from the existing pit and from different steps within the facility`s processes. The test results have been evaluated, compared to commercial ash, and are discussed as they relate to reutilization alternatives. This study recommends that the ash be used in flowable fill concrete for Deactivation and Demolition work at the Idaho National Engineering and Environmental Laboratory.

  4. Developing Effective Continuous On-Line Monitoring Technologies to Manage Service Degradation of Nuclear Power Plants

    SciTech Connect (OSTI)

    Meyer, Ryan M.; Ramuhalli, Pradeep; Bond, Leonard J.; Cumblidge, Stephen E.

    2011-09-30

    Recently, there has been increased interest in using prognostics (i.e, remaining useful life (RUL) prediction) for managing and mitigating aging effects in service-degraded passive nuclear power reactor components. A vital part of this philosophy is the development of tools for detecting and monitoring service-induced degradation. Experience with in-service degradation has shown that rapidly-growing cracks, including several varieties of stress corrosion cracks (SCCs), can grow through a pipe in less than one fuel outage cycle after they initiate. Periodic inspection has limited effectiveness at detecting and managing such degradation requiring a more versatile monitoring philosophy. Acoustic emission testing (AET) and guided wave ultrasonic testing (GUT) are related technologies with potential for on-line monitoring applications. However, harsh operating conditions within NPPs inhibit the widespread implementation of both technologies. For AET, another hurdle is the attenuation of passive degradation signals as they travel though large components, relegating AET to targeted applications. GUT is further hindered by the complexity of GUT signatures limiting its application to the inspection of simple components. The development of sensors that are robust and inexpensive is key to expanding the use of AET and GUT for degradation monitoring in NPPs and improving overall effectiveness. Meanwhile, the effectiveness of AET and GUT in NPPs can be enhanced through thoughtful application of tandem AET-GUT techniques.

  5. Cordierite silicon nitride filters. Final report

    SciTech Connect (OSTI)

    Sawyer, J.; Buchan, B.; Duiven, R.; Berger, M.; Cleveland, J.; Ferri, J.

    1992-02-01

    The objective of this project was to develop a silicon nitride based crossflow filter. This report summarizes the findings and results of the project. The project was phased with Phase I consisting of filter material development and crossflow filter design. Phase II involved filter manufacturing, filter testing under simulated conditions and reporting the results. In Phase I, Cordierite Silicon Nitride (CSN) was developed and tested for permeability and strength. Target values for each of these parameters were established early in the program. The values were met by the material development effort in Phase I. The crossflow filter design effort proceeded by developing a macroscopic design based on required surface area and estimated stresses. Then the thermal and pressure stresses were estimated using finite element analysis. In Phase II of this program, the filter manufacturing technique was developed, and the manufactured filters were tested. The technique developed involved press-bonding extruded tiles to form a filter, producing a monolithic filter after sintering. Filters manufactured using this technique were tested at Acurex and at the Westinghouse Science and Technology Center. The filters did not delaminate during testing and operated and high collection efficiency and good cleanability. Further development in areas of sintering and filter design is recommended.

  6. October 2006, Report of the ADVANCED NUCLEAR TRANSFORMATION TECHNOLOGY SUBCOMMITTEE of the NUCLEAR ENERGY RESEARCH ADVISORY COMMITTEE

    Broader source: Energy.gov [DOE]

    The Global Nuclear Energy Partnership (GNEP) program is still evolving. Since our report of March 22, 2006 the DOE has sought to gauge industry interest in participation in the program from its...

  7. Basis for Section 3116 Determination for the Idaho Nuclear Technology and Engineering Center Tank Farm Facility at the Idaho National Laboratory

    Office of Environmental Management (EM)

    NE-ID-11226 Revision 0 Basis for Section 3116 Determination for the Idaho Nuclear Technology and Engineering Center Tank Farm Facility November 2006 DOE/NE-ID-11226 Revision 0 Basis for Section 3116 Determination for the Idaho Nuclear Technology and Engineering Center Tank Farm Facility November 2006 ii CONTENTS ACRONYMS.............................................................................................................................................. vii 1. INTRODUCTION AND

  8. Nuclear Deployment Scorecards | Department of Energy

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

    Initiatives Nuclear Reactor Technologies Nuclear Deployment Scorecards Nuclear Deployment Scorecards April 28, 2016 Quarterly Nuclear Deployment Scorecard - April 2016 News ...

  9. Calcined Waste Storage at the Idaho Nuclear Technology and Engineering Center

    SciTech Connect (OSTI)

    Staiger, M. Daniel, Swenson, Michael C.

    2011-09-01

    This comprehensive report provides definitive volume, mass, and composition (chemical and radioactivity) of calcined waste stored at the Idaho Nuclear Technology and Engineering Center. Calcine composition data are required for regulatory compliance (such as permitting and waste disposal), future treatment of the caline, and shipping the calcine to an off-Site-facility (such as a geologic repository). This report also contains a description of the calcine storage bins. The Calcined Solids Storage Facilities (CSSFs) were designed by different architectural engineering firms and built at different times. Each CSSF has a unique design, reflecting varying design criteria and lessons learned from historical CSSF operation. The varying CSSF design will affect future calcine retrieval processes and equipment. Revision 4 of this report presents refinements and enhancements of calculations concerning the composition, volume, mass, chemical content, and radioactivity of calcined waste produced and stored within the CSSFs. The historical calcine samples are insufficient in number and scope of analysis to fully characterize the entire inventory of calcine in the CSSFs. Sample data exist for all the liquid wastes that were calcined. This report provides calcine composition data based on liquid waste sample analyses, volume of liquid waste calcined, calciner operating data, and CSSF operating data using several large Microsoft Excel (Microsoft 2003) databases and spreadsheets that are collectively called the Historical Processing Model. The calcine composition determined by this method compares favorably with historical calcine sample data.

  10. Technology

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

    - Sandia Energy Energy Search Icon Sandia Home Locations Contact Us Employee Locator Energy & Climate Secure & Sustainable Energy Future Stationary Power Energy Conversion Efficiency Solar Energy Wind Energy Water Power Supercritical CO2 Geothermal Natural Gas Safety, Security & Resilience of the Energy Infrastructure Energy Storage Nuclear Power & Engineering Grid Modernization Battery Testing Nuclear Fuel Cycle Defense Waste Management Programs Advanced Nuclear Energy Nuclear

  11. Observations on A Technology Roadmap for Generation IV Nuclear Energy Systems: Technical Roadmap Report

    Broader source: Energy.gov [DOE]

    The development of advanced nuclear energy systems in the U.S. will depend greatly on the continued success of currently operating light water nuclear power plants and the ordering of new...

  12. Evaluating the use of PAO (4 cSt polyalphaoelfin) oil instead of DOP (di-octyl phthalate) oil for measuring the aerosol capture of nuclear canister filters

    SciTech Connect (OSTI)

    Moore, Murray E.

    2014-07-18

    This document details the distinction between using PAO (4 cSt polyalphaoelfin) oil instead of DOP (di-octyl phthalate) oil for measuring the aerosol capture of filters. This document is developed to justify the use of PAO rather than DOP for evaluating the performance of filters in the SAVY 4000 and Hagan containers. The design criteria (Anderson et al, 2012) for purchasing SAVY 4000 containers and the Safety Analysis Report for the SAVY 4000 Container Series specified that the filter must “capture greater than 99.97% of 0.45 μm mean diameter dioctyl phthalate (DOP) aerosol at the rated flow with a DOP concentration of 65±15 micrograms per liter.”This corresponds to a leakage percent of 0.03% (3.0x10-2). The density of DOP oil is 985 kg/m3 and the density of PAO oil is 819 kg/m3. ATI Test Inc measured the mass mean diameter of aerosol distributions produced by a single Laskin type III-A nozzle operating at a 20 psig air pressure as 0.563 μm for DOP oil and 0.549 μm for PAO oil. (See Appendix A.) For both types of oil in this document, the single fiber method calculated the leakage percent to be 4.4x10-5 for DOP oil and 4.7x10-5 for PAO oil. Although the percent error between these two quantities is 7.7%, these calculated leakage percent values are more than two orders of magnitude less than the criterion specified in the SAVY canister SAR. As a point of reference, the photometer used to measure the SAVY canister filter performance cannot resolve values for the leakage percent below 1.0x10-5. Additionally, over a range of particle sizes from 0.01 μm to 3.0 μm, there was less than 4.0x10-5 error between the calculated filter efficiency for the two types of oil at any particular particle size diameter. In conclusion, the difference between using DOP and PAO for testing SAVY canister filters is of inconsequential concern.

  13. Ceramic Particulate Filters | Department of Energy

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

    Poster presentation at the 2007 Diesel Engine-Efficiency & Emissions Research Conference (DEER 2007). 13-16 August, 2007, Detroit, Michigan. Sponsored by the U.S. Department of Energy's (DOE) Office of FreedomCAR and Vehicle Technologies (OFCVT). PDF icon deer07_yonushonis.pdf More Documents & Publications Durability of Diesel Engine Particulate Filters Durability of Diesel Engine Particulate Filters Durability of Diesel Engine Particulate Filters

  14. nuclear

    National Nuclear Security Administration (NNSA)

    2%2A en U.S-, Japan Exchange Best Practices on Nuclear Emergency Response http:nnsa.energy.govmediaroompressreleasesu.s-japan-exchange-best-practices-nuclear-emergency-respon...

  15. Nuclear Test Scenarios for Discussion of On-Site Inspection Technologies

    SciTech Connect (OSTI)

    Sweeney, J J; Hawkins, W

    2009-03-13

    The purpose of the ISS OSI Invited Meeting being held in Vienna March 24-27, 2009 is to obtain a better understanding of the phenomenology of underground nuclear explosions for On-Site Inspection (OSI) purposes. In order to focus the technology discussions, we have developed two very general scenarios, or models, of underground nuclear test configurations and phenomena that will help us explore the application of OSI methodologies and techniques. The scenarios describe testing environments, operations, logistics, equipment, and facilities that might be used in conducting an underground nuclear test. One scenario involves emplacement of a nuclear device into a vertical borehole in an area with relatively flat terrain; the other involves emplacement within a tunnel (horizontally) in an area with mountainous terrain. Vertical borehole geometry The example for this scenario is an intermediate yield nuclear explosion carried out in a flat desert area. The ground was cleared and smoothed over a 200 X 200 m fenced area for operational support activities, access to the borehole, and in order to place a few structures to house diagnostics equipment and control functions. Power lines were provided for local electrical power. The vertical emplacement borehole was 2 m in diameter and bored to a depth of 350 m. The emplacement hole was lined with steel pipe in order to keep the hole open and to avoid cave-ins during emplacement of the nuclear device. Emplacement was above the local water table, and the top of the saturation zone is about 30 m below the bottom of the emplacement hole. The detonation point was at a depth of 340 m. All of the rock material removed while drilling the borehole was removed to another place. Diagnostics and control for the test were relatively simple: about 2 dozen high capacity coaxial cables feed from the down hole instruments to the surface and then about 100 m laterally to a diagnostics trailer. Two strong steel cables were used to emplace the device and diagnostic instruments and to support the down hole cables. The borehole was stemmed after the device was emplaced. The stemming material was relatively simple: the hole was backfilled with sand or gravel about 20-30 m above the nuclear experiment package, a grouted plug about 3 m thick is added, and the hole backfilled with a mixture of sand and gravel to the surface. After the test, the testing party removed all structures and power lines and covered the top of the borehole with a small building. Geologic environment before the test--The geology for the test consists of flat-lying alluvium and tuff, with 50 m of poorly consolidated alluvium near the surface and moderately welded tuff from 50 m depth to 50 m below the bottom of the hole. The upper tuff is underlain by a densely welded tuff unit, with basement Paleozoic sedimentary rock beginning at a depth of about 1000 m. The tuff is intact with a few fractures. There are no known faults located within 500 m of the borehole. Alteration of the underground environment--The blast created a spherical or near spherical cavity with a lens of vitrified material at the bottom. There are several zones surrounding the detonation point with decreasing levels of rock damage. The zones are: (1) the crushed zone (several tens of meters)where the rock has lost all prior integrity; (2) the fractured zone (out to a couple of hundred meters) characterized by radial and concentric fissures; and (3) the zone of irreversible strain (out to a couple of thousand meters) with local media deformation. A collapse chimney formed one hour after the detonation, in which overlying material fell into the explosion cavity. This chimney zone reached up to within 50 m of the surface and a small apical void formed (10 m high and 80 m in diameter) at the top of the rubble chimney. The rubble chimney is dry and density is about 20% less than the surrounding intact rock. Alteration at the surface--No surface depression formed, but there is significant 'fluffing' of the surface soil from the effects of the initial shock wave. A few radial

  16. February 2004, Report of the ADVANCED NUCLEAR TRANSFORMATION TECHNOLOGY SUBCOMMITTEE of the NUCLEAR ENERGY RESEARCH ADVISORY COMMITTEE

    Broader source: Energy.gov [DOE]

    The ANTT Subcommittee of NERAC met February 26th and 27th (S. Pillon absent) to begin a review of the potential role of transmutation technologies in increasing the capacity of the geological...

  17. Maintaining a Technology-Neutral Approach to Hydrogen Production Process Development through Conceptual Design of the Next Generation Nuclear Plant

    SciTech Connect (OSTI)

    Michael W. Patterson

    2008-05-01

    The Next Generation Nuclear Plant (NGNP) project was authorized in the Energy Policy Act of 2005 (EPAct), tasking the U.S. Department of Energy (DOE) with demonstrating High Temperature Gas-Cooled Reactor (HTGR) technology. The demonstration is to include the technical, licensing, operational, and commercial viability of HTGR technology for the production of electricity and hydrogen. The Nuclear Hydrogen Initiative (NHI), a component of the DOE Hydrogen Program managed by the Office of Nuclear Energy, is also investigating multiple approaches to cost effective hydrogen production from nuclear energy. The objective of NHI is development of the technology and information basis for a future decision on commercial viability. The initiatives are clearly intertwined. While the objectives of NGNP and NHI are generally consistent, NGNP has progressed to the project definition phase and the project plan has matured. Multiple process applications for the NGNP require process heat, electricity and hydrogen in varied combinations and sizes. Coupling these processes to the reactor in multiple configurations adds complexity to the design, licensing and demonstration of both the reactor and the hydrogen production process. Commercial viability of hydrogen production may depend on the specific application and heat transport configuration. A component test facility (CTF) is planned by the NGNP to support testing and demonstration of NGNP systems, including those for hydrogen production, in multiple configurations. Engineering-scale demonstrations in the CTF are expected to start in 2012 to support scheduled design and licensing activities leading to subsequent construction and operation. Engineering-scale demonstrations planned by NHI are expected to start at least two years later. Reconciliation of these schedules is recommended to successfully complete both initiatives. Hence, closer and earlier integration of hydrogen process development and heat transport systems is sensible. For integration purposes, an analysis comparing the design, cost and schedule impact of maintaining a technology neutral approach through conceptual design or making an early hydrogen process technology selection was performed. Early selection does not specifically eliminate a technology, but rather selects the first hydrogen technology for demonstration. A systems-engineering approach was taken to define decision-making criteria for selecting a hydrogen technology. The relative technical, cost and schedule risks of each approach were analyzed and risk mitigation strategies were recommended, including provisions to maintain close collaboration with the NHI. The results of these analyses are presented here.

  18. Technologies

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

    Technologies Technologies Scientists and engineers at Los Alamos have developed a variety of advanced technologies that anticipate-affect, detect, and neutralize & mitigate all types of explosive threats. v Technologies Since its inception in 1943, Los Alamos National Laboratory has been a driving force in explosives science. Scientists and engineers at Los Alamos have developed a variety of advanced technologies that anticipate, detect, and mitigate all types of explosive threats. ANDE:

  19. Technology for Brayton-cycle space powerplants using solar and nuclear energy

    SciTech Connect (OSTI)

    English, R.E.

    1986-02-01

    Brayton-cycle gas turbines have the potential to use either solar heat or nuclear reactors to generate from tens of kilowatts to tens of megawatts of power in space, all this from a single technology for the power-generating system. Their development for solar-energy dynamic power generation for the space station could be the first step in an evolution of such powerplants for a very wide range of applications. At the low power level of only 10 kWe, a power-generating system has already demonstrated overall efficiency of 0.29 and operated for 38,000 hr. Tests of improved components show that, if installed in the power-generating system, these components would raise that efficiency to 0.32; this efficiency is twice that so far demonstrated by any alternate concept, a characteristic especially important for solar power systems. Because of this high efficiency, solar-heat Brayton-cycle power generators offer the potential to increase power per unit of solar-collector area to levels exceeding four times that from photovoltaic powerplants based on present technology for silicon solar cells. For the heat source, paraboloidal mirrors have been assembled from sectors here on Earth. One mirror, 1.5-m diameter, had a standard error for its surface of only 1 arc-min and a specific mass of only 1.3 kg/m 2. A heavier mirror (nearly 5 kg/m{sup 2}), assembled from 12 sectors, had a standard surface error of 3 arc-min but was 6 m in diameter. Either of these mirrors is sufficiently accurate for use with the Brayton cycle, but the techniques for actually assembling large mirrors in space must yet be worked out. For use during the shadow period of a low Earth orbit (LEO), heat could be stored in LiF, a salt that melts at 1121 K (1558{degrees}F) and whose latent heat of fusion exceeds 1 MJ/kg. Because of the prior experience with its fabrication and of its tolerance of the thermal cycling in LEO, Nb-1Zr was selected to contain the LiF.

  20. Filter systems for IGCC applications

    SciTech Connect (OSTI)

    Bevan, S.; Gieger, R.; Sobel, N.; Johnson, D.

    1995-11-01

    The objectives of this program were to identify metallic filter medium to be utilized in the Integrated Gasification Combined Cycle process (IGCC). In IGCC processes utilizing high efficiency desulfurizing technology, the traditional corrosion attack, sulfidation, is minimized so that metallic filters are viable alternatives over ceramic filters. Tampa Electric Company`s Polk Power Station is being developed to demonstrate Integrated Gasification Combined Cycle technology. The Pall Gas Solid Separation (GSS) System is a self cleaning filtration system designed to remove virtually all particulate matter from gas streams. The heart of the system is the filter medium used to collect the particles on the filter surface. The medium`s filtration efficiency, uniformity, permeability, voids volume, and surface characteristics are all important to establishing a permeable permanent cake. In-house laboratory blowback tests, using representative full scale system particulate, were used to confirm the medium selection for this project. Test elements constructed from six alloys were supplied for exposure tests: PSS 310SC (modified 310S alloy); PSS 310SC heat treated; PSS 310SC-high Cr; PSS 310SC-high Cr heat treated; PSS Hastelloy X; and PSS Hastelloy X heat treated.

  1. Preoperational Subsurface Conditions at the Idaho Nuclear Technology and Engineering Center Service Wastewater Discharge Facility

    SciTech Connect (OSTI)

    Ansley, Shannon L.

    2002-02-20

    The Idaho Nuclear Technology and Engineering Center (INTEC) Service Wastewater Discharge Facility replaces the existing percolation ponds as a disposal facility for the INTEC Service Waste Stream. A preferred alternative for helping decrease water content in the subsurface near INTEC, closure of the existing ponds is required by the INTEC Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) Record of Decision (ROD) for Waste Area Group 3 Operable Unit 3-13 (DOE-ID 1999a). By August 2002, the replacement facility was constructed approximately 2 miles southwest of INTEC, near the Big Lost River channel. Because groundwater beneath the Idaho National Engineering and Environmental Laboratory (INEEL) is protected under Federal and State of Idaho regulations from degradation due to INEEL activities, preoperational data required by U.S. Department of Energy (DOE) Order 5400.1 were collected. These data include preexisting physical, chemical, and biological conditions that could be affected by the discharge; background levels of radioactive and chemical components; pertinent environmental and ecological parameters; and potential pathways for human exposure or environmental impact. This document presents specific data collected in support of DOE Order 5400.1, including: four quarters of groundwater sampling and analysis of chemical and radiological parameters; general facility description; site specific geology, stratigraphy, soils, and hydrology; perched water discussions; and general regulatory requirements. However, in order to avoid duplication of previous information, the reader is directed to other referenced publications for more detailed information. Documents that are not readily available are compiled in this publication as appendices. These documents include well and borehole completion reports, a perched water evaluation letter report, the draft INEEL Wellhead Protection Program Plan, and the Environmental Checklist.

  2. Guidance for Deployment of Mobile Technologies for Nuclear Power Plant Field Workers

    Broader source: Energy.gov [DOE]

    This report is a guidance document prepared for the benefit of commercial nuclear power plants’ (NPPs) supporting organizations and personnel who are considering or undertaking deployment of mobile...

  3. HEPA filter dissolution process

    DOE Patents [OSTI]

    Brewer, K.N.; Murphy, J.A.

    1994-02-22

    A process is described for dissolution of spent high efficiency particulate air (HEPA) filters and then combining the complexed filter solution with other radioactive wastes prior to calcining the mixed and blended waste feed. The process is an alternate to a prior method of acid leaching the spent filters which is an inefficient method of treating spent HEPA filters for disposal. 4 figures.

  4. Hepa filter dissolution process

    DOE Patents [OSTI]

    Brewer, Ken N. (Arco, ID); Murphy, James A. (Idaho Falls, ID)

    1994-01-01

    A process for dissolution of spent high efficiency particulate air (HEPA) filters and then combining the complexed filter solution with other radioactive wastes prior to calcining the mixed and blended waste feed. The process is an alternate to a prior method of acid leaching the spent filters which is an inefficient method of treating spent HEPA filters for disposal.

  5. Recirculating electric air filter

    DOE Patents [OSTI]

    Bergman, Werner

    1986-01-01

    An electric air filter cartridge has a cylindrical inner high voltage eleode, a layer of filter material, and an outer ground electrode formed of a plurality of segments moveably connected together. The outer electrode can be easily opened to remove or insert filter material. Air flows through the two electrodes and the filter material and is exhausted from the center of the inner electrode.

  6. Recirculating electric air filter

    DOE Patents [OSTI]

    Bergman, W.

    1985-01-09

    An electric air filter cartridge has a cylindrical inner high voltage electrode, a layer of filter material, and an outer ground electrode formed of a plurality of segments moveably connected together. The outer electrode can be easily opened to remove or insert filter material. Air flows through the two electrodes and the filter material and is exhausted from the center of the inner electrode.

  7. Proceedings of the 21st Seismic Research Symposium: Technologies for Monitoring The Comprehensive Nuclear Test-Ban Treaty

    SciTech Connect (OSTI)

    Warren, N. Jill

    1999-09-21

    These proceedings contain papers prepared for the 21st Seismic Research Symposium: Technologies for Monitoring The Comprehensive Nuclear-Test-Ban Treaty, held 21-24 September 1999 in Las Vegas, Nevada. These papers represent the combined research related to ground-based nuclear explosion monitoring funded by the National Nuclear Security Administration (NNSA), Defense Threat Reduction Agency (DTRA), Air Force Technical Applications Center (AFTAC), Department of Defense (DoD), the Comprehensive Nuclear-Test-Ban Treaty Organization (CTBTO), and other invited sponsors. The scientific objectives of the research are to improve the United States capability to detect, locate, and identify nuclear explosions. The purpose of the meeting is to provide the sponsoring agencies, as well as potential users, an opportunity to review research accomplished during the preceding year and to discuss areas of investigation for the coming year. For the researchers, it provides a forum for the exchange of scientific information toward achieving program goals, and an opportunity to discuss results and future plans. Paper topics include: seismic regionalization and calibration; detection and location of sources; wave propagation from source to receiver; the nature of seismic sources, including mining practices; hydroacoustic, infrasound, and radionuclide methods; on-site inspection; and data processing.

  8. Magnetic Centrifugal Mass Filter Abraham J. Fetterman and Nathaniel J.

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

    Fisch | Princeton Plasma Physics Lab Magnetic Centrifugal Mass Filter Abraham J. Fetterman and Nathaniel J. Fisch This invention is of a magnetic centrifugal mass filter that can separate ions of different mass or ions of different energies into separate streams. The filter, which uses both the centrifugal and magnetic confinement of ions, can be used to separate radioactive fission products from nuclear waste or from spent nuclear fuel in a nonproliferative manner. No.: M-818

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

    SciTech Connect (OSTI)

    Bunch, Kyle J.; Jones, Anthony M.; Ramuhalli, Pradeep; Benz, Jacob M.; Denlinger, Laura Schmidt

    2014-05-04

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

  10. ARRANGEMENT FOR REPLACING FILTERS

    DOE Patents [OSTI]

    Blomgren, R.A.; Bohlin, N.J.C.

    1957-08-27

    An improved filtered air exhaust system which may be continually operated during the replacement of the filters without the escape of unfiltered air is described. This is accomplished by hermetically sealing the box like filter containers in a rectangular tunnel with neoprene covered sponge rubber sealing rings coated with a silicone impregnated pneumatic grease. The tunnel through which the filters are pushed is normal to the exhaust air duct. A number of unused filters are in line behind the filters in use, and are moved by a hydraulic ram so that a fresh filter is positioned in the air duct. The used filter is pushed into a waiting receptacle and is suitably disposed. This device permits a rapid and safe replacement of a radiation contaminated filter without interruption to the normal flow of exhaust air.

  11. Electrically-Assisted Diesel Particulate Filter Regeneration | Department

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

    of Energy 2 DOE Hydrogen and Fuel Cells Program and Vehicle Technologies Program Annual Merit Review and Peer Evaluation Meeting PDF icon pm041_lance_2012_o.pdf More Documents & Publications Substrate Studies of an Electrically-Assisted Diesel Particulate Filter Electrically-Assisted Diesel Particulate Filter Regeneration Durability of Diesel Engine Particulate Filters (Agreement ID:10461)

  12. Coupling Ocean Thermal Energy Conversion technology (OTEC) with nuclear power plants

    SciTech Connect (OSTI)

    Goldstein, M.K.; Rezachek, D.; Chen, C.S.

    1981-01-01

    The prospects of utilizing an OTEC Related Bottoming Cycle to recover waste heat generated by a large nuclear (or fossil) power plant are examined. With such improvements, OTEC can become a major energy contributor. 12 refs.

  13. Technological Opportunities to Increase the Proliferation Resistance of Global Civilian Nuclear Power Systems (TOPS)

    Broader source: Energy.gov [DOE]

    In 1999 the U.S. Department of Energy (DOE) formed a special task force, called the TOPS Task Force, from the Nuclear Energy Research Advisory Committee (NERAC) to identify near- and long-term...

  14. Technolog

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

    Research in Science and Technolog y Sandia pushes frontiers of knowledge to meet the nation's needs, today and tomorrow Sandia National Laboratories' fundamental science and technology research leads to greater understanding of how and why things work and is intrinsic to technological advances. Basic research that challenges scientific assumptions enables the nation to push scientific boundaries. Innovations and breakthroughs produced at Sandia allow it to tackle critical issues, from

  15. Technology

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

    Technology /newsroom/_assets/images/s-icon.png Technology Delivering science to the marketplace through commercialization, spinoffs and industry partnerships. Health Space Computing Energy Earth Materials Science Technology The Lab All Glen Wurden in the stellarator's vacuum vessel during camera installation in 2014. Innovative imaging systems on the Wendelstein 7-X bring steady-state fusion energy closer to reality Innovative new imaging systems designed at Los Alamos are helping physicists

  16. Department of Energy Issues Requests for Applications for Nuclear...

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

    Engineering, Electrical Engineering, Chemistry, Health Physics, Nuclear Materials ... also included, such as Nuclear Power Technology, Nuclear Maintenance Technology, ...

  17. Technolog

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

    Research in Science and Technolog y Sandia pushes frontiers of knowledge to meet the nation's needs, today and tomorrow ... Basic research that challenges scientific assumptions ...

  18. DOE Announces Strategic Engineering and Technology Roadmap for Cleanup of Cold War Era Nuclear Waste

    Broader source: Energy.gov [DOE]

    WASHINGTON, DC - The U.S. Department of Energy (DOE) today released an Engineering and Technology Roadmap (Roadmap), which details initiatives aimed at reducing the technical risks and...

  19. Rigid porous filter

    DOE Patents [OSTI]

    Chiang, Ta-Kuan; Straub, Douglas L.; Dennis, Richard A.

    2000-01-01

    The present invention involves a porous rigid filter including a plurality of concentric filtration elements having internal flow passages and forming external flow passages there between. The present invention also involves a pressure vessel containing the filter for the removal of particulates from high pressure particulate containing gases, and further involves a method for using the filter to remove such particulates. The present filter has the advantage of requiring fewer filter elements due to the high surface area-to-volume ratio provided by the filter, requires a reduced pressure vessel size, and exhibits enhanced mechanical design properties, improved cleaning properties, configuration options, modularity and ease of fabrication.

  20. Filter type gas sampler with filter consolidation

    DOE Patents [OSTI]

    Miley, H.S.; Thompson, R.C.; Hubbard, C.W.; Perkins, R.W.

    1997-03-25

    Disclosed is an apparatus for automatically consolidating a filter or, more specifically, an apparatus for drawing a volume of gas through a plurality of sections of a filter, where after the sections are subsequently combined for the purpose of simultaneously interrogating the sections to detect the presence of a contaminant. 5 figs.

  1. Filter type gas sampler with filter consolidation

    DOE Patents [OSTI]

    Miley, Harry S.; Thompson, Robert C.; Hubbard, Charles W.; Perkins, Richard W.

    1997-01-01

    Disclosed is an apparatus for automatically consolidating a filter or, more specifically, an apparatus for drawing a volume of gas through a plurality of sections of a filter, whereafter the sections are subsequently combined for the purpose of simultaneously interrogating the sections to detect the presence of a contaminant.

  2. The use of filtered bags to increase waste payload capacity

    SciTech Connect (OSTI)

    Dustin, D.F.; Thorp, D.T.; Rivera, M.A.

    1998-03-03

    For the past few years, the Department of Energy has favored the direct disposal of low plutonium content residue materials from Rocky Flats rather than engage in expensive and time consuming plutonium recovery operations. One impediment to direct disposal has been the wattage limit imposed by the Waste Isolation Pilot Plant on hydrogenous materials such as combustibles and sludges. The issue of concern is the radiolytic generation and accumulation of hydrogen and other explosive gases in waste containers. The wattage limits that existed through 1996 restricted the amount of plutonium bearing hydrogenous materials that could be packaged in a WIPP bound waste drum to only a fraction of the capacity of a drum. Typically, only about one kilogram of combustible residue could be packaged in a waste drum before the wattage limit was exceeded resulting in an excessively large number of drums to be procured, stored, shipped, and interred. The Rocky Flats Environmental Technology Site has initiated the use of filtered plastic bags (called bag-out bags) used to remove transuranic waste materials from glove box lines. The bags contain small, disk like HEPA filters which are effective in containing radioactively contaminated particulate material but allow for the diffusion of hydrogen gas. Used in conjunction with filtered 55 gallon drums, filtered bag-out bags were pursued as a means to increase the allowable wattage limits for selected residue materials. In February 1997, the Nuclear Regulatory Commission approved the use of filtered bag-out bags for transuranic waste materials destined for WIPP. The concomitant increase in wattage limits now allows for approximately four times the payload per waste drum for wattage limited materials.

  3. Technical task plan for testing filter box sorbent-paint filter test

    SciTech Connect (OSTI)

    Kilpatrick, L.L.

    1993-09-01

    At the Savannah River Plant, High Level Waste Engineering (HLWE) asked Interim Waste Technology (IWT) to choose and test a sorbent to add to the ITP filter box that meets the EPA requirement for land disposal of containerized liquid hazardous wastes per Paint Filter Liquids (PFL) test method 9095. This report outlines the process to be used in accomplishing this task.

  4. Finding of no significant impact. Consolidation and interim storage of special nuclear material at Rocky Flats Environmental Technology Site

    SciTech Connect (OSTI)

    1995-06-01

    The Department of Energy (DOE) has prepared an environmental assessment (EA), DOE/EA -- 1060, for the consolidation, processing, and interim storage of Category I and II special nuclear material (SNM) in Building 371 at the Rocky Flats Environmental Technology Site (hereinafter referred to as Rocky Flats or Site), Golden, Colorado. The scope of the EA included alternatives for interim storage including the no action alternative, the construction of a new facility for interim storage at Rocky Flats, and shipment to other DOE facilities for interim storage.

  5. MST Filterability Tests

    SciTech Connect (OSTI)

    Poirier, M. R.; Burket, P. R.; Duignan, M. R.

    2015-03-12

    The Savannah River Site (SRS) is currently treating radioactive liquid waste with the Actinide Removal Process (ARP) and the Modular Caustic Side Solvent Extraction Unit (MCU). The low filter flux through the ARP has limited the rate at which radioactive liquid waste can be treated. Recent filter flux has averaged approximately 5 gallons per minute (gpm). Salt Batch 6 has had a lower processing rate and required frequent filter cleaning. Savannah River Remediation (SRR) has a desire to understand the causes of the low filter flux and to increase ARP/MCU throughput. In addition, at the time the testing started, SRR was assessing the impact of replacing the 0.1 micron filter with a 0.5 micron filter. This report describes testing of MST filterability to investigate the impact of filter pore size and MST particle size on filter flux and testing of filter enhancers to attempt to increase filter flux. The authors constructed a laboratory-scale crossflow filter apparatus with two crossflow filters operating in parallel. One filter was a 0.1 micron Mott sintered SS filter and the other was a 0.5 micron Mott sintered SS filter. The authors also constructed a dead-end filtration apparatus to conduct screening tests with potential filter aids and body feeds, referred to as filter enhancers. The original baseline for ARP was 5.6 M sodium salt solution with a free hydroxide concentration of approximately 1.7 M.3 ARP has been operating with a sodium concentration of approximately 6.4 M and a free hydroxide concentration of approximately 2.5 M. SRNL conducted tests varying the concentration of sodium and free hydroxide to determine whether those changes had a significant effect on filter flux. The feed slurries for the MST filterability tests were composed of simple salts (NaOH, NaNO2, and NaNO3) and MST (0.2 – 4.8 g/L). The feed slurry for the filter enhancer tests contained simulated salt batch 6 supernate, MST, and filter enhancers.

  6. HEPA filter encapsulation

    DOE Patents [OSTI]

    Gates-Anderson, Dianne D.; Kidd, Scott D.; Bowers, John S.; Attebery, Ronald W.

    2003-01-01

    A low viscosity resin is delivered into a spent HEPA filter or other waste. The resin is introduced into the filter or other waste using a vacuum to assist in the mass transfer of the resin through the filter media or other waste.

  7. Filter service system

    DOE Patents [OSTI]

    Sellers, Cheryl L.; Nordyke, Daniel S.; Crandell, Richard A.; Tomlins, Gregory; Fei, Dong; Panov, Alexander; Lane, William H.; Habeger, Craig F.

    2008-12-09

    According to an exemplary embodiment of the present disclosure, a system for removing matter from a filtering device includes a gas pressurization assembly. An element of the assembly is removably attachable to a first orifice of the filtering device. The system also includes a vacuum source fluidly connected to a second orifice of the filtering device.

  8. Retrieval of Hanford Single Shell Nuclear Waste Tanks using Technologies Foreign and Domestic

    SciTech Connect (OSTI)

    EACKER, J.A.; GIBBONS, P.W.

    2003-01-01

    The Hanford Site is accelerating its SST retrieval mission. One aspect of this acceleration is the identification of new baseline retrieval technologies that can be applied to all tank conditions for salt & sludge wastes in both sound & leaking tanks.

  9. Supplying the nuclear arsenal: Production reactor technology, management, and policy, 1942--1992

    SciTech Connect (OSTI)

    Carlisle, R.P.; Zenzen, J.M.

    1994-01-01

    This book focuses on the lineage of America`s production reactors, those three at Hanford and their descendants, the reactors behind America`s nuclear weapons. The work will take only occasional sideways glances at the collateral lines of descent, the reactor cousins designed for experimental purposes, ship propulsion, and electric power generation. Over the decades from 1942 through 1992, fourteen American production reactors made enough plutonium to fuel a formidable arsenal of more than twenty thousand weapons. In the last years of that period, planners, nuclear engineers, and managers struggled over designs for the next generation of production reactors. The story of fourteen individual machines and of the planning effort to replace them might appear relatively narrow. Yet these machines lay at the heart of the nation`s nuclear weapons complex. The story of these machines is the story of arming the winning weapon, supplying the nuclear arms race. This book is intended to capture the history of the first fourteen production reactors, and associated design work, in the face of the end of the Cold War.

  10. Indestructible Ultra-filtration: Ceramic HEPA Filters - Energy Innovation

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

    Portal Building Energy Efficiency Building Energy Efficiency Advanced Materials Advanced Materials Find More Like This Return to Search Indestructible Ultra-filtration: Ceramic HEPA Filters Lawrence Livermore National Laboratory Contact LLNL About This Technology Technology Marketing Summary High Efficiency Particulate Air (HEPA) filters are widely used commercial products to remove airborne particulates from a gas stream in a gas process system or ventilation system. Filter life span is

  11. Technologies

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

    Matter and Technologies R&D activities towards a future cw LINAC at GSI Winfried Barth Matter and Technologies Super Heavy Nuclei International Symposium, Texas A & M University, College Station TX, USA, March 31 - April 02, 2015 W. Barth, R&D activities towards a future cw LINAC at GSI 2 R&D activities towards a future cw LINAC at GSI 1. Introduction 2. Status of the Unilac High Current Performance 3. Cavity Development 4. General linac layout 5. R&D approach 6. Status of

  12. Proceedings of the 2. MIT international conference on the next generation of nuclear power technology. Final report

    SciTech Connect (OSTI)

    1993-12-31

    The goal of the conference was to try to attract a variety of points of view from well-informed people to debate issues concerning nuclear power. Hopefully from that process a better understanding of what one should be doing will emerge. In organizing the conference lessons learned from the previous one were applied. A continuous effort was made to see to it that the arguments for the alternatives to nuclear power were given abundant time for presentation. This is ultimately because nuclear power is going to have to compete with all of the energy technologies. Thus, in discussing energy strategy all of the alternatives must be considered in a reasonable fashion. The structure the conference used has seven sessions. The first six led up to the final session which was concerned with what the future nuclear power strategy should be. Each session focused upon a question concerning the future. None of these questions has a unique correct answer. Rather, topics are addressed where reasonable people can disagree. In order to state some of the important arguments for each session`s question, the combination of a keynote paper followed by a respondent was used. The respondent`s paper is not necessarily included to be a rebuttal to the keynote; but rather, it was recognized that two people will look at a complex question with different shadings. Through those two papers the intention was to get out the most important arguments affecting the question for the session. The purpose of the papers was to set the stage for about an hour of discussion. The real product of this conference was that discussion.

  13. Technology, Safety and Costs of Decommissioning Nuclear Reactors At Multiple-Reactor Stations

    SciTech Connect (OSTI)

    Wittenbrock, N. G.

    1982-01-01

    Safety and cost information is developed for the conceptual decommissioning of large (1175-MWe) pressurized water reactors (PWRs) and large (1155-MWe) boiling water reactors {BWRs) at multiple-reactor stations. Three decommissioning alternatives are studied: DECON (immediate decontamination), SAFSTOR (safe storage followed by deferred decontamination), and ENTOMB (entombment). Safety and costs of decommissioning are estimated by determining the impact of probable features of multiple-reactor-station operation that are considered to be unavailable at a single-reactor station, and applying these estimated impacts to the decommissioning costs and radiation doses estimated in previous PWR and BWR decommissioning studies. The multiple-reactor-station features analyzed are: the use of interim onsite nuclear waste storage with later removal to an offsite nuclear waste disposal facility, the use of permanent onsite nuclear waste disposal, the dedication of the site to nuclear power generation, and the provision of centralized services. Five scenarios for decommissioning reactors at a multiple-reactor station are investigated. The number of reactors on a site is assumed to be either four or ten; nuclear waste disposal is varied between immediate offsite disposal, interim onsite storage, and immediate onsite disposal. It is assumed that the decommissioned reactors are not replaced in one scenario but are replaced in the other scenarios. Centralized service facilities are provided in two scenarios but are not provided in the other three. Decommissioning of a PWR or a BWR at a multiple-reactor station probably will be less costly and result in lower radiation doses than decommissioning an identical reactor at a single-reactor station. Regardless of whether the light water reactor being decommissioned is at a single- or multiple-reactor station: • the estimated occupational radiation dose for decommissioning an LWR is lowest for SAFSTOR and highest for DECON • the estimated cost of decommissioning a PWR is lowest for ENTOMB and highest for SAFSTOR • the estimated cost of decommissioning a BWR is lowest for OECON and highest for SAFSTOR. In all cases, SAFSTOR has the lowest occupational radiation dose and the highest cost.

  14. Developments of Spent Nuclear Fuel Pyroprocessing Technology at Idaho National Laboratory

    SciTech Connect (OSTI)

    Michael F. Simpson

    2012-03-01

    This paper summarizes research in used fuel pyroprocessing that has been published by Idaho National Laboratory over the last decade. It includes work done both on treatment of Experimental Breeder Reactor-II and development of advanced technology for potential scale-up and commercialization. Collaborations with universities and other laboratories is included in the cited work.

  15. Technology, safety, and costs of decommissioning reference nuclear research and test reactors. Appendices

    SciTech Connect (OSTI)

    Konzek, G.J.; Ludwick, J.D.; Kennedy, W.E. Jr.; Smith, R.I.

    1982-03-01

    Safety and Cost Information is developed for the conceptual decommissioning of two representative licensed nuclear research and test reactors. Three decommissioning alternatives are studied to obtain comparisons between costs (in 1981 dollars), occupational radiation doses, potential radiation dose to the public, and other safety impacts. The alternatives considered are: DECON (immediate decontamination), SAFSTOR (safe storage followed by deferred decontamination), and EMTOMB (entombment). The study results are presented in two volumes. Volume 2 (Appendices) contains the detailed data that support the results given in Volume 1, including unit-component data.

  16. Contactor/filter improvements

    DOE Patents [OSTI]

    Stelman, D.

    1988-06-30

    A contactor/filter arrangement for removing particulate contaminants from a gaseous stream is described. The filter includes a housing having a substantially vertically oriented granular material retention member with upstream and downstream faces, a substantially vertically oriented microporous gas filter element, wherein the retention member and the filter element are spaced apart to provide a zone for the passage of granular material therethrough. A gaseous stream containing particulate contaminants passes through the gas inlet means as well as through the upstream face of the granular material retention member, passing through the retention member, the body of granular material, the microporous gas filter element, exiting out of the gas outlet means. A cover screen isolates the filter element from contact with the moving granular bed. In one embodiment, the granular material is comprised of porous alumina impregnated with CuO, with the cover screen cleaned by the action of the moving granular material as well as by backflow pressure pulses. 6 figs.

  17. Filter vapor trap

    DOE Patents [OSTI]

    Guon, Jerold

    1976-04-13

    A sintered filter trap is adapted for insertion in a gas stream of sodium vapor to condense and deposit sodium thereon. The filter is heated and operated above the melting temperature of sodium, resulting in a more efficient means to remove sodium particulates from the effluent inert gas emanating from the surface of a liquid sodium pool. Preferably the filter leaves are precoated with a natrophobic coating such as tetracosane.

  18. ENDF/B-VII.1 Nuclear Data for Science and Technology: Cross Sections, Covariances, Fission Product Yields and Decay Data

    SciTech Connect (OSTI)

    G. Palmiotti

    2011-12-01

    The ENDF/B-VII.1 library is our latest recommended evaluated nuclear data file for use in nuclear science and technology applications, and incorporates advances made in the five years since the release of ENDF/B-VII.0. These advances focus on neutron cross sections, covariances, fission product yields and decay data, and represent work by the US Cross Section Evaluation Working Group (CSEWG) in nuclear data evaluation that utilizes developments in nuclear theory, modeling, simulation, and experiment. The principal advances in the new library are: (1) An increase in the breadth of neutron reaction cross section coverage, extending from 393 nuclides to 418 nuclides; (2) Covariance uncertainty data for 185 of the most important nuclides, as documented in companion papers in this edition; (3) R-matrix analyses of neutron reactions on light nuclei, including isotopes of He, Li, and Be; (4) Resonance parameter analyses at lower energies and statistical high energy reactions at higher energies for isotopes of F, Cl, K, Ti, V, Mn, Cr, Ni, Zr and W; (5) Modifications to thermal neutron reactions on fission products (isotopes of Mo, Tc, Rh, Ag, Cs, Nd, Sm, Eu) and neutron absorber materials (Cd, Gd); (6) Improved minor actinide evaluations for isotopes of U, Np, Pu, and Am (we are not making changes to the major actinides 235,238U and 239Pu at this point, except for delayed neutron data, and instead we intend to update them after a further period of research in experiment and theory), and our adoption of JENDL-4.0 evaluations for isotopes of Cm, Bk, Cf, Es, Fm, and some other minor actinides; (7) Fission energy release evaluations; (8) Fission product yield advances for fission-spectrum neutrons and 14 MeV neutrons incident on 239Pu; and (9) A new Decay Data sublibrary. Integral validation testing of the ENDF/B-VII.1 library is provided for a variety of quantities: For nuclear criticality, the VII.1 library maintains the generally-good performance seen for VII.0 for a wide range of MCNP simulations of criticality benchmarks, with improved performance coming from new structural material evaluations, especially for Ti, Mn, Cr, Zr and W. For Be we see some improvements although the fast assembly data appear to be mutually inconsistent. Actinide cross section updates are also assessed through comparisons of fission and capture reaction rate measurements in critical assemblies and fast reactors. We describe the cross section evaluations that have been updated for ENDF/B-VII.1 and the measured data and calculations that motivated the changes, and therefore this paper augments the ENDF/B-VII.0 publication [1].

  19. Linear phase compressive filter

    DOE Patents [OSTI]

    McEwan, Thomas E.

    1995-01-01

    A phase linear filter for soliton suppression is in the form of a laddered series of stages of non-commensurate low pass filters with each low pass filter having a series coupled inductance (L) and a reverse biased, voltage dependent varactor diode, to ground which acts as a variable capacitance (C). L and C values are set to levels which correspond to a linear or conventional phase linear filter. Inductance is mapped directly from that of an equivalent nonlinear transmission line and capacitance is mapped from the linear case using a large signal equivalent of a nonlinear transmission line.

  20. Linear phase compressive filter

    DOE Patents [OSTI]

    McEwan, T.E.

    1995-06-06

    A phase linear filter for soliton suppression is in the form of a laddered series of stages of non-commensurate low pass filters with each low pass filter having a series coupled inductance (L) and a reverse biased, voltage dependent varactor diode, to ground which acts as a variable capacitance (C). L and C values are set to levels which correspond to a linear or conventional phase linear filter. Inductance is mapped directly from that of an equivalent nonlinear transmission line and capacitance is mapped from the linear case using a large signal equivalent of a nonlinear transmission line. 2 figs.

  1. TIGER -- A technology to improve the delivery capability of nuclear bombs and the survivability of the delivery aircraft

    SciTech Connect (OSTI)

    1980-12-31

    The TIGER (Terminal guided and Extended-Range) Program was initiated in 1972 to study improved delivery capabilities for stockpiled tactical nuclear bombs. The Southeast Asia conflict fostered the development of air-delivered standoff conventional weapons utilizing terminal guidance systems. SNL initiated the TIGER program to determine if current nuclear bombs could be provided with a similarly accurate standoff capabilities. These conventional weapon delivery techniques, while allowing highly accurate attack, generally require entering the target area at high altitude to establish line of sight to the target. In parallel with the TIGER program, system studies analyzed this concept and showed marked improvement in aircraft and weapon survivability with moderate standoff (10--20 km) if low level deliveries (60 m) could be accomplished. As a result of this work, the TIGER program was redirected in early 1974 to demonstrate a standoff bomb with good accuracy (90 m CEP) when delivered from low flying aircraft. This program redirection resulted in the selection of an inertial guidance system to replace the earlier terminal guidance systems. This program was called the Extended-Range Bomb (ERB). In May 1974, a joint Air Force/DOE study identified the desirability of having a single tactical weapon which could be employed against either fixed, preselected targets, or mobile battlefield targets. Studies conducted on the ERB system showed that the inertially guided weapon could fly not only the standoff mission but also a return-to-target mission against the mobile battlefield targets whose locations are not known accurately enough to use a standoff delivery. The ERB program evolved from these initial investigations into an exploratory program to develop the hardware and demonstrate the technology required to fly standoff and return-to-target trajectories. The application of this technology in the form of field retrofit kits to the B61 bomb is called TIGER II.

  2. Retrieval Of Hanford's Single Shell Nuclear Waste Tanks Using Technologies Foreign And Domestic

    SciTech Connect (OSTI)

    Eacker, J. A.; Thompson, W. T.; Gibbons, P. W.

    2003-02-26

    Significant progress has been made on the Hanford single shell tank (SST) retrieval projects since they were initiated as part of the modified Hanford Federal Facility Agreement and Consent Order (Tri-party Agreement) in 2000. Four of the 149 SSTs at the U.S. Department of Energy (DOE) Office of River Protection (ORP) Hanford facility are being retrieved to meet Tri-Party Agreement commitments. An additional tank is being retrieved to demonstrate an alternate technical approach. As the Hanford Site transitions to an accelerated retrieval and closure mission, these methods will be the baseline methods for SST retrieval. The five SSTs are located within the Hanford 200- Area tank farms operated by CH2M HILL Hanford Group (CH2M HILL) for ORP. Included in this paper will be discussions on the technologies selected for retrieval of each tank; electrical resistance technologies that are being evaluated for ex-tank leak detection and monitoring; and the Cold Test Training Facility (CTTF) used for testing of and training on the different retrieval systems.

  3. Filter holder and gasket assembly for candle or tube filters

    DOE Patents [OSTI]

    Lippert, T.E.; Alvin, M.A.; Bruck, G.J.; Smeltzer, E.E.

    1999-03-02

    A filter holder and gasket assembly are disclosed for holding a candle filter element within a hot gas cleanup system pressure vessel. The filter holder and gasket assembly includes a filter housing, an annular spacer ring securely attached within the filter housing, a gasket sock, a top gasket, a middle gasket and a cast nut. 9 figs.

  4. Filter holder and gasket assembly for candle or tube filters

    DOE Patents [OSTI]

    Lippert, Thomas Edwin; Alvin, Mary Anne; Bruck, Gerald Joseph; Smeltzer, Eugene E.

    1999-03-02

    A filter holder and gasket assembly for holding a candle filter element within a hot gas cleanup system pressure vessel. The filter holder and gasket assembly includes a filter housing, an annular spacer ring securely attached within the filter housing, a gasket sock, a top gasket, a middle gasket and a cast nut.

  5. Sintered composite filter

    DOE Patents [OSTI]

    Bergman, W.

    1986-05-02

    A particulate filter medium formed of a sintered composite of 0.5 micron diameter quartz fibers and 2 micron diameter stainless steel fibers is described. Preferred composition is about 40 vol.% quartz and about 60 vol.% stainless steel fibers. The media is sintered at about 1100/sup 0/C to bond the stainless steel fibers into a cage network which holds the quartz fibers. High filter efficiency and low flow resistance are provided by the smaller quartz fibers. High strength is provided by the stainless steel fibers. The resulting media has a high efficiency and low pressure drop similar to the standard HEPA media, with tensile strength at least four times greater, and a maximum operating temperature of about 550/sup 0/C. The invention also includes methods to form the composite media and a HEPA filter utilizing the composite media. The filter media can be used to filter particles in both liquids and gases.

  6. Sub-micron filter

    DOE Patents [OSTI]

    Tepper, Frederick; Kaledin, Leonid

    2009-10-13

    Aluminum hydroxide fibers approximately 2 nanometers in diameter and with surface areas ranging from 200 to 650 m.sup.2/g have been found to be highly electropositive. When dispersed in water they are able to attach to and retain electronegative particles. When combined into a composite filter with other fibers or particles they can filter bacteria and nano size particulates such as viruses and colloidal particles at high flux through the filter. Such filters can be used for purification and sterilization of water, biological, medical and pharmaceutical fluids, and as a collector/concentrator for detection and assay of microbes and viruses. The alumina fibers are also capable of filtering sub-micron inorganic and metallic particles to produce ultra pure water. The fibers are suitable as a substrate for growth of cells. Macromolecules such as proteins may be separated from each other based on their electronegative charges.

  7. In-place HEPA filter penetration test

    SciTech Connect (OSTI)

    Bergman, W.; Wilson, kK.; Elliott, J.; Bettencourt, B.; Slawski, J.W.

    1997-01-01

    We have demonstrated the feasibility of conducting penetration tests on high efficiency particulate air (HEPA) filters as installed in nuclear ventilation systems. The in-place penetration test, which is designed to yield equivalent penetration measurements as the standard DOP efficiency test, is based on measuring the aerosol penetration of the filter installation as a function of particle size using a portable laser particle counter. This in-place penetration test is compared to the current in-place leak test using light scattering photometers for single HEPA filter installations and for HEPA filter plenums using the shroud method. Test results show the in-place penetration test is more sensitive than the in-place leak test, has a similar operating procedure, but takes longer to conduct. Additional tests are required to confirm that the in-place penetration test yields identical results as the standard dioctyl phthalate (DOP) penetration test for HEPA filters with controlled leaks in the filter and gasket and duct by-pass leaks. Further development of the procedure is also required to reduce the test time before the in- place penetration test is practical.

  8. Ceramic fiber reinforced filter

    DOE Patents [OSTI]

    Stinton, David P.; McLaughlin, Jerry C.; Lowden, Richard A.

    1991-01-01

    A filter for removing particulate matter from high temperature flowing fluids, and in particular gases, that is reinforced with ceramic fibers. The filter has a ceramic base fiber material in the form of a fabric, felt, paper of the like, with the refractory fibers thereof coated with a thin layer of a protective and bonding refractory applied by chemical vapor deposition techniques. This coating causes each fiber to be physically joined to adjoining fibers so as to prevent movement of the fibers during use and to increase the strength and toughness of the composite filter. Further, the coating can be selected to minimize any reactions between the constituents of the fluids and the fibers. A description is given of the formation of a composite filter using a felt preform of commercial silicon carbide fibers together with the coating of these fibers with pure silicon carbide. Filter efficiency approaching 100% has been demonstrated with these filters. The fiber base material is alternately made from aluminosilicate fibers, zirconia fibers and alumina fibers. Coating with Al.sub.2 O.sub.3 is also described. Advanced configurations for the composite filter are suggested.

  9. Criteria for calculating the efficiency of HEPA filters during and after design basis accidents

    SciTech Connect (OSTI)

    Bergman, W.; First, M.W.; Anderson, W.L.; Gilbert, H.; Jacox, J.W.

    1994-12-01

    We have reviewed the literature on the performance of high efficiency particulate air (HEPA) filters under normal and abnormal conditions to establish criteria for calculating the efficiency of HEPA filters in a DOE nonreactor nuclear facility during and after a Design Basis Accident (DBA). The literature review included the performance of new filters and parameters that may cause deterioration in the filter performance such as filter age, radiation, corrosive chemicals, seismic and rough handling, high temperature, moisture, particle clogging, high air flow and pressure pulses. The deterioration of the filter efficiency depends on the exposure parameters; in severe exposure conditions the filter will be structurally damaged and have a residual efficiency of 0%. Despite the many studies on HEPA filter performance under adverse conditions, there are large gaps and limitations in the data that introduce significant error in the estimates of HEPA filter efficiencies under DBA conditions. Because of this limitation, conservative values of filter efficiency were chosen when there was insufficient data.

  10. Nuclear Controls | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    About Our Programs Nonproliferation Nonproliferation and Arms Control Nuclear Controls Challenge: Detectdeter illicit transfers of nucleardual-use materials, technology, ...

  11. Active-R filter

    DOE Patents [OSTI]

    Soderstrand, Michael A.

    1976-01-01

    An operational amplifier-type active filter in which the only capacitor in the circuit is the compensating capacitance of the operational amplifiers, the various feedback and coupling elements being essentially solely resistive.

  12. Catalytic Filter for Diesel Exhaust Purification | Department of Energy

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

    This project is developing a precious metal-free passive diesel particulate filter. PDF icon deer09_fokema.pdf More Documents & Publications Active Soot Filter Regeneration Vehicle Technologies Office Merit Review 2014: Particulate Emissions Control by Advanced Filtration Systems for GDI Engines Towards Fuel-Efficient DPF Systems: Understanding the Soot Oxidation Process

  13. Contactor/filter improvements

    DOE Patents [OSTI]

    Stelman, David

    1989-01-01

    A contactor/filter arrangement for removing particulate contaminants from a gaseous stream includes a housing having a substantially vertically oriented granular material retention member with upstream and downstream faces, a substantially vertically oriented microporous gas filter element, wherein the retention member and the filter element are spaced apart to provide a zone for the passage of granular material therethrough. The housing further includes a gas inlet means, a gas outlet means, and means for moving a body of granular material through the zone. A gaseous stream containing particulate contaminants passes through the gas inlet means as well as through the upstream face of the granular material retention member, passing through the retention member, the body of granular material, the microporous gas filter element, exiting out of the gas outlet means. Disposed on the upstream face of the filter element is a cover screen which isolates the filter element from contact with the moving granular bed and collects a portion of the particulates so as to form a dust cake having openings small enough to exclude the granular material, yet large enough to receive the dust particles. In one embodiment, the granular material is comprised of prous alumina impregnated with CuO, with the cover screen cleaned by the action of the moving granular material as well as by backflow pressure pulses.

  14. Remotely serviced filter and housing

    DOE Patents [OSTI]

    Ross, Maurice J.; Zaladonis, Larry A.

    1988-09-27

    A filter system for a hot cell comprises a housing adapted for input of air or other gas to be filtered, flow of the air through a filter element, and exit of filtered air. The housing is tapered at the top to make it easy to insert a filter cartridge using an overhead crane. The filter cartridge holds the filter element while the air or other gas is passed through the filter element. Captive bolts in trunnion nuts are readily operated by electromechanical manipulators operating power wrenches to secure and release the filter cartridge. The filter cartridge is adapted to make it easy to change a filter element by using a master-slave manipulator at a shielded window station.

  15. eFRMAC Overview: Data Management and Enabling Technologies for Characterization of a Radiological Release A Case Study: The Fukushima Nuclear Power Plant Incident

    SciTech Connect (OSTI)

    Blumenthal, Daniel J.; Clark, Harvey W.; Essex, James J.; Wagner, Eric C.

    2013-07-01

    The eFRMAC enterprise is a suite of technologies and software developed by the United States Department of Energy, National Nuclear Security Administration’s Office of Emergency Response to coordinate the rapid data collection, management, and analysis required during a radiological emergency. This enables the Federal Radiological Monitoring and Assessment Center assets to evaluate a radiological or nuclear incident efficiently to facilitate protective actions to protect public health and the environment. This document identifies and describes eFRMAC methods including (1) data acquisition, (2) data management, (3) data analysis, (4) product creation, (5) quality control, and (6) dissemination.

  16. Filter and method of fabricating

    DOE Patents [OSTI]

    Janney, Mark A.

    2006-02-14

    A method of making a filter includes the steps of: providing a substrate having a porous surface; applying to the porous surface a coating of dry powder comprising particles to form a filter preform; and heating the filter preform to bind the substrate and the particles together to form a filter.

  17. Anti-clogging filter system

    DOE Patents [OSTI]

    Brown, Erik P.

    2015-05-19

    An anti-clogging filter system for filtering a fluid containing large particles and small particles includes an enclosure with at least one individual elongated tubular filter element in the enclosure. The individual elongated tubular filter element has an internal passage, a closed end, an open end, and a filtering material in or on the individual elongated tubular filter element. The fluid travels through the open end of the elongated tubular element and through the internal passage and through the filtering material. An anti-clogging element is positioned on or adjacent the individual elongated tubular filter element and provides a fluid curtain that preferentially directs the larger particulates to one area of the filter material allowing the remainder of the filter material to remain more efficient.

  18. Filters for cathodic arc plasmas

    DOE Patents [OSTI]

    Anders, Andre; MacGill, Robert A.; Bilek, Marcela M. M.; Brown, Ian G.

    2002-01-01

    Cathodic arc plasmas are contaminated with macroparticles. A variety of magnetic plasma filters has been used with various success in removing the macroparticles from the plasma. An open-architecture, bent solenoid filter, with additional field coils at the filter entrance and exit, improves macroparticle filtering. In particular, a double-bent filter that is twisted out of plane forms a very compact and efficient filter. The coil turns further have a flat cross-section to promote macroparticle reflection out of the filter volume. An output conditioning system formed of an expander coil, a straightener coil, and a homogenizer, may be used with the magnetic filter for expanding the filtered plasma beam to cover a larger area of the target. A cathodic arc plasma deposition system using this filter can be used for the deposition of ultrathin amorphous hard carbon (a-C) films for the magnetic storage industry.

  19. Remotely serviced filter and housing

    DOE Patents [OSTI]

    Ross, M.J.; Zaladonis, L.A.

    1987-07-22

    A filter system for a hot cell comprises a housing adapted for input of air or other gas to be filtered, flow of the air through a filter element, and exit of filtered air. The housing is tapered at the top to make it easy to insert a filter cartridge holds the filter element while the air or other gas is passed through the filter element. Captive bolts in trunnion nuts are readily operated by electromechanical manipulators operating power wrenches to secure and release the filter cartridge. The filter cartridge is adapted to make it easy to change a filter element by using a master-slave manipulator at a shielded window station. 6 figs.

  20. WIPP Workers Perform Filter Replacement

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

    December 10, 2015 WIPP Workers Perform Filter Replacement As recovery operations at the Waste Isolation Pilot Plant continue, increased work activity in the underground results in higher levels of airborne salt dust, increasing the frequency with which filters are replaced. Last week, workers performed a filter replacement on WIPP's Underground Ventilation System. WIPP's ventilation system has two filter units. Each unit has 84 separate filters arranges in four layers- moderate efficiency

  1. Stack filter classifiers

    SciTech Connect (OSTI)

    Porter, Reid B; Hush, Don

    2009-01-01

    Just as linear models generalize the sample mean and weighted average, weighted order statistic models generalize the sample median and weighted median. This analogy can be continued informally to generalized additive modeels in the case of the mean, and Stack Filters in the case of the median. Both of these model classes have been extensively studied for signal and image processing but it is surprising to find that for pattern classification, their treatment has been significantly one sided. Generalized additive models are now a major tool in pattern classification and many different learning algorithms have been developed to fit model parameters to finite data. However Stack Filters remain largely confined to signal and image processing and learning algorithms for classification are yet to be seen. This paper is a step towards Stack Filter Classifiers and it shows that the approach is interesting from both a theoretical and a practical perspective.

  2. Rotating drum filter

    DOE Patents [OSTI]

    Anson, Donald

    1990-01-01

    A perforated drum (10) rotates in a coaxial cylindrical housing (18) having three circumferential ports (19,22,23), and an axial outlet (24) at one end. The axis (11) is horizontal. A fibrous filter medium (20) is fed through a port (19) on or near the top of the housing (81) by a distributing mechanism (36) which lays a uniform mat (26) of the desired thickness onto the rotating drum (10). This mat (26) is carried by the drum (10) to a second port (23) through which dirty fluid (13) enters. The fluid (13) passes through the filter (26) and the cleaned stream (16) exits through the open end (15) of the drum (10) and the axial port (24) in the housing (18). The dirty filter material (20) is carried on to a third port (22) near the bottom of the housing (18) and drops into a receiver (31) from which it is continuously removed, cleaned (30), and returned (32) to the charging port (36) at the top. To support the filter mat, the perforated cylinder may carry a series of tines (40), shaped blades (41), or pockets, so that the mat (26) will not fall from the drum (10) prematurely. To minimize risk of mat failure, the fluid inlet port (23) may be located above the horizontal centerline (11).

  3. Ozone decomposing filter

    DOE Patents [OSTI]

    Simandl, Ronald F.; Brown, John D.; Whinnery, Jr., LeRoy L.

    1999-01-01

    In an improved ozone decomposing air filter carbon fibers are held together with a carbonized binder in a perforated structure. The structure is made by combining rayon fibers with gelatin, forming the mixture in a mold, freeze-drying, and vacuum baking.

  4. Stabilization void-fill encapsulation high-efficiency particulate filters

    SciTech Connect (OSTI)

    Alexander, R.G.; Stewart, W.E.; Phillips, S.J.; Serkowski, M.M.; England, J.L.; Boynton, H.C.

    1994-05-01

    This report discusses high-efficiency particulate air (HEPA) filter systems that which are contaminated with radionuclides are part of the nuclear fuel processing systems conducted by the US Department of Energy (DOE) and require replacement and safe and efficient disposal for plant safety. Two K-3 HEPA filters were removed from service, placed burial boxes, buried, and safely and efficiently stabilized remotely which reduced radiation exposure to personnel and the environment.

  5. Filter assembly for metallic and intermetallic tube filters

    DOE Patents [OSTI]

    Alvin, Mary Anne; Lippert, Thomas E.; Bruck, Gerald J.; Smeltzer, Eugene E.

    2001-01-01

    A filter assembly (60) for holding a filter element (28) within a hot gas cleanup system pressure vessel is provided, containing: a filter housing (62), said filter housing having a certain axial length and having a peripheral sidewall, said sidewall defining an interior chamber (66); a one piece, all metal, fail-safe/regenerator device (68) within the interior chamber (66) of the filter housing (62) and/or extending beyond the axial length of the filter housing, said device containing an outward extending radial flange (71) within the filter housing for seating an essential seal (70), the device also having heat transfer media (72) disposed inside and screens (80) for particulate removal; one compliant gasket (70) positioned next to and above the outward extending radial flange of the fail-safe/regenerator device; and a porous metallic corrosion resistant superalloy type filter element body welded at the bottom of the metal fail-safe/regenerator device.

  6. Technology of high-level nuclear waste disposal. Advances in the science and engineering of the management of high-level nuclear wastes. Volume 1

    SciTech Connect (OSTI)

    Hofmann, P.L.; Breslin, J.J.

    1981-01-01

    The papers in this volume cover the following subjects: waste isolation and the natural geohydrologic system; repository perturbations of the natural system; radionuclide migration through the natural system; and repository design technology. Individual papers are abstracted.

  7. Evaluation of Alternative Filter Media for the Rotary Microfilter

    SciTech Connect (OSTI)

    Poirier, M. R.; Herman, D. T.; Bhave, R.

    2011-11-09

    The Savannah River Site is currently developing and testing several processes to treat high level radioactive liquid waste. Each of these processes has a solid-liquid separation process that limits its throughput. Savannah River National Laboratory researchers identified and tested the rotary microfilter as a technology to increase solid-liquid separation throughput. The authors believe the rotary microfilter throughput can be improved by using a better filter membrane. Previous testing showed that asymmetric filters composed of a ceramic membrane on top of a stainless steel support produced higher filter flux than 100% stainless steel symmetric filters in crossflow filter tests. Savannah River National Laboratory and Oak Ridge National Laboratory are working together to develop asymmetric ceramic ? stainless steel composite filters and asymmetric 100% stainless steel filters to improve the throughput of the rotary microfilter. The Oak Ridge National Laboratory Inorganic Membrane Group fabricated samples of alternative filter membranes. In addition, Savannah River National Laboratory obtained samples of filter membranes from Pall, Porvair, and SpinTek. They tested these samples in a static test cell with feed slurries containing monosodium titanate and simulated sludge.

  8. Prestack mid-value filtering

    SciTech Connect (OSTI)

    Changlian, X. )

    1992-01-01

    This paper describes mid-value filtering, a specific nonlinear smoothing filtering, and widely used in graphic processing, etc. Mid-value filtering before stack of seismic data can remove wild value (inconceivable particular big value) and improve signal-noise ratio. In view of big data volume before stack, computation efficiency of mid-value filtering is critical to its feasibility. The algorithm used here is sufficiently based on the properties of mid-value filtering, so that the computation efficiency is greatly improved. It is experimentally shown that prestack mid-value filtering can quite well eliminate wild value, abnormal traces as well as surface waves, and raise signal-noise ratio. After lateral low frequency noises are removed by high pass filtering, mid-value filtering works better.

  9. Filtered cathodic arc source

    DOE Patents [OSTI]

    Falabella, Steven; Sanders, David M.

    1994-01-01

    A continuous, cathodic arc ion source coupled to a macro-particle filter capable of separation or elimination of macro-particles from the ion flux produced by cathodic arc discharge. The ion source employs an axial magnetic field on a cathode (target) having tapered sides to confine the arc, thereby providing high target material utilization. A bent magnetic field is used to guide the metal ions from the target to the part to be coated. The macro-particle filter consists of two straight solenoids, end to end, but placed at 45.degree. to one another, which prevents line-of-sight from the arc spot on the target to the parts to be coated, yet provides a path for ions and electrons to flow, and includes a series of baffles for trapping the macro-particles.

  10. Filtered cathodic arc source

    DOE Patents [OSTI]

    Falabella, S.; Sanders, D.M.

    1994-01-18

    A continuous, cathodic arc ion source coupled to a macro-particle filter capable of separation or elimination of macro-particles from the ion flux produced by cathodic arc discharge is described. The ion source employs an axial magnetic field on a cathode (target) having tapered sides to confine the arc, thereby providing high target material utilization. A bent magnetic field is used to guide the metal ions from the target to the part to be coated. The macro-particle filter consists of two straight solenoids, end to end, but placed at 45[degree] to one another, which prevents line-of-sight from the arc spot on the target to the parts to be coated, yet provides a path for ions and electrons to flow, and includes a series of baffles for trapping the macro-particles. 3 figures.

  11. Drilling fluid filter

    DOE Patents [OSTI]

    Hall, David R.; Fox, Joe; Garner, Kory

    2007-01-23

    A drilling fluid filter for placement within a bore wall of a tubular drill string component comprises a perforated receptacle with an open end and a closed end. A hanger for engagement with the bore wall is mounted at the open end of the perforated receptacle. A mandrel is adjacent and attached to the open end of the perforated receptacle. A linkage connects the mandrel to the hanger. The linkage may be selected from the group consisting of struts, articulated struts and cams. The mandrel operates on the hanger through the linkage to engage and disengage the drilling fluid filter from the tubular drill string component. The mandrel may have a stationary portion comprising a first attachment to the open end of the perforated receptacle and a telescoping adjustable portion comprising a second attachment to the linkage. The mandrel may also comprise a top-hole interface for top-hole equipment.

  12. Nuclear Data Links

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

    Control Nuclear Controls Challenge: Detect/deter illicit transfers of nuclear/dual-use materials, technology, and commodities. Solution: Build domestic and international capacity to implement and meet export control obligations. Related Topics international security international security policy NIS nuclear controls safeguards safeguards and security verification Related News Nuclear Verification Nonproliferation International Nuclear Safeguards Nonproliferation Policy Nonproliferation and Arms

  13. Regenerable particulate filter

    DOE Patents [OSTI]

    Stuecker, John N.; Cesarano, III, Joseph; Miller, James E.

    2009-05-05

    A method of making a three-dimensional lattice structure, such as a filter used to remove particulates from a gas stream, where the physical lattice structure is designed utilizing software simulation from pre-defined mass transfer and flow characteristics and the designed lattice structure is fabricated using a free-form fabrication manufacturing technique, where the periodic lattice structure is comprised of individual geometric elements.

  14. Quick-change filter cartridge

    DOE Patents [OSTI]

    Rodgers, John C.; McFarland, Andrew R.; Ortiz, Carlos A.

    1995-01-01

    A quick-change filter cartridge. In sampling systems for measurement of airborne materials, a filter element is introduced into the sampled airstream such that the aerosol constituents are removed and deposited on the filter. Fragile sampling media often require support in order to prevent rupture during sampling, and careful mounting and sealing to prevent misalignment, tearing, or creasing which would allow the sampled air to bypass the filter. Additionally, handling of filter elements may introduce cross-contamination or exposure of operators to toxic materials. Moreover, it is desirable to enable the preloading of filter media into quick-change cartridges in clean laboratory environments, thereby simplifying and expediting the filter-changing process in the field. The quick-change filter cartridge of the present invention permits the application of a variety of filter media in many types of instruments and may also be used in automated systems. The cartridge includes a base through which a vacuum can be applied to draw air through the filter medium which is located on a porous filter support and held there by means of a cap which forms an airtight seal with the base. The base is also adapted for receiving absorbing media so that both particulates and gas-phase samples may be trapped for investigation, the latter downstream of the aerosol filter.

  15. Drive Diagnostic Filter Wheel Control

    Energy Science and Technology Software Center (OSTI)

    2007-07-17

    DrD Filter Wheel Control is National Instrument's Labview software that drives a Drive Diagnostic filter wheel. The software can drive the filter wheel between each end limit, detect the positive and negative limit and each home position and post the stepper motot values to an Excel spreadsheet. The software can also be used to cycle the assembly between the end limits.

  16. Higher temperature reactor materials workshop sponsored by the Department of Energy Office of Nuclear Energy, Science, and Technology (NE) and the Office of Basic Energy Sciences (BES).

    SciTech Connect (OSTI)

    Allen, T.; Bruemmer, S.; Kassner, M.; Odette, R.; Stoller, R.; Was, G.; Wolfer, W.; Zinkle, S.; Elmer, J.; Motta, A.

    2002-08-12

    On March 18-21, 2002, the Department of Energy, Office of Nuclear Energy, Science, and Technology (NE) and the Office of Basic Energy Sciences (BES) sponsored a workshop to identify needs and opportunities for materials research aimed at performance improvements of structural materials in higher temperature reactors. The workshop focused discussion around the reactor concepts proposed as part of the Generation IV Nuclear Energy System Roadmap. The goal of the Generation IV initiative is to make revolutionary improvements in nuclear energy system design in the areas of sustainability, economics, safety and reliability. The Generation IV Nuclear Energy Systems Roadmap working groups have identified operation at higher temperature as an important step in improving economic performance and providing a means for nuclear energy to support thermochemical production of hydrogen. However, the move to higher operating temperatures will require the development and qualification of advanced materials to perform in the more challenging environment. As part of the process of developing advanced materials for these reactor concepts, a fundamental understanding of materials behavior must be established and the data-base defining critical performance limitations of these materials under irradiation must be developed. This workshop reviewed potential reactor designs and operating regimes, potential materials for application in high-temperature reactor environments, anticipated degradation mechanisms, and research necessary to understand and develop reactor materials capable of satisfactory performance while subject to irradiation damage at high temperature. The workshop brought together experts from the reactor materials and fundamental materials science communities to identify research and development needs and opportunities to provide optimum high temperature nuclear energy system structural materials.

  17. Technology of high-level nuclear waste disposal. Advances in the science and engineering of the management of high-level nuclear wastes. Volume 2

    SciTech Connect (OSTI)

    Hofmann, P.L.

    1982-01-01

    The twenty papers in this volume are divided into three parts: site exploration and characterization; repository development and design; and waste package development and design. These papers represent the status of technology that existed in 1981 and 1982. Individual papers were processed for inclusion in the Energy Data Base.

  18. Development of ceramic composite hot-gas filters

    SciTech Connect (OSTI)

    Judkins, R.R.; Stinton, D.P.; Smith, R.G.; Fischer, E.M.; Eaton, J.H.; Weaver, B.L.; Kahnke, J.L.; Pysher, D.J.

    1995-04-01

    A novel type of hot-gas filter based on a ceramic fiber-reinforced ceramic matrix was developed and extended to fullsize, 60-mm OD by 1.5-meter-long, candle filters. A commercially viable process for producing the filters was developed, and the filters are undergoing testing and demonstration throughout the world for applications in pressurized fluidized-bed combustion (PFBC) and integrated gasification combined cycle (IGCC) plants. Development activities at Oak Ridge National Laboratory (ORNL) and at the 3M Company, and testing at the Westinghouse Science and Technology Center (STC) are presented. Demonstration tests at the Tidd PFBC are underway. Issues identified during the testing and demonstration phases of the development are discussed. Resolution of the issues and the status of commercialization of the filters are described.

  19. Oil Bypass Filter and Diesel Engine Idling Wear-Rate Evaluations |

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

    Department of Energy 05 Diesel Engine Emissions Reduction (DEER) Conference Presentations and Posters PDF icon 2005_deer_zirker.pdf More Documents & Publications Demonstrated Petroleum Reduction Using Oil Bypass Filter Technology on Heavy and Light Vehicles Development of Partial Filter Technology for HDD Retrofit Comparing Emissions Benefits from Regulating Heavy Vehicle Idling

  20. DEVELOPMENT OF AN ADHESIVE CANDLE FILTER SAFEGUARD DEVICE

    SciTech Connect (OSTI)

    John P. Hurley; Ann K. Henderson; Jan W. Nowok; Michael L. Swanson

    2002-01-01

    In order to reach the highest possible efficiencies in a coal-fired turbine-based power system, the turbine should be directly fired with the products of coal conversion. Two main types of systems employ these turbines: those based on pressurized fluidized-bed combustors and those based on integrated gasification combined cycles. In both systems, suspended particulates must be cleaned from the gas stream before it enters the turbine so as to prevent fouling and erosion of the turbine blades. To produce the cleanest gas, barrier filters are being developed and are in use in several facilities. Barrier filters are composed of porous, high-temperature materials that allow the hot gas to pass but collect the particulates on the surface. The three main configurations of the barrier filters are candle, cross-flow, and tube filters. Both candle and tube filters have been tested extensively. They are composed of coarsely porous ceramic that serves as a structural support, overlain with a thin, microporous ceramic layer on the dirty gas side that serves as the primary filter surface. They are highly efficient at removing particulate matter from the gas stream and, because of their ceramic construction, are resistant to gas and ash corrosion. However, ceramics are brittle and individual elements can fail, allowing particulates to pass through the hole left by the filter element and erode the turbine. Preventing all failure of individual ceramic filter elements is not possible at the present state of development of the technology. Therefore, safeguard devices (SGDs) must be employed to prevent the particulates streaming through occasional broken filters from reaching the turbine. However, the SGD must allow for the free passage of gas when it is not activated. Upon breaking of a filter, the SGD must either mechanically close or quickly plug with filter dust to prevent additional dust from reaching the turbine. Production of a dependable rapidly closing autonomous mechanical device at high temperatures in a dusty gas stream is difficult because of problems with materials corrosion, dust leakage, and detection of filter failure. Therefore, the Energy & Environmental Research Center is using its knowledge of the factors that make filter dust sticky at gas filtration temperatures to make a simple and inexpensive SGD that employs an adhesive yet thermodynamically stable coating on a highly porous ceramic substrate. The SGDs are placed on top of individual candle filters at the filtered gas exit. Upon failure of the filter, the dirty gas flows through the SGD where the adhesive surface rapidly and permanently traps dust particles, causing the device to plug and prevent the dust from reaching the turbine.

  1. Evaluation of the Effectiveness of a New Technology for Extraction of Insoluble Impurities from Nuclear Power Plant Steam Generators with Purge Water

    SciTech Connect (OSTI)

    Bud'ko, I. O.; Zhukov, A. G.

    2013-11-15

    An experimental technology for the removal of insoluble impurities from a horizontal steam generator with purge water during planned shutdowns of the power generating unit is improved through a more representative determination of the concentration of impurities in the purge water ahead of the water cleanup facility and a more precise effective time for the duration of the purge process. Tests with the improved technique at power generating unit No. 1 of the Rostov Nuclear Power Plant show that the efficiency with which insoluble impurities are removed from the steam generator volume was more than two orders of magnitude greater than under the standard regulations.

  2. Comprehensive Nuclear Test-Ban Treaty | National Nuclear Security...

    National Nuclear Security Administration (NNSA)

    Comprehensive Nuclear Test-Ban Treaty Administrator Leads a Strong NNSA Team at CTBT ... 2015, at the fifth Comprehensive Nuclear Test-Ban Treaty (CTBT) Science & Technology ...

  3. ADVANCED SECOND GENERATION CERAMIC CANDLE FILTERS

    SciTech Connect (OSTI)

    M.A. Alvin

    2002-01-31

    Through sponsorship from the Department of Energy's National Energy Technology Laboratory (DOE/NETL), development and manufacture of advanced second generation candle filters was undertaken in the early 1990's. Efforts were primarily focused on the manufacture of fracture toughened, 1.5 m, continuous fiber ceramic composite (CFCC) and filament wound candle filters by 3M, McDermott, DuPont Lanxide Composites, and Techniweave. In order to demonstrate long-term thermal, chemical, and mechanical stability of the advanced second generation candle filter materials, Siemens Westinghouse initiated high temperature, bench-scale, corrosion testing of 3M's CVI-SiC and DuPont's PRD-66 mini-candles, and DuPont's CFCC SiC-SiC and IF&P Fibrosic{sup TM} coupons under simulated, pressurized fluidized-bed combustion (PFBC) conditions. This effort was followed by an evaluation of the mechanical and filtration performance of the advanced second generation filter elements in Siemens Westinghouse's bench-scale PFBC test facility in Pittsburgh, Pennsylvania. Arrays of 1.4-1.5 m 3M CVI-SiC, DuPont PRD-66, DuPont SiC-SiC, and IF&P Fibrosic{sup TM} candles were subjected to steady state process operating conditions, increased severity thermal transients, and accelerated pulse cycling test campaigns which represented {approx}1760 hours of equivalent filter operating life. Siemens Westinghouse subsequently participated in early material surveillance programs which marked entry of the 3M CVI-SiC and DuPont PRD-66 candle filters in Siemens Westinghouse Advanced Particulate Filtration (APF) system at the American Electric Power (AEP) Tidd Demonstration Plant in Brilliant, Ohio. Siemens Westinghouse then conducted an extended, accelerated life, qualification program, evaluating the performance of the 3M, McDermott, and Techniweave oxide-based CFCC filter elements, modified DuPont PRD-66 elements, and the Blasch, Scapa Cerafil{sup TM}, and Specific Surface monolithic candles for use in the APF system at the Foster Wheeler pressurized circulating fluidized-bed combustion (PCFBC), pilot-scale, test facility in Karhula, Finland. This report presents a summary of these efforts, defining the stability of the various porous ceramic filter materials, as well as component performance and extended life for use in advanced coal-based power systems.

  4. CASL - Massachusetts Institute of Technology

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

    Massachusetts Institute of Technology Cambridge, MA The Department of Nuclear Science and Engineering at MIT has been a leader in the development of the nuclear engineering...

  5. Initial technical basis for late washing filter cleaning

    SciTech Connect (OSTI)

    Morrissey, M.F.; Dworjanyn, L.O.

    1992-07-23

    Bench scale filter cleaning tests at the Savannah River Technology Center have shown that cross-flow filter elements can be cleaned between late wash filtration runs and restored to original clean water flux conditions. The most effective cleaning technique was high flow axial recirculation, followed by flushing with caustic solution. Simple flushing with oxalic acid and caustic is less effective and is not recommended because of adverse experience in ITP filter cleaning and uncertainty in the.nature of radiolysis by-product contaminants.

  6. Next Generation Nuclear Plant Project Technology Development Roadmaps: The Technical Path Forward for 750800C Reactor Outlet Temperature

    SciTech Connect (OSTI)

    John Collins

    2009-08-01

    This document presents the NGNP Critical PASSCs and defines their technical maturation path through Technology Development Roadmaps (TDRMs) and their associated Technology Readiness Levels (TRLs). As the critical PASSCs advance through increasing levels of technical maturity, project risk is reduced and the likelihood of within-budget and on-schedule completion is enhanced. The current supplier-generated TRLs and TDRMs for a 750800C reactor outlet temperature (ROT) specific to each supplier are collected in Appendix A.

  7. Defense Nuclear Nonproliferation | National Nuclear Security...

    National Nuclear Security Administration (NNSA)

    United States and China Continue Partnership for the Peaceful Uses of Nuclear Technology ... NNSA Transfers Responsibility for Radiation Detection System to China Customs US, ...

  8. SPACE-R Thermionic Space Nuclear Power System: Design and Technology Demonstration Program. Semiannual technical progress report for period ending March 1993

    SciTech Connect (OSTI)

    Not Available

    1993-05-01

    This Semiannual Technical Progress Report summarizes the technical progress and accomplishments for the Thermionic Space Nuclear Power System (TI-SNPS) Design and Technology Demonstration Program of the Prime Contractor, Space Power Incorporated (SPI), its subcontractors and supporting National Laboratories during the first half of the Government Fiscal Year (GFY) 1993. SPI`s subcontractors and supporting National Laboratories include: Babcock & Wilcox for the reactor core and externals; Space Systems/Loral for the spacecraft integration; Thermocore for the radiator heat pipes and the heat exchanger; INERTEK of CIS for the TFE, core elements and nuclear tests; Argonne National Laboratories for nuclear safety, physics and control verification; and Oak Ridge National laboratories for materials testing. Parametric trade studies are near completion. However, technical input from INERTEK has yet to be provided to determine some of the baseline design configurations. The INERTEK subcontract is expected to be initiated soon. The Point Design task has been initiated. The thermionic fuel element (TFE) is undergoing several design iterations. The reactor core vessel analysis and design has also been started.

  9. Coated x-ray filters

    DOE Patents [OSTI]

    Steinmeyer, P.A.

    1992-11-24

    A radiation filter for filtering radiation beams of wavelengths within a preselected range of wavelengths comprises a radiation transmissive substrate and an attenuating layer deposited on the substrate. The attenuating layer may be deposited by a sputtering process or a vacuum process. Beryllium may be used as the radiation transmissive substrate. In addition, a second radiation filter comprises an attenuating layer interposed between a pair of radiation transmissive layers. 4 figs.

  10. Spatial filters for high average power lasers

    DOE Patents [OSTI]

    Erlandson, Alvin C

    2012-11-27

    A spatial filter includes a first filter element and a second filter element overlapping with the first filter element. The first filter element includes a first pair of cylindrical lenses separated by a first distance. Each of the first pair of cylindrical lenses has a first focal length. The first filter element also includes a first slit filter positioned between the first pair of cylindrical lenses. The second filter element includes a second pair of cylindrical lenses separated by a second distance. Each of the second pair of cylindrical lenses has a second focal length. The second filter element also includes a second slit filter positioned between the second pair of cylindrical lenses.

  11. Mode Filtered Fiber Amplifier

    ScienceCinema (OSTI)

    Sandia

    2009-09-01

    A breakthrough technology for fabricating practical, high-power, high-beam-quality laser sources that are compact, rugged, and extremely efficient. 2007 R&D 100 winner (SAND2007-1475P)

  12. Low-energy RI beam technology and nuclear clusters in the explosive pp-chain breakout process

    SciTech Connect (OSTI)

    Kubono, S. [Institute of Modern Physics, Chinese Academy of Sciences, Nanchang Road 509, Lanzhou 73000 (China); RIKEN Nishina Center, 2-1 Hirosawa, Wako, Saitama 351-0198 (Japan); Center for Nuclear Study, University of Tokyo, 2-1 Hirosawa, Wako, Saitama 351-0 (Japan); Yamaguchi, H.; Kahl, D. M.; Ohshiro, Y.; Watanabe, S.; Yamazaki, N. [Center for Nuclear Study, University of Tokyo, 2-1 Hirosawa, Wako, Saitama 351-0198 (Japan); Teranishi, T. [Department of Physics, Kyushu University, 6-10-1 Hakozaki, Fukuoka 812-858 (Japan); Yanagisawa, Y.; Wakabayashi, Y.; Kase, M. [RIKEN Nishina Center, 2-1 Hirosawa, Wako, Saitama 351-0198 (Japan); Hayakawa, S. [Laboratori Nazionali del Sud, Istituto Nazionale di Fisica Nucleare, Via S. Sofia 62, 95125 Catania (Italy); Kwon, Y. K. [Institute for Basic Science, 70, Yuseong-daero 1689-gil, Yuseong-gu, Daejeon 305-81 (Korea, Republic of); Hashimoto, T.; Fukuda, Y. [Research Center for Nuclear Physics, Osaka University, 10-1 Mihogaoka, Ibaraki, Osaka 567-0047 (Japan); He, J. J. [Institute of Modern Physics, Chinese Academy of Sciences, Nanchang Road 509, Lanzhou 73000 (China); Goto, A. [Faculty of Medcine, Yamagata University, Yamagata 990-2331 (Japan); Muto, H. [Center of General Education, Tokyo University of Science at Suwa, Chino, Nagano 391-0292 (Japan)

    2014-05-09

    The lecture includes two parts: One is a discussion on the technology for developing RIB beam facility based on the in-flight method and relevant experimental technology. The second part is a discussion on experimental efforts for studying the breakout process from the pp-chain region based on recent works with low energy RI beams. The discussion of the second part specifically covers the problem of the vp-process in type II supernovae in terms of alpha cluster nature for the reactions.

  13. EVALUATION OF ALTERNATIVE FILTER MEDIA FOR THE ROTARY MICROFILTER

    SciTech Connect (OSTI)

    Poirier, M.; Herman, D.; Bhave, R.

    2011-09-13

    SRS is currently developing and testing several processes to treat high level radioactive liquid waste. These processes include the Integrated Salt Disposition Process (ISDP), the Salt Waste Processing Facility (SWPF), and the Small Column Ion Exchange Process (SCIX). Each of these processes has a solid-liquid separation process that limits its throughput. SRNL researchers identified and tested the rotary microfilter as a technology to increase solid-liquid separation throughput. The testing showed significant improvement in filter flux with the rotary microfilter over the baseline crossflow filter (i.e., 2.5-6.5X during scoping tests, as much as 10X in actual waste tests, and approximately 3X in pilot-scale tests). SRNL received funding from DOE EM-21, and subsequently DOE EM-31 to develop the rotary microfilter for high level radioactive service. The work has included upgrading the rotary microfilter for radioactive service, testing with simulated SRS waste streams, and testing it with simulated Hanford waste streams. While the filtration rate is better than that obtained during testing of crossflow filters, the authors believe the rotary microfilter throughput can be improved by using a better filter membrane. The rotary microfilter membrane is made of stainless steel (Pall PMM050). Previous testing, funded by DOE EM-21, showed that asymmetric filters composed of a ceramic membrane on top of a stainless steel support produced higher filter flux than 100% stainless steel symmetric filters in crossflow filter tests. In that testing, the Pall Accusep and Graver filters produced 13-21% larger filter flux than the baseline 0.1 {micro}m Mott filter. While the improvement in flux is not as dramatic as the improvement of the rotary filter over a crossflow filter, a 13-21% increase could reduce the lifetime of a 30 year process by 4-6 years, with significant cost savings. Subsequent rotary filter testing showed the Pall PMM050 stainless steel filter membrane produced higher flux than the Mott filter media in bench-scale and pilot-scale testing. The Accusep and Graver filter media were not evaluated in that testing, because they are not available as flat sheets. The Accusep filter was developed at ORNL and licensed to Pall Corporation. This filter has a stainless steel support structure with a zirconium oxide ceramic membrane. The pore size is 0.1 {micro}m absolute. The Graver filter has a stainless steel support structure with a titanium dioxide ceramic membrane. The pore size is 0.07 {micro}m absolute. SRNL and ORNL are working together to develop filter media similar to the Accusep and Graver media, and to test them in a bench-scale filtration apparatus to attempt to improve the throughput of the rotary microfilter. This report describes the effort.

  14. TESTING OF THE SECOND GENERATION SPINTEK ROTARY FILTER -11357

    SciTech Connect (OSTI)

    Herman, D.; Poirier, M.; Fowley, M.; Keefer, M.; Huff, T.

    2011-02-02

    The SpinTek rotary microfilter has been developed under the Department of Energy (DOE) Office of Environmental Management (EM) for the purpose of deployment in radioactive service in the DOE complex. The unit that was fabricated and tested is the second generation of the filter that incorporates recommended improvements from previous testing. The completion of this test satisfied a key milestone for the EM technology development program and technology readiness for deployment by Savannah River Remediation in the Small Column Ion Exchange and Sludge Washing processes at the Savannah River Site (SRS). The Savannah River National Laboratory (SRNL) contracted SpinTek Filtration to fabricate a full scale 25 disk rotary filter and perform a 1000 hour endurance test with a simulated SRS sludge. Over 1500 hours of operation have been completed with the filter. SpinTek Filtration fabricated a prototypic 25 disk rotary filter including updates to manufacturing tolerances, an updated design to the rotary joint, improved cooling to the bottom journal, decreases in disk and filter shaft hydraulic resistances. The filter disks were fabricated with 0.5 {micro} pore size, sintered-metal filter media manufactured by Pall Corporation (M050). After fabrication was complete, the filter passed acceptance tests demonstrating rejection of solids and clean water flux with a 50% improvement over the previous filters. Once the acceptance test was complete, a 1000 hour endurance test was initiated simulating a sludge washing process. The test used a simulated SRS Sludge Batch 6 recipe. The insoluble solids started at 5 wt% and were raised to 10 and 15 wt% insoluble solids to simulate the concentration of a large volume tank. The filter system was automated and set up for 24 hour unattended operation. To facilitate this, process control logic was written to operate the filter. During the development it was demonstrated that the method of starting and stopping the filter can affect the build up of filter cake on the disks and therefore the performance of the filter. The filter performed well with the simulant. Very little drop in production was noticed between the 5 and 10 wt% insoluble solids feed. Increasing to 15 wt% had a more pronounced impact due to the rheology of the feed. Acid cleaning was used to clean the filter disks in-situ and restore filtration rate to almost 90% of the initial clean disk rate. Eighty liters of 0.2 M nitric acid in conjunction with water rinses were used to clean the filter in less than 2 hours. Filter testing was completed after 1000 hours of operation were performed on the final filter assembly configuration. The total run time for the testing was over 1500 hours. At the end of the test, the sludge washing was performed successfully from approximately 5.6 M to less than 1 M sodium.

  15. The path to clean energy: direct coupling of nuclear and renewable technologies for thermal and electrical applications

    SciTech Connect (OSTI)

    Bragg-Sitton, Shannon; Boardman, Richard; Ruth, Mark

    2015-07-01

    The U.S. Department of Energy (DOE) recognizes the need to transform the energy infrastructure of the U.S. and elsewhere to systems that can significantly reduce environmental impacts in an efficient and economically viable manner while utilizing both clean energy generation sources and hydrocarbon resources. Thus, DOE is supporting research and development that could lead to more efficient utilization of clean nuclear and renewable energy generation sources. A concept being advanced by the DOE Offices of Nuclear Energy (NE) and Energy Efficiency and Renewable Energy (EERE) is tighter coupling of nuclear and renewable energy sources in a manner that better optimizes energy use for the combined electricity, industrial manufacturing, and the transportation sectors. This integration concept has been referred to as a “hybrid system” that is capable of providing energy (thermal or electrical) where it is needed, when it is needed. For the purposes of this work, the hybrid system would integrate two or more energy resources to generate two or more products, one of which must be an energy commodity, such as electricity or transportation fuel. This definition requires coupling of subsystems ‘‘behind’’ the electrical transmission bus, where energy flows are dynamically apportioned as necessary to meet demand and the system has a single connection to the grid that provides dispatchable electricity as required while capital intensive generation assets operate at full capacity. Development of integrated energy systems for an “energy park” must carefully consider the intended location and the associated regional resources, traditional industrial processes, energy delivery infrastructure, and markets to identify viable region-specific system configurations. This paper will provide an overview of the current status of regional hybrid energy system design, development and application of dynamic analysis tools to assess technical and economic performance, and roadmap development to identify and prioritize component, subsystem and system testing that will lead to prototype demonstration.

  16. New Technologies for Repairing Aging Cables in Nuclear Power Plants: M3LW-14OR0404015 Cable Rejuvenation Report

    SciTech Connect (OSTI)

    Simmons, Kevin L.; Fifield, Leonard S.; Westman, Matthew P.; Roberts, John A.

    2014-09-08

    The goal of this project is to conceptually demonstrate techniques to repair cables that have degraded through subjection to long-term thermal and radiation exposure in nuclear power plants. In fiscal year 2014 (FY14) we focused on commercially available ethylene-propylene rubber (EPR) as the relevant test material, isolated a high surface area form of the EPR material to facilitate chemical treatment screening and charaterization, and measured chemical changes in the material due to aging and treatment using Fourier Transfrom Infrared (FTIR) spectroscopy.

  17. Filter desulfation system and method

    DOE Patents [OSTI]

    Lowe, Michael D.; Robel, Wade J.; Verkiel, Maarten; Driscoll, James J.

    2010-08-10

    A method of removing sulfur from a filter system of an engine includes continuously passing an exhaust flow through a desulfation leg of the filter system during desulfation. The method also includes sensing at least one characteristic of the exhaust flow and modifying a flow rate of the exhaust flow during desulfation in response to the sensing.

  18. Solid colloidal optical wavelength filter

    DOE Patents [OSTI]

    Alvarez, Joseph L.

    1992-01-01

    A solid colloidal optical wavelength filter includes a suspension of spheal particles dispersed in a coagulable medium such as a setting plastic. The filter is formed by suspending spherical particles in a coagulable medium; agitating the particles and coagulable medium to produce an emulsion of particles suspended in the coagulable medium; and allowing the coagulable medium and suspended emulsion of particles to cool.

  19. Global Nuclear Energy Partnership Fact Sheet - Develop Enhanced Nuclear

    Office of Environmental Management (EM)

    Safeguards | Department of Energy Develop Enhanced Nuclear Safeguards Global Nuclear Energy Partnership Fact Sheet - Develop Enhanced Nuclear Safeguards GNEP will help prevent misuse of civilian nuclear facilities for nonpeaceful purposes by developing enhanced safeguards programs and technologies. International nuclear safeguards are integral to implementing the GNEP vision of a peaceful expansion of nuclear energy and demonstration of more proliferation-resistant fuel cycle technologies.

  20. Sintered composite medium and filter

    DOE Patents [OSTI]

    Bergman, Werner

    1987-01-01

    A particulate filter medium is formed of a sintered composite of 0.5 micron diameter quartz fibers and 2 micron diameter stainless steel fibers. A preferred composition is about 40 vol. % quartz and about 60 vol. % stainless steel fibers. The media is sintered at about 1100.degree. C. to bond the stainless steel fibers into a cage network which holds the quartz fibers. High filter efficiency and low flow resistance are provided by the smaller quartz fibers. High strength is provided by the stainless steel fibers. The resulting media has a high efficiency and low pressure drop similar to the standard HEPA media, with tensile strength at least four times greater, and a maximum operating temperature of about 550.degree. C. The invention also includes methods to form the composite media and a HEPA filter utilizing the composite media. The filter media can be used to filter particles in both liquids and gases.

  1. Digital Sensor Technology

    SciTech Connect (OSTI)

    Ted Quinn; Jerry Mauck; Richard Bockhorst; Ken Thomas

    2013-07-01

    The nuclear industry has been slow to incorporate digital sensor technology into nuclear plant designs due to concerns with digital qualification issues. However, the benefits of digital sensor technology for nuclear plant instrumentation are substantial in terms of accuracy, reliability, availability, and maintainability. This report demonstrates these benefits in direct comparisons of digital and analog sensor applications. It also addresses the qualification issues that must be addressed in the application of digital sensor technology.

  2. Structural Integrity Program for the 300,000-Gallon Radioactive Liquid Waste Storage Tanks at the Idaho Nuclear Technology and Engineering Center

    SciTech Connect (OSTI)

    Bryant, Jeffrey W.

    2010-08-12

    This report provides a record of the Structural Integrity Program for the 300,000-gal liquid waste storage tanks and associated equipment at the Idaho Nuclear Technology and Engineering Center, as required by U.S. Department of Energy M 435.1-1, “Radioactive Waste Management Manual.” This equipment is known collectively as the Tank Farm Facility. This report is an update, and replaces the previous report by the same title issued April 2003. The conclusion of this report is that the Tank Farm Facility tanks, vaults, and transfer systems that remain in service for storage are structurally adequate, and are expected to remain structurally adequate over the remainder of their planned service life through 2012. Recommendations are provided for continued monitoring of the Tank Farm Facility.

  3. International Nuclear Safeguards | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    International Nuclear Safeguards Challenge: Detect/deter undeclared nuclear materials and activities. Solution: Build capacity of the International Atomic Energy Agency and Member States to implement and meet safeguards obligations. The Office of International Nuclear Safeguards develops and supports the policies, concepts, technologies, expertise, and international safeguards infrastructure necessary to strengthen and sustain the international safeguards system as it evolves to meet new

  4. State-of-the-Art of Non-Destructive Testing Methods and Technologies for Application to Nuclear Power Plant Safety-Related Concrete Structures

    SciTech Connect (OSTI)

    Wiggenhauser, Dr. Herbert; Naus, Dan J

    2014-01-01

    The inspection of nuclear power plant concrete structures presents challenges different from conventional civil engineering structures. Wall thicknesses can be in excess of one meter and the structures often have increased steel reinforcement density with more complex detailing. The accessibility for any testing method may be limited due to the presence of liners and other components and there can be a number of penetrations or cast-in-place items present. The objective of the report is to present the state-of-the art of non-destructive testing methods and technologies for the inspection of thick, heavily-reinforced nuclear power plant concrete cross-sections with particular respect to: locating steel reinforcement and identification of its cover depth locating tendon ducts and identification of the condition of the grout materials detection of cracking, voids, delamination, and honeycombing in concrete structures detection of inclusions of different materials or voids adjacent to the concrete side of the containment liner methods capable of identification of corrosion occurrence on the concrete side of the containment liner

  5. Nuclear Physics: Meetings

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

    Physics Topics: Meetings Talks given at the Science & Technology Review 2004 Larry Cardman: Science Overview and the Experimental Program ppt | pdf Tony Thomas: Nuclear Physics ...

  6. nuclear bombs | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    nuclear bombs

  7. nuclear fusion | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    nuclear fusion

  8. nuclear reactors | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    nuclear reactors

  9. Filter Specialty Bioenergy | Open Energy Information

    Open Energy Info (EERE)

    Filter Specialty Bioenergy Jump to: navigation, search Name: Filter Specialty Bioenergy Place: Autryville, NC, North Carolina Product: The company runs a 6m liter biodiesel plant...

  10. Electrically-Assisted Diesel Particulate Filter Regeneration...

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

    More Documents & Publications Substrate Studies of an Electrically-Assisted Diesel Particulate Filter Electrically-Assisted Diesel Particulate Filter Regeneration Durability of ...

  11. Pleated Ceramic Fiber Diesel Particulate Filter | Department...

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

    Pleated Ceramic Fiber Diesel Particulate Filter Pleated Ceramic Fiber Diesel Particulate Filter 2005 Diesel Engine Emissions Reduction (DEER) Conference Presentations and Posters ...

  12. Electrically-Assisted Diesel Particulate Filter Regeneration...

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

    More Documents & Publications Electrically-Assisted Diesel Particulate Filter Regeneration Substrate Studies of an Electrically-Assisted Diesel Particulate Filter Biofuels Impact ...

  13. Nuclear Security Summit | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    Nuclear Security Summit U.S. and China Continue Cooperative Partnership to Advance Safe, Secure Civil Nuclear Energy for Clean Energy Future DOE/NNSA Hosts 11th U.S.-China Peaceful Uses of Nuclear Technology Meeting at Savannah River National Laboratory in Aiken, South Carolina (Aiken, South Carolina) - On May 10-11, 2016 the U.S. Department of Energy's (DOE) National Nuclear Security Administration (NNSA) and the China... Statement on Signing of the Administrative Arrangement to the Agreement

  14. Nuclear Facilities | Department of Energy

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

    Nuclear Facilities Nuclear Facilities Nuclear Facilities Locator Map Numerical map data points indicate two or more nuclear facilities in the same geographic location. Nuclear Facilities List: Argonne National Laboratory East Tennessee Technology Park Hanford Idaho Site Los Alamos National Laboratory Lawrence Livermore National Laboratory Nevada National Security Site New Brunswick Laboratory Oak Ridge National Laboratory cont. Paducah Pantex Pacific Northwest National Laboratory Portsmouth

  15. Nuclear Engineering | Argonne National Laboratory

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

    Nuclear Engineering Advancing the safe and secure use of nuclear energy Argonne's Nuclear Engineering (NE) division works to advance nuclear energy as a proven, abundant and non-emitting energy source through research, technology development, design, analysis and application of our nuclear energy-related expertise to current and emerging programs of national and international significance. Argonne nuclear engineers have been instrumental in developing civilian nuclear power systems for over 65

  16. Advanced Reactor Technologies | Department of Energy

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

    Nuclear Reactor Technologies » Advanced Reactor Technologies Advanced Reactor Technologies Advanced Reactor Technologies Advanced Reactor Technologies The Office of Advanced Reactor Technologies (ART) sponsors research, development and deployment (RD&D) activities through its Next Generation Nuclear Plant (NGNP), Advanced Reactor Concepts (ARC), and Advanced Small Modular Reactor (aSMR) programs to promote safety, technical, economical, and environmental advancements of innovative

  17. Sub-wavelength efficient polarization filter (SWEP filter)

    DOE Patents [OSTI]

    Simpson, Marcus L.; Simpson, John T.

    2003-12-09

    A polarization sensitive filter includes a first sub-wavelength resonant grating structure (SWS) for receiving incident light, and a second SWS. The SWS are disposed relative to one another such that incident light which is transmitted by the first SWS passes through the second SWS. The filter has a polarization sensitive resonance, the polarization sensitive resonance substantially reflecting a first polarization component of incident light while substantially transmitting a second polarization component of the incident light, the polarization components being orthogonal to one another. A method for forming polarization filters includes the steps of forming first and second SWS, the first and second SWS disposed relative to one another such that a portion of incident light applied to the first SWS passes through the second SWS. A method for separating polarizations of light, includes the steps of providing a filter formed from a first and second SWS, shining incident light having orthogonal polarization components on the first SWS, and substantially reflecting one of the orthogonal polarization components while substantially transmitting the other orthogonal polarization component. A high Q narrowband filter includes a first and second SWS, the first and second SWS are spaced apart a distance being at least one half an optical wavelength.

  18. Advanced High Porosity Ceramic Honeycomb Wall Flow Filters | Department of

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

    Energy 07 Diesel Engine-Efficiency & Emissions Research Conference (DEER 2007). 13-16 August, 2007, Detroit, Michigan. Sponsored by the U.S. Department of Energy's (DOE) Office of FreedomCAR and Vehicle Technologies (OFCVT). PDF icon deer07_zuberi.pdf More Documents & Publications New Cordierite Diesel Particulate Filters for Catalyzed and Non-Catalyzed Applications Incorporation of Catalytic Compounds in the Porosity of SiC Wall Flow Filters - 4 Way Catalyst and DeNOx Application

  19. Water washable stainless steel HEPA filter

    DOE Patents [OSTI]

    Phillips, Terrance D.

    2001-01-01

    The invention is a high efficiency particulate (HEPA) filter apparatus and system, and method for assaying particulates. The HEPA filter provides for capture of 99.99% or greater of particulates from a gas stream, with collection of particulates on the surface of the filter media. The invention provides a filter system that can be cleaned and regenerated in situ.

  20. Spatial filters for high power lasers

    DOE Patents [OSTI]

    Erlandson, Alvin Charles; Bayramian, Andrew James

    2014-12-02

    A spatial filter includes a first filter element and a second filter element overlapping with the first filter element. The first filter element includes a first pair of cylindrical lenses separated by a first distance. Each of the first pair of cylindrical lenses has a first focal length. The first filter element also includes a first longitudinal slit filter positioned between the first pair of cylindrical lenses. The second filter element includes a second pair of cylindrical lenses separated by a second distance. Each of the second pair of cylindrical lenses has a second focal length. The second filter element also includes a second longitudinal slit filter positioned between the second pair of cylindrical lenses.

  1. Nuclear Facility Operations | Department of Energy

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

    Nuclear Facility Operations INL is a science-based, applied engineering national laboratory dedicated to meeting the nation's environmental, energy, nuclear technology, and ...

  2. Press Releases | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    ... November 03, 2015 NNSA Labs host U.S. and Nuclear Non-Proliferation Treaty (NPT) ... to Sign Agreement on Countering the Proliferation of Nuclear Materials and Technologies ...

  3. Determination of filter-cake thicknesses from on-line flow measurements and gas/particle transport modeling

    SciTech Connect (OSTI)

    Smith, D.H.; Powell, V.; Ibrahim, E.; Ferer, M.; Ahmadi, G.

    1996-12-31

    The use of cylindrical candle filters to remove fine ({approx}0.005 mm) particles from hot ({approx}500- 900{degrees}C) gas streams currently is being developed for applications in advanced pressurized fluidized bed combustion (PFBC) and integrated gasification combined cycle (IGCC) technologies. Successfully deployed with hot-gas filtration, PFBC and IGCC technologies will allow the conversion of coal to electrical energy by direct passage of the filtered gases into non-ruggedized turbines and thus provide substantially greater conversion efficiencies with reduced environmental impacts. In the usual approach, one or more clusters of candle filters are suspended from a tubesheet in a pressurized (P {approx_lt}1 MPa) vessel into which hot gases and suspended particles enter, the gases pass through the walls of the cylindrical filters, and the filtered particles form a cake on the outside of each filter. The cake is then removed periodically by a backpulse of compressed air from inside the filter, which passes through the filter wall and filter cake. In various development or demonstration systems the thickness of the filter cake has proved to be an important, but unknown, process parameter. This paper describes a physical model for cake and pressure buildups between cleaning backpulses, and for longer term buildups of the ``baseline`` pressure drop, as caused by incomplete filter cleaning and/or re-entrainment. When combined with operating data and laboratory measurements of the cake porosity, the model may be used to calculate the (average) filter permeability, the filter-cake thickness and permeability, and the fraction of filter-cake left on the filter by the cleaning backpulse or re-entrained after the backpulse. When used for a variety of operating conditions (e.g., different coals, sorbents, temperatures, etc.), the model eventually may provide useful information on how the filter-cake properties depend on the various operating parameters.

  4. Radiant zone heated particulate filter

    DOE Patents [OSTI]

    Gonze, Eugene V [Pinckney, MI

    2011-12-27

    A system includes a particulate matter (PM) filter including an upstream end for receiving exhaust gas and a downstream end. A radiant zoned heater includes N zones, where N is an integer greater than one, wherein each of the N zones includes M sub-zones, where M is an integer greater than or equal to one. A control module selectively activates at least a selected one of the N zones to initiate regeneration in downstream portions of the PM filter from the one of the N zones, restricts exhaust gas flow in a portion of the PM filter that corresponds to the selected one of the N zones, and deactivates non-selected ones of the N zones.

  5. Method and means of monitoring the effluent from nuclear facilities

    DOE Patents [OSTI]

    Lattin, Kenneth R.; Erickson, Gerald L.

    1976-01-01

    Radioactive iodine is detected in the effluent cooling gas from a nuclear reactor or nuclear facility by passing the effluent gas through a continuously moving adsorbent filter material which is then purged of noble gases and conveyed continuously to a detector of radioactivity. The purging operation has little or no effect upon the concentration of radioactive iodine which is adsorbed on the filter material.

  6. Secondary Waste Considerations for Vitrification of Sodium-Bearing Waste at the Idaho Nuclear Techology and Engineering Center FY-2001 Status Report

    SciTech Connect (OSTI)

    Herbst, Alan Keith; Kirkham, Robert John; Losinski, Sylvester John

    2001-09-01

    The Idaho Nuclear Technology and Engineering Center (INTEC) is considering vitrification to process liquid sodium-bearing waste. Preliminary studies were completed to evaluate the potential secondary wastes from the melter off-gas clean up systems. Projected secondary wastes comprise acidic and caustic scrubber solutions, HEPA filters, activated carbon, and ion exchange media. Possible treatment methods, waste forms, and disposal sites are evaluated from radiological and mercury contamination estimates.

  7. Office Of Nuclear Energy

    Energy Savers [EERE]

    Operator Support Technologies for Fault Tolerance and Resilience Richard Vilim, Argonne National Laboratory Ken Thomas, Idaho National Laboratory Nuclear Energy Enabling Technology October 28-29, 2015 2 Project Overview § A nuclear plant operator presently takes a symptom- based approach to upsets § Not necessarily expected to diagnose a fault § Fault diagnosis is time consuming, approximate, and prone to error § Situational awareness is limited by old technologies 3 Project

  8. Hot gas cross flow filtering module

    DOE Patents [OSTI]

    Lippert, Thomas E. (Murrysville Boro, PA); Ciliberti, David F. (Murrysville Boro, PA)

    1988-01-01

    A filter module for use in filtering particulates from a high temperature gas has a central gas duct and at least one horizontally extending support mount affixed to the duct. The support mount supports a filter element thereon and has a chamber therein, which communicates with an inner space of the duct through an opening in the wall of the duct, and which communicates with the clean gas face of the filter element. The filter element is secured to the support mount over an opening in the top wall of the support mount, with releasable securement provided to enable replacement of the filter element when desired. Ceramic springs may be used in connection with the filter module either to secure a filter element to a support mount or to prevent delamination of the filter element during blowback.

  9. Vapor purification with self-cleaning filter

    DOE Patents [OSTI]

    Josephson, Gary B.; Heath, William O.; Aardahl, Christopher L.

    2003-12-09

    A vapor filtration device including a first electrode, a second electrode, and a filter between the first and second electrodes is disclosed. The filter is formed of dielectric material and the device is operated by applying a first electric potential between the electrodes to polarize the dielectric material such that upon passing a vapor stream through the filter, particles from the vapor stream are deposited onto the filter. After depositing the particles a second higher voltage is applied between the electrodes to form a nonthermal plasma around the filter to vaporize the collected particles thereby cleaning the filter. The filter can be a packed bed or serpentine filter mat, and an optional upstream corona wire can be utilized to charge airborne particles prior to their deposition on the filter.

  10. Measurements of filter-cake properties

    SciTech Connect (OSTI)

    Smith, D.H.; Grimm, U.; Haddad, G.J.

    1996-12-31

    The Pressurized Fluidized-Bed Combustion (PFBC) and Integrated Gasification Combined Cycle (IGCC) programs of the U.S. Department of Energy require filtration, at temperatures from about 600 to 900 {degrees}C, of fine particles of coal ash, char, or spent and unreacted sorbent from hot-gas streams. Achieving acceptable filter lifetimes requires solutions to or avoidance of, such problems as incomplete filter cleaning, re-entrainment (i.e., re-filtration) of particles from filter cleaning, and bridging of filter cake between adjacent filters. These and other potential problems may arise from the materials properties of filter cakes, from the filter-bank design, and from the mechanisms of filter cleaning. Avoiding re-entrainment requires that some bonding and agglomeration of particles occur in the cakes (so that the agglomerates from filter cleaning are too large to be re-entrained), but excessive agglomeration can produce poor cleaning or bridging. For both PFBC and IGCC applications, we can form filter cakes at process temperatures, gas compositions, and gas flow rates, and measure the gas-phase permeabilities, porosities, tensile strengths, and deformation coefficients of these filter cakes to determine their dependencies on temperature, reaction time, gas composition, particle compositions, and particle size distributions. Filter-cake shear strengths and flow factors can be measured for powders ``as received,`` for filter cakes that we have heated to process temperatures, or for powders heated in reactive gases to simulate gas-solid reactions in process filter cakes.

  11. Autonomous Correction of Sensor Data Applied to Building Technologies Using

    Office of Scientific and Technical Information (OSTI)

    Filtering Methods (Conference) | SciTech Connect Autonomous Correction of Sensor Data Applied to Building Technologies Using Filtering Methods Citation Details In-Document Search Title: Autonomous Correction of Sensor Data Applied to Building Technologies Using Filtering Methods Sensor data validity is extremely important in a number of applications, particularly building technologies where collected data are used to determine performance. An example of this is Oak Ridge National Laboratory

  12. RAPID SEPARATION METHOD FOR ACTINIDES IN EMERGENCY AIR FILTER SAMPLES

    SciTech Connect (OSTI)

    Maxwell, S.; Noyes, G.; Culligan, B.

    2010-02-03

    A new rapid method for the determination of actinides and strontium in air filter samples has been developed at the Savannah River Site Environmental Lab (Aiken, SC, USA) that can be used in emergency response situations. The actinides and strontium in air filter method utilizes a rapid acid digestion method and a streamlined column separation process with stacked TEVA, TRU and Sr Resin cartridges. Vacuum box technology and rapid flow rates are used to reduce analytical time. Alpha emitters are prepared using cerium fluoride microprecipitation for counting by alpha spectrometry. The purified {sup 90}Sr fractions are mounted directly on planchets and counted by gas flow proportional counting. The method showed high chemical recoveries and effective removal of interferences. This new procedure was applied to emergency air filter samples received in the NRIP Emergency Response exercise administered by the National Institute for Standards and Technology (NIST) in April, 2009. The actinide and {sup 90}Sr in air filter results were reported in {approx}4 hours with excellent quality.

  13. A rigid porous filter and filtration method

    SciTech Connect (OSTI)

    Chiang, Ta-Kuan; Straub, Douglas, Straub L.; Dennis, Richard A.

    1998-12-01

    The present invention involves a porous rigid filter comprising a plurality of concentric filtration elements having internal flow passages and forming external flow passages there between. The present invention also involves a pressure vessel containing the filter for the removal of particulate from high pressure particulate containing gases, and further involves a method for using the filter to remove such particulate. The present filter has the advantage of requiring fewer filter elements due to the high surface area- to-volume ratio provided by the filter, requires a reduced pressure vessel size, and exhibits enhanced mechanical design properties, improved cleaning properties, configuration options, modularity and ease of fabrication.

  14. Electric filter with movable belt electrode

    DOE Patents [OSTI]

    Bergman, W.

    1983-09-20

    A method and apparatus for removing airborne contaminants entrained in a gas or airstream includes an electric filter characterized by a movable endless belt electrode, a grounded electrode, and a filter medium sandwiched there between. Inclusion of the movable, endless belt electrode provides the driving force for advancing the filter medium through the filter, and reduces frictional drag on the filter medium, thereby permitting a wide choice of filter medium materials. Additionally, the belt electrode includes a plurality of pleats in order to provide maximum surface area on which to collect airborne contaminants. 4 figs.

  15. Electric filter with movable belt electrode

    DOE Patents [OSTI]

    Bergman, Werner

    1983-01-01

    A method and apparatus for removing airborne contaminants entrained in a gas or airstream includes an electric filter characterized by a movable endless belt electrode, a grounded electrode, and a filter medium sandwiched therebetween. Inclusion of the movable, endless belt electrode provides the driving force for advancing the filter medium through the filter, and reduces frictional drag on the filter medium, thereby permitting a wide choice of filter medium materials. Additionally, the belt electrode includes a plurality of pleats in order to provide maximum surface area on which to collect airborne contaminants.

  16. Development of active porous medium filters based on plasma textiles

    SciTech Connect (OSTI)

    Kuznetsov, Ivan A.; Saveliev, Alexei V.; Rasipuram, Srinivasan; Kuznetsov, Andrey V.; Brown, Alan; Jasper, Warren

    2012-05-15

    Inexpensive, flexible, washable, and durable materials that serve as antimicrobial filters and self-decontaminating fabrics are needed to provide active protection to people in areas regularly exposed to various biohazards, such as hospitals and bio research labs working with pathogens. Airlines and cruise lines need such material to combat the spread of infections. In households these materials can be used in HVAC filters to fight indoor pollution, which is especially dangerous to people suffering from asthma. Efficient filtering materials are also required in areas contaminated by other types of hazardous dust particulates, such as nuclear dust. The primary idea that guided the undertaken study is that a microplasma-generating structure can be embedded in a textile fabric to generate a plasma sheath (''plasma shield'') that kills bacterial agents coming in contact with the fabric. The research resulted in the development of a plasma textile that can be used for producing new types of self-decontaminating garments, fabrics, and filter materials, capable of activating a plasma sheath that would filter, capture, and destroy any bacteriological agent deposited on its surface. This new material relies on the unique antimicrobial and catalytic properties of cold (room temperature) plasma that is benign to people and does not cause thermal damage to many polymer textiles, such as Nomex and polypropylene. The uniqueness of cold plasma as a disinfecting agent lies in the inability of bacteria to develop resistance to plasma exposure, as they can for antibiotics. Plasma textiles could thus be utilized for microbial destruction in active antimicrobial filters (for continuous decontamination and disinfection of large amounts of air) as well as in self-decontaminating surfaces and antibacterial barriers (for example, for creating local antiseptic or sterile environments around wounds and burns).

  17. Some thoughts on the nonproliferation of nuclear weapons

    SciTech Connect (OSTI)

    Krikorian N.H.; Hawkins, H.T.

    1996-05-01

    This paper discusses factors controlling the dissemination of nuclear technologies and especially fissile materials.

  18. technology | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    (KrF) laser. Nike was developed primarily to investigate interactions of high intensity KrF light with matter. The target facility is well equipped for experiments on laser ...

  19. Testing and Disposal Strategy for Secondary Wastes from Vitrification of Sodium-Bearing Waste at Idaho Nuclear Technology and Engineering Center

    SciTech Connect (OSTI)

    Herbst, Alan K.

    2002-01-02

    The Idaho National Engineering and Environmental Laboratory (INEEL) is considering vitrification to process liquid sodium-bearing waste. Preliminary studies were completed to evaluate the potential secondary wastes comprise acidic and caustic scrubber solutions, HEPA filters, activated carbon, and ion exchange media. Possible treatment methods, waste forms, and disposal sites are evaluated from radiological and mercury contamination estimates.

  20. Testing and Disposal Strategy for Secondary Wastes from Vitrification of Sodium-Bearing Waste at the Idaho Nuclear Technology and Engineering Center

    SciTech Connect (OSTI)

    Herbst, Alan Keith

    2002-01-01

    The Idaho National Engineering and Environmental Laboratory (INEEL) is considering vitrification to process liquid sodium-bearing waste. Preliminary studies were completed to evaluate the potential secondary wastes comprise acidic and caustic scrubber solutions, HEPA filters, activated carbon, and ion exchange media. Possible treatment methods, waste forms, and disposal sites are evaluated from radiological and mercury contamination estimates.

  1. Advanced hot-gas filter development. Topical report, September 30, 1994--May 31, 1996

    SciTech Connect (OSTI)

    Lane, J.E.; LeCostaouec, J.F.; Painter, C.J.; Sue, W.A.; Radford, K.C.

    1996-12-31

    The application of high-performance, high-temperature particulate control devices is considered to be beneficial to advanced fossil fuel processing technology, to selected high-temperature industrial processes, and to waste incineration concepts. Ceramic rigid filters represent the most attractive technology for these applications due to their capability to withstand high-temperature corrosive environments. However, current generation monolithic filters have demonstrated poor resistance to crack propagation and can experience catastrophic failure during use. To address this problem, ceramic fiber-reinforced ceramic matrix composite (CMC) filter materials are needed for reliable damage tolerant candle filters. This program is focused on the development of an oxide-fiber reinforced oxide material composite filter material that is cost competitive with prototype next generation filters. This goal would be achieved through the development of a low cost sol-gel fabrication process and a three-dimensional fiber architecture optimized for high volume filter manufacturing. The 3D continuous fiber reinforcement provides a damage tolerant structure which is not subject to delamination-type failures. This report documents the Phase 1, Filter Material Development and Evaluation, results. Section 2 provides a program summary. Technical results, including experimental procedures, are presented and discussed in Section 3. Section 4 and 5 provide the Phase 1 conclusions and recommendations, respectively. The remaining sections cover acknowledgements and references.

  2. Nuclear Nonproliferation

    SciTech Connect (OSTI)

    Atkins-Duffin, C E

    2008-12-10

    With an explosion equivalent of about 20kT of TNT, the Trinity test was the first demonstration of a nuclear weapon. Conducted on July 16, 1945 in Alamogordo, NM this site is now a Registered National Historic Landmark. The concept and applicability of nuclear power was demonstrated on December 20, 1951 with the Experimental Breeder Reactor Number One (EBR-1) lit four light bulbs. This reactor is now a Registered National Historic Landmark, located near Arco, ID. From that moment forward it had been clearly demonstrated that nuclear energy has both peaceful and military applications and that the civilian and military fuel cycles can overlap. For the more than fifty years since the Atoms for Peace program, a key objective of nuclear policy has been to enable the wider peaceful use of nuclear energy while preventing the spread of nuclear weapons. Volumes have been written on the impact of these two actions on the world by advocates and critics; pundits and practioners; politicians and technologists. The nations of the world have woven together a delicate balance of treaties, agreements, frameworks and handshakes that are representative of the timeframe in which they were constructed and how they have evolved in time. Collectively these vehicles attempt to keep political will, nuclear materials and technology in check. This paper captures only the briefest abstract of the more significant aspects on the Nonproliferation Regime. Of particular relevance to this discussion is the special nonproliferation sensitivity associated with the uranium isotope separation and spent fuel reprocessing aspects of the nuclear fuel cycle.

  3. DOE Deputy Secretary and Rosatom Director Visit Y-12, Oak Ridge National Laboratory During First Meeting of U.S.-Russian Nuclear Energy and Nuclear Security Working Group

    Broader source: Energy.gov [DOE]

    Discussions emphasize mutual efforts to counter emerging threats to nuclear materials and cooperation on civil nuclear technologies

  4. Criteria for calculating the efficiency of deep-pleated HEPA filters with aluminum separators during and after design basis accidents

    SciTech Connect (OSTI)

    Bergman, W.; First, M.W.; Anderson, W.L.; Gilbert, H.; Jacox, J.W.

    1995-02-01

    The authors have reviewed the literature on the performance of high efficiency particulate air (HEPA) filters under normal and abnormal conditions to establish criteria for calculating the efficiency of HEPA filters in a DOE nonreactor nuclear facility during and after a Design Basis Accident (DBA). This study is only applicable to the standard deep-pleated HEPA filter with aluminum separators as specified in ASME N509. The literature review included the performance of new filters and parameters that may cause deterioration in the filter performance such as filter age, radiation, corrosive chemicals, seismic and rough handling, high temperature, moisture, particle clogging, high air flow and pressure pulses. The deterioration of the filter efficiency depends on the exposure parameters; in severe exposure conditions the filter will be structurally damaged and have a residual efficiency of 0%. Despite the many studies on HEPA filter performance under adverse conditions, there are large gaps and limitations in the data that introduce significant error in the estimates of HEPA filter efficiencies under DBA conditions. Because of this limitation, conservative values of filter efficiency were chosen when there was insufficient data.

  5. National Nuclear Chemistry Summer School

    Broader source: Energy.gov [DOE]

    The Division of Nuclear Chemistry and Technology of the American Chemical Society (ACS) is sponsoring two INTENSIVE six-week Summer Schools in Nuclear and Radiochemistry for undergraduates. Funding is provided by the US Department of Energy.

  6. National Nuclear Chemistry Summer School

    Broader source: Energy.gov [DOE]

    he Division of Nuclear Chemistry and Technology of the American Chemical Society (ACS) is sponsoring two INTENSIVE six-week Summer Schools in Nuclear and Radiochemistry for undergraduates. Funding...

  7. Development of Advanced Particulate Filters | Department of Energy

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

    2012 DOE Hydrogen and Fuel Cells Program and Vehicle Technologies Program Annual Merit Review and Peer Evaluation Meeting PDF icon ace024_lee_2012_o.pdf More Documents & Publications Particulate Emissions Control by Advanced Filtration Systems or GDI Engines Diesel Particulate Filter: A Success for Faurecia Exhaust Systems Uncovering Fundamental Ash-Formation Mechanisms and Potential Means to Control the Impact on DPF Performance and Engine Efficiency

  8. Diesel Soot Filter Characterization and Modeling for Advanced Substrates |

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

    Department of Energy 9 DOE Hydrogen Program and Vehicle Technologies Program Annual Merit Review and Peer Evaluation Meeting, May 18-22, 2009 -- Washington D.C. PDF icon ace_23_gallant.pdf More Documents & Publications CLEERS Coordination & Development of Catalyst Process Kinetic Data Development of Optimal Catalyst Designs and Operating Strategies for Lean NOx Reduction in Coupled LNT-SCR Systems CLEERS Activities: Diesel Soot Filter Characterization & NOx Control Fundamental

  9. Predictive Science Academic Alliance Program | National Nuclear...

    National Nuclear Security Administration (NNSA)

    Predictive Science Academic Alliance Program | National Nuclear Security Administration ... Home About Us Our Programs Defense Programs Future Science & Technology Programs ...

  10. Ceramic hot-gas filter

    DOE Patents [OSTI]

    Connolly, E.S.; Forsythe, G.D.; Domanski, D.M.; Chambers, J.A.; Rajendran, G.P.

    1999-05-11

    A ceramic hot-gas candle filter is described having a porous support of filament-wound oxide ceramic yarn at least partially surrounded by a porous refractory oxide ceramic matrix, and a membrane layer on at least one surface thereof. The membrane layer may be on the outer surface, the inner surface, or both the outer and inner surface of the porous support. The membrane layer may be formed of an ordered arrangement of circularly wound, continuous filament oxide ceramic yarn, a ceramic filler material which is less permeable than the filament-wound support structure, or some combination of continuous filament and filler material. A particularly effective membrane layer features circularly wound filament with gaps intentionally placed between adjacent windings, and a filler material of ceramic particulates uniformly distributed throughout the gap region. The filter can withstand thermal cycling during back pulse cleaning and is resistant to chemical degradation at high temperatures.

  11. Ceramic hot-gas filter

    DOE Patents [OSTI]

    Connolly, Elizabeth Sokolinski (Wilmington, DE); Forsythe, George Daniel (Landenberg, PA); Domanski, Daniel Matthew (New Castle, DE); Chambers, Jeffrey Allen (Hockessin, DE); Rajendran, Govindasamy Paramasivam (Boothwyn, PA)

    1999-01-01

    A ceramic hot-gas candle filter having a porous support of filament-wound oxide ceramic yarn at least partially surrounded by a porous refractory oxide ceramic matrix, and a membrane layer on at least one surface thereof. The membrane layer may be on the outer surface, the inner surface, or both the outer and inner surface of the porous support. The membrane layer may be formed of an ordered arrangement of circularly wound, continuous filament oxide ceramic yarn, a ceramic filler material which is less permeable than the filament-wound support structure, or some combination of continuous filament and filler material. A particularly effective membrane layer features circularly wound filament with gaps intentionally placed between adjacent windings, and a filler material of ceramic particulates uniformly distributed throughout the gap region. The filter can withstand thermal cycling during backpulse cleaning and is resistant to chemical degradation at high temperatures.

  12. Filter for a drill string

    DOE Patents [OSTI]

    Hall, David R.; Pixton, David S.; Briscoe, Michael; McPherson, James

    2007-12-04

    A filter for a drill string comprises a perforated receptacle having an open end and a perforated end and first and second mounting surfaces are adjacent the open end. A transmission element is disposed within each of the first and second mounting surfaces. A capacitor may modify electrical characteristics of an LC circuit that comprises the transmission elements. The respective transmission elements are in communication with each other and with a transmission network integrated into the drill string. The transmission elements may be inductive couplers, direct electrical contacts, or optical couplers. In some embodiments of the present invention, the filter comprises an electronic component. The electronic component may be selected from the group consisting of a sensor, a router, a power source, a clock source, a repeater, and an amplifier.

  13. PUNT | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    PUNT U.S. and China Continue Cooperative Partnership to Advance Safe, Secure Civil Nuclear Energy for Clean Energy Future DOE/NNSA Hosts 11th U.S.-China Peaceful Uses of Nuclear Technology Meeting at Savannah River National Laboratory in Aiken, South Carolina (Aiken, South Carolina) - On May 10-11, 2016 the U.S. Department of Energy's (DOE) National Nuclear Security Administration (NNSA) and the China... United States and China Continue Partnership for the Peaceful Uses of Nuclear Technology

  14. Electrically heated particulate filter restart strategy

    DOE Patents [OSTI]

    Gonze, Eugene V [Pinckney, MI; Ament, Frank [Troy, MI

    2011-07-12

    A control system that controls regeneration of a particulate filter is provided. The system generally includes a propagation module that estimates a propagation status of combustion of particulate matter in the particulate filter. A regeneration module controls current to the particulate filter to re-initiate regeneration based on the propagation status.

  15. In situ microbial filter used for bioremediation

    DOE Patents [OSTI]

    Carman, M. Leslie; Taylor, Robert T.

    2000-01-01

    An improved method for in situ microbial filter bioremediation having increasingly operational longevity of an in situ microbial filter emplaced into an aquifer. A method for generating a microbial filter of sufficient catalytic density and thickness, which has increased replenishment interval, improved bacteria attachment and detachment characteristics and the endogenous stability under in situ conditions. A system for in situ field water remediation.

  16. Filter:Incentives by Efficiency or Renewable | Open Energy Information

    Open Energy Info (EERE)

    Datasets Community Login | Sign Up Search Filter Edit History Filter:Incentives by Efficiency or Renewable Jump to: navigation, search This filter covers the property Incentive...

  17. Neutron Imaging of Diesel Particulate Filters | Department of...

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

    Diesel Particulate Filters Neutron Imaging of Diesel Particulate Filters Neutron computed tomography shows soot and ash loading in a cordierite diesel particulate filter PDF icon ...

  18. Design rules for dislocation filters (Journal Article) | SciTech...

    Office of Scientific and Technical Information (OSTI)

    Design rules for dislocation filters Citation Details In-Document Search Title: Design rules for dislocation filters The efficacy of strained layer threading dislocation filter...

  19. Belgium Nuclear Security Summit: Fact Sheet | National Nuclear Security

    National Nuclear Security Administration (NNSA)

    Administration Nuclear Security Summit: Fact Sheet March 27, 2012 As one of the leaders in nuclear technology development, Belgium's nuclear program has covered all aspects of nuclear fuel cycle including reprocessing and operated a reprocessing plant between 1966 and 1974. Belgium signed the NPT in 1975 as a non-weapons state, but has retained a leading nuclear technology research center and derives over 50% of its energy from nuclear power using 7 power reactors. SCK-CEN is one of the

  20. China | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    China NNSA Deputy Administrator Creedon Travels to China United States and China Continue Partnership for the Peaceful Uses of Nuclear Technology United States and China Mark 10th ...

  1. Leadership | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    People Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy ... military, and commercial technological advances in countries of a proliferation concern. ...

  2. Nonproliferation | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    dispose of dangerous nuclear and radiological material, and detect and control the proliferation of related WMD technology and expertise. Vietnam Removal Working in close...

  3. Experimental and simulational study of the operation conditions for a high transmission mass filter

    SciTech Connect (OSTI)

    Ayesh, A. I.; Lassesson, A.; Brown, S. A.; Dunbar, A. D. F.; Kaufmann, M.; Partridge, J. G.; Reichel, R.; Lith, J. van

    2007-05-15

    The operation conditions of a double pulsed field mass filter were studied using both experiment and simulation. The mass filter consists of two pairs of parallel plates and operates on the time-of-flight principle. The study showed that the ions' beam deflection angle is a critical factor in optimizing the mass filter transmission efficiency. This angle is dependent on the accelerating voltage, ion mass, and horizontal velocity of the ions. The optimum operating conditions for the mass filter were found and used to study the mass distribution of palladium ions produced by a magnetron sputtering source. The study shows that this mass filter is suitable for technological applications because of its high transmission and wide mass range.

  4. DOE-HDBK-1169-2003; DOE Handbook Nuclear Air Cleaning Handbook

    Energy Savers [EERE]

    ... 8-1 8.2 Proof of Design - HEPA Filter Design Qualification testing for Nuclear Service ......8-3 8.3 Manufacturer's Quality Control - ...

  5. Development of Refrigerant Change Indicator and Dirty Air Filter Sensor

    SciTech Connect (OSTI)

    Mei, V.

    2003-06-24

    The most common problems affecting residential and light commercial heating, ventilation, and air-conditioning (HVAC) systems are slow refrigerant leaks and dirty air filters. Equipment users are usually not aware of a problem until most of the refrigerant has escaped or the air filter is clogged with dirt. While a dirty air filter can be detected with a technology based on the air pressure differential across the filter, such as a ''whistling'' indicator, it is not easy to incorporate this technology into existing HVAC diagnostic equipment. Oak Ridge National Laboratory is developing a low-cost, nonintrusive refrigerant charge indicator and dirty air filter detection sensor. The sensors, based on temperature measurements, will be inexpensive and easy to incorporate into existing heat pumps and air conditioners. The refrigerant charge indicator is based on the fact that when refrigerant starts to leak, the evaporator coil temperature starts to drop and the level of liquid subcooling drops. When the coil temperature or liquid subcooling drops below a preset reading, a signal, such as a yellow warning light, can be activated to warn the equipment user that the system is undercharged. A further drop of coil temperature or liquid subcooling below another preset reading would trigger a second warning signal, such as a red warning light, to warn the equipment user that the unit now detects a leak and immediate action should be taken. The warning light cannot be turned off until it is re-set by a refrigeration repairman. To detect clogged air filters, two additional temperature sensors can be applied, one each across the evaporator. When the air filter is accumulating buildup, the temperature differential across the evaporator will increase because of the reduced airflow. When the temperature differential reaches a pre-set reading, a signal will be sent to the equipment user that the air filter needs to be changed. A traditional refrigerant charge indicator requires intrusion into the system to measure the refrigerant high-side and low-side pressures. Once the pressures are known, based on the equipment's refrigerant charging chart? or in most cases, based on the technician's experience? the refrigerant charging status is determined. However, there is a catch: by the time a refrigeration technician is called, most of the refrigerant has already escaped into the atmosphere. The new technology provides a real-time warning so that when, say, 20% of the refrigerant has leaked, the equipment users will be warned, even though the equipment is still functioning properly at rated capacity. Temperature sensors are becoming very accurate and very low in cost, compared with pressure sensors. Using temperature sensors to detect refrigerant charge status is inherently nonintrusive, inexpensive, and accurate. With the addition of two temperature sensors for detecting dirty air filters, the capability of the diagnostic equipment is further enhanced with very little added cost. This report provides laboratory test data on the change of indoor coil refrigerant temperature and subcooling as a function of refrigerant charge for a 2-ton split heat pump system. The data can be used in designing the indicators for refrigerant loss and dirty air filter sensors.

  6. Filter for isotopic alteration of mercury vapor

    DOE Patents [OSTI]

    Grossman, M.W.; George, W.A.

    1989-06-13

    A filter is described for enriching the [sup 196]Hg content of mercury, including a reactor, a low pressure electric discharge lamp containing a fill of mercury and an inert gas. A filter is arranged concentrically around the lamp. The reactor is arranged around said filter, whereby radiation from said lamp passes through the filter and into said reactor. The lamp, the filter and the reactor are formed of quartz, and are transparent to ultraviolet light. The [sup 196]Hg concentration in the mercury fill is less than that which is present in naturally occurring mercury, that is, less than about 0.146 atomic weight percent. Hydrogen is also included in the fill and serves as a quenching gas in the filter, the hydrogen also serving to prevent disposition of a dark coating on the interior of the filter. 9 figs.

  7. Filter for isotopic alteration of mercury vapor

    DOE Patents [OSTI]

    Grossman, Mark W.; George, William A.

    1989-01-01

    A filter for enriching the .sup.196 Hg content of mercury, including a reactor, a low pressure electric discharge lamp containing a fill of mercury and an inert gas. A filter is arranged concentrically around the lamp. The reactor is arranged around said filter, whereby radiation from said lamp passes through the filter and into said reactor. The lamp, the filter and the reactor are formed of quartz, and are transparent to ultraviolet light. The .sup.196 Hg concentration in the mercury fill is less than that which is present in naturally occurring mercury, that is less than about 0.146 atomic weight percent. Hydrogen is also included in the fill and serves as a quenching gas in the filter, the hydrogen also serving to prevent disposition of a dark coating on the interior of the filter.

  8. Filter unit for use at high temperatures

    DOE Patents [OSTI]

    Ciliberti, David F.; Lippert, Thomas E.

    1988-01-01

    A filtering unit for filtering particulates from high temperature gases uses a spiral ceramic spring to bias a ceramic, tubular filter element into sealing contact with a flange about an aperture of a metallic tube sheet. The ceramic spiral spring may contact the upper edge of the filter element and be restrained by a stop member spaced from one end of the tube sheet, or the spring may contact the bottom of the filter element and be restrained by a support member spaced from the opposite end of the tube sheet. The stop member and support member are adjustably secured to the tube sheet. A filtering system uses the ceramic spiral spring to bias a plurality of ceramic, tubular filter elements in a respective plurality of apertures in a tube sheet which divides a vessel into upper and lower enclosed sections.

  9. Ceramic fiber ceramic matrix filter development

    SciTech Connect (OSTI)

    Judkins, R.R.; Stinton, D.P.; Smith, R.G.; Fischer, E.M.

    1994-09-01

    The objectives of this project were to develop a novel type of candle filter based on a ceramic fiber-ceramic matrix composite material, and to extend the development to full-size, 60-mm OD by 1-meter-long candle filters. The goal is to develop a ceramic filter suitable for use in a variety of fossil energy system environments such as integrated coal gasification combined cycles (IGCC), pressurized fluidized-bed combustion (PFBC), and other advanced coal combustion environments. Further, the ceramic fiber ceramic matrix composite filter, hereinafter referred to as the ceramic composite filter, was to be inherently crack resistant, a property not found in conventional monolithic ceramic candle filters, such as those fabricated from clay-bonded silicon carbide. Finally, the adequacy of the filters in the fossil energy system environments is to be proven through simulated and in-plant tests.

  10. Diesel Particulate Filter Technology for Low-Temperature and...

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

    Applications Part 1 Aftertreatment Modeling Status, Futur Potential, and Application Issues Exhaust Aftertreatment and Low Pressure Loop EGR Applied to an Off-Highway Engine

  11. Mercury Oxidation via Catalytic Barrier Filters Phase II

    SciTech Connect (OSTI)

    Wayne Seames; Michael Mann; Darrin Muggli; Jason Hrdlicka; Carol Horabik

    2007-09-30

    In 2004, the Department of Energy National Energy Technology Laboratory awarded the University of North Dakota a Phase II University Coal Research grant to explore the feasibility of using barrier filters coated with a catalyst to oxidize elemental mercury in coal combustion flue gas streams. Oxidized mercury is substantially easier to remove than elemental mercury. If successful, this technique has the potential to substantially reduce mercury control costs for those installations that already utilize baghouse barrier filters for particulate removal. Completed in 2004, Phase I of this project successfully met its objectives of screening and assessing the possible feasibility of using catalyst coated barrier filters for the oxidation of vapor phase elemental mercury in coal combustion generated flue gas streams. Completed in September 2007, Phase II of this project successfully met its three objectives. First, an effective coating method for a catalytic barrier filter was found. Second, the effects of a simulated flue gas on the catalysts in a bench-scale reactor were determined. Finally, the performance of the best catalyst was assessed using real flue gas generated by a 19 kW research combustor firing each of three separate coal types.

  12. Nuclear Fuel Reprocessing

    SciTech Connect (OSTI)

    Michael F. Simpson; Jack D. Law

    2010-02-01

    This is an a submission for the Encyclopedia of Sustainable Technology on the subject of Reprocessing Spent Nuclear Fuel. No formal abstract was required for the article. The full article will be attached.

  13. A Green Technology

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

    Green Technology - Sandia Energy Energy Search Icon Sandia Home Locations Contact Us Employee Locator Energy & Climate Secure & Sustainable Energy Future Stationary Power Energy Conversion Efficiency Solar Energy Wind Energy Water Power Supercritical CO2 Geothermal Natural Gas Safety, Security & Resilience of the Energy Infrastructure Energy Storage Nuclear Power & Engineering Grid Modernization Battery Testing Nuclear Fuel Cycle Defense Waste Management Programs Advanced Nuclear

  14. Smart Grid Technologies

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

    Technologies - Sandia Energy Energy Search Icon Sandia Home Locations Contact Us Employee Locator Energy & Climate Secure & Sustainable Energy Future Stationary Power Energy Conversion Efficiency Solar Energy Wind Energy Water Power Supercritical CO2 Geothermal Natural Gas Safety, Security & Resilience of the Energy Infrastructure Energy Storage Nuclear Power & Engineering Grid Modernization Battery Testing Nuclear Fuel Cycle Defense Waste Management Programs Advanced Nuclear

  15. Technology disrupted

    SciTech Connect (OSTI)

    Papatheodorou, Y.

    2007-02-15

    Three years ago, the author presented a report on power generation technologies which in summary said 'no technology available today has the potential of becoming transformational or disruptive in the next five to ten years'. In 2006 the company completed another strategic view research report covering the electric power, oil, gas and unconventional energy industries and manufacturing industry. This article summarises the strategic view findings and then revisits some of the scenarios presented in 2003. The cost per megawatt-hour of the alternatives is given for plants ordered in 2005 and then in 2025. The issue of greenhouse gas regulation is dealt with through carbon sequestration and carbon allowances or an equivalent carbon tax. Results reveal substantial variability through nuclear power, hydro, wind, geothermal and biomass remain competitive through every scenario. Greenhouse gas scenario analysis shows coal still be viable, albeit less competitive against nuclear and renewable technologies. A carbon tax or allowance at $24 per metric ton has the same effect on IGCC cost as a sequestration mandate. However, the latter would hurt gas plants much more than a tax or allowance. Sequestering CO{sub 2} from a gas plant is almost as costly per megawatt-hour as for coal. 5 refs., 5 figs., 5 tabs.

  16. Hybrid Plasma Reactor/Filter for Transportable Collective Protection Systems

    SciTech Connect (OSTI)

    Josephson, Gary B.; Tonkyn, Russell G.; Frye, J. G.; Riley, Brian J.; Rappe, Kenneth G.

    2011-04-06

    Pacific Northwest National Laboratory (PNNL) has performed an assessment of a Hybrid Plasma/Filter system as an alternative to conventional methods for collective protection. The key premise of the hybrid system is to couple a nonthermal plasma (NTP) reactor with reactive adsorption to provide a broader envelope of protection than can be provided through a single-solution approach. The first step uses highly reactive species (e.g. oxygen radicals, hydroxyl radicals, etc.) created in a nonthermal plasma (NTP) reactor to destroy the majority (~75% - 90%) of an incoming threat. Following the NTP reactor an O3 reactor/filter uses the O3 created in the NTP reactor to further destroy the remaining organic materials. This report summarizes the laboratory development of the Hybrid Plasma Reactor/Filter to protect against a worst-case simulant, methyl bromide (CH3Br), and presents a preliminary engineering assessment of the technology to Joint Expeditionary Collective Protection performance specifications for chemical vapor air purification technologies.

  17. Method and apparatus for filtering gas with a moving granular filter bed

    DOE Patents [OSTI]

    Brown, Robert C.; Wistrom, Corey; Smeenk, Jerod L.

    2007-12-18

    A method and apparatus for filtering gas (58) with a moving granular filter bed (48) involves moving a mass of particulate filter material (48) downwardly through a filter compartment (35); tangentially introducing gas into the compartment (54) to move in a cyclonic path downwardly around the moving filter material (48); diverting the cyclonic path (58) to a vertical path (62) to cause the gas to directly interface with the particulate filter material (48); thence causing the gas to move upwardly through the filter material (48) through a screened partition (24, 32) into a static upper compartment (22) of a filter compartment for exodus (56) of the gas which has passed through the particulate filter material (48).

  18. Specification for HEPA Filters Used by DOE Contractors

    Energy Savers [EERE]

    3020-2015 June 2015 Supersedes DOE-STD-3020-2005 December 2005 DOE TECHNICAL STANDARD Specification for HEPA Filters Used by DOE Contractors U.S. Department of Energy AREA SAFT Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. DOE-STD-3020-2015 i This document is available on the Department of Energy Technical Standards Program Web page at http://www.energy.gov/ehss/services/nuclear-safety/department-energy-technical-standards- program

  19. Naval Nuclear Propulsion | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    Naval Nuclear Propulsion

  20. CHARACTERIZATION OF A RIGID BARRIER FILTER SYSTEM

    SciTech Connect (OSTI)

    Chiang, Ta-Kuan

    2001-11-06

    A mathematical model is formulated to describe the dynamics of a rigid barrier filter system. Complete with filtration, regeneration and particle re-deposition, this model provides sizing information for new filter systems and diagnostic information for operating filter systems. To turn this model into a practical and smart filter system predictive model, monitoring devices for variables such as real-time particle concentration and size distribution are currently under laboratory development. The program goal is to introduce a smart filter system to supervise its operation and to assure its system reliability. Primarily, a smart filter system will update operating information, sound up malfunction alarms, and provide self-activated measures such as adjusting the cleaning frequency, intensity and back-pulse duration.

  1. Face crack reduction strategy for particulate filters

    DOE Patents [OSTI]

    Gonze, Eugene V [Pinckney, MI

    2012-01-31

    A system comprises a particulate matter (PM) filter that comprises an upstream end for receiving exhaust gas, a downstream end and at least one portion. A control module initiates combustion of PM in the PM filter using a heater and selectively adjusts oxygen levels of the exhaust gas to adjust a temperature of combustion adjacent to the at least one portion of the PM filter. A method comprises providing a particulate matter (PM) filter that comprises an upstream end for receiving exhaust gas, a downstream end and at least one portion; initiating combustion of PM in the PM filter using a heater; selectively adjusting oxygen levels of the exhaust gas to adjust a temperature of combustion adjacent to the at least one portion of the PM filter.

  2. Miniature lowpass filters in low loss 9k7 LTCC

    SciTech Connect (OSTI)

    Dai, Steve; Hsieh, Lung -Hwa

    2015-04-01

    DuPont 9k7 low temperature cofired ceramic (LTCC) is a low loss, or high quality factor Q, tape system targeting at radio frequency (RF) applications. This paper reports the effect of a critical process parameter, heating rate, on the densification and dielectric properties of the 9k7 LTCC. The role of competing densification and crystallization during the sintering of 9k7 is discussed. The high Q of DuPont 9K7 can be used to improve RF system performance, for example a better receiver noise figure, by designing embedded passive RF components such as inductors, capacitors and filters. As a result, miniaturized multilayer low pass filters (LPF) with a wide stopband were fabricated to showcase the technology.

  3. Miniature lowpass filters in low loss 9k7 LTCC

    DOE Public Access Gateway for Energy & Science Beta (PAGES Beta)

    Dai, Steve; Hsieh, Lung -Hwa

    2015-04-01

    DuPont 9k7 low temperature cofired ceramic (LTCC) is a low loss, or high quality factor Q, tape system targeting at radio frequency (RF) applications. This paper reports the effect of a critical process parameter, heating rate, on the densification and dielectric properties of the 9k7 LTCC. The role of competing densification and crystallization during the sintering of 9k7 is discussed. The high Q of DuPont 9K7 can be used to improve RF system performance, for example a better receiver noise figure, by designing embedded passive RF components such as inductors, capacitors and filters. As a result, miniaturized multilayer low passmore » filters (LPF) with a wide stopband were fabricated to showcase the technology.« less

  4. DOE-HDBK-1169-2003; DOE Handbook Nuclear Air Cleaning Handbook

    Energy Savers [EERE]

    ... USAEC Report TID-7023, August 1961. Nuclear Air Cleaning Handbook U.S. Department of ... Nuclear Air Cleaning Handbook U.S. Department of Energy A-4 5. Install the filter with ...

  5. Zone heated diesel particulate filter electrical connection

    DOE Patents [OSTI]

    Gonze, Eugene V.; Paratore, Jr., Michael J.

    2010-03-30

    An electrical connection system for a particulate filter is provided. The system includes: a particulate filter (PF) disposed within an outer shell wherein the PF is segmented into a plurality of heating zones; an outer mat disposed between the particulate filter and the outer shell; an electrical connector coupled to the outer shell of the PF; and a plurality of printed circuit connections that extend along the outer surface of the PF from the electrical connector to the plurality of heating zones.

  6. Diesel particulate filter with zoned resistive heater

    DOE Patents [OSTI]

    Gonze, Eugene V [Pinckney, MI

    2011-03-08

    A diesel particulate filter assembly comprises a diesel particulate filter (DPF) and a heater assembly. The DPF filters a particulate from exhaust produced by an engine. The heater assembly has a first metallic layer that is applied to the DPF, a resistive layer that is applied to the first metallic layer, and a second metallic layer that is applied to the resistive layer. The second metallic layer is etched to form a plurality of zones.

  7. The development of a porous silicon nitride crossflow filter; Final report, September 1988--September 1992

    SciTech Connect (OSTI)

    1992-09-01

    This report summarizes the work performed in developing a permeable form of silicon nitride for application to ceramic crossflow filters for use in advanced coal-fired electric power plants. The program was sponsored by the Department of Energy Morgantown Energy Technology Center and consisted of a design analysis and material development phase and a filter manufacture and demonstration phase. The crossflow filter design and operating requirements were defined. A filter design meeting the requirements was developed and thermal and stress analyses were performed. Material development efforts focused initially on reaction-bonded silicon nitride material. This approach was not successful, and the materials effort was refocused on the development of a permeable form of sintered silicon nitride (SSN). This effort was successful. The SSN material was used for the second phase of the program, filter manufacture and evaluation. Four half-scale SAN filter modules were fabricated. Three of the modules were qualified for filter performance tests. Tests were performed on two of the three qualified modules in the High-Temperature, High-Pressure facility at the Westinghouse Science and Technology Center. The first module failed on test when it expanded into the clamping device, causing dust leakage through the filter. The second module performed well for a cumulative 150-hr test. It displayed excellent filtration capability during the test. The blowback pulse cleaning was highly effective, and the module apparently withstood the stresses induced by the periodic pulse cleaning. Testing of the module resumed, and when the flow of combustion gas through the filter was doubled, cracks developed and the test was concluded.

  8. Maintaining the Stockpile | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    Maintaining the Stockpile NNSA ensures the Nation sustains a safe, secure, and effective nuclear deterrent through the application of science, technology, engineering, and manufacturing. To deal with the changing face of nuclear deterrence and more-widely dispersed nuclear knowledge, NNSA also ensures the United States maintains excellence in nuclear science and technology that is second to none. Within the Nuclear Security Enterprise, the central mission which includes maintaining the active

  9. Hot-Gas Filter Ash Characterization Project

    SciTech Connect (OSTI)

    Swanson, M.L.; Hurley, J.P.; Dockter, B.A.; O`Keefe, C.A.

    1997-07-01

    Large-scale hot-gas filter testing over the past 10 years has revealed numerous cases of cake buildup on filter elements that has been difficult, if not impossible, to remove. At times, the cake can blind or bridge between candle filters, leading to filter failure. Physical factors, including particle-size distribution, particle shape, the aerodynamics of deposition, and system temperature, contribute to the difficulty in removing the cake, but chemical factors such as surface composition and gas-solid reactions also play roles in helping to bond the ash to the filters or to itself. This project is designed to perform the research necessary to determine the fuel-, sorbent-, and operations-related conditions that lead to blinding or bridging of hot-gas particle filters. The objectives of the project are threefold: (1) Determine the mechanisms by which a difficult-to-clean ash is formed and how it bridges hot-gas filters (2) Develop a method to determine the rate of bridging based on analyses of the feed coal and sorbent, filter properties, and system operating conditions and (3) Suggest and test ways to prevent filter bridging.

  10. Sandia National Laboratories: New phononic filter

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

    that rely solely on conventional electronics," says manager Patrick Chu. The radio frequency (RF) filters, which promise both high-bandwidth and wide functional flexibility,...

  11. Microhydropower Conveyance and Filter Basics | Department of...

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

    Before water enters the turbine or waterwheel of a microhydropower system, it is funneled through a series of components that control its flow and filter out debris. These ...

  12. In-place filter testing summary

    SciTech Connect (OSTI)

    Ortiz, J.P.; Garcia, E.D.; Ortega, J.M.

    1988-03-01

    The most common method of identifying particle penetration through a filter or adsorber system is through the performance of a periodic penetration test, i.e., in-place test or leak test using an aerosol or gas vapor to challenge the filter or adsorber system. The aerosol is usually formed by vaporization of a liquid, di-2(ethelhexyl sebacate) (DEHS), and allowed to condense to form liquid particles of a certain size and distribution. The gas vapor is formed by vaporization of Freon 11 liquid. The periodic penetration test, although conducted annually, can and has been demonstrated to show the beginning degradation of a filter or adsorber system. Other evidence of penetration can include detection of radiation downstream of the filter system or the existence of an unusually low pressure drop across the filter, i.e., torn filter, etc. However, these kinds of occurrences show up instantaneously and could release radioactive material to the atmosphere before the systems could be shut down. When a filter system fails the in--place test or is showing evidence of.filter or component degradation, corrective measures are put into place in order to return,the system back to its best operating condition. This report presents a summary of all filter tests.

  13. Amplitude- and rise-time-compensated filters

    DOE Patents [OSTI]

    Nowlin, Charles H.

    1984-01-01

    An amplitude-compensated rise-time-compensated filter for a pulse time-of-occurrence (TOOC) measurement system is disclosed. The filter converts an input pulse, having the characteristics of random amplitudes and random, non-zero rise times, to a bipolar output pulse wherein the output pulse has a zero-crossing time that is independent of the rise time and amplitude of the input pulse. The filter differentiates the input pulse, along the linear leading edge of the input pulse, and subtracts therefrom a pulse fractionally proportional to the input pulse. The filter of the present invention can use discrete circuit components and avoids the use of delay lines.

  14. Continuous air monitor filter changeout apparatus

    DOE Patents [OSTI]

    Rodgers, John C.

    2008-07-15

    An apparatus and corresponding method for automatically changing out a filter cartridge in a continuous air monitor. The apparatus includes: a first container sized to hold filter cartridge replacements; a second container sized to hold used filter cartridges; a transport insert connectively attached to the first and second containers; a shuttle block, sized to hold the filter cartridges that is located within the transport insert; a transport driver mechanism means used to supply a motive force to move the shuttle block within the transport insert; and, a control means for operating the transport driver mechanism.

  15. Proceedings of the 21st Seismic Research Symposium: Technologies...

    Office of Scientific and Technical Information (OSTI)

    Nuclear Test-Ban Treaty Citation Details In-Document Search Title: Proceedings of the 21st Seismic Research Symposium: Technologies for Monitoring The Comprehensive Nuclear ...

  16. Overview paper on nuclear power

    SciTech Connect (OSTI)

    Spiewak, I.; Cope, D.F.

    1980-09-01

    This paper was prepared as an input to ORNL's Strategic Planning Activity, ORNL National Energy Perspective (ONEP). It is intended to provide historical background on nuclear power, an analysis of the mission of nuclear power, a discussion of the issues, the technology choices, and the suggestion of a strategy for encouraging further growth of nuclear power.

  17. 2012 Monitoring Research Review: Ground-Based Nuclear Explosion...

    Office of Scientific and Technical Information (OSTI)

    Review: Ground-Based Nuclear Explosion Monitoring Technologies Citation Details In-Document Search Title: 2012 Monitoring Research Review: Ground-Based Nuclear Explosion Monitoring ...

  18. (Environmental technology)

    SciTech Connect (OSTI)

    Boston, H.L.

    1990-10-12

    The traveler participated in a conference on environmental technology in Paris, sponsored by the US Embassy-Paris, US Environmental Protection Agency (EPA), the French Environmental Ministry, and others. The traveler sat on a panel for environmental aspects of energy technology and made a presentation on the potential contributions of Oak Ridge National Laboratory (ORNL) to a planned French-American Environmental Technologies Institute in Chattanooga, Tennessee, and Evry, France. This institute would provide opportunities for international cooperation on environmental issues and technology transfer related to environmental protection, monitoring, and restoration at US Department of Energy (DOE) facilities. The traveler also attended the Fourth International Conference on Environmental Contamination in Barcelona. Conference topics included environmental chemistry, land disposal of wastes, treatment of toxic wastes, micropollutants, trace organics, artificial radionuclides in the environment, and the use biomonitoring and biosystems for environmental assessment. The traveler presented a paper on The Fate of Radionuclides in Sewage Sludge Applied to Land.'' Those findings corresponded well with results from studies addressing the fate of fallout radionuclides from the Chernobyl nuclear accident. There was an exchange of new information on a number of topics of interest to DOE waste management and environmental restoration needs.

  19. heu | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    heu NNSA deputy administrator travels to Ukraine Earlier this month, Deputy Administrator for Defense Nuclear Nonproliferation Anne Harrington traveled to Ukraine to celebrate the 20th anniversary of the Science and Technology Center in Ukraine (STCU) and visit the Neutron Source Facility at the Kharkiv Institute of Physics and Technology. The U... NNSA keeps the promises borne out of the Nuclear Security Summit On Thursday and Friday President Obama will host his fourth and final Nuclear

  20. Nuclear Science

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

    Nuclear Science Nuclear Science Experimental and theoretical nuclear research carried out at NERSC is driven by the quest for improving our understanding of the building blocks of...

  1. Nuclear Security for Floating Nuclear Power Plants

    SciTech Connect (OSTI)

    Skiba, James M.; Scherer, Carolynn P.

    2015-10-13

    Recently there has been a lot of interest in small modular reactors. A specific type of these small modular reactors (SMR,) are marine based power plants called floating nuclear power plants (FNPP). These FNPPs are typically built by countries with extensive knowledge of nuclear energy, such as Russia, France, China and the US. These FNPPs are built in one country and then sent to countries in need of power and/or seawater desalination. Fifteen countries have expressed interest in acquiring such power stations. Some designs for such power stations are briefly summarized. Several different avenues for cooperation in FNPP technology are proposed, including IAEA nuclear security (i.e. safeguards), multilateral or bilateral agreements, and working with Russian design that incorporates nuclear safeguards for IAEA inspections in non-nuclear weapons states

  2. Thermoluminescence dosimeters with narrow bandpass filters

    DOE Patents [OSTI]

    Walker, Scottie W.

    2004-07-20

    A dosimetry method exposes more than one thermoluminescence crystals to radiation without using conventional filters, and reads the energy stored in the crystals by converting the energy to light in a conventional manner, and then filters each crystal output in a different portion of the spectrum generated by the crystals.

  3. Method and apparatus for PM filter regeneration

    DOE Patents [OSTI]

    Opris, Cornelius N.; Verkiel, Maarten

    2006-01-03

    A method and apparatus for initiating regeneration of a particulate matter (PM) filter in an exhaust system in an internal combustion engine. The method and apparatus includes determining a change in pressure of exhaust gases passing through the PM filter, and responsively varying an opening of an intake valve in fluid communication with a combustion chamber.

  4. Active imaging system with Faraday filter

    DOE Patents [OSTI]

    Snyder, J.J.

    1993-04-13

    An active imaging system has a low to medium powered laser transmitter and receiver wherein the receiver includes a Faraday filter with an ultranarrow optical bandpass and a bare (nonintensified) CCD camera. The laser is locked in the vicinity of the passband of the Faraday filter. The system has high sensitivity to the laser illumination while eliminating solar background.

  5. Active Soot Filter Regeneration | Department of Energy

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

    2 DEER Conference Presentation: Cummins, Inc. PDF icon 2002_deer_bunting.pdf More Documents & Publications Evaluation of Passive and Active Soot Filters for Removal of Particulate Emissions from Diesel Engines Development of an Active Regeneration Diesel Particulate Filter System Investigation on continuous soot oxidation and NOx reduction by SCR coated DPF

  6. Hydrogen Technology Research at SRNL

    SciTech Connect (OSTI)

    Danko, E.

    2011-02-13

    The Savannah River National Laboratory (SRNL) is a U.S. Department of Energy research and development laboratory located at the Savannah River Site (SRS) near Aiken, South Carolina. SRNL has over 50 years of experience in developing and applying hydrogen technology, both through its national defense activities as well as through its recent activities with the DOE Hydrogen Programs. The hydrogen technical staff at SRNL comprises over 90 scientists, engineers and technologists. SRNL has ongoing R&D initiatives in a variety of hydrogen storage areas, including metal hydrides, complex hydrides, chemical hydrides and carbon nanotubes. SRNL has over 25 years of experience in metal hydrides and solid-state hydrogen storage research, development and demonstration. As part of its defense mission at SRS, SRNL developed, designed, demonstrated and provides ongoing technical support for the largest hydrogen processing facility in the world based on the integrated use of metal hydrides for hydrogen storage, separation, and compression. The SRNL has been active in teaming with academic and industrial partners to advance hydrogen technology. A primary focus of SRNL's R&D has been hydrogen storage using metal and complex hydrides. SRNL and its Hydrogen Technology Research Laboratory have been very successful in leveraging their defense infrastructure, capabilities and investments to help solve this country's energy problems. SRNL has participated in projects to convert public transit and utility vehicles for operation using hydrogen fuel. Two major projects include the H2Fuel Bus and an Industrial Fuel Cell Vehicle (IFCV) also known as the GATOR{trademark}. Both of these projects were funded by DOE and cost shared by industry. These are discussed further in Section 3.0, Demonstration Projects. In addition to metal hydrides technology, the SRNL Hydrogen group has done extensive R&D in other hydrogen technologies, including membrane filters for H2 separation, doped carbon nanotubes, storage vessel design and optimization, chemical hydrides, hydrogen compressors and hydrogen production using nuclear energy. Several of these are discussed further in Section 2, SRNL Hydrogen Research and Development.

  7. Melt processed crystalline ceramic waste forms for advanced nuclear fuel cycles: CRP T21027 1813: Processing technologies for high level waste, formulation of matrices and characterization of waste forms, Task 17208: Final report

    SciTech Connect (OSTI)

    Amoroso, J. W.; Marra, J. C.

    2015-08-26

    A multi-phase ceramic waste form is being developed at the Savannah River National Laboratory (SRNL) for treatment of secondary waste streams generated by reprocessing commercial spent nuclear. The envisioned waste stream contains a mixture of transition, alkali, alkaline earth, and lanthanide metals. Ceramic waste forms are tailored (engineered) to incorporate waste components as part of their crystal structure based on knowledge from naturally found minerals containing radioactive and non-radioactive species similar to the radionuclides of concern in wastes from fuel reprocessing. The ability to tailor ceramics to mimic naturally occurring crystals substantiates the long term stability of such crystals (ceramics) over geologic timescales of interest for nuclear waste immobilization [1]. A durable multi-phase ceramic waste form tailored to incorporate all the waste components has the potential to broaden the available disposal options and thus minimize the storage and disposal costs associated with aqueous reprocessing. This report summarizes results from three years of work on the IAEA Coordinated Research Project on “Processing technologies for high level waste, formulation of matrices and characterization of waste forms” (T21027), and specific task “Melt Processed Crystalline Ceramic Waste Forms for Advanced Nuclear Fuel Cycles” (17208).

  8. Melt processed crystalline ceramic waste forms for advanced nuclear fuel cycles: CRP T21027 1813: Processing technologies for high level waste, formulation of matrices and characterization of waste forms, task 17208: Final report

    SciTech Connect (OSTI)

    Amoroso, J. W.; Marra, J. C.

    2015-08-26

    A multi-phase ceramic waste form is being developed at the Savannah River National Laboratory (SRNL) for treatment of secondary waste streams generated by reprocessing commercial spent nuclear. The envisioned waste stream contains a mixture of transition, alkali, alkaline earth, and lanthanide metals. Ceramic waste forms are tailored (engineered) to incorporate waste components as part of their crystal structure based on knowledge from naturally found minerals containing radioactive and non-radioactive species similar to the radionuclides of concern in wastes from fuel reprocessing. The ability to tailor ceramics to mimic naturally occurring crystals substantiates the long term stability of such crystals (ceramics) over geologic timescales of interest for nuclear waste immobilization [1]. A durable multi-phase ceramic waste form tailored to incorporate all the waste components has the potential to broaden the available disposal options and thus minimize the storage and disposal costs associated with aqueous reprocessing. This report summarizes results from three years of work on the IAEA Coordinated Research Project on “Processing technologies for high level waste, formulation of matrices and characterization of waste forms” (T21027), and specific task “Melt Processed Crystalline Ceramic Waste Forms for Advanced Nuclear Fuel Cycles” (17208).

  9. Thermovoltaic semiconductor device including a plasma filter

    DOE Patents [OSTI]

    Baldasaro, Paul F.

    1999-01-01

    A thermovoltaic energy conversion device and related method for converting thermal energy into an electrical potential. An interference filter is provided on a semiconductor thermovoltaic cell to pre-filter black body radiation. The semiconductor thermovoltaic cell includes a P/N junction supported on a substrate which converts incident thermal energy below the semiconductor junction band gap into electrical potential. The semiconductor substrate is doped to provide a plasma filter which reflects back energy having a wavelength which is above the band gap and which is ineffectively filtered by the interference filter, through the P/N junction to the source of radiation thereby avoiding parasitic absorption of the unusable portion of the thermal radiation energy.

  10. Nuclear Engineering | Argonne National Laboratory

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

    Nuclear Engineering Nearly every commercial reactor in existence today owes its development to seminal research conducted at Argonne National Laboratory. Building on this heritage, the mission of Argonne's Nuclear Engineering (NE) division is to advance the safe and sustainable use of nuclear energy and to apply its nuclear technology related expertise to current and emerging programs of national and international significance. PDF icon NE_fact_sheet

  11. Advanced Nuclear Energy Projects | Department of Energy

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

    Projects Advanced Nuclear Energy Projects Advanced Nuclear Energy Projects Advanced Nuclear Energy Projects Advanced Nuclear Energy Projects Advanced Nuclear Energy Projects ADVANCED NUCLEAR ENERGY 1 PROJECT in 1 LOCATION 2,200 MW GENERATION CAPACITY 17,200,000 MWh PROJECTED ANNUAL GENERATION * 10,000,000 METRIC TONS OF CO2 EMISSIONS PREVENTED ANNUALLY ALL FIGURES AS OF MARCH 2015 * Calculated using the project's and NREL Technology specific capacity factors. For cases in which NREL's capacity

  12. Potential for Hepa filter damage from water spray systems in filter plenums

    SciTech Connect (OSTI)

    Bergman, W.; Fretthold, J.K.; Slawsld, J.W.

    1997-01-01

    The water spray systems in high efficiency particulate air (HEPA) filter plenums that are used in nearly all Department of Energy (DOE) facilities for protection against fire was designed under the assumption that the HEPA filters would not be damaged by the water sprays. The most likely scenario for filter damage involves filter plugging by the water spray, followed by the fan blowing out the filter medium. A number of controlled laboratory tests that were previously conducted in the late 1980s are reviewed in this paper to provide a technical basis for the potential HEPA filter damage by the water spray system in HEPA filter plenums. In addition to the laboratory tests, the scenario for HEPA filter damage during fires has also occurred in the field. Afire in a four-stage, HEPA filter plenum at Rocky Flats in 1980 caused the first three stages of HEPA filters to blow out of their housing and the fourth stage to severely bow. Details of this recently declassified fire are presented in this paper. Although these previous findings suggest serious potential problems exist with the current water spray system in filter plenum , additional studies are required to confirm unequivocally that DOE`s critical facilities are at risk.

  13. National Center for Nuclear Security: The Nuclear Forensics Project (F2012)

    SciTech Connect (OSTI)

    Klingensmith, A. L.

    2012-03-21

    These presentation visuals introduce the National Center for Nuclear Security. Its chartered mission is to enhance the Nations verification and detection capabilities in support of nuclear arms control and nonproliferation through R&D activities at the NNSS. It has three focus areas: Treaty Verification Technologies, Nonproliferation Technologies, and Technical Nuclear Forensics. The objectives of nuclear forensics are to reduce uncertainty in the nuclear forensics process & improve the scientific defensibility of nuclear forensics conclusions when applied to nearsurface nuclear detonations. Research is in four key areas: Nuclear Physics, Debris collection and analysis, Prompt diagnostics, and Radiochemistry.

  14. Method for reducing pressure drop through filters, and filter exhibiting reduced pressure drop

    DOE Patents [OSTI]

    Sappok, Alexander; Wong, Victor

    2014-11-18

    Methods for generating and applying coatings to filters with porous material in order to reduce large pressure drop increases as material accumulates in a filter, as well as the filter exhibiting reduced and/or more uniform pressure drop. The filter can be a diesel particulate trap for removing particulate matter such as soot from the exhaust of a diesel engine. Porous material such as ash is loaded on the surface of the substrate or filter walls, such as by coating, depositing, distributing or layering the porous material along the channel walls of the filter in an amount effective for minimizing or preventing depth filtration during use of the filter. Efficient filtration at acceptable flow rates is achieved.

  15. Nuclear Physics

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

    Science Programs Office of Science Nuclear Physics science-innovationassetsimagesicon-science.jpg Nuclear Physics Enabling remarkable discoveries and tools that ...

  16. Nuclear Astrophysics

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

    Nuclear & Uranium Glossary › FAQS › Overview Data Status of U.S. Nuclear Outages (interactive) Summary Uranium & nuclear fuel Nuclear power plants Spent nuclear fuel International All nuclear data reports Analysis & Projections Major Topics Most popular Nuclear plants and reactors Projections Recurring Uranium All reports Browse by Tag Alphabetical Frequency Tag Cloud Current Issues & Trends See more › Updated EIA survey provides data on spent nuclear fuel in the United

  17. DOE Announces Strategic Engineering and Technology Roadmap for...

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

    Strategic Engineering and Technology Roadmap for Cleanup of Cold War Era Nuclear Waste DOE Announces Strategic Engineering and Technology Roadmap for Cleanup of Cold War Era ...

  18. Evaluated Nuclear Data

    SciTech Connect (OSTI)

    Oblozinsky, P.; Oblozinsky,P.; Herman,M.; Mughabghab,S.F.

    2010-10-01

    This chapter describes the current status of evaluated nuclear data for nuclear technology applications. We start with evaluation procedures for neutron-induced reactions focusing on incident energies from the thermal energy up to 20 MeV, though higher energies are also mentioned. This is followed by examining the status of evaluated neutron data for actinides that play dominant role in most of the applications, followed by coolants/moderators, structural materials and fission products. We then discuss neutron covariance data that characterize uncertainties and correlations. We explain how modern nuclear evaluated data libraries are validated against an extensive set of integral benchmark experiments. Afterwards, we briefly examine other data of importance for nuclear technology, including fission yields, thermal neutron scattering and decay data. A description of three major evaluated nuclear data libraries is provided, including the latest version of the US library ENDF/B-VII.0, European JEFF-3.1 and Japanese JENDL-3.3. A brief introduction is made to current web retrieval systems that allow easy access to a vast amount of up-to-date evaluated nuclear data for nuclear technology applications.

  19. TESTING OF THE DUAL ROTARY FILTER SYSTEM

    SciTech Connect (OSTI)

    Herman, D.; Fowley, M.; Stefanko, D.

    2011-08-29

    The Savannah River National Laboratory (SRNL) installed and tested two hydraulically connected SpinTek rotary microfilter (RMF) units to determine the behavior of a multiple filter system. Both units were successfully controlled by a control scheme written in DELTA-V architecture by Savannah River Remediation (SRR) Process Control Engineering personnel. The control system was tuned to provide satisfactory response to changing conditions during the operation of the multi-filter system. Stability was maintained through the startup and shutdown of one of the filter units while the second was still in operation. The installation configuration originally proposed by the Small Colum Ion Exchange (SCIX) project of independent filter and motor mountings may be susceptible to vibration. Significant stiffening of the filter and motor mounts was required to minimize the vibration. Alignment of the motor to the filter was a challenge in this test configuration. The deployment configuration must be easy to manipulate and allow for fine adjustment. An analysis of the vibration signature of the test system identified critical speeds. Whether it corresponds to the resonance frequency of a rotor radial vibration mode that was excited by rotor unbalance is uncertain based upon the measurements. A relative motion series should be completed on the filter with the final shaft configuration to determine if the resonances exist in the final filter design. The instrumentation selected for deployment, including the concentrate discharge control valve and flow meters, performed well. Automation of the valve control integrated well with the control scheme and when used in concert with the other control variables, allowed automated control of the dual RMF system. The one area of concern with the instrumentation was the condition resulting when the filtrate flow meter operated with less than three gpm. This low flow was at the lower range of performance for the flow meter. This should not be an issue in deployment where the desired flow rate will be within the normal operating range of the meter. Testing demonstrated that the use of a flexible line for the filtrate discharge is highly desired at the outlet of the rotary union to transition to the system piping. Isolating the vibration from the rotary union will significantly improve the lifetime of the seals. Methods to monitor and isolate individual filters should be considered during deployment. The ability to diagnose issues and isolate individual filters would allow isolation prior to failure. Thus, filters may be cleaned or repaired instead of requiring complete replacement if the condition were to continue unnoticed. Isolating the filtrate line of each filter during startup will minimize the premature buildup of solids on the filter disks. Several tests have shown that the method of filter startup can improve performance lifetime of the filters. The installation must factor in an air inlet for the draining of a filter that does not involve a reverse flow through the filter disks. The reverse flow may cause deformation of the disks or may damage other components of the filters themselves.

  20. Multiple stage multiple filter hydrate store

    DOE Patents [OSTI]

    Bjorkman, Jr., Harry K.

    1983-05-31

    An improved hydrate store for a metal halogen battery system is disclosed which employs a multiple stage, multiple filter means or separating the halogen hydrate from the liquid used in forming the hydrate. The filter means is constructed in the form of three separate sections which combine to substantially cover the interior surface of the store container. Exit conduit means is provided in association with the filter means for transmitting liquid passing through the filter means to a hydrate former subsystem. The hydrate former subsystem combines the halogen gas generated during the charging of the battery system with the liquid to form the hydrate in association with the store. Relief valve means is interposed in the exit conduit means for controlling the operation of the separate sections of the filter means, such that the liquid flow through the exit conduit means from each of the separate sections is controlled in a predetermined sequence. The three separate sections of the filter means operate in three discrete stages to provide a substantially uniform liquid flow to the hydrate former subsystem during the charging of the battery system. The separation of the liquid from the hydrate causes an increase in the density of the hydrate by concentrating the hydrate along the filter means.

  1. 3D Oxide/Oxide Composite Filter

    SciTech Connect (OSTI)

    Lane, J.E.; LeCostaouec, J.; Painter, C.J.; Su, Wei-Fang A.; Radford, K.C.

    1996-12-31

    Hot gas particulate filters are key components for the successful commercialization of advanced coal-based power-generation systems such as Pressurized Fluidized-bed Combustion (PFBC), including second- generation PFBC, and Integrated Gasification Combined Cycles (IGCC). Current generation monolithic ceramic filters are subject to catastrophic failure because they have very low resistance to crack propagation. To overcome this problem, a damage -tolerant ceramic filter element is needed. Westinghouse, with Techniweave as a major subcontractor, is conducting a three-phase program aimed at providing advanced candle filters for a 1996 pilot scale demonstration in one of the two hot gas filter systems at Southern Company Service`s Wilsonville PSD Facility. The Base Program (Phases I and II) objective is to develop and demonstrate the suitability of the Westinghouse/Techniweave next generation composite candle filter for use PFBC and/or IGCC power generation systems. The optional Task (Phase III, Task 5) objective is to fabricate, inspect and ship to Wilsonville 50 advanced candle filters for pilot scale testing.

  2. Multiple stage multiple filter hydrate store

    DOE Patents [OSTI]

    Bjorkman, H.K. Jr.

    1983-05-31

    An improved hydrate store for a metal halogen battery system is disclosed which employs a multiple stage, multiple filter means for separating the halogen hydrate from the liquid used in forming the hydrate. The filter means is constructed in the form of three separate sections which combine to substantially cover the interior surface of the store container. Exit conduit means is provided in association with the filter means for transmitting liquid passing through the filter means to a hydrate former subsystem. The hydrate former subsystem combines the halogen gas generated during the charging of the battery system with the liquid to form the hydrate in association with the store. Relief valve means is interposed in the exit conduit means for controlling the operation of the separate sections of the filter means, such that the liquid flow through the exit conduit means from each of the separate sections is controlled in a predetermined sequence. The three separate sections of the filter means operate in three discrete stages to provide a substantially uniform liquid flow to the hydrate former subsystem during the charging of the battery system. The separation of the liquid from the hydrate causes an increase in the density of the hydrate by concentrating the hydrate along the filter means. 7 figs.

  3. Electrically heated particulate filter embedded heater design

    DOE Patents [OSTI]

    Gonze, Eugene V.; Chapman, Mark R.

    2014-07-01

    An exhaust system that processes exhaust generated by an engine is provided. The system generally includes a particulate filter (PF) that filters particulates from the exhaust wherein an upstream end of the PF receives exhaust from the engine and wherein an upstream surface of the particulate filter includes machined grooves. A grid of electrically resistive material is inserted into the machined grooves of the exterior upstream surface of the PF and selectively heats exhaust passing through the grid to initiate combustion of particulates within the PF.

  4. Neutron Imaging of Diesel Particulate Filters

    SciTech Connect (OSTI)

    Strzelec, Andrea; Bilheux, Hassina Z; FINNEY, Charles E A; Daw, C Stuart; Foster, Prof. Dave; Rutland, Prof. Christopher J.; Schillinger, Burkhard; Schulz, Michael

    2009-01-01

    This article presents nondestructive neutron computed tomography (nCT) measurements of Diesel Particulate Filters (DPFs) as a method to measure ash and soot loading in the filters. Uncatalyzed and unwashcoated 200cpsi cordierite DPFs exposed to 100% biodiesel (B100) exhaust and conventional ultra low sulfur 2007 certification diesel (ULSD) exhaust at one speed-load point (1500rpm, 2.6bar BMEP) are compared to a brand new (never exposed) filter. Precise structural information about the substrate as well as an attempt to quantify soot and ash loading in the channel of the DPF illustrates the potential strength of the neutron imaging technique.

  5. Pakistan’s nuclear Taj Mahal

    SciTech Connect (OSTI)

    Leslie, Stuart W.

    2015-02-15

    Inspired by the promise of Atoms for Peace, the Pakistan Institute of Nuclear Science and Technology eventually succumbed to the demands of the country’s nuclear weapons program.

  6. Office of Nuclear Energy Fiscal Year 2014 Budget Request

    Broader source: Energy.gov [DOE]

    The Office of Nuclear Energy (NE) supports the diverse civilian nuclear energy programs of the U.S. Government, leading Federal efforts to research and develop nuclear energy technologies,...

  7. Nuclear Fabrication Consortium

    SciTech Connect (OSTI)

    Levesque, Stephen

    2013-04-05

    This report summarizes the activities undertaken by EWI while under contract from the Department of Energy (DOE) – Office of Nuclear Energy (NE) for the management and operation of the Nuclear Fabrication Consortium (NFC). The NFC was established by EWI to independently develop, evaluate, and deploy fabrication approaches and data that support the re-establishment of the U.S. nuclear industry: ensuring that the supply chain will be competitive on a global stage, enabling more cost-effective and reliable nuclear power in a carbon constrained environment. The NFC provided a forum for member original equipment manufactures (OEM), fabricators, manufacturers, and materials suppliers to effectively engage with each other and rebuild the capacity of this supply chain by : • Identifying and removing impediments to the implementation of new construction and fabrication techniques and approaches for nuclear equipment, including system components and nuclear plants. • Providing and facilitating detailed scientific-based studies on new approaches and technologies that will have positive impacts on the cost of building of nuclear plants. • Analyzing and disseminating information about future nuclear fabrication technologies and how they could impact the North American and the International Nuclear Marketplace. • Facilitating dialog and initiate alignment among fabricators, owners, trade associations, and government agencies. • Supporting industry in helping to create a larger qualified nuclear supplier network. • Acting as an unbiased technology resource to evaluate, develop, and demonstrate new manufacturing technologies. • Creating welder and inspector training programs to help enable the necessary workforce for the upcoming construction work. • Serving as a focal point for technology, policy, and politically interested parties to share ideas and concepts associated with fabrication across the nuclear industry. The report the objectives and summaries of the Nuclear Fabrication Consortium projects. Full technical reports for each of the projects have been submitted as well.

  8. U-252: Barracuda Web Filter Input Validation Flaws Permit Cross...

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

    2: Barracuda Web Filter Input Validation Flaws Permit Cross-Site Scripting Attacks U-252: Barracuda Web Filter Input Validation Flaws Permit Cross-Site Scripting Attacks September...

  9. Filter:Incentives by Place | Open Energy Information

    Open Energy Info (EERE)

    This filter covers the property Place. Retrieved from "http:en.openei.orgwindex.php?titleFilter:IncentivesbyPlace&oldid267397" Feedback Contact needs updating Image...

  10. California ARB Verification Testing of the CBSTM Soot Filter...

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

    California ARB Verification Testing of the CBSTM Soot Filter for Stationary Diesel Applications California ARB Verification Testing of the CBSTM Soot Filter for Stationary Diesel ...

  11. Kalman Filter Models for Data Assimilation (Conference) | SciTech...

    Office of Scientific and Technical Information (OSTI)

    Conference: Kalman Filter Models for Data Assimilation Citation Details In-Document Search Title: Kalman Filter Models for Data Assimilation You are accessing a document from ...

  12. Orthogonal Transformations for the Ensemble Kalman Filter (Conference...

    Office of Scientific and Technical Information (OSTI)

    Orthogonal Transformations for the Ensemble Kalman Filter Citation Details In-Document Search Title: Orthogonal Transformations for the Ensemble Kalman Filter You are accessing ...

  13. Orthogonal Transformations for the Ensemble Kalman Filter (Conference...

    Office of Scientific and Technical Information (OSTI)

    Orthogonal Transformations for the Ensemble Kalman Filter Citation Details In-Document Search Title: Orthogonal Transformations for the Ensemble Kalman Filter Authors: Godinez ...

  14. Predicting Thermal Stress in Diesel Particulate Filters | Department...

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

    Thermal Stress in Diesel Particulate Filters Predicting Thermal Stress in Diesel Particulate Filters 2004 Diesel Engine Emissions Reduction (DEER) Conference Presentation: Corning ...

  15. California Energy Standards Recognize the Importance of Filter...

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

    This research on HVAC air filter sizing prompted a change in the California "Title 24" ... PDF icon California Energy Standards Recognize The Importance of Filter Selection More ...

  16. Versatile Diesel Particulate Filter Cartridge Any Size, Any Shape...

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

    Versatile Diesel Particulate Filter Cartridge Any Size, Any Shape Versatile Diesel Particulate Filter Cartridge Any Size, Any Shape Presentation given at DEER 2006, August 20-24, ...

  17. New Cordierite Diesel Particulate Filters for Catalyzed and Non...

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

    Cordierite Diesel Particulate Filters for Catalyzed and Non-Catalyzed Applications New Cordierite Diesel Particulate Filters for Catalyzed and Non-Catalyzed Applications 2003 DEER ...

  18. CARB Verification of Catalyzed Diesel Particulate Filters for...

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

    CARB Verification of Catalyzed Diesel Particulate Filters for Emergency Generator Sets CARB Verification of Catalyzed Diesel Particulate Filters for Emergency Generator Sets 2005 ...

  19. Durability of Diesel Particulate Filters - Bench Studies on Cordierite...

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

    Particulate Filters - Bench Studies on Cordierite Filters Durability of Diesel Particulate ... More Documents & Publications Requirements-Driven Diesel Catalyzed Particulate Trap Design ...

  20. Ultra-Lite Diesel Particulate Filter Cartridge for Reduced Regeneratio...

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

    Lite Diesel Particulate Filter Cartridge for Reduced Regeneration Time and Fuel Consumption Ultra-Lite Diesel Particulate Filter Cartridge for Reduced Regeneration Time and Fuel ...

  1. Broadband Particle Filtering in a Noisy Littoral Ocean (Conference...

    Office of Scientific and Technical Information (OSTI)

    Broadband Particle Filtering in a Noisy Littoral Ocean Citation Details In-Document Search Title: Broadband Particle Filtering in a Noisy Littoral Ocean You are accessing a ...

  2. Adaptive Particle Filtering for Mode Tracking: A Shallow Ocean...

    Office of Scientific and Technical Information (OSTI)

    Adaptive Particle Filtering for Mode Tracking: A Shallow Ocean Application Citation Details In-Document Search Title: Adaptive Particle Filtering for Mode Tracking: A Shallow Ocean ...

  3. Electrically heated particulate filter with zoned exhaust flow...

    Office of Scientific and Technical Information (OSTI)

    Electrically heated particulate filter with zoned exhaust flow control Title: Electrically heated particulate filter with zoned exhaust flow control A system includes a particulate ...

  4. IL conversion technology

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

    conversion technology - Sandia Energy Energy Search Icon Sandia Home Locations Contact Us Employee Locator Energy & Climate Secure & Sustainable Energy Future Stationary Power Energy Conversion Efficiency Solar Energy Wind Energy Water Power Supercritical CO2 Geothermal Natural Gas Safety, Security & Resilience of the Energy Infrastructure Energy Storage Nuclear Power & Engineering Grid Modernization Battery Testing Nuclear Fuel Cycle Defense Waste Management Programs Advanced

  5. Marine Energy Technology Symposium

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

    Energy Technology Symposium - Sandia Energy Energy Search Icon Sandia Home Locations Contact Us Employee Locator Energy & Climate Secure & Sustainable Energy Future Stationary Power Energy Conversion Efficiency Solar Energy Wind Energy Water Power Supercritical CO2 Geothermal Natural Gas Safety, Security & Resilience of the Energy Infrastructure Energy Storage Nuclear Power & Engineering Grid Modernization Battery Testing Nuclear Fuel Cycle Defense Waste Management Programs

  6. Vehicle Technologies Office

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

    Technologies Office - Sandia Energy Energy Search Icon Sandia Home Locations Contact Us Employee Locator Energy & Climate Secure & Sustainable Energy Future Stationary Power Energy Conversion Efficiency Solar Energy Wind Energy Water Power Supercritical CO2 Geothermal Natural Gas Safety, Security & Resilience of the Energy Infrastructure Energy Storage Nuclear Power & Engineering Grid Modernization Battery Testing Nuclear Fuel Cycle Defense Waste Management Programs Advanced

  7. Nuclear Forensics

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

    Nuclear Forensics AMS is a Powerful Tool for Nuclear Forensics Nuclear forensics, which can be applied to both interdicted materials and debris from a nuclear explosion, is the application of laboratory analysis and interpretation to provide technical conclusions (provenance, design, etc.) about a nuclear device or interdicted nuclear material. Nuclear forensic analysts can build confidence in their conclusions by employing multiple signatures that collectively minimize the subset of possible

  8. Electro-optical tunable birefringent filter

    DOE Patents [OSTI]

    Levinton, Fred M.

    2012-01-31

    An electrically tunable Lyot type filter is a Lyot that include one or more filter elements. Each filter element may have a planar, solid crystal comprised of a material that exhibits birefringence and is electro-optically active. Transparent electrodes may be coated on each face of the crystal. An input linear light polarizer may be located on one side of the crystal and oriented at 45 degrees to the optical axis of the birefringent crystal. An output linear light polarizer may be located on the other side of the crystal and oriented at -45 degrees with respect to the optical axis of the birefringent crystal. When an electric voltage is applied between the electrodes, the retardation of the crystal changes and so does the spectral transmission of the optical filter.

  9. Emergency Filter for Low Pressure EGR

    Broader source: Energy.gov [DOE]

    This project uses CFD simulation and laboratory tests to design single- and multi-layer mesh as an EGR emergency filter to prevent combustion particles from passing back to the engine.

  10. Electrically heated particulate filter regeneration methods and...

    Office of Scientific and Technical Information (OSTI)

    A control system for controlling regeneration of a particulate filter for a hybrid vehicle ... An engine control module controls operation of an engine of the hybrid vehicle based on ...

  11. National Nuclear Science Week 2014 - SRSCRO

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

    Science Week is celebrated annually across the United States. It is a week-long educational opportunity to focus local, regional and national interest on all aspects of nuclear science. The SRS Community Reuse Organization and its affiliated Nuclear Workforce Initiative are collaborating with local organizations to conduct activities designed to encourage and bring awareness of nuclear technology and the many careers available within nuclear technology and other high-tech industries. Regional

  12. Research and Development | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    Research and Development NNSA reduces the threat to national security posed by nuclear weapons proliferation and possible detonation or the illicit trafficking of nuclear materials through the long-term development of new technology. NNSA reduces the threat to national security posed by nuclear weapons proliferation and possible detonation or the illicit trafficking of nuclear materials through the long-term development of new technology. NNSA reduces the threat to national security posed by

  13. Vehicle Technologies Office: Technologies

    Broader source: Energy.gov [DOE]

    To support DOE's goal to provide clean and secure energy, the Vehicle Technologies Office (VTO) invests in research and development that:

  14. FILTER FOR HIGH VELOCITY GAS STREAMS

    DOE Patents [OSTI]

    Heckman, R.A.; Warner, H.F.

    1963-11-01

    An air filter that is particularly useful in air-sampling rockets is presented. The filter comprises a cellulose fiber mat having an evenly disposed thin coating of stearic acid. Protective loose weave fabric covers are stitched to the front and back of the fiber mat, the stitching being in the form of a sine wave spiraled from the midpoint of the mat out to its periphery. (AEC)

  15. Electrical diesel particulate filter (DPF) regeneration

    DOE Patents [OSTI]

    Gonze, Eugene V; Ament, Frank

    2013-12-31

    An exhaust system that processes exhaust generated by an engine includes a diesel particulate filter (DPF) that is disposed downstream of the engine and that filters particulates from the exhaust. An electrical heater is disposed upstream of the DPF and selectively heats the exhaust to initiate combustion of the particulates within the exhaust as it passes therethrough. Heat generated by combustion of the particulates induces combustion of particulates within the DPF.

  16. Nuclear Security Administration

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

    8, 2006, the National Nuclear Security Administration (NNSA) announced the selection of National Security Technologies, LLC (NSTec) to manage and operate the Nevada Test Site (NTS) for the NNSA Nevada Site Office. The contract, valued at approxi- mately $500 million annually, is for five years. There are poten- tially five additional perform- ance-based award-term years available under this contract. NSTec is made up of Northrop Grumman, AECOM, CH2M Hill, and Nuclear Fuel Services. Dr. James E.

  17. Marine and Hydrokinetic Technology Database

    DOE Data Explorer [Office of Scientific and Technical Information (OSTI)]

    DOE’s Marine and Hydrokinetic Technology Database provides up-to-date information on marine and hydrokinetic renewable energy, both in the U.S. and around the world. The database includes wave, tidal, current, and ocean thermal energy, and contains information on the various energy conversion technologies, companies active in the field, and development of projects in the water. Depending on the needs of the user, the database can present a snapshot of projects in a given region, assess the progress of a certain technology type, or provide a comprehensive view of the entire marine and hydrokinetic energy industry. Results are displayed as a list of technologies, companies, or projects. Data can be filtered by a number of criteria, including country/region, technology type, generation capacity, and technology or project stage. The database was updated in 2009 to include ocean thermal energy technologies, companies, and projects.

  18. Marine and Hydrokinetic Technology Database

    DOE Data Explorer [Office of Scientific and Technical Information (OSTI)]

    DOEs Marine and Hydrokinetic Technology Database provides up-to-date information on marine and hydrokinetic renewable energy, both in the U.S. and around the world. The database includes wave, tidal, current, and ocean thermal energy, and contains information on the various energy conversion technologies, companies active in the field, and development of projects in the water. Depending on the needs of the user, the database can present a snapshot of projects in a given region, assess the progress of a certain technology type, or provide a comprehensive view of the entire marine and hydrokinetic energy industry. Results are displayed as a list of technologies, companies, or projects. Data can be filtered by a number of criteria, including country/region, technology type, generation capacity, and technology or project stage. The database was updated in 2009 to include ocean thermal energy technologies, companies, and projects.

  19. 3-D woven, mullite matrix, composite filter

    SciTech Connect (OSTI)

    Lane, J.E.; Painter, C.J.; Radford, K.C. LeCostaouec, J.F.

    1995-12-01

    Westinghouse, with Techniweave as a major subcontractor, is conducting a three-phase program aimed at providing advanced candle filters for a 1996 pilot scale demonstration in one of the two hot gas filter systems at Southern Company Service`s Wilsonville PSD Facility. The Base Program (Phases I and II) objective is to develop and demonstrate the suitability of the Westinghouse/Techniweave next generation composite candle filter for use in Pressurized Fluidized Bed Combustion (PFBC) and/or Integrated Gasification Combined Cycle (IGCC) power generation systems. The Optional Task (Phase M, Task 5) objective is to fabricate, inspect and ship to Wilsonville Hot gas particulate filters are key components for the successful commercializaion of advanced coal-based power-generation systems such as Pressurized Fluidized-bed Combustion (PFBC), including second-generation PFBC, and Integrated Gasification Combined Cycles (IGCC). Current generation monolithic ceramic filters are subject to catastrophic failure because they have very low resistance to crack propagation. To overcome this problem, a damage-tolerant ceramic filter element is needed.

  20. Digital Actuator Technology

    SciTech Connect (OSTI)

    Ken Thomas; Ted Quinn; Jerry Mauck; Richard Bockhorst

    2014-09-01

    There are significant developments underway in new types of actuators for power plant active components. Many of these make use of digital technology to provide a wide array of benefits in performance of the actuators and in reduced burden to maintain them. These new product offerings have gained considerable acceptance in use in process plants. In addition, they have been used in conventional power generation very successfully. This technology has been proven to deliver the benefits promised and substantiate the claims of improved performance. The nuclear industry has been reluctant to incorporate digital actuator technology into nuclear plant designs due to concerns due to a number of concerns. These could be summarized as cost, regulatory uncertainty, and a certain comfort factor with legacy analog technology. The replacement opportunity for these types of components represents a decision point for whether to invest in more modern technology that would provide superior operational and maintenance benefits. Yet, the application of digital technology has been problematic for the nuclear industry, due to qualification and regulatory issues. With some notable exceptions, the result has been a continuing reluctance to undertake the risks and uncertainties of implementing digital actuator technology when replacement opportunities present themselves. Rather, utilities would typically prefer to accept the performance limitations of the legacy analog actuator technologies to avoid impacts to project costs and schedules. The purpose of this report is to demonstrate that the benefits of digital actuator technology can be significant in terms of plant performance and that it is worthwhile to address the barriers currently holding back the widespread development and use of this technology. It addresses two important objectives in pursuit of the beneficial use of digital actuator technology for nuclear power plants: 1. To demonstrate the benefits of digital actuator technology over legacy analog sensor technology in both quantitative and qualitative ways. 2. To recognize and address the added difficulty of digital technology qualification, especially in regard to software common cause failure (SCCF), that is introduced by the use of digital actuator technology.

  1. National Laboratories' Energy Technologies and System Solutions...

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

    Laboratories' Energy Technologies and System Solutions Center Director - Sandia Energy Energy Search Icon Sandia Home Locations ... Nuclear Fuel Cycle Defense Waste Management Programs ...

  2. Energy Department Announces Small Modular Reactor Technology...

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

    leverage Savannah River's land assets, energy facilities and nuclear expertise to support potential private sector development, testing and licensing of prototype SMR technologies. ...

  3. IEA Technology Roadmaps | Open Energy Information

    Open Energy Info (EERE)

    Plug-in Hybrid Vehicles Energy Efficient Buildings: heating & cooling systems Geothermal Nuclear Power Smart Grids Solar Photovoltaic Wind Energy" References "IEA Technology...

  4. Method and apparatus for a self-cleaning filter

    DOE Patents [OSTI]

    Diebold, James P.; Lilley, Arthur; Browne, III, Kingsbury; Walt, Robb Ray; Duncan, Dustin; Walker, Michael; Steele, John; Fields, Michael

    2010-11-16

    A method and apparatus for removing fine particulate matter from a fluid stream without interrupting the overall process or flow. The flowing fluid inflates and expands the flexible filter, and particulate is deposited on the filter media while clean fluid is permitted to pass through the filter. This filter is cleaned when the fluid flow is stopped, the filter collapses, and a force is applied to distort the flexible filter media to dislodge the built-up filter cake. The dislodged filter cake falls to a location that allows undisrupted flow of the fluid after flow is restored. The shed particulate is removed to a bin for periodic collection. A plurality of filter cells can operate independently or in concert, in parallel, or in series to permit cleaning the filters without shutting off the overall fluid flow. The self-cleaning filter is low cost, has low power consumption, and exhibits low differential pressures.

  5. Research and Development | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    R&D is organized into two offices: Proliferation Detection develops technologies to detect ... Learn More Proliferation Detection Nuclear Detonation Detection Related Topics ...

  6. Joint Coordinating Committee | National Nuclear Security Administratio...

    National Nuclear Security Administration (NNSA)

    Joint Coordinating Committee United States and China Mark 10th Anniversary of Peaceful Uses of Nuclear Technology Joint Coordination Meetings CHENGDU, CHINA - On May 6 and 7, the ...

  7. Monitoring international nuclear activity

    SciTech Connect (OSTI)

    Firestone, R.B.

    2006-05-19

    The LBNL Table of Isotopes website provides primary nuclearinformation to>150,000 different users annually. We have developedthe covert technology to identify users by IP address and country todetermine the kinds of nuclear information they are retrieving. Wepropose to develop pattern recognition software to provide an earlywarning system to identify Unusual nuclear activity by country or regionSpecific nuclear/radioactive material interests We have monitored nuclearinformation for over two years and provide this information to the FBIand LLNL. Intelligence is gleaned from the website log files. Thisproposal would expand our reporting capabilities.

  8. Advanced Nuclear Fuel Cycle Options

    SciTech Connect (OSTI)

    Roald Wigeland; Temitope Taiwo; Michael Todosow; William Halsey; Jess Gehin

    2010-06-01

    A systematic evaluation has been conducted of the potential for advanced nuclear fuel cycle strategies and options to address the issues ascribed to the use of nuclear power. Issues included nuclear waste management, proliferation risk, safety, security, economics and affordability, and sustainability. The two basic strategies, once-through and recycle, and the range of possibilities within each strategy, are considered for all aspects of the fuel cycle including options for nuclear material irradiation, separations if needed, and disposal. Options range from incremental changes to todays implementation to revolutionary concepts that would require the development of advanced nuclear technologies.

  9. A Simple Candle Filter Safeguard Device

    SciTech Connect (OSTI)

    Hurley, J.P.; Henderson, A.K.; Swanson, M.L.

    2002-09-18

    In order to reach the highest possible efficiencies in a coal-fired turbine-based power system, the turbine should be directly fired with the products of coal utilization. Two main designs employ these turbines: those based on pressurized fluidized-bed combustors (PFBCs) and those based on integrated gasification combined cycles (IGCCs). In both designs, the suspended particulates, or dust, must be cleaned from the gas before it enters the turbine to prevent fouling and erosion of the blades. To produce the cleanest gas, barrier filters are being developed and are in commercial use. Barrier filters are composed of porous, high-temperature materials that allow the hot gas to pass but collect the dust on the surface. The three main configurations are candle, cross-flow, and tube. Both candle and tube filters have been tested extensively. They are primarily composed of coarsely porous ceramic that serves as a structural support, overlain with a thin, microporous ceramic layer o n the dirty gas side that serves as the primary filter surface. They are highly efficient at removing particulate matter from the gas stream and, because of their ceramic construction, are resistant to gas and ash corrosion. However, ceramics are brittle, and individual elements can fail, allowing the particulates to pass through the hole left by the filter element and erode the turbine. Because of the possibility of occasional filter breakage, safeguard devices (SGDs) must be employed to prevent the dust streaming through broken filters from reaching the turbine. The Energy & Environmental Research Center (EERC) safeguard device is composed of three main parts: the ceramic substrate, the adhesive coating, and the safeguard device housing. This report describes the development and laboratory testing of each of those parts as well as the bench-scale performance of both types of complete SGDs.

  10. nuclear security

    National Nuclear Security Administration (NNSA)

    3%2A en Shaping the future of nuclear detection http:nnsa.energy.govblogshaping-future-nuclear-detection

    Learning techniques to combat nuclear trafficking, touring the...

  11. Frequency Selective Surfaces as Near Infrared Electro-Magnetic Filters for Thermophotovoltaic Spectral Control

    SciTech Connect (OSTI)

    RF Kristensen; JF Beausang; DM DePoy

    2004-06-28

    Frequency selective surfaces (FSS) effectively filter electromagnetic radiation in the microwave band (1 mm to 100 mm). Interest exists in extending this technology to the near infrared (1 {micro}m to 10 {micro}m) for use as a filter of thermal radiation in thermophotovoltaic (TPV) direct energy conversion. This paper assesses the ability of FSS to meet the strict spectral performance requirements of a TPV system. Inherent parasitic absorption, which is the result of the induced currents in the FSS metallization, is identified as a significant obstacle to achieving high spectral performance.

  12. Frequency Selective Surfaces as Near Infrared Electro-Magnetic Filters for Thermophotovoltaic Spectral Control

    SciTech Connect (OSTI)

    Ryan T. Kristensen; John F. Beausang; David M. DePoy

    2003-12-01

    Frequency selective surfaces (FSS) effectively filter electromagnetic radiation in the microwave band (1mm to 100mm). Interest exists in extending this technology to the near infrared (1 {micro}m to 10 {micro}m) for use as a filter of thermal radiation in thermophotovoltaic (TPV) direct energy conversion. This paper assesses the ability of FSS to meet the strict spectral performance requirements of a TPV system. Inherent parasitic absorption, which is the result of the induced currents in the FSS metallization, is identified as a significant obstacle to achieving high spectral performance.

  13. Nuclear Science

    Energy Savers [EERE]

    and Engineering Education Sourcebook 2013 American Nuclear Society US Department of Energy Nuclear Science & Engineering Education Sourcebook 2013 North American Edition American Nuclear Society Education, Training, and Workforce Division US Department of Energy Office of Nuclear Energy Editor and Founder John Gilligan Professor of Nuclear Engineering North Carolina State University Version 5.13 Welcome to the 2013 Edition of the Nuclear Science and Engineering Education (NS&EE)

  14. Office of Nuclear Energy | Department of Energy

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

    Office of Nuclear Energy Small Modular Reactors Small Modular Reactors The Small Modular Reactor program advances the licensing and commercialization of this next-generation technology in the United States. Read more Middle School STEM Curriculum Middle School STEM Curriculum The Harnessed Atom curriculum offers essential principles and fundamental concepts on energy and nuclear science. Read more Educating Future Nuclear Engineers Educating Future Nuclear Engineers The Nuclear Energy University

  15. Nuclear Deterrence | Y-12 National Security Complex

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

    Nuclear Deterrence Nuclear Deterrence Y-12's core mission is to ensure a safe, secure, and reliable U.S. nuclear deterrent, which is essential to national security. Every weapon in the U.S. nuclear stockpile has components manufactured, maintained or ultimately dismantled by Y-12, the nation's Uranium Center of Excellence. We employ only the most advanced and failsafe technologies to protect the stockpile. Nuclear Deterrence Sharing resources: the benefits of consolidation Stockpile Weapons

  16. Removal of residual particulate matter from filter media

    DOE Patents [OSTI]

    Almlie, Jay C; Miller, Stanley J

    2014-11-11

    A method for removing residual filter cakes that remain adhered to a filter after typical particulate removal methodologies have been employed, such as pulse-jet filter element cleaning, for all cleanable filters used for air pollution control, dust control, or powder control.

  17. Electrically heated particulate matter filter with recessed inlet end plugs

    DOE Patents [OSTI]

    Gonze, Eugene V.; Ament, Frank

    2012-02-21

    A particulate matter (PM) filter includes filter walls having inlet ends and outlet ends. First adjacent pairs of the filter walls define inlet channels. Second adjacent pairs of the filter walls define outlet channels. Outlet end plugs are arranged in the inlet channels adjacent to the output ends. Inlet end plugs arranged in the outlet channels spaced from the inlet ends.

  18. nuclear enterprise

    National Nuclear Security Administration (NNSA)

    Outlines Accomplishments in Stockpile Stewardship, Nuclear Nonproliferation, Naval Reactors and Managing the Nuclear Enterprise

    The...

  19. Suggestion of typical phases of in-vessel fuel-debris by thermodynamic calculation for decommissioning technology of Fukushima-Daiichi nuclear power station

    SciTech Connect (OSTI)

    Ikeuchi, Hirotomo; Yano, Kimihiko; Kaji, Naoya; Washiya, Tadahiro; Kondo, Yoshikazu; Noguchi, Yoshikazu

    2013-07-01

    For the decommissioning of the Fukushima-Daiichi Nuclear Power Station (1F), the characterization of fuel-debris in cores of Units 1-3 is necessary. In this study, typical phases of the in-vessel fuel-debris were estimated using a thermodynamic equilibrium (TDE) calculation. The FactSage program and NUCLEA database were applied to estimate the phase equilibria of debris. It was confirmed that the TDE calculation using the database can reproduce the phase separation behavior of debris observed in the Three Mile Island accident. In the TDE calculation of 1F, the oxygen potential [G(O{sub 2})] was assumed to be a variable. At low G(O{sub 2}) where metallic zirconium remains, (U,Zr)O{sub 2}, UO{sub 2}, and ZrO{sub 2} were found as oxides, and oxygen-dispersed Zr, Fe{sub 2}(Zr,U), and Fe{sub 3}UZr{sub 2} were found as metals. With an increase in zirconium oxidation, the mass of those metals, especially Fe{sub 3}UZr{sub 2}, decreased, but the other phases of metals hardly changed qualitatively. Consequently, (U,Zr)O{sub 2} is suggested as a typical phase of oxide, and Fe{sub 2}(Zr,U) is suggested as that of metal. However, a more detailed estimation is necessary to consider the distribution of Fe in the reactor pressure vessel through core-melt progression. (authors)

  20. Method of and apparatus for testing the integrity of filters

    DOE Patents [OSTI]

    Herman, R.L.

    1985-05-07

    A method of and apparatus are disclosed for testing the integrity of individual filters or filter stages of a multistage filtering system including a diffuser permanently mounted upstream and/or downstream of the filter stage to be tested for generating pressure differentials to create sufficient turbulence for uniformly dispersing trace agent particles within the airstream upstream and downstream of such filter stage. Samples of the particle concentration are taken upstream and downstream of the filter stage for comparison to determine the extent of particle leakage past the filter stage. 5 figs.