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Sample records for nuclear filter technology

  1. Nuclear Filter Technology | Open Energy Information

    Open Energy Info (EERE)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on QA:QA J-E-1 SECTION J APPENDIXsourceII Jump to:Information 3rd|Northfork Electric Coop,NovopolymersNualgiFilter

  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...

  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

    E-Print Network [OSTI]

    Gueroult, Renaud; Fisch, Nathaniel J

    2015-01-01

    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. 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. Reactor Technology | Nuclear Science | ORNL

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

    Reactor Technology Advanced Reactor Concepts Advanced Instrumentation & Controls Light Water Reactor Sustainability Safety and Regulatory Technology Small Modular Reactors Nuclear...

  9. Security Science & Technology | Nuclear Science | ORNL

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

    Security Treaty Verification Nuclear Systems Modeling, Simulation & Validation Nuclear Systems Technology Reactor Technology Nuclear Science Home | Science & Discovery |...

  10. Nuclear Reactors and Technology

    SciTech Connect (OSTI)

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

    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.

  11. 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.

  12. 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...

  13. 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.

  14. 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.

  15. ANS 2006 WINTER MEETING & Nuclear Technology Expo

    E-Print Network [OSTI]

    Krings, Axel W.

    ) EXCEL Services Corporation Florida Power & Light GE Nuclear Energy Idaho National Laboratory INVENSYS support of the ANS Expo Special Events: Bechtel Nuclear Power BWX Technologies, Inc. Doosan HF ControlsANS 2006 WINTER MEETING & Nuclear Technology Expo "Ensuringthe

  16. 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.

  17. 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.

  18. 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.

  19. Security Science & Technology | Nuclear Science | ORNL

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

    Nuclear Security Science & Technology Border Security Comprehensive Vulnerability and Threat Analysis Consequence Management, Safeguards, and Non-Proliferation Tools Export...

  20. 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.

  1. 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.

  2. 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 organization’s capabilities, facilities, and culture.

  3. Nuclear Physics Technology Saves Lives | Jefferson Lab

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

    Nuclear Physics Technology Saves Lives January 11, 2006 Listen to this story Ribbon With early detection, breast cancer can often be treated successfully. There are over two...

  4. Fusion Nuclear Science and Technology (FNST)Fusion Nuclear Science and Technology (FNST) Challenges and Facilities

    E-Print Network [OSTI]

    California at Los Angeles, University of

    Fusion Nuclear Science and Technology (FNST)Fusion Nuclear Science and Technology (FNST) Challenges on MFE Roadmapping in the ITER Era Princeton, NJ 7-10 September 2011 1 #12;Fusion Nuclear Science never done any experiments on FNST in a real fusion nuclear environment we must be realistic on what

  5. 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.

  6. Hindawi Publishing Corporation Science and Technology of Nuclear Installations

    E-Print Network [OSTI]

    Demazičre, Christophe

    Hindawi Publishing Corporation Science and Technology of Nuclear Installations Volume 2013, Article Department of Nuclear Chemistry, Chalmers University of Technology, 412 96 Gothenburg, Sweden 2 Department of Nuclear Engineering, Chalmers University of Technology, 412 96 Gothenburg, Sweden Correspondence should

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

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

    Fusion Nuclear Science and Technology Program - Status and Plans for Tritium Research Fusion Nuclear Science and Technology Program - Status and Plans for Tritium Research...

  8. 16 years of successful projects in16 years of successful projects in Nuclear Science & TechnologyNuclear Science & Technology

    E-Print Network [OSTI]

    & TechnologyNuclear Science & Technology 13th CERNISTC SAC Seminar New Perspectives of High Energy Physics 01 in Nuclear Science & Technology · Fundamental Nuclear/High Energy Physics · Nuclear safety and efficiency; · Nuclear technologies for medicine; · Fusion; ....observing carefully nonproliferation aspects in all

  9. 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.

  10. 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.

  11. 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.

  12. 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.

  13. 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.

  14. Low Loss LTCC Cavity Filters Using System-on-Package Technology at 60 GHz

    E-Print Network [OSTI]

    Tentzeris, Manos

    1 Low Loss LTCC Cavity Filters Using System-on- Package Technology at 60 GHz Jong-Hoon Lee, Student-on-package (SOP) compact solution for RF front-end modules at 60 GHz using the low- temperature cofired ceramic-dimensional (3-D) low loss 3- pole band pass filter for 60 GHz WLAN narrowband (~ 1GHz) applications

  15. Autonomous Correction of Sensor Data Applied to Building Technologies Using Filtering Methods

    E-Print Network [OSTI]

    Wang, Xiaorui "Ray"

    predictive coding (LPC) filter is also used to model the data. · The LPC filter is a finite impulse response Building Technologies Research at ORNL Kalman and Linear Predictive Coding (LPC) · Residential. · These include power backup outages, data acquisition kernel panics, multiplexer timing failures, sensor wire

  16. Prairie Island Nuclear Station Spent Filter Processing for Direct Disposal - 12333

    SciTech Connect (OSTI)

    Anderson, H. Michael [WMG, Inc., 16 Bank Street, Peekskill, NY 10566 (United States)

    2012-07-01

    This paper will discuss WMG's filter processing experience within the commercial nuclear power industry, specifically recent experience processing high activity spent filters generated by Xcel Energy's Prairie Island Nuclear Station (Prairie Island), located in Welch, MN. WMG processed for disposal eighty-four 55-gallon drums filled with varying types of high activity spent filters. The scope of work involved characterization, packaging plan development, transport to the WMG's Off-Site Processing location, shredding the filter contents of each drum, cement solidifying the shredded filter material, and finally shipping the solidified container of shredded filter material to Clive, Utah where the container was presented to EnergySolutions Disposal site for disposal in their Containerised Waste Facility. This sequence of events presented in this paper took place a total of nine (9) times over a period of four weeks. All 1294 filters were successfully solidified into nine (9) -WMG 142 steel liners, and each was successfully disposed of as Class A Waste at EnergySolutions Disposal Site in Clive, Utah. Prairie Island's waste material was unique in that all its filters were packaged in 55-gallon drums; and since the station packaged its filters in drums it was much easier to develop packaging plans for such a large volume of legacy filters. For this author, having over 20-years of waste management experiences, storing and shipping waste material in 55-gallon drums is not immediately thought of as a highly efficient method of managing its waste material. However, Prairie Island's use of 55-gallon drums to store and package its filters provided a significant advantage. Drums could be mixed and matched to provide the most efficient processing method while still meeting the Waste Class A limits required for disposal. (author)

  17. M. Abdou April 2013 Fusion Nuclear Science and Technology

    E-Print Network [OSTI]

    California at Los Angeles, University of

    M. Abdou April 2013 Fusion Nuclear Science and Technology Challenges and Required R&D Mohamed Fusion Nuclear Science and Technology Challenges and Required R&D Presentation Outline Introduction to the Fusion Nuclear Environment and Fusion Nuclear Components FNST R&D Challenges Need for Fusion Nuclear

  18. 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...

  19. Nuclear fission and nuclear safeguards: Common technologies and challenges

    SciTech Connect (OSTI)

    Keepin, G.R.

    1989-01-01

    Nuclear fission and nuclear safeguards have much in common, including the basic physical phenomena and technologies involved as well as the commitments and challenges posed by expanding nuclear programs in many countries around the world. The unique characteristics of the fission process -- such as prompt and delayed neutron and gamma ray emission -- not only provide the means of sustaining and controlling the fission chain reaction, but also provide unique ''signatures'' that are essential to quantitative measurement and effective safeguarding of key nuclear materials (notably /sup 239/Pu and /sup 235/U) against theft, loss, or diversion. In this paper, we trace briefly the historical emergence of safeguards as an essential component of the expansion of the nuclear enterprise worldwide. We then survey the major categories of passive and active nondestructive assay techniques that are currently in use or under development for rapid, accurate measurement and verification of safe-guarded nuclear materials in the many forms in which they occur throughout the nuclear fuel cycle. 23 refs., 14 figs.

  20. 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.

  1. Graphite in Science and Nuclear Technology

    E-Print Network [OSTI]

    Zhmurikov, Evgenij

    2015-01-01

    This review is devoted to the application of the graphite and graphite composites in the science and technology. The structure and an electrical properties, the technological aspects of producing the high-strength artificial graphite and dynamics of its destruction are considered. These type of graphite are traditionally used in the nuclear industry, so author concentrates on the actual problems of the application and testing of the graphite materials in the modern science and technology. Translated from chapters 1 of the the monograph (by Zhmurikov E.I., Bubnenkov I.A., Pokrovsky A.S. et al. Graphite in Science and Nuclear Technique// eprint arXiv:1307.1869, 07/2013 (BC 2013arXiv1307.1869Z).

  2. Graphite in Science and Nuclear Technology

    E-Print Network [OSTI]

    Evgenij Zhmurikov

    2015-08-12

    This review is devoted to the application of the graphite and graphite composites in the science and technology. The structure and an electrical properties, the technological aspects of producing the high-strength artificial graphite and dynamics of its destruction are considered. These type of graphite are traditionally used in the nuclear industry, so author concentrates on the actual problems of the application and testing of the graphite materials in the modern science and technology. Translated from chapters 1 of the the monograph (by Zhmurikov E.I., Bubnenkov I.A., Pokrovsky A.S. et al. Graphite in Science and Nuclear Technique// eprint arXiv:1307.1869, 07/2013 (BC 2013arXiv1307.1869Z).

  3. NASA's progress in nuclear electric propulsion technology

    SciTech Connect (OSTI)

    Stone, J.R.; Doherty, M.P.; Peecook, K.M.

    1993-01-01

    The National Aeronautics and Space Administration (NASA) has established a requirement for Nuclear Electric Propulsion (NEP) technology for robotic planetary science mission applications with potential future evolution to systems for piloted Mars vehicles. To advance the readiness of NEP for these challenging missions, a near-term flight demonstration on a meaningful robotic science mission is very desirable. The requirements for both near-term and outer planet science missions are briefly reviewed, and the near-term baseline system established under a recent study jointly conducted by the Lewis Research Center (LeRC) and the Jet Propulsion Laboratory (JPL) is described. Technology issues are identified where work is needed to establish the technology for the baseline system, and technology opportunities which could provide improvement beyond baseline capabilities are discussed. Finally, the plan to develop this promising technology is presented and discussed. 19 refs.

  4. NASA's progress in nuclear electric propulsion technology

    SciTech Connect (OSTI)

    Stone, J.R.; Doherty, M.P.; Peecook, K.M.

    1993-06-01

    The National Aeronautics and Space Administration (NASA) has established a requirement for Nuclear Electric Propulsion (NEP) technology for robotic planetary science mission applications with potential future evolution to systems for piloted Mars vehicles. To advance the readiness of NEP for these challenging missions, a near-term flight demonstration on a meaningful robotic science mission is very desirable. The requirements for both near-term and outer planet science missions are briefly reviewed, and the near-term baseline system established under a recent study jointly conducted by the Lewis Research Center (LeRC) and the Jet Propulsion Laboratory (JPL) is described. Technology issues are identified where work is needed to establish the technology for the baseline system, and technology opportunities which could provide improvement beyond baseline capabilities are discussed. Finally, the plan to develop this promising technology is presented and discussed.

  5. Fusion Nuclear Science and Technology ProgramFusion Nuclear Science and Technology Program Issues and Strategy for Fusion Nuclear Science Facility (FNSF)

    E-Print Network [OSTI]

    California at Los Angeles, University of

    Need for Fusion Nuclear Science and Technology ProgramFusion Nuclear Science and Technology Program ­Issues and Strategy for Fusion Nuclear Science Facility (FNSF) ­Key R&D Areas to begin NOW (modeling 12, 2010 #12;Fusion Nuclear Science and Technology (FNST) FNST is the science engineering technology

  6. Energy Department Invests $60 Million to Advance Nuclear Technology...

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

    Invests 60 Million to Advance Nuclear Technology Energy Department Invests 60 Million to Advance Nuclear Technology June 5, 2015 - 11:18am Addthis News Media Contact 202-586-4940...

  7. 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

  8. Fast Introduction to Fusion Nuclear Science and Technology

    E-Print Network [OSTI]

    California at Los Angeles, University of

    Fast Introduction to Fusion Nuclear Science and Technology Blankets, PFC, Materials, Neutronics development still lies ahead: The Development of Fusion Nuclear Science and TechnologyThe Development of Fusion Nuclear Science and Technology 4 The cost of R&D and the time to DEMO and commercialization

  9. NASA's nuclear electric propulsion technology project

    SciTech Connect (OSTI)

    Stone, J.R.; Sovey, J.S. (NASA, Lewis Research Center, Cleveland, OH (United States))

    1992-07-01

    The National Aeronautics and Space Administration (NASA) has initiated a program to establish the readiness of nuclear electric propulsion (NEP) technology for relatively near-term applications to outer planet robotic science missions with potential future evolution to system for piloted Mars vehicles. This program was initiated in 1991 with a very modest effort identified with nuclear thermal propulsion (NTP); however, NEP is also an integral part of this program and builds upon NASA's Base Research and Technology Program in power and electric propulsion as well as the SP-100 space nuclear power program. The NEP Program will establish the feasibility and practicality of electric propulsion for robotic and piloted solar system exploration. The performance objectives are high specific impulse (200 greater than I(sub sp) greater than 10000 s), high efficiency (over 0.50), and low specific mass. The planning for this program was initially focussed on piloted Mars missions, but has since been redirected to first focus on 100-kW class systems for relatively near-term robotic missions, with possible future evolution to megawatt-and multi-megawatt-class systems applicable to cargo vehicles supporting human missions as well as to the piloted vehicles. This paper reviews current plans and recent progress for the overall nuclear electric propulsion project and closely related activities. 33 refs.

  10. Sterling Technology ultra-pure filtered diesel fuel. Final report, April 1984-April 1988

    SciTech Connect (OSTI)

    Adams, E.C.

    1988-05-01

    This report details testing done on ultra-pure filtered diesel fuel and unfiltered diesel fuel. Several barrels of filtered fuel, shipped from the manufacturer--Sterling Technology, Inc., Jacksonville, Florida--were tested using the 690-in. Deutz F-8L-413A Air Cooled V8 Engine. No significant difference was found, but due to a delay in starting the tests, it was suspected that some deterioration might have occurred in the fuel. The objective was to investigate the possible benefits of the ultra-pure filtered diesel fuel in power improvement and reduction of exhaust smoke.

  11. Institute for Critical Technology and Applied Science Seminar Series Emerging Technologies in Nuclear

    E-Print Network [OSTI]

    Crawford, T. Daniel

    Institute for Critical Technology and Applied Science Seminar Series Emerging Technologies in Nuclear Science & Engineering ­ Development of novel techniques/tools using particle transport theory methodologies with Alireza Haghighat, Nuclear Engineering Program, Mechanical Engineering Department Virginia

  12. Fusion Nuclear Science and Technology (FNST) Challenges and Facilities

    E-Print Network [OSTI]

    Fusion Nuclear Science and Technology (FNST) Challenges and Facilities on the Pathway to DEMO Princeton,NJ 7-10 September 2011 1 #12;Fusion Nuclear Science and Technology (FNST) must be the Central Mountain to climb Since we have never done any experiments on FNST in a real fusion nuclear environment, we

  13. Roadmap: Radiologic Imaging Sciences -Nuclear Medicine (with AAS Radiologic Technology) -

    E-Print Network [OSTI]

    Sheridan, Scott

    Roadmap: Radiologic Imaging Sciences - Nuclear Medicine (with AAS Radiologic Technology) - Bachelor Safety 3 C #12;Roadmap: Radiologic Imaging Sciences - Nuclear Medicine (with AAS Radiologic Technology of Radiologic and Imaging Sciences Technology [RE-BRIT-RIS-NMRT] Regional College Catalog Year: 2013-2014 Page 1

  14. Roadmap: Radiologic Imaging Sciences -Nuclear Medicine (with AAS Radiologic Technology) -

    E-Print Network [OSTI]

    Sheridan, Scott

    Roadmap: Radiologic Imaging Sciences - Nuclear Medicine (with AAS Radiologic Technology) - Bachelor Imaging Sciences - Nuclear Medicine (with AAS Radiologic Technology) - Bachelor of Radiologic and Imaging of Radiologic and Imaging Sciences Technology [RE-BRIT-RIS-NMRT] Regional College Catalog Year: 2012-2013 Page 1

  15. 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 >...

  16. 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.

  17. Fuel Cycle Science & Technology | Nuclear Science | ORNL

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

    Radiochemical Separation & Processing Recycle & Waste Management Uranium Enrichment Used Nuclear Fuel Storage, Transportation, and Disposal Fusion Nuclear Science Isotope...

  18. 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 plans for tritium research Presentation from the 35th Tritium Focus Group Meeting held in...

  19. Features of adsorbed radioactive chemical elements and their isotopes distribution in iodine air filters AU-1500 at nuclear power plants

    E-Print Network [OSTI]

    Neklyudov, I M; Dikiy, N P; Ledenyov, O P; Lyashko, Yu V

    2013-01-01

    The main aim of research is to investigate the physical features of spatial distribution of the adsorbed radioactive chemical elements and their isotopes in the granular filtering medium in the iodine air filters of the type of AU1500 in the forced exhaust ventilation systems at the nuclear power plant. The gamma activation analysis method is applied to accurately characterize the distribution of the adsorbed radioactive chemical elements and their isotopes in the granular filtering medium in the AU1500 iodine air filter after its long term operation at the nuclear power plant. The typical spectrum of the detected chemical elements and their isotopes in the AU1500 iodine air filter, which was exposed to the bremsstrahlung gamma quantum irradiation, produced by the accelerating electrons in the tantalum target, are obtained. The spatial distributions of the detected chemical element 127I and some other chemical elements and their isotopes in the layer of absorber, which was made of the cylindrical coal granule...

  20. Features of adsorbed radioactive chemical elements and their isotopes distribution in iodine air filters AU-1500 at nuclear power plants

    E-Print Network [OSTI]

    I. M. Neklyudov; A. N. Dovbnya; N. P. Dikiy; O. P. Ledenyov; Yu. V. Lyashko

    2013-06-21

    The main aim of research is to investigate the physical features of spatial distribution of the adsorbed radioactive chemical elements and their isotopes in the granular filtering medium in the iodine air filters of the type of AU1500 in the forced exhaust ventilation systems at the nuclear power plant. The gamma activation analysis method is applied to accurately characterize the distribution of the adsorbed radioactive chemical elements and their isotopes in the granular filtering medium in the AU1500 iodine air filter after its long term operation at the nuclear power plant. The typical spectrum of the detected chemical elements and their isotopes in the AU1500 iodine air filter, which was exposed to the bremsstrahlung gamma quantum irradiation, produced by the accelerating electrons in the tantalum target, are obtained. The spatial distributions of the detected chemical element 127I and some other chemical elements and their isotopes in the layer of absorber, which was made of the cylindrical coal granules of the type of SKT3, in the AU1500 iodine air filter are also researched. The possible influences by the standing acoustic wave of air pressure in the iodine air filter on the spatial distribution of the chemical elements and their isotopes in the iodine air filter are discussed. The comprehensive analysis of obtained research results on the distribution of the adsorbed chemical elements and their isotopes in the absorber of iodine air filter is performed.

  1. NUCLEAR SCIENCE AND TECHNOLOGY DIVISION OAK RIDGE NATIONAL LABORATORY

    E-Print Network [OSTI]

    McDonald, Kirk

    NUCLEAR SCIENCE AND TECHNOLOGY DIVISION OAK RIDGE NATIONAL LABORATORY U.S. DEPARTMENT OF ENERGY Upton, NY #12;2 NUCLEAR SCIENCE AND TECHNOLOGY DIVISION OAK RIDGE NATIONAL LABORATORY U.S. DEPARTMENT OF ENERGY Outline · Properties, Safety Limits · Background - SNS Target Test Facility · Installing Hg & New

  2. PNNL's Community Science & Technology Seminar Series Nuclear Power in a

    E-Print Network [OSTI]

    PNNL's Community Science & Technology Seminar Series Nuclear Power in a Post-Fukushima World generated by nuclear power. What will the U.S. energy portfolio look like, and how will the energy demand is focused on longer- term operation of nuclear power plants, including measurements to detect

  3. Nuclear Electric Propulsion Technology Panel findings and recommendations

    SciTech Connect (OSTI)

    Doherty, M.P.

    1992-01-01

    Summarized are the findings and recommendations of a triagency (NASA/DOE/DOD) panel on Nuclear Electric Propulsion (NEP) Technology. NEP has been identified as a candidate nuclear propulsion technology for exploration of the Moon and Mars as part of the Space Exploration Initiative (SEI). The findings are stated in areas of system and subsystem considerations, technology readiness, and ground test facilities. Recommendations made by the panel are summarized concerning: (1) existing space nuclear power and propulsion programs, and (2) the proposed multiagency NEP technology development program.

  4. 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...

  5. 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...

  6. 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).

  7. Nuclear Energy Governance and the Politics of Social Justice: Technology, Public Goods, and Redistribution in Russia and France

    E-Print Network [OSTI]

    Grigoriadis, Theocharis N

    2009-01-01

    Atomic Energy Agency. Nuclear Technology Review 2008. Vienna1: Generations of Nuclear Technology Time 53 1945-1965 -the expansion of their nuclear technology potential. 3 The

  8. JOURNAL OF LIGHTWAVE TECHNOLOGY, VOL. 25, NO. 11, NOVEMBER 2007 3283 Tunable Photonic Microwave Bandpass Filter With

    E-Print Network [OSTI]

    Yao, Jianping

    JOURNAL OF LIGHTWAVE TECHNOLOGY, VOL. 25, NO. 11, NOVEMBER 2007 3283 Tunable Photonic Microwave, Member, OSA Abstract--A continuously tunable photonic microwave band- pass filter with positive at different physical locations in the LCFBGs. A two-tap microwave bandpass filter with a free spectral range

  9. 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.

  10. Production Technology | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    Twitter Youtube Flickr RSS People Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure...

  11. 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.

  12. A Unique Master's Program in Combined Nuclear Technology and Nuclear Chemistry at Chalmers University of Technology, Sweden

    SciTech Connect (OSTI)

    Skarnemark, Gunnar; Allard, Stefan; Ekberg, Christian [Nuclear Chemistry, Department of Chemical and Biological Engineering, Chalmers University of Technology, S-41296 Gothenburg (Sweden); Nordlund, Anders [Nuclear Technology, Department of Applied Physics, Chalmers University of Technology S-41296 Gothenburg (Sweden)

    2009-08-19

    The need for engineers and scientists who can ensure safe and secure use of nuclear energy is large in Sweden and internationally. Chalmers University of Technology is therefore launching a new 2-year master's program in Nuclear Engineering, with start from the autumn of 2009. The program is open to Swedish and foreign students. The program starts with compulsory courses dealing with the basics of nuclear chemistry and physics, radiation protection, nuclear power and reactors, nuclear fuel supply, nuclear waste management and nuclear safety and security. There are also compulsory courses in nuclear industry applications and sustainable energy futures. The subsequent elective courses can be chosen freely but there is also a possibility to choose informal tracks that concentrate on nuclear chemistry or reactor technology and physics. The nuclear chemistry track comprises courses in e.g. chemistry of lanthanides, actinides and transactinides, solvent extraction, radioecology and radioanalytical chemistry and radiopharmaceuticals. The program is finished with a one semester thesis project. This is probably a unique master program in the sense of its combination of deep courses in both nuclear technology and nuclear chemistry.

  13. Nuclear Technology & Canadian Oil Sands: Integration of Nuclear Power with In-Situ Oil Extraction

    E-Print Network [OSTI]

    Nuclear Technology & Canadian Oil Sands: Integration of Nuclear Power with In-Situ Oil Extraction A for a Canadian oil sands extraction facility using Steam-Assisted Gravity Drainage (SAGD) technology. The energy to produce steam as well as electricity for the oil sands facility; and (3) using the reactor to produce

  14. References R-3 ANS 1986. Glossary of Terms in Nuclear Science and Technology, American Nuclear Society.

    E-Print Network [OSTI]

    Pennycook, Steve

    of Environment and Conservation, Department of Energy, Oversight Division Status Report to the Public, NashvilleReferences #12;References R-3 REFERENCES ANS 1986. Glossary of Terms in Nuclear Science and Technology, American Nuclear Society. ANSI 1969. N13.1, Sampling Airborne Radioactive Materials in Nuclear

  15. Development and Testing of a Moving Granular Bed Filter at the Taiwan Industrial Technology Research Institute

    SciTech Connect (OSTI)

    Peng, C.Y.; Hsiau, S-S.; Lee, H-T.; Smid, J.; Wu, T-C.

    2002-09-18

    The main purpose of developing high temperature gas cleaning technologies are to clean the gas under high temperature in order to be cost effective and to improve energy efficiency. Moving granular bed filters are technically and economically applicable for high temperature cleaning system because of low cost, possible to keep operation at a constant pressure drop, simple structure, easy in operation and maintenance, no high risk internals, and more tolerant to process thermal flow. Energy and Resource Laboratories, Taiwan Industrial Technology Research Institute (ERL/ITRI) has been developing a moving granular bed filter (MGBF) for BIGCC(Biomass Integrated Gasification Combined Cycle) high temperature gas cleanup. The filter granules move downwards directed by louver-like guide plates and the hot gases penetrate the MGBF horizontally. Filtration mechanisms include collection of the dust cake over the bed media surface and deep bed filtration. Stagnant zones of filter granules combining with the dusts always exist along the louver walls. Such stagnant zones often corrode the louver-like guide plates, increase the system pressure drop and decrease the total reaction efficiency that may endanger MGBF operation. Series louver and inert structure research that modify the granular flow pattern have been designed to eliminate the formation of these stagnant zones. By connecting to an auxiliary dust/bed media separation system, MGBF can be operated continuously at a stable pressure drop with a stable high efficiency. There are several MGBF R&D activities in progress: (1) a 3-dimensional cold flow system for testing the MGBF filtration efficiency; (2) a high temperature gas cleanup experimental system that has been designed and installed; (3) a 2-dimensional flow pattern experimental system for approving design concepts.

  16. 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 leak rates through very small orifices and channels. From sealed PuOsub 2 containers under...

  17. 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.

  18. Advanced Technology Development and Mitigation | National Nuclear...

    National Nuclear Security Administration (NNSA)

    national security missions of the National Nuclear Security Administration. Next Generation Code Development & Applications This product is focused on long-term research that...

  19. On the structurization of coal dust precipitations and their influence on aerodynamic resistance by granulated mediums in air filters at nuclear power plants

    E-Print Network [OSTI]

    Neklyudov, I M; Fedorova, L I; Poltinin, P Ya

    2012-01-01

    The processes of structurization of dust precipitations in granulated filtering mediums, formed by the monolithic glass spherical granules with the diameters of 2mm and 3mm, are re-searched. The distinctions between the distributions of filtered coal dust masses in the air filters with cylindrical granules and the air filters with spherical granules, are found. The influences by the filtered dust masses on the air resistance of both the air filters with the cylindrical granules and the air filters with the spherical granules are described. The conclusions on a possibility of the use of various chemical adsorbents with different geometric forms and volumetric dimensions to improve the filtering properties of granulated filtering mediums in air filters at nuclear power plants are formulated.

  20. On the structurization of coal dust precipitations and their influence on aerodynamic resistance by granulated mediums in air filters at nuclear power plants

    E-Print Network [OSTI]

    I. M. Neklyudov; O. P. Ledenyov; L. I. Fedorova; P. Ya. Poltinin

    2012-07-02

    The processes of structurization of dust precipitations in granulated filtering mediums, formed by the monolithic glass spherical granules with the diameters of 2mm and 3mm, are re-searched. The distinctions between the distributions of filtered coal dust masses in the air filters with cylindrical granules and the air filters with spherical granules, are found. The influences by the filtered dust masses on the air resistance of both the air filters with the cylindrical granules and the air filters with the spherical granules are described. The conclusions on a possibility of the use of various chemical adsorbents with different geometric forms and volumetric dimensions to improve the filtering properties of granulated filtering mediums in air filters at nuclear power plants are formulated.

  1. 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 Division’s 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 65±15 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

  2. The Nuclear Education and Staffing Challenge: Rebuilding Critical Skills in Nuclear Science and Technology

    SciTech Connect (OSTI)

    Wogman, Ned A.; Bond, Leonard J.; Waltar, Alan E.; Leber, R E.

    2005-01-01

    The United States, the Department of Energy (DOE) and its National Laboratories, including the Pacific Northwest National Laboratory (PNNL), are facing a serious attrition of nuclear scientists and engineers and their capabilities through the effects of aging staff. Within the DOE laboratories, 75% of nuclear personnel will be eligible to retire by 2010. It is expected that there will be a significant loss of senior nuclear science and technology staff at PNNL within five years. PNNL's nuclear legacy is firmly rooted in the DOE Hanford site, the World War II Manhattan Project, and subsequent programs. Historically, PNNL was a laboratory were 70% of its activities were nuclear/radiological, and now just under 50% of its current business science and technology are nuclear and radiologically oriented. Programs in the areas of Nuclear Legacies, Global Security, Nonproliferation, Homeland Security and National Defense, Radiobiology and Nuclear Energy still involve more than 1,000 of the 3,800 current laboratory staff, and these include more than 420 staff who are certified as nuclear/radiological scientists and engineers. This paper presents the current challenges faced by PNNL that require an emerging strategy to solve the nuclear staffing issues through the maintenance and replenishment of the human nuclear capital needed to support PNNL nuclear science and technology programs.

  3. The Nuclear Education and Staffing Challenge: Rebuilding Critical Skills in Nuclear Science and Technology.

    SciTech Connect (OSTI)

    Wogman, Ned A.; Bond, Leonard J.; Waltar, Alan E.; Leber, R. E.

    2005-01-01

    The United States, the Department of Energy (DOE) and its National Laboratories, including the Pacific Northwest National Laboratory (PNNL), are facing a serious attrition of nuclear scientists and engineers and their capabilities through the effects of aging staff. Within the DOE laboratories, 75% of nuclear personnel will be eligible to retire by 2010. It is expected that there will be a significant loss of senior nuclear science and technology staff at PNNL within five years. PNNL's nuclear legacy is firmly rooted in the DOE Hanford site, the World War II Manhattan Project, and subsequent programs. Historically, PNNL was a laboratory where 70% of its activities were nuclear/radiological, and now just under 50% of its current business science and technology are nuclear and radiologically oriented. Programs in the areas of Nuclear Legacies, Global Security, Nonproliferation, Homeland Security and National Defense, Radiobiology and Nuclear Energy still involve more than 1,000 of the 3,800 current laboratory staff, and these include more than 420 staff who are certified as nuclear/radiological scientists and engineers. This paper presents the current challenges faced by PNNL that require an emerging strategy to solve the nuclear staffing issues through the maintenance and replenishment of the human nuclear capital needed to support PNNL nuclear science and technology programs.

  4. New Techniques and Technologies for Information Retrieval and Knowledge Extraction from Nuclear Fusion Massive Databases

    E-Print Network [OSTI]

    New Techniques and Technologies for Information Retrieval and Knowledge Extraction from Nuclear Fusion Massive Databases

  5. Latest Developments in Image Processing Methods and Technologies for Magnetic Confinement Nuclear Fusion

    E-Print Network [OSTI]

    Latest Developments in Image Processing Methods and Technologies for Magnetic Confinement Nuclear Fusion

  6. Nuclear technology and the export control laws. [Nuclear technical data military items and classified information

    SciTech Connect (OSTI)

    Lundy, A.S.; Pankratz, M.C.; Hogsett, V.H.; Munroe, J.L.

    1988-01-01

    Three basic US laws regulate the export of commodities, services, and technical data. People working in nuclear fields need to know of these laws and their impact on professional endeavors. Export of technical data means the communication may be a model, blueprint, sketch, or any other device that can convey information. If the data relates to items on one of the control lists, a license must be sought from the appropriate federal agency. The Militarily Critical Technologies List (MCTL), though not itself a control list, plays a major role in determining what technical data will require a validated license. The US Department of Energy (DOE), through Technical Working Group (TWG) 11, is responsible for the Nuclear Technology chapter of the MCTL. TWG 11 also prepares the Nuclear Technology Reference Book (NTRB), a classified guide to sensitive nuclear technology.

  7. 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.

  8. INSTITUTE OF NUCLEAR TECHNOLOGY RADIATION PROTECTION

    E-Print Network [OSTI]

    Occupational Risk Assessment I.A. Papazoglou Human Reliability Z. Nivolianitou Comparative Consequence.A. Papazoglou Energy Technologies & Environmental Impacts A. Stubos Transport Phenomena in Porous Media A. Belesiotis Thermal Storage V. Belesiotis Solar Distillation - Desalination M. Mathioulakis Solar Air

  9. 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 state’s 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.

  10. INSTITUTE OF NUCLEAR TECHNOLOGY RADIATION PROTECTION

    E-Print Network [OSTI]

    . Papazoglou Energy Technologies & Environmental Impacts A. Stubos Transport Phenomena in Porous Media A Assessment of Electrical Generation Systems I. Kollas SYSTEMS RELIABILITY & INDUSTRIAL SAFETY LABORATORY I Plasma in Tokamak Machines N. Tsois PLASMA PHYSICS LABORATORY N. Tsois Thermal Solar Collectors & Systems

  11. Nuclear Reactor Technologies | Department of Energy

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious Rank EERE: Alternative Fuelsof EnergyApril 2014Department ofWind CareerEnergy Nuclear FuelsReactor

  12. Proceedings of the Nuclear Criticality Technology and Safety Project Workshop

    SciTech Connect (OSTI)

    Sanchez, R.G. [comp.

    1994-01-01

    This report is the proceedings of the annual Nuclear Criticality Technology and Safety Project (NCTSP) Workshop held in Monterey, California, on April 16--28, 1993. The NCTSP was sponsored by the Department of Energy and organized by the Los Alamos Critical Experiments Facility. The report is divided into six sections reflecting the sessions outlined on the workshop agenda.

  13. 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.

  14. Roadmap: Radiologic Imaging Sciences Nuclear Medicine (with certification and ATS Radiologic Technology)

    E-Print Network [OSTI]

    Sheridan, Scott

    Roadmap: Radiologic Imaging Sciences ­ Nuclear Medicine (with certification and ATS Radiologic Technology) ­ Bachelor of Radiologic Imaging Sciences Technology [RE-BRIT-RIS-NMHO] Regional College Catalog technology; successfully completed the certification exam for the American Registry of Radiologic Technology

  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, April-- September 1990

    SciTech Connect (OSTI)

    Harmon, J.E. (ed.)

    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.

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

    SciTech Connect (OSTI)

    NONE

    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. [ed.

    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 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.

  20. 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.

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

    Office of Energy Efficiency and Renewable Energy (EERE)

    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...

  2. The Use of Smart Materials Technologies in Radiation Environment and Nuclear Industry

    E-Print Network [OSTI]

    Giurgiutiu, Victor

    1 The Use of Smart Materials Technologies in Radiation Environment and Nuclear Industry Victor ABSTRACT Application of smart materials technology in nuclear industry offer new opportunities safety of nuclear facilities could benefit from the use of smart materials technologies in both

  3. Refractory alloy technology for space nuclear power applications

    SciTech Connect (OSTI)

    Cooper, R.H. Jr.; Hoffman, E.E. (eds.)

    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)

  4. Physical features of small disperse coal dust fraction transportation and structurization processes in iodine air filters of absorption type in ventilation systems at nuclear power plants

    E-Print Network [OSTI]

    Ledenyov, Oleg P; Poltinin, P Ya; Fedorova, L I

    2012-01-01

    The research on the physical features of transportation and structurization processes by the air-dust aerosol in the granular filtering medium with the cylindrical coal adsorbent granules in an air filter of the adsorption type in the heating ventilation and cooling (HVAC) system at the nuclear power plant is completed. The physical origins of the coal dust masses distribution along the absorber with the granular filtering medium with the cylindrical coal granules during the air-dust aerosol intake process in the near the surface layer of absorber are researched. The quantitative technical characteristics of air filtering elements, which have to be considered during the optimization of air filters designs for the application in the ventilation systems at the nuclear power plants, are obtained.

  5. 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)

  6. Influence by small dispersive coal dust particles of different fractional consistence on characteristics of iodine air filter at nuclear power plant

    E-Print Network [OSTI]

    Neklyudov, I M; Fedorova, L I; Poltinin, P Ya

    2013-01-01

    The main purpose of research is to determine the influence by the small dispersive coal dust particles of the different fractional consistence on the technical characteristics of the vertical iodine air filter at nuclear power plant. The research on the transport properties of the small dispersive coal dust particles in the granular filtering medium of absorber in the vertical iodine air filter is completed in the case, when the modeled aerodynamic conditions are similar to the real aerodynamic conditions. It is shown that the appearance of the different fractional consistence of small dispersive coal dust particles with the decreasing dimensions down to the micro and nano sizes at the action of the air dust aerosol stream normally results in a significant change of distribution of the small dispersive coal dust particles masses in the granular filtering medium of an absorber in the vertical iodine air filter, changing the vertical iodine air filter aerodynamic characteristics. The precise characterization of...

  7. Nuclear electric propulsion for planetary science missions: NASA technology program planning

    SciTech Connect (OSTI)

    Doherty, M.P.

    1993-05-01

    This paper presents the status of technology program planning to develop those Nuclear Electric Propulsion technologies needed to meet the advanced propulsion system requirements for planetary science missions in the next century. The technology program planning is based upon technologies with significant development heritage: ion electric propulsion and the SP-100 space nuclear power technologies. Detailed plans are presented for the required ion electric propulsion technology development and demonstration. Closer coordination between space nuclear power and space electric propulsion technology programs is a necessity as technology plans are being further refined in light of NEP concept definition and possible early NEP flight activities.

  8. 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.

  9. 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.

  10. History of the Development of NERVA Nuclear Rocket Engine Technology

    SciTech Connect (OSTI)

    David L. Black

    2000-06-04

    During the 17 yr between 1955 and 1972, the Atomic Energy Commission (AEC), the U.S. Air Force (USAF), and the National Aeronautics and Space Administration (NASA) collaborated on an effort to develop a nuclear rocket engine. Based on studies conducted in 1946, the concept selected was a fully enriched uranium-filled, graphite-moderated, beryllium-reflected reactor, cooled by a monopropellant, hydrogen. The program, known as Rover, was centered at Los Alamos Scientific Laboratory (LASL), funded jointly by the AEC and the USAF, with the intent of designing a rocket engine for long-range ballistic missiles. Other nuclear rocket concepts were studied during these years, such as cermet and gas cores, but are not reviewed herein. Even thought the program went through the termination phase in a very short time, the technology may still be fully recoverable/retrievable to the state of its prior technological readiness in a reasonably short time. Documents; drawings; and technical, purchasing, manufacturing, and materials specifications were all stored for ease of retrieval. If the U.S. space program were to discover a need/mission for this engine, its 1972 'pencils down' status could be updated for the technology developments of the past 28 yr for flight demonstration in 8 or fewer years. Depending on today's performance requirements, temperatures and pressures could be increased and weight decreased considerably.

  11. Proceedings of Nuclear and Emerging Technologies for Space 2013 Albuquerque, NM, February 25-28, 2013

    E-Print Network [OSTI]

    Meunier, Michel

    Proceedings of Nuclear and Emerging Technologies for Space 2013 Albuquerque, NM, February 25 #12;Proceedings of Nuclear and Emerging Technologies for Space 2013 Albuquerque, NM, February 25-28, 2013 Paper 6722 DRAGON5: Designing Computational Schemes Dedicated to Fission Nuclear Reactors

  12. Physical features of accumulation and distribution processes of small disperse coal dust precipitations and absorbed radioactive chemical elements in iodine air filter at nuclear power plant

    E-Print Network [OSTI]

    Ledenyov, Oleg P; Poltinin, P Ya; Fedorova, L I

    2012-01-01

    The physical features of absorption process of radioactive chemical elements and their isotopes in the iodine air filters of the type of AU-1500 at the nuclear power plants are researched. It is shown that the non-homogenous spatial distribution of absorbed radioactive chemical elements and their isotopes in the iodine air filter, probed by the gamma-activation analysis method, is well correlated with the spatial distribution of small disperse coal dust precipitations in the iodine air filter. This circumstance points out to an important role by the small disperse coal dust fractions of absorber in the absorption process of radioactive chemical elements and their isotopes in the iodine air filter. The physical origins of characteristic interaction between the radioactive chemical elements and the accumulated small disperse coal dust precipitations in an iodine air filter are considered. The analysis of influence by the researched physical processes on the technical characteristics and functionality of iodine ...

  13. 395NUCLEAR ENGINEERING AND TECHNOLOGY, VOL.37 NO.4, AUGUST 2005 CONSTRUCTION OF AN ENVIRONMENTAL RADON

    E-Print Network [OSTI]

    395NUCLEAR ENGINEERING AND TECHNOLOGY, VOL.37 NO.4, AUGUST 2005 CONSTRUCTION OF AN ENVIRONMENTAL RADON MONITORING SYSTEM USING CR-39 NUCLEAR TRACK DETECTORS GIL HOON AHN* and JAI-KI LEE1 National Nuclear Management & Control Agency 305-600, POX 114 Yuseong, Daejeon, Korea 1 Dept. of Nuclear

  14. U.S. Department of Energy FreedomCAR & Vehicle Technologies Program: Oil Bypass Filter Technology Evaluation Seventh Quarterly Report April - June 2004

    SciTech Connect (OSTI)

    Larry Zirker; James Francfort; Jordan Fielding

    2004-08-01

    This Oil Bypass Filter Technology Evaluation quarterly report (April–June 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 (DOE) FreedomCAR & Vehicle Technologies Program. Eight INEEL four-cycle diesel engine buses used to transport INEEL employees on various routes and six INEEL Chevrolet Tahoes with gasoline engines are 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 eight diesel engine buses traveled 85,632 miles. As of the end of June 2004, the eight buses have accumulated 498,814 miles since the beginning of the test and 473,192 miles without an oil change. This represents an avoidance of 39 oil changes, which equates to 1,374 quarts (343 gallons) of new oil not consumed and, furthermore, 1,374 quarts of waste oil not generated. One bus had its oil changed due to the degraded quality of the engine oil. Also this quarter, the six Tahoe test vehicles traveled 48,193 miles; to date, the six Tahoes have accumulated 109,708 total test miles. The oil for all six of the Tahoes was changed this quarter due to low Total Base Numbers (TBN). The oil used initially in the Tahoe testing was recycled oil; the recycled oil has been replaced with Castrol virgin oil, and the testing was restarted. However, the six Tahoe’s did travel a total of 98,266 miles on the initial engine oil. This represents an avoidance of 26 oil changes, which equates to 130 quarts (32.5 gallons) of new oil not consumed and, consequently, 130 quarts of waste oil not generated. Based on the number of oil changes avoided by the test buses and Tahoes to date, the potential engine oil savings if an oil bypass filter system were used was estimated for the INEEL, DOE complex and all Federal fleets of on-road vehicles. The estimated potential annual engine oil savings for the three fleets are: INEEL – 3,400 gallons, all DOE fleets – 32,000 gallons, and all Federal fleet – 1.7 million gallons.

  15. Nuclear electric propulsion for planetary science missions: NASA technology program planning

    SciTech Connect (OSTI)

    Doherty, M.P. (NASA Lewis Research Center, 21000 Brookpark Rd., Cleveland, Ohio 44135 (United States))

    1993-01-10

    This paper presents the status of technology program planning to achieve readiness of Nuclear Electric Propulsion technologies needed to meet the advanced propulsion system requirements for planetary science missions in the next century. The technology program planning is based upon technologies of significant maturity: ion electric propulsion and the SP-100 space nulcear power technologies. Detailed plans are presented herein for the required ion electric propulsion technology development and demonstration. Closer coordination between space nuclear power and space electric propulsion technology programs is a necessity as technology plans are being further refined in light of NEP concept definition and possible early NEP flight activities.

  16. 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.

  17. Influence by small dispersive coal dust particles of different fractional consistence on characteristics of iodine air filter at nuclear power plant

    E-Print Network [OSTI]

    I. M. Neklyudov; O. P. Ledenyov; L. I. Fedorova; P. Ya. Poltinin

    2013-02-18

    The main purpose of research is to determine the influence by the small dispersive coal dust particles of the different fractional consistence on the technical characteristics of the vertical iodine air filter at nuclear power plant. The research on the transport properties of the small dispersive coal dust particles in the granular filtering medium of absorber in the vertical iodine air filter is completed in the case, when the modeled aerodynamic conditions are similar to the real aerodynamic conditions. It is shown that the appearance of the different fractional consistence of small dispersive coal dust particles with the decreasing dimensions down to the micro and nano sizes at the action of the air dust aerosol stream normally results in a significant change of distribution of the small dispersive coal dust particles masses in the granular filtering medium of an absorber in the vertical iodine air filter, changing the vertical iodine air filter aerodynamic characteristics. The precise characterization of the aerodynamic resistance of a model of the vertical iodine air filter is completed. The comparative analysis of the technical characteristics of the vertical and horizontal iodine air filters is also made.

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

    Office of Environmental Management (EM)

    Baione Office of Waste Processing DOE-EM Office of Engineering & Technology 2 Outline Nuclear Safety Research & Development Overview Summary of EM- NSR&D Presentations from...

  19. 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.

  20. Fusion Nuclear Science | ORNL

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

    Fusion Nuclear Science Isotope Development and Production Nuclear Security Science & Technology Nuclear Systems Modeling, Simulation & Validation Nuclear Systems Technology...

  1. Energy Department Invests $67 Million to Advanced Nuclear Technology...

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

    to high priority nuclear energy research challenges, including instrumentation and vacuum drying systems associated with the storage of used nuclear fuel, an integrated...

  2. 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.

  3. How to Proceed with the Thorium Nuclear Technology: a Real Options Analysis

    E-Print Network [OSTI]

    Guillas, Serge

    emissions from fossil fuel use, new technology such as passively safe plants, and energy security concerns have all renewed interest in both nuclear power plants and renewable energy (RE) technologies. Fossil in this category may include fusion nuclear energy and new generations of so-called fast and/or breeder reactors

  4. 2 Science and Technology of Nuclear Installations the nuclear data are added in a speci c format to so-called

    E-Print Network [OSTI]

    Demazičre, Christophe

    #12;2 Science and Technology of Nuclear Installations the nuclear data are added in a speci c format to so-called evaluated nuclear data les, such as ENDF-6 (Evaluated Nuclear Data File-6). e be of different type, containing an arbitrary number of nuclear data sets for each isotope, or only one

  5. Critical technologies for reactors used in nuclear electric propulsion

    SciTech Connect (OSTI)

    Bhattacharyya, S.K. (Argonne National Lab., IL (United States))

    1993-01-01

    Nuclear electric Propulsion (NEP) systems are expected to play a significant role in the exploration and exploitation of space. Unlike nuclear thermal propulsion (NTP) systems in which the hot reactor coolant is directly discharged from nozzles to provide the required thrust, NEP systems include electric power generation and conditioning units that in turn are used to drive electric thrusters. These thrusters accelerate sub atomic particles to produce thrust. The major advantage of NEP systems is the ability to provide very high specific impulses ([approximately]5000 s) that minimize the requirement for propellants. In addition, the power systems used in NEP could pro vide the dual purpose of also providing power for the missions at the destination. This synergism can be exploited in shared development costs. The NEP systems produce significantly lower thrust that NTP systems and are generally more massive. Both systems have their appropriate roles in a balanced space program. The technology development needs of NEP systems differ in many important ways from the development needs for NTP systems because of the significant differences in the operating conditions of the systems. The NEP systems require long-life reactor power systems operating at power levels that are considerably lower than those for NTP systems. In contrast, the operational lifetime of an NEP system (years) is orders of magnitude longer than the operational lifetime of NTP systems (thousands of second). Thus, the critical issue of NEP is survivability and reliable operability for very long times at temperatures that are considerably more modest than the temperatures required for effective NTP operations but generally much higher than those experienced in terrestrial reactors.

  6. Int. J. Nuclear Energy Science and Technology, Vol. 2, No. 3, 2006 189 Copyright 2006 Inderscience Enterprises Ltd.

    E-Print Network [OSTI]

    Pázsit, Imre

    Int. J. Nuclear Energy Science and Technology, Vol. 2, No. 3, 2006 189 Copyright © 2006* and Imre Pázsit Department of Nuclear Engineering Chalmers University of Technology SE-412 96 Göteborg and positron transport. He is the Director of the Chalmers Centre for Nuclear Technology, and Head

  7. Nuclear Power and Its Fuel Cycle No technological system more dramatically illustrates the central themes of this book-

    E-Print Network [OSTI]

    Kammen, Daniel M.

    109 7 Nuclear Power and Its Fuel Cycle No technological system more dramatically illustrates public opinion toward nuclear technology. But probably the biggest obstacle to further nuclear the central themes of this book- the complexity of real world applications of technology and the pitfalls

  8. 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.

  9. Office of Nuclear Energy, Science and Technology Executive Summary

    E-Print Network [OSTI]

    the second most important source of electric energy in the United States and at the same time, the most method of generating energy from nuclear fission in both the United States and the world. A key mission system using nuclear energy by 2015; and developing a next-generation nuclear system for deployment after

  10. 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)

  11. Nuclear Resonance Fluorescence for Nuclear Materials Assay

    E-Print Network [OSTI]

    Quiter, Brian Joseph

    2010-01-01

    to Journal of Nuclear Technology. [46] C.J. Hagmann and J.Library for Nuclear Science and Technology,” Nuclear Dataof Standards and Technology daughter nuclear data processing

  12. Autonomous Correction of Sensor Data Applied to Building Technologies Using Filtering Methods

    E-Print Network [OSTI]

    Wang, Xiaorui "Ray"

    , and airflow data, while the LPC method performed best with energy consumption data. Keywords--sensor systems of sensors (e.g., humidity, temperature, and wind speed) to develop and characterize performance. In 2008 in Oak Ridge, TN that integrates sensors with energy-efficient technologies to gauge the integral success

  13. Nuclear Research & Consultancy Group (NRG) develops and provides sustainable nuclear technology for energy, environment, and health. NRG offers a wide range of services to energy

    E-Print Network [OSTI]

    Lindken, Ralph

    Nuclear Research & Consultancy Group (NRG) develops and provides sustainable nuclear technology organizations and various branches of industry - including the nuclear, financial services and medical sectors: Better prediction of the flow and heat transfer in liquid metal cooled nuclear reactors will contribute

  14. 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.

  15. Next Generation Nuclear Plant Project Technology Development Roadmaps: The Technical Path Forward

    SciTech Connect (OSTI)

    John Collins

    2009-01-01

    This document presents the Next Generation Nuclear Plant (NGNP) Systems, Subsystems, and Components, establishes a baseline for the current technology readiness status, and provides a path forward to achieve increasing levels of technical maturity.

  16. International Conference on Nuclear Data for Science and Technology 2007 DOI: 10.1051/ndata:07756

    E-Print Network [OSTI]

    Danon, Yaron

    International Conference on Nuclear Data for Science and Technology 2007 DOI: 10.1051/ndata:07756 at http://nd2007.edpsciences.org or http://dx.doi.org/10.1051/ndata:07756 #12;402 International Conference

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

    Office of Scientific and Technical Information (OSTI)

    that could affect geologic high-level waste repositories Not Available (1984) 32 Reactor safety study. An assessment of accident risks in U. S. commercial nuclear power...

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

    SciTech Connect (OSTI)

    M. D. Staiger

    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.

  19. Technology diffusion of a different nature: Applications of nuclear safeguards technology to the chemical weapons verification regime

    SciTech Connect (OSTI)

    Kadner, S.P. [Aquila Technologies Group, Inc., Albuquerque, NM (United States); Reisman, A. [Brookhaven National Lab., Upton, NY (United States); Turpen, E. [Aquila Technologies Group, Inc., Cambridge, MA (United States)

    1996-10-01

    The following discussion focuses on the issue of arms control implementation from the standpoint of technology and technical assistance. Not only are the procedures and techniques for safeguarding nuclear materials undergoing substantial changes, but the implementation of the Chemical Weapons Convention (CWC) and the Biological Weapons Convention (BWC) will give rise to technical difficulties unprecedented in the implementation of arms control verification. Although these regimes present new challenges, an analysis of the similarities between the nuclear and chemical weapons non-proliferation verification regimes illustrates the overlap in technological solutions. Just as cost-effective and efficient technologies can solve the problems faced by the nuclear safeguards community, these same technologies offer solutions for the CWC safeguards regime. With this in mind, experts at the Organization for the Prohibition of Chemical Weapons (OPCW), who are responsible for verification implementation, need to devise a CWC verification protocol that considers the technology already available. The functional similarity of IAEA and the OPCW, in conjunction with the technical necessities of both verification regimes, should receive attention with respect to the establishment of a technical assistance program. Lastly, the advanced status of the nuclear and chemical regime vis-a-vis the biological non-proliferation regime can inform our approach to implementation of confidence building measures for biological weapons.

  20. Overview of Fusion Nuclear Technology in the US

    E-Print Network [OSTI]

    / Shield Module 18 ­ Tokamak Exhaust Plant IFE Technology Research ­ High Average Power Laser ­ Z) Department of Energy (DOE) Enabling Technologies Program ITER Project Office (US-IPO) High Average Power is coordinated by the Virtual Laboratory for Technology - VLT Director S. Milora Deputy Director D. Petti Program

  1. 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.

  2. Nuclear Materials Technology Division/Los Alamos National Laboratory

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantityBonneville Power Administration wouldMass map shinesSolarNewsusceptometer under pressure |CafésNuclearNuclear16 NuclearWinter

  3. Nuclear Materials Technology Division/Los Alamos National Laboratory

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantityBonneville Power Administration wouldMass map shinesSolarNewsusceptometer under pressure |CafésNuclearNuclear16 NuclearWinter0

  4. FY 2010 National Security Technologies, LLC, PER Summary | National Nuclear

    National Nuclear Security Administration (NNSA)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity of NaturalDukeWakefield Municipal GasAdministration Medal01 Sandia National 1NuclearNational NuclearNuclearFY 2010

  5. 11.11.2004 08:48:00 GMT China aims to employ nuclear fusion technology in power generation

    E-Print Network [OSTI]

    Search 11.11.2004 08:48:00 GMT China aims to employ nuclear fusion technology in power generation to employ nuclear fusion technologies in power generation by 2050. China will adopt a three-step strategy-2% to 60-70%; and third step is the employment of nuclear fusion. However, a report by Zhongguo Dianli Wang

  6. Nuclear Materials Science:Materials Science Technology:MST-16...

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

    Nuclear Materials Science (MST-16) Home About Us MST Related Links Research Highlights Focus on Facilities MST e-News Experimental Physical Sciences Vistas MaRIE: Matter-Radiation...

  7. March 2014 Most Viewed Documents for Fission And Nuclear Technologies...

    Office of Scientific and Technical Information (OSTI)

    phases in various two-phase flow regimes Ishii, M. (1977) 20 > Fundamental aspects of nuclear reactor fuel elements: solutions to problems Olander, D.R. (1976) 20 > Title list...

  8. June 2014 Most Viewed Documents for Fission And Nuclear Technologies...

    Office of Scientific and Technical Information (OSTI)

    summary: main report. PWR and BWR Not Available (1975) 28 Fundamental aspects of nuclear reactor fuel elements: solutions to problems Olander, D.R. (1976) 26 Vapor-liquid...

  9. March 2015 Most Viewed Documents for Fission And Nuclear Technologies...

    Office of Scientific and Technical Information (OSTI)

    of Stellite Alloys 12 and 712 Mickalonis, J.I. (2000) 50 Fundamental aspects of nuclear reactor fuel elements Olander, D.R. (1976) 49 Materials and design bases issues in...

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

    Office of Scientific and Technical Information (OSTI)

    bridge ten millennia. Contains glossary Sebeok, T.A. (1984) 30 Fundamental aspects of nuclear reactor fuel elements: solutions to problems Olander, D.R. (1976) 30 Vapor-liquid...

  11. 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....

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

    Energy Savers [EERE]

    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...

  13. An historical perspective of the NERVA nuclear rocket engine technology program. Final Report

    SciTech Connect (OSTI)

    Robbins, W.H.; Finger, H.B.

    1991-07-01

    Nuclear rocket research and development was initiated in the United States in 1955 and is still being pursued to a limited extent. The major technology emphasis occurred in the decade of the 1960s and was primarily associated with the Rover/NERVA Program where the technology for a nuclear rocket engine system for space application was developed and demonstrated. The NERVA (Nuclear Engine for Rocket Vehicle Application) technology developed twenty years ago provides a comprehensive and viable propulsion technology base that can be applied and will prove to be valuable for application to the NASA Space Exploration Initiative (SEI). This paper, which is historical in scope, provides an overview of the conduct of the NERVA Engine Program, its organization and management, development philosophy, the engine configuration, and significant accomplishments.

  14. 309NUCLEAR ENGINEERING AND TECHNOLOGY, VOL.37 NO.4, AUGUST 2005 A NEW BOOK: "LIGHT-WATER REACTOR MATERIALS"

    E-Print Network [OSTI]

    Motta, Arthur T.

    309NUCLEAR ENGINEERING AND TECHNOLOGY, VOL.37 NO.4, AUGUST 2005 A NEW BOOK: "LIGHT-WATER REACTOR review; it is a book preview. Thirty years ago, "Fundamental Aspects of Nuclear Reactor Fuel Elements of nuclear fuels among other topics pertinent to the materials in the ensemble of the nuclear reactor

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

    E-Print Network [OSTI]

    Danon, Yaron

    ENDF/B-VII.1 Nuclear Data for Science and Technology: Cross Sections, Covariances, Fission Product Jozef Stefan Institute, Jamova 39, 1000 Ljubljana, Slovenia 11 Nuclear Research and Consultancy Group, P 2011) The ENDF/B-VII.1 library is our latest recommended evaluated nuclear data file for use in nuclear

  16. Nuclear Energy Governance and the Politics of Social Justice: Technology, Public Goods, and Redistribution in Russia and France

    E-Print Network [OSTI]

    Grigoriadis, Theocharis N

    2009-01-01

    Electricity Markets" OECD/IEA Report 2000. OECD/IEA. "Nuclear Power in the OECD" OECD/IEA Report 2001.OECD/IEA. "Nuclear Power". IEA Energy Technology Essentials,

  17. 1472 IEEE PHOTONICS TECHNOLOGY LETTERS, VOL. 19, NO. 19, OCTOBER 1, 2007 A Tunable Photonic Microwave Filter With

    E-Print Network [OSTI]

    Yao, Jianping

    Microwave Filter With a Complex Coefficient Using an Optical RF Phase Shifter Yu Yan and Jianping Yao, Senior Member, IEEE Abstract--A novel tunable photonic microwave filter with complex coefficients modulators, and the phase shift remains constant over the microwave spectral region of interest. A two

  18. IEEE PHOTONICS TECHNOLOGY LETTERS, VOL. 25, NO. 19, OCTOBER 1, 2013 1889 A Nonuniformly Spaced Microwave Photonic Filter

    E-Print Network [OSTI]

    Yao, Jianping

    Microwave Photonic Filter Using a Spatially Discrete Chirped FBG Chao Wang, Member, IEEE, and Jianping Yao microwave delay-line filter imple- mented using an incoherent broadband optical source and a spatially response is achieved. To verify the effectiveness of the proposed method, a flat-top bandpass microwave

  19. Nuclear rocket performance based on Rover/NERVA technology

    SciTech Connect (OSTI)

    Kirk, W.L.

    1990-01-01

    It has been suggested that the 1955-1972 nuclear rocket development (Rover) program provides a strong foundation for a renewed nuclear engine development effort. It is concluded that there is an extensive development base deriving from the Rover/NERVA program for bead-loaded graphite-fueled reactors (Isp = 825-900 s), a moderate base for composite fuel (Isp = 875-925 s), and a modest base for carbide fuel (Isp = 975-1025 s). For carbide fuel and to some extent for composite fuel, there is a potential for considerable increase in reactor core and presumable engine lifetime with only modest reduction in Isp.

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

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantityBonneville Power Administration wouldMass map shinesSolarNewsusceptometer under pressure |CafésNuclearNuclear Fuels011

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

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantityBonneville Power Administration wouldMass map shinesSolarNewsusceptometer under pressure |CafésNuclearNuclear Fuels011Magnetic

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

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantityBonneville Power Administration wouldMass map shinesSolarNewsusceptometer under pressure |CafésNuclearNuclear

  3. Nuclear Materials Technology Division/Los Alamos National Laboratory

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantityBonneville Power Administration wouldMass map shinesSolarNewsusceptometer under pressure |CafésNuclearNuclear16

  4. Nuclear Materials Technology Division/Los Alamos National Laboratory

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantityBonneville Power Administration wouldMass map shinesSolarNewsusceptometer under pressure |CafésNuclearNuclear16Los Alamos

  5. Nuclear Materials Technology Division/Los Alamos National Laboratory

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantityBonneville Power Administration wouldMass map shinesSolarNewsusceptometer under pressure |CafésNuclearNuclear16Los AlamosSpring

  6. Nuclear Materials Technology Division/Los Alamos National Laboratory

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantityBonneville Power Administration wouldMass map shinesSolarNewsusceptometer under pressure |CafésNuclearNuclear16Los

  7. Nuclear Materials Technology Division/Los Alamos National Laboratory

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantityBonneville Power Administration wouldMass map shinesSolarNewsusceptometer under pressure |CafésNuclearNuclear16Los6 Los Alamos

  8. Nuclear Materials Technology Division/Los Alamos National Laboratory

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantityBonneville Power Administration wouldMass map shinesSolarNewsusceptometer under pressure |CafésNuclearNuclear16Los6 Los

  9. Nuclear Materials Technology Division/Los Alamos National Laboratory

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantityBonneville Power Administration wouldMass map shinesSolarNewsusceptometer under pressure |CafésNuclearNuclear16Los6 LosWinter

  10. Nuclear Materials Technology/Los Alamos National Laboratory

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantityBonneville Power Administration wouldMass map shinesSolarNewsusceptometer under pressure |CafésNuclearNuclear16Los6

  11. Nuclear Materials Technology/Los Alamos National Laboratory

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantityBonneville Power Administration wouldMass map shinesSolarNewsusceptometer under pressure |CafésNuclearNuclear16Los6Shelf-Life

  12. FY 2009 National Security Technologies, LLC, PER Summary | National Nuclear

    National Nuclear Security Administration (NNSA)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity of NaturalDukeWakefield Municipal GasAdministration Medal01 Sandia National 1Nuclear SecurityNuclear

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

    SciTech Connect (OSTI)

    Gohar, Yousry; /Argonne; 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.

  14. Nuclear Research & Consultancy Group (NRG) develops and provides sustainable nuclear technology for energy, environment, and health. NRG offers a wide range of services to energy

    E-Print Network [OSTI]

    Vuik, Kees

    for energy, environment, and health. NRG offers a wide range of services to energy utilities, governmentNuclear Research & Consultancy Group (NRG) develops and provides sustainable nuclear technology organizations and various branches of industry - including the nuclear, financial services and medical sectors

  15. 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.

  16. Making the World Safe for Nuclear Energy 65 John Deutch, Institute Professor at the Massachusetts Institute of Technology, served as

    E-Print Network [OSTI]

    Deutch, John

    Making the World Safe for Nuclear Energy 65 John Deutch, Institute Professor at the Massachusetts Institute of Technology, served as Under Secretary of Defense for Acquisition & Technology, Deputy Secretary of Defense, and Director of Central Intelligence in the Clinton

  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. Massachusetts Institute of Technology Department of Nuclear Engineering

    E-Print Network [OSTI]

    . · No Reprocessing · High Burnup >90,000 Mwd/MT · Direct Disposal of HLW #12;Massachusetts Institute of Technology it can compete with natural gas and still meet safety, proliferation resistance and waste disposal Safety · Improved Proliferation Resistance · Readily Disposable Waste Form #12;Massachusetts Institute

  20. Fusion Nuclear Science and Technology (FNST) Mohamed Abdou

    E-Print Network [OSTI]

    of Energy Research and Educa;on Leaders, CEREL (USA) With input from the FNST Community Remarks at the FPA and Applied Science (UCLA) Director, Center for Energy Science & Technology (UCLA) President, Council launch an aggressive FNST R&D program if fusion energy is to be realized in the 21st century

  1. Summary and recommendations on nuclear electric propulsion technology for the space exploration initiative

    SciTech Connect (OSTI)

    Doherty, M.P.; Holcomb, R.S.

    1993-04-01

    A project in Nuclear Electric Propulsion (NEP) technology is being established to develop the NEP technologies needed for advanced propulsion systems. A paced approach has been suggested which calls for progressive development of NEP component and subsystem level technologies. This approach will lead to major facility testing to achieve TRL-5 for megawatt NEP for SEI mission applications. This approach is designed to validate NEP power and propulsion technologies from kilowatt class to megawatt class ratings. Such a paced approach would have the benefit of achieving the development, testing, and flight of NEP systems in an evolutionary manner. This approach may also have the additional benefit of synergistic application with SEI extraterrestrial surface nuclear power applications.

  2. FY 2011 National Security Technologies, LLC, PER Summary | National Nuclear

    National Nuclear Security Administration (NNSA)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity of NaturalDukeWakefield Municipal GasAdministration Medal01 Sandia National 1NuclearNationalNational

  3. 2012 Nuclear Energy Enabling Technology Factsheet | Department of Energy

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity of Natural GasAdjustmentsShirleyEnergyTher i n c i p a l De p u t y A s s i s tDistributedDISCLAIMER ThisNationalNuclear

  4. Future Science & Technology Programs | National Nuclear Security

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity ofkandz-cm11 Outreach Home Room NewsInformation Current HABFESOpportunities Nuclear Physics (NP) NPAdministration Future

  5. Preventing Proliferation of Nuclear Materials and Technology | National

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity ofkandz-cm11 Outreach Home RoomPreservation of Fe(II) by Carbon-Rich Matrices in Hydrothermal PlumesPress1, 2015Nuclear

  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. 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.

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

    SciTech Connect (OSTI)

    Camillo A. DiNunzio Framatome ANP DE& S; Dr. Abhinav Gupta Assistant Professor NCSU; Dr. Michael Golay Professor MIT Dr. Vincent Luk Sandia National Laboratories; Rich Turk Westinghouse Electric Company Nuclear Systems; Charles Morrow, Sandia National Laboratories; Geum-Taek Jin, Korea Power Engineering Company Inc.

    2002-11-30

    OAK-B135 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.

  9. SCINTILLA A European project for the development of scintillation detectors and new technologies for nuclear security

    E-Print Network [OSTI]

    A. Alemberti; M. Battaglieri; E. Botta; R. De Vita; E. Fanchini; G. Firpo

    2014-04-14

    Europe monitors transits using radiation detectors to prevent illicit trafficking of nuclear materials. The SCINTILLA project aims to develop a toolbox of innovative technologies designed to address different usage cases. This article will review the scope, approach, results of the first benchmark campaign and future plans of the SCINTILLA project.

  10. SCINTILLA A European project for the development of scintillation detectors and new technologies for nuclear security

    E-Print Network [OSTI]

    Alemberti, A; Botta, E; De Vita, R; Fanchini, E; Firpo, G

    2014-01-01

    Europe monitors transits using radiation detectors to prevent illicit trafficking of nuclear materials. The SCINTILLA project aims to develop a toolbox of innovative technologies designed to address different usage cases. This article will review the scope, approach, results of the first benchmark campaign and future plans of the SCINTILLA project.

  11. International Symposium on Fusion Nuclear Technology (ISFNT-5) SAFETY ISSUES ASSOCIATED WITH MOBILIZED ACTIVATION

    E-Print Network [OSTI]

    California at Los Angeles, University of

    of the tin component. Screening Criteria The designs under development in the APEX project are at a pre project, we have developed a set of screening criteria that are used at early stages of design to identify Symposium on Fusion Nuclear Technology (ISFNT-5) A design must adequately transfer heat from plasma

  12. 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.

  13. Innovative nuclear thermal propulsion technology evaluation: Results of the NASA/DOE Task Team study

    SciTech Connect (OSTI)

    Howe, S. (Los Alamos National Lab., NM (United States)); Borowski, S. (National Aeronautics and Space Administration, Cleveland, OH (United States). Lewis Research Center); Motloch, C. (EG and G Idaho, Inc., Idaho Falls, ID (United States)); Helms, I. (Nuclear Utility Services, Damascus, MD (United States)); Diaz, N.; Anghaie, S. (Florida Univ., Gainesville, FL (United States)); Latham, T. (United

    1991-01-01

    In response to findings from two NASA/DOE nuclear propulsion workshops held in the summer of 1990, six task teams were formed to continue evaluation of various nuclear propulsion concepts. The Task Team on Nuclear Thermal Propulsion (NTP) created the Innovative Concepts Subpanel to evaluate thermal propulsion concepts which did not utilize solid fuel. The Subpanel endeavored to evaluate each of the concepts on a level technological playing field,'' and to identify critical technologies, issues, and early proof-of-concept experiments. The concepts included the liquid core fission, the gas core fission, the fission foil reactors, explosively driven systems, fusion, and antimatter. The results of the studies by the panel will be provided. 13 refs., 6 figs., 2 tabs.

  14. 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.

  15. State Nuclear Power Technology Corporation SNPTC | Open Energy Information

    Open Energy Info (EERE)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on QA:QA J-E-1 SECTION J APPENDIX ECoop Inc JumpHeter BatterySolarfinMarket Studies Jump to:Stardate SolarTechnology

  16. Technology Survey and Performance Scaling for the Design of High Power Nuclear Electric Power and Propulsion Systems

    E-Print Network [OSTI]

    1 Technology Survey and Performance Scaling for the Design of High Power Nuclear Electric Power OF HIGH POWER NUCLEAR ELECTRIC POWER AND PROPULSION SYSTEMS by Daniel B. White Jr. Submitted for the degree of Doctor of Philosophy in Aeronautics and Astronautics ABSTRACT High power nuclear electric

  17. Abstract. The problem of controlled nuclear fusion (CNF) is a colossal scientific and technological challenge on a global

    E-Print Network [OSTI]

    Abstract. The problem of controlled nuclear fusion (CNF) is a colossal scientific and technological044n08ABEH001068 The initial period in the history of nuclear fusion research at the Kurchatov Institute1 V D Shafranov 1. Introduction The first period of research into controlled nuclear fusion (CNF

  18. 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...

  19. 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.

  20. Disk filter

    DOE Patents [OSTI]

    Bergman, Werner (Pleasanton, CA)

    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.

  1. Research Areas | Nuclear Science | ORNL

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

    Fuel Cycle Science & Technology Fusion Nuclear Science Isotope Development and Production Nuclear Security Science & Technology Nuclear Systems Modeling, Simulation & Validation...

  2. IEEE PHOTONICS TECHNOLOGY LETTERS, VOL. 22, NO. 7, APRIL 1, 2010 477 Differential Monitoring of AWG-Filtered Reflection

    E-Print Network [OSTI]

    Park, Namkyoo

    in lightwave communication systems, its direct application to injection-locked, wavelength-divi- sion-Filtered Reflection Signal for Accurate Transmitter Power Control of Injection-Locked WDM PON Systems Kyoungmin Kim control architecture for the injection-locked, wavelength- division-multiplexed passive optical network

  3. 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.

  4. 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.

  5. The Nuclear Emulsion Technology and the Analysis of the OPERA Experiment Data

    E-Print Network [OSTI]

    Tsutomu Fukuda

    2009-10-17

    OPERA is an experiment that aims at detecting the appearance of tau-neutrino in an almost pure mu-neutrino beam (the CNGS neutrino beam) through oscillation. OPERA is a hybrid detector that associates nuclear emulsions to electronic detectors. The nuclear emulsion provides the resolution necessary to detect tau-neutrino CC interactions. The first physics run started in July and ended in November 2008. In this presentation, the status of the emulsion technology and of the analysis of its data is reported.

  6. NEAC Nuclear Reactor Technology (NRT) Subcommittee Advanced Test and/or Demonstration Reactor Planning Study

    Energy Savers [EERE]

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on DeliciousMathematicsEnergyInterested Parties -Department of EnergyNEW YORKFuel Cycle TechnologiesNuclear

  7. 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.

  8. Nuclear Systems Modeling, Simulation & Validation | Nuclear Science...

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

    Research Areas Fuel Cycle Science & Technology Fusion Nuclear Science Isotope Development and Production Nuclear Security Science & Technology Nuclear Systems Modeling, Simulation...

  9. 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.

  10. 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.

  11. 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.

  12. 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.

  13. Professor Emeritus of Nuclear Science and Engineering Massachusetts Institute of Technology, Cambridge, MA 02139 (USA), syip@mit.edu

    E-Print Network [OSTI]

    Chen, Sow-Hsin

    , stress corrosion fatigue of metals in harsh oil-well environment, and creep in irradiated nuclear reactor (aging) phenomena in complex but technologically significant materials, such as hardening of cement paste

  14. 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.

  15. ``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.

  16. 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).

  17. Experts in Defense: How China’s Academicians Contribute to Its Defense Science and Technology Development

    E-Print Network [OSTI]

    WILSON, Jordan

    2015-01-01

    leader Nuclear propulsion and basic nuclear technology Groupmember Nuclear weapons technology Group leader Precisionrockets Information technology and computing Nuclear Medical

  18. Tags and seals for controling nuclear materials, Arms control and nonproliferation technologies. Second quarter 1993

    SciTech Connect (OSTI)

    Staehle, G; Talaber, C; Stull, S; Moulthrop, P [eds.

    1993-12-31

    This issue of Arms Control and Nonproliferation Technologies summarizes demonstrations and addresses related topics. The first article, ``Basic Nuclear Material Control and Accountability Concepts as Might be Applied to the Uranium from the US-Russian HEU Purchase,`` describes safeguards sybsystems necessary for effective nuclear material safeguards. It also presents a general discussion on HEU-to-low-enrichment uranium (LEU) commingling processes and suggests applicable key measurement points. The second article, ``A Framework for Evaluating Tamper-Indicating-Device Technologies (TIDs),`` describes their uses, proper selection, and evaluation. The final three articles discuss the tags and seals applications and general characteristics of several nuclear material containers: the Type 30B uranium hexafluoride container, the AT-400R container, and the DOT Specification 6M container for SNM. Finally, the Appendix displays short descriptions and illustrations of seven tags and seals, including: the E-cup and wire seal, the python seal, the secure loop inspectable tag/seal (SLITS), bolt-and-loop type electronic identification devices, and the shrink-wrap seal.

  19. 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...

  20. Distribution of small dispersive coal dust particles and absorbed radioactive chemical elements in conditions of forced acoustic resonance in iodine air filter at nuclear power plant

    E-Print Network [OSTI]

    Oleg P. Ledenyov; Ivan M. Neklyudov

    2013-06-14

    The physical features of distribution of the small dispersive coal dust particles and the adsorbed radioactive chemical elements and their isotopes in the absorber with the granular filtering medium with the cylindrical coal granules were researched in the case of the intensive air dust aerosol stream flow through the iodine air filter (IAF). It was shown that, at the certain aerodynamic conditions in the IAF, the generation of the acoustic oscillations is possible. It was found that the acoustic oscillations generation results in an appearance of the standing acoustic waves of the air pressure (density) in the IAF. In the case of the intensive blow of the air dust aerosol, it was demonstrated that the standing acoustic waves have some strong influences on both: 1) the dynamics of small dispersive coal dust particles movement and their accumulation in the IAF; 2) the oversaturation of the cylindrical coal granules by the adsorbed radioactive chemical elements and their isotopes in the regions, where the antinodes of the acoustic waves are positioned. Finally, we completed the comparative analysis of the theoretical calculations with the experimental results, obtained for the cases of: 1) the experimental aerodynamic modeling of physical processes of the absorbed radioactive chemical elements and their isotopes distribution in the IAF; and 2) the gamma-activation spectroscopy analysis of the absorbed radioactive chemical elements and their isotopes distribution in the IAF. We made the innovative propositions on the necessary technical modifications with the purpose to improve the IAF technical characteristics and increase its operational time at the nuclear power plant (NPP), going from the completed precise characterization of the IAF parameters at the long term operation.

  1. 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.

  2. 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.

  3. The Nuclear Revolution, Relative Gains, and International Nuclear Assistance

    E-Print Network [OSTI]

    Kroenig, Matthew

    2006-01-01

    it would transfer nuclear technology. Washington Post. 26preferences: the export of sensitive nuclear technology.export of sensitive nuclear technology presents a kind of

  4. 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.

  5. 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.

  6. Filtering apparatus

    DOE Patents [OSTI]

    Haldipur, Gaurang B. (Monroeville, PA); Dilmore, William J. (Murrysville, PA)

    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.

  7. China's Nuclear Industry After Fukushima

    E-Print Network [OSTI]

    YUAN, Jingdong

    2013-01-01

    the previous year. NUCLEAR TECHNOLOGY AND FUEL CYCLES China’third-generation nuclear technology and reactor design, withs own third-generation nuclear technology. Westing- house,

  8. 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.

  9. Nuclear Resonance Fluorescence to Measure Plutonium Mass in Spent Nuclear Fuel

    E-Print Network [OSTI]

    Ludewigt, Bernhard A

    2011-01-01

    10-01096) Journal of Nuclear Technology, in Press. [46] G.W.Library for Nuclear Science and Technology,” Nuclear Datacalculations,” Nuclear Data for Science and Technology

  10. 288 Int. J. Nuclear Energy Science and Technology, Vol. 7, No. 4, 2013 Multi-physics modelling of nuclear reactors

    E-Print Network [OSTI]

    Demazičre, Christophe

    of nuclear reactors: current practices in a nutshell Christophe Demazičre Department of Applied Physics of nuclear reactors are based on the use of different solvers for resolving the different physical fields and the corresponding approximations. Keywords: nuclear reactors; multi-physics; multi-scale; modelling; deterministic

  11. Status report on the activity of the TT network The technology transfer network of institutions active in particle, astro-particle and nuclear physics

    E-Print Network [OSTI]

    2014-01-01

    Status report on the activity of the TT network The technology transfer network of institutions active in particle, astro-particle and nuclear physics

  12. Continuation of the activity of the TT network The technology transfer network of institutions active in particle, astro-particle and nuclear physics

    E-Print Network [OSTI]

    2011-01-01

    Continuation of the activity of the TT network The technology transfer network of institutions active in particle, astro-particle and nuclear physics

  13. 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.

  14. 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.

  15. 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.

  16. Accelerator technology for Los Alamos nuclear-waste-transmutation and energy-production concepts

    SciTech Connect (OSTI)

    Lawrence, G.P.; Jameson, R.A.; Schriber, S.O.

    1991-01-01

    Powerful proton linacs are being studied at Los Alamos as drivers for high-flux neutron sources that can transmute long-lived fission products and actinides in defense nuclear waste, and also as drivers of advanced fission-energy systems that could generate electric power with no long-term waste legacy. A transmuter fed by an 800-MeV, 140-mA cw conventional copper linac could destroy the accumulated {sup 99}Tc and {sup 129}I at the DOE's Hanford site within 30 years. A high-efficiency 1200-MeV, 140-mA niobium superconducting linac could drive an energy-producing system generating 1-GWe electric power. Preliminary design concepts for these different high-power linacs are discussed, along with the principal technical issues and the status of the technology base. 9 refs., 5 figs., 4 tabs.

  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. 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.

  19. 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.

  20. 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.

  1. 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. __________________________________________________

  2. 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.

  3. 288 Int. J. Nuclear Energy Science and Technology, Vol. 7, No. 4, 2013 Copyright 2013 Inderscience Enterprises Ltd.

    E-Print Network [OSTI]

    Demazičre, Christophe

    and boiling water reactor physics, reactor dynamics applied to both critical and sub-critical systems, power, Chalmers University of Technology, Sweden. His research interests include pressurised water reactor Inderscience Enterprises Ltd. Multi-physics modelling of nuclear reactors: current practices in a nutshell

  4. JOURNAL OF THE AMERICAN SOCIETY FOR INFORMATION SCIENCE AND TECHNOLOGY, 57(3):306320, 2006 The outputs of several information filtering (IF) systems

    E-Print Network [OSTI]

    documents in an incoming stream of information. This becomes a dual objective: to maximize the relevant IF systems according to each user's preferences (profile). The combination seeks to maximize the expected filtering (IF) systems to maximize user utility. Information filtering systems seek precisely the relevant

  5. 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.

  6. 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.

  7. A Characteristics-Based Approach to Radioactive Waste Classification in Advanced Nuclear Fuel Cycles

    E-Print Network [OSTI]

    Djokic, Denia

    2013-01-01

    Repository”,   Nuclear  Technology,   154,   April  2006.  Materials,”  Nuclear   Technology,  62,  335  (1983).  ERA  1974]   of   nuclear   technologies   into   the  

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

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

    2005deerzirker.pdf More Documents & Publications Demonstrated Petroleum Reduction Using Oil Bypass Filter Technology on Heavy and Light Vehicles Development of Partial Filter...

  9. Nuclear Energy Governance and the Politics of Social Justice: Technology, Public Goods, and Redistribution in Russia and France

    E-Print Network [OSTI]

    Grigoriadis, Theocharis N

    2009-01-01

    waste disposal (Low) and nuclear reactor construction (Construction of Nuclear Reactors Global Sustainability (High) Nuclear Waste

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

    Office of Energy Efficiency and Renewable Energy (EERE)

    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...

  11. 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.

  12. 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.

  13. Addendum to the Calcined Waste Storage at the Idaho Nuclear Technology Center

    SciTech Connect (OSTI)

    M. D. Staiger; Michael Swenson; T. R. Thomas

    2004-05-01

    This report is an addendum to the report Calcined Waste Storage at the Idaho Nuclear Technology and Engineering Center, INEEL/EXT-98-00455 Rev. 1, June 2003. The original report provided a summary description of the Calcined Solids Storage Facilities (CSSFs). It also contained dozens of pages of detailed data tables documenting the volume and composition (chemical content and radionuclide activity) of the calcine stored in the CSSFs and the liquid waste from which the calcine was derived. This addendum report compiles the calcine composition data from the original report. It presents the compiled data in a graphical format with units (weight percent, curies per cubic meter, and nanocuries per gram) that are commonly used in regulatory and waste acceptance criteria documents. The compiled data are easier to use and understand when comparing the composition of the calcine with potential regulatory or waste acceptance criteria. This addendum report also provides detailed explanations for the large variability in the calcine composition among the CSSFs. The calcine composition varies as a result of reprocessing different types of fuel that had different cladding materials. Different chemicals were used to dissolve the various types of fuel, extract the uranium, and calcine the resulting waste. This resulted in calcine with variable compositions. This addendum report also identifies a few trace chemicals and radionuclides for which the accuracy of the amounts estimated to be in the calcine could be improved by making adjustments to the assumptions and methods used in making the estimates.

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

    Office of Energy Efficiency and Renewable Energy (EERE)

    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...

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

    Office of Energy Efficiency and Renewable Energy (EERE)

    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...

  16. Nuclear Nonproliferation Programs | ORNL

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

    Initiatives Nonproliferation Technology Nonproliferation Systems Safeguards and Security Technology International Safeguards Nuclear Material Detection and Characterization For...

  17. 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.

  18. 5. Wick, O. J. (ed.) Plutonium Handbook: a Guide to the Technology 3357 (American Nuclear Society, LaGrange Park, IL, 1980).

    E-Print Network [OSTI]

    5. Wick, O. J. (ed.) Plutonium Handbook: a Guide to the Technology 33­57 (American Nuclear Society superconductors. Phys. Rev. Lett. 8, 250­253 (1962). 11. Wolfer, W. G. Radiation effects in plutonium. Los Alamos

  19. Nuclear Energy Governance and the Politics of Social Justice: Technology, Public Goods, and Redistribution in Russia and France

    E-Print Network [OSTI]

    Grigoriadis, Theocharis N

    2009-01-01

    2005. Cowan Robin. "Nuclear Power Reactors: A Study inThe Last Chance for Nuclear Power?" Energy Studies Reviewa National Infrastructure for Nuclear Power", IAEA Nuclear

  20. Nuclear Energy Governance and the Politics of Social Justice: Technology, Public Goods, and Redistribution in Russia and France

    E-Print Network [OSTI]

    Grigoriadis, Theocharis N

    2009-01-01

    2005. Cowan Robin. "Nuclear Power Reactors: A Study inThe Last Chance for Nuclear Power?" Energy Studies ReviewInfrastructure for Nuclear Power", IAEA Nuclear Energy

  1. 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 ?m 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 ?m for DOP oil and 0.549 ?m 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 ?m to 3.0 ?m, 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.

  2. Distribution of small dispersive coal dust particles and absorbed radioactive chemical elements in conditions of forced acoustic resonance in iodine air filter at nuclear power plant

    E-Print Network [OSTI]

    Ledenyov, Oleg P

    2013-01-01

    The physical features of distribution of the small dispersive coal dust particles and the adsorbed radioactive chemical elements and their isotopes in the absorber with the granular filtering medium with the cylindrical coal granules were researched in the case of the intensive air dust aerosol stream flow through the iodine air filter (IAF). It was shown that, at the certain aerodynamic conditions in the IAF, the generation of the acoustic oscillations is possible. It was found that the acoustic oscillations generation results in an appearance of the standing acoustic waves of the air pressure (density) in the IAF. In the case of the intensive blow of the air dust aerosol, it was demonstrated that the standing acoustic waves have some strong influences on both: 1) the dynamics of small dispersive coal dust particles movement and their accumulation in the IAF; 2) the oversaturation of the cylindrical coal granules by the adsorbed radioactive chemical elements and their isotopes in the regions, where the antin...

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

    SciTech Connect (OSTI)

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

    2014-05-04

    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.

  4. An improved visualization of diesel particulate filter/

    E-Print Network [OSTI]

    Boehm, Kevin (Kevin W.)

    2011-01-01

    The prevalence of diesel particulate filters (DPF) is increasing as emissions standards worldwide evolve to match current technologies. Since the first application of DPFs in the 1980's, PM trapping effectiveness has ...

  5. 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.

  6. Predicting Thermal Stress in Diesel Particulate Filters | Department...

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

    More Documents & Publications Diesel Emission Control Review Substrate Studies of an Electrically-Assisted Diesel Particulate Filter Neutron Imaging of Advanced Engine Technologies...

  7. Working Group Report on - Space Nuclear Power Systems and Nuclear...

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

    Working Group Report on - Space Nuclear Power Systems and Nuclear Waste Technology R&D Working Group Report on - Space Nuclear Power Systems and Nuclear Waste Technology R&D "Even...

  8. Positioning Nuclear Spins in Interacting Clusters for Quantum Technologies and Bio-imaging

    E-Print Network [OSTI]

    Zhen-Yu Wang; Jan F. Haase; Jorge Casanova; Martin B. Plenio

    2015-10-09

    We propose a method to measure the hyperfine vectors between a nitrogen-vacancy (NV) center and an environment of interacting nuclear spins. Our protocol enables the generation of tunable electron-nuclear coupling Hamiltonians while suppressing unwanted inter-nuclear interactions. In this manner, each nucleus can be addressed and controlled individually thereby permitting the reconstruction of the individual hyperfine vectors. With this ability the 3D-structure of spin ensembles and spins in bio-molecules can be identified without the necessity of varying the direction of applied magnetic fields. We demonstrate examples including the complete identification of an interacting spin cluster in diamond and 3D imaging of all the nuclear spins in a bio-molecule of L-malic acid.

  9. Alkali metal Rankine cycle boiler technology challenges and some potential solutions for space nuclear power and propulsion applications

    SciTech Connect (OSTI)

    Stone, J.R.

    1994-07-01

    Alkali metal boilers are of interest for application to future space Rankine cycle power conversion systems. Significant progress on such boilers was accomplished in the 1960's and early 1970's, but development was not continued to operational systems since NASA's plans for future space missions were drastically curtailed in the early 1970's. In particular, piloted Mars missions were indefinitely deferred. With the announcement of the Space Exploration Initiative (SEI) in July 1989 by President Bush, interest was rekindled in challenging space missions and, consequently in space nuclear power and propulsion. Nuclear electric propulsion (NEP) and nuclear thermal propulsion (NTP) were proposed for interplanetary space vehicles, particularly for Mars missions. The potassium Rankine power conversion cycle became of interest to provide electric power for NEP vehicles and for 'dual-mode' NTP vehicles, where the same reactor could be used directly for propulsion and (with an additional coolant loop) for power. Although the boiler is not a major contributor to system mass, it is of critical importance because of its interaction with the rest of the power conversion system; it can cause problems for other components such as excess liquid droplets entering the turbine, thereby reducing its life, or more critically, it can drive instabilities-some severe enough to cause system failure. Funding for the SEI and its associated technology program from 1990 to 1993 was not sufficient to support significant new work on Rankine cycle boilers for space applications. In Fiscal Year 1994, funding for these challenging missions and technologies has again been curtailed, and planning for the future is very uncertain. The purpose of this paper is to review the technologies developed in the 1960's and 1970's in the light of the recent SEI applications. In this way, future Rankine cycle boiler programs may be conducted most efficiently.

  10. 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.

  11. Design and Transient Analysis of Passive Safety Cooling Systems for Advanced Nuclear Reactors

    E-Print Network [OSTI]

    Galvez, Cristhian

    2011-01-01

    heat transfer. Nuclear Technology 163 (2008) 344- [18] V.and Electricity . Nuclear Technology 144 [5] D. F. Williams,Vessel Technology . Nuclear Technology, 78 (1987) 245- [5

  12. Nuclear Energy Governance and the Politics of Social Justice: Technology, Public Goods, and Redistribution in Russia and France

    E-Print Network [OSTI]

    Grigoriadis, Theocharis N

    2009-01-01

    force. 14 Opponents of nuclear energy expansion contend thatfar prevented the expansion of nuclear-intensive electricitysecurity through the expansion of nuclear infrastructure for

  13. Nuclear Energy Governance and the Politics of Social Justice: Technology, Public Goods, and Redistribution in Russia and France

    E-Print Network [OSTI]

    Grigoriadis, Theocharis N

    2009-01-01

    efficiency and direct state control in nuclear energyEfficiency of hydrogen production systems using alternative nuclear energyEfficiency of hydrogen production systems using alternative nuclear energy

  14. Nuclear Energy Governance and the Politics of Social Justice: Technology, Public Goods, and Redistribution in Russia and France

    E-Print Network [OSTI]

    Grigoriadis, Theocharis N

    2009-01-01

    then I compare the politics of nuclear policy in Russia andpaper, I discussed the politics of nuclear energy regulationNuclear Energy Regulation and the Politics of Social

  15. Nuclear Energy Governance and the Politics of Social Justice: Technology, Public Goods, and Redistribution in Russia and France

    E-Print Network [OSTI]

    Grigoriadis, Theocharis N

    2009-01-01

    for global nuclear security, given my aforementionedthe national security dimensions of nuclear energy see forecological and security risks associated with nuclear energy

  16. Nuclear Energy Governance and the Politics of Social Justice: Technology, Public Goods, and Redistribution in Russia and France

    E-Print Network [OSTI]

    Grigoriadis, Theocharis N

    2009-01-01

    science and 4. Nuclear and radiation safety. 10 Thisof the nuclear fuel cycle as well as safety measures drivewhy safety has been the central priority of French nuclear

  17. It is a unique programme of its kind not only in this country but also in the whole of South East Asian region. Besides offering M.Tech and Ph.D degrees in the area of Nuclear Engineering & Technology, the programme provides research and development exper

    E-Print Network [OSTI]

    Srivastava, Kumar Vaibhav

    Asian region. Besides offering M.Tech and Ph.D degrees in the area of Nuclear Engineering & TechnologyDepartmentofAtomicEnergy. Contact Head Nuclear Engineering & Technology Programme Indian Institute of Technology Kanpur Kanpur - 208.iitk.ac.in/net/ Nuclear Engineering & Technology Programme IITK Indian Institute of Technology Kanpur 3D Tomographic

  18. 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.

  19. 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.

  20. 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.

  1. Recirculating electric air filter

    DOE Patents [OSTI]

    Bergman, Werner (Pleasanton, CA)

    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.

  2. Filtering Noisy ECG Signals Using the Extended Kalman Filter Based on a Modified Dynamic ECG Model

    E-Print Network [OSTI]

    Paris-Sud XI, Université de

    of biomedical signal processing. Specifically, the extraction of ECG signals from low SNR measurementsFiltering Noisy ECG Signals Using the Extended Kalman Filter Based on a Modified Dynamic ECG Model University of Technology, Tehran, Iran 2 Images and Signals Laboratory, Institut National Polytechnique de

  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. Nuclear Energy Governance and the Politics of Social Justice: Technology, Public Goods, and Redistribution in Russia and France

    E-Print Network [OSTI]

    Grigoriadis, Theocharis N

    2009-01-01

    Nuclear Power", IAEA Nuclear Energy Series, No. NG-G-3.1.Essentials, March 2007. OECD/Nuclear Energy Agency. "Nuclear Energy and the Kyoto Protocol" OECD/IEA Report OECD/

  5. Climate Change, Nuclear Power and Nuclear

    E-Print Network [OSTI]

    Climate Change, Nuclear Power and Nuclear Proliferation: Magnitude Matters Rob Goldston MIT IAP biomass wind hydro coal CCS coal nat gas CCS nat gas nuclear Gen IV nuclear Gen III nuclear Gen II 5-1 Electricity Generation: CCS and Nuclear Power Technology Options Available Global Electricity Generation WRE

  6. Technolog

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

    focuses on multi-scale, multiphysics approaches to understanding natural systems, "engineering the earth" with sensing and drilling technologies and characterizing geomaterials...

  7. 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.

  8. 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.

  9. Nuclear Energy Governance and the Politics of Social Justice: Technology, Public Goods, and Redistribution in Russia and France

    E-Print Network [OSTI]

    Grigoriadis, Theocharis N

    2009-01-01

    Frank N. "Plutonium and Reprocessing of Spent Nuclear Fuel",Frank N. "Plutonium and Reprocessing of Spent Nuclear Fuel",

  10. Nuclear Energy Governance and the Politics of Social Justice: Technology, Public Goods, and Redistribution in Russia and France

    E-Print Network [OSTI]

    Grigoriadis, Theocharis N

    2009-01-01

    Plutonium and Reprocessing of Spent Nuclear Fuel", Science,Plutonium and Reprocessing of Spent Nuclear Fuel", Science,

  11. Nuclear Sciences | More Science | ORNL

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

    Sciences SHARE Nuclear Sciences In World War II's Manhattan Project, ORNL helped usher in the nuclear age. Today, laboratory scientists are leaders in using nuclear technologies...

  12. Nuclear Science | More Science | ORNL

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

    Science SHARE Nuclear Science In World War II's Manhattan Project, ORNL helped usher in the nuclear age. Today, laboratory scientists are leaders in using nuclear technologies and...

  13. 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.

  14. Passive and inherent safety technologies for light-water nuclear reactors

    SciTech Connect (OSTI)

    Forsberg, C.W.

    1990-07-01

    Passive/inherent safety implies a technical revolution in our approach to nuclear power safety. This direction is discussed herein for light-water reactors (LWRs) -- the predominant type of power reactor used in the world today. At Oak Ridge National Laboratory (ORNL) the approach to the development of passive/inherent safety for LWRs consists of four steps: identify and quantify safety requirements and goals; identify and quantify the technical functional requirements needed for safety; identify, invent, develop, and quantify technical options that meet both of the above requirements; and integrate safety systems into designs of economic and reliable nuclear power plants. Significant progress has been achieved in the first three steps of this program. The last step involves primarily the reactor vendors. These activities, as well as related activities worldwide, are described here. 27 refs., 7 tabs.

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

    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 ENTOMB (entombment). The study results are presented in two volumes. Volume 1 (Main Report) contains the results in summary form.

  16. Recapturing Graphite-Based Fuel Element Technology for Nuclear Thermal Propulsion

    SciTech Connect (OSTI)

    Trammell, Michael P [ORNL; Jolly, Brian C [ORNL; Miller, James Henry [ORNL; Qualls, A L [ORNL; Harrison, Thomas J [ORNL

    2013-01-01

    ORNL is currently recapturing graphite based fuel forms for Nuclear Thermal Propulsion (NTP). This effort involves research and development on materials selection, extrusion, and coating processes to produce fuel elements representative of historical ROVER and NERVA fuel. Initially, lab scale specimens were fabricated using surrogate oxides to develop processing parameters that could be applied to full length NTP fuel elements. Progress toward understanding the effect of these processing parameters on surrogate fuel microstructure is presented.

  17. Arsenic Removal Using AgedArsenic Removal Using Aged Rapid Sand Filter MediaRapid Sand Filter Media

    E-Print Network [OSTI]

    Arsenic Removal Using AgedArsenic Removal Using Aged Rapid Sand Filter MediaRapid Sand Filter Media byby C. Menard, D. Burt, M.R. CollinsC. Menard, D. Burt, M.R. Collins Water Treatment Technology Assistance CenterWater Treatment Technology Assistance Center Department of Civil Engineering

  18. 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.

  19. Rigid porous filter

    DOE Patents [OSTI]

    Chiang, Ta-Kuan (Morgantown, WV); Straub, Douglas L. (Morgantown, WV); Dennis, Richard A. (Morgantown, WV)

    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. 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.

  1. Fusion Nuclear Science and Technology (FNST) Strategic Issues, challenges, and Facilities

    E-Print Network [OSTI]

    California at Los Angeles, University of

    ) Director, Fusion Science and Technology Center (UCLA) Founding President, Council of Energy Research and Education Leaders, CEREL (USA) With input from the FNST Community Related publications can be found at www-vessel Components Plasma Facing Components divertor, limiter, heating/fueling and final optics, etc. Blanket

  2. 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].

  3. Nondestructive Spent Fuel Assay Using Nuclear Resonance Fluorescence

    E-Print Network [OSTI]

    Quiter, Brian

    2010-01-01

    Library for Nuclear Science and Technology," Nuclear Datanuclear structure studies. More recently, NRF has been identified as a promising technology

  4. 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.

  5. Citizens for Nuclear Technology Awareness (CNTA) will hold their 23rd Annual

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity ofkandz-cm11 OutreachProductswsicloudwsiclouddenDVA N C E D BGene NetworkNuclearDNP 2008 1Browse by Topic5,4Citizens for

  6. 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.

  7. Nuclear Energy Governance and the Politics of Social Justice: Technology, Public Goods, and Redistribution in Russia and France

    E-Print Network [OSTI]

    Grigoriadis, Theocharis N

    2009-01-01

    does not prevent the proliferation of nuclear weapons andNuclear Policy in the 21 st Century Environment", ProliferationNuclear Policy in the 21 st Century Environment", Proliferation

  8. Nuclear Energy Governance and the Politics of Social Justice: Technology, Public Goods, and Redistribution in Russia and France

    E-Print Network [OSTI]

    Grigoriadis, Theocharis N

    2009-01-01

    Energy Agency. "Nuclear Energy and the Kyoto Protocol" OECD/Energy Agency. "Nuclear Energy and the Kyoto Protocol" OECD/et al. "Perception of Nuclear Energy and Coal in France and

  9. Technologies

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity ofkandz-cm11 Outreach Home RoomPreservationBio-Inspired Solar Fuel ProductionRecoverable15/2008Technologies Technologies

  10. Technology

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity ofkandz-cm11 Outreach Home RoomPreservationBio-Inspired Solar FuelTechnology /newsroom/_assets/images/s-icon.png Technology

  11. Filter service system

    DOE Patents [OSTI]

    Sellers, Cheryl L. (Peoria, IL); Nordyke, Daniel S. (Arlington Heights, IL); Crandell, Richard A. (Morton, IL); Tomlins, Gregory (Peoria, IL); Fei, Dong (Peoria, IL); Panov, Alexander (Dunlap, IL); Lane, William H. (Chillicothe, IL); Habeger, Craig F. (Chillicothe, IL)

    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.

  12. Nuclear Energy Governance and the Politics of Social Justice: Technology, Public Goods, and Redistribution in Russia and France

    E-Print Network [OSTI]

    Grigoriadis, Theocharis N

    2009-01-01

    France, the key nuclear policy actors are the Commission on Nuclear Energy,energy regulation in France is not a single-dimensional public policy

  13. A Joint Interview with Professor Joonhong Ahn and Professor Cathryn Carson on Nuclear Waste Management: a Technical and Social Problem

    E-Print Network [OSTI]

    Chowdhary, Harshika; Gill, Manraj; Kim, Juwon; McGuinness, Philippa; Miller, Daniel; Nuckolls, Kevin

    2015-01-01

    is applicable for the nuclear reactor. But for waste issues,How is waste from nuclear reactors typically created andusing this filter in nuclear reactors? JA: The Archimedes

  14. 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.

  15. Accelerator-driven transmutation technologies for resolution of long-term nuclear waste concerns

    SciTech Connect (OSTI)

    Bowman, C.D.

    1996-10-01

    The paper provides a rationale for resolution of the long-term waste disposition issue based on complete destruction of fissile material and all higher actinides. It begins with a brief history of geologic storage leading to the present impasse in the US. The proliferation aspects of commercial plutonium are presented in a new light as a further driver for complete destruction. The special problems in Russia and the US of the disposition of the highly enriched spent naval reactor fuel and spent research reactor fuel are also presented. The scale of the system required for complete destruction is also examined and it is shown that a practical system for complete destruction of commercial and defense fissile material must be widely dispersed rather than concentrated at a single site. Central tenants of the US National Academy of Sciences recommendations on waste disposition are examined critically and several technologies considered for waste destruction are described briefly and compared Recommendations for waste disposition based on Accelerator-Driven Transmutation Technology suitable for both the US and Russia are presented.

  16. Nuclear Energy Governance and the Politics of Social Justice: Technology, Public Goods, and Redistribution in Russia and France

    E-Print Network [OSTI]

    Grigoriadis, Theocharis N

    2009-01-01

    costs required for the construction of nuclear infrastructure 3. The development of renewable energy

  17. Evaluation of the complementary use of the ceramic (Kosim) filter and Aquatabs in Northern Region, Ghana

    E-Print Network [OSTI]

    Swanton, Andrew A

    2008-01-01

    The Kosim filter is a ceramic water filter that is currently used in Northern Ghana. Based on prior MIT research in Northern Ghana, this technology is effective at removing 92% of turbidity, 99.4% of total coliforms, and ...

  18. NUCLEAR ISOTOPIC DILUTION OF HIGHLY ENRICHED URANIUM BY DRY BLENDING VIA THE RM-2 MILL TECHNOLOGY

    SciTech Connect (OSTI)

    Raj K. Rajamani; Sanjeeva Latchireddi; Vikas Devrani; Harappan Sethi; Roger Henry; Nate Chipman

    2003-08-01

    DOE has initiated numerous activities to focus on identifying material management strategies to disposition various excess fissile materials. In particular the INEEL has stored 1,700 Kg of offspec HEU at INTEC in CPP-651 vault facility. Currently, the proposed strategies for dispositioning are (a) aqueous dissolution and down blending to LEU via facilities at SRS followed by shipment of the liquid LEU to NFS for fabrication into LWR fuel for the TVA reactors and (b) dilution of the HEU to 0.9% for discard as a waste stream that would no longer have a criticality or proliferation risk without being processed through some type of enrichment system. Dispositioning this inventory as a waste stream via aqueous processing at SRS has been determined to be too costly. Thus, dry blending is the only proposed disposal process for the uranium oxide materials in the CPP-651 vault. Isotopic dilution of HEU to typically less than 20% by dry blending is the key to solving the dispositioning issue (i.e., proliferation) posed by HEU stored at INEEL. RM-2 mill is a technology developed and successfully tested for producing ultra-fine particles by dry grinding. Grinding action in RM-2 mill produces a two million-fold increase in the number of particles being blended in a centrifugal field. In a previous study, the concept of achieving complete and adequate blending and mixing (i.e., no methods were identified to easily separate and concentrate one titanium compound from the other) in remarkably short processing times was successfully tested with surrogate materials (titanium dioxide and titanium mono-oxide) with different particle sizes, hardness and densities. In the current project, the RM-2 milling technology was thoroughly tested with mixtures of natural uranium oxide (NU) and depleted uranium oxide (DU) stock to prove its performance. The effects of mill operating and design variables on the blending of NU/DU oxides were evaluated. First, NU and DU both made of the same oxide, UO{sub 3}, was used in the testing. Next, NU made up of UO{sub 3} and DU made up of UO{sub 2} was used in the test work. In every test, the blend achieved was characterized by spatial sampling of the ground product and analyzing for {sup 235}U concentration. The test work proved that these uranium oxide materials can be blended successfully. The spatial concentration was found to be uniform. Next, sintered thorium oxide pellets were used as surrogate for light water breeder reactor pellets (LWBR). To simulate LWBR pellet dispositioning, the thorium oxide pellets were first ground to a powder form and then the powder was blended with NU. In these tests also the concentration of {sup 235}U and {sup 232}Th in blended products fell within established limits proving the success of RM-2 milling technology. RM-2 milling technology is applicable to any dry radioactive waste, especially brittle solids that can be ground up and mixed with the non-radioactive stock.

  19. An evolution of technologies and applications of gamma imagers in the nuclear cycle industry

    SciTech Connect (OSTI)

    Khalil, R. A. [AREVA/CANBERRA - Nuclear Measurements Business Unit (France); Carrel, F. [CEA, LIST, F-91191 Gif-sur-Yvette (France); Menaa, N.; De Toro, D. [AREVA/CANBERRA - Nuclear Measurements Business Unit (France); Schoepff, V.; Gmar, M. [CEA, LIST, F-91191 Gif-sur-Yvette (France); Varet, T. [AREVA/Nuclear Site Value Development Business Unit (France); Toubon, H. [AREVA/CANBERRA - Nuclear Measurements Business Unit (France)

    2011-07-01

    The tracking of radiation contamination and distribution has become a high priority in the nuclear cycle industry in order to respect the ALARA principle which is a main challenge during decontamination and dismantling activities. To support this need, AREVA/CANBERRA and CEA LIST have been actively carrying out research and development on a gamma-radiation imager. In this paper we will present the new generation of gamma camera, called GAMPIX. This system is based on the Timepix chip, hybridized with a CdTe substrate. A coded mask could be used in order to increase the sensitivity of the camera. Moreover, due to the USB connection with a standard computer, this gamma camera is immediately operational and user-friendly. The final system is a very compact gamma camera (global weight is less than 1 kg without any shielding) which could be used as a hand-held device for radioprotection purposes. In this article, we present the main characteristics of this new generation of gamma camera and we expose experimental results obtained during in situ measurements. Even though we present preliminary results the final product is under industrialization phase to address various applications specifications. (authors)

  20. Pyroprocessing Technologies

    E-Print Network [OSTI]

    Kemner, Ken

    of pyrochemical processes for the recycle of oxide, carbide and other advanced fuels and laid the foundationPyroprocessing Technologies RECYCLING USED NUCLEAR FUEL FOR A SUSTAINABLE ENERGY FUTURE #12;32 Storing Used Nuclear Fuel is a Real Waste Nuclear power is the most environmentally friendly way

  1. Long-Term Planning for Nuclear Energy Systems Under Deep Uncertainty

    E-Print Network [OSTI]

    Kim, Lance Kyungwoo

    2011-01-01

    a Geologic Repository. Nuclear Technology, 154:95–106, Mayfor the promise of nuclear technology inspired my ownof the ever-changing nuclear technology landscape. Making

  2. Environmental Challenges of Climate-Nuclear Fusion: A Case Study of India

    E-Print Network [OSTI]

    Badrinarayan, Deepa

    2011-01-01

    149 B. Transferring Nuclear Technology to India Sets thepromotion of advanced nuclear technology in the Bali ActionB. Transferring Nuclear Technology to India Sets the Stage

  3. Spin-On for the Renaissance? The Current State of China's Nuclear Industry

    E-Print Network [OSTI]

    Yuan, Jing-dong

    2010-01-01

    and oversee and review nuclear technology trans- fers andwith China’s State Nuclear Power Technology Corpora- tion,China’s own technologies in developing nuclear power proj-

  4. 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.

  5. Technologies

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantityBonneville Power AdministrationRobust,Field-effectWorking With U.S. CoalMexico IndependentMatter and Technologies R&D

  6. Isotope Development & Production | Nuclear Science | ORNL

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

    Separation & Processing Strategic Isotope Production Super Heavy Element Discovery Nuclear Security Science & Technology Nuclear Systems Modeling, Simulation & Validation...

  7. The high-density Z-pinch as a pulsed fusion neutron source for fusion nuclear technology and materials testing

    SciTech Connect (OSTI)

    Krakowski, R.A.; Sethian, J.D.; Hagenson, R.L.

    1989-01-01

    The dense Z-pinch (DZP) is one of the earliest and simplest plasma heating and confinement schemes. Recent experimental advances based on plasma initiation from hair-like (10s ..mu..m in radius) solid hydrogen filaments have so far not encountered the usually devastating MHD instabilities that plagued early DZP experiments. These encouraging results along with debt of a number of proof-of principle, high-current (1--2 MA in 10--100 ns) experiments have prompted consideration of the DZP as a pulsed source of DT fusion neutrons of sufficient strength (/dot S//sub N/ greater than or equal to 10/sup 19/ n/s) to provide uncollided neutron fluxes in excess of I/sub ..omega../ = 5--10 MW/m/sup 2/ over test volumes of 10--30 litre or greater. While this neutron source would be pulsed (100s ns pulse widths, 10--100 Hz pulse rate), giving flux time compressions in the range 10/sup 5/--10/sup 6/, its simplicity, near-time feasibility, low cost, high-Q operation, and relevance to fusion systems that may provide a pulsed commercial end-product (e.g., inertial confinement or the DZP itself) together create the impetus for preliminary considerations as a neutron source for fusion nuclear technology and materials testings. The results of a preliminary parametric systems study (focusing primarily on physics issues), conceptual design, and cost versus performance analyses are presented. The DZP promises an expensive and efficient means to provide pulsed DT neutrons at an average rate in excess of 10/sup 19/ n/s, with neutron currents I/sub ..omega../ /approx lt/ 10 MW/m/sup 2/ over volumes V/sub exp/ greater than or equal to 30 litre using single-pulse technologies that differ little from those being used in present-day experiments. 34 refs., 17 figs., 6 tabs.

  8. 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. [NNSA; Clark, Harvey W. [NSTec; Essex, James J. [NSTec; Wagner, Eric C. [NSTec

    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.

  9. 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.

  10. Moving granular-bed filter development program. Topical report

    SciTech Connect (OSTI)

    Newby, R.A.; Yang, W.C.; Smeltzer, E.E.; Lippert, T.E.

    1994-04-01

    Advanced, coal-based, power plants, such as IGCC and Advanced-PFBC, are currently nearing commercial demonstration. These power plant technologies require hot gas filtration as part of their gas cleaning trains. Ceramic barrier filters are the major filter candidates being developed for these hot gas cleaning applications. While ceramic barrier filters achieve high levels of particle removal, concerns exist for their reliability and operability in these applications. An alternative hot gas filtration technology is the moving granular bed filter. An advanced, moving granular bed filter has been conceived, and early development activities performed by the Westinghouse Electric Corporation, Science and Technology Center. This document reports on the Base Contract tasks performed to resolve the barrier technical issues for this technology. The concept, the Standleg Moving Granular Bed Filter (SMGBF) has a concurrent downward, gas and bed media flow configuration that results in simplified features and improved scaleup feasibility compared to alternative designs. Two modes of bed media operation were assessed in the program: once-through using pelletized power plant waste as bed media, and recycle of bed media via standleg and pneumatic transport techniques. Cold Model testing; high-temperature, high-pressure testing; and pelletization testing using advanced power plant wastes, have been conducted in the program. A commercial, economic assessment of the SMGBF technology was performed for IGCC and Advanced-PFBC applications. The evaluation shows that the barrier technical issues can be resolved, and that the technology is potentially competitive with ceramic barrier filters.

  11. 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.

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

    DOE Patents [OSTI]

    Lippert, Thomas Edwin (Murrysville, PA); Alvin, Mary Anne (Pittsburgh, PA); Bruck, Gerald Joseph (Murrysville, PA); Smeltzer, Eugene E. (Export, PA)

    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.

  13. National Nuclear Science Week 2014 - SRSCRO

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

    local organizations to conduct activities designed to encourage and bring awareness of nuclear technology and the many careers available within nuclear technology and other...

  14. Nuclear Energy Governance and the Politics of Social Justice: Technology, Public Goods, and Redistribution in Russia and France

    E-Print Network [OSTI]

    Grigoriadis, Theocharis N

    2009-01-01

    power generation and nonproliferation purposes, state responsibility may be the only sufficient regulatory clause to confine nuclear waste disposal risks

  15. Making the World Safe for Nuclear Energy 65 John Deutch, Institute Professor at the Massachusetts Institute of Technology, served as

    E-Print Network [OSTI]

    Deutch, John

    -Qaeda considers obtaining nuclear weapons to be a religious duty, presenting a risk of catastrophic terrorismDeutch,ArnoldKanter,ErnestMonizandDanielPoneman Interestin building nuclear power stationsis stirring At the same time, the world may be on the verge of a new phase of widespread deployment of nuclear power. The rapidly growing global demand for electricity

  16. 259NUCLEAR ENGINEERING AND TECHNOLOGY, VOL.38 NO.3 APRIL 2006 NuSEE: AN INTEGRATED ENVIRONMENT OF SOFTWARE

    E-Print Network [OSTI]

    . In safety-critical systems such as a Nuclear Power Plant (NPP), extremely high- confidence for software and analysis have become increasingly important in nuclear power plant (NPP) safety-critical systems. KEYWORDS : V&V, Software Specification, Safety-Critical System, Tool #12;260 NUCLEAR ENGINEERING

  17. ORNL/TM-2009/021 Effect of Intake Air Filter Condition on

    E-Print Network [OSTI]

    Pennycook, Steve

    contractors, Energy Technology Data Exchange (ETDE) representatives, and International Nuclear Information

  18. A Belief Function Theory Method for Prognostics in Clogging Filters

    E-Print Network [OSTI]

    Boyer, Edmond

    the heat exchangers of a nuclear reactor condenser. The prognostic approach is developed considering available few sequences of clogging-related observation collected on similar filters. The real industrial nuclear power plant to clean the sea water pumped through the condenser. Several data-driven methods have

  19. Examining 239Pu and 240Pu Nuclear Resonance Fluorescence Measurements on Spent Fuel for Nuclear Safeguards

    E-Print Network [OSTI]

    Quiter, Brian

    2013-01-01

    10- 01096) Journal of Nuclear Technology, p. 150, Vol. 175,linac and laser technologies for nuclear photonics gamma-rayNuclear resonance fluorescence (NRF) has been identified as a technology

  20. Sub-micron filter

    DOE Patents [OSTI]

    Tepper, Frederick (Sanford, FL); Kaledin, Leonid (Port Orange, FL)

    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.

  1. 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.

  2. Facilities & Capabilities | Nuclear Science | ORNL

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

    R&D in radioisotopes and stable isotopes; radioisotope production; radiochemistry; global nuclear security technologies; fusion energy science; nuclear criticality safety; and all...

  3. Nuclear Energy Governance and the Politics of Social Justice: Technology, Public Goods, and Redistribution in Russia and France

    E-Print Network [OSTI]

    Grigoriadis, Theocharis N

    2009-01-01

    energy regulation in France is not a single-dimensional public policy space;space, where corporate organization meets public oversight. The nuclear energy

  4. Nuclear Energy Governance and the Politics of Social Justice: Technology, Public Goods, and Redistribution in Russia and France

    E-Print Network [OSTI]

    Grigoriadis, Theocharis N

    2009-01-01

    an export partnership between RAO UESR, Russia’s electricityRussia’s nuclear intensity is due to drastic increase of uranium exports

  5. Ceramic fiber reinforced filter

    DOE Patents [OSTI]

    Stinton, David P. (Knoxville, TN); McLaughlin, Jerry C. (Oak Ridge, TN); Lowden, Richard A. (Powell, TN)

    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.

  6. Filter design for hybrid spin gates

    E-Print Network [OSTI]

    Andreas Albrecht; Martin B. Plenio

    2015-04-14

    The impact of control sequences on the environmental coupling of a quantum system can be described in terms of a filter. Here we analyze how the coherent evolution of two interacting spins subject to periodic control pulses, at the example of a nitrogen vacancy center coupled to a nuclear spin, can be described in the filter framework in both the weak and the strong coupling limit. A universal functional dependence around the filter resonances then allows for tuning the coupling type and strength. Originally limited to small rotation angles, we show how the validity range of the filter description can be extended to the long time limit by time-sliced evolution sequences. Based on that insight, the construction of tunable, noise decoupled, conditional gates composed of alternating pulse sequences is proposed. In particular such an approach can lead to a significant improvement in fidelity as compared to a strictly periodic control sequence. Moreover we analyze the decoherence impact, the relation to the filter for classical noise known from dynamical decoupling sequences, and we outline how an alternating sequence can improve spin sensing protocols.

  7. Remotely serviced filter and housing

    DOE Patents [OSTI]

    Ross, Maurice J. (Pocatello, ID); Zaladonis, Larry A. (Idaho Falls, ID)

    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.

  8. Performance Evaluation of Axial Flow AG-1 FC and Prototype FM (High Strength) HEPA Filters - 13123

    SciTech Connect (OSTI)

    Giffin, Paxton K.; Parsons, Michael S.; Wilson, John A.; Waggoner, Charles A. [Institute for Clean Energy Technology, Mississippi State University, 205 Research Blvd Starkville, MS 39759 (United States)] [Institute for Clean Energy Technology, Mississippi State University, 205 Research Blvd Starkville, MS 39759 (United States)

    2013-07-01

    High efficiency particulate air (HEPA) filters are routinely used in DOE nuclear containment activities. The Nuclear Air Cleaning Handbook (NACH) stipulates that air cleaning devices and equipment used in DOE nuclear applications must meet the American Society of Mechanical Engineers (ASME) Code on Nuclear Air and Gas Treatment (AG-1) standard. This testing activity evaluates two different axial flow HEPA filters, those from AG-1 Sections FC and FM. Section FM is under development and has not yet been added to AG-1 due to a lack of qualification data available for these filters. Section FC filters are axial flow units that utilize a fibrous glass filtering medium. The section FM filters utilize a similar fibrous glass medium, but also have scrim backing. The scrim-backed filters have demonstrated the ability to endure pressure impulses capable of completely destroying FC filters. The testing activities presented herein will examine the total lifetime loading for both FC and FM filters under ambient conditions and at elevated conditions of temperature and relative humidity. Results will include loading curves, penetration curves, and testing condition parameters. These testing activities have been developed through collaborations with representatives from the National Nuclear Security Administration (NNSA), DOE Office of Environmental Management (DOE-EM), New Mexico State University, and Mississippi State University. (authors)

  9. 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.

  10. Differential Filtering and Detexturing 

    E-Print Network [OSTI]

    He, Lei

    2014-08-18

    introduce how to use bilateral filter appropriately on image texture removal by modifying its range image. While current existing methods either fail to remove the textures completely or over blur main structures, our method delivers best-in-class image...

  11. Contactor/filter improvements

    DOE Patents [OSTI]

    Stelman, David (West Hills, CA)

    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.

  12. Single-periodic-film optical bandpass filter

    E-Print Network [OSTI]

    Niraula, Manoj; Magnusson, Robert

    2015-01-01

    Resonant periodic surfaces and films enable new functionalities with wide applicability in practical optical systems. Their material sparsity, ease of fabrication, and minimal interface count provide environmental and thermal stability and robustness in applications. Here we report an experimental bandpass filter fashioned in a single patterned layer on a substrate. Its performance corresponds to bandpass filters requiring perhaps 30 traditional thin-film layers as shown by an example. We demonstrate an ultra-narrow, high-efficiency bandpass filter with extremely wide, flat, and low sidebands. This class of devices is designed with rigorous solutions of the Maxwell equations while engaging the physical principles of resonant waveguide gratings. The proposed technology is integration-friendly and opens doors for further development in various disciplines and spectral regions where thin-film solutions are traditionally applied.

  13. 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.

  14. Reconversion of nuclear weapons

    E-Print Network [OSTI]

    Kapitza, Sergei P

    1993-01-01

    The nuclear predicament or nuclear option. Synopsis of three lectures : 1- The physical basis of nuclear technology. Physics of fission. Chain reaction in reactors and weapons. Fission fragments. Separration of isotopes. Radiochemistry.2- Nuclear reactors with slow and fast neutrons. Power, size, fuel and waste. Plutonium production. Dose rate, shielding and health hazard. The lessons of Chernobyl3- Nuclear weapons. Types, energy, blast and fallout. Fusion and hydrogen bombs. What to do with nuclear weapons when you cannot use them? Testing. Nonmilittary use. Can we get rid of the nuclear weapon? Nuclear proliferation. Is there a nuclear future?

  15. 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.

  16. Filters for cathodic arc plasmas

    DOE Patents [OSTI]

    Anders, Andre (Albany, CA); MacGill, Robert A. (Richmond, CA); Bilek, Marcela M. M. (Engadine, AU); Brown, Ian G. (Berkeley, CA)

    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.

  17. 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.

  18. Knowing a good HOG filter when you see it: Efficient selection of filters for detection

    E-Print Network [OSTI]

    Shakhnarovich, Greg

    . In that sense, it is a category- independent method for part selection. Of course, some information about Technological Institute at Chicago greg@ttic.edu 3 University of Massachusetts, Amherst smaji. The intuition is that good filters across categories exhibit common traits such as, low clutter and gradients

  19. The potential role of new technology for enhanced safety and performance of nuclear power plants through improved service maintenance

    E-Print Network [OSTI]

    Achorn, Ted Glen

    1991-01-01

    Refinements in the safety and performance of nuclear power plants must be made to maintain public confidence and ensure competitiveness with other power sources. The aircraft industry, US Navy, and other programs have ...

  20. Technology survey and performance scaling for the design of high power nuclear electric power and propulsion systems

    E-Print Network [OSTI]

    White, Daniel B., Jr

    2011-01-01

    High power nuclear electric propulsion systems have the capability to enable many next-generation space exploration applications. To date, use of electric primary propulsion in flight systems has been limited to low-power, ...

  1. Linear Filtering and Decimation & Expansion

    E-Print Network [OSTI]

    Fowler, Mark

    decimating Pre-filter w/ M-Band D-T LPF (i.e. a D-T anti-alias filter) /M-/M M Filter & Decimate ][nx ][^ nx (an "anti-image" filter) - /3-/3 n - /3-/3 n /L-/L L Expand & Filter ][nx - )(f X n L=3 Looks Just ][nx ][^ nx ][^ )( nx M -= i inhixnx ][][][^ -== i M inMhixnMxnx ][][][^][^ )( #12;6/6 Time

  2. Moving granular-bed filter development program topical report

    SciTech Connect (OSTI)

    Newby, R.A.; Dilmore, W.J.; Fellers, A.W.; Gasparovic, A.C.; Kittle, W.F.; Lippert, T.E.; Smeltzer, E.E.; Yang, W.C.

    1991-10-17

    The Westinghouse Science Technology Center has proposed a novel moving granular-bed filter concept, the Standleg Moving Granular-Bed Filter (S-MGBF) system, that overcomes the inherent deficiencies of the current state-of-the-art moving granular-bed filter technology. The S-MGBF system combines two unique features that make it highly effective for use in advanced coal-fueled power plants. First, the S-MGBF system applies pelletization technology to generate filter pellets from the power plant solid waste materials, and uses these pellets as a once-through'' filtering media to eliminate the need for costly, complex, and large filter media recycling equipment. This pelletizing step also generates a more environmentally acceptable solid waste product and provides the potential to incorporate gas-phase contaminant sorbents into the filtering media. Secondly, the S-MGBF system passes these pellets and the flyash laden power plant gas through a highly compact S-MGBF that uses cocurrent gas-pellet contacting in an arrangement that greatly simplifies and enhances the distribution of dirty gas to the moving bed and the disengagement of clean gas from the moving bed.

  3. POLICIES For CONTENT FILTERING In EDUCATIONAL NETWORKS: The CASE Of GREECE

    E-Print Network [OSTI]

    POLICIES For CONTENT FILTERING In EDUCATIONAL NETWORKS: The CASE Of GREECE Maria Avgoulea, Patras, GREECE Christos Bouras Department of Computer Engineering and Informatics, University of Patras & Computer Technology Institute, Patras, GREECE Email: bouras@cti.gr Michael Paraskevas Computer Technology

  4. 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.

  5. 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. (ed.)

    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.

  6. 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.

  7. 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.

  8. Filter assembly for metallic and intermetallic tube filters

    DOE Patents [OSTI]

    Alvin, Mary Anne (113 Lehr Ave., Pittsburgh, PA 15223); Lippert, Thomas E. (3205 Cambridge Rd., Murrysville, PA 15668); Bruck, Gerald J. (4469 Sardis Rd., Murrysville, PA 15668); Smeltzer, Eugene E. (R.D. 7, Box 267-I, Italy Rd., Export, PA 15632-9621)

    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.

  9. Minimizing the Cost of Innovative Nuclear Technology Through Flexibility: The Case of a Demonstration Accelerator-Driven Subcritical Reactor Park

    E-Print Network [OSTI]

    Cardin, Michel-Alexandre; Steer, Steven J.; Nuttall, William J.; Parks, Geoffrey T.; Gonçalves, Leonardo V. N.; de Neufville, Richard

    Presented is a methodology to analyze the expected Levelised Cost Of Electricity (LCOE) in the face of technology uncertainty for Accelerator-Driven Subcritical Reactors (ADSRs). It shows that flexibility in the design and deployment strategy...

  10. Int. J. Nuclear Energy Science and Technology, Vol. 4, No. 4, 2009 287 Development of computational methods and their

    E-Print Network [OSTI]

    Demazičre, Christophe

    engineering. His research interests include pressurised water reactor and boiling water reactor physics, with typically 150­800 fuel assemblies constituting the core for Light Water Reactor (LWR) systems. Each@nephy.chalmers.se Abstract: A specificity of nuclear reactors is their multiphysics and multiscale character

  11. Department of Energy Awards $15 Million for Nuclear Fuel Cycle...

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

    Department of Energy Awards 15 Million for Nuclear Fuel Cycle Technology Research and Development Department of Energy Awards 15 Million for Nuclear Fuel Cycle Technology...

  12. Ozone decomposing filter

    DOE Patents [OSTI]

    Simandl, Ronald F. (Farragut, TN); Brown, John D. (Harriman, TN); Whinnery, Jr., LeRoy L. (Dublin, CA)

    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.

  13. Rotating drum filter

    DOE Patents [OSTI]

    Anson, Donald (Worthington, OH)

    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).

  14. Next Generation Nuclear Plant Project Technology Development Roadmaps: The Technical Path Forward for 750–800°C 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 750–800°C reactor outlet temperature (ROT) specific to each supplier are collected in Appendix A.

  15. Web Content Filtering 1 User Guidelines Web content filter guidelines

    E-Print Network [OSTI]

    Swain, Peter

    Web Content Filtering 1 User Guidelines Web content filter guidelines Introduction The basic criterion for blocking a Web page Categories of material which will be blocked Requesting the unblocking of Aberdeen applies a Web Content Filtering service to all web pages accessed from the undergraduate network

  16. Westinghouse standleg moving granular bed filter development program

    SciTech Connect (OSTI)

    Newby, R.A.; Yang, W.C.; Smeltzer, E.E.; Lippert, T.E.

    1994-10-01

    Advanced, coal-based, power plants, such as IGCC and Advanced-PFBC, are currently nearing commercial demonstration. These power plant technologies require hot gas filtration as part of their gas cleaning trains. Ceramic barrier filters are the major filter candidates being developed for these hot gas cleaning applications. While ceramic barrier filters achieve high levels of particle removal, there are concerns for their reliability and operability. An alternative hot gas filtration technology is the moving granular bed filter. These systems are at a lower state of development than ceramic barrier filters, and their effectiveness as filters is still in question. Their apparent attributes, result from their much less severe mechanical design and materials constraints, and the potential for more reliable, failure-free particle removal operation. The standleg moving granular-bed filter (SMGBF) system, is a compact unit that uses cocurrent gas-pellet contacting in an arrangement that greatly simplifies and enhances the distribution of dirty, process gas to the moving bed and allows effective disengagement of clean gas from the moving bed. This paper describes the equipment and process test results.

  17. A macroscale model for simulating pressure drop and collection efficiency of pleated filters over time

    E-Print Network [OSTI]

    Tafreshi, Hooman Vahedi

    time. To the knowledge of the authors, there are no criteria for designing pleat shape and pleat count time S. Fotovati a , H. Vahedi Tafreshi a, , B. Pourdeyhimi b a Department of Mechanical and Nuclear geometry. The general consensus in designing pleated fibrous filters in industry is that a filter

  18. Quick-change filter cartridge

    DOE Patents [OSTI]

    Rodgers, John C. (Santa Fe, NM); McFarland, Andrew R. (College Station, TX); Ortiz, Carlos A. (Bryan, TX)

    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.

  19. 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.

  20. Siphon filter assessment for Northern Ghana

    E-Print Network [OSTI]

    Ziff, Sara Elizabeth

    2009-01-01

    The siphon filter is a household water filter developed by the Basic Water Needs Foundation based on the design of ceramic candle filters. The siphon filter is marketed under brand names CrystalPur and Tulip and is sold ...

  1. 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.

  2. 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...

  3. CLEERS Activities: Diesel Soot Filter Characterization & NOx...

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

    Activities: Diesel Soot Filter Characterization & NOx Control Fundamentals CLEERS Activities: Diesel Soot Filter Characterization & NOx Control Fundamentals 2009 DOE Hydrogen...

  4. 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.

  5. 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.

  6. Regenerable particulate filter

    DOE Patents [OSTI]

    Stuecker, John N. (Albuquerque, NM); Cesarano, III, Joseph (Albuquerque, NM); Miller, James E. (Albuquerque, NM)

    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.

  7. 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.

  8. Nuclear Energy Research and Development Roadmap | Department...

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

    NuclearEnergyRoadmapFinal.pdf More Documents & Publications Before the House Science and Technology Committee Appendix B to the Minutes for the Nuclear Energy Research Advisory...

  9. 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.

  10. 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.

  11. 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

  12. 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.

  13. 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.

  14. 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.

  15. As the demand for power increases in populated areas, so will the demand for water. Current power plant technology relies heavily on the Rankine cycle in coal, nuclear and even solar thermal

    E-Print Network [OSTI]

    plant technology relies heavily on the Rankine cycle in coal, nuclear and even solar thermal powerAs the demand for power increases in populated areas, so will the demand for water. Current power the cooling power from radiation were developed and run. The results showed a cooling power of 35 W/m2

  16. THE CREATIVE APPLICATION OF SCIENCE TECHNOLOGY & WORK FORCE INNOVATIONS TO THE D&D OF PLUTONIUM FINISHING PLANT (PFP) AT THE HANFORD NUCLEAR RESERVATION

    SciTech Connect (OSTI)

    CHARBONEAU, S.L.

    2006-02-01

    The Plutonium Finishing Plant (PFP) consists of a number of process and support buildings for handling plutonium. Building construction began in the late 1940's to meet national priorities and became operational in 1950 producing refined plutonium salts and metal for the United States nuclear weapons program. The primary mission of the PFP was to provide plutonium used as special nuclear material for fabrication into a nuclear device for the war effort. Subsequent to the end of World War II, the PFP's mission expanded to support the Cold War effort through plutonium production during the nuclear arms race. PFP has now completed its mission and is fully engaged in deactivation, decontamination and decommissioning (D&D). At this time the PFP buildings are planned to be reduced to ground level (slab-on-grade) and the site remediated to satisfy national, Department of Energy (DOE) and Washington state requirements. The D&D of a highly contaminated plutonium processing facility presents a plethora of challenges. PFP personnel approached the D&D mission with a can-do attitude. They went into D&D knowing they were facing a lot of challenges and unknowns. There were concerns about the configuration control associated with drawings of these old process facilities. There were unknowns regarding the location of electrical lines and process piping containing chemical residues such as strong acids and caustics. The gloveboxes were highly contaminated with plutonium and chemical residues. Most of the glovebox windows were opaque with splashed process chemicals that coated the windows or etched them, reducing visibility to near zero. Visibility into the glovebox was a serious worker concern. Additionally, all the gloves in the gloveboxes were degraded and unusable. Replacing gloves in gloveboxes was necessary to even begin glovebox cleanout. The sheer volume of breathing air needed was also an issue. These and other challenges and PFP's approach to overcome these challengers are described. Many of the challenges to the D&D work at PFP were met with innovative approaches based on new science and/or technology and many were also based on the creativity and motivation of the work force personnel.

  17. Filter Press Building 

    E-Print Network [OSTI]

    Bush, W. M.

    1986-01-01

    -of-the-art installations in the United States. The new facility, as part of a modern water pollution contiol center, offered a unique oppor tunity for a total state-of-the-art energy system. Heat recovery from treated wastewater for space heating would be the major... containing vast reservoirs of heat energy. CONCEPT OF HEAT RECOVERY The concept of a heat recovery system for the Filter Press Building was not only practical, but exciting. It was estimated the Avon Lake waste water treatment effluent had an energy...

  18. Sampled data lattice filters 

    E-Print Network [OSTI]

    Thrift, William Terry

    1980-01-01

    Lattice Filters (December 1979) William Terry Thrift III, B. S. , Texas A&M University Chairman of Advisory Committee: Dr. P. E. Allen The thesis studies the sensitivity properties of a 2nd order z-domain lattice structure as they apply to analog.... In the indirect method an s-domain transfer function is first converted to an s-domain signal flowgraph. Next the flowgraph is implemented by continuous circuits. The continuous circuits are then approximated with discrete time circuits which consist...

  19. 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.

  20. Coated x-ray filters

    DOE Patents [OSTI]

    Steinmeyer, Peter A. (Farmington, NM)

    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.

  1. 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.

  2. Preparing Non-nuclear Engineers for the Nuclear Field

    E-Print Network [OSTI]

    Ervin, Elizabeth K.

    . An understanding of power generation is important for all modern-day engineers, and nuclear energy serves as a good technology, the proposed course relates nuclear systems engineering, safe reactor design, infrastructurePreparing Non-nuclear Engineers for the Nuclear Field Elizabeth K. Ervin The University

  3. Paola Cappellaro Assistant Professor of Nuclear Science and Engineering

    E-Print Network [OSTI]

    Chen, Sow-Hsin

    Massachusetts Institute of Technology, Cambridge, MA (2001­2006) ­ Ph.D. in Nuclear of Technology, Dept. of Nuclear Science and Engineering: ­ Instructor for "22Paola Cappellaro Assistant Professor of Nuclear Science and Engineering

  4. Relative Movements for Design of Commodities in Nuclear Power Plants

    Broader source: Energy.gov [DOE]

    Relative Movements for Design of Commodities in Nuclear Power Plants Javad Moslemian, Vice President, Nuclear Power Technologies, Sargent & Lundy LLC Nezar Abraham, Senior Associate II, Nuclear Power Technologies, Sargent & Lundy LLC

  5. The magnetic centrifugal mass filter Abraham J. Fetterman and Nathaniel J. Fisch

    E-Print Network [OSTI]

    The magnetic centrifugal mass filter Abraham J. Fetterman and Nathaniel J. Fisch Department centrifugal and magnetic confinement of ions in a way similar to the asymmetric centrifugal trap. This magnetic centrifugal mass filter is shown to be more proliferation resistant than present technology

  6. BACTERIA-FILTERS: PERSISTENT PARTICLE FILTERS FOR BACKGROUND SUBTRACTION

    E-Print Network [OSTI]

    Peleg, Shmuel

    BACTERIA-FILTERS: PERSISTENT PARTICLE FILTERS FOR BACKGROUND SUBTRACTION Yair Movshovitz switch of bacteria between two states: A normal growing cell and a dormant but persistent cell after the stress is over, bacterial growth continues. Similar to bacteria, particles will switch between

  7. 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)

  8. 1 Filter_Supplemental-Info_090913.doc Supplemental Information Regarding RF/Microwave Filter Design

    E-Print Network [OSTI]

    Weller/USF 1 Filter_Supplemental-Info_090913.doc Supplemental Information Regarding RF/Microwave Filter Design The video module on RF/microwave filter design, Filter Demonstration in Microwave Office

  9. 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...

  10. 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.

  11. SRNS | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    for careers in plant maintenance and operations at nuclear facilities by supporting Augusta Technical College's Nuclear Engineering Technology Program. http:1.usa.gov1uKSDdW...

  12. Nuclear Systems Technology | Nuclear Science | ORNL

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

    Cycle Systems Criticality Safety Irradiation Experiment Development and Execution Robotics & Remote Systems Engineering and Applications Thermal & Hydraulic Experiments &...

  13. Filtered Patent Maps for Predicting Diversification Paths of Inventors and Organizations

    E-Print Network [OSTI]

    Yan, Bowen

    2015-01-01

    In a patent technology network map, almost all pairs of technology classes are connected, whereas most of the connections are extremely weak. This observation suggests the need and also the possibility to filter the network map by removing the negligible and noisy links. But link removal may reduce the power of the network for predicting the cross-field patent portfolio diversification of inventors and inventing organizations. This paper proposes a metric for such predictive power of a patent network, and a method that allows one to objectively choose a best tradeoff between predictive power and the removal of weak links. We show the results that identify filtered networks below the optimal tradeoff, and also remove a degree of arbitrariness compared with other filtering treatments from the literature. On that basis, we further demonstrate the use of filtered technology maps to visualize and analyze the main paths of patent portfolio diversification of a prolific inventor (Leonard Forbes) and a technology com...

  14. Sintered composite medium and filter

    DOE Patents [OSTI]

    Bergman, Werner (Pleasanton, CA)

    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.

  15. Fuel Efficient Diesel Particulate Filter (DPF) Modeling and Development

    SciTech Connect (OSTI)

    Stewart, Mark L.; Gallant, Thomas R.; Kim, Do Heui; Maupin, Gary D.; Zelenyuk, Alla

    2010-08-01

    The project described in this report seeks to promote effective diesel particulate filter technology with minimum fuel penalty by enhancing fundamental understanding of filtration mechanisms through targeted experiments and computer simulations. The overall backpressure of a filtration system depends upon complex interactions of particulate matter and ash with the microscopic pores in filter media. Better characterization of these phenomena is essential for exhaust system optimization. The acicular mullite (ACM) diesel particulate filter substrate is under continuing development by Dow Automotive. ACM is made up of long mullite crystals which intersect to form filter wall framework and protrude from the wall surface into the DPF channels. ACM filters have been demonstrated to effectively remove diesel exhaust particles while maintaining relatively low backpressure. Modeling approaches developed for more conventional ceramic filter materials, such as silicon carbide and cordierite, have been difficult to apply to ACM because of properties arising from its unique microstructure. Penetration of soot into the high-porosity region of projecting crystal structures leads to a somewhat extended depth filtration mode, but with less dramatic increases in pressure drop than are normally observed during depth filtration in cordierite or silicon carbide filters. Another consequence is greater contact between the soot and solid surfaces, which may enhance the action of some catalyst coatings in filter regeneration. The projecting crystals appear to provide a two-fold benefit for maintaining low backpressures during filter loading: they help prevent soot from being forced into the throats of pores in the lower porosity region of the filter wall, and they also tend to support the forming filter cake, resulting in lower average cake density and higher permeability. Other simulations suggest that soot deposits may also tend to form at the tips of projecting crystals due to the axial velocity component of exhaust moving down the filter inlet channel. Soot mass collected in this way would have a smaller impact on backpressure than soot forced into the flow restrictions deeper in the porous wall structure. This project has focused on the development of computational, analytical, and experimental techniques that are generally applicable to a wide variety of exhaust aftertreatment technologies. By helping to develop improved fundamental understanding pore-scale phenomena affecting filtration, soot oxidation, and NOX abatement, this cooperative research and development agreement (CRADA) has also assisted Dow Automotive in continuing development and commercialization of the ACM filter substrate. Over the course of this research project, ACM filters were successfully deployed on the Audi R10 TDI racecar which won the 24 Hours of LeMans endurance race in 2006, 2007, and 2008; and the 12 Hours of Sebring endurance race in 2006 and 2007. It would not have been possible for the R10 to compete in these traditionally gasoline-dominated events without reliable and effective exhaust particulate filtration. These successes demonstrated not only the performance of automotive diesel engines, but the efficacy of DPF technology as it was being deployed around the world to meet new emissions standards on consumer vehicles. During the course of this CRADA project, Dow Automotive commercialized their ACM DPF technology under the AERIFYTM DPF brand.

  16. Introduction to Nuclear Waste Management Nuclear Waste is a type of radioactive waste that is usually the by-product of

    E-Print Network [OSTI]

    Auerbach, Scott M.

    that is usually the by-product of a nuclear technology. -Nuclear Technology includes: -Nuclear ReactorsIntroduction to Nuclear Waste Management Nuclear Waste is a type of radioactive waste -Nuclear Medicine Chemicals Nuclear reactors -Radioactive materials are placed in a reactor vessel

  17. 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.

  18. I. Nuclear Production Reaction and Chemical Isolation Procedure for 240Am II. New Superheavy Element Isotopes: 242Pu(48Ca,5n)285-114

    E-Print Network [OSTI]

    Ellison, Paul Andrew

    2011-01-01

    library for nuclear science and technology. Nuclear DataJournal of Nuclear Science and Technology, 7(10):487–499,Journal of Nuclear Science and Technology, G.T. Seaborg,

  19. Educational Outreach | Nuclear Science | ORNL

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

    Science | Educational Outreach SHARE Educational Outreach The future viability of ORNL's nuclear science & technology programs depends on developing and maintaining worthwhile...

  20. SRNS | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    signs on as industry partner for Nuclear Engineering Technology Education at Augusta Technical College. http:1.usa.gov1uKSDdW...

  1. Technological Opportunities to Increase the Proliferation Resistance...

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

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

  2. Diesel Particulate Filters: Market Introducution in Europe |...

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

    Filters: Market Introducution in Europe Diesel Particulate Filters: Market Introducution in Europe 2004 Diesel Engine Emissions Reduction (DEER) Conference Presentation: Aaqius and...

  3. Catalytic Filter for Diesel Exhaust Purification | Department...

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

    Catalytic Filter for Diesel Exhaust Purification Catalytic Filter for Diesel Exhaust Purification This project is developing a precious metal-free passive diesel particulate...

  4. 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...

  5. 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.

  6. Policy Paper 37: Energy and Security in Northeast Asia: Proposals for Nuclear Cooperation

    E-Print Network [OSTI]

    Kaneko, Kumao; Suzuki, Atsuyuki; Choi, Jor-Shan; Fei, Edward

    1998-01-01

    security, nuclear energy, and environment. It also indicatesbased on its nuclear submarine technology Energy Environmentalternatives? Environment--Use of nuclear energy can lessen

  7. Spin-On for the Renaissance? The Current State of China's Nuclear Industry

    E-Print Network [OSTI]

    Yuan, Jing-dong

    2010-01-01

    can develop indigenous nuclear power capacities. The role ofwith China’s State Nuclear Power Technology Corpora-tion, Sanmen Nuclear Power Company, and China National

  8. Spin Filtering in Storage Rings

    E-Print Network [OSTI]

    N. N. Nikolaev; F. F. Pavlov

    2005-12-05

    The spin filtering in storage rings is based on the multiple passage of a stored beam through a polarized internal gas target. Apart from the polarization by transmission, a unique geometrical feature of interaction with the target in such a filtering process, pointed out by H.O. Meyer \\cite{Meyer}, is a scattering of stored particles within the beam. A rotation of the spin in the scattering process affects the polarization buildup. We derive here a quantum-mechanical evolution equation for the spin-density matrix of the stored beam which incorporates scattering within the beam. We show how the interplay of transmission and scattering with the beam changes from polarized electrons to polarized protons in the atomic target. After discussions of the FILTEX results on the filtering of stored protons \\cite{FILTEX}, we comment on the strategy of spin filtering of antiprotons for the PAX experiment at GSI FAIR \\cite{PAX-TP}.

  9. 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.

  10. Analysis of Nuclear Reconstitution, Nuclear

    E-Print Network [OSTI]

    Forbes, Douglass

    CHAPTER Analysis of Nuclear Reconstitution, Nuclear Envelope Assembly, and Nuclear Pore Assembly ....................................................................... 180 8.5 Assaying Assembly and Integrity of the Nuclear Envelope................................... 182 8.6 A Nuclear Pore Complex Assembly Assay Using pore-free Nuclear Intermediates

  11. The development and evaluation of a neutron window filter facility utilizing the TAMU NSC TRIGA reactor 

    E-Print Network [OSTI]

    Harding, Patricia Colleen

    1982-01-01

    THE DEVELOPMENT AND EVALUATION OF A NEUTRON WINDOW FILTER FACILITY UTILIZING THE TAMU NSC TRIGA REACTOR A Thesis by PATRICIA COLLEEN HARDING Submitted to the Graduate College of Texas AAM University in partial fulfillment of the requirement... for the degree of MASTER OF SCIENCE December 1982 Major Subject: Nuclear Engineering THE DEVELOPMENT AND EVALUATION OF A NEUTRON WINDOW FILTER FACILITY UTILIZING THE TAMU NSC TRIGA REACTOR A Thesis by PATRICIA COLLEEN HARDING Approved as to style...

  12. Water washable stainless steel HEPA filter

    DOE Patents [OSTI]

    Phillips, Terrance D. (617 Chestnut Ct., Aiken, SC 29803)

    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.

  13. Filter!Demonstration Microwave!Office

    E-Print Network [OSTI]

    Filter!Demonstration in Microwave!Office muse #12;Objectives · Demonstrate!project!setup!in!Microwave

  14. 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.

  15. 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.

  16. NUCLEAR PLANT OPERATIONS AND

    E-Print Network [OSTI]

    Demazičre, Christophe

    NUCLEAR PLANT OPERATIONS AND CONTROL KEYWORDS: moderator temper ature coefficient, reactivity co reactor Unit 4 of the Ringhals Nuclear Power Plant (Sweden) during fuel cycle 16 is analyzed of Reactor Physics SE-41296 Gothenburg, Sweden GABOR PÓR Budapest University of Technology and Economics H

  17. NUCLEAR PLANT OPERATIONS AND

    E-Print Network [OSTI]

    Pázsit, Imre

    NUCLEAR PLANT OPERATIONS AND CONTROL KEYWORDS: moderator temper- ature coefficient, reactivity co reactor Unit 4 of the Ringhals Nuclear Power Plant (Sweden) during fuel cycle 16 is analyzed of Reactor Physics SE-41296 Gothenburg, Sweden GABOR PÓR Budapest University of Technology and Economics H

  18. Nuclear Instruments and Methods in Physics Research A 562 (2006) 401406 Generating a multi-line neutron beam using an electron

    E-Print Network [OSTI]

    Danon, Yaron

    2006-01-01

    Nuclear Instruments and Methods in Physics Research A 562 (2006) 401­406 Generating a multi-line neutron beam using an electron Linac and a U-filter R. Moreha,b,Ă, R.C. Blockb , Y. Danonb a Physics with the steady-state filtered neutron beams obtained using nuclear reactors [1­4]. The filter materials used

  19. 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.

  20. 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.

  1. List of Major Information Systems,National Nuclear Security Administra...

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

    emerging information networking technology to production processes in support of the U.S. nuclear weapons stockpile. National Nuclear Security Administration ADaPT Network...

  2. A Critical Step Toward Sustainable Nuclear Fuel Disposal | Department...

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

    that the United States remains at the forefront of nuclear safety and security, non-proliferation, and nuclear energy technology we must develop an effective strategy and...

  3. Physics-based multiscale coupling for full core nuclear reactor...

    Office of Scientific and Technical Information (OSTI)

    multiscale coupling for full core nuclear reactor simulation Numerical simulation of nuclear reactors is a key technology in the quest for improvements in efficiency, safety,...

  4. Microsoft PowerPoint - Nuclear Material Import Export License...

    National Nuclear Security Administration (NNSA)

    Material ImportExport License - Uses & Reporting processes Gary Langlie - Nuclear Regulatory Commission Karen Antizzo - Link Technologies Overview What is a Nuclear Regulatory...

  5. Moving granular-bed filter development program topical report. Base contract test plan

    SciTech Connect (OSTI)

    Newby, R.A.; Dilmore, W.J.; Fellers, A.W.; Gasparovic, A.C.; Kittle, W.F.; Lippert, T.E.; Smeltzer, E.E.; Yang, W.C.

    1991-10-17

    The Westinghouse Science & Technology Center has proposed a novel moving granular-bed filter concept, the Standleg Moving Granular-Bed Filter (S-MGBF) system, that overcomes the inherent deficiencies of the current state-of-the-art moving granular-bed filter technology. The S-MGBF system combines two unique features that make it highly effective for use in advanced coal-fueled power plants. First, the S-MGBF system applies pelletization technology to generate filter pellets from the power plant solid waste materials, and uses these pellets as a ``once-through`` filtering media to eliminate the need for costly, complex, and large filter media recycling equipment. This pelletizing step also generates a more environmentally acceptable solid waste product and provides the potential to incorporate gas-phase contaminant sorbents into the filtering media. Secondly, the S-MGBF system passes these pellets and the flyash laden power plant gas through a highly compact S-MGBF that uses cocurrent gas-pellet contacting in an arrangement that greatly simplifies and enhances the distribution of dirty gas to the moving bed and the disengagement of clean gas from the moving bed.

  6. technology | National Nuclear Security Administration

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantityBonneville Power AdministrationRobust,Field-effectWorkingLosThe 26thI D- 6 0 4 2 r m m mDiurnalCarbonU C Lszhou9tchoutechnology

  7. ^ x>*/87ooo VS of Energy Technology

    E-Print Network [OSTI]

    The change from nuclear reactor technology towards non-nuclear energy technologies was continued during^ x>*/87ooo VS Risř-R-543 DPI Department of Energy Technology Annual Progress Report 1 January - 31 #12;Risř-R-543 DEPARTMENT OF ENERGY TECHNOLOGY ANNUAL PROGRESS REPORT 1 January - 31 December 1986

  8. Kalman Filter Tracking on Parallel Architectures

    E-Print Network [OSTI]

    Giuseppe Cerati; Peter Elmer; Steven Lantz; Kevin McDermott; Dan Riley; Matevž Tadel; Peter Wittich; Frank Würthwein; Avi Yagil

    2015-05-18

    Power density constraints are limiting the performance improvements of modern CPUs. To address this we have seen the introduction of lower-power, multi-core processors, but the future will be even more exciting. In order to stay within the power density limits but still obtain Moore's Law performance/price gains, it will be necessary to parallelize algorithms to exploit larger numbers of lightweight cores and specialized functions like large vector units. Example technologies today include Intel's Xeon Phi and GPGPUs. Track finding and fitting is one of the most computationally challenging problems for event reconstruction in particle physics. At the High Luminosity LHC, for example, this will be by far the dominant problem. The need for greater parallelism has driven investigations of very different track finding techniques including Cellular Automata or returning to Hough Transform. The most common track finding techniques in use today are however those based on the Kalman Filter. Significant experience has been accumulated with these techniques on real tracking detector systems, both in the trigger and offline. They are known to provide high physics performance, are robust and are exactly those being used today for the design of the tracking system for HL-LHC. Our previous investigations showed that, using optimized data structures, track fitting with Kalman Filter can achieve large speedup both with Intel Xeon and Xeon Phi. We report here our further progress towards an end-to-end track reconstruction algorithm fully exploiting vectorization and parallelization techniques in a realistic simulation setup.

  9. 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).

  10. 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.

  11. SCIENCE CHINA Technological Sciences

    E-Print Network [OSTI]

    Liu, Yijun

    turbines, jet engines, nuclear power plants and space crafts, have placed severe demands on highSCIENCE CHINA Technological Sciences © Science China Press and Springer-Verlag Berlin Heidelberg

  12. I.N. Sviatoslavsky, M.E. Sawan, E.A. Mogahed, University of Wisconsin S. Malang, Fusion Nuclear Technology Consulting, Germany

    E-Print Network [OSTI]

    ratcheting criteria as determined by the ITER Structural Design Criteria (ISDC). To satisfy the cyclicI.N. Sviatoslavsky, M.E. Sawan, E.A. Mogahed, University of Wisconsin S. Malang, Fusion Nuclear.g., maximizing nuclear parameters to achieve high conversion efficiency) are well worth striving for. SUMMARY

  13. Kalman Filter Tracking on Parallel Architectures

    E-Print Network [OSTI]

    Cerati, Giuseppe; Lantz, Steven; McDermott, Kevin; Riley, Dan; Tadel, Matevž; Wittich, Peter; Würthwein, Frank; Yagil, Avi

    2015-01-01

    Power density constraints are limiting the performance improvements of modern CPUs. To address this we have seen the introduction of lower-power, multi-core processors, but the future will be even more exciting. In order to stay within the power density limits but still obtain Moore's Law performance/price gains, it will be necessary to parallelize algorithms to exploit larger numbers of lightweight cores and specialized functions like large vector units. Example technologies today include Intel's Xeon Phi and GPGPUs. Track finding and fitting is one of the most computationally challenging problems for event reconstruction in particle physics. At the High Luminosity LHC, for example, this will be by far the dominant problem. The need for greater parallelism has driven investigations of very different track finding techniques including Cellular Automata or returning to Hough Transform. The most common track finding techniques in use today are however those based on the Kalman Filter. Significant experience has...

  14. EVALUATION OF UPFLOW FILTERS FOREVALUATION OF UPFLOW FILTERS FOR STORMWATER TREATMENT AT CRITICALSTORMWATER TREATMENT AT CRITICAL

    E-Print Network [OSTI]

    Clark, Shirley E.

    .brakes, etc. Infiltration Devices: Subsurface Infiltration Trenches,Infiltration Devices: Subsurface Infiltration Trenches, Surface Percolation Areas, Porous Pavement, Grass Filters,Surface Percolation Areas filters.downflow filters. OBJECTIVES OF THE STUDYOBJECTIVES OF THE STUDY Primary:Primary: Optimize

  15. Centrifugal Filter Devices Centricon centrifugal filter devices with 10,000 NMWL, 30,000 NMWL,

    E-Print Network [OSTI]

    Kirschner, Marc W.

    CENTRICON ® Centrifugal Filter Devices User Guide Centricon centrifugal filter devices with 10-vitro diagnostic use. Centricon centrifugal filter devices with 3,000 NMWL Ultracel YM membranes are for research ................................................... 3 Maximum Centrifugal Force .............................................................. 3 Rotor

  16. 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.

  17. 39.2 / B. L. Zhang 39.2: Optical Analysis of Vertical Aligned Mode on Color Filter

    E-Print Network [OSTI]

    39.2 / B. L. Zhang 39.2: Optical Analysis of Vertical Aligned Mode on Color Filter Liquid of Science and Technology, Clear Water Bay, Hong Kong Y. C. Chen Himax Display, No.12, Nanke 8th Road, Tainan on color filter liquid-crystal-on-silicon microdisplay. Three-dimensional optical analyses were performed

  18. 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.

  19. 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.

  20. Electric filter with movable belt electrode

    DOE Patents [OSTI]

    Bergman, Werner (Pleasanton, CA)

    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.

  1. 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 Nation’s 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.

  2. 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...

  3. Evaluation of the KanchanTM Arsenic Filter under various water quality conditions of the Nawalparasi District, Nepal

    E-Print Network [OSTI]

    Espinoza, Claudia M. (Claudia Maritza)

    2011-01-01

    In 2002, the Massachusetts Institute of Technology Department of Civil and Environmental Engineering partnered with the Environment and Public Health Organization to develop and disseminate the KanchanTM Arsenic Filter ...

  4. An HMM-based speech synthesiser using Glottal Post-Filtering Jo~ao P. Cabral1,2

    E-Print Network [OSTI]

    Edinburgh, University of

    An HMM-based speech synthesiser using Glottal Post-Filtering Jo~ao P. Cabral1,2 , Steve Renals2 Dublin, Ireland 2 The Centre for Speech Technology Research, University of Edinburgh,UK joao.cabral

  5. PLUTONIUM-URANIUM EXTRACTION (PUREX) FACILITY ALARACT DEMONSTRATION FOR FILTER HOUSING

    SciTech Connect (OSTI)

    LEBARON GJ

    2008-11-25

    This document presents an As Low As Reasonably Achievable Control Technology (ALARACT) demonstration for evaluating corrosion on the I-beam supporting filter housing No.9 for the 291-A-l emission unit of the Plutonium-Uranium Extraction (PUREX) Facility, located in the 200 East Area of the Hanford Site. The PUREX facility is currently in surveillance and maintenance mode. During a State of Washington, Department of Health (WDOH) 291-A-l emission unit inspection, a small amount of corrosion was observed at the base of a high-efficiency particulate air (HEPA) filter housing. A series of internal and external inspections identified the source of the corrosion material as oxidation of a small section of one of the carbon steel I-beams that provides support to the stainless steel filter housing. The inspections confirmed the corrosion is isolated to one I-beam support location and does not represent any compromise of the structural support or filter housing integrity. Further testing and inspections of the support beam corrosion and its cause were conducted but did not determine the cause. No definitive evidence was found to support any degradation of the housing. Although no degradation of the housing was found, a conservative approach will be implemented. The following actions will be taken: (1) The current operating filter housing No.9 will be removed from service. (2) The only remaining available filter housings (No.1, No.2, and No.3) will be placed in service. These filter housings have new HEPA filters fitted with stainless steel frames and faceguards which were installed in the spring of 2007. (3) Filter housings No.5 and No.10 will be put on standby as backups. To document the assessment of the unit, a draft ALARACT filter housing demonstration for the PUREX filter housing was prepared, and informally provided to WDOH on August 7, 2008. A follow up WDOH response to the draft ALARACT filter housing demonstration for the PUREX filter housing questioned whether deteriorated galvanized filter faceguards discovered during an internal filter housing inspection met American Society of Mechanical Engineers (ASME) AG-l or Military Specification (MIL) 51068 standards. The filter system was designed and installed prior to the issuance of AG-l, February 1986; however, MIL 51068 did require galvanized faceguards. The faceguards are not necessary for filtration or structural purposes; it is concluded that the system is in compliance with the intent of the applicable standard. Appendix B provides supporting information to address this issue.

  6. Improving Filtering for Computer Graphics 

    E-Print Network [OSTI]

    Manson, Josiah

    2014-04-30

    When drawing images onto a computer screen, the information in the scene is typically more detailed than can be displayed. Most objects, however, will not be close to the camera, so details have to be filtered out, or anti-aliased, when the objects...

  7. Sixth American Nuclear Society International Topical Meeting on Nuclear Plant Instrumentation, Control, and Human-Machine Interface Technologies NPIC&HMIT 2009, Knoxville, Tennessee, April 5-9, 2009, on CD-ROM, American Nuclear Society, LaGrange Park, IL

    E-Print Network [OSTI]

    Heljanko, Keijo

    , automation 1 INTRODUCTION In nuclear power plants (NPPs), novel digitalized I&C systems enable complicatedSixth American Nuclear Society International Topical Meeting on Nuclear Plant Instrumentation, on CD-ROM, American Nuclear Society, LaGrange Park, IL (2009) VERIFICATION OF SAFETY LOGIC DESIGNS

  8. Features of coal dust dynamics at action of differently oriented forces in granular filtering medium

    E-Print Network [OSTI]

    I. M. Neklyudov; L. I. Fedorova; P. Ya. Poltinin; O. P. Ledenyov

    2013-01-24

    The process of the coal dust particles transportation and structurization in the experimental horizontal model of air filter with the cylindrical coal adsorbent granules as in the iodine air filter at the nuclear power plant is researched. In the investigated case the vector of carrying away force of air flow and the vector of gravitation force are mutually perpendicular, and the scattering of the dust particles on the granules occurs in the normal directions. It is found that the phenomenon of non controlled spontaneous sharp increase of aerodynamic resistance in the iodine air filter under the big integral volumes of filtered air and the big masses of introduced coal dust particles is not observed at the described experimental conditions in distinction from the case of the parallel orientation of this forces as in the vertical iodine air filters at the nuclear power plant. The quantitative measurements of the main parameters of the process of the dust masses transportation and structurization are made on a developed experimental model of the iodine air filter with the cylindrical coal adsorbent granules.

  9. On the Kalman Filter and Its Variations

    E-Print Network [OSTI]

    Lindsey, Theodore S.

    2014-05-31

    The objective of this paper is to explore the standard Kalman filter and two non-linear variations. Additionally, we will discuss the derivation of the Kalman filter using Newton's method. Next we will consider the implementation of both...

  10. Automatic tuning of continuous-time filters 

    E-Print Network [OSTI]

    Sumesaglam, Taner

    2004-11-15

    Integrated high-Q continuous-time filters require adaptive tuning circuits that will correct the filter parameters such as center frequency and quality factor (Q). Three different automatic tuning techniques are introduced. In all of the proposed...

  11. Nuclear Energy Page 570Page 570

    E-Print Network [OSTI]

    Nuclear Energy Page 570Page 570 #12;Energy Supply and Conservation/ Nuclear Energy FY 2007;Energy Supply and Conservation/Nuclear Energy/ Overview FY 2007 Congressional Budget Energy Supply and Conservation Office of Nuclear Energy, Science and Technology Overview Appropriation Summary by Program

  12. 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.

  13. In situ microbial filter used for bioremediation

    DOE Patents [OSTI]

    Carman, M. Leslie (San Ramon, CA); Taylor, Robert T. (Roseville, CA)

    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.

  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. 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.

  16. National Nuclear Security Administration to Help Train Former...

    National Nuclear Security Administration (NNSA)

    Former Soviet WMD Scientists in Commercial Information Technology Fields --Reduces Proliferation Threats-- | National Nuclear Security Administration Facebook Twitter Youtube...

  17. Industry program needed for nuclear accident management

    SciTech Connect (OSTI)

    Klopp, G.T

    1989-05-01

    This paper addresses the need for a management program for nuclear power accidents. According to the author, the tools and technology for severe accident management exist. The need for a clear, realistic definition of nuclear accident program requirements is discussed.

  18. 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.

  19. DOE Announces Strategic Engineering and Technology Roadmap for...

    Energy Savers [EERE]

    Announces 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...

  20. Before House Committee on Science, Space, and Technology | Department...

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

    Committee on Science, Space, and Technology Before House Committee on Science, Space, and Technology By: Peter Lyons Subject: Assessing America's Nuclear Future - A review of the...

  1. Before the House Science and Technology Subcommittee on Energy...

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

    Energy - Committee on Science, Space, and Technology EA-0813: Final Environmental Assessment Fusion Nuclear Science and Technology Program - Status and Plans for Tritium Research...

  2. Nonlinear bayesian filtering with applications to estimation and navigation 

    E-Print Network [OSTI]

    Lee, Deok-Jin

    2005-08-29

    . First, as sampling-based nonlinear filters, the sigma point filters, the unscented Kalman fil- ter and the divided difference filter are investigated. Secondly, a direct numerical nonlinear filter is introduced where the state conditional probability...

  3. Master's programme in Nuclear Energy Engineering Programme outline

    E-Print Network [OSTI]

    Haviland, David

    .With advances in science and technology, nuclear energy is increasingly re- garded as an eminent part technology will play an important role in future sustainable energy systems.the ongoing advances in nuclear science and technology play the central role in the development of future nuclear power systems

  4. American Nuclear Society 2013 Student Conference Massachusetts Institute of Technology Boston, Massachusetts, USA, April 4-6, 2013, on CD-ROM, American Nuclear Society, LaGrange Park, IL (2013)

    E-Print Network [OSTI]

    Danon, Yaron

    2013-01-01

    of the total energy principle, shown to scale #12;McDermott et al. American Nuclear Society 2013 Student efficiency be proportional to the energy of the gamma ray (E) striking the detector: i = kEi (2) This then allows the capture detection efficiency to be directly proportional to the total excitation energy

  5. 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.

  6. 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.

  7. Filter for a drill string

    DOE Patents [OSTI]

    Hall, David R. (Provo, UT); Pixton, David S. (Lehi, UT); Briscoe, Michael (Lehi, UT); McPherson, James (Sandy, UT)

    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.

  8. 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.

  9. 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.

  10. Research and Development | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    effectiveness of the nuclear weapons stockpile through well-managed scientific research, technology development, and advantageous international collaborations. The Office of...

  11. Broadband Terahertz Modulators based on MEMS-Reconfigurable Mesh Filters

    E-Print Network [OSTI]

    Unlu, Mehmet; Li, Shenglin; Yang, Shang-Hua; Hashemi, Mohammad R; Jarrahi, Mona

    2013-01-01

    Despite the extensive progress in terahertz technology, existing terahertz modulators have not yet offered the modulation specifications required for high-performance terahertz imaging, spectroscopy, and communication systems. Here, we present a novel terahertz intensity modulation technique based on MEMS-reconfigurable double-layered mesh filters, which offers record-high modulation depths and modulation bandwidths, without a considerable compromise in modulation speed or modulation voltage through a fully integrated device configuration. The unique advantage of the presented modulation technique compared with the previously demonstrated terahertz modulation schemes based on tunable metamaterials is reconfiguring the device geometry, which enables radical changes in the device scattering parameters over a broad range of frequencies. Device geometry reconfiguration is made possible through integration of a double-layered mesh filter with an array of electrostatically-actuated MEMS switches. We experimentally ...

  12. Advances in Technology To Realize

    E-Print Network [OSTI]

    Advances in Technology To Realize Fusion Energy in the International Context Kathryn A. McCarthy Deputy Associate Laboratory Director Nuclear Science & Technology Idaho National Laboratory 2008 AAAS Meeting Boston, Massachusetts February 16, 2008 #12;2 The US Enabling Technology Research Mission

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

    DOE Patents [OSTI]

    Brown, Robert C. (Ames, IA); Wistrom, Corey (Ames, IA); Smeenk, Jerod L. (Ames, IA)

    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).

  14. Nuclear Resonance Fluorescence for Nuclear Materials Assay

    E-Print Network [OSTI]

    Quiter, Brian Joseph

    2010-01-01

    Potential of Nuclear Resonance Fluorescence . . . . . . . .2.9.1 Nuclear ThomsonSections . . . . . . . . . . . . . . . Nuclear Resonance

  15. Technology Assessment TECHNOLOGY ASSESSMENT

    E-Print Network [OSTI]

    Rock, Chris

    Technology Assessment 10/14/2004 1 TECHNOLOGY ASSESSMENT STRATEGIC PLAN MISSION STATEMENT Support the Mission of Texas Tech University and the TTU Information Technology Division by providing timely and relevant information and assistance in current and emerging technologies and their practical applications

  16. Bioscience Technology Bioscience Technology

    E-Print Network [OSTI]

    Vertes, Akos

    Bioscience Technology Bioscience Technology Advantage Business Media 100 Enterprise Drive Rockaway, co-director of George Washington University's Institute for Proteomics Technology and Applications-by-point. Manufacturers have stampeded to offer the new technology. Applied Biosystems got out in front in 2004 when

  17. January 3, 2007 National Nuclear Security AdministrationNational Nuclear Security Administration

    E-Print Network [OSTI]

    Learned, John

    & Objectives Reduce the threat to national security posed by nuclear weapons proliferation: Objectives: Develop and demonstrate technologies for detecting the stages of a foreign nuclear weapons · Detection of nuclear weapon and material smuggling Nonproliferation R&D #12;4 Nuclear Detonation Detection

  18. 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.

  19. 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 today’s implementation to revolutionary concepts that would require the development of advanced nuclear technologies.

  20. Simultaneous Removal of Particulates and NOx Using Catalyst Impregnated Fibrous Ceramic Filters

    SciTech Connect (OSTI)

    Choi, J.I.; Mun, S.H.; Kim, S.T.; Hong, M.S.; Lee, J.C.

    2002-09-19

    The research is focused on the development and commercialization of high efficiency, cost effective air pollution control system, which can replace in part air pollution control devices currently in use. In many industrial processes, hot exhaust gases are cooled down to recover heat and to remove air pollutants in exhaust gases. Conventional air pollution control devices such as bag filters, E.P. and adsorption towers withstand operating temperatures up to 300 C. Also, reheating is sometimes necessary to meet temperature windows for S.C.R. Since Oxidation reactions of acid gases such as SO{sub 2}, and HCl with lime are enhanced at high temperatures, catalyst impregnated ceramic filters can be candidate for efficient and cost effective air pollution control devices. As shown on Fig. 1., catalytic ceramic filters remove particulates on exterior surface of filters and acid gases are oxidized to salts reacting with limes injected in upstream ducts. Oxidation reactions are enhanced in the cake formed on exterior of filters. Finally, injected reducing gas such as NH{sub 3} react with NOx to form N{sub 2} and H{sub 2}O interior of filters in particulate-free environment. Operation and maintenance technology is similar to conventional bag filters except that systems are exposed to relatively high temperatures ranging 300-500 C.