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Note: This page contains sample records for the topic "nuclear filter technology" from the National Library of EnergyBeta (NLEBeta).
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they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


1

Nuclear Filter Technology | Open Energy Information  

Open Energy Info (EERE)

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

2

Nuclear Spin Filter  

Science Journals Connector (OSTI)

A "spin filter" for selecting metastable hydrogen, deuterium, or tritium atoms with a given nuclear spin magnetic quantum number (mI) has been built and tested. With the device installed in the Los Alamos "Lamb-shift" polarized-ion source, we have obtained a deuterium negative-ion beam with ? 55% spin-state purity for mI=1,0,爋r-1. An improved magnetic field homogeneity in the apparatus is expected to increase the purity to ? 75%.

Joseph L. McKibben; George P. Lawrence; Gerald G. Ohlsen

1968-05-20T23:59:59.000Z

3

Nuclear Science & Technology  

NLE Websites -- All DOE Office Websites (Extended Search)

Nuclear Science & Technology Nuclear Science & Technology Nuclear Science & Technology1354608000000Nuclear Science & TechnologySome of these resources are LANL-only and will require Remote Access. /No/ Nuclear Science & Technology Some of these resources are LANL-only and will require Remote Access. Key Resources Databases Organizations Journals Key Resources International Atomic Energy Agency IAEA scientific and technical publications cover areas of nuclear power, radiation therapy, nuclear security, nuclear law, and emergency repose. Search under Publications/Books and Reports for scientific books, standards, technical guides and reports National Nuclear Data Center Nuclear physics data for basic nuclear research and for applied nuclear technologies, operated by Brookhaven.

4

Plasma Mass Filters For Nuclear Waste Reprocessing  

SciTech Connect

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.

Abraham J. Fetterman and Nathaniel J. Fisch

2011-05-26T23:59:59.000Z

5

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...

6

Oil Bypass filter technology evaluation final report  

NLE Websites -- All DOE Office Websites (Extended Search)

6-01355 6-01355 U.S. Department of Energy FreedomCAR & Vehicle Technologies Program Oil Bypass Filter Technology Evaluation Final Report TECHNICAL REPORT Larry Zirker James Francfort Jordan Fielding March 2006 Idaho National Laboratory Operated by Battelle Energy Alliance INL/EXT-06-01355 U.S. Department of Energy FreedomCAR & Vehicle Technologies Program Oil Bypass Filter Technology Evaluation Final Report Larry Zirker James Francfort Jordan Fielding March 2006 Idaho National Laboratory Transportation Technology Department Idaho Falls, Idaho 83415 Prepared for the U.S. Department of Energy Assistant Secretary for Energy Efficiency and Renewable Energy Under DOE Idaho Operations Office Contract DE-AC07-05ID14517

7

Nuclear Systems Technology | Nuclear Science | ORNL  

NLE Websites -- All DOE Office Websites (Extended Search)

Advanced Fuel Cycle Systems Criticality Safety Irradiation Experiment Development and Execution Robotics & Remote Systems Engineering and Applications Thermal & Hydraulic Experiments & Analysis Used Nuclear Fuel Storage, Transportation, and Disposal Reactor Technology Nuclear Science Home | Science & Discovery | Nuclear Science | Research Areas | Nuclear Systems Technology SHARE Nuclear Systems Technology Nuclear Systems Technology Image 2 ORNL has had historic involvement in a broad set of nuclear research areas: irradiated materials and isotopes R&D, fission and fusion reactors development, neutron scattering, fuel enrichment, used fuel recycling and disposal, etc. The skills and knowledge required to succeed in these research areas often cultivated core areas of expertise in which ORNL is

8

2012 Nuclear Energy Enabling Technology Factsheet | Department...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Nuclear Energy Enabling Technology Factsheet 2012 Nuclear Energy Enabling Technology Factsheet Learn more about the Nuclear Energy Enabling Technologies (NEET) program, which will...

9

Defense and nuclear technologies  

SciTech Connect

Fulfilling our national security and stockpile stewardship responsibilities requires tremendous scientific and technical breadth: from esoteric theoretical physics and computational modeling to materials science and precision engineering. Because there exists no broad industrial or university base from which to draw expertise in nuclear weapon science and technology, we rely heavily on formal peer reviews and informal exchanges with our sister laboratory at Los Alamos. LLNL has an important, long-term role in the nation`s nuclear weapons program. We are responsible for four of the ten weapon systems in the enduring US stockpile (three of nine after 2002), including the only systems that incorporate all modern safety features. For years to come, we will be responsible for these weapons and for the problems that will inevitably arise. Our nuclear expertise will also play a crucial role as the US attempts to deal effectively with the threat of nuclear proliferation. This past year brought the culmination of our response to profound changes in the nation`s defense needs as we restructured and refocused our activities to address the Administration`s goal of reducing global nuclear danger. We made major contributions to important national security issues in spite of severe fiscal constraints.

NONE

1995-01-01T23:59:59.000Z

10

Security Science & Technology | Nuclear Science | ORNL  

NLE Websites -- All DOE Office Websites (Extended Search)

Research Areas Fuel Cycle Science & Technology Fusion Nuclear Science Isotope Development and Production Nuclear Security Science & Technology Border Security Comprehensive...

11

Nuclear Waste Management using Electrometallurgical Technology - Nuclear  

NLE Websites -- All DOE Office Websites (Extended Search)

Technology Technology Nuclear Fuel Cycle and Waste Management Technologies Overview Modeling and analysis Unit Process Modeling Mass Tracking System Software Waste Form Performance Modeling Safety Analysis, Hazard and Risk Evaluations Development, Design, Operation Overview Systems and Components Development Expertise System Engineering Design Other Major Programs Work with Argonne Contact us For Employees Site Map Help Join us on Facebook Follow us on Twitter NE Division on Flickr Nuclear Waste Management using Electrometallurgical Technology Bookmark and Share The NE system engineering activities involve the conceptual design, through the manufacturing and qualification testing of the Mk-IV and Mk-V electrorefiner and the cathode processor. These first-of-a-kind large scale

12

Future Science & Technology Programs | National Nuclear Security...  

National Nuclear Security Administration (NNSA)

Future Science & Technology Programs | National Nuclear Security Administration People Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency...

13

Three Successful Tests of Color Transparency and Nuclear Filtering  

E-Print Network (OSTI)

We review the theoretical formalism for hard exclusive processes in a nuclear medium. Theory suggests that these processes will show the very interesting phenomena of color transparency and nuclear filtering. The survival probability in nuclear media has also been predicted to show a scaling behavior at large momentum and large nuclear number. We show that all of these effects may have already been seen experimentally.

Pankaj Jain; John P. Ralston

1993-10-06T23:59:59.000Z

14

Nuclear Proliferation Technology Trends Analysis  

SciTech Connect

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.

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

2005-10-04T23:59:59.000Z

15

Nuclear Reactors and Technology; (USA)  

SciTech Connect

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.

Cason, D.L.; Hicks, S.C. (eds.)

1991-01-01T23:59:59.000Z

16

Using the particle filter for nuclear decision support  

Science Journals Connector (OSTI)

In the case of a nuclear accident, forecasting the spread of contamination is important for determining whether contamination thresholds are exceeded. In this study we explore ensemble modeling for forecasting threshold exceedance. This involves defining ... Keywords: Data assimilation, Monte Carlo, Nuclear accidents, Particle filter, Spatial aggregation, Threshold exceedance

Paul H. Hiemstra; Derek Karssenberg; Arjan Van Dijk; Steven M. De Jong

2012-11-01T23:59:59.000Z

17

ANS 2006 WINTER MEETING & Nuclear Technology Expo  

E-Print Network (OSTI)

ANS 2006 WINTER MEETING & Nuclear Technology Expo "Ensuringthe (TOFE) 5th International Topical Meeting on Nuclear Plant Instrumentation, Controls, and Human Machine for their support of the 2006 ANS Winter Meeting & Nuclear Technology Expo; Embedded Topical Meeting: TOFE 2006

Krings, Axel W.

18

The Governance of Nuclear Technology  

SciTech Connect

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.

Vergino, E S; May, M

2003-09-22T23:59:59.000Z

19

Nuclear Energy Enabling Technologies | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Enabling Technologies Enabling Technologies Nuclear Energy Enabling Technologies Nuclear Energy Enabling Technologies The Nuclear Energy Enabling Technologies (NEET) Program will develop crosscutting technologies that directly support and complement the Department of Energy, Office of Nuclear Energy's (DOE-NE) advanced reactor and fuel cycle concepts, focusing on innovative research that offers the promise of dramatically improved performance. NEET will coordinate research efforts on common issues and challenges that confront the DOE-NE R&D programs (Light Water Reactor Sustainability [LWRS], Next Generation Nuclear Plant [NGNP], Advanced Reactor Technologies [ART], and Small Modular Reactors [SMR]) to advance technology development and deployment. The activities undertaken in the NEET program will

20

Preventing Proliferation of Nuclear Materials and Technology...  

National Nuclear Security Administration (NNSA)

Preventing Proliferation of Nuclear Materials and Technology | National Nuclear Security Administration Facebook Twitter Youtube Flickr RSS People Mission Managing the Stockpile...

Note: This page contains sample records for the topic "nuclear filter technology" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


21

Geothermal: Sponsored by OSTI -- Nuclear Technology Division...  

Office of Scientific and Technical Information (OSTI)

Nuclear Technology Division annual progress report for period ending June 30, 1973 Geothermal Technologies Legacy Collection HelpFAQ | Site Map | Contact Us | Admin Log On Home...

22

Nuclear Power Technology: A Mandate for Change  

Science Journals Connector (OSTI)

Technical Paper / NSF Workshop on the Research Needs of the Next Generation Nuclear Power Technology / Fission Reactor

Kunmo Chung; George A. Hazelrigg

23

ADVANCED NUCLEAR TRANSFORMATION TECHNOLOGY SUBCOMMITTEE  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Report of Report of ADVANCED NUCLEAR TRANSFORMATION TECHNOLOGY SUBCOMMITTEE of the NUCLEAR ENERGY RESEARCH ADVISORY COMMITTEE 24 October 2003 BURTON RICHTER, CHAIR DARLEANE C. HOFFMAN SEKAZI K. MTINGWA RONALD P. OMBERG SILVIE PILLON JOY L. REMPE I. INTRODUCTION AND SUMMARY The committee met in Washington on September 16 and 17 to review progress in the program with respect to a changed set of mission priorities. Our last meeting took place in December 2002 after the reorganization that had placed the Advanced Fuel Cycle Initiative (AFCI) and the GEN IV program together in the Advanced Nuclear Research Office (AN-20). Since mission priorities have been evolving, the committee felt that it should wait until they have settled down before we met again. We have kept in touch

24

Production Technology | National Nuclear Security Administration  

National Nuclear Security Administration (NNSA)

Production Technology | National Nuclear Security Administration Production Technology | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Continuing Management Reform Countering Nuclear Terrorism About Us Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Media Room Congressional Testimony Fact Sheets Newsletters Press Releases Speeches Events Social Media Video Gallery Photo Gallery NNSA Archive Federal Employment Apply for Our Jobs Our Jobs Working at NNSA Blog Production Technology Home > About Us > Our Programs > Defense Programs > Future Science & Technology Programs > Production Technology Production Technology NNSA continues to assure the safety, security, and reliability of the

25

Light Water Reactors Technology Development - Nuclear Reactors  

NLE Websites -- All DOE Office Websites (Extended Search)

Light Water Reactors Light Water Reactors About Director's Welcome Organization Achievements Highlights Fact Sheets, Brochures & Other Documents Multimedia Library Visit Argonne Work with Argonne Contact us Nuclear Energy Why Nuclear Energy? Why are some people afraid of Nuclear Energy? How do nuclear reactors work? Cheaper & Safer Nuclear Energy Helping to Solve the Nuclear Waste Problem Nuclear Reactors Nuclear Reactors Early Exploration Training Reactors Basic and Applied Science Research LWR Technology Development BORAX-III lighting Arco, Idaho (Press Release) Heavy Water and Graphite Reactors Fast Reactor Technology Integral Fast Reactor Argonne Reactor Tree CP-1 70th Anniversary CP-1 70th Anniversary Argonne's Nuclear Science and Technology Legacy Argonne's Nuclear Science and Technology Legacy

26

Massachusetts Institute of Technology Department of Nuclear Engineering  

E-Print Network (OSTI)

Massachusetts Institute of Technology Department of Nuclear Engineering Advanced Reactor Technology of Technology Department of Nuclear Engineering Advanced Reactor Technology Pebble Bed Project MPBR-2 Student Department of Nuclear Engineering Advanced Reactor Technology Pebble Bed Project MPBR-3 Project Objective

27

Nuclear Science and Technology Division - Home page  

NLE Websites -- All DOE Office Websites (Extended Search)

image image image - mural in bldg 5200 image image Fuels, Isotopes, and Nuclear Materials image Fuels, Isotopes, and Nuclear Materials Nuclear System Analysis, Design, and Safety image Nuclear System Analysis, Design, and Safety WELCOME Performing basic and applied R&D for the Department of Energy, the National Nuclear Security Administration, and other government agencies, as well as supporting and leveraging industrial partnerships Mission Statement The Nuclear Science and Technology Division at Oak Ridge National Laboratory will provide leading-edge science, technology, and engineering research that support our Nation's nuclear science and technology enterprise across a broad spectrum of applications including but not limited to advanced nuclear power systems, nuclear medicine,and nuclear

28

Summary, Long-Term Nuclear Technology Research and Development...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Summary, Long-Term Nuclear Technology Research and Development Plan Summary, Long-Term Nuclear Technology Research and Development Plan In 1998, DOE established the Nuclear Energy...

29

Nuclear Physics Technology Saves Lives | Jefferson Lab  

NLE Websites -- All DOE Office Websites (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...

30

Nuclear technology for the year 2000  

SciTech Connect

Eighteen papers and abstracts are presented under the following session headings: space nuclear power, health physics and dosimetry, nuclear design and thermal hydraulics, nuclear diagnostics, and fusion technology and plasma physics. The papers were processed separately for the data base. (DLC)

Not Available

1987-01-01T23:59:59.000Z

31

Evaluation of Oil Bypass Filter Technology on Heavy-Duty Vehicles  

NLE Websites -- All DOE Office Websites (Extended Search)

(Advanced Vehicle Testing Activity) (Advanced Vehicle Testing Activity) Evaluation of Oil Bypass Filter Technology on Heavy-Duty Vehicles James Francfort American Filtration and Separations Society April 2005 Presentation Outline * Background & Objectives * Oil bypass filters - features & reported benefits * INL testing method * puraDYN oil bypass filters * Refined Global Solutions (RGS) oil bypass filters * Testing results & trends * Particulate and ferrography testing * Initial INL Oil Bypass Filter Economics * Potential fleet oil savings * Testing Status Bypass Filter Evaluation - Background * Funded by the U.S. Department of Energy's FreedomCAR & Vehicle Technologies Program (Advanced Vehicle Testing Activity) * Vehicles operated by Idaho National Laboratory's Fleet Operations group * Idaho National Laboratory

32

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

Office of Environmental Management (EM)

Fostering the Next Generation of Nuclear Energy Technology Fostering the Next Generation of Nuclear Energy Technology September 29, 2014 - 11:06am Addthis Fostering the Next...

33

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

Office of Environmental Management (EM)

Energy Department Invests 67 Million to Advanced Nuclear Technology Energy Department Invests 67 Million to Advanced Nuclear Technology August 20, 2014 - 12:00pm Addthis News...

34

Nuclear Separations Technologies Workshop Report 2011  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

i i NUCLEAR SEPARATIONS TECHNOLOGIES WORKSHOP REPORT November 7, 2011 FINAL TABLE OF CONTENTS Acronyms and Initialisms............................................................................................................ iii Executive Summary ...................................................................................................................... 1 1. Introduction ............................................................................................................................. 9 1.1 Overview .......................................................................................................................... 9 1.2 Background .................................................................................................................... 10

35

Nuclear Reactor Technologies | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Reactor Technologies Reactor Technologies Nuclear Reactor Technologies TVA Watts Bar Nuclear Power Plant | Photo courtesy of Tennessee Valley Authority TVA Watts Bar Nuclear Power Plant | Photo courtesy of Tennessee Valley Authority Nuclear power has reliably and economically contributed almost 20% of electrical generation in the United States over the past two decades. It remains the single largest contributor (more than 70%) of non-greenhouse-gas-emitting electric power generation in the United States. Small Modular Reactor Technologies Small modular reactors can also be made in factories and transported to sites where they would be ready to "plug and play" upon arrival, reducing both capital costs and construction times. The smaller size also makes these reactors ideal for small electric grids and for locations that

36

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

NLE Websites -- All DOE Office Websites (Extended Search)

Demonstrated Petroleum Demonstrated Petroleum Reduction Using Oil Bypass Filter Technology on Heavy and Light Vehicles James Francfort (PI) Timothy Murphy Larry Zirker Oil Bypass Filter Technology Evaluation * Funded by the U.S. Department of Energy's FreedomCAR & Vehicle Technologies Program * Performed by Idaho National Engineering and Environmental Laboratory (INEEL) Fleet Operations * Goal - Support DOE's efforts to reduce petroleum consumption & ensure the energy security of the United States Oil Bypass Filter Technology Evaluation * Objectives - Test the concept of using oil bypass filters to minimize engine oil changes & the generation of waste oils - Demonstration the economics of oil bypass filter systems - Estimate potential engine oil saving from bypass filter technologies that can be achieved by INEEL,

37

Nuclear Fuel Cycle and Waste Management Technologies - Nuclear Engineering  

NLE Websites -- All DOE Office Websites (Extended Search)

Nuclear Fuel Cycle and Nuclear Fuel Cycle and Waste Management Technologies Nuclear Fuel Cycle and Waste Management Technologies Overview Modeling and analysis Unit Process Modeling Mass Tracking System Software Waste Form Performance Modeling Safety Analysis, Hazard and Risk Evaluations Development, Design, Operation Overview Systems and Components Development Expertise System Engineering Design Other Major Programs Work with Argonne Contact us For Employees Site Map Help Join us on Facebook Follow us on Twitter NE Division on Flickr Nuclear Fuel Cycle and Waste Management Technologies Overview Bookmark and Share Much of the NE Division's research is directed toward developing software and performing analyses, system engineering design, and experiments to support the demonstration and optimization of the electrometallurgical

38

Spent Nuclear Fuel Alternative Technology Decision Analysis  

SciTech Connect

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.

Shedrow, C.B.

1999-11-29T23:59:59.000Z

39

The Magnetic Centrifugal Mass Filter  

SciTech Connect

Mass filters using rotating plasmas have been considered for separating nuclear waste and spent nuclear fuel. We propose a new mass filter that utilizes 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. This filter is collisional and produces well confined output streams, among other advantages. __________________________________________________

Abraham J. Fetterman and Nathaniel J. Fisch

2011-08-04T23:59:59.000Z

40

Nuclear medicine technology and techniques  

SciTech Connect

The book is separated into two sections approximately equal in length. Basic sciences are well represented with chapters on mathematics, physics, instrumentation, laboratory sciences, radiopharmacy, radiation safety and computer science. The section on clinical nuclear medicine contains 12 chapters, ranging in length from 5 to 37 pages and covering all organ systems, the previously mentioned patient care and pediatric imaging chapters, radioimmunoassay, and a chapter devoted to inflammatory disease and tumor imaging.

Bernier, D.L.; Langan, J.K.; Wells, L.D. (eds.)

1981-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear filter technology" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


41

Fuel Cycle Science & Technology | Nuclear Science | ORNL  

NLE Websites -- All DOE Office Websites (Extended Search)

Advanced Fuel Cycle Systems Radiochemical Separation & Processing Recycle & Waste Management Uranium Enrichment Used Nuclear Fuel Storage, Transportation, and Disposal Fusion Nuclear Science Isotope Development and Production Nuclear Security Science & Technology Nuclear Systems Modeling, Simulation & Validation Nuclear Systems Technology Reactor Technology Nuclear Science Home | Science & Discovery | Nuclear Science | Research Areas | Fuel Cycle Science & Technology SHARE Fuel Cycle Science and Technology The ORNL expertise and experience across the entire nuclear fuel cycle is underpinned by extensive facilities and a comprehensive modeling and simulation capability ORNL supports the understanding, development, evaluation and deployment of

42

Nuclear technologies for Moon and Mars exploration  

SciTech Connect

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.

Buden, D.

1991-01-01T23:59:59.000Z

43

Nuclear Power Technology for the Future  

SciTech Connect

Ensuring sufficient energy for electricity, fresh water and transportation represents a major challenge for this century. Energy demand will increase dramatically as developing countries improve their standards of living. Nuclear power will become an increasingly important source of energy for production of electricity, fresh water and hydrogen as transportation fuel. Hydrocarbon sources of energy are not acceptable in the long term because of global warming and uneven supply. To ensure that nuclear power can meet this challenge, improved technologies are required to address the problems of nuclear waste, management of nuclear materials and safety as many more nuclear plants are built. These technologies are being developed at Argonne National Laboratory as part of the DOE international program of Generation IV reactors. Essential to meeting these challenges is the development of fast-spectrum nuclear reactors for which fuel and fission products are recycled to the reactor to be 'burned'. I will discuss work on fast-spectrum reactor and fuel-cycle design. The technologies discussed will be 'passively safe' reactor design and 'pyroprocessing' for fuel reprocessing.

Sackett, John I. (ANL) [ANL

2003-07-23T23:59:59.000Z

44

Review of Current Nuclear Vacuum System Technologies  

SciTech Connect

Nearly all industrial operations generate unwanted dust, particulate matter, and/or liquid wastes. Waste dust and particulates can be readily tracked to other work locations, and airborne particulates can be spread through ventilation systems to all locations within a building, and even vented outside the building - a serious concern for processes involving hazardous, radioactive, or nuclear materials. Several varieties of vacuum systems have been proposed and/or are commercially available for clean up of both solid and liquid hazardous and nuclear materials. A review of current technologies highlights both the advantages and disadvantages of the various systems, and demonstrates the need for a system designed to address issues specific to hazardous and nuclear material cleanup. A review of previous and current hazardous/nuclear material cleanup technologies is presented. From simple conventional vacuums modified for use in industrial operations, to systems specifically engineered for such purposes, the advantages and disadvantages are examined in light of the following criteria: minimal worker exposure; minimal secondary waste generation;reduced equipment maintenance and consumable parts; simplicity of design, yet fully compatible with all waste types; and ease of use. The work effort reviews past, existing and proposed technologies in light of such considerations. Accomplishments of selected systems are presented, including identified areas where technological improvements could be suggested.

Carroll, M.; McCracken, J.; Shope, T.

2003-02-25T23:59:59.000Z

45

Virtual active filters for HVDC networks using V2G technology F.R. Islam  

E-Print Network (OSTI)

Virtual active filters for HVDC networks using V2G technology F.R. Islam , H.R. Pota School 23 July 2013 Keywords: Power system HVDC Active filter PHEV V2G a b s t r a c t Active and passive filters are essential to maintain the power quality of a HVDC link. In this paper the Vehicle to Grid (V2G

Pota, Himanshu Roy

46

Reactors: Modern-Day Alchemy - Argonne's Nuclear Science and Technology  

NLE Websites -- All DOE Office Websites (Extended Search)

Achievements > Achievements > Legacy > Reactors: Modern-Day Alchemy About Director's Welcome Organization Achievements Highlights Fact Sheets, Brochures & Other Documents Multimedia Library Visit Argonne Work with Argonne Contact us Nuclear Energy Why Nuclear Energy? Why are some people afraid of Nuclear Energy? How do nuclear reactors work? Cheaper & Safer Nuclear Energy Helping to Solve the Nuclear Waste Problem Nuclear Reactors Nuclear Reactors Early Exploration Training Reactors Basic and Applied Science Research LWR Technology Development BORAX-III lighting Arco, Idaho (Press Release) Heavy Water and Graphite Reactors Fast Reactor Technology Integral Fast Reactor Argonne Reactor Tree CP-1 70th Anniversary CP-1 70th Anniversary Argonne's Nuclear Science and Technology Legacy

47

Education: The Effort Is Global - Argonne's Nuclear Science and Technology  

NLE Websites -- All DOE Office Websites (Extended Search)

Achievements > Achievements > Argonne Reactors > Education: The Effort Is Global About Director's Welcome Organization Achievements Highlights Fact Sheets, Brochures & Other Documents Multimedia Library Visit Argonne Work with Argonne Contact us Nuclear Energy Why Nuclear Energy? Why are some people afraid of Nuclear Energy? How do nuclear reactors work? Cheaper & Safer Nuclear Energy Helping to Solve the Nuclear Waste Problem Nuclear Reactors Nuclear Reactors Early Exploration Training Reactors Basic and Applied Science Research LWR Technology Development BORAX-III lighting Arco, Idaho (Press Release) Heavy Water and Graphite Reactors Fast Reactor Technology Integral Fast Reactor Argonne Reactor Tree CP-1 70th Anniversary CP-1 70th Anniversary Argonne's Nuclear Science and Technology Legacy

48

Improved Technology To Prevent Nuclear Proliferation And Counter Nuclear Terrorism  

SciTech Connect

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.

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

2006-06-12T23:59:59.000Z

49

V2G Technology for Designing Active Filter System to Improve Wind Power Quality  

E-Print Network (OSTI)

V2G Technology for Designing Active Filter System to Improve Wind Power Quality F. R. Islam, H. R factor correction and harmonics current compensation. Index Terms--PHEVs, V2G, Wind Power, Battery Scheme to design active filter is proposed here to improve the quality of wind power output. Harmonics is one

Pota, Himanshu Roy

50

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

E-Print Network (OSTI)

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

Abdou, Mohamed

51

NUCLEAR SCIENCE AND TECHNOLOGY DIVISION OAK RIDGE NATIONAL LABORATORY  

E-Print Network (OSTI)

NUCLEAR SCIENCE AND TECHNOLOGY DIVISION OAK RIDGE NATIONAL LABORATORY U.S. DEPARTMENT OF ENERGY-27, 2004 CERN Geneva, Switzerland #12;NUCLEAR SCIENCE AND TECHNOLOGY DIVISION OAK RIDGE NATIONAL LABORATORY Experience Installing New Equipment 路 Conclusions #12;NUCLEAR SCIENCE AND TECHNOLOGY DIVISION OAK RIDGE

McDonald, Kirk

52

NUCLEAR SCIENCE AND TECHNOLOGY DIVISION OAK RIDGE NATIONAL LABORATORY  

E-Print Network (OSTI)

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;3 NUCLEAR SCIENCE AND TECHNOLOGY DIVISION OAK RIDGE NATIONAL LABORATORY U.S. DEPARTMENT OF ENERGY Properties

McDonald, Kirk

53

(Nuclear power plant control and instrumentation technology)  

SciTech Connect

While on vacation, the traveler attended the European Nuclear Conference in Lyon, France. This trip was part of an outside activity approved by DOE. The traveler is a consultant to Loyola College, serving as chairman of a panel to assess the state of the art in the controls and instrumentation technology in the European nuclear community. This study is being conducted by Loyola College under subcontract to the National Science Foundation. The traveler was surprised by the level of automation claimed (by the company Siemens AG KWU) to be present in the German Konvoi nuclear power plants. The claim was that this was done to improve the safety of the plant by keeping the operator out of the loop'' for the first 30 minutes of some transients or accidents.

White, J.D.

1990-10-10T23:59:59.000Z

54

Report, Long-Term Nuclear Technology Research and Development Plan |  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Report, Long-Term Nuclear Technology Research and Development Plan Report, Long-Term Nuclear Technology Research and Development Plan Report, Long-Term Nuclear Technology Research and Development Plan This document constitutes the first edition of a long-term research and development (R&D) plan for nuclear technology in the United States. The federally-sponsored nuclear technology programs of the United States are almost exclusively the province of the U.S. Department of Energy (DOE). The nuclear energy areas in DOE include, but are not limited to, R&D related to power reactors and the responsibility for the waste management system for final disposition of the spent fuel resulting from nuclear power reactors. Although a major use of nuclear technology is to supply energy for electricity production, the DOE has far broader roles regarding nuclear

55

Advanced Particulate Filter Technologies for Direct Injection Gasoline Engine Applications  

Energy.gov (U.S. Department of Energy (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

56

Freeze Technology for Nuclear Applications - 13590  

SciTech Connect

Freezing of soil materials is a complicated process of a number of physical processes: - freezing of pore water in a thermal gradient, - cryogenic suction causing water migration and - ice formation expanding pores inducing frost heave. Structural changes due to increase of effective stress during freezing also take place. The over consolidation gives a powerful dewatering/drying effect and the freeze process causes separation of contaminates. Artificial ground freezing (AGF is a well established technique first practiced in south Wales, as early as 1862. AGF is mostly used to stabilize tunnels and excavations. During the last ten years underwater applications of freeze technologies based on the AGF have been explored in Sweden. The technology can, and has been, used in many different steps in a remediation action. Freeze Sampling where undisturbed samples are removed in both soft and hard sediment/sludge, Freeze Dredging; retrieval of sediment with good precision and minimal redistribution, and Freeze Drying; volume reduction of contaminated sludge/sediment. The application of these technologies in a nuclear or radioactive environment provides several advantages. Sampling by freezing gives for example an advantage of an undisturbed sample taken at a specified depth, salvaging objects by freezing or removal of sludges is other applications of this, for the nuclear industry, novel technology. (authors)

Rostmark, Susanne C.; Knutsson, Sven [Lulea University of Technology (Sweden)] [Lulea University of Technology (Sweden); Lindberg, Maria [Studsvik Nuclear AB, 611 82 Nykoeping (Sweden)] [Studsvik Nuclear AB, 611 82 Nykoeping (Sweden)

2013-07-01T23:59:59.000Z

57

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

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

DEER Conference, 2004 Sougato Chatterjee, Ray Conway, Satish Viswanathan, Todd Jacobs Johnson Matthey Catalysts Environmental Catalysts & Technologies Outline * Introduction * CRT...

58

Nuclear Separations Technologies Workshop Report | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Nuclear Separations Technologies Workshop Report Nuclear Separations Technologies Workshop Report Nuclear Separations Technologies Workshop Report The Department of Energy (DOE) sponsored a workshop on nuclear separations technologies in Bethesda, Maryland, on July 27 and 28, 2011, to (1) identify common needs and potential requirements in separations technologies and opportunities for program partnerships, and (2) evaluate the need for a DOE nuclear separations center of knowledge to improve cross- program collaboration in separations technology. The workshop supported Goal 3 of the DOE Strategic Plan1 to enhance nuclear security through defense, nonproliferation, and environmental management. The Office of Environmental Management (EM), Office of Nuclear Energy (NE), and National Nuclear Security Administration (NNSA) jointly sponsored the workshop. The Office of Science

59

The Italian Navigator Lands - Argonne's Nuclear Science and Technology  

NLE Websites -- All DOE Office Websites (Extended Search)

The Italian Navigator Lands The Italian Navigator Lands About Director's Welcome Organization Achievements Highlights Fact Sheets, Brochures & Other Documents Multimedia Library Visit Argonne Work with Argonne Contact us Nuclear Energy Why Nuclear Energy? Why are some people afraid of Nuclear Energy? How do nuclear reactors work? Cheaper & Safer Nuclear Energy Helping to Solve the Nuclear Waste Problem Nuclear Reactors Nuclear Reactors Early Exploration Training Reactors Basic and Applied Science Research LWR Technology Development BORAX-III lighting Arco, Idaho (Press Release) Heavy Water and Graphite Reactors Fast Reactor Technology Integral Fast Reactor Argonne Reactor Tree CP-1 70th Anniversary CP-1 70th Anniversary Argonne's Nuclear Science and Technology Legacy Argonne's Nuclear Science and Technology Legacy

60

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

SciTech Connect

Sensor data validity is extremely important in a number of applications, particularly building technologies where collected data are used to determine performance. An example of this is Oak Ridge National Laboratory s ZEBRAlliance research project, which consists of four single-family homes located in Oak Ridge, TN. The homes are outfitted with a total of 1,218 sensors to determine the performance of a variety of different technologies integrated within each home. Issues arise with such a large amount of sensors, such as missing or corrupt data. This paper aims to eliminate these problems using: (1) Kalman filtering and (2) linear prediction filtering techniques. Five types of data are the focus of this paper: (1) temperature; (2) humidity; (3) energy consumption; (4) pressure; and (5) airflow. Simulations show the Kalman filtering method performed best in predicting temperature, humidity, pressure, and airflow data, while the linear prediction filtering method performed best with energy consumption data.

Castello, Charles C [ORNL] [ORNL; New, Joshua Ryan [ORNL] [ORNL; Smith, Matt K [ORNL] [ORNL

2013-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear filter technology" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


61

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.E. FINAN, K. MIU, A.C. KADAK Massachusetts Institute of Technology Department of Nuclear Science the technical aspects and the economics of utilizing nuclear reactors to provide the energy needed

62

Nuclear Safety R&D in the Waste Processing Technology Development & Deployment Program  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

R&D in the Waste Processing R&D in the Waste Processing Technology Development & Deployment Program Presentation to the DOE High Level Waste Corporate Board July 29, 2009 Al 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 February 2009 Evaluating Performance of Nuclear Grade HEPA Filters under Fire/Smoke Challenge Conditions Structural Integrity Initiative for HLW Tanks Pipeline Plugging and Prevention Advanced Mixing Models Basic Science Opportunities in HLW Storage and Processing Safety Cementitious Barriers Partnership 3 Nuclear Safety Research & Development Overview DNFSB 2004-1 identified need for renewed DOE attention to nuclear safety R&D

63

Thomas Miller Office of Nuclear Energy, Science and Technology  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Miller Miller Office of Nuclear Energy, Science and Technology U.S. Department of Energy September 30, 2002 Presentation at the Nuclear Energy Research Advisory Committee Nuclear Power 2010 Program Strategy to Deploy New Nuclear Power Plants Nuclear Power 2010 Program Strategy to Deploy New Nuclear Power Plants Office of Nuclear Energy, Science and Technology TMiller/Sept11_02 ESE Project.ppt ( 2) Nuclear Power 2010: Overview Nuclear Power 2010: Overview Goal 6 Achieve industry decision by 2005 to deploy at least one new advanced nuclear power plant by 2010 Cooperative Activities 6 Regulatory Demonstration Projects * Early Site Permit (ESP) * Combined Construction and Operating License (COL) 6 Reactor Technology Development Projects * NRC Design Certification (DC) * First-of-a-kind engineering for a standardized plant

64

March 2006, Report of the ADVANCED NUCLEAR TRANSFORMATION TECHNOLOGY  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

March 2006, Report of the ADVANCED NUCLEAR TRANSFORMATION March 2006, Report of the ADVANCED NUCLEAR TRANSFORMATION TECHNOLOGY SUBCOMMITTEE of the NUCLEAR ENERGY RESEARCH ADVISORY COMMITTEE March 2006, Report of the ADVANCED NUCLEAR TRANSFORMATION TECHNOLOGY SUBCOMMITTEE of the NUCLEAR ENERGY RESEARCH ADVISORY COMMITTEE 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 reduce the problem of nuclear waste treatment and to reduce the proliferation risk in a world with a greatly expanded nuclear power program. It brings the U.S. program into much closer alignment with that of the other major nuclear energy states. GNEP proposes to take spent fuel from existing light water reactors (LWRs),

65

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

E-Print Network (OSTI)

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

Sheridan, Scott

66

Oil Bypass Filter Technology Evaluation Eleventh Quarterly Report April- June 2005  

NLE Websites -- All DOE Office Websites (Extended Search)

651 651 U.S. Department of Energy FreedomCAR & Vehicle Technologies Program Oil Bypass Filter Technology Evaluation Eleventh Quarterly Report April-June 2005 TECHNICAL REPORT Larry Zirker James Francfort Jordan Fielding September 2005 Idaho National Laboratory Operated by Battelle Energy Alliance INL/EXT-05-00651 U.S. Department of Energy FreedomCAR & Vehicle Technologies Program Oil Bypass Filter Technology Evaluation Eleventh Quarterly Report April-June 2005 Larry Zirker James Francfort Jordan Fielding September 2005 Idaho National Laboratory Transportation Technology Department Idaho Falls, Idaho 83415 Prepared for the U.S. Department of Energy Assistant Secretary for Energy Efficiency and Renewable Energy Under DOE Idaho Operations Office

67

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

Office of Scientific and Technical Information (OSTI)

June 2014 Most Viewed Documents for Fission And Nuclear Technologies Behavior of spent nuclear fuel in water pool storage Johnson, A.B. Jr. (1977) 78 Estimation of gas leak rates...

68

Nuclear Separations Technologies Workshop Report | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Separations Technologies Workshop Report Separations Technologies Workshop Report Nuclear Separations Technologies Workshop Report The Department of Energy (DOE) sponsored a workshop on nuclear separations technologies in Bethesda, Maryland, on July 27 and 28, 2011, to (1) identify common needs and potential requirements in separations technologies and opportunities for program partnerships, and (2) evaluate the need for a DOE nuclear separations center of knowledge to improve cross- program collaboration in separations technology. The workshop supported Goal 3 of the DOE Strategic Plan1 to enhance nuclear security through defense, nonproliferation, and environmental management. The Office of Environmental Management (EM), Office of Nuclear Energy (NE), and National Nuclear Security Administration (NNSA) jointly sponsored the workshop. The Office of Science

69

Security Science & Technology | Nuclear Science | ORNL  

NLE Websites -- All DOE Office Websites (Extended Search)

Consequence Management, Safeguards, and Non-Proliferation Tools Export Control Human Reliability International Collaborations on Nuclear Safeguards Nuclear Forensics Radiation...

70

Oil Bypass Filter Technology Evaluation, Fourth Quarterly Report, July--September 2003  

SciTech Connect

This fourth Oil Bypass Filter Technology Evaluation report 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抯 FreedomCAR & Vehicle Technologies Program. Eight four-cycle diesel-engine buses used to transport INEEL employees on various routes have been equipped with oil bypass filter systems from the puraDYN Corporation. The bypass filters are reported to have engine oil filtering capability of <1 micron and a built-in additive package to facilitate extended oil-drain intervals. To date, the eight buses have accumulated 259,398 test miles. This represents an avoidance of 21 oil changes, which equates to 740 quarts (185 gallons) of oil not used or disposed of. To validate the extended oil-drain intervals, an oil-analysis regime evaluates the fitness of the oil for continued service by monitoring the presence of necessary additives, undesirable contaminants, and engine-wear metals. For bus 73450, higher values of iron have been reported, but the wear rate ratio (parts per million of iron per thousand miles driven) has remained consistent. In anticipation of also evaluating oil bypass systems on six Chevrolet Tahoe sport utility vehicles, the oil is being sampled on each of the Tahoes to develop a characterization history or baseline for each engine.

James E. Francfort; Larry Zirker

2003-11-01T23:59:59.000Z

71

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

National Nuclear Security Administration (NNSA)

National Security Technologies, LLC, PER Summary | National Nuclear National Security Technologies, LLC, PER Summary | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Continuing Management Reform Countering Nuclear Terrorism About Us Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Media Room Congressional Testimony Fact Sheets Newsletters Press Releases Speeches Events Social Media Video Gallery Photo Gallery NNSA Archive Federal Employment Apply for Our Jobs Our Jobs Working at NNSA Blog FY 2011 National Security Technologies, LLC, PER Summary Home > About Us > Our Operations > Acquisition and Project Management > Performance Evaluations > FY 2011 National Security Technologies, LLC, PER

72

FY 2007 National Security Technologies, LLC, PER Summary | National Nuclear  

National Nuclear Security Administration (NNSA)

National Security Technologies, LLC, PER Summary | National Nuclear National Security Technologies, LLC, PER Summary | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Continuing Management Reform Countering Nuclear Terrorism About Us Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Media Room Congressional Testimony Fact Sheets Newsletters Press Releases Speeches Events Social Media Video Gallery Photo Gallery NNSA Archive Federal Employment Apply for Our Jobs Our Jobs Working at NNSA Blog FY 2007 National Security Technologies, LLC, PER Summary Home > About Us > Our Operations > Acquisition and Project Management > Performance Evaluations > FY 2007 National Security Technologies, LLC, PER

73

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

National Nuclear Security Administration (NNSA)

National Security Technologies, LLC, PER Summary | National Nuclear National Security Technologies, LLC, PER Summary | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Continuing Management Reform Countering Nuclear Terrorism About Us Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Media Room Congressional Testimony Fact Sheets Newsletters Press Releases Speeches Events Social Media Video Gallery Photo Gallery NNSA Archive Federal Employment Apply for Our Jobs Our Jobs Working at NNSA Blog FY 2009 National Security Technologies, LLC, PER Summary Home > About Us > Our Operations > Acquisition and Project Management > Performance Evaluations > FY 2009 National Security Technologies, LLC, PER

74

Hot demonstrations of nuclear-waste processing technologies  

Science Journals Connector (OSTI)

Several types of nuclear-waste-treatment technologies are currently being demonstrated at Argonne National Laboratory-West, ranging from complex,...

H. F. McFarlane; K. M. Goff; F. S. Felicione; C. C. Dwight; D. B. Barber

1997-07-01T23:59:59.000Z

75

University Program in Advanced Technology | National Nuclear Security  

National Nuclear Security Administration (NNSA)

University Program in Advanced Technology | National Nuclear Security University Program in Advanced Technology | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Continuing Management Reform Countering Nuclear Terrorism About Us Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Media Room Congressional Testimony Fact Sheets Newsletters Press Releases Speeches Events Social Media Video Gallery Photo Gallery NNSA Archive Federal Employment Apply for Our Jobs Our Jobs Working at NNSA Blog University Program in Advanced Technology Home > About Us > Our Programs > Defense Programs > Future Science & Technology Programs > Office of Advanced Simulation and Computing and

76

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

E-Print Network (OSTI)

and commercial buildings consume 41% of primary energy (72% electricity) used in the U.S. 路 Retrofitting inefficient buildings with new and innovative technologies that help to curb energy consumption will reduce filters. 路 Specifically, temperature, humidity, energy usage, pressure, and airflow sensor data is used

Wang, Xiaorui "Ray"

77

Oil Bypass Filter Technology Evaluation Ninth Quarterly Report October朌ecember 2004  

SciTech Connect

This Oil Bypass Filter Technology Evaluation quarterly report (October朌ecember 2004) details the ongoing fleet evaluation of oil bypass filter technologies being conducted by the Idaho National Laboratory (INL; formerly Idaho National Engineering and Environmental Laboratory) for the U.S. Department of Energy抯 FreedomCAR & Vehicle Technologies Program. Eight INL four-cycle diesel-engine buses used to transport INL employees on various routes and six INL Chevrolet Tahoes with gasoline engines are equipped with oil bypass filter systems from the puraDYN Corporation. This quarter, three additional buses were equipped with bypass filters from Refined Global Solutions. Oil bypass filters are reported to have an engine oil filtering capability of less than 1 micron. Both the puraDYN and Refined Global Solutions bypass filters have a heating chamber to remove liquid contaminate from the oil. During the quarter, the eleven diesel engine buses traveled 62,188 miles, and as of January 3, 2005 the buses had accumulated 643,036 total test miles. Two buses had their engine oil changed this quarter. In one bus, the oil was changed due to its degraded quality as determined by a low total base number (<3.0 mg KOH/g). The other bus had high oxidation and nitration numbers (>30.0 Abs/cm). Although a total of six buses have had their oil changed during the last 26 months, by using the oil bypass filters the buses in the evaluation avoided 48 oil changes, which equates to 1,680 quarts (420 gallons) of new oil not consumed and 1,680 quarts of waste oil not generated. Therefore, over 80% of the oil normally required for oil-changes was not used, and, consequently, the evaluation achieved over 80% reduction in the amount of waste oil normally generated. The six Tahoe test vehicles traveled 39,514 miles, and as of January 3, 2005 the Tahoes had accumulated 189,970 total test miles. The Tahoe filter test is in transition. To increase the rate of bypass filter oil flow on the Tahoes, puraDYN provided a larger orifice assembly, and these are being changed out as the Tahoes come in for regular service.

Larry Zirker; James Francfort; Jordan Fielding

2005-02-01T23:59:59.000Z

78

January 2003, Report of the ADVANCED NUCLEAR TRANSFORMATION TECHNOLOGY  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

January 2003, Report of the ADVANCED NUCLEAR TRANSFORMATION January 2003, Report of the ADVANCED NUCLEAR TRANSFORMATION TECHNOLOGY SUBCOMMITTEE of the NUCLEAR ENERGY RESEARCH ADVISORY COMMITTEE January 2003, Report of the ADVANCED NUCLEAR TRANSFORMATION TECHNOLOGY SUBCOMMITTEE of the NUCLEAR ENERGY RESEARCH ADVISORY COMMITTEE The ANTT Subcommittee met in Washington on Dec 4-5, 2002 to review progress in the transmutation program, and to learn about major organizational changes that affect the management of the program. The NE's new Advanced Nuclear Research Office (NE-20) now oversees both the transmutation program (ANTT) and the Generation-IV program (GEN-IV). antt14Jan_03.pdf More Documents & Publications October 2003, Report of the ADVANCED NUCLEAR TRANSFORMATION TECHNOLOGY SUBCOMMITTEE of the NUCLEAR ENERGY RESEARCH ADVISORY COMMITTEE

79

The Los Alamos nuclear safeguards and nonproliferation technology development program  

SciTech Connect

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

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

1994-04-01T23:59:59.000Z

80

FY 2012 National Security Technologies, LLC, PEP | National Nuclear  

National Nuclear Security Administration (NNSA)

PEP | National Nuclear PEP | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Continuing Management Reform Countering Nuclear Terrorism About Us Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Media Room Congressional Testimony Fact Sheets Newsletters Press Releases Speeches Events Social Media Video Gallery Photo Gallery NNSA Archive Federal Employment Apply for Our Jobs Our Jobs Working at NNSA Blog FY 2012 National Security Technologies, LLC, PEP Home > About Us > Our Operations > Acquisition and Project Management > Performance Evaluations > FY 2012 National Security Technologies, LLC, PEP FY 2012 National Security Technologies, LLC, PEP

Note: This page contains sample records for the topic "nuclear filter technology" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


81

Idaho Nuclear Technology and Engineering Center Tank Farm Facility |  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Idaho Nuclear Technology and Engineering Center Tank Farm Facility Idaho Nuclear Technology and Engineering Center Tank Farm Facility Idaho Nuclear Technology and Engineering Center Tank Farm Facility The Secretary of Energy signed Section 3116 of the Ronald W. Reagan National Defense Authorization Act for Fiscal Year 2005 basis of determination for the disposal of grouted residual waste in the tank systems at the Idaho Nuclear Technology and Engineering Center (INTEC) Tank Farm Facility (TFF) on November 19, 2006. Section 3116 of the Ronald W. Reagan National Defense Authorization Act for Fiscal Year 2005 authorizes the Secretary of Energy, in consultation with the Nuclear Regulatory Commission, to reclassify certain waste from reprocessing spent nuclear fuel from high-level waste to low-level waste if it meets the criteria set

82

Observations on A Technology Roadmap for Generation IV Nuclear Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Observations on A Technology Roadmap for Generation IV Nuclear Observations on A Technology Roadmap for Generation IV Nuclear Energy Systems: Technical Roadmap Report Observations on A Technology Roadmap for Generation IV Nuclear Energy Systems: Technical Roadmap Report 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 installations in the short term. DOE needs to give those immediate objectives the highest priority and any additional support they require to assure their success. DOE is pursuing two initiatives to encourage a greater use of nuclear energy systems. The initiatives have been reviewed by NERAC Subcommittee on Generation IV Technology Planning (GRNS) and they are: * A Near Term Development (NTD) Roadmap which is in the process of being

83

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

84

Nuclear Science and Technology, November 2000. NEUTRON CROSS SECTION EVALUATIONS  

E-Print Network (OSTI)

Nuclear Science and Technology, November 2000. 1 NEUTRON CROSS SECTION EVALUATIONS FOR 238 U UP and Power Engineering, 249020 Obninsk, Russia A.Ventura ENEA, Nuclear Data Center and INFN, Bologna Section of the statistical description that includes direct, pre-equilibrium and equilibrium mechanisms of nuclear reactions

85

Office of Nuclear Energy, Science and Technology Executive Summary  

E-Print Network (OSTI)

Office of Nuclear Energy, Science and Technology Executive Summary Mission As we become more in this new century, the benefits of nuclear fission as a key energy source for both the near- and long method of generating energy from nuclear fission in both the United States and the world. A key mission

86

Guidance for Deployment of Mobile Technologies for Nuclear Power Plant  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Guidance for Deployment of Mobile Technologies for Nuclear Power Guidance for Deployment of Mobile Technologies for Nuclear Power Plant Field Workers Guidance for Deployment of Mobile Technologies for Nuclear Power Plant Field Workers 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,

87

Technology Readiness Levels for Advanced Nuclear Fuels and Materials Development  

SciTech Connect

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).

Jon Carmack

2014-01-01T23:59:59.000Z

88

New sensor technology detects chemical, biological, nuclear and explosive  

NLE Websites -- All DOE Office Websites (Extended Search)

New New sensor technology detects chemical, biological, nuclear and explosive materials Director's Welcome Organization Achievements Highlights Fact Sheets, Brochures & Other Documents Multimedia Library About Nuclear Energy Nuclear Reactors Designed by Argonne Argonne's Nuclear Science and Technology Legacy Opportunities within NE Division Visit Argonne Work with Argonne Contact us For Employees Site Map Help Join us on Facebook Follow us on Twitter NE on Flickr Celebrating the 70th Anniversary of Chicago Pile 1 (CP-1) Argonne OutLoud on Nuclear Energy Argonne Energy Showcase 2012 Highlights Bookmark and Share New sensor technology detects chemical, biological, nuclear and explosive materials Applications for homeland security, emergency planning Instruments in Argonne's Terahertz Test Facility, such as the one Sami Gopalsami is using, can detect trace chemicals at the part-per-billion level.

89

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...

90

The public perception of hydrogen and nuclear technologies  

Science Journals Connector (OSTI)

Nuclear is the most likely candidate to produce the energy needed for the 21st century. However, the existing negative perception of nuclear power production by most of the population is a problem that hampers the successful development of both nuclear energy and new technologies such as hydrogen energy. Insufficient nuclear erudition is the main reason for distrust of modern nuclear hydrogen production methods. This knowledge deficiency does not give the majority of people the possibility of focusing in a correct way on radiation problems and to estimate accurately the possible damage to the health of a human being from the effects of different radiation sources.

Svetlana V. Vastchenko

2006-01-01T23:59:59.000Z

91

Enertech partners with CCI Thermal Technologies on nuclear filtration  

Science Journals Connector (OSTI)

Curtiss-Wright Flow Control Co's Enertech business unit and CCI Thermal Technologies Inc have signed an agreement to work together to provide heating and filtration solutions and products to the nuclear industry worldwide.

2011-01-01T23:59:59.000Z

92

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

Office of Scientific and Technical Information (OSTI)

July 2013 Most Viewed Documents for Fission And Nuclear Technologies Science Subject Feed Estimation of gas leak rates through very small orifices and channels. From sealed PuO...

93

October 2003, Report of the ADVANCED NUCLEAR TRANSFORMATION TECHNOLOGY  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

3, Report of the ADVANCED NUCLEAR TRANSFORMATION 3, Report of the ADVANCED NUCLEAR TRANSFORMATION TECHNOLOGY SUBCOMMITTEE of the NUCLEAR ENERGY RESEARCH ADVISORY COMMITTEE October 2003, Report of the ADVANCED NUCLEAR TRANSFORMATION TECHNOLOGY SUBCOMMITTEE of the NUCLEAR ENERGY RESEARCH ADVISORY COMMITTEE The committee met in Washington in Sept 16-17 to review progress in the program with respect to a changed set of mission priorities. Our last meeting took place in Dec 2002 after the reorganization that had place the Advanced Fuel Cycle Initiative (AFCI) and GEN IV program together in the Advanced Nuclear Reserach Office (AN-20). Since mission priorities have been evolving, the committee felt that it should wait unti they have settled down before we met again. We have kept in touch during the process,

94

October 2006, Report of the ADVANCED NUCLEAR TRANSFORMATION TECHNOLOGY  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

6, Report of the ADVANCED NUCLEAR TRANSFORMATION 6, Report of the ADVANCED NUCLEAR TRANSFORMATION TECHNOLOGY SUBCOMMITTEE of the NUCLEAR ENERGY RESEARCH ADVISORY COMMITTEE October 2006, Report of the ADVANCED NUCLEAR TRANSFORMATION TECHNOLOGY SUBCOMMITTEE of the NUCLEAR ENERGY RESEARCH ADVISORY COMMITTEE 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 very beginning. At the time the ANTT committee met, August 30- 31, 2006, responses had not yet been received from industry to the DOE's request for Expressions of Interest. This report is based on the assumption that the program outlined recently, which does not include an Advanced Burner Test Reactor, is what

95

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

SciTech Connect

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.

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

2005-01-01T23:59:59.000Z

96

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

E-Print Network (OSTI)

Roadmap: Radiologic Imaging Sciences - Nuclear Medicine (with AAS Radiologic Technology) - Bachelor of Radiologic and Imaging Sciences Technology [RE-BRIT-RIS-NMRT] Regional College Catalog Year: 2012-2013 Page 1 of 2 | Last Updated: 21-May-12/LNHD This roadmap is a recommended semester-by-semester plan of study

Sheridan, Scott

97

Energy: Nuclear Technology Status - Symposium at Northwestern University  

NLE Websites -- All DOE Office Websites (Extended Search)

Nuclear Energy Symposium at Nuclear Energy Symposium at Northwestern University (Oct. 2011) Workshops Nuclear Energy Symposium @ Northwestern University Symposium Overview & Agenda About the Annual Technical Meeting Annual Technical Meeting Information Join us on Facebook Follow us on Twitter 48th Annual Technical Meeting of Society of Engineering Sciences Northwestern University, October 12-14, 2011 | http://ses2011.org/ Bookmark and Share Fluid, Thermal and Energy Track Symposium 2.6, "Energy: Nuclear Energy Technology" Chair: Roger Blomquist Session date: Thursday, Oct 13, 2011 Sixteen papers by world-leading experts in nuclear technology from Argonne National Laboratory will be presented on October 13 at the Annual Technical Meeting of the Society of Engineering Sciences to be held at Northwestern

98

Technologies for detection of nuclear materials  

SciTech Connect

Detection of smuggled nuclear materials at transit points requires monitoring unknown samples in large closed packages. This review contends that high-confidence nuclear-material detection requires induced fission as the primary mechanism, with passive radiation screening in a complementary role. With the right equipment, even small quantities of nuclear materials are detectable with a high probability at transit points. The equipment could also be linked synergistically with detectors of other contrabond. For screening postal mail and packages, passive monitors are probably more cost-effective. When a suspicious item is detected, a single active probe could then be used. Until active systems become mass produced, this two-stage screening/interrogation role for active/passive equipment is more economic for cargo at border crossings. For widespread monitoring of nuclear smuggling, it will probably be necessary to develop a system for simultaneously detecting most categories of contraband, including explosives and illicit drugs. With control of nuclear materials at known storage sites being the first line of defense, detection capabilities at international borders could establish a viable second line of defense against smuggling.

DeVolpi, A.

1996-03-30T23:59:59.000Z

99

Nuclear Energy Enabling Technologies (NEET) Reactor Materials  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Enabling Technologies (NEET) Reactor Materials Enabling Technologies (NEET) Reactor Materials Award Recipient Estimated Award Amount* Award Location Supporting Organizations Project Description University of Nebraska $979,978 Lincoln, NE Massachusetts Institute of Technology (Cambridge, MA), Texas A&M (College Station, TX) Project will explore the development of advanced metal/ceramic composites. These improvements could lead to more efficient production of electricity in advanced reactors. Oak Ridge National Laboratory $849,000 Oak Ridge, TN University of Wisconsin-Madison (Madison, WI) Project will develop novel high-temperature high-strength steels with the help of computational modeling, which could lead to increased efficiency in advanced reactors. Pacific Northwest National Laboratory

100

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)

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.

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

2012-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear filter technology" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


101

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)

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.

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

2012-07-02T23:59:59.000Z

102

Office of Advanced Nuclear Research Office of Nuclear Energy, Science and Technology  

E-Print Network (OSTI)

Integrate applicable work conducted in programs in the Offices of Nuclear Energy (Gen IV, NERI, I 路 FY 2010: Complete the design of a commercial-scale nuclear hydrogen production system 路 FY 2015 to budget uncertainties (risk/benefit) 路 Guide the development of technology to support decisions Develop

103

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

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

PPPL's MINDS Technology Takes Nuclear Detection to the Marketplace PPPL's MINDS Technology Takes Nuclear Detection to the Marketplace PPPL's MINDS Technology Takes Nuclear Detection to the Marketplace October 20, 2011 - 5:25pm Addthis Charles Gentile (center) and other members of the MINDS team, including Ken Silber (right) and Bill Davis (left) work on new techniques to identify radionuclides. | Photo by Elle Starkman/Princeton Plasma Physics Laboratory Office of Communications Charles Gentile (center) and other members of the MINDS team, including Ken Silber (right) and Bill Davis (left) work on new techniques to identify radionuclides. | Photo by Elle Starkman/Princeton Plasma Physics Laboratory Office of Communications April Saylor April Saylor Former Digital Outreach Strategist, Office of Public Affairs What are the key facts?

104

Analysis of nuclear proliferation resistance reprocessing and recycling technologies  

SciTech Connect

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

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

2011-05-01T23:59:59.000Z

105

INSTITUTE OF NUCLEAR TECHNOLOGY RADIATION PROTECTION  

E-Print Network (OSTI)

LABORATORY C. Housiadas Dynamic Reliability of Complex System & Decision Analysis I.A. Papazoglou Laboratory: Research, Development and Services *reports to the Director of the Centre REACTOR SAFETY RADIATION PROTECTION HEALTH & PHYSICS OF THE REACTOR F.Tzika SUPPORT TO GAEC A.G. Youtsos TECHNOLOGICAL

106

A methodology for evaluating ``new`` technologies in nuclear power plants  

SciTech Connect

As obsolescence and spare parts issues drive nuclear power plants to upgrade with new technology (such as optical fiber communication systems), the ability of the new technology to withstand stressors present where it is installed needs to be determined. In particular, new standards may be required to address qualification criteria and their application to the nuclear power plants of tomorrow. This paper discusses the failure modes and age-related degradation mechanisms of fiber optic communication systems, and suggests a methodology for identifying when accelerated aging should be performed during qualification testing.

Korsah, K.; Clark, R.L.; Holcomb, D.E.

1994-06-01T23:59:59.000Z

107

Proceedings of the Nuclear Criticality Technology and Safety Project Workshop  

SciTech Connect

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.

Sanchez, R.G. [comp.

1994-01-01T23:59:59.000Z

108

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 April 2013 Most Viewed Documents for Fission And Nuclear Technologies Behavior of spent nuclear fuel in water pool storage Johnson, A.B. Jr. (null) 298 Estimation of gas leak rates through very small orifices and channels. [From sealed PuO/sub 2/ containers under accident conditions] Bomelburg, H.J. (null) 292 Graphite design handbook Ho, F.H. (1988) 216 System Definition and Analysis: Power Plant Design and Layout NONE (1996) 123 Flow-induced vibration of circular cylindrical structures Chen, S.S. (1985) 116 Stress analysis and evaluation of a rectangular pressure vessel. [For equipment for sampling Hanford tank radwaste] Rezvani, M.A.; Ziada, H.H. (Westinghouse Hanford Co., Richland, WA (United States)); Shurrab, M.S. (Westinghouse Savannah River Co., Aiken, SC (United

109

Zirconium research in nuclear science and technology: a scientometric perspective  

Science Journals Connector (OSTI)

The present study is aimed at analysing the growth of publications on zirconium in nuclear science and technology. International Nuclear Information System (INIS) database is used as a tool to analyse the focused areas of this field for the period 1970-2008. The database contained a total of 65,592 publications on zirconium. The study analysed the broad features of zirconium in nuclear science and technology focusing on its publication growth characteristics such as year-wise distribution of publications, country-wise distribution of publications, country-wise activity index, domain-wise distribution of publications, highly productive institutions, language-wise distribution of publications, distribution of publications by document types and journals preferred for publication by the scientists.

B.S. Kademani; Ganesh Surwase; K. Bhanumurthy

2011-01-01T23:59:59.000Z

110

Important technology considerations for space nuclear power systems  

SciTech Connect

This paper discusses the technology considerations that guide the development of space nuclear power sources (NPS) by the Department of Energy (DOE) to meet a wide variety of applications. The Department and its predecessor agencies have been developing NPS since the 1950s and producing NPS for spacecraft for the National Aeronautics and Space Administration (NASA) and the Department of Defense (DOD) since the early 1960s. No one nuclear power type, isotope or reactor, will suffice over the entire range of mission power required. Nor is one type of power conversion system, be it static or dynamic, the optimum choice of all space nuclear power system applications. There is a need for DOE, in partnership with its users, NASA and DOD, to develop a variety of types of space nuclear power sources -- isotope-static, isotope-dynamic, reactor-static, and reactor-dynamic -- to meet mission requirements well into the next century. 2 figs., 1 tab.

Kuspa, J.P.; Wahlquist, E.J.; Bitz, D.A.

1988-03-01T23:59:59.000Z

111

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

E-Print Network (OSTI)

288 Int. J. Nuclear Energy Science and Technology, Vol. 7, No. 4, 2013 Multi-physics modelling practices in a nutshell', Int. J. Nuclear Energy Science and Technology, Vol. 7, No. 4, pp.288 Energy and Nuclear Applications', G枚teborg, Sweden, 13颅14 October 2011 Copyright 漏 2013 Inderscience

Demazi猫re, Christophe

112

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

SciTech Connect

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

U.S. Department of Energy; Larry Zirker

2004-06-01T23:59:59.000Z

113

U.S. Department of Energy FreedomCAR & Vehicle Technologies Program Oil Bypass Filter Technology Evaluation Fifth Quarterly Report October - December 2003  

SciTech Connect

This Oil Bypass Filter Technology Evaluation quarterly report (October-December 2003) details the ongoing fleet evaluation of an oil bypass filter technology by the Idaho National Engineering and Environmental Laboratory (INEEL) for the U.S. Department of Energy's FreedomCAR & Vehicle Technologies Program. Eight four-cycle diesel-engine buses used to transport INEEL employees on various routes have been equipped with oil bypass filter systems from the puraDYN Corporation. The bypass filters are reported to have engine oil filtering capability of <1 micron and a built-in additive package to facilitate extended oil-drain intervals. To date, the eight buses have accumulated 324,091 test miles. This represents an avoidance of 27 oil changes, which equate to 952 quarts (238 gallons) of new oil not conserved and therefore, 952 quarts of waste oil not generated. To validate the extended oil-drain intervals, an oil-analysis regime is used to evaluate the fitness of the oil for continued service by monitoring the presence of necessary additives, undesirable contaminants, and engine-wear metals. The test fleet has been expanded to include six Chevrolet Tahoe sport utility vehicles with gasoline engines.

Larry Zirker; James Francfort

2004-02-01T23:59:59.000Z

114

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

SciTech Connect

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

Avrigeanu, V.; Avrigeanu, M. [Horia Hulubei National Institute for Physics and Nuclear Engineering, POBox MG-6, 077125 Magurele, Ilfov (Romania)

2012-11-20T23:59:59.000Z

115

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

SciTech Connect

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.

Not Available

1993-07-01T23:59:59.000Z

116

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

SciTech Connect

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.

Harmon, J.E. [ed.

1990-12-01T23:59:59.000Z

117

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

SciTech Connect

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.

NONE

1992-12-01T23:59:59.000Z

118

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

E-Print Network (OSTI)

International Symposium on Fusion Nuclear Technology (ISFNT-5) SAFETY ISSUES ASSOCIATED;International Symposium on Fusion Nuclear Technology (ISFNT-5) heat from in-vessel systems with high neutron Symposium on Fusion Nuclear Technology (ISFNT-5) A design must adequately transfer heat from plasma

California at Los Angeles, University of

119

September 2013 Most Viewed Documents for Fission And Nuclear Technologies |  

Office of Scientific and Technical Information (OSTI)

Fission And Nuclear Technologies Fission And Nuclear Technologies Estimation of gas leak rates through very small orifices and channels. [From sealed PuO/sub 2/ containers under accident conditions] Bomelburg, H.J. (1977) 133 Stress analysis and evaluation of a rectangular pressure vessel. [For equipment for sampling Hanford tank radwaste] Rezvani, M.A.; Ziada, H.H. (Westinghouse Hanford Co., Richland, WA (United States)); Shurrab, M.S. (Westinghouse Savannah River Co., Aiken, SC (United States)) (1992) 78 Graphite design handbook Ho, F.H. (1988) 76 Feed-pump hydraulic performance and design improvement, Phase I: research program design. Final report Brown, W.H.; Gopalakrishnan, S.; Fehlau, R.; Thompson, W.E.; Wilson, D.G. (1982) 69 Flow-induced vibration of circular cylindrical structures Chen, S.S. (1985)

120

Innovative applications of technology for nuclear power plant productivity improvements  

SciTech Connect

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)

Naser, J. A. [Electric Power Research Inst., 3420 Hillview Avenue, Palo Alto, CA 94303 (United States)

2012-07-01T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear filter technology" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


121

Programme A. Nuclear Power Subprogramme A.4 Technology Development for Advanced Reactor Lines  

E-Print Network (OSTI)

Programme A. Nuclear Power Subprogramme A.4 Technology Development for Advanced Reactor Lines the databases that will be produced in the course of the CRP and make them accessible through the IAEA's nuclear-Electrical Applications of Nuclear Power Project A.5.02: Nuclear hydrogen production CRP Title: Advances in nuclear power

De Cindio, Fiorella

122

A Home for Heffalump and Pooh - Argonne's Nuclear Science and Technology  

NLE Websites -- All DOE Office Websites (Extended Search)

A Home for Heffalump and Pooh A Home for Heffalump and Pooh About Director's Welcome Organization Achievements Highlights Fact Sheets, Brochures & Other Documents Multimedia Library Visit Argonne Work with Argonne Contact us Nuclear Energy Why Nuclear Energy? Why are some people afraid of Nuclear Energy? How do nuclear reactors work? Cheaper & Safer Nuclear Energy Helping to Solve the Nuclear Waste Problem Nuclear Reactors Nuclear Reactors Early Exploration Training Reactors Basic and Applied Science Research LWR Technology Development BORAX-III lighting Arco, Idaho (Press Release) Heavy Water and Graphite Reactors Fast Reactor Technology Integral Fast Reactor Argonne Reactor Tree CP-1 70th Anniversary CP-1 70th Anniversary Argonne's Nuclear Science and Technology Legacy Argonne's Nuclear Science and Technology Legacy

123

Program Overview Shane Johnson Office of Nuclear Energy, Science and Technology  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Program Overview Program Overview Shane Johnson Office of Nuclear Energy, Science and Technology April 15, 2002 Presentation to the Nuclear Energy Research Advisory Committee Office of Nuclear Energy, Science and Technology Johnson/April15_02 NP 2010 to NERAC.ppt 2 Nuclear Power 2010 Overview Nuclear Power 2010 Overview Goals 6 Orders for one or more new nuclear plants by 2005 6 Operation of new nuclear power plants by 2010 6 New program initiative unveiled February 2002 6 Based on Near-Term Deployment Roadmap 6 Public/private partnership to: ! Develop advanced reactor technologies ! Explore sites that could host new nuclear power plants ! Demonstrate new Nuclear Regulatory Commission (NRC) regulatory processes Office of Nuclear Energy, Science and Technology Johnson/April15_02 NP 2010 to NERAC.ppt 3

124

Institute for Nuclear and Energy Technologies 1 L. Stoppel, Th. Wetzel  

E-Print Network (OSTI)

facilities 路 Developing and testing of new measuring techniques May 2 - 6, 2011 #12;Institute for NuclearInstitute for Nuclear and Energy Technologies 1 L. Stoppel, Th. Wetzel FAIR and IFMIF liquid metal Power Targetry Workshop, May 3, 2011 #12;Institute for Nuclear and Energy Technologies 2 L. Stoppel, Th

McDonald, Kirk

125

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)

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.

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

2012-01-01T23:59:59.000Z

126

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)

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...

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

2013-01-01T23:59:59.000Z

127

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

128

Trends in cobalt-60 research in nuclear science and technology  

Science Journals Connector (OSTI)

This paper quantitatively analyses the growth and development of cobalt-60 research in nuclear science and technology in terms of publications. As per the International Nuclear Information System (INIS) database during 2000-2007, a total of 5874 publications were published. The highest number of papers in a year (896) was in 2002. The average number of publications per year was 734.25. China topped the list with 960 (14.96%) publications followed by Japan with 600 (9.35%), India with 463 (7.21%), Brazil with 339 (5.28%), and the Russian Federation with 266 (4.14%). The authorship and collaboration trend is towards multiauthored papers. Researchers in China, Japan, the Russian Federation and the USA were inclined to work in larger groups. The highly productive institutions were Bhabha Atomic Research Centre, India, with 260 publications; Instituto de Pesquisas Energeticas e Nucleares (IPEN), Brazil with 151 publications; and Japan Atomic Energy Research Institute (JAERI), Japan with 94 publications. The journals most preferred by scientists for the publication of papers were Acta Agriculturae Nucleatae Sinica with 183 publications, followed by Chinese Journal of Radiological Medicine and Protection with 182 publications and Radiation Physics and Chemistry with 175 publications.

Anil Sagar; B.S. Kademani; R.G. Garg; Vijai Kumar

2010-01-01T23:59:59.000Z

129

Features of technology of high-temperature superconductor films for microwave filters  

Science Journals Connector (OSTI)

The characteristics of fourth-order bandpass microwave filters based on high-temperature super-conductor (HTS) films have been numerically simulated and experimentally measured for the devices based on YBCO fi...

I. B. Vendik; O. G. Vendik; K. N. Zemlyakov; I. V. Kolmakova

2011-05-01T23:59:59.000Z

130

Technology Insights and Perspectives for Nuclear Fuel Cycle Concepts  

SciTech Connect

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.

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

2010-09-01T23:59:59.000Z

131

ENDF/B-VII.0: Next Generation Evaluated Nuclear Data Library for Nuclear Science and Technology  

SciTech Connect

We describe the next generation general purpose Evaluated Nuclear Data File, ENDF/B-VII.0, of recommended nuclear data for advanced nuclear science and technology applications. The library, released by the U.S. Cross Section Evaluation Working Group (CSEWG) in December 2006, contains data primarily for reactions with incident neutrons, protons, and photons on almost 400 isotopes. The new evaluations are based on both experimental data and nuclear reaction theory predictions. The principal advances over the previous ENDF/B-VI library are the following: (1) New cross sections for U, Pu, Th, Np and Am actinide isotopes, with improved performance in integral validation criticality and neutron transmission benchmark tests; (2) More precise standard cross sections for neutron reactions on H, {sup 6}Li, {sup 10}B, Au and for {sup 235,238}U fission, developed by a collaboration with the IAEA and the OECD/NEA Working Party on Evaluation Cooperation (WPEC); (3) Improved thermal neutron scattering; (4) An extensive set of neutron cross sections on fission products developed through a WPEC collaboration; (5) A large suite of photonuclear reactions; (6) Extension of many neutron- and proton-induced reactions up to an energy of 150 MeV; (7) Many new light nucleus neutron and proton reactions; (8) Post-fission beta-delayed photon decay spectra; (9) New radioactive decay data; and (10) New methods developed to provide uncertainties and covariances, together with covariance evaluations for some sample cases. The paper provides an overview of this library, consisting of 14 sublibraries in the same, ENDF-6 format, as the earlier ENDF/B-VI library. We describe each of the 14 sublibraries, focusing on neutron reactions. Extensive validation, using radiation transport codes to simulate measured critical assemblies, show major improvements: (a) The long-standing underprediction of low enriched U thermal assemblies is removed; (b) The {sup 238}U, {sup 208}Pb, and {sup 9}Be reflector biases in fast systems are largely removed; (c) ENDF/B-VI.8 good agreement for simulations of highly enriched uranium assemblies is preserved; (d) The underprediction of fast criticality of {sup 233,235}U and {sup 239}Pu assemblies is removed; and (e) The intermediate spectrum critical assemblies are predicted more accurately. We anticipate that the new library will play an important role in nuclear technology applications, including transport simulations supporting national security, nonproliferation, advanced reactor and fuel cycle concepts, criticality safety, medicine, space applications, nuclear astrophysics, and nuclear physics facility design. The ENDF/B-VII.0 library is archived at the National Nuclear Data Center, BNL. The complete library, or any part of it, may be retrieved from www.nndc.bnl.gov.

Chadwick, M B; Oblozinsky, P; Herman, M; Greene, N M; McKnight, R D; Smith, D L; Young, P G; MacFarlane, R E; Hale, G M; Haight, R C; Frankle, S; Kahler, A C; Kawano, T; Little, R C; Madland, D G; Moller, P; Mosteller, R; Page, P; Talou, P; Trellue, H; White, M; Wilson, W B; Arcilla, R; Dunford, C L; Mughabghab, S F; Pritychenko, B; Rochman, D; Sonzogni, A A; Lubitz, C; Trumbull, T H; Weinman, J; Brown, D; Cullen, D E; Heinrichs, D; McNabb, D; Derrien, H; Dunn, M; Larson, N M; Leal, L C; Carlson, A D; Block, R C; Briggs, B; Cheng, E; Huria, H; Kozier, K; Courcelle, A; Pronyaev, V; der Marck, S

2006-10-02T23:59:59.000Z

132

Ceramic HEPA Filter Program  

SciTech Connect

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.

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

2012-04-30T23:59:59.000Z

133

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

SciTech Connect

This Oil Bypass Filter Technology Evaluation quarterly report (April朖une 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抯 (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抯 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.

Larry Zirker; James Francfort; Jordan Fielding

2004-08-01T23:59:59.000Z

134

Applications of Nuclear Science and Technology| U.S. DOE Office of Science  

Office of Science (SC) Website

Applications of Nuclear Science and Technology Nuclear Physics (NP) NP Home About Research Facilities Science Highlights Benefits of NP Spinoff Applications SBIR/STTR Applications of Nuclear Science and Technology Funding Opportunities Nuclear Science Advisory Committee (NSAC) News & Resources Contact Information Nuclear Physics U.S. Department of Energy SC-26/Germantown Building 1000 Independence Ave., SW Washington, DC 20585 P: (301) 903-3613 F: (301) 903-3833 E: sc.np@science.doe.gov More Information 禄 Benefits of NP Applications of Nuclear Science and Technology Print Text Size: A A A RSS Feeds FeedbackShare Page Applications of Nuclear Science and Technology (ANS&T) Exchange Meeting: August 22-23, 2011 Hilton Washington DC/Rockville Hotel & Executive Meeting Center

135

Nuclear Energy: Policies and Technology for the 21st Century | Department  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Nuclear Energy: Policies and Technology for the 21st Century Nuclear Energy: Policies and Technology for the 21st Century Nuclear Energy: Policies and Technology for the 21st Century 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. nuclear energy policy and a Technical Subcommittee to review facilities for nuclear energy programs. The two subcommittee reports follow this brief summary.1 The mission of the Policy Subcommittee was to explore the critical choices and implications in U.S. nuclear energy policy, with a view to framing options for the next President to consider. Both in the United States and worldwide, nuclear power has the potential to curtail the dependence on fossil fuels and thereby to reduce the amount of

136

Department of Energy Awards $15 Million for Nuclear Fuel Cycle Technology  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

15 Million for Nuclear Fuel Cycle 15 Million for Nuclear Fuel Cycle Technology Research and Development Department of Energy Awards $15 Million for Nuclear Fuel Cycle Technology Research and Development August 1, 2008 - 2:40pm Addthis WASHINGTON, DC - The U.S. Department of Energy (DOE) today announced it will award up to $15 million to 34 research organizations as part of the Department's Advanced Fuel Cycle Initiative (AFCI). AFCI is the Department's nuclear energy research and development program supporting the long-term goals and objectives of the United States' nuclear energy policy. These projects will provide necessary data and analyses to further U.S. nuclear fuel cycle technology development, meet the need for advanced nuclear energy production and help to close the nuclear fuel cycle

137

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)

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 ...

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

2012-01-01T23:59:59.000Z

138

Analysis of partial discharge detection in power cable by WTST-NST filter technology  

Science Journals Connector (OSTI)

The objectives of on-line monitoring are to prevent failures, reduce maintenance costs, and predict the life of the power system equipment. It is non-destructive and also cost-effective due to its ability to be applied when the equipments are in-service ... Keywords: MRD-MRR algorithm, adaptive WTST-NST filter, partial discharge, power cable, stationary noise interference

Hui Wang; Chengjun Huang; Junhua Liu; Linpeng Yao; Yong Qian; Xiuchen Jiang

2009-05-01T23:59:59.000Z

139

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

E-Print Network (OSTI)

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 a unique challenge to the testing, qualification and use of smart materials. The present study assesses

Giurgiutiu, Victor

140

1Nuclear Materials Technology Division/Los Alamos National Laboratory Publications  

E-Print Network (OSTI)

, the United States had no easy way of recover- ing plutonium from its nuclear weapons with- out generating1Nuclear Materials Technology Division/Los Alamos National Laboratory 0 Publications Nuclear Fuels-Dehydride Recycle Process for Plutonium Recovery 4-5 Electrolytic Decontamination of Oralloy 6 Applied Weapons

Note: This page contains sample records for the topic "nuclear filter technology" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


141

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)

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.

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

2013-02-18T23:59:59.000Z

142

Improving the management of nuclear technology: Technical, financial, and organizational measures for assessing the performance of nuclear utilities  

Science Journals Connector (OSTI)

This paper is the outcome of a study with the objective of better understanding and improving the quality of the management of technology in the case of the nuclear power industry. The authors tried to deal with this topic in an empirical way, namely by conducting four case studies on the major nuclear power utilities in the State of New York and by doing a comparative analysis of the material collected, focusing on the main economic and organizational issues, and the management of technology practices that pertain to nuclear power generation. The study covered in depth the nuclear divisions of only four out of a total of fifty-five nuclear utilities that exist in the United States, hence we want to stress the caveat that it has an exploratory rather than a statistically conclusive nature.

Elias Carayannis; Jose Maldifassi

1992-01-01T23:59:59.000Z

143

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

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

One the cover: One the cover: Albert Einstein (1879-1955) U.S. Department of Energy Office of Nuclear Energy, Science and Technology Washington, D.C. 20585 The History of Nuclear Energy Table of Contents Preface ................................................................... 1 Introduction .......................................................... 3 The Discovery of Fission ...................................... 4 The First Self-Sustaining Chain Reaction ............ 5 The Development of Nuclear Energy for Peaceful Applications ..................................... 7 Chronology of Nuclear Research and Development, 1942-1994 .................................... 13 Selected References ............................................. 23 Glossary ..............................................................

144

Nuclear Energy: Policies and Technology for the 21st Century | Department  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Energy: Policies and Technology for the 21st Century Energy: Policies and Technology for the 21st Century Nuclear Energy: Policies and Technology for the 21st Century 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. nuclear energy policy and a Technical Subcommittee to review facilities for nuclear energy programs. The two subcommittee reports follow this brief summary.1 The mission of the Policy Subcommittee was to explore the critical choices and implications in U.S. nuclear energy policy, with a view to framing options for the next President to consider. Both in the United States and worldwide, nuclear power has the potential to curtail the dependence on fossil fuels and thereby to reduce the amount of

145

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

E-Print Network (OSTI)

Int. J. Nuclear Energy Science and Technology, Vol. 4, No. 4, 2009 287 Development of computational plants', Int. J. Nuclear Energy Science and Technology, Vol. 4, No. 4, pp.287颅298. Biographical notes methods and their applications for the analysis of nuclear power plants C. Demazi猫re Department of Nuclear

Demazi猫re, Christophe

146

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

National Nuclear Security Administration (NNSA)

Dr. Rick Hall, Vice President of Academic Affairs, Augusta Technical College and Carol Johnson, Savannah River Nuclear Solutions President & CEO, to sign an Agreement of...

147

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

Office of Scientific and Technical Information (OSTI)

Nicolas; Pruess, Karsten (2004) 21 Levelized Costs for Nuclear, Gas and Coal for Electricity, under the Mexican Scenario Palacios, J.C.; Alonso, G.; Ramirez, R.; Gomez, A.;...

148

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

Office of Scientific and Technical Information (OSTI)

J. (1978) 30 > Reactor safety study. An assessment of accident risks in U. S. commercial nuclear power plants. Executive summary: main report. PWR and BWR Not Available (1975)...

149

A Explanatory Model of Public Acceptance for Nuclear Power Technology: From Low-Carbon Perspective  

Science Journals Connector (OSTI)

There are not so many literature about nuclear power technology of public acceptance in China, but different scholars have different opinions about the determinants of public acceptance. Xi and Xue studied that w...

Yuan-hua Yang; Li Li; Guo-hua Niu

2013-01-01T23:59:59.000Z

150

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

E-Print Network (OSTI)

, and airflow data, while the LPC method performed best with energy consumption data. Keywords--sensor systems inefficient buildings with new and innovative technologies that help to curb energy consumption will reduce Charles C. Castello1 and Joshua R. New2 Energy Transportation and Science Division Oak Ridge National

Wang, Xiaorui "Ray"

151

Calcined Waste Storage at the Idaho Nuclear Technology and Engineering Center  

SciTech Connect

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.

M. D. Staiger

2007-06-01T23:59:59.000Z

152

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

SciTech Connect

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)

First, M.W. [ed.] [Harvard Univ., Boston, MA (United States). Harvard Air Cleaning Lab.

1991-02-01T23:59:59.000Z

153

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

E-Print Network (OSTI)

Roadmap: Radiologic Imaging Sciences 颅 Nuclear Medicine (with certification and ATS Radiologic Technology) 颅 Bachelor of Radiologic Imaging Sciences Technology [RE-BRIT-RIS-NMHO] Regional College Catalog Year: 2013-2014 Page 1 of 2 | Last Updated: 1-May 13/LNHD This roadmap is a recommended semester

Sheridan, Scott

154

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

E-Print Network (OSTI)

Roadmap: Radiologic Imaging Sciences 颅 Nuclear Medicine (with certification and ATS Radiologic Technology) 颅 Bachelor of Radiologic Imaging Sciences Technology [RE-BRIT-RIS-NMHO] Regional College Catalog Year: 2012-2013 Page 1 of 2 | Last Updated: 11-Apr-12/LNHD This roadmap is a recommended semester

Sheridan, Scott

155

Basis for Section 3116 Determination for the Idaho Nuclear Technology and  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Basis for Section 3116 Determination for the Idaho Nuclear Basis for Section 3116 Determination for the Idaho Nuclear Technology and Engineering Center Tank Farm Facility at the Idaho National Laboratory Basis for Section 3116 Determination for the Idaho Nuclear Technology and Engineering Center Tank Farm Facility at the Idaho National Laboratory This 3116 Basis Document addresses the disposal of stabilized residuals in the TFF, and the TFF tank system, and disposal of the tanks, vaults, and associated piping and ancillary equipment at INTEC. The TFF tank system comprises the eleven 300,000-gal tanks, four 30,000-gal tanks, and the vaults, piping, structures, and ancillary equipment associated with these tanks. Basis for Section 3116 Determination for the Idaho Nuclear Technology and Engineering Center Tank Farm Facility at the Idaho National Laboratory

156

Work for the DOE Office of Transportation Technologies - Nuclear  

NLE Websites -- All DOE Office Websites (Extended Search)

of of Transportation Technologies Capabilities Sensors and Instrumentation and Nondestructive Evaluation Overview Energy System Applications Overview DOE Office of Fossil Energy DOE Office of Transportation Technologies Ion-mobility Spectrometry Based NOx Sensor DOE Office of Power Technology Work for Others Safety-Related Applications Homeland Security Applications Biomedical Applications Millimiter Wave Group Papers Other NPNS Capabilities Work with Argonne Contact us For Employees Site Map Help Join us on Facebook Follow us on Twitter NE on Flickr Sensors and Instrumentation and Nondestructive Evaluation Energy System Applications Bookmark and Share DOE Office of Transportation Technologies Ion-mobility Spectrometry Based NOx Sensor Real-time measurement of NOx content in the exhaust gas can provide the

157

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

E-Print Network (OSTI)

288 Int. J. Nuclear Energy Science and Technology, Vol. 7, No. 4, 2013 Copyright 漏 2013 to safety analyses' presented at the `JSPS Colloquium on Nuclear Energy and Nuclear Applications', G枚teborg Inderscience Enterprises Ltd. Multi-physics modelling of nuclear reactors: current practices in a nutshell

Demazi猫re, Christophe

158

Fusion Nuclear Science and Technology (FNST) Mohamed Abdou  

E-Print Network (OSTI)

Systems / Components affected by the Nuclear Environment: 2 Reactor Core Inside the Vacuum Vessel "Reactor analysis methods and codes 路 engineering scaling 路 failure modes/effects and RAMI analysis methods 路 design Material degradation by radiation and other damage Fabrication and joining for reliable components

159

Nuclear fission: the interplay of science and technology  

Science Journals Connector (OSTI)

...the present radioactive waste () came from early weapons...nuclear energy from such waste, and there are schemes...involve a decision between long-term storage (i.e. with access...medium-level and high-level wastes. How a particular radioactive...

2010-01-01T23:59:59.000Z

160

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

SciTech Connect

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.

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

2011-04-01T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear filter technology" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


161

Sensors and nuclear power. Report by the Technology Transfer Sensors Task Team  

SciTech Connect

The existing sensor systems for the basic process parameters in nuclear power plant operation have limitations with respect to accuracy, ease of maintenance and signal processing. These limitations comprise the economy of nuclear power generation. To reduce the costs and improve performance of nuclear power plant fabrication, operation, maintenance and repair we need to advance the sensor technology being applied in the nuclear industry. The economic viability and public acceptance of nuclear power will depend on how well we direct and apply technological advances to the industry. This report was prepared by a team with members representing a wide range of the nuclear industry embracing the university programs, national laboratories, architect engineers and reactor manufacturers. An intensive effort was made to survey current sensor technology, evaluate future trends and determine development needs. This included literature surveys, visits with utilities, universities, laboratories and organizations outside the nuclear industry. Several conferences were attended to take advantage of the access to experts in selected topics and to obtain opinions. Numerous telephone contacts and exchanges by mail supplemented the above efforts. Finally, the broad technical depth of the team members provided the basis for the stimulating working sessions during which this report was organized and drafted.

Not Available

1985-06-01T23:59:59.000Z

162

ULTRA?COMPACT ACCELERATOR TECHNOLOGIES FOR APPLICATION IN NUCLEAR TECHNIQUES  

Science Journals Connector (OSTI)

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 ?10 MV/m gradients for 10 s of nanoseconds pulses and ?100 MV/m gradients for ?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 describe 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.

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

2009-01-01T23:59:59.000Z

163

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)

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 utilities, government organizations and various branches of industry - including the nuclear, financial services and medical sectors

Lindken, Ralph

164

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

Energy.gov (U.S. Department of Energy (DOE))

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

165

Cordierite silicon nitride filters  

SciTech Connect

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.

Sawyer, J.; Buchan, B. (Acurex Environmental Corp., Mountain View, CA (United States)); Duiven, R.; Berger, M. (Aerotherm Corp., Mountain View, CA (United States)); Cleveland, J.; Ferri, J. (GTE Products Corp., Towanda, PA (United States))

1992-02-01T23:59:59.000Z

166

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

SciTech Connect

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.

Vinson, D.

2010-07-11T23:59:59.000Z

167

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

E-Print Network (OSTI)

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.

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

2014-04-14T23:59:59.000Z

168

An evaluation of the dismantling technologies for decommissioning of nuclear power plants  

Science Journals Connector (OSTI)

Abstract This paper is to suggest an evaluation method on the dismantling technologies for decommissioning of nuclear power plants. The parameters of evaluation are performance impacts, site-specific impacts, safety impacts, and cost impacts. The evaluation model was provided and applied for dismantling of a steam generator.

KwanSeong Jeong; ByungSeon Choi; Jeikwon Moon; Dongjun Hyun; JongHwan Lee; IkJune Kim; GeunHo Kim; JaeSeok Seo

2014-01-01T23:59:59.000Z

169

Status of Rankine-cycle technology for space nuclear power applications  

SciTech Connect

A substantial effort on the development of the liquid metal Rankine cycle space nuclear power system was carried out in programs jointly sponsored by the National Aeronautics and Space Administration (NASA) and the Atomic Energy Commission (AEC) during the period of 1960--1972. Component tests were conducted which have established a considerable technology base for the concept. The development effort and technology status of each component are presented. The key technology issues remaining for development of the system are: refractory metal parts fabrication, turbine blade endurance, turbine bearings and seals, and generator winding seal. 5 refs.

Holcomb, R.S.

1991-01-01T23:59:59.000Z

170

Technolog  

NLE Websites -- All DOE Office Websites (Extended Search)

Research in Research in Science and Technolog y Sandia pushes frontiers of knowledge to meet the nation's needs, today and tomorrow Sandia National Laboratories' fundamental science and technology research leads to greater understanding of how and why things work and is intrinsic to technological advances. Basic research that challenges scientific assumptions enables the nation to push scientific boundaries. Innovations and breakthroughs produced at Sandia allow it to tackle critical issues, from maintaining the safety, security and effectiveness of the nation's nuclear weapons and preventing domestic and interna- tional terrorism to finding innovative clean energy solutions, develop- ing cutting-edge nanotechnology and moving the latest advances to the marketplace. Sandia's expertise includes:

171

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

SciTech Connect

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.

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

1991-01-01T23:59:59.000Z

172

Next Generation CANDU Technology: Competitive Design for the Nuclear Renaissance  

SciTech Connect

AECL has developed the design for a next generation of CANDU{sup R} plants by marrying a set of enabling technologies to well-established successful CANDU features. The basis for the design is to replicate or adapt existing CANDU components for a new core design. By adopting slightly enriched uranium fuel, a core design with light water coolant, heavy water moderator and reflector has been defined, based on the existing CANDU fuel channel module. This paper summarizes the main features and characteristics of the reference next-generation CANDU design. The progress of the next generation of CANDU design program in meeting challenging cost, schedule and performance targets is described. AECL's cost reduction methodology is summarized as an integral part of the design optimization process. Examples are given of cost reduction features together with enhancement of design margins. (authors)

Hopwood, J.M.; Hedges, K.R.; Pakan, M. [Atomic Energy of Canada Ltd., Ontario (Canada)

2002-07-01T23:59:59.000Z

173

A version of this appeared in Current Science 75(6) 1998 India's Nuclear Breeders: Technology, Viability, and Options  

E-Print Network (OSTI)

A version of this appeared in Current Science 75(6) 1998 India's Nuclear Breeders: Technology tongia@andrew.cmu.edu; vsa@andrew.cmu.edu Abstract: India's nuclear power program is based on indigenous to nuclear capacity in the short-term. The Th-U233 cycle in fast breeders does not appear attractive, and

174

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

E-Print Network (OSTI)

testing of the ENDF/B-VII.1 library is provided for a variety of quantities: For nuclear criticalityENDF/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

Danon, Yaron

175

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

Office of Scientific and Technical Information (OSTI)

Most Viewed Documents - Fission and Nuclear Technologies Most Viewed Documents - Fission and Nuclear Technologies Metals design handbook Betts, W.S. (1988) Estimation of gas leak rates through very small orifices and channels. [From sealed PuO/sub 2/ containers under accident conditions] Bomelburg, H.J. () Graphite design handbook Ho, F.H. (1988) Motor-operated valve (MOV) actuator motor and gearbox testing DeWall, K.; Watkins, J.C.; Bramwell, D. [Lockheed Idaho Technologies Co., Idaho Falls, ID (United States)] (1997) Environmental Aspects, Objectives and Targets Identification Process R. Green (2002) Flow-induced vibration of circular cylindrical structures Chen, S.S. (1985) System Definition and Analysis: Power Plant Design and Layout NONE (1996) Materials and design bases issues in ASME Code Case N-47 Huddleston, R.L.; Swindeman, R.W. (Oak Ridge National Lab., TN (United

176

Precision linac and laser technologies for nuclear photonics gamma-ray sources  

SciTech Connect

Tunable, high precision gamma-ray sources are under development to enable nuclear photonics, an emerging field of research. This paper focuses on the technological and theoretical challenges related to precision Compton scattering gamma-ray sources. In this scheme, incident laser photons are scattered and Doppler upshifted by a high brightness electron beam to generate tunable and highly collimated gamma-ray pulses. The electron and laser beam parameters can be optimized to achieve the spectral brightness and narrow bandwidth required by nuclear photonics applications. A description of the design of the next generation precision gamma-ray source currently under construction at Lawrence Livermore National Laboratory is presented, along with the underlying motivations. Within this context, high-gradient X-band technology, used in conjunction with fiber-based photocathode drive laser and diode pumped solid-state interaction laser technologies, will be shown to offer optimal performance for high gamma-ray spectral flux, narrow bandwidth applications.

Albert, F.; Hartemann, F. V.; Anderson, S. G.; Cross, R. R.; Gibson, D. J.; Hall, J.; Marsh, R. A.; Messerly, M.; Wu, S. S.; Siders, C. W.; Barty, C. P. J. [Lawrence Livermore National Laboratory, NIF and Photon Science, 7000 East Avenue, Livermore, California 94550 (United States)

2012-05-15T23:59:59.000Z

177

Hydrogen Gas Production from Nuclear Power Plant in Relation to Hydrogen Fuel Cell Technologies Nowadays  

Science Journals Connector (OSTI)

Recently world has been confused by issues of energy resourcing including fossil fuel use global warming and sustainable energy generation. Hydrogen may become the choice for future fuel of combustion engine. Hydrogen is an environmentally clean source of energy to end?users particularly in transportation applications because without release of pollutants at the point of end use. Hydrogen may be produced from water using the process of electrolysis. One of the GEN?IV reactors nuclear projects (HTGRs HTR VHTR) is also can produce hydrogen from the process. In the present study hydrogen gas production from nuclear power plant is reviewed in relation to commercialization of hydrogen fuel cell technologies nowadays.

2010-01-01T23:59:59.000Z

178

High Efficiency Particulate Air Filters  

NLE Websites -- All DOE Office Websites (Extended Search)

High Efficiency Particulate Air (HEPA) Filters High Efficiency Particulate Air (HEPA) Filters Home Standards DOE Workshops Nuclear Air Cleaning Conference Proceedings Qualified Filter List News Items Related Sites HEPA Related Lessons Learned Contact Us HSS Logo High Efficiency Particulate Air Filters The HEPA Filter web site provides a forum for informing and reporting department-wide activities related to filtration and ventilation issues with special reference to the High Efficiency Particulate Air (HEPA) Filters' use, inspection, and testing. This site contains essentials of DOE HEPA filter test program, procedures, requirements and quality assurance aspects applicable to HEPA filters used in DOE facilities. This site contains information about the DOE-accepted Filter Test Facility and its management, operation and quality assuranceprogram.

179

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

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Sheet Sheet NNSA issues Preliminary Notice of Violation to National Security Technologies, LLC, for Nuclear Safety Violations On August 22, 2011, the National Nuclear Security Administration (NNSA) issued a Preliminary Notice of Violation (PNOV) to National Security Technologies, LLC (NSTec) for violations of Department of Energy's (DOE) nuclear safety regulations. NSTec is the operating contractor of NNSA's Nevada National Security Site (NNSS) located 65 miles northwest of Las Vegas, Nevada. The PNOV cites four violations of DOE regulations governing nuclear safety management. The violations are associated with quality assurance (QA) related deficiencies in the inspection and installation of penetration fire seals and other components at the Criticality Experiments Facility

180

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

SciTech Connect

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

Wai, Chien M.

2003-09-10T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear filter technology" from the National Library of EnergyBeta (NLEBeta).
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they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
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181

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

SciTech Connect

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.

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

2011-09-13T23:59:59.000Z

182

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

SciTech Connect

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.

Wetovsky, Marvin A. [Editor; Patterson, Eileen F. [Editor

2010-09-21T23:59:59.000Z

183

Disk filter  

DOE Patents (OSTI)

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.

Bergman, W.

1985-01-09T23:59:59.000Z

184

Report on the Scientific Committee for the Evaluation of the Institute of Nuclear Technology and Radiation Protection (INTRP)  

E-Print Network (OSTI)

and radiobiology Radioecology Environmental pollution Reliability and risk analysis of industrial installations and evaluated the Institute of Nuclear Reactor Technology and Radiation Protection, following the instructions characterization for Fusion The Institute operates the Research Reactor with main activities

185

Financial valuation of investments in future power generation technologies: nuclear fusion and CCS in an emissions trading system  

Science Journals Connector (OSTI)

This paper outlines a model approach for the financial valuation of future power generation technologies, such as nuclear fusion or carbon capture and storage (CCS) under an emissions trading regime. Since on imp...

Heinz Eckart Klingelh鰂er; Peter Kurz

2011-12-01T23:59:59.000Z

186

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

SciTech Connect

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.

Farfan, E.

2009-11-23T23:59:59.000Z

187

METAL MEDIA FILTERS, AG-1 SECTION FI  

SciTech Connect

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.

Adamson, D.

2012-05-23T23:59:59.000Z

188

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

SciTech Connect

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).

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

2011-08-31T23:59:59.000Z

189

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

SciTech Connect

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.

Bowman, C.D.

1996-07-01T23:59:59.000Z

190

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

SciTech Connect

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.

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

1993-12-31T23:59:59.000Z

191

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

NLE Websites -- All DOE Office Websites (Extended Search)

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

192

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

SciTech Connect

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.

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

2009-09-21T23:59:59.000Z

193

Scientometric mapping of vacuum research in nuclear science & technology: a global perspective  

Science Journals Connector (OSTI)

This paper attempts to analyse the growth and development of Vacuum research in Nuclear Science and Technology, as reflected in publication output covered by International Nuclear Information System (INIS) database during 2002-2006. A total of 12027 papers were published in the field of vacuum science. United States topped the list with 1936 (16.10%) publications followed by Japan with 1770 (14.70%) publications, The highest number of publications (3276) were published in 2004. The average number of publications published per year were 2405.4. The highest number of publications were in 'Physics of Elementary Particles and Fields' with 2644 (21.98%) publications. The authorship and collaboration trend is towards multi-authored papers. The highly productive institutions were: Japan Atomic Energy Research Institute (Japan) with 366 publications, University of Tokyo (Japan) with 274 publications, Hiroshima University (Japan) with 245 publications, Osaka University Japan (Japan) with 224 publications and Chinese Academy of Science (P-R-China) with 223 publications. The most preferred journals for publication were: Journal of Vacuum Science and Technology-A with 857 papers, Physical Review -D with 765 papers, Journal of High Energy Physics with 500 papers, Thin Solid Films with 311 papers, Journal of Electron Spectroscopy and Related Phenomena with 309 papers, and AIP Conference Proceedings with 308 papers.

B S Kademani; A Sagar; A Kumar; V Kumar

2008-01-01T23:59:59.000Z

194

Spatial Frequency Filtering Using Nondelineated Thin Films  

Science Journals Connector (OSTI)

We present a new approach for achieving spatial frequency filtering in the analog domain. Our device, the Thin Film Spatial Filter, is a hybrid structure which combines the strengths of analog VLSI technology with the simplicity of a continuous sheet ...

J. Mcelvain; J. Langan; A. J. Heeger

1997-10-01T23:59:59.000Z

195

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)

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.

Oleg P. Ledenyov; Ivan M. Neklyudov

2013-06-14T23:59:59.000Z

196

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

SciTech Connect

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.

L.E. Demick

2010-09-01T23:59:59.000Z

197

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

SciTech Connect

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.

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

2002-02-25T23:59:59.000Z

198

Filtering apparatus  

DOE Patents (OSTI)

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.

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

1992-01-01T23:59:59.000Z

199

Calcine Waste Storage at the Idaho Nuclear Technology and Engineering Center  

SciTech Connect

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.

M. D. Staiger

1999-06-01T23:59:59.000Z

200

Deuterium transport and isotope effects in type 316L stainless steel at high temperatures for nuclear fusion and nuclear hydrogen technology applications  

Science Journals Connector (OSTI)

Abstract We present the first complete data set for the permeability, diffusivity, and solubility of both deuterium and hydrogen in 316L stainless steel (316L SS) obtained over a wide temperature range of 350850牥C that accommodates both nuclear fusion and nuclear hydrogen technology applications. The deuterium results were also compared with the hydrogen results to estimate the isotope effect. The isotope effect ratio for diffusivity was different from the classical prediction. Furthermore, some of our results were compared with the results previously reported for 316 SS. Results and discussion are presented with an emphasis on the deuterium permeation and isotope effects.

S.K. Lee; S.-H. Yun; Han Gyu Joo; S.J. Noh

2014-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear filter technology" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


201

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

SciTech Connect

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.

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

2011-09-30T23:59:59.000Z

202

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

SciTech Connect

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.

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

1998-05-01T23:59:59.000Z

203

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

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

Control Fundamentals CLEERS Activities: Diesel Soot Filter Characterization & NOx Control Fundamentals 2009 DOE Hydrogen Program and Vehicle Technologies Program Annual Merit...

204

Powered by technology or powering technology?爾 Belief-based decision-making in nuclear power and synthetic fuel.  

E-Print Network (OSTI)

?? The overarching question in this study is how and why technical-fixes in energy policy failed. In the post-WWII era, civilian nuclear power and synthetic (more)

Yang, Chi-Jen

2008-01-01T23:59:59.000Z

205

Toward Green Systems for Cleanrooms: Energy Efficient Fan-filter Units Ming-Shan Jeng, Industrial Technology Research Institute, msjeng@itri.org.tw  

E-Print Network (OSTI)

Toward Green Systems for Cleanrooms: Energy Efficient Fan-filter Units Ming-Shan Jeng, Industrial results of laboratory-measured performance of fan-filter units (FFUs) used for cleanrooms. A total for many cleanroom applications. ) 2004 Semiconductor Equipment and Materials International Keywords

206

Graduate Research Assistant Program for Professional Development at Oak Ridge National Laboratory (ORNL) Global Nuclear Security Technology Division (GNSTD)  

SciTech Connect

The southeast is a highly suitable environment for establishing a series of nuclear safety, security and safeguards 'professional development' courses. Oak Ridge National Laboratory (ORNL) provides expertise in the research component of these subjects while the Y-12 Nuclear Security Complex handles safeguards/security and safety applications. Several universities (i.e., University of Tennessee, Knoxville (UTK), North Carolina State University, University of Michigan, and Georgia Technology Institute) in the region, which offer nuclear engineering and public policy administration programs, and the Howard Baker Center for Public Policy make this an ideal environment for learning. More recently, the Institute for Nuclear Security (INS) was established between ORNL, Y-12, UTK and Oak Ridge Associate Universities (ORAU), with a focus on five principal areas. These areas include policy, law, and diplomacy; education and training; science and technology; operational and intelligence capability building; and real-world missions and applications. This is a new approach that includes professional development within the graduate research assistant program addressing global needs in nuclear security, safety and safeguards.

Eipeldauer, Mary D [ORNL; Shelander Jr, Bruce R [ORNL

2012-01-01T23:59:59.000Z

207

Nuclear Fusion  

Science Journals Connector (OSTI)

Although not yet developed at the commercial stage, nuclear fusion technology is still being considered as a ... used in nuclear warfare. Since research in nuclear fusion for the production of energy started abou...

Ricardo Guerrero-Lemus; Jos Manuel Mart韓ez-Duart

2013-01-01T23:59:59.000Z

208

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

Energy.gov (U.S. Department of Energy (DOE))

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

209

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

SciTech Connect

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

Michael W. Patterson

2008-05-01T23:59:59.000Z

210

Metrics For Comparing Plasma Mass Filters  

SciTech Connect

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. __________________________________________________

Abraham J. Fetterman and Nathaniel J. Fisch

2012-08-15T23:59:59.000Z

211

Fleet test evaluation of fully formulated heavy-duty coolant technology maintained with a delayed-release filter compared with coolant inhibited with a nitrited organic acid technology: An interim report  

SciTech Connect

This paper is a controlled extended service interval (ESI) study of the comparative behaviors of a nitrite/borate/low-silicate, low total dissolved solids (TDS) coolant maintained with delayed-release filters, and an organic acid inhibited coolant technology in heavy-duty engines. It reports both laboratory and fleet test data from 66 trucks, powered with different makes of heavy-duty diesel engines. The engines were cooled with three different types of inhibitors and two different glycol base (ethylene glycol and propylene glycol) coolants for an initial period exceeding two years and 500,000 km (300,000 miles). The data reported include chemical depletion rates, periodic coolant chemical analyses, and engine/cooling system reliability experience. The ongoing test will continue for approximately five years and a 1.6 million km (1 million miles) duration. Thirteen trucks were retained as controls, operating with ASTM D 4985 specification (GM-6038 type) coolant maintained with a standard ASTM D 57542 supplemental coolant additive (SCA). Engines produced by Caterpillar, Detroit Diesel Corp., Cummins Engine Co., and Mack Trucks are included in the test mix.

Aroyan, S.S.; Eaton, E.R. [Penray Companies, Inc., Elk Grove Village, IL (United States). Technical Service

1999-08-01T23:59:59.000Z

212

Advances in Filter Miniaturization and Design/Analysis of RF MEMS Tunable Filters  

E-Print Network (OSTI)

-band filters, the use of cross-shaped fractals in half-mode substrate-integrated-waveguide bandpass filters resulted in a 37 percent size reduction. A compact bandpass filter that occupies an area of 0.315 mm2 is implemented in 90-nm CMOS technology for 20 GHz...

Sekar, Vikram

2012-10-19T23:59:59.000Z

213

Technologies for destruction of long-lived radionuclides in high-level nuclear waste - overview and requirements  

SciTech Connect

A major issue surrounding current nuclear power generation is the management and disposal of long-lived, high-level waste (HLW). The planned and scientifically acceptable destination for this waste is in deep underground, geologically stable, repositories. However, public concerns surrounding such disposal of long-lived nuclear wastes and other issues such as proliferation and safety negatively affect the potential role that nuclear power can play in meeting current and future national energy needs. This paper and this topical session on nuclear waste minimization, management, and remediation focus on two nuclear systems and their associated technologies that have the potential to address concerns surrounding long-lived radionuclides in HLW. Both systems offer technology applicable to HLW from current light water reactors (LWRs). In addition, these systems represent advanced nuclear power concepts that have important features associated with integrated management of wastes long-term fuel supplies, and enhanced safety. The first system is the integral fast reactor (IFR) concept. This system incorporates a metal-fueled fast reactor coupled with chemical separations based on pyroprocessing to produce power while burning long-lived actinide waste. The IFR applications include the burning of actinides from current LWR spent fuel and energy production in a breeder environment. The second concept, accelerator transmutation of waste (ATW), is based on an accelerator-induced intense source of thermal neutrons and is aimed at the destruction of long-lived actinides and fission products. This concept can be applied to long-lived radionuclides in spent-fuel HLW as well as a future fission power source built around use of natural thorium or uranium as fuels coupled with concurrent waste destruction.

Arthur, E.D. (Los Alamos National Lab., NM (United States))

1993-01-01T23:59:59.000Z

214

Evaluation of HEPA filter service life  

SciTech Connect

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.

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

1997-07-14T23:59:59.000Z

215

Nuclear fuels technologies fiscal year 1998 research and development test plan  

SciTech Connect

A number of research and development (R and D) activities are planned at Los Alamos National Laboratory (LANL) in FY98 in support of the Department of Energy Office of Fissile Materials Disposition (DOE-MD). During the past few years, the ability to fabricate mixed oxide (MOX) nuclear fuel using surplus-weapons plutonium has been researched, and various experiments have been performed. This research effort will be continued in FY98 to support further development of the technology required for MOX fuel fabrication for reactor-based plutonium disposition. R and D activities for FY98 have been divided into four major areas: (1) feed qualification/supply, (2) fuel fabrication development, (3) analytical methods development, and (4) gallium removal. Feed qualification and supply activities encompass those associated with the production of both PuO{sub 2} and UO{sub 2} feed materials. Fuel fabrication development efforts include studies with a new UO{sub 2} feed material, alternate sources of PuO{sub 2}, and determining the effects of gallium on the sintering process. The intent of analytical methods development is to upgrade and improve several analytical measurement techniques in support of other R and D and test fuel fabrication tasks. Finally, the purpose of the gallium removal system activity is to develop and integrate a gallium removal system into the Pit Disassembly and Conversion Facility (PDCF) design and the Phase 2 Advanced Recovery and Integrated Extraction System (ARIES) demonstration line. These four activities will be coordinated and integrated appropriately so that they benefit the Fissile Materials Disposition Program. This plan describes the activities that will occur in FY98 and presents the schedule and milestones for these activities.

Alberstein, D.; Blair, H.T.; Buksa, J.J. [and others

1998-06-01T23:59:59.000Z

216

Vehicle Technologies Office: Materials for Energy Recovery Systems...  

Energy Savers (EERE)

penalties associated with many emission control technologies. These technologies include diesel particulate filters, catalysts, filter substrates, and exhaust-gas recirculation...

217

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

SciTech Connect

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.

Warren, N. Jill [Editor

1999-09-21T23:59:59.000Z

218

Cordierite silicon nitride filters. Final report  

SciTech Connect

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.

Sawyer, J.; Buchan, B. [Acurex Environmental Corp., Mountain View, CA (United States); Duiven, R.; Berger, M. [Aerotherm Corp., Mountain View, CA (United States); Cleveland, J.; Ferri, J. [GTE Products Corp., Towanda, PA (United States)

1992-02-01T23:59:59.000Z

219

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

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

NE-ID-11226 NE-ID-11226 Revision 0 Basis for Section 3116 Determination for the Idaho Nuclear Technology and Engineering Center Tank Farm Facility November 2006 DOE/NE-ID-11226 Revision 0 Basis for Section 3116 Determination for the Idaho Nuclear Technology and Engineering Center Tank Farm Facility November 2006 ii CONTENTS ACRONYMS.............................................................................................................................................. vii 1. INTRODUCTION AND PURPOSE.................................................................................................. 1 2. BACKGROUND................................................................................................................................ 5 2.1 Tank Farm Facility Description.............................................................................................

220

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

E-Print Network (OSTI)

I.N. Sviatoslavsky, M.E. Sawan, E.A. Mogahed, University of Wisconsin S. Malang, Fusion Nuclear Technology Consulting, Germany C.P.C. Wong, M. Friend, General Atomics S. Majumdar, Argonne National.g., maximizing nuclear parameters to achieve high conversion efficiency) are well worth striving for. SUMMARY

Note: This page contains sample records for the topic "nuclear filter technology" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


221

Technologies for destruction of long-lived radionuclides in high-level nuclear waste: Overview and requirements  

SciTech Connect

This paper, and this topical session on Nuclear Waste Minimization, Management and Remediation, focuses on two nuclear systems, and their associated technologies, that have the potential to address concerns surrounding long-lived radionuclides in high-level waste. Both systems offer technology applicable to HLW from present light-water reactors (LWR). Additionally these systems represent advanced nuclear power concepts that have important features associated with integrated management of wastes, long-term fuel supplies, and enhanced safety. The first system is the Integral Fast Reactor (IFR) concept. This system incorporates a metal-fueled fast reactor coupled with chemical separations based on pyroprocessing to produce power while simultaneously burning long-lived actinide waste. IFR applications include burning of actinides from current LWR spent fuel and energy production in a breeder environment. The second concept, Accelerator Transmutation of Waste (ATW), is based upon an accelerator-induced intense source of thermal neutrons and is aimed at destruction of long-lived actinides and fission products. This concept can be applied to long-lived radionuclides in spent fuel HLW as well as a future fission power source built around use of natural thorium or uranium as fuels coupled with concurrent waste destruction.

Arthur, E.D.

1993-10-01T23:59:59.000Z

222

Roadmapping - A Tool for Resolving Science and Technology Issues Related to Processing, Packaging, and Shipping Nuclear Materials and Waste  

SciTech Connect

Roadmapping is an effective methodology to identify and link technology development and deployment efforts to a program's or project's needs and requirements. Roadmapping focuses on needed technical support to the baselines (and to alternatives to the baselines) where the probability of success is low (high uncertainty) and the consequences of failure are relatively high (high programmatic risk, higher cost, longer schedule, or higher ES&H risk). The roadmap identifies where emphasis is needed, i.e., areas where investments are large, the return on investment is high, or the timing is crucial. The development of a roadmap typically involves problem definition (current state versus the desired state) and major steps (functions) needed to reach the desired state. For Nuclear Materials (NM), the functions could include processing, packaging, storage, shipping, and/or final disposition of the material. Each function is examined to determine what technical development would be needed to make the function perform as desired. This requires a good understanding of the current state of technology and technology development and validation activities to ensure the viability of each step. In NM disposition projects, timing is crucial! Technology must be deployed within the project window to be of value. Roadmaps set the stage to keep the technology development and deployment focused on project milestones and ensure that the technologies are sufficiently mature when needed to mitigate project risk and meet project commitments. A recent roadmapping activity involved a 'cross-program' effort, which included NM programs, to address an area of significant concern to the Department of Energy (DOE) related to gas generation issues, particularly hydrogen. The roadmap that was developed defined major gas generation issues within the DOE complex and research that has been and is being conducted to address gas generation concerns. The roadmap also provided the basis for sharing ''lessons learned'' from R&D efforts across DOE programs to increase efficiency and effectiveness in addressing gas generation issues. The gas generation roadmap identified pathways that have significant risk, indicating where more emphasis should be placed on contingency planning. Roadmapping further identified many opportunities for sharing of information and collaboration. Roadmapping will continue to be useful in keeping focused on the efforts necessary to mitigate the risk in the disposition pathways and to respond to the specific needs of the sites. Other areas within NM programs, including transportation and disposition of orphan and other nuclear materials, are prime candidates for additional roadmapping to assure achievement of timely and cost effective solutions for the processing, packaging, shipping, and/or final disposition of nuclear materials.

Luke, Dale Elden; Dixon, Brent Wayne; Murphy, James Anthony

2002-06-01T23:59:59.000Z

223

Work for the DOE Office of Power Technology - Nuclear Engineering Division  

NLE Websites -- All DOE Office Websites (Extended Search)

of Power of Power Technology Capabilities Sensors and Instrumentation and Nondestructive Evaluation Overview Energy System Applications Overview DOE Office of Fossil Energy DOE Office of Transportation Technologies Ion-mobility Spectrometry Based NOx Sensor DOE Office of Power Technology Work for Others Safety-Related Applications Homeland Security Applications Biomedical Applications Millimiter Wave Group Papers Other NPNS Capabilities Work with Argonne Contact us For Employees Site Map Help Join us on Facebook Follow us on Twitter NE on Flickr Sensors and Instrumentation and Nondestructive Evaluation Energy System Applications Bookmark and Share DOE Office of Power Technology NDE for Ceramics in Microturbines The concept of distributed energy systems using small gas turbines (< 500

224

The feasibility of modern technologies for reinforced concrete containment structures of nuclear power plants.  

E-Print Network (OSTI)

??This report explores the requirements for the design and analysis of concrete containment and shows how newer material technologies such as self-consolidating concrete (SCC) and (more)

Czerniewski, Sarah

2009-01-01T23:59:59.000Z

225

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

SciTech Connect

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.

Stone, J.R.

1994-07-01T23:59:59.000Z

226

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

SciTech Connect

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.

NONE

1995-06-01T23:59:59.000Z

227

Development of pyro-processing technology at CRIEPI for carving out the future of nuclear fuel cycle  

SciTech Connect

Pyro-processing has been attracting increasing attention as a promising candidate as an advanced nuclear fuel cycle technology. It provides economic advantage as well as reduction in proliferation risk and burden of long live radioactive waste, especially when it is combined with advanced fuels such as metallic or nitride fuel which gives excellent burning efficiency of minor actinides (MA). CRIEPI has been developing pyro-processing technology since late eighties with both domestic and international collaborations. In the early stage, electrochemical and thermodynamic properties in LiCl-KCl eutectic melt, and fundamental feasibility of core technology like electrorefining were chiefly investigated. Currently, stress in the process chemistry development is also placed on supporting technologies, such as treatment of anode residue and high temperature distillation for cathode product from electrorefining, and so on. Waste treatment process development, such as studies on adsorption behavior of various FP elements into zeolite and conditions for the fabrication of glass-bonded sodalite waste form, are steadily improved as well. In parallel, dedicated pyro-processing equipment such as zeolite column for treatment of spent electro-refiner salt is currently in progress. Recently, an integrated engineering-scale fuel cycle tests were performed funded by Japanese government (MEXT) as an important step before proceeding to large scale hot demonstration of pyro-processing. Oxide fuels can be readily introduced into the pyro-processing by reducing them to metals by adoption of electrochemical reduction technique. Making use of this advantage, the pyro-processing is currently under preliminary evaluation for its applicability to the treatment of the corium, mainly consisting of (U,Zr)O{sub 2}, formed in different composition during the accident of the Fukushima Daiichi nuclear power plant. (authors)

Iizuka, M.; Koyama, T.; Sakamura, Y.; Uozumi, K.; Fujihata, K.; Kato, T.; Murakami, T.; Tsukada, T. [Central Research Institute of Electric Power Industry, Komae-shi, Tokyo 201-8511 (Japan); Glatz, J.P. [European Commission, JRC, Institute for Transuranium Elements (Germany)

2013-07-01T23:59:59.000Z

228

Fuel Cycle Technologies Near Term Planning for Storage and Transportation of Used Nuclear Fuel  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

of Section 180(c) of the Nuclear of Section 180(c) of the Nuclear Waste Policy Act, as amended National Transportation Stakeholder's Forum Buffalo, NY May 15, 2013 Section 180(c) Mandate "The Secretary shall provide technical assistance and funds to States for training for public safety officials of appropriate units of local government and Indian tribes through whose jurisdiction the Secretary plans to transport spent nuclear fuel or high-level radioactive waste [to an NWPA-authorized facility]. * The training shall cover procedures for safe routine transportation of these materials and procedures for dealing with emergency response situations. * Covers all modes of transport 2 Section 180(c) - Background 飩 DOE nearly implemented Section 180(c) in the mid-

229

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)

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...

Ledenyov, Oleg P

2013-01-01T23:59:59.000Z

230

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

E-Print Network (OSTI)

for nuclear cooperation with Russia", The Nonproliferationof nuclear energy see for Russia, Trenin Dmitri. "Russia`s Nuclear Policy in the 21 st Century Environment",

Grigoriadis, Theocharis N

2009-01-01T23:59:59.000Z

231

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

E-Print Network (OSTI)

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

Grigoriadis, Theocharis N

2009-01-01T23:59:59.000Z

232

Comparative technology and public policy: The development of the nuclear power reactor in six nations  

Science Journals Connector (OSTI)

This essay proposes an analytic framework to compare the development and commercialization of a number of advanced civilian technologies. This framework emphasizes the multiple institutional actors and their obje...

Peter DeLeon

1980-02-01T23:59:59.000Z

233

Semi-Annual Report 2008 Page 1 SKCSwedish Center forNuclear Technology  

E-Print Network (OSTI)

in nuclear power plants 17 Study of post-dryout heat transfer and internal structure of annular and mist two Progress in some of the research projects 11 Development of an integrated neutronic / thermal-hydraulic tool for noise analysis 11 Uncertainty and sensitivity analysis applied to the simulation

Haviland, David

234

Research trends in neutron activation analysis in nuclear science and technology: a global perspective  

Science Journals Connector (OSTI)

This paper quantitatively analyses the growth and development of research in Neutron Activation Analysis (NAA) in terms of publications. As per the International Nuclear Information System (INIS) database during 1993-2007, a total of 6491 publications were published. The highest number of papers in a year (615) was published in 2004. The average number of publications published per year was 432.73. Japan topped the list with 605 publications followed by the USA with 468, Brazil with 449, China with 442, the Russian Federation with 324 and India with 316. The authorship and collaboration trend is towards multi-authored papers. Researchers in Japan, Brazil and China are more inclined to work in larger groups. The highly productive institutions were Instituto de Pesquisas Energeticas e Nucleares (IPEN), Sao Paulo, Brazil with 281 publications; Bhabha Atomic Research Centre, Mumbai, India with 257; Institute of High Energy Physics, Academia Sinica, Beijing, China with 162; and Japan Atomic Energy Agency, Tokai, Ibaraki, Japan with 140. The journals most preferred by the scientists for the publication of papers are the Journal of Radioanalytical and Nuclear Chemistry with 1204 papers, followed by Applied Radiation and Isotopes with 116 papers, and Nuclear Instruments and Methods in Physics Research-A with 84 papers.

Anil Sagar; B.S. Kademani; Vijai Kumar

2009-01-01T23:59:59.000Z

235

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)

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

Srivastava, Kumar Vaibhav

236

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

E-Print Network (OSTI)

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/

Grigoriadis, Theocharis N

2009-01-01T23:59:59.000Z

237

New Cordierite Diesel Particulate Filters for Catalyzed and Non...  

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

RESEARCH CONFERENCE (DEER 2006) PRESENTATIONS Combination and Integration of DPF-SCR Aftertreatment Technologies Advanced High Porosity Ceramic Honeycomb Wall Flow Filters...

238

Filter systems for IGCC applications  

SciTech Connect

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.

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

1995-11-01T23:59:59.000Z

239

New technology for purging the steam generators of nuclear power plants  

SciTech Connect

A technology for removal of undissolved impurities from a horizontal steam generator using purge water is developed on the basis of a theoretical analysis. A purge with a maximal flow rate is drawn off from the zone with the highest accumulation of sludge in the lower part of the steam generator after the main circulation pump of the corresponding loop is shut off and the temperatures of the heat transfer medium at the inlet and outlet of the steam generator have equilibrated. An improved purge configuration is used for this technology; it employs shutoff and regulator valves, periodic purge lines separated by a cutoff fixture, and a D{sub y} 100 drain union as a connector for the periodic purge. Field tests show that the efficiency of this technology for sludge removal by purge water is several times that for the standard method.

Budko, I. O.; Kutdjusov, Yu. F.; Gorburov, V. I. [Scientific-Research Center for Energy Technology 'NICE Centrenergo' (Russian Federation); Rjasnyj, S. I. [JSC 'The All-Rissia Nuklear Power Engineering Research and Development Institute' (VNIIAM) (Russian Federation)

2011-07-15T23:59:59.000Z

240

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

SciTech Connect

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.

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

1982-03-01T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear filter technology" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


241

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

SciTech Connect

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.

Wittenbrock, N. G.

1982-01-01T23:59:59.000Z

242

Developments of Spent Nuclear Fuel Pyroprocessing Technology at Idaho National Laboratory  

SciTech Connect

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.

Michael F. Simpson

2012-03-01T23:59:59.000Z

243

Gas Filter Testing Methods  

Science Journals Connector (OSTI)

Gas filtration of air in the cleanroom is carried out with HEPA (high- ... filter. The ambient air filters for the cleanroom are relatively fragile and require great care...

Alvin Lieberman

1992-01-01T23:59:59.000Z

244

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

245

SPACE-R thermionic space nuclear power system: Design and technology demonstration. Monthly report for 1 August 1994--1 September 1994  

SciTech Connect

The objective of this program is to design, develop, demonstrate, and advance the technology for thermionic space nuclear power system (TI-SNPS) to meet key functional requirements with reliable 5{approximately}40 kWe output and 18-month near-term/10-year long-term goals. A 40 kWe TI-SNPS point design will be prepared, and key technologies and critical components supporting that design will be validated. This program will produce an assessed design of a 40 kWe-EOL space nuclear power system. Phase 1 will provide for the performance of parametric trade studies and demonstration of key technologies, resulting in a preferred conceptual design for the TI-SNPS. The focus of the tasks is technology validation drive by the system design.

Not Available

1994-10-01T23:59:59.000Z

246

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

SciTech Connect

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

NONE

1980-12-31T23:59:59.000Z

247

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

E-Print Network (OSTI)

Nuclear Fuel, Nuclear 燛ngineering 燼nd Technology, 爄n Engineering -? Nuclear 燛ngineering and 爐he 爄n 燛ngineering -? Nuclear 燛ngineering and 爐he

Djokic, Denia

2013-01-01T23:59:59.000Z

248

Fuel Cycle Technologies Near Term Planning for Storage and Transportation of Used Nuclear Fuel  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Fuels Storage Fuels Storage and Transportation Planning Project (NFST) Program Status Jeff Williams Project Director National Transportation Stakeholders Forum Buffalo, New York May 2013 2 飦 "With the appropriate authorizations from Congress, the Administration currently plans to implement a program over the next 10 years that: 飩 Sites, designs and licenses, constructs and begins operations of a pilot interim storage facility by 2021 with an initial focus on accepting used nuclear fuel from shut-down reactor sites; 飩 Advances toward the siting and licensing of a larger interim storage facility to be available by 2025 that will have sufficient capacity to provide flexibility in the waste management system and allows for acceptance of enough used

249

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

E-Print Network (OSTI)

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

Grigoriadis, Theocharis N

2009-01-01T23:59:59.000Z

250

Recirculating electric air filter  

DOE Patents (OSTI)

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.

Bergman, W.

1985-01-09T23:59:59.000Z

251

Hepa filter dissolution process  

DOE Patents (OSTI)

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.

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

1994-01-01T23:59:59.000Z

252

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

SciTech Connect

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.

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

2003-08-01T23:59:59.000Z

253

ELECTROSTATICALLY ENHANCED BARRIER FILTER COLLECTION  

SciTech Connect

This work was performed through the University of North Dakota (UND) Chemical Engineering Department with assistance from UND's Energy & Environmental Research Center. This research was undertaken in response to the U.S. Department of Energy Federal Technology Center Program Solicitation No. DE-PS26-99FT40479, Support of Advanced Coal Research at U.S. Universities and Colleges. Specifically, this research was in support of the UCR Core Program and addressees Topic 1, Improved Hot-Gas Contaminant and Particulate Removal Techniques, introducing an advanced design for particulate removal. Integrated gasification combined cycle (IGCC) offers the potential for very high efficiency and clean electric generation. In IGCC, the product gas from the gasifier needs to be cleaned of particulate matter to avoid erosion and high-temperature corrosion difficulties arising with the turbine blades. Current methods involve cooling the gases to {approx}100 C to condense alkalis and remove sulfur and particulates using conventional scrubber technology. This ''cool'' gas is then directed to a turbine for electric generation. While IGCC has the potential to reach efficiencies of over 50%, the current need to cool the product gas for cleaning prior to firing it in a turbine is keeping IGCC from reaching its full potential. The objective of the current project was to develop a highly reliable particulate collector system that can meet the most stringent turbine requirements and emission standards, can operate at temperatures above 1500 F, is applicable for use with all U.S. coals, is compatible with various sorbent injection schemes for sulfur and alkali control, can be integrated into a variety of configurations for both pressurized gasification and combustion, increases allowable face velocity to reduce filter system capital cost, and is cost-competitive with existing technologies. The collector being developed is a new concept in particulate control called electrostatically enhanced barrier filter collection (EBFC). This concept combines electrostatic precipitation (ESP) with candle filters in a single unit. Similar technology has been recently proven on a commercial scale for atmospheric applications, but needed to be tested at high temperatures and pressures. The synergy obtained by combining the two control technologies into a single system should actually reduce filter system capital and operating costs and make the system more reliable. More specifically, the ESP is expected to significantly reduce candle filter load and also to limit ash reintrainment, allowing for full recovery of baseline pressure drop during backpulsing of the filters.

John Erjavec; Michael D. Mann; Ryan Z. Knutson; Michael L. Swanson; Michael E. Collings

2003-06-01T23:59:59.000Z

254

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

E-Print Network (OSTI)

CV SIDNEY YIP Professor Emeritus of Nuclear Science and Engineering Massachusetts Institute.S. (Nuclear Engineering, 1959), and Ph.D. (Nuclear Engineering, 1962), all from the University of Michigan Professor (1965-69), Department of Nuclear Engineering, MIT, Research Associate (1963-65, Cornell University

Chen, Sow-Hsin

255

Cooperative efforts to improve nuclear materials accounting, control and physical protection at the National Science Center, Kharkov Institute of Physics and Technology  

SciTech Connect

The US Department of Energy (DOE) and the Ukrainian Government are engaged in a program of cooperation to enhance the nonproliferation of nuclear weapons by developing a strong national system of nuclear material protection, control, and accounting (MPC and A). This paper describes the capabilities and work of the Kharkov Institute of Physics and Technology (KIPT) and cooperative efforts to improve MPC and A at this facility. It describes how these cooperative efforts grew out of Ukraine`s decision to become a non-nuclear weapon state and the shortcomings in MPC and A that developed at KIPT after the disintegration of the former Soviet Union. It also envisions expanded future cooperation in other areas of nuclear materials management.

Zelensky, V.F.; Mikhailov, V.A. [Kharkov Inst. of Physics and Technology (Ukraine). National Science Center

1996-12-31T23:59:59.000Z

256

Review of Diesel Emission Control Technology  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Diesel Emission Control Technology Tim Johnson August 2002 2 Outline * Introduction - Regulatory update and technology approaches * Ultrafines * Filters * NOx - LNC - SCR - LNT *...

257

Fail Save Shut Off Valve for Filtering Systems Employing Candle Filters  

NLE Websites -- All DOE Office Websites (Extended Search)

Fail Save Shut Off Fail Save Shut Off Valve for Filtering Systems Employing Candle Filters Opportunity The Department of Energy's National Energy Technology Laboratory (NETL) is seeking licensing partners interested in implementing United States Patent Number 6,981,516 entitled "Fail save shut off valve for filtering systems employing candle filters." Disclosed in this patent is a novel fail save shut off valve system that allows fluid flow during normal operational conditions, but prevents the flow of fluids in the event of system failure upstream that causes over- pressurization. It is particularly well suited for use in conjunction with hot gas filtering systems, which utilize ceramic candle filters. Used in such a hot gas system, the fail save valve stops the flow

258

Nuclear choices  

SciTech Connect

This book contains part of the series New Liberal Arts, which is intended to make science and technology more accessible to students of the liberal arts. Volume in hand provides a comprehensive, multifaceted examination of nuclear energy, in nontechnical terms. Wolfson explains the basics of nuclear energy and radiation, nuclear power..., and nuclear weapons..., and he invites readers to make their own judgments on controversial nuclear issues. Illustrated with photos and diagrams. Each chapter contains suggestions for additional reading and a glossary. For policy, science, and general collections in all libraries. (ES) Topics contained include Atoms and nuclei. Effects and uses of radiation. Energy and People. Reactor safety. Nuclear strategy. Defense in the nuclear age. Nuclear power, nuclear weapons, and nuclear futures.

Wolfson, R.

1991-01-01T23:59:59.000Z

259

Technology Transfer: Available Technologies  

NLE Websites -- All DOE Office Websites (Extended Search)

test test Please refer to the list of technologies below for licensing and research collaboration availability. If you can't find the technology you're interested in, please contact us at TTD@lbl.gov. Energy ENERGY EFFICIENT TECHNOLOGIES Aerosol Sealing Aerosol Remote Sealing System Clog-free Atomizing and Spray Drying Nozzle Air-stable Nanomaterials for Efficient OLEDs Solvent Processed Nanotube Composites OLEDS with Air-stable Structured Electrodes APIs for Online Energy Saving Tools: Home Energy Saver and EnergyIQ Carbon Dioxide Capture at a Reduced Cost Dynamic Solar Glare Blocking System Electrochromic Device Controlled by Sunlight Electrochromic Windows with Multiple-Cavity Optical Bandpass Filter Electrochromic Window Technology Portfolio Universal Electrochromic Smart Window Coating

260

Nuclear Hydrogen Initiative  

NLE Websites -- All DOE Office Websites (Extended Search)

Advanced Nuclear Research Advanced Nuclear Research Office of Nuclear Energy, Science and Technology FY 2003 Programmatic Overview Nuclear Hydrogen Initiative Nuclear Hydrogen Initiative Office of Nuclear Energy, Science and Technology Henderson/2003 Hydrogen Initiative.ppt 2 Nuclear Hydrogen Initiative Nuclear Hydrogen Initiative Program Goal * Demonstrate the economic commercial-scale production of hydrogen using nuclear energy by 2015 Need for Nuclear Hydrogen * Hydrogen offers significant promise for reduced environmental impact of energy use, specifically in the transportation sector * The use of domestic energy sources to produce hydrogen reduces U.S. dependence on foreign oil and enhances national security * Existing hydrogen production methods are either inefficient or produce

Note: This page contains sample records for the topic "nuclear filter technology" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


261

U.S. Department of Energy Roadmap on Instrumentation, Controls, and Human-Machine Interface Technologies in Current and Future Nuclear Power Plants  

SciTech Connect

The U.S. Department of Energy (DOE) Office of Nuclear Energy (NE) recently sponsored the creation of a roadmap for instrumentation, controls, and human-machine interface (ICHMI) technology development. The roadmap represents the collective efforts of a group of subject matter experts from the DOE national laboratories, academia, vendors, the U.S. Nuclear Regulatory Commission (NRC), and utilities. It is intended to provide the underpinnings to the government sponsored ICHMI research, development, and demonstration (RD&D) performed in the United States for the next several years. A distinguishing feature of this roadmapping effort is that it is not limited to a technology progression plan but includes a detailed rationale, aimed at the nonspecialist, for the existence of a focused ICHMI RD&D program. Eight specific technology areas were identified for focused RD&D as follows: (1) sensors and electronics for harsh environments,(2) uncertainty characterization for diagnostics/prognostics applications, (3) quantification of software quality for high-integrity digital applications, (4) intelligent controls for nearly autonomous operation of advanced nuclear plants, (5) plant network architecture, (6) intelligent aiding technology for operational support, (7) human system interaction models and analysis tools, and (8) licensing and regulatory challenges and solutions.

Holcomb, David Eugene [ORNL] [ORNL

2007-01-01T23:59:59.000Z

262

Global Nuclear Energy Partnership Fact Sheet - Develop Enhanced Nuclear  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

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

263

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

SciTech Connect

The eFRMAC enterprise is a suite of technologies and software developed by the United States Department of Energy, National Nuclear Security Administration抯 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.

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

2013-07-01T23:59:59.000Z

264

Diesel particulate filters  

Science Journals Connector (OSTI)

Is the broad market introduction of diesel particulate filters throughout Europe wishful thinking or reality? The challenges facing the introduction of diesel particulate filters with a fuel-borne catalyst...

Pierre Macaudi鑢e; Laurent Rocher; Wolfgang Naschke

2004-04-01T23:59:59.000Z

265

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

E-Print Network (OSTI)

Making the World Safe for Nuclear Energy 65 John Deutch for Nuclear Energy John Deutch,Arnold Kanter,Ernest Moniz and Daniel Poneman The discovery of secret in countries from the United States and some European states to China. To succeed, nuclear energy must overcome

Deutch, John

266

An Overview of strategic measures to assess workforce needs and ensure technology transfer to meet current and future nuclear power operations  

SciTech Connect

Between 1956 and 1989, the number of operating commercial nuclear power plants in the United States increased from none to 109. With the exception of a few plants that were still in final construction, no new nuclear power plants were ordered in the United States as the new millennium began. In 2005, the federal government pronounced the need for new electric power generating systems during the first quarter of the 21. century. The need comes from a desire to curb our reliance on fossil fuels, as well as to provide for a cleaner environment. One of those fuel systems noted was nuclear energy. Given the time between the last active period of nuclear power plant development and construction, there is a need to supply a talented and well-prepared workforce to operate the new plants. It will also be necessary to assess the needs of our current fleet of operating nuclear power plants, of which many are in the process of re-licensing, yet also facing an aging plant workforce. This paper will review and discuss measures to assess diverse workforce needs and technology transfer to meet current licensing requirements as that of future nuclear power plant development in the United States. (authors)

Vincenti, J.R. [acuri.net, 1344 Curtin Street, State College, PA (United States); Stigers, R.A. [Senior Health Physicist-Radwaste, PPL Susquehanna, Berwick, PA (United States)

2007-07-01T23:59:59.000Z

267

Adaptive and Temporallydependent Document Filtering  

E-Print Network (OSTI)

Adaptive and Temporally颅dependent Document Filtering een wetenschappelijke proeve op het gebied van . . . . . . . . . . . . . . . . . . . . . 1 1.2 Document Filtering . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 1.3 Filtering Filtering Track 57 5.1 What is TREC . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 57 5

Arampatzis, Avi

268

Innovations in Nuclear Infrastructure  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Innovations in Nuclear Infrastructure Innovations in Nuclear Infrastructure and Education (INIE) Innovations in Nuclear Infrastructure and Education (INIE) Presented to the Nuclear Energy Research Advisory Committee Crystal City, Virginia John Gutteridge Director, University Programs Office of Nuclear Energy, Science and Technology September 30 - October 1, 2002 Office of Nuclear Energy, Science and Technology Gutteridge/Sep-Oct_02 INIE-NERAC.ppt (2) INIE The Stimuli .... INIE The Stimuli .... 6 Declining number of operating university research/training reactors 6 Dwindling student population in nuclear engineering 6 Closing or loss of identity of university nuclear engineering programs 6 Looming shortage of nuclear engineering graduates 6 Threat of additional reactor closures -- Cornell, Michigan, MIT

269

Filtering diesel exhaust gases with ceramic filters  

Science Journals Connector (OSTI)

Results are given from three test series on a ceramic filter for diesel exhausts. In the first and second series, use was made of diesel fuel (in the summer), while in...

A. Yu. Val抎berg; A. N. Tsedilin; T. O. Kosogorova

2008-03-01T23:59:59.000Z

270

Nuclear Data Program - Nuclear Engineering Division (Argonne)  

NLE Websites -- All DOE Office Websites (Extended Search)

Data Program Data Program Nuclear Data Program Overview Current Projects & Recent Activities Collaborating Organizations Publications Nuclear Data Measurements (NDM) Reports Experimental Nuclear Data Resources Contact ND Program Related Resources Other Major Programs Work with Argonne Contact us For Employees Site Map Help Join us on Facebook Follow us on Twitter NE Division on Flickr Nuclear Data Program We contribute to the development of comprehensive nuclear reactions and nuclear structure databases, including nuclear data measurement, analysis, modeling and evaluation methodologies, that are implemented in basic science research and advanced nuclear technologies. Bookmark and Share Recent Events Nuclear Structure 2012 Conference Argonne National Laboratory hosted the

271

Evaluation of a Cyclone and Hot Gas Filter System  

NLE Websites -- All DOE Office Websites (Extended Search)

a Cyclone and a Cyclone and Hot Gas Filter System Description The Wabash River Coal Gasification Plant uses an oxygen-blown E-Gas gasifier technology, owned by ConocoPhillips, which produces fuel gas containing significant amounts of fine particulates. Currently, particulates are cleaned from the fuel gas with metal candle filters. These filters require two costly plant shut-downs per year for cleaning or replacement. During the U.S Department of Energy-supported project

272

Moving granular-bed filter development program. Topical report  

SciTech Connect

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.

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

1994-04-01T23:59:59.000Z

273

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

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.

Hofmann, P.L.; Breslin, J.J. (eds.)

1981-01-01T23:59:59.000Z

274

Linear phase compressive filter  

DOE Patents (OSTI)

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.

McEwan, Thomas E. (Livermore, CA)

1995-01-01T23:59:59.000Z

275

Filter Replacement Activities Complete  

NLE Websites -- All DOE Office Websites (Extended Search)

airflow levels now that both filter units are operational. Additionally, teams can resume entries to evaluate the condition of the underground facility and verify that...

276

Modeling Multi Output Filtering Effects in PCMOS  

E-Print Network (OSTI)

Modeling Multi Output Filtering Effects in PCMOS Anshul Singh*, Arindam Basu, Keck-Voon Ling, Nanyang Technological University (NTU), Singapore *NTU-Rice Institute of Sustainable and Applied Infodynamics (ISAID), NTU, Singapore $School of Computer Engineering, NTU, Singapore 搂School of ECE, Georgia

Mooney, Vincent

277

NISTIR 7516 Forensic Filtering of Cell  

E-Print Network (OSTI)

NISTIR 7516 Forensic Filtering of Cell Phone Protocols Aur茅lienDelaitre WayneJansen #12;ii Forensic of Standards and Technology Interagency Report 42 pages (2008) iii #12;Abstract Phone managers are non-forensic managers are sometimes used by forensic investigators to recover data from a cell phone when no suitable

278

Evaluation of Alternative Filter Media for the Rotary Microfilter  

SciTech Connect

M. R. Poirier , D. T. Herman & R. Bhave (2012) Evaluation of Alternative Filter Media for the Rotary Microfilter, Separation Science and Technology, 47:14-15, 2108-2114

Poirier, M. [Savannah River National Laboratory, Environmental and Chemical Process Technology; Herman, [Savannah River National Laboratory, Environmental and Chemical Process Technology; Bhave, Ramesh R [ORNL

2012-01-01T23:59:59.000Z

279

Nuclear Deterrence  

NLE Websites -- All DOE Office Websites (Extended Search)

Nuclear Deterrence Nuclear Deterrence Nuclear Deterrence LANL's mission is to develop and apply science and technology to ensure the safety, security, and effectiveness of the U.S. nuclear deterrent; reduce global threats; and solve other emerging national security and energy challenges. April 12, 2012 A B-2 Spirit bomber refuels from a KC-135 Stratotanker A B-2 Spirit bomber refuels from a KC-135 Stratotanker. Contact Operator Los Alamos National Laboratory (505) 667-5061 Charlie McMillan, Director: "For the last 70 years there has not been a world war, and I have to think that our strong deterrent has something to do with that fact." Mission nuclear weapons Charlie McMillan, Director of Los Alamos National Laboratory 1:06 Director McMillan on nuclear deterrence While the role and prominence of nuclear weapons in U.S. security policy

280

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

E-Print Network (OSTI)

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 ...

Achorn, Ted Glen

1991-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear filter technology" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


281

Review of the Potential of Nuclear Hydrogen for Addressing Energy Security and Climate Change  

Science Journals Connector (OSTI)

Technical Paper / Safety and Technology of Nuclear Hydrogen Production, Control, and Management / Nuclear Hydrogen Production

James E. O'Brien

282

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

SciTech Connect

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.

Bud'ko, I. O. [JSC NIITsE 'Tsentrenergo' (Russian Federation)] [JSC NIITsE 'Tsentrenergo' (Russian Federation); Zhukov, A. G. [Rostov Nuclear Power Plant (Russian Federation)] [Rostov Nuclear Power Plant (Russian Federation)

2013-11-15T23:59:59.000Z

283

METAL FILTERS FOR PRESSURIZED FLUID BED COMBUSTION (PFBC) APPLICATIONS  

SciTech Connect

Advanced coal and biomass-based gas turbine power generation technologies (IGCC, PFBC, PCFBC, and Hipps) are currently under development and demonstration. Efforts at the Siemens Westinghouse Power Corporation (SWPC) have been focused on the development and demonstration of hot gas filter systems as an enabling technology for power generation. As part of the demonstration effort, SWPC has been actively involved in the development of advanced filter materials and component configuration, has participated in numerous surveillance programs characterizing the material properties and microstructure of field-tested filter elements, and has undertaken extended, accelerated filter life testing programs. This report reviews SWPC's material and component assessment efforts, identifying the performance, stability, and life of porous commercial metal, advanced alloy, and intermetallic filters under simulated, pressurized fluidized-bed combustion (PFBC) conditions.

M.A. Alvin

2004-01-02T23:59:59.000Z

284

Reconversion of nuclear weapons  

E-Print Network (OSTI)

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?

Kapitza, Sergei P

1993-01-01T23:59:59.000Z

285

Nuclear power, nuclear eapons link argued  

Science Journals Connector (OSTI)

Nuclear power, nuclear eapons link argued ... The problem of the spread of nuclear weapons to nations not currently possessing them梥o-called horizontal proliferation梠ften is linked to development of commercial nuclear power. ... However, John P. Holdren, professor of energy and resources at the University of California, Berkeley, maintains that commercial nuclear power is linked intimately to horizontal proliferation and that the development of alternative energy technologies is crucial to prevent the spread. ...

1982-02-08T23:59:59.000Z

286

Argonne Historical News Releases about Nuclear Energy  

NLE Websites -- All DOE Office Websites (Extended Search)

Releases Releases About Director's Welcome Organization Achievements Highlights Fact Sheets, Brochures & Other Documents Multimedia Library Visit Argonne Work with Argonne Contact us Nuclear Energy Why Nuclear Energy? Why are some people afraid of Nuclear Energy? How do nuclear reactors work? Cheaper & Safer Nuclear Energy Helping to Solve the Nuclear Waste Problem Nuclear Reactors Nuclear Reactors Early Exploration Training Reactors Basic and Applied Science Research LWR Technology Development BORAX-III lighting Arco, Idaho (Press Release) Heavy Water and Graphite Reactors Fast Reactor Technology Integral Fast Reactor Argonne Reactor Tree CP-1 70th Anniversary CP-1 70th Anniversary Argonne's Nuclear Science and Technology Legacy Argonne's Nuclear Science and Technology Legacy

287

Remotely serviced filter and housing  

DOE Patents (OSTI)

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.

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

1988-09-27T23:59:59.000Z

288

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

E-Print Network (OSTI)

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...

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

289

Nuclear Science & Engineering  

E-Print Network (OSTI)

. 1 Nuclear Science & Engineering Nuclear Energy Present and Future Ian H. Hutchinson Head, Department of Nuclear Science and Engineering CoPrincipal, Alcator Tokamak Project, Plasma Science and Fusion Center Massachusetts Institute of Technology Outline: Nuclear Power in the US and the World Limitations

290

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

SciTech Connect

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.

Not Available

1993-05-01T23:59:59.000Z

291

Hacks and Filters  

Science Journals Connector (OSTI)

In this chapter you have learned that hacks and filters can be an important weapon ... in any CSS developer抯 arsenal. However, hacks need to be used sparingly, and preferably ... resort. If you do need to use hacks

2006-01-01T23:59:59.000Z

292

Chernobyl nuclear accident: Effects on food. (Latest citations from the Food Science and Technology Abstracts database). Published Search  

SciTech Connect

The bibliography contains citations concerning studies and measurements of the radioactive contamination by the Chernobyl nuclear reactor accident of food and the food chain. The studies cover meat and dairy products, vegetables, fish, food chains, and radioactive contamination of agricultural farms and lands. (Contains 250 citations and includes a subject term index and title list.)

NONE

1993-09-01T23:59:59.000Z

293

21NUCLEAR ENGINEERING AND TECHNOLOGY, VOL.41 NO.1 FEBRUARY 2009 METALLIC INTERFACES IN HARSH CHEMO-MECHANICAL  

E-Print Network (OSTI)

, Cambridge, MA 02139, USA 3 Center for Advanced Nuclear Energy Systems, MIT * Corresponding author. E layer also greatly facilitates the migration of embrittling species such as oxygen and chloride to new reactive zones in the material, the transport is again coupled to an evolving thermal, microstructural

Yildiz, Bilge

294

Sampled data lattice filters  

E-Print Network (OSTI)

SAMPLED DATA LATTICE FILTERS A Thesis by WILLIAM TERRY THRIFT III Submitted to the Graduate College of Texas A&M University in partial fulfillment of the requirements for the degree of MASTER OF SCIENCE December 1979 Major Subfect...: Electrical Engineering SAMPLED DATA LATTICE FILTERS A Thesis by WILLIAM TERRY THRIFT III Approved as to style and content by: (Chair an of Committee) (Hea f Department) (Member) (Member) (Member) (Member) December 1979 ABSTRACT Sampled Data...

Thrift, William Terry

2012-06-07T23:59:59.000Z

295

Closure of 324 Facility potential HEPA filter failure unreviewed safety questions  

SciTech Connect

This document summarizes the activities which occurred to resolve an Unreviewed Safety Question (USQ) for the 324 Facility [Waste Technology Engineering Laboratory] involving Potential HEPA Filter Breach. The facility ventilation system had the capacity to fail the HEPA filters during accident conditions which would totally plug the filters. The ventilation system fans were modified which lowered fan operating parameters and prevented HEPA filter failures which might occur during accident conditions.

Enghusen, M.B.

1997-11-07T23:59:59.000Z

296

Kalman Filtering Jur van den Berg  

E-Print Network (OSTI)

Kalman Filtering Jur van den Berg #12;Kalman Filtering 路 (Optimal) estimation of the (hidden) state

van den Berg, Jur

297

Nuclear Energy & Energy Security  

Science Journals Connector (OSTI)

Safety issues related to use of nuclear energy and secure operation of nuclear installations are mail stones of great importance. Although none of technologies producing energy are absolutely safe it is obvious t...

Jumber Mamasakhlisi

2010-01-01T23:59:59.000Z

298

Energy and technology review  

SciTech Connect

Research is described in three areas, high-technology design of unconventional, nonnuclear weapons, a model for analyzing special nuclear materials safeguards decisions, and a nuclear weapons accident exercise (NUWAX-81). (GHT)

Not Available

1981-10-01T23:59:59.000Z

299

Remotely serviced filter and housing  

DOE Patents (OSTI)

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.

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

1987-07-22T23:59:59.000Z

300

Filters for cathodic arc plasmas  

DOE Patents (OSTI)

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.

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

2002-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear filter technology" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


301

DOE Initiates Environmental Impact Statement for Global Nuclear...  

Office of Environmental Management (EM)

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

302

Measurement of 37Ar to support technology for On-site Inspection under the Comprehensive Nuclear-Test-Ban Treaty  

E-Print Network (OSTI)

On-Site Inspection (OSI) is a key component of the verification regime for the Comprehensive Nuclear-Test-Ban Treaty (CTBT). Measurements of radionuclide isotopes created by an underground nuclear explosion are a valuable signature of a Treaty violation. Argon-37 is produced from neutron interaction with calcium in soil, 40Ca(n,{\\alpha})37Ar. For OSI, the 35-day half-life of 37Ar provides both high specific activity and sufficient time for completion of an inspection before decay limits sensitivity. This paper presents a low-background internal-source gas proportional counter with an 37Ar measurement sensitivity level equivalent to 45.1 mBq/SCM in whole air.

C. E. Aalseth; A. R. Day; D. A. Haas; E. W. Hoppe; B. J. Hyronimus; M. E. Keillor; E. K. Mace; J. L. Orrell; A. Seifert; V. T. Woods

2010-08-04T23:59:59.000Z

303

6 Nuclear Fuel Designs  

NLE Websites -- All DOE Office Websites (Extended Search)

Message from the Director Message from the Director 2 Nuclear Power & Researrh Reactors 3 Discovery of Promethium 4 Nuclear Isotopes 4 Nuclear Medicine 5 Nuclear Fuel Processes & Software 6 Nuclear Fuel Designs 6 Nuclear Safety 7 Nuclear Desalination 7 Nuclear Nonproliferation 8 Neutron Scattering 9 Semiconductors & Superconductors 10 lon-Implanted Joints 10 Environmental Impact Analyses 11 Environmental Quality 12 Space Exploration 12 Graphite & Carbon Products 13 Advanced Materials: Alloys 14 Advanced Materials: Ceramics 15 Biological Systems 16 Biological Systems 17 Computational Biology 18 Biomedical Technologies 19 Intelligent Machines 20 Health Physics & Radiation Dosimetry 21 Radiation Shielding 21 Information Centers 22 Energy Efficiency: Cooling & Heating

304

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

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

Million for Nuclear Fuel Cycle Technology Research and Development Department of Energy Awards 15 Million for Nuclear Fuel Cycle Technology Research and Development August 1,...

305

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

SciTech Connect

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, 揜adioactive 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.

Bryant, Jeffrey W.

2010-08-12T23:59:59.000Z

306

Nuclear Detection and Forensics | Y-12 National Security Complex  

NLE Websites -- All DOE Office Websites (Extended Search)

Nuclear Detection and ... Nuclear Detection and Forensics We have a firm foundation to support the science and technology needed for the important, growing areas of nuclear...

307

Argonne National Laboratory - West's approach to filter characterization.  

SciTech Connect

Like other DOE facilities, ANL-W uses a variety of nuclear grade, industrial grade, or furnace-type particulate filters to control airborne radioactivity and hazardous contaminants in radiological containment structures or processes. As designed, these filters entrain and ultimately concentrate contaminants in the media. Toxic metal contaminants include cadmium, chromium, lead; and mercury present in sufficient concentrations to exhibit the hazardous waste characteristic of toxicity as defined in 40 CFR 261.24. Radionuclide contaminants deposited in the media may at times accumulate in sufficient quantity to classify the filter as transuranic or remote-handled waste. Upon their removal from the ventilation system, these particulate filters become wastes, which must be characterized to determine their hazardous and radioactive classifications. A well defined filter characterization process is essential for the proper/consistent waste characterization and minimization and for maintaining personnel radiological exposures as-low-as-reasonably-achievable (ALARA) (1,2). ANL-W has developed an approach to filter sampling and characterization to meet these needs. The ANL-W filter sampling and characterization process is designed to ensure representative sampling and/or process knowledge is utilized in characterizing the filters. The data obtained through sampling and/or process knowledge is used to show compliance with the Resource Conservation and Recovery Act (3) and Treatment/Storage/Disposal Facility Waste Acceptance Criteria. The ANL-W filter characterization involves the collection of process information, filter handling and sampling, sample analysis, data management filter characterization, and waste handling. Each element of the process is streamlined to ensure proper characterization while minimizing radiological exposure to maintenance workers, samplers, laboratory personnel, and waste handlers.

Miller, T. A.

1999-02-10T23:59:59.000Z

308

Nuclear Thermal Rocket/Stage Technology Options for NASA's Future Human Exploration Missions to the Moon and Mars  

Science Journals Connector (OSTI)

The nuclear thermal rocket (NTR) provides a unique propulsion capability to planners and designers of future human exploration missions to the Moon and Mars. In addition to its high specific impulse (Isp ? 8501000 seconds) and engine thrust?to?weight ratio (? 310) the NTR can also be configured as a 揹ual mode system capable of generating stage electrical power. At present NASA is examining a variety of mission applications for the NTR ranging from an expendable 搒ingle burn trans?lunar injection (TLI) stage for NASA's 揊irst Lunar Outpost (FLO) mission to all propulsive 搈ulti?burn spacecraft supporting a 搒plit cargo/piloted sprint Mars mission architecture. Two 損roven solid core NTR concepts are examined ?one based on NERVA (Nuclear Engine for Rocket Vehicle Application)?derivative reactor (NDR) technology and a second concept which utilizes a ternary carbide 搕wisted ribbon fuel form developed by the Commonwealth of Independent States (CIS). Integrated systems and mission study results are used in designing 揳erobraked and 揳ll propulsive Mars vehicle concepts which are mass? and volume?compatible with both a reference 240 metric tonne (t) heavy lift launch vehicle (HLLV) and a smaller 120 t HLLV option. For the 揳erobraked scenario the 2010 piloted mission determines the size of the expendable trans?Mars injection (TMI) stage which is a growth version of the FLO TLI stage. An 揳ll?propulsive Moon/Mars mission architecture is also described which uses common 搈odular engine and stage hardware consisting of: (1) clustered 15 thousand pounds force (klbf) NDR or CIS engines; (2) two 搒tandardized liquid hydrogen (LH2) tank sizes; and (3) 揹ual mode NTR and refrigeration system technologies for long duration missions. The 搈odular NTR approach can form the basis for a 揻aster safer and cheaper space transportation system for tomorrow's piloted missions to the Moon and Mars.

Stanley K. Borowski; Robert R. Corban; Melissa L. McGuire; Erik G. Beke

1994-01-01T23:59:59.000Z

309

NETL: Gasification - Long-Term Candle Filter Tests  

NLE Websites -- All DOE Office Websites (Extended Search)

Long-Term Candle Filter Tests Long-Term Candle Filter Tests National Carbon Capture Center at the Power Systems Development Facility Southern Company Services, Inc. Project Number: NT0000749 Project Description The National Carbon Capture Center advancement of hot gas filtration technology provides the design for optimal, long-term evaluation of material performance for particulate control device (PCD) filter elements. Testing is performed using the commercially available Siemens PCD, due to its demonstrated excellent collection efficiency during normal operation. The PCD, located downstream of the primary gas cooler, houses up to 91 candle-type filter elements. They're currently used in the development of candle filters that can efficiently remove particulates at varying temperatures, using low-cost materials and innovative design.

310

Nuclear Energy Program  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

April 15, 2002 April 15, 2002 NERAC Spring 2002 Meeting Office of Nuclear Energy, Science and Technology Magwood/April15_02 NERAC.ppt (2) 2002 Will Be A Transition Year 2002 Will Be A Transition Year 6 Nuclear Power 2010 6 Major Program Developments 6 FY 2003 Budget Request Office of Nuclear Energy, Science and Technology Magwood/April15_02 NERAC.ppt (3) Nuclear Power 2010 Nuclear Power 2010 Nuclear Power 2010 is a new R&D initiative announced by Secretary Abraham on February 14, 2002. This initiative is designed to clear the way for the construction of new nuclear power plants by 2010. Office of Nuclear Energy, Science and Technology Magwood/April15_02 NERAC.ppt (4) Can We Build New U.S. Reactors By 2010? Yes! Can We Build New U.S. Reactors By 2010? Yes! Can Be Deployed by 2010

311

State-of-the-art of non-destructive testing methods and technologies for application to nuclear power plant safety-related concrete structures  

SciTech Connect

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: 昹ocating steel reinforcement and identification of its cover depth 昹ocating tendon ducts and identification of the condition of the grout materials 昫etection of cracking, voids, delamination, and honeycombing in concrete structures 昫etection of inclusions of different materials or voids adjacent to the concrete side of the containment liner 昺ethods capable of identification of corrosion occurrence on the concrete side of the containment liner.

Wiggenhauser, Herbert [BAM - Federal Institute for Materials Research and Testing, Berlin, D (Germany); Naus, Dan J. [Oak Ridge National Laboratory, Oak Ridge, TN (United States)

2014-02-18T23:59:59.000Z

312

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

SciTech Connect

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

Wiggenhauser, Dr. Herbert [Federal Institute for Materials Research and Testing (BAM)] [Federal Institute for Materials Research and Testing (BAM); Naus, Dan J [ORNL] [ORNL

2014-01-01T23:59:59.000Z

313

WaVPeak: picking NMR peaks through wavelet-based smoothing and volume-based filtering  

Science Journals Connector (OSTI)

......Tramontano Motivation: Nuclear magnetic resonance...the literature. The dataset comprises 32 2D and 3D...the last two decades, nuclear magnetic resonance...volume-based filtering. | Nuclear magnetic resonance...the literature. The dataset comprises 32 2D and 3D......

Zhi Liu; Ahmed Abbas; Bing-Yi Jing; Xin Gao

2012-04-01T23:59:59.000Z

314

Requirements for a Dynamic Solvent Extraction Module to Support Development of Advanced Technologies for the Recycle of Used Nuclear Fuel  

SciTech Connect

The Department of Energy's Nuclear Energy Advanced Modeling and Simulation (NEAMS) Program has been established to create and deploy next generation, verified and validated nuclear energy modeling and simulation capabilities for the design, implementation, and operation of future nuclear energy systems to improve the U.S. energy security. As part of the NEAMS program, Integrated Performance and Safety Codes (IPSC's) are being produced to significantly advance the status of modeling and simulation of energy systems beyond what is currently available to the extent that the new codes be readily functional in the short term and extensible in the longer term. The four IPSC areas include Safeguards and Separations, Reactors, Fuels, and Waste Forms. As part of the Safeguards and Separations (SafeSeps) IPSC effort, interoperable process models are being developed that enable dynamic simulation of an advanced separations plant. A SafeSepss IPSC 'toolkit' is in development to enable the integration of separation process modules and safeguards tools into the design process by providing an environment to compose, verify and validate a simulation application to be used for analysis of various plant configurations and operating conditions. The modules of this toolkit will be implemented on a modern, expandable architecture with the flexibility to explore and evaluate a wide range of process options while preserving their stand-alone usability. Modules implemented at the plant-level will initially incorporate relatively simple representations for each process through a reduced modeling approach. Final versions will incorporate the capability to bridge to subscale models to provide required fidelity in chemical and physical processes. A dynamic solvent extraction model and its module implementation are needed to support the development of this integrated plant model. As a stand-alone application, it will also support solvent development of extraction flowsheets and integrated safeguards approaches within the Fuel Cycle Research and Development (FCR&D) Program. The purpose of this document is to identify the requirements for this dynamic solvent extraction model to guide process modelers and code developers to produce a computational module that meets anticipated future needs.

Jack Law; Veronica Rutledge; Candido Pereira; Jackie Copple; Kurt Frey; John Krebs; Laura Maggos; Kevin Nichols; Kent Wardle; Pratap Sadasivan; Valmor DeAlmieda; David Depaoli

2011-06-01T23:59:59.000Z

315

Rotating drum filter  

DOE Patents (OSTI)

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).

Anson, Donald (Worthington, OH)

1990-01-01T23:59:59.000Z

316

Ozone decomposing filter  

DOE Patents (OSTI)

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.

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

1999-01-01T23:59:59.000Z

317

DEVELOPMENT OF AN ADHESIVE CANDLE FILTER SAFEGUARD DEVICE  

SciTech Connect

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

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

2002-01-01T23:59:59.000Z

318

Advanced nuclear precleaner  

SciTech Connect

This Phase II Small Business Innovation Research (SBIR) program`s goal is to develop a dynamic, self-cleaning air precleaner for high-efficiency particulate air (HEPA) filtration systems that would extend significantly the life of HEPA filter banks by reducing the particulate matter that causes filter fouling and increased pack pressure. HEPA filters are widely used in DOE, Department of Defense, and a variety of commercial facilities. InnovaTech, Inc. (Formerly Micro Composite materials Corporation) has developed a proprietary dynamic separation device using a concept called Boundary Layer Momentum Transfer (BLMT) to extract particulate matter from fluid process streams. When used as a prefilter in the HVAC systems or downstream of waste vitrifiers in nuclear power plants, fuel processing facilities, and weapons decommissioning factories, the BLMT filter will dramatically extend the service life and increase the operation efficiency of existing HEPA filtration systems. The BLMT filter is self cleaning, so there will be no degraded flow or increased pressure drop. Because the BLMT filtration process is independent of temperature, it can be designed to work in ambient, medium, or high-temperature applications. During Phase II, the authors are continuing development of the computerized flow simulation model to include turbulence and incorporate expansion into a three-dimensional model that includes airflow behavior inside the filter housing before entering the active BLMT device. A full-scale (1000 ACFM) prototype filter is being designed to meet existing HEPA filter standards and will be fabricated for subsequent testing. Extensive in-house testing will be performed to determine a full range of performance characteristics. Final testing and evaluation of the prototype filter will be conducted at a DOE Quality Assurance Filter Test Station.

Wright, S.R. [InnovaTech, Inc., Durham, NC (United States)

1997-10-01T23:59:59.000Z

319

Filter Press Building  

E-Print Network (OSTI)

"FILTER PRESS BUILDING" AVON LAKE WATER POLLUTION CONTROL CENTER HEAT PUMP HEATING AND COOLING SYSTEM William M. Bush, P.E. The Cleveland Electric Illuminating Company Cleveland, Ohio ABSTRACT The high heat value of the plant's treated wa..." of the thousands of homes in the com munity, we were able to recommend a system of heat recovery refrigeration cycles that would provide space conditioning at a fraction of the cost of natural gas. The all-electric recommendation was accepted because...

Bush, W. M.

320

Electrically-Assisted Diesel Particulate Filter Regeneration...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

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

Note: This page contains sample records for the topic "nuclear filter technology" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


321

Nuclear Energy  

Science Journals Connector (OSTI)

Nuclear Energy ... A brief summary of the history and key concepts of nuclear energy. ... Nuclear / Radiochemistry ...

Charles D. Mickey

1980-01-01T23:59:59.000Z

322

Nuclear batteries  

Science Journals Connector (OSTI)

Nuclear batteries ... Describes the structure, operation, and application of nuclear batteries. ... Nuclear / Radiochemistry ...

Alfred B. Garrett

1956-01-01T23:59:59.000Z

323

Materials Research Needs for Near-Term Nuclear Reactors  

Science Journals Connector (OSTI)

Technical Paper / NSF Workshop on the Research Needs of the Next Generation Nuclear Power Technology / Material

John R. Weeks

324

Sandia National Laboratories: National Security Missions: Nuclear...  

NLE Websites -- All DOE Office Websites (Extended Search)

& Technology National labs provide the science and technology to maintain and certify the nuclear stockpile in the absence of full-scale weapons testing. The facilities and...

325

DEVELOPMENT OF A CANDLE FILTER FAILURE SAFEGUARD DEVICE  

SciTech Connect

The full-flow mechanical safeguard device (FFMSGD) has been developed under contract to the National Energy Technology Laboratory (NETL) to address problems with the reliability of ceramic candle filter elements installed on high-temperature, high-pressure (HTHP) Hot Gas Cleanup (HGCU) filters. Although systems candle filters are expected to perform satisfactorily when in good operating condition, the failure of even a single filter element can increase the filter system outlet dust loading enough to potentially damage gas turbine blades, contaminate other downstream processes, and limit the availability of the power system. Filter failure safeguard devices that are installed on each individual candle filter element are envisioned as a guarantee of a candle filter system's ability to withstand some number of element failures and continue operation without these negative consequences. The intention of the FFMSGD is to provide this guarantee without incurring any significant pressure drop penalty or constraining the filter system's reverse-pulse cleaning procedures. The FFMSGD provides a clear flow path for filtered and reverse-flow cleaning gases when its filter element is intact, and activates to provide a positive mechanical seal against gas flow in either direction when its filter element breaks or fails. This activation is induced by the increase in the flow rate of gas through the device in event of filter failure. The FFMSGD is designed to be easily removed and reconditioned when the filter system is taken off line for routine maintenance. This report is intended to be issued with a companion appendix. As instructed in Section J.12 of Contract No. DE-AC26-99FT40678, all the restricted, proprietary, and patentable information (not yet disclosed through the patent application process) related to the FFMSGD and its evaluation under this contract has been included only in the appendix. This Final Report, which is available to the public, contains background information and general descriptions of the operating principles of the FFMSGD. This report also describes the results of various evaluations of the device at room temperature and in HTHP environments. This Final Report also includes discussions of commercialization issues. For clarity and completeness, all of the information contained in this Final Report has also been included in the appendix.

Todd R. Snyder

2002-03-29T23:59:59.000Z

326

USING TECHNOLOGY TO SUPPORT PROACTIVE MANAGEMENT OF MATERIALS DEGRADATION FOR THE U.S. NUCLEAR REGULATORY COMMISSION  

SciTech Connect

The majority of the U.S. reactor fleet is applying for license renewal to extend the operating life from the current 40 years to 60 years, and there is now active interest in extending the operating life to beyond 60 years. Many plants are also applying for increases in power rating and both of these changes increases the need for an improved understanding of materials degradation. Many materials degrade over time and much is known about the degradation of materials under normal environmental conditions; however, less is known about the characteristics of materials degradation when the environment is subject to higher than normal radiological conditions over extended periods of time. Significant efforts are being made by industrial, academic and regulatory groups worldwide to identify, classify and mitigate potential problems arising from degradation of components in this context. From a regulatory perspective, the U.S. Nuclear Regulatory Commission (USNRC) is very interested in being able to identify ways to insure their licensees proactively manage the identification of materials degradation and the mitigation of its effects. To date, the USNRC has consolidated 揼eneric programs for mitigating aging issues in the two volume Generic Aging Lessons Learned (GALL) Report (NUREG-1801) [1][2], and have encouraged applicants for license renewal to use these programs where applicable in their plant when applying for renew of their reactor抯 license. The USNRC has also published a comprehensive report entitled Expert Panel Report on Proactive Materials Degradation (NUREG/CR-6923) [3] that inventories the types of degradation mechanisms that could exist in each component of a Light Water Reactor (LWR) and each degradation mechanism is assessed regarding how much is known about mitigating its effects. Since the number of plant designs and materials used varies greatly within the U.S. fleet, there are many variations to implementing aging management programs (AMPs), requiring significant dialogs between the Licensee and the USNRC. These discussions are part of the licensing basis and as such are documented with up to multi-hundred page responses that are loosely coupled through the USNRC Agency-wide Document Access and Management System (ADAMS), which serves as an electronic records repository for the USNRC . These discussions have supported revisions to the GALL, including the revision that is being prepared as this paper is being written. The USNRC has sought the help of the Pacific Northwest National Laboratory to improve the staff抯 ability to navigate the significant numbers of documents that are generated in this process and to provide a forum for regulators, licensees and researchers to share knowledge in the efforts to improve the cyclic process for defining, applying, validating and re-defining AMPs. Work to date in this area is publicly accessible and this paper will describe that work and outline a potential path forward. The presenter will also demonstrate the capabilities of the PMMD information tools (http://pmmd.pnl.gov).

Taylor, W Boyd; Knobbs, Katherine J.; Carpenter, C. E. (Gene) [Gene; Malik, Shah

2010-07-19T23:59:59.000Z

327

TESTING OF THE SECOND GENERATION SPINTEK ROTARY FILTER -11357  

SciTech Connect

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.

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

2011-02-02T23:59:59.000Z

328

Relative Movements for Design of Commodities in Nuclear Power Plants  

Energy.gov (U.S. Department of Energy (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

329

Idaho HWMA/RCRA Closure Plan for Idaho Nuclear Technology and Engineering Center Tanks WM-182 and WM-183 - Rev. 2  

SciTech Connect

This document presents the plan for the closure of the Idaho Nuclear Technology and Engineering Center Tank Farm Facility tanks WM-182 and WM-183 in accordance with Idaho Hazardous Waste Management Act/Resource Conservation and Recovery Act interim status closure requirements. Closure of these two tanks is the first in a series of closures leading to the final closure of the eleven 300,000-gal tanks in the Tank Farm Facility. As such, closure of tanks WM-182 and WM-183 will serve as a proof-of-process demonstration of the waste removal, decontamination, and sampling techniques for the closure of the remaining Tank Farm Facility tanks. Such an approach is required because of the complexity and uniqueness of the Tank Farm Facility closure. This plan describes the closure units, objectives, and compliance strategy as well as the operational history and current status of the tanks. Decontamination, closure activities, and sampling and analysis will be performed with the goal of achieving clean closure of the tanks. Coordination with other regulatory requirements, such as U.S. Department of Energy closure requirements, is also discussed.

Evans, Susan Kay; unknown

2000-12-01T23:59:59.000Z

330

Nuclear Forensics  

NLE Websites -- All DOE Office Websites (Extended Search)

nuclear forensics Nuclear Forensics AMS is a Powerful Tool for Nuclear Forensics Nuclear forensics, which can be applied to both interdicted materials and debris from a nuclear...

331

Nuclear Energy Research Brookhaven National  

E-Print Network (OSTI)

Nuclear Energy Research Brookhaven National Laboratory William C. Horak, Chair Nuclear Science and Technology Department #12;BNL Nuclear Energy Research Brookhaven Graphite Research Reactor - 1948 National&T Department #12;Nuclear Energy Today 435 Operable Power Reactors, 12% electrical generation (100 in US, 19

Ohta, Shigemi

332

Nuclear Power and the Public  

Science Journals Connector (OSTI)

This study is an attempt to understand attitudes, perceptions, and behaviors with respect to nuclear power and several other technological risk sources. A ... obtains about 80% of its electricity from nuclear power

Paul Slovic; James Flynn; C. K. Mertz; Marc Poumad鑢e

2000-01-01T23:59:59.000Z

333

National Nuclear Chemistry Summer School  

Energy.gov (U.S. Department of Energy (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.

334

Secondary Pollutants from Ozone Reaction with Ventilation Filters and Degradation of Filter Media Additives  

E-Print Network (OSTI)

2007. Ozone removal by HVAC filters. Atmospheric Environmentozone reactions on HVAC filters cannot be ignored as aof pollutants from HVAC filters may be degradation of

Destaillats, Hugo

2012-01-01T23:59:59.000Z

335

Note: Cryogenic coaxial microwave filters  

SciTech Connect

The careful filtering of microwave electromagnetic radiation is critical for controlling the electromagnetic environment for experiments in solid-state quantum information processing and quantum metrology at millikelvin temperatures. We describe the design and fabrication of a coaxial filter assembly and demonstrate that its performance is in excellent agreement with theoretical modelling. We further perform an indicative test of the operation of the filters by making current-voltage measurements of small, underdamped Josephson junctions at 15 mK.

Tancredi, G.; Meeson, P. J. [Department of Physics, Royal Holloway, University of London, Egham TW20 0EX (United Kingdom)] [Department of Physics, Royal Holloway, University of London, Egham TW20 0EX (United Kingdom); Schmidlin, S. [Department of Physics, Royal Holloway, University of London, Egham TW20 0EX (United Kingdom) [Department of Physics, Royal Holloway, University of London, Egham TW20 0EX (United Kingdom); National Physical Laboratory, Hampton Road, Teddington TW11 0LW (United Kingdom)

2014-02-15T23:59:59.000Z

336

Generating the Option of a Two-Stage Nuclear Renaissance  

Science Journals Connector (OSTI)

...resources. However, the technology has not been demonstrated...nonrenewable natural gas), although various measures...energy. Outlook Nuclear technology is at a crossroads. The...International Forum, 揂 Technology Roadmap for Generation IV Nuclear...

Robin W. Grimes; William J. Nuttall

2010-08-13T23:59:59.000Z

337

Ozone removal by HVAC filters  

Science Journals Connector (OSTI)

Residential and commercial HVAC filters that have been loaded with particles during operation in the field can remove ozone from intake or recirculated air. However, knowledge of the relative importance of HVAC filters as a removal mechanism for ozone in residential and commercial buildings is incomplete. We measured the ozone removal efficiencies of clean (unused) fiberglass, clean synthetic filters, and field-loaded residential and commercial filters in a controlled laboratory setting. For most filters, the ozone removal efficiency declined rapidly but converged to a non-zero (steady-state) value. This steady-state ozone removal efficiency varied from 0% to 9% for clean filters. The mean steady-state ozone removal efficiencies for loaded residential and commercial filters were 10% and 41%, respectively. Repeated exposure of filters to ozone following a 24-h period of no exposure led to a regeneration of ozone removal efficiency. Based on a theoretical scaling analysis of mechanisms that are involved in the ozone removal process, we speculate that the steady-state ozone removal efficiency is limited by reactant diffusion out of particles, and that regeneration is due to internal diffusion of reactive species to sites available to ozone for reaction. Finally, by applying our results to a screening model for typical residential and commercial buildings, HVAC filters were estimated to contribute 22% and 95%, respectively, of total ozone removal in HVAC systems.

P. Zhao; J.A. Siegel; R.L. Corsi

2007-01-01T23:59:59.000Z

338

Multi-frequency aluminum nitride micro-filters for advanced RF communications.  

SciTech Connect

An AlN MEMS resonator technology has been developed, enabling massively parallel filter arrays on a single chip. Low-loss filter banks covering the 10 MHz--10-GHz frequency range have been demonstrated, as has monolithic integration with inductors and CMOS circuitry. The high level of integration enables miniature multi-bandm spectrally aware, and cognitive radios.

Nordquist, Christopher Daniel; Stevens, James E.; Olsson, Roy H., III; Wojciechowski, Kenneth E.; Tuck, Melanie R.

2010-03-01T23:59:59.000Z

339

A Design Space Approach to Analysis of Information Retrieval Adaptive Filtering Systems  

E-Print Network (OSTI)

A Design Space Approach to Analysis of Information Retrieval Adaptive Filtering Systems Dmitriy, Adaptive Filtering 1. INTRODUCTION Constructing and tuning a good Information Retrieval (IR) system it requires to accomplish its various tasks. In many other technologies, such as HVAC (heating, venti- lation

340

Perceptual improvement of Wiener filtering employing a post-filter  

Science Journals Connector (OSTI)

A major drawback of many speech enhancement methods in speech applications is the generation of an annoying residual noise with musical character. Although the Wiener filter introduces less musical noise than spectral subtraction methods, such noise, ... Keywords: MMSE, Modified masking threshold, Musical critical band, Perceptual post-filter, Speech enhancement

Md. Jahangir Alam; Douglas O'Shaughnessy

2011-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear filter technology" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


341

Ceramic Particulate Filters  

Energy.gov (U.S. Department of Energy (DOE))

Poster presentation at the 2007 Diesel Engine-Efficiency & Emissions Research Conference (DEER 2007). 13-16 August, 2007, Detroit, Michigan. Sponsored by the U.S. Department of Energy's (DOE) Office of FreedomCAR and Vehicle Technologies (OFCVT).

342

MODELING MULTI-OUTPUT FILTERING EFFECTS IN PCMOS Anshul Singh*  

E-Print Network (OSTI)

MODELING MULTI-OUTPUT FILTERING EFFECTS IN PCMOS Anshul Singh* , Arindam Basu , Keck-Voon Ling* and Vincent J. Mooney III*$搂 Email: anshul.singh@research.iiit.ac.in, {arindam.basu, ekvling}@ntu, Nanyang Technological University (NTU), Singapore * NTU-Rice Institute of Sustainable and Applied

Mooney, Vincent

343

Modelling of Brain Consciousness based on Collaborative Adaptive Filters  

E-Print Network (OSTI)

Modelling of Brain Consciousness based on Collaborative Adaptive Filters Ling Lia, , Yili Xiaa of Technology, Japan c Laboratory for Advanced Brain Signal Processing, RIKEN Brain Science Institute, Saitama method for the discrimination between discrete states of brain con- sciousness is proposed, achieved

Kent, University of

344

Spent Nuclear Fuel Fact Sheets  

NLE Websites -- All DOE Office Websites (Extended Search)

management needs. By coordinating common needs for research, technology development, and testing programs, the National Spent Nuclear Fuel Program is achieving cost efficiencies...

345

Solid colloidal optical wavelength filter  

DOE Patents (OSTI)

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

Alvarez, Joseph L. (Boulder, CO)

1992-01-01T23:59:59.000Z

346

DOE Seeks to Invest up to $15 Million in Funding for Nuclear...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

technologies closing the nuclear fuel cycle. These projects will provide necessary data and analyses to further U.S. nuclear fuel cycle technology development, as part of...

347

Nuclear Fabrication Consortium  

SciTech Connect

This report summarizes the activities undertaken by EWI while under contract from the Department of Energy (DOE) 芒?? 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 : 芒?垄 Identifying and removing impediments to the implementation of new construction and fabrication techniques and approaches for nuclear equipment, including system components and nuclear plants. 芒?垄 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. 芒?垄 Analyzing and disseminating information about future nuclear fabrication technologies and how they could impact the North American and the International Nuclear Marketplace. 芒?垄 Facilitating dialog and initiate alignment among fabricators, owners, trade associations, and government agencies. 芒?垄 Supporting industry in helping to create a larger qualified nuclear supplier network. 芒?垄 Acting as an unbiased technology resource to evaluate, develop, and demonstrate new manufacturing technologies. 芒?垄 Creating welder and inspector training programs to help enable the necessary workforce for the upcoming construction work. 芒?垄 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.

Levesque, Stephen

2013-04-05T23:59:59.000Z

349

ADVANCED NUCLEAR TRANSFORMATION TECHNOLOGY SUBCOMMITTEE  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

data for higher priority isotopes and fuel mixes in the thermal, epithermal and fast-neutron ANTT Report 14 January 2003 8 spectra using heated samples in low-power critical...

350

Assessment of Metal Media Filters for Advanced Coal-Based Power Generation Applications  

SciTech Connect

Advanced coal and biomass-based gas turbine power generation technologies (IGCC, PFBC, PCFBC, and Hipps) are currently under development and demonstration. Efforts at Siemens Westinghouse Power Corporation (SWPC) have been focused on the development and demonstration of hot gas filter systems as an enabling technology for power generation. This paper reviews SWPC's material and component assessment efforts, identifying the performance, stability, and life of porous metal, advanced alloy, and intermetallic filters under simulated, pressurized fluidized-bed combustion conditions.

Alvin, M.A.

2002-09-19T23:59:59.000Z

351

Specification for HEPA Filters Used By DOE Contractors  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

DOE-STD-3020-2005 DOE-STD-3020-2005 December 2005 Supersedes DOE-STD-3020-97 January 1997 DOE TECHNICAL STANDARD Specification for HEPA Filters Used by DOE Contractors U.S. Department of Energy AREA SAFT Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited FOREWARD This U.S. Department of Energy (DOE) standard supersedes DOE-STD-3020-97 and is approved for use by DOE and its contractors. This standard was developed primarily for application in DOE programs. It provides guidance to DOE contractors for procurement and required testing of High Efficiency Particulate Air (HEPA) filters used in DOE nuclear facilities. Required testing is performed by the filter manufacturer and

352

Specification for HEPA Filters Used By DOE Contractors  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

DOE-STD-3020-2005 DOE-STD-3020-2005 December 2005 Supersedes DOE-STD-3020-97 January 1997 DOE TECHNICAL STANDARD Specification for HEPA Filters Used by DOE Contractors U.S. Department of Energy AREA SAFT Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited FOREWARD This U.S. Department of Energy (DOE) standard supersedes DOE-STD-3020-97 and is approved for use by DOE and its contractors. This standard was developed primarily for application in DOE programs. It provides guidance to DOE contractors for procurement and required testing of High Efficiency Particulate Air (HEPA) filters used in DOE nuclear facilities. Required testing is performed by the filter manufacturer and

353

Backpulse and filter feed velocity effects on Norton filter performance  

SciTech Connect

A series of tests have been conducted using the 2.2 ft{sup 2} Norton filter to solve the fouling problems observed with the ETF Norton system. The objective of these tests was to determine filter efficiency as a function of backpulse strength and feed velocity. Based on experimental results, it is recommend that the filters should be operated at the following conditions: (1) Backpulse Transmembrane Pressure/FeedTransmembrane Pressure (BP/FP) > 1.5, preferably 2 or 3. (2) Feed crossflow velocity = 6--8 f/s. It is expected that operation at these conditions should improve performance by 30--60%.

Siler, J.L.

1990-05-08T23:59:59.000Z

354

Results from Evaluation of Proposed ASME AG-1 Section FI Metal Media Filters - 13063  

SciTech Connect

High efficiency particulate air (HEPA) filtration technology is commonly used in Department of Energy (DOE) facilities that require control of radioactive particulate matter (PM) emissions due to treatment or management of radioactive materials. Although HEPA technology typically makes use of glass fiber media, metal and ceramic media filters are also capable of filtering efficiencies beyond the required 99.97%. Sintered metal fiber filters are good candidates for use in DOE facilities due to their resistance to corrosive environments and resilience at high temperature and elevated levels of relative humidity. Their strength can protect them from high differential pressure or pressure spikes and allow for back pulse cleaning, extending filter lifetime. Use of these filters has the potential to reduce the cost of filtration in DOE facilities due to life cycle cost savings. ASME AG-1 section FI has not been approved due to a lack of protocols and performance criteria for qualifying section FI filters. The Institute for Clean Energy Technology (ICET) with the aid of the FI project team has developed a Section FI test stand and test plan capable of assisting in the qualification ASME AG-1 section FI filters. Testing done at ICET using the FI test stand evaluates resistance to rated air flow, test aerosol penetration and resistance to heated air of the section FI filters. Data collected during this testing consists of temperature, relative humidity, differential pressure, flow rate, upstream particle concentration, and downstream particle concentration. (authors)

Wilson, John A.; Giffin, Paxton K.; Parsons, Michael S.; 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)

2013-07-01T23:59:59.000Z

355

Modeling service life of pleated filters exposed to poly-dispersed aerosols A.M. Saleh a  

E-Print Network (OSTI)

. Fotovati a , H. Vahedi Tafreshi a, , B. Pourdeyhimi b a Department of Mechanical and Nuclear Engineering to accommodate a flat-sheet filter is limited, such as in engines or HVAC systems. Understanding the air flow

Tafreshi, Hooman Vahedi

356

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...

357

A Framework for Nonlinear Filtering in MATLAB.  

E-Print Network (OSTI)

?? The object of this thesis is to provide a MATLAB framework for nonlinear filtering in general, and particle filtering in particular. This is done (more)

Ros閚, Jakob

2005-01-01T23:59:59.000Z

358

Catalytic Filter for Diesel Exhaust Purification | Department...  

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

Filter for Diesel Exhaust Purification This project is developing a precious metal-free passive diesel particulate filter. deer09fokema.pdf More Documents & Publications...

359

A Survey of Mixed-Waste HEPA Filters in the DOE Complex  

SciTech Connect

A brief investigation was made to determine the quantities of spent, mixed-waste HEPA filters within the DOE Complex. The quantities of both the mixed-waste filters that are currently being generated, as well as the legacy mixed-waste filters being stored and awaiting disposition were evaluated. Seven DOE sites representing over 89% of the recent HEPA filter usage were identified. These sites were then contacted to determine the number of these filters that were likely destined to become mixed waste and to survey the legacy-filter quantities. Inquiries into the disposition plans for the filters were also made. It was determined that the seven sites surveyed possess approximately 500 m3 of legacy mixed-waste HEPA filters that will require processing, with an annual generation rate of approximately 25 m3. No attempt was made to extrapolate the results of this survey to the entire DOE Complex. These results were simply considered to be the lower bound of the totality of mixed-waste HEPA filters throughout the Complex. The quantities determined encourage the development of new treatment technologies for these filters, and provide initial data on which an appropriate capacity for a treatment process may be based.

Felicione, F. S.; Barber, D. B.; Carney, K. P.

2002-02-28T23:59:59.000Z

360

Nuclear Deployment Scorecards | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Initiatives 禄 Nuclear Reactor TechnologiesNuclear Deployment Initiatives 禄 Nuclear Reactor TechnologiesNuclear Deployment Scorecards Nuclear Deployment Scorecards October 31, 2013 Quarterly Nuclear Deployment Scorecard - October 2013 The scorecard includes news updates, regulatory status, reactor design certification, early site permits, new plant construction progress, and expected operation dates. August 8, 2013 Quarterly Nuclear Deployment Scorecard - July 2013 The scorecard includes news updates, regulatory status, reactor design certification, early site permits, new plant construction progress, and expected operation dates. May 1, 2013 Quarterly Nuclear Power Deployment Scorecard - April 2013 The scorecard includes news updates, regulatory status, reactor design certification, early site permits, and new plant construction progress.

Note: This page contains sample records for the topic "nuclear filter technology" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


361

Nuclear Sciences | More Science | ORNL  

NLE Websites -- All DOE Office Websites (Extended Search)

Chemistry Chemistry Advanced Materials Nuclear Forensics Climate & Environment Biology and Soft Matter Chemical and Engineering Materials Quantum Condensed Matter Computational Chemistry Nuclear Sciences More Science Home | Science & Discovery | More Science | Chemistry | Nuclear 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 and systems to improve human health; explore safer, more environmentally friendly power; and better understand the structure of matter. Thanks to its nuclear heritage, ORNL is a world leader in the production of isotopes for medical purposes and research. The lab's High Flux Isotope Reactor (HFIR) and Radiochemical Engineering Development Center (REDC)

362

Nuclear power can reduce emissions and maintain a strong economy: Rating Australia抯 optimal future electricity-generation mix by technologies and policies  

Science Journals Connector (OSTI)

Abstract Legal barriers currently prohibit nuclear power for electricity generation in Australia. For this reason, published future electricity scenarios aimed at policy makers for this country have not seriously considered a full mix of energy options. Here we addressed this deficiency by comparing the life-cycle sustainability of published scenarios using multi-criteria decision-making analysis, and modeling the optimized future electricity mix using a genetic algorithm. The published 慍SIRO e-future scenario under its default condition (excluding nuclear) has the largest aggregate negative environmental and economic outcomes (score=4.51 out of 8), followed by the Australian Energy Market Operator抯 100% renewable energy scenario (4.16) and the Greenpeace scenario (3.97). The e-future projection with maximum nuclear-power penetration allowed yields the lowest negative impacts (1.46). After modeling possible future electricity mixes including or excluding nuclear power, the weighted criteria recommended an optimized scenario mix where nuclear power generated >40% of total electricity. The life-cycle greenhouse-gas emissions of the optimization scenarios including nuclear power were nuclear power is an effective and logical option for the environmental and economic sustainability of a future electricity network in Australia.

Sanghyun Hong; Corey J.A. Bradshaw; Barry W. Brook

2014-01-01T23:59:59.000Z

363

Formaldehyde emissions from ventilation filters under different relative  

NLE Websites -- All DOE Office Websites (Extended Search)

Formaldehyde emissions from ventilation filters under different relative Formaldehyde emissions from ventilation filters under different relative humidity conditions Title Formaldehyde emissions from ventilation filters under different relative humidity conditions Publication Type Journal Article Refereed Designation Refereed Year of Publication 2013 Authors Sidheswaran, Meera A., Wenhao Chen, Agatha Chang, Robert Miller, Sebastian Cohn, Douglas P. Sullivan, William J. Fisk, Kazukiyo Kumagai, and Hugo Destaillats Journal Environmental Science and Technology Date Published 04/18/2013 Abstract A method combining life cycle assessment (LCA) and real options analyses is developed to predict project environmental and financial performance over time, under market uncertainties and decision-making flexibility. The method is applied to examine alternative uses for oil sands coke, a carbonaceous byproduct of processing the unconventional petroleum found in northern Alberta, Canada. Under uncertainties in natural gas price and the imposition of a carbon price, our method identifies that selling the coke to China for electricity generation by integrated gasification combined cycle is

364

Nuclear Power桽uccess Assured  

Science Journals Connector (OSTI)

Nuclear Power桽uccess Assured ... Confidence in nuclear power's future mounts technology shaves costs, improves efficiency ... This informed opinion as to the economic practicality of commercial nuclear power was expressed to C&EN by National Carbon's Clarence E. Larson, a pioneer in the atomic energy field. ...

1955-12-26T23:59:59.000Z

365

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

E-Print Network (OSTI)

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...

Harding, Patricia Colleen

2012-06-07T23:59:59.000Z

366

Achievements: Nuclear Reactors designed/built by Argonne National  

NLE Websites -- All DOE Office Websites (Extended Search)

Achievements > Achievements > Argonne National Laboratory Reactors About Director's Welcome Organization Achievements Highlights Fact Sheets, Brochures & Other Documents Multimedia Library Visit Argonne Work with Argonne Contact us Nuclear Energy Why Nuclear Energy? Why are some people afraid of Nuclear Energy? How do nuclear reactors work? Cheaper & Safer Nuclear Energy Helping to Solve the Nuclear Waste Problem Nuclear Reactors Nuclear Reactors Early Exploration Training Reactors Basic and Applied Science Research LWR Technology Development BORAX-III lighting Arco, Idaho (Press Release) Heavy Water and Graphite Reactors Fast Reactor Technology Integral Fast Reactor Argonne Reactor Tree CP-1 70th Anniversary CP-1 70th Anniversary Argonne's Nuclear Science and Technology Legacy

367

Water washable stainless steel HEPA filter  

DOE Patents (OSTI)

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.

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

2001-01-01T23:59:59.000Z

368

Document Filtering With Inference Networks Jamie Callan  

E-Print Network (OSTI)

Document Filtering With Inference Networks Jamie Callan Computer Science Department University document filtering. The prob颅 lems of document retrieval and document filtering are sim颅 ilar of the infor颅 mation available, are all different. This paper describes a new statistical document filtering

Callan, Jamie

369

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

SciTech Connect

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

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

1996-12-31T23:59:59.000Z

370

Nuclear Energy Program  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

September 30, 2002 September 30, 2002 NERAC Fall 2002 Meeting Office of Nuclear Energy, Science and Technology Major Program Developments Major Program Developments 6 June 2002: Department selects three U.S. electric utilities (Dominion Energy, Entergy, and Exelon) to participate in joint government/ industry projects to demonstrate NRC's Early Site Permit (ESP) process and seek NRC approval by mid-decade 6 July 2002: Secretary Abraham announces transition of management of the Idaho National Engineering and Environmental Laboratory to Nuclear Energy and revitalization of its nuclear R&D mission 6 September 2002: Generation IV International Forum reaches agreement on six advanced reactor and fuel cycle technologies for joint development Office of Nuclear Energy, Science and Technology

371

Spatial filters for high power lasers  

DOE Patents (OSTI)

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.

Erlandson, Alvin Charles; Bayramian, Andrew James

2014-12-02T23:59:59.000Z

372

Why Nuclear Energy? - Reactors designed/built by Argonne National  

NLE Websites -- All DOE Office Websites (Extended Search)

Nuclear Energy: Nuclear Energy: Why Nuclear Energy? About Director's Welcome Organization Achievements Highlights Fact Sheets, Brochures & Other Documents Multimedia Library Visit Argonne Work with Argonne Contact us Nuclear Energy Why Nuclear Energy? Why are some people afraid of Nuclear Energy? How do nuclear reactors work? Cheaper & Safer Nuclear Energy Helping to Solve the Nuclear Waste Problem Nuclear Reactors Nuclear Reactors Early Exploration Training Reactors Basic and Applied Science Research LWR Technology Development BORAX-III lighting Arco, Idaho (Press Release) Heavy Water and Graphite Reactors Fast Reactor Technology Integral Fast Reactor Argonne Reactor Tree CP-1 70th Anniversary CP-1 70th Anniversary Argonne's Nuclear Science and Technology Legacy Argonne's Nuclear Science and Technology Legacy

373

Active dc filter for HVDC systems  

SciTech Connect

This article is a case history of the installation of active dc filters for high-performance, low-cost harmonics filtering at the Lindome converter station in the Konti-Skan 2 HVDC transmission link between Denmark and Sweden. The topics of the article include harmonics, interference, and filters, Lindome active dc filter, active dc filter design, digital signal processor, control scheme, protection and fault monitoring, and future applications.

Zhang, W. (Royal Inst. of Tech., Stockholm (Sweden)); Asplund, G.

1994-01-01T23:59:59.000Z

374

Nuclear power outlook dim, report concludes  

Science Journals Connector (OSTI)

Nuclear power outlook dim, report concludes ... Without significant changes in technology, management, and level of public acceptance, nuclear power in the U.S. is unlikely to be expanded in this century beyond the reactors already under construction, says Congress' Office of Technology Assessment. ... Nuclear power is not inherently unsafe, OTA says. ...

1984-02-13T23:59:59.000Z

375

RAPID SEPARATION METHOD FOR ACTINIDES IN EMERGENCY AIR FILTER SAMPLES  

SciTech Connect

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

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

2010-02-03T23:59:59.000Z

376

Nuclear activation technique for analysis of laser induced energetic protons  

E-Print Network (OSTI)

. For that purpose, we have developed a method in which the particles induce nuclear reactions in a stack of copper for medical applications [6]). In addition, nuclear reaction yields and nuclear decay rates might be studied radioactive nuclei. In a stack of samples, each foil acts as a low energy proton filter for the following ones

Paris-Sud XI, Universit茅 de

377

IEEE TRANSACTIONS ON NUCLEAR SCIENCE, VOL. 58, NO. 1, FEBRUARY 2011 277 Anomaly Detection in Nuclear Power Plants via  

E-Print Network (OSTI)

in Nuclear Power Plants via Symbolic Dynamic Filtering Xin Jin, Student Member, IEEE, Yin Guo, Soumik Sarkar detection algorithm for condition monitoring of nuclear power plants, where symbolic feature extraction Innova- tive & Secure (IRIS) simulator of nuclear power plants, and its per- formance is evaluated

Ray, Asok

378

National Center for Nuclear Security: The Nuclear Forensics Project (F2012)  

SciTech Connect

These presentation visuals introduce the National Center for Nuclear Security. Its chartered mission is to enhance the Nation抯 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.

Klingensmith, A. L.

2012-03-21T23:59:59.000Z

379

Development of active porous medium filters based on plasma textiles  

Science Journals Connector (OSTI)

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 (損lasma 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).

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

2012-01-01T23:59:59.000Z

380

(Environmental technology)  

SciTech Connect

The traveler participated in a conference on environmental technology in Paris, sponsored by the US Embassy-Paris, US Environmental Protection Agency (EPA), the French Environmental Ministry, and others. The traveler sat on a panel for environmental aspects of energy technology and made a presentation on the potential contributions of Oak Ridge National Laboratory (ORNL) to a planned French-American Environmental Technologies Institute in Chattanooga, Tennessee, and Evry, France. This institute would provide opportunities for international cooperation on environmental issues and technology transfer related to environmental protection, monitoring, and restoration at US Department of Energy (DOE) facilities. The traveler also attended the Fourth International Conference on Environmental Contamination in Barcelona. Conference topics included environmental chemistry, land disposal of wastes, treatment of toxic wastes, micropollutants, trace organics, artificial radionuclides in the environment, and the use biomonitoring and biosystems for environmental assessment. The traveler presented a paper on The Fate of Radionuclides in Sewage Sludge Applied to Land.'' Those findings corresponded well with results from studies addressing the fate of fallout radionuclides from the Chernobyl nuclear accident. There was an exchange of new information on a number of topics of interest to DOE waste management and environmental restoration needs.

Boston, H.L.

1990-10-12T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear filter technology" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


381

MICHAEL L. CORRADINI Wisconsin Distinguished Professor Nuclear Engineering and Engineering Physics, Chair, Engineering Physics Department  

E-Print Network (OSTI)

MICHAEL L. CORRADINI Wisconsin Distinguished Professor Nuclear Engineering and Engineering Physics.S. Mechanical Engineering - 1975 Marquette University, Milwaukee WI M.S. Nuclear Engineering - 1976 Massachusetts Institute of Technology PhD Nuclear Engineering - 1978 Massachusetts Institute of Technology

Volpe, Francesco

382

Hydrogen Technology Research at SRNL  

SciTech Connect

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.

Danko, E.

2011-02-13T23:59:59.000Z

383

Nuclear Energy  

NLE Websites -- All DOE Office Websites (Extended Search)

Research Programs >> Nuclear Energy Error Error Nuclear Energy Home - RCC cannot be displayed due to a timeout error. We recommend: * Refresh Nuclear Energy Home - RCC * Increasing...

384

Nuclear Forensics | More Science | ORNL  

NLE Websites -- All DOE Office Websites (Extended Search)

Materials Science and Engineering Materials Science and Engineering Advanced Materials Clean Energy Materials Theory and Simulation Neutron Science Nuclear Forensics Nuclear Science Supercomputing Theory, Modeling and Simulation More Science Home | Science & Discovery | More Science | Materials Science and Engineering | Nuclear Forensics SHARE Nuclear Forensics image Tools, techniques, and expertise in nuclear fuel cycle research gained over seven decades help ORNL scientists control and track nuclear bomb-grade materials to be sure they don't fall into the wrong hands. Among the leading-edge technologies used by researchers are high-resolution techniques that allow analysis of radiation detector data in stunning detail. Researchers are also developing aerosol sampling systems to collect

385

SC e-journals, Nuclear  

Office of Scientific and Technical Information (OSTI)

Nuclear Nuclear Annals of Nuclear Energy Annual Review of Nuclear and Particle Science Atomic Data & Nuclear Data Tables Atomic Energy BMC Medical Physics - OAJ Cancer Prevention Journals Portal Cancer Prevention Research Cancer Reviews Online Dose Response Energy & Environmental Science Energy Policy EURASIP Journal on Advances in Signal Processing - OAJ EURASIP Journal on Bioinformatics and Systems Biology - OAJ EURASIP Journal on Embedded Systems (2006 forward) - OAJ Fuel Fusion Engineering and Design Fusion Nuclear Society Health Physics IETE Journal of Research - OAJ International Journal of Cancer International Journal of Low Radiation International Journal of Microwave Science and Technology - OAJ International Journal of Radiation Biology Journal of Cancer Eqidemiology - OAJ

386

Development of an extended-service coolant filter  

SciTech Connect

An extended-service engine coolant filter has been developed, using conventional supplemental coolant additive (SCA) technology. This has been achieved by the use of a proprietary polymer coating, which delays the release of active engine coolant chemistry. Initial field data show a gradual release pattern for introducing SCA chemistry into the coolant, with complete release typically occurring in the range of 70,000 to 140,000 miles (112,651--225,302 km).

Mitchell, W.A. [BetzDearborn, Crystal Lake, IL (United States). Venture Activities Group; Hudgens, R.D. [Fleetguard/Nelson Inc., Cookeville, TN (United States)

1999-08-01T23:59:59.000Z

387

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

388

Nuclear Science | ORNL  

NLE Websites -- All DOE Office Websites (Extended Search)

Educational Outreach Educational Outreach Publications and Reports News and Awards Home | Science & Discovery | Nuclear Science Nuclear Science | Nuclear Science SHARE In World War II's Manhattan Project, ORNL helped usher in the nuclear age. Today, laboratory scientists are leaders in using nuclear technologies and systems to improve human health; explore safer, more environmentally friendly power; and better understand the structure of matter. Thanks to its nuclear heritage, ORNL is a world leader in the production of isotopes for medical purposes and research. The lab's High Flux Isotope Reactor (HFIR) and Radiochemical Engineering Development Center (REDC) together provide the western world's sole supply of californium-252, an isotope instrumental in a wide variety of uses including cancer therapy,

389

Nuclear energy: The civilians take charge - Argonne's Historical News  

NLE Websites -- All DOE Office Websites (Extended Search)

Nuclear energy: The civilians take charge Nuclear energy: The civilians take charge About Director's Welcome Organization Achievements Highlights Fact Sheets, Brochures & Other Documents Multimedia Library Visit Argonne Work with Argonne Contact us Nuclear Energy Why Nuclear Energy? Why are some people afraid of Nuclear Energy? How do nuclear reactors work? Cheaper & Safer Nuclear Energy Helping to Solve the Nuclear Waste Problem Nuclear Reactors Nuclear Reactors Early Exploration Training Reactors Basic and Applied Science Research LWR Technology Development BORAX-III lighting Arco, Idaho (Press Release) Heavy Water and Graphite Reactors Fast Reactor Technology Integral Fast Reactor Argonne Reactor Tree CP-1 70th Anniversary CP-1 70th Anniversary Argonne's Nuclear Science and Technology Legacy Argonne's Nuclear Science and Technology Legacy

390

Why are Some People Afraid of Nuclear Energy?  

NLE Websites -- All DOE Office Websites (Extended Search)

Why are some people afraid of Nuclear Energy? Why are some people afraid of Nuclear Energy? About Director's Welcome Organization Achievements Highlights Fact Sheets, Brochures & Other Documents Multimedia Library Visit Argonne Work with Argonne Contact us Nuclear Energy Why Nuclear Energy? Why are some people afraid of Nuclear Energy? How do nuclear reactors work? Cheaper & Safer Nuclear Energy Helping to Solve the Nuclear Waste Problem Nuclear Reactors Nuclear Reactors Early Exploration Training Reactors Basic and Applied Science Research LWR Technology Development BORAX-III lighting Arco, Idaho (Press Release) Heavy Water and Graphite Reactors Fast Reactor Technology Integral Fast Reactor Argonne Reactor Tree CP-1 70th Anniversary CP-1 70th Anniversary Argonne's Nuclear Science and Technology Legacy Argonne's Nuclear Science and Technology Legacy

391

Research helps safeguard nuclear workers worldwide - Argonne's Historical  

NLE Websites -- All DOE Office Websites (Extended Search)

Research helps safeguard nuclear workers Research helps safeguard nuclear workers worldwide About Director's Welcome Organization Achievements Highlights Fact Sheets, Brochures & Other Documents Multimedia Library Visit Argonne Work with Argonne Contact us Nuclear Energy Why Nuclear Energy? Why are some people afraid of Nuclear Energy? How do nuclear reactors work? Cheaper & Safer Nuclear Energy Helping to Solve the Nuclear Waste Problem Nuclear Reactors Nuclear Reactors Early Exploration Training Reactors Basic and Applied Science Research LWR Technology Development BORAX-III lighting Arco, Idaho (Press Release) Heavy Water and Graphite Reactors Fast Reactor Technology Integral Fast Reactor Argonne Reactor Tree CP-1 70th Anniversary CP-1 70th Anniversary Argonne's Nuclear Science and Technology Legacy Argonne's Nuclear Science and Technology Legacy

392

Fukushima fallout: Gauging the change in Japanese nuclear energy policy  

Science Journals Connector (OSTI)

The Fukushima nuclear disaster is a special case: a major ... technological disaster, which resulted in a serious nuclear accident. Because the various costs are so ... of life in Japan. This article describes nuclear

Elena Shadrina

2012-06-01T23:59:59.000Z

393

Advanced Reactor Technologies | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Advanced Reactor Advanced Reactor Technologies Advanced Reactor Technologies Advanced Reactor Technologies Advanced Reactor Technologies The Office of Advanced Reactor Technologies (ART) sponsors research, development and deployment (RD&D) activities through its Next Generation Nuclear Plant (NGNP), Advanced Reactor Concepts (ARC), and Advanced Small Modular Reactor (aSMR) programs to promote safety, technical, economical, and environmental advancements of innovative Generation IV nuclear energy technologies. The Office of Nuclear Energy (NE) will pursue these advancements through RD&D activities at the Department of Energy (DOE) national laboratories and U.S. universities, as well as through collaboration with industry and international partners. These activities will focus on advancing scientific

394

Electric filter with movable belt electrode  

DOE Patents (OSTI)

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.

Bergman, W.

1983-09-20T23:59:59.000Z

395

A rigid porous filter and filtration method  

SciTech Connect

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.

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

1998-12-01T23:59:59.000Z

396

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...

397

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

E-Print Network (OSTI)

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 ...

Espinoza, Claudia M. (Claudia Maritza)

2011-01-01T23:59:59.000Z

398

Monitoring Thermal Fatigue Damage In Nuclear Power Plant Materials Using Acoustic Emission  

SciTech Connect

Proactive aging management of nuclear power plant passive components requires technologies to enable monitoring and accurate quantification of material condition at early stages of degradation (i.e., pre-macrocrack). Acoustic emission (AE) is well-suited to continuous monitoring of component degradation and is proposed as a method to monitor degradation during accelerated thermal fatigue tests. A key consideration is the ability to separate degradation responses from external sources such as water spray induced during thermal fatigue testing. Water spray provides a significant background of acoustic signals, which can overwhelm AE signals caused by degradation. Analysis of AE signal frequency and energy is proposed in this work as a means for separating degradation signals from background sources. Encouraging results were obtained by applying both frequency and energy filters to preliminary data. The analysis of signals filtered using frequency and energy provides signatures exhibiting several characteristics that are consistent with degradation accumulation in materials. Future work is planned to enable verification of the efficacy of AE for thermal fatigue crack initiation detection. While the emphasis has been placed on the use of AE for crack initiation detection during accelerated aging tests, this work also has implications with respect to the use of AE as a primary tool for early degradation monitoring in nuclear power plant materials. The development of NDE tools for characterization of aging in materials can also benefit from the use of a technology such as AE which can continuously monitor and detect crack initiation during accelerated aging tests.

Meyer, Ryan M.; Ramuhalli, Pradeep; Watson, Bruce E.; Pitman, Stan G.; Roosendaal, Timothy J.; Bond, Leonard J.

2012-04-26T23:59:59.000Z

399

Nuclear Debate  

Science Journals Connector (OSTI)

Nuclear Debate ... This month, the Senate will consider the nominations of two women to serve on the Nuclear Regulatory Commission. ... Svinicki is a nuclear engineer with experience in the Department of Energy抯 nuclear energy programs. ...

JEFF JOHNSON

2012-06-11T23:59:59.000Z

400

Improving Filtering for Computer Graphics  

E-Print Network (OSTI)

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...

Manson, Josiah

2014-04-30T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear filter technology" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


401

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

SciTech Connect

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.

LEBARON GJ

2008-11-25T23:59:59.000Z

402

Are Ventilation Filters Degrading Indoor Air Quality in California Classrooms?  

E-Print Network (OSTI)

2007)爴Ozone燫emoval燽y燞VACFilters. 敔Atmos. 燛nviron. 燞VACfilters牋ozone燿eposition爄n HVACfilters燼nd燽yproduct爁ormation,

Fisk, Michael G. Apte and William J.

2009-01-01T23:59:59.000Z

403

System Effects of High Efficiency Filters in Homes  

E-Print Network (OSTI)

FIELD TESTING OF FILTER IMPACTS ON HVAC SYSTEM PERFORMANCEof Filters in Residential and Light-Commercial HVAC systems.HVAC system performance changes with different MERV filters

Walker, Iain S.

2014-01-01T23:59:59.000Z

404

ADVANCED HOT GAS FILTER DEVELOPMENT  

SciTech Connect

This report describes the fabrication and testing of continuous fiber ceramic composite (CFCC) based hot gas filters. The fabrication approach utilized a modified filament winding method that combined both continuous and chopped fibers into a novel microstructure. The work was divided into five primary tasks. In the first task, a preliminary set of compositions was fabricated in the form of open end tubes and characterized. The results of this task were used to identify the most promising compositions for sub-scale filter element fabrication and testing. In addition to laboratory measurements of permeability and strength, exposure testing in a coal combustion environment was performed to asses the thermo-chemical stability of the CFCC materials. Four candidate compositions were fabricated into sub-scale filter elements with integral flange and a closed end. Following the 250 hour exposure test in a circulating fluid bed combustor, the retained strength ranged from 70 t 145 percent of the as-fabricated strength. The post-test samples exhibited non-catastrophic failure behavior in contrast to the brittle failure exhibited by monolithic materials. Filter fabrication development continued in a filter improvement and cost reduction task that resulted in an improved fiber architecture, the production of a net shape flange, and an improved low cost bond. These modifications were incorporated into the process and used to fabricate 50 full-sized filter elements for testing in demonstration facilities in Karhula, Finland and at the Power Systems Development Facility (PSDF) in Wilsonville, AL. After 581 hours of testing in the Karhula facility, the elements retained approximately 87 percent of their as-fabricated strength. In addition, mechanical response testing at Virginia Tech provided a further demonstration of the high level of strain tolerance of the vacuum wound filter elements. Additional testing in the M. W. Kellogg unit at the PSDF has accumulated over 1800 hours of coal firing at temperatures of 760 癈 including a severe thermal upset that resulted in the failure of several monolithic oxide elements. No failures of any kind have been reported for the MTI CFCC elements in either of these test campaigns. Additional testing is planned at the M. W. Kellogg unit and Foster Wheeler unit at the PSDF over the next year in order to qualify for consideration for the Lakeland PCFB. Process scale-up issues have been identified and manufacturing plans are being evaluated to meet the needs of future demand.

RICHARD A. WAGNER

1998-09-04T23:59:59.000Z

405

ENGINEERING TECHNOLOGY Engineering Technology  

E-Print Network (OSTI)

, Mechatronics Technology, and Renewable Energy Technology. Career Opportunities Graduates of four: business administration, wind farm management, aircraft maintenance, tooling production, quality and safety or selected program track focus. Transfer students must talk to their advisor about transferring their courses

406

ENGINEERING TECHNOLOGY Engineering Technology  

E-Print Network (OSTI)

: business administration, energy management, wind farm management, automation and controls, aircraft, Mechatronics Technology, and Renewable Energy Technology. Career Opportunities Graduates of four students must talk to their advisor about transferring their courses over for WSU credit. Laboratory

407

Building Technologies Office: Emerging Technologies  

NLE Websites -- All DOE Office Websites (Extended Search)

Emerging Technologies Emerging Technologies Printable Version Share this resource Send a link to Building Technologies Office: Emerging Technologies to someone by E-mail Share Building Technologies Office: Emerging Technologies on Facebook Tweet about Building Technologies Office: Emerging Technologies on Twitter Bookmark Building Technologies Office: Emerging Technologies on Google Bookmark Building Technologies Office: Emerging Technologies on Delicious Rank Building Technologies Office: Emerging Technologies on Digg Find More places to share Building Technologies Office: Emerging Technologies on AddThis.com... About Take Action to Save Energy Partner with DOE Activities Technology Research, Standards, & Codes Popular Links Success Stories Previous Next Lighten Energy Loads with System Design.

408

Koch Filter and DOW Teaming Profile  

NLE Websites -- All DOE Office Websites (Extended Search)

Koch Filter Corporation Dow Chemical Koch Filter Corporation Dow Chemical 4411-A Darien Street 2301 Brazosport Boulevard Houston, TX 77028 Freeport, TX 77541 Business: HVAC Filter Manufacturer Business: Chemical Manufacturer Bob Sheppard John Theile Regional Sales Manager Reliability Engineer Phone: 713-672-6550 Phone: 979-238-1894 Email: bobs@kochfilter.com Email: jptheile@dow.com Koch Filter saves Dow $156,000 by improving air flow to turbines Project Scope Koch Filter Corporation evaluated the turbine operation at a Dow Chemical facility. They determined that the gas turbine's air intake system was undersized and pre-filters had an initial resistance that was too high, causing the turbine to be "starved" for air. Koch replaced these filters with a better filter that

409

Automatic tuning of continuous-time filters  

E-Print Network (OSTI)

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...

Sumesaglam, Taner

2004-11-15T23:59:59.000Z

410

Waveguide Filter Tutorial Julius O. Smith III  

E-Print Network (OSTI)

Waveguide Filter Tutorial Julius O. Smith III Center for Computer Research in Music and Acoustics was adapted from the conference paper "Waveguide Filter Tutorial," by J.O. Smith, Proceedings

Smith III, Julius Orion

411

An energy recovery filter for HVDC systems  

SciTech Connect

The paper investigates the use of a novel filter arrangement for eliminating harmonic instability. The CIGRE benchmark model is selected as the base system. Presented in the paper is an example of harmonic instability which is first eliminated using a conventional low Q filter. Subsequently an energy recovery filter (ER-filter) replaces the conventional low Q filter. It is shown that the ER-filter provides similar performance with a fraction of the power loss when compared with a low Q filter. The dynamic performance of the ER-filter is also demonstrated via the simulations of system start-up and faults. The tool used for this investigation is an electromagnetic transient simulation program.

Jiang, X.; Gole, A.M. (Univ. of Manitoba, Winnipeg (Canada). Dept. of Electrical and Computer Engineering)

1994-01-01T23:59:59.000Z

412

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

E-Print Network (OSTI)

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.

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

2013-01-24T23:59:59.000Z

413

ATOMKRAFT - NEJ TAK?; NUCLEAR POWER - NO THANKS?.  

E-Print Network (OSTI)

??In this report, we examine nuclear power and several other energy sources, in an attempt to investigate how sustainable these technologies are. The main focus (more)

Fjederholt, Mads

2014-01-01T23:59:59.000Z

414

Maintaining the Stockpile | National Nuclear Security Administration  

National Nuclear Security Administration (NNSA)

sustains a safe, secure, and effective nuclear deterrent through the application of science, technology, engineering, and manufacturing. To deal with the changing face of...

415

Administrator's Update - July 2014 | National Nuclear Security...  

National Nuclear Security Administration (NNSA)

Update - July 2014 The NNSA holds a unique and important place in global nuclear science and technology. Through our laboratories and plants, our scientists conduct...

416

Nuclear Facility Operations | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

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

417

National Securities Technologies _NSTec_ Livermore Operations...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

National Nuclear Security Administration NRTL Nationally Recognized Testing Laboratory NSTec National Security Technologies, LLC NTS Nevada Test Site OSHA Occupational Safety and...

418

Development of Advanced Particulate Filters  

Energy.gov (U.S. Department of Energy (DOE))

2012 DOE Hydrogen and Fuel Cells Program and Vehicle Technologies Program Annual Merit Review and Peer Evaluation Meeting

419

FPGA-based Particle Recognition in the HADES Abstract--Modern FPGA technologies are often employed in nuclear and particle physics experimental facilities to accelerate  

E-Print Network (OSTI)

1 FPGA-based Particle Recognition in the HADES Experiment Abstract--Modern FPGA technologies-specific computation. We present the particle recognition computation for the HADES experiment in this article of commodity PCs for the HADES experiment. Index Terms--reconfigurable computing, FPGA accelerator, pattern

Jantsch, Axel

420

Digital Actuator Technology  

SciTech Connect

There are significant developments underway in new types of actuators for power plant active components. Many of these make use of digital technology to provide a wide array of benefits in performance of the actuators and in reduced burden to maintain them. These new product offerings have gained considerable acceptance in use in process plants. In addition, they have been used in conventional power generation very successfully. This technology has been proven to deliver the benefits promised and substantiate the claims of improved performance. The nuclear industry has been reluctant to incorporate digital actuator technology into nuclear plant designs due to concerns due to a number of concerns. These could be summarized as cost, regulatory uncertainty, and a certain comfort factor with legacy analog technology. The replacement opportunity for these types of components represents a decision point for whether to invest in more modern technology that would provide superior operational and maintenance benefits. Yet, the application of digital technology has been problematic for the nuclear industry, due to qualification and regulatory issues. With some notable exceptions, the result has been a continuing reluctance to undertake the risks and uncertainties of implementing digital actuator technology when replacement opportunities present themselves. Rather, utilities would typically prefer to accept the performance limitations of the legacy analog actuator technologies to avoid impacts to project costs and schedules. The purpose of this report is to demonstrate that the benefits of digital actuator technology can be significant in terms of plant performance and that it is worthwhile to address the barriers currently holding back the widespread development and use of this technology. It addresses two important objectives in pursuit of the beneficial use of digital actuator technology for nuclear power plants: 1. To demonstrate the benefits of digital actuator technology over legacy analog sensor technology in both quantitative and qualitative ways. 2. To recognize and address the added difficulty of digital technology qualification, especially in regard to software common cause failure (SCCF), that is introduced by the use of digital actuator technology.

Ken Thomas; Ted Quinn; Jerry Mauck; Richard Bockhorst

2014-09-01T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear filter technology" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


421

Advanced Remediation Technologies  

SciTech Connect

The United States Department of Energy (DOE), Office of Environmental Management (EM) is responsible for the cleanup of nation's nuclear weapons program legacy wastes, along with waste associated with nuclear energy programs and research. The EM cleanup efforts continue to progress, however the cleanup continues to be technologically complex, heavily regulated, long-term; and the effort also has a high life cycle cost estimate (LCCE) effort. Over the past few years, the EM program has undergone several changes to accelerate its cleanup efforts with varying degrees of success. This article will provide some insight into the Advanced Remediation Technologies (ART) projects that may enhance cleanup efforts and reduce life cycle costs. (authors)

Krahn, St.; Miller, C.E. [The United States Department of Energy, Office of Environmental Management, Washington, D.C. (United States)

2008-07-01T23:59:59.000Z

422

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

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

for Low-Temperature and Low-NOxPM Applications 2004 DEER Conference Presentation: Johnson-Matthey Catalysts 2004deerchatterjee.pdf More Documents & Publications Performance...

423

Nuclear Science Day live webinar (National Nuclear Science Week) - Argonne  

NLE Websites -- All DOE Office Websites (Extended Search)

Nuclear Science Day live webinar Nuclear Science Day live webinar Search Go Home Postdocs Students Student Outreach Resources for Schools U.S.-based International (English) International (Other) Events IGED 2013 Science Careers in Search of Women Girls, choose a career in Nuclear Science and Technology! Argonne Nuclear Engineers tell why they chose a Nuclear Career Resources Contact Us Recent Events Science Careers in Search of Women, Apr. 18, 2013 Junior Girl Scout Workshop 'Atomic Fission Fun with the American Nuclear Society', Jan. 26, 2013 Getting to know nuclear energy: the past, the present & the future - free public lecture (Nov. 15, 2012, Argonne National Laboratory) On January 26, 2013, Argonne staff members participated in the Junior Girl Scout Workshop 'Atomic Fission Fun with the American Nuclear Society'

424

Nuclear Resonance Fluorescence for Nuclear Materials Assay  

E-Print Network (OSTI)

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

Quiter, Brian Joseph

2010-01-01T23:59:59.000Z

425

Nuclear Energy Advisory Committee  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

December 9, 2010 L'Enfant Plaza Hotel Washington, D.C. Committee Members Participating John Ahearne Raymond Juzaitis Ashok Bhatnagar William Martin, Chair Dana Christensen Carl Paperiello Thomas Cochran Burton Richter Michael Corradini John Sackett Marvin Fertel Allen Sessoms Donald Hintz Neil Todreas Committee Members Absent Brew Barron Susan Ion Other Participants: Richard Black, Director, Office of Advanced Reactor Concepts, Office of Nuclear Energy, USDOE Nancy Carder, Medical University of South Carolina, NEAC Support Staff David Hill, Director, Institute for Nuclear Energy Science and Technology, Idaho National Laboratory Shane Johnson, Chief Operating Officer, Office of Nuclear Energy, USDOE

426

Technology, safety, and costs of decommissioning reference nuclear research and test reactors: sensitivity of decommissioning radiation exposure and costs to selected parameters  

SciTech Connect

Additional analyses of decommissioning at the reference research and test (R and T) reactors and analyses of five recent reactor decommissionings are made that examine some parameters not covered in the initial study report (NUREG/CR-1756). The parameters examined for decommissioning are: (1) the effect on costs and radiation exposure of plant size and/or type; (2) the effects on costs of increasing disposal charges and of unavailability of waste disposal capacity at licensed waste disposal facilities; and (3) the costs of and the available alternatives for the disposal of nuclear R and T reactor fuel assemblies.

Konzek, G.J.

1983-07-01T23:59:59.000Z

427

Hybrid Plasma Reactor/Filter for Transportable Collective Protection Systems  

SciTech Connect

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 憌orst-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.

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

2011-04-06T23:59:59.000Z

428

Ceramic hot-gas filter  

DOE Patents (OSTI)

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.

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)

1999-01-01T23:59:59.000Z

429

Ceramic hot-gas filter  

DOE Patents (OSTI)

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.

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

1999-05-11T23:59:59.000Z

430

NUCLEAR ISLANDS International Leasing  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

ISLANDS ISLANDS International Leasing of Nuclear Fuel Cycle Sites to Provide Enduring Assurance of Peaceful Use Christopher E. Paine and Thomas B. Cochran Current International Atomic Energy Agency safeguards do not provide adequate protection against the diversion to military use of materials or technology from certain types of sensitive nuclear fuel cycle facilities. In view of highly enriched uranium's relatively greater ease of use as a nuclear explosive material than plutonium and the significant diseconomies of commercial spent fuel reprocessing, this article focuses on the need for improved international controls over uranium enrichment facilities as the proximate justification for creation of an International Nuclear Fuel Cycle Association (INFCA). In principle, the proposal is equally applicable to alleviating the proliferation concerns provoked by nuclear fuel

431

Fiscal year 1985 Department of Energy authorization (nuclear fission R and D and waste management). Volume IV. Hearings before the Subcommittee on Energy Research and Production of the Committee on Science and Technology, US House of Representatives, Ninety-Eighth Congress, Second Session, February 7, 8, 9, 1984  

SciTech Connect

Volume IV of the DOE authorization hearings covers material relating to research and development on nuclear fission and on waste management during three days of testimony. The 29 witnesses included nuclear scientists in both the private and public sector, as well as specialists in energy policy, electric power, and the nuclear industry. Among the issues covered were the distribution of resources for nuclear research to ensure the development of innovative technology, problems within the nuclear industry, regulatory reform, the progress on spent fuel research and development, and funding for the light water reactor extended burnup program. Chairman Lloyd noted the problems associated with a 50% decline in federal funding during the Reagan administration. An appendix with supplemental questions and answers for the record follows the testimony.

Not Available

1984-01-01T23:59:59.000Z

432

Nuclear Forensics | National Security | ORNL  

NLE Websites -- All DOE Office Websites (Extended Search)

Initiatives Initiatives Cyber Security Nuclear Forensics Bioinformatics National Security Home | Science & Discovery | National Security | Initiatives | Nuclear Forensics SHARE Nuclear Forensics image Tools, techniques, and expertise in nuclear fuel cycle research gained over seven decades help ORNL scientists control and track nuclear bomb-grade materials to be sure they don't fall into the wrong hands. Among the leading-edge technologies used by researchers are high-resolution techniques that allow analysis of radiation detector data in stunning detail. Researchers are also developing aerosol sampling systems to collect airborne particulates and instantly send an alert if radiation is detected. For more information, please contact: nuclearforensicsinitiative

433

Supercomputers | National Nuclear Security Administration  

NLE Websites -- All DOE Office Websites (Extended Search)

Supercomputers | National Nuclear Security Administration Supercomputers | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Continuing Management Reform Countering Nuclear Terrorism About Us Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Media Room Congressional Testimony Fact Sheets Newsletters Press Releases Speeches Events Social Media Video Gallery Photo Gallery NNSA Archive Federal Employment Apply for Our Jobs Our Jobs Working at NNSA Blog The National Nuclear Security Administration Supercomputers Home > About Us > Our Programs > Defense Programs > Future Science & Technology Programs > Office of Advanced Simulation and Computing and Institutional R&D Programs > Supercomputers

434

Ozone Removal by Filters Containing Activated Carbon: A Pilot Study  

E-Print Network (OSTI)

used as the only filter in a HVAC system, in this buildingair conditioning (HVAC) system. Filters containing 300 g of

Fisk, William

2012-01-01T23:59:59.000Z

435

Nuclear Returns  

Science Journals Connector (OSTI)

Nuclear Returns ... For the first time since 1978, the Nuclear Regulatory Commission has given the green light for a new U.S. nuclear power plant. ... NRC granted a license to Southern Co. to build and operate twin 1,100-MW reactors adjacent to two operating nuclear power plants at its Vogtle nuclear facility, near Waynesboro, Ga. ...

JEFF JOHNSON

2012-02-19T23:59:59.000Z

436

Filter for isotopic alteration of mercury vapor  

DOE Patents (OSTI)

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

Grossman, Mark W. (Belmont, MA); George, William A. (Gloucestor, MA)

1989-01-01T23:59:59.000Z

437

Filter for isotopic alteration of mercury vapor  

DOE Patents (OSTI)

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

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

1989-06-13T23:59:59.000Z

438

Vehicle Technologies Program High-temperaturestrengthinthe  

E-Print Network (OSTI)

by DOE's Vehicle Technologies Program, the two partners developed and tested a modified version, gas turbines, and nuclear reactors. The engineering of the microstructure of CF8C, which cannot.vehicles.energy.gov Vehicle Technologies Program Vehicle Technologies Program Contacts Jerry Gibbs Technology Development

Pennycook, Steve

439

Nuclear Nonproliferation  

NLE Websites -- All DOE Office Websites (Extended Search)

Nuclear Nonproliferation As more countries embrace nuclear power as a cost-effective and clean alternative to fossil fuels, the need exists to ensure that the nuclear fuel cycle is...

440

Nuclear Engineering Nuclear Criticality Safety  

E-Print Network (OSTI)

Nuclear Engineering Nuclear Criticality Safety The Nuclear Engineering Division (NE) of Argonne National Laboratory is experienced in performing criticality safety and shielding evaluations for nuclear, and neutron spectra. The NE nuclear criticality safety (NCS) capabilities are based on a staff with decades

Kemner, Ken

Note: This page contains sample records for the topic "nuclear filter technology" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


441

Nuclear Power and its Development  

Science Journals Connector (OSTI)

... make the effect on the coal industry the deciding factor in determining the development of nuclear power. The implications of technological change have been ignored, as has the effect of development ... been ignored, as has the effect of development on the cost of electricity supplied by nuclear power-stations, which Sir Christopher Hinton stressed very strongly in his Axel Ax:son Johnson ...

1959-08-08T23:59:59.000Z

442

Development of Advanced Particulate Filters  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

of Technology ILJIN Electric Co., Korea Relevance and Objectives Existing DPF systems still need to improve filtrationregeneration efficiencies and back pressure. DPF...

443

NUCLEAR REACTORS.  

E-Print Network (OSTI)

??Nuclear reactors are devices containing fissionable material in sufficient quantity and so arranged as to be capable of maintaining a controlled, self-sustaining NUCLEAR FISSION chain (more)

Belachew, Dessalegn

2010-01-01T23:59:59.000Z

444

nuclear reactor  

Science Journals Connector (OSTI)

...a complex atomic apparatus used to obtain energy from nuclear fission chain reaction. Used to produce nuclear energy, radioactive isotopes, and artificial elements.... atomic pile ...

2009-01-01T23:59:59.000Z

445

Nuclear Energy  

NLE Websites -- All DOE Office Websites (Extended Search)

Nuclear Energy Idaho National Laboratory is the Department of Energy's lead nuclear energy research and development facility. Building upon its legacy responsibilities,...

446

Nuclear Hydrogen  

NLE Websites -- All DOE Office Websites (Extended Search)

Error Error Nuclear Hydrogen - RCC cannot be displayed due to a timeout error. We recommend: * Refresh Nuclear Hydrogen - RCC * Increasing your portlet timeout setting. *...

447

Nuclear Physics  

NLE Websites -- All DOE Office Websites (Extended Search)

Underground Research Facility in South Dakota, which will search for neutrinoless double-beta decay. Strong Los Alamos programs in nuclear data and nuclear theory supports...

448

Environment and Nuclear Programs | Department of Energy  

NLE Websites -- All DOE Office Websites (Extended Search)

Environment and Nuclear Programs Environment and Nuclear Programs Environment and Nuclear Programs Cooling Tower Reflection | Credit: DOE Archives Cooling Tower Reflection | Credit: DOE Archives Offices of the Deputy General Counsel for Environment and Nuclear Programs Office of the Assistant General Counsel for Environment (GC-51) Office of the Assistant General Counsel for Civilian Nuclear Programs (GC-52 ) Office of the Assistant General Counsel for International and National Security Programs (GC-53) Office of NEPA Policy and Compliance (GC-54) Office of Standard Contract Management (GC-55) Litigation and Enforcement Environment and Nuclear Programs Environment Civilian Nuclear Programs International and National Security Programs NEPA Policy and Compliance Standard Contract Management Technology Transfer and Procurement

449

Final Technical Report; NUCLEAR ENGINEERING RECRUITMENT EFFORT  

SciTech Connect

This report provides the summary of a project whose purpose was to support the costs of developing a nuclear engineering awareness program, an instruction program for teachers to integrate lessons on nuclear science and technology into their existing curricula, and web sites for the exchange of nuclear engineering career information and classroom materials. The specific objectives of the program were as follows: OBJECTIVE 1: INCREASE AWARENESS AND INTEREST OF NUCLEAR ENGINEERING; OBJECTIVE 2: INSTRUCT TEACHERS ON NUCLEAR TOPICS; OBJECTIVE 3: NUCLEAR EDUCATION PROGRAMS WEB-SITE; OBJECTIVE 4: SUPPORT TO UNIVERSITY/INDUSTRY MATCHING GRANTS AND REACTOR SHARING; OBJECTIVE 5: PILOT PROJECT; OBJECTIVE 6: NUCLEAR ENGINEERING ENROLLMENT SURVEY AT UNIVERSITIES

Kerrick, Sharon S.; Vincent, Charles D.

2007-07-02T23:59:59.000Z

450

The effect of porosity on the mechanical properties of cordierite diesel particulate filter substrates  

SciTech Connect

Diesel particulate filter (DPF) technology depends on porous ceramic structures that trap the particulate matter in the diesel engine exhaust gas stream. The design of DPFs requires balancing the functional requirement of soot filtration with the mechanical properties and both are influenced by the porosity of the substrate. In addition, increasing the porosity of the substrate can assist with the catalytic washcoating, engine back pressure and engine efficiency. The effect of porosity on the elastic and fracture mechanical properties of cordierite based ceramic particulate filters was examined and will be described. Elastic modulus of DPF substrates was determined using resonant ultrasound spectroscopy while fracture toughness was characterized using the double-torsion test method. The interrelationships among specimen thickness, wall orientation, porosity and mechanical properties of the filter substrates will be discussed. A materials selection procedure to obtain filters with high thermal shock resistance and optimal mechanical properties will be described.

Shyam, Amit [ORNL; Lara-Curzio, Edgar [ORNL; Watkins, Thomas R [ORNL

2009-01-01T23:59:59.000Z

451

Virtual nuclear weapons  

SciTech Connect

The term virtual nuclear weapons proliferation and arsenals, as opposed to actual weapons and arsenals, has entered in recent years the American lexicon of nuclear strategy, arms control, and nonproliferation. While the term seems to have an intuitive appeal, largely due to its cyberspace imagery, its current use is still vague and loose. The author believes, however, that if the term is clearly delineated, it might offer a promising approach to conceptualizing certain current problems of proliferation. The first use is in a reference to an old problem that has resurfaced recently: the problem of growing availability of weapon-usable nuclear materials in civilian nuclear programs along with materials made `excess` to defense needs by current arms reduction and dismantlement. It is argued that the availability of these vast materials, either by declared nuclear-weapon states or by technologically advanced nonweapon states, makes it possible for those states to rapidly assemble and deploy nuclear weapons. The second use has quite a different set of connotations. It is derived conceptually from the imagery of computer-generated reality. In this use, one thinks of virtual proliferation and arsenals not in terms of the physical hardware required to make the bomb but rather in terms of the knowledge/experience required to design, assemble, and deploy the arsenal. Virtual weapons are a physics reality and cannot be ignored in a world where knowledge, experience, materials, and other requirements to make nuclear weapons are widespread, and where dramatic army reductions and, in some cases, disarmament are realities. These concepts are useful in defining a continuum of virtual capabilities, ranging from those at the low end that derive from general technology diffusion and the existence of nuclear energy programs to those at the high end that involve conscious decisions to develop or maintain militarily significant nuclear-weapon capabilities.

Pilat, J.F.

1997-08-01T23:59:59.000Z

452

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

E-Print Network (OSTI)

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 ...

Neklyudov, I M; Poltinin, P Ya; Ledenyov, O P

2013-01-01T23:59:59.000Z

453

A critical study on Kennedys Cost-Benefit-Analysis 慛ew nuclear power generation in the UK.  

E-Print Network (OSTI)

?? The demand for energy is forever growing. The technology of extracting power from uranium through nuclear facilities is rather old. Core melting, nuclear bombs, (more)

Str鋘g, Jonathan

2011-01-01T23:59:59.000Z

454

E-Print Network 3.0 - alternative nuclear fuel Sample Search...  

NLE Websites -- All DOE Office Websites (Extended Search)

Summary: of electricity from nuclear power plants is far less than any of the alternative energy technologies now contem... Processing of Nuclear Fuel, EGRN 430 ...

455

Energy Recovered Light Source Technology at TJNAF | U.S. DOE...  

Office of Science (SC) Website

Energy Recovered Light Source Technology at TJNAF Nuclear Physics (NP) NP Home About Research Facilities Science Highlights Benefits of NP Applications of Nuclear Science...

456

Widget:RRSectionFilter | Open Energy Information  

Open Energy Info (EERE)

RRSectionFilter RRSectionFilter Jump to: navigation, search This widget creates a filter tool, which will allow the user to filter the content displayed on the screen by RR Section region. It has been designed for use explicitly with the Geothermal Regulatory Roadmap home page. It is not designed for any other use. Parameters No paramteres Dependancies The Geothermal Regulatory Roadmap Sections page. Usage This Widget assumes the existence of HTML elements created by the Geothermal Regulatory Roadmap Sections page, and is called by that page using the following code: {{#Widget:RRSectionFilter}} Example For an example of this widget in use, please visit the page referenced above. (GRR/Sections) Retrieved from "http://en.openei.org/w/index.php?title=Widget:RRSectionFilter&oldid=65912

457

Multi-Canister overpack internal HEPA filters  

SciTech Connect

The rationale for locating a filter assembly inside each Multi-Canister Overpack (MCO) rather than include the filter in the Cold Vacuum Drying (CVD) process piping system was to eliminate the potential for contamination to the operators, processing equipment, and the MCO. The internal HEPA filters provide essential protection to facility workers from alpha contamination, both external skin contamination and potential internal depositions. Filters installed in the CVD process piping cannot mitigate potential contamination when breaking the process piping connections. Experience with K-Basin material has shown that even an extremely small release can result in personnel contamination and costly schedule disruptions to perform equipment and facility decontamination. Incorporating the filter function internal to the MCO rather than external is consistent with ALARA requirements of 10 CFR 835. Based on the above, the SNF Project position is to retain the internal HEPA filters in the MCO design.

SMITH, K.E.

1998-11-03T23:59:59.000Z

458

Nuclear Matter and Nuclear Dynamics  

E-Print Network (OSTI)

Highlights on the recent research activity, carried out by the Italian Community involved in the "Nuclear Matter and Nuclear Dynamics" field, will be presented.

M Colonna

2009-02-26T23:59:59.000Z

459

Suggestion of typical phases of in-vessel fuel-debris by thermodynamic calculation for decommissioning technology of Fukushima-Daiichi nuclear power station  

SciTech Connect

For the decommissioning of the Fukushima-Daiichi Nuclear Power Station (1F), the characterization of fuel-debris in cores of Units 1-3 is necessary. In this study, typical phases of the in-vessel fuel-debris were estimated using a thermodynamic equilibrium (TDE) calculation. The FactSage program and NUCLEA database were applied to estimate the phase equilibria of debris. It was confirmed that the TDE calculation using the database can reproduce the phase separation behavior of debris observed in the Three Mile Island accident. In the TDE calculation of 1F, the oxygen potential [G(O{sub 2})] was assumed to be a variable. At low G(O{sub 2}) where metallic zirconium remains, (U,Zr)O{sub 2}, UO{sub 2}, and ZrO{sub 2} were found as oxides, and oxygen-dispersed Zr, Fe{sub 2}(Zr,U), and Fe{sub 3}UZr{sub 2} were found as metals. With an increase in zirconium oxidation, the mass of those metals, especially Fe{sub 3}UZr{sub 2}, decreased, but the other phases of metals hardly changed qualitatively. Consequently, (U,Zr)O{sub 2} is suggested as a typical phase of oxide, and Fe{sub 2}(Zr,U) is suggested as that of metal. However, a more detailed estimation is necessary to consider the distribution of Fe in the reactor pressure vessel through core-melt progression. (authors)

Ikeuchi, Hirotomo; Yano, Kimihiko; Kaji, Naoya; Washiya, Tadahiro [Japan Atomic Energy Agency, 4-33 Muramatsu, Tokai-mura, Ibaraki-ken, 319-1194 (Japan); Kondo, Yoshikazu; Noguchi, Yoshikazu [PESCO Co.Ltd. (Korea, Republic of)

2013-07-01T23:59:59.000Z

460

Dynamical decoupling sequence construction as a filter-design problem  

E-Print Network (OSTI)

Over the past decade we have seen an explosion of demonstrations of quantum coherence in atomic, optical, and condensed matter systems. These developments have placed a new emphasis on the production of robust and optimal quantum control techniques in the presence of environmental noise. We discuss the use of dynamical decoupling as a form of open-loop quantum control capable of suppressing the effects of dephasing in quantum coherent systems. We introduce the concept of dynamical decoupling pulse-sequence construction as a filter-design problem, making connections with filter design from control theory and electrical engineering in the analysis of pulse-sequence performance for the preservation of the phase degree of freedom in a quantum superposition. A detailed mathematical description of how dephasing and the suppression of dephasing can be reduced to a linear control problem is provided, and used as motivation and context for studies of the filtration properties of various dynamical decoupling sequences. Our work then takes this practical perspective in addressing both "standard" sequences derived from nuclear magnetic resonance and novel optimized sequences developed in the context of quantum information. Additionally, we review new techniques for the numerical construction of optimized pulse sequences using the filter-design perspective. We show how the filter-design perspective permits concise comparisons of the relative capabilities of these sequences and reveals the physics underlying their functionality. The use of this new analytical framework allows us to derive new insights into the performance of these sequences and reveals important limiting issues, such as the effect of digital clocking on optimized sequence performance.

M. J. Biercuk; A. C. Doherty; H. Uys

2011-04-23T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear filter technology" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


461

Ground Testing a Nuclear Thermal Rocket: Design of a sub-scale demonstration experiment  

SciTech Connect

In 2008, the NASA Mars Architecture Team found that the Nuclear Thermal Rocket (NTR) was the preferred propulsion system out of all the combinations of chemical propulsion, solar electric, nuclear electric, aerobrake, and NTR studied. Recently, the National Research Council committee reviewing the NASA Technology Roadmaps recommended the NTR as one of the top 16 technologies that should be pursued by NASA. One of the main issues with developing a NTR for future missions is the ability to economically test the full system on the ground. In the late 1990s, the Sub-surface Active Filtering of Exhaust (SAFE) concept was first proposed by Howe as a method to test NTRs at full power and full duration. The concept relied on firing the NTR into one of the test holes at the Nevada Test Site which had been constructed to test nuclear weapons. In 2011, the cost of testing a NTR and the cost of performing a proof of concept experiment were evaluated.

David Bedsun; Debra Lee; Margaret Townsend; Clay A. Cooper; Jennifer Chapman; Ronald Samborsky; Mel Bulman; Daniel Brasuell; Stanley K. Borowski

2012-07-01T23:59:59.000Z

462

Diesel particulate filter with zoned resistive heater  

DOE Patents (OSTI)

A diesel particulate filter assembly comprises a diesel particulate filter (DPF) and a heater assembly. The DPF filters a particulate from exhaust produced by an engine. The heater assembly has a first metallic layer that is applied to the DPF, a resistive layer that is applied to the first metallic layer, and a second metallic layer that is applied to the resistive layer. The second metallic layer is etched to form a plurality of zones.

Gonze, Eugene V [Pinckney, MI

2011-03-08T23:59:59.000Z

463

Zone heated diesel particulate filter electrical connection  

DOE Patents (OSTI)

An electrical connection system for a particulate filter is provided. The system includes: a particulate filter (PF) disposed within an outer shell wherein the PF is segmented into a plurality of heating zones; an outer mat disposed between the particulate filter and the outer shell; an electrical connector coupled to the outer shell of the PF; and a plurality of printed circuit connections that extend along the outer surface of the PF from the electrical connector to the plurality of heating zones.

Gonze, Eugene V. (Pinckney, MI); Paratore, Jr., Michael J. (Howell, MI)

2010-03-30T23:59:59.000Z

464

DC side filters for multiterminal HVDC systems  

SciTech Connect

Multiterminal HVDC systems present challenges in the specification and design of suitable dc side filtering. This document examines the existing experience and addresses the particular technical problems posed by multiterminal systems. The filtering requirements of small taps are discussed, as is the potential use of active filters. Aspects of calculation and design are considered and recommendations made to guide the planners and designers of future multiterminal schemes.

Shore, N.L.; Adamson, K.; Bard, P. [and others] [and others

1996-10-01T23:59:59.000Z

465

nuclear power Update of the mit 2003  

E-Print Network (OSTI)

#12;Future of nuclear power Update of the mit 2003 PROFESSOR JOHN M.DEUTCH Institute Professor of Technology. All rights reserved. #12;Update of the MIT 2003 Future of Nuclear Power Study 3 In 2003 a group of MIT faculty issued a study on The Future of Nuclear Power.1 The study was motivated by growing concern

Reuter, Martin

466

The Politically Correct Nuclear Energy Plant  

E-Print Network (OSTI)

The Politically Correct Nuclear Energy Plant Andrew C. Kadak Massachusetts Institute of Technology - Small is Beautiful 路 Nuclear Energy - But Getting Better #12;Politically Correct ! 路 Natural Safety is a bad idea. 路 There is no new nuclear energy plant that is competitive at this time. 路 De-regulation did

467

1 1/15/2014 Technologies  

E-Print Network (OSTI)

1 1/15/2014 Energy Technologies Electricity Delivery/ Energy Reliability Dominic Lee EERE Support Tracy Strader Nuclear Fuels Gary Bell (NSED) Nuclear颅Light Water Reactors Jeremy Busby Tech Lara-Curzio Nuclear Fuel Materials Gary Bell (NSED) Radiation Effects and Microstructural Analysis

468

Working Group Report on - Space Nuclear Power Systems and Nuclear Waste  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Working Group Report on - Space Nuclear Power Systems and Nuclear 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 though one cannot anticipate the answers in basic research, the return on the public's investment can be maximized through long-range planning of the most promising avenues to explore and the resources needed to explore them." (p. v) "Pursuit of this goal entails developing new technologies and advanced facilities, educating young scientists, training a technical workforce, and contributing to the broader science and technology enterprise?." (p. vi) Ref:: "Nuclear Science: A Long Range Plan", DOE/NSF, Feb. 1996. The purpose of this effort is to develop the first iteration of a

469

Working Group Report on - Space Nuclear Power Systems and Nuclear Waste  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Working Group Report on - Space Nuclear Power Systems and Nuclear 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 though one cannot anticipate the answers in basic research, the return on the public's investment can be maximized through long-range planning of the most promising avenues to explore and the resources needed to explore them." (p. v) "Pursuit of this goal entails developing new technologies and advanced facilities, educating young scientists, training a technical workforce, and contributing to the broader science and technology enterprise?." (p. vi) Ref:: "Nuclear Science: A Long Range Plan", DOE/NSF, Feb. 1996. The purpose of this effort is to develop the first iteration of a

470

Electrically-Assisted Diesel Particulate Filter Regeneration...  

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

Evaluation pm041lance2011p.pdf More Documents & Publications Electrically-Assisted Diesel Particulate Filter Regeneration Substrate Studies of an Electrically-Assisted Diesel...

471

Magnetic Filtration Process, Magnetic Filtering Material, and...  

NLE Websites -- All DOE Office Websites (Extended Search)

SummaryORNL researchers developed a new method for filtering materials and managing wastewater. This invention offers an integrated, intensified process to handle organic...

472

Nuclear code of ethics  

Science Journals Connector (OSTI)

The nuclear industry is inseparable from the other techniques making up our industrial society. It is not an excrescence that can be lanced without impinging upon the other sectors of this society, one of whose aspects is its interrelativity. The ethical question concerning nuclear energy in its application, its operation, its use, is part of a wider question from which it cannot be separated: the question of development and of technical progress. It is one of the impressive aspects of nuclear energy, either because its technology and performance are admired, or because its effects are feared and its potential perils denounced. Nuclear energy is a fruit of the irreversible progress of scientific and technical knowledge, which brought it into being, and whose expansion it now largely ensures. It derives from the profound dynamics of human beings wishing to put their knowledge at the service of humanity, for its well-being and its development.

World Council of Nuclear Workers

2005-01-01T23:59:59.000Z

473

Chapter 7 - Nuclear Energy  

Science Journals Connector (OSTI)

Abstract Nuclear energy grew rapidly during the 19601975 period in countries such as France, the United States, and Norway. But nuclear energy ran into problems in the 1970s because of public concern over the radioactive waste it generates, and this concern suppressed the further expansion of nuclear power. The public perception had begun to change in recent years, as concern about atmospheric carbon dioxide levels led to a renewed interest in energy sources not reliant on hydrocarbons. But, in 2010, a tsunami in Japan led to an accident at the Fukushima nuclear power plant, and the ensuing release of radioactive materials once again raised concerns about safety. At the same time, limited supplies of uranium have caused the price of that fuel material to go up. The solution to the shortage and resulting price increase is fast breeder reactors that use both uranium and thorium fuels. Unfortunately, this