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to obtain the most current and comprehensive results.


1

Nuclear Filter Technology | Open Energy Information  

Open Energy Info (EERE)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home5b9fcbce19 No revision hasInformation Earth's HeatMexico:CommunityNorthwest Basin andNsbowde's blog Home >NuFilter

2

Advanced Particulate Filter Technologies for Direct Injection...  

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

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

3

Plasma Mass Filters For Nuclear Waste Reprocessing  

SciTech Connect (OSTI)

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

2011-05-25T23:59:59.000Z

4

Plasma Mass Filters For Nuclear Waste Reprocessing  

SciTech Connect (OSTI)

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

Nuclear Reactors and Technology  

SciTech Connect (OSTI)

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

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

1992-01-01T23:59:59.000Z

7

Nuclear Technology Programs  

SciTech Connect (OSTI)

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

Harmon, J.E. (ed.)

1990-10-01T23:59:59.000Z

8

Advanced Particulate Filter Technologies for Direct Injection...  

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

Public * Continuing efforts for further CO 2 and PN reduction create a challenging environment for vehicles equipped with DI gasoline engines * Gasoline particulate filters...

9

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

10

Nuclear Proliferation Technology Trends Analysis  

SciTech Connect (OSTI)

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

11

Nuclear Reactors and Technology; (USA)  

SciTech Connect (OSTI)

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

12

Nuclear Science & Technology  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear Security Administration the ContributionsArms Control R&D ConsortiumNuclearSafeguards and Nuclear

13

Nuclear power high technology colloquium: proceedings  

SciTech Connect (OSTI)

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

Not Available

1984-12-10T23:59:59.000Z

14

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

E-Print Network [OSTI]

Fusion Nuclear Science and Technology (FNST)Fusion Nuclear Science and Technology (FNST) Challenges these issues. 2 #12;FNST is the science, engineering, technology and materials Fusion Nuclear Science & Technology (FNST) FNST is the science, engineering, technology and materials for the fusion nuclear

Abdou, Mohamed

15

Security Science & Technology | Nuclear Science | ORNL  

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

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

16

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

17

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

E-Print Network [OSTI]

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

Abdou, Mohamed

18

Nuclear Systems Technology | Nuclear Science | ORNL  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear Security Administration the ContributionsArms Control R&D ConsortiumNuclearSafeguardsResearch AreasNuclear

19

Oil Bypass Filter Technology Performance Evaluation - First Quarterly Report  

SciTech Connect (OSTI)

This report details the initial activities to evaluate the performance of the oil bypass filter technology being tested by the Idaho National Engineering and Environmental Laboratory (INEEL) for the U.S. Department of Energy's FreedomCAR & Vehicle Technologies Program. Eight full-size, four-cycle diesel-engine buses used to transport INEEL employees on various routes have been equipped with oil bypass systems from the puraDYN Corporation. Each bus averages about 60,000 miles a year. The evaluation includes an oil analysis regime to monitor the presence of necessary additives in the oil and to detect undesirable contaminants. Very preliminary economic analysis suggests that the oil bypass system can reduce life-cycle costs. As the evaluation continues and oil avoidance costs are quantified, it is estimated that the bypass system economics may prove increasingly favorable, given the anticipated savings in operational costs and in reduced use of oil and waste oil avoidance.

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

2003-01-31T23:59:59.000Z

20

Oil Bypass Filter Technology Performance Evaluation - January 2003 Quarterly Report  

SciTech Connect (OSTI)

This report details the initial activities to evaluate the performance of the oil bypass filter technology being tested by the Idaho National Engineering and Environmental Laboratory (INEEL) for the U.S. Department of Energy's FreedomCAR & Vehicle Technologies Program. Eight full-size, four-cycle diesel-engine buses used to transport INEEL employees on various routes have been equipped with oil bypass systems from the puraDYN Corporation. Each bus averages about 60,000 miles a year. The evaluation includes an oil analysis regime to monitor the presence of necessary additives in the oil and to detect undesirable contaminants. Very preliminary economic analysis suggests that the oil bypass system can reduce life-cycle costs. As the evaluation continues and oil avoidance costs are quantified, it is estimated that the bypass system economics may prove increasingly favorable, given the anticipated savings in operational costs and in reduced use of oil and waste oil avoidance.

Laurence R. Zirker; James E. Francfort

2003-01-01T23:59:59.000Z

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.


21

Nuclear technology for the year 2000  

SciTech Connect (OSTI)

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

22

The nuclear materials control technology briefing book  

SciTech Connect (OSTI)

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

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

1992-03-01T23:59:59.000Z

23

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

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

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...

24

DOE NHI: Progress in Nuclear Connection Technologies  

SciTech Connect (OSTI)

The U.S. Department of Energy Nuclear Hydrogen Initiative (NHI) is seeking to develop the technologies to enable the large-scale production of hydrogen from water using a nuclear powered heat source. A necessary component in any nuclear powered hydrogen production process is the energy transfer connection between the nuclear plant and the hydrogen plant. This article provides an overview of the research and development work that has been accomplished on the high-temperature heat transfer connection between the nuclear power plant and the hydrogen production plant by the NHI. A description of future work is also provided.

Steven R. Sherman

2007-06-01T23:59:59.000Z

25

SOMS HYBRID SPIN-ON FILTER Sponsor: SOMS Technologies  

E-Print Network [OSTI]

the lubricating oil. Some premium filters state filtration efficiency down to 25 microns. However, it is particles engine oil filters effectively remove contaminant particles larger than 40 -50 microns from smaller than these, which accumulate in the oil, damage the filter, and force regular and frequent oil

Salama, Khaled

26

Spent Nuclear Fuel Alternative Technology Decision Analysis  

SciTech Connect (OSTI)

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

27

Current Abstracts Nuclear Reactors and Technology  

SciTech Connect (OSTI)

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

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

1993-01-01T23:59:59.000Z

28

Future AI and Robotics Technology for Nuclear Plants Decommissioning  

E-Print Network [OSTI]

Future AI and Robotics Technology for Nuclear Plants Decommissioning Huosheng Hu and Liam Cragg to aid in decommissioning nuclear plants that have been used to process or store nuclear materials. Scope potential applications to nuclear plant decommissioning, namely Nanotechnology, Telepresence

Hu, Huosheng

29

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

30

technology | National Nuclear Security Administration  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear SecurityTensile Strain Switched5 Industrial Carbon CaptureFY08 JointProgramApplication ofU Ctdball Amestechnology |

31

Reactor Technology | Nuclear Science | ORNL  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear Security Administration the1 -the Mid-Infrared at 278, 298, andEpidermalOxide Fuel CellsReaction of NO2, H2O and

32

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

33

M. Abdou April 2013 Fusion Nuclear Science and Technology  

E-Print Network [OSTI]

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

Abdou, Mohamed

34

Review of Current Nuclear Vacuum System Technologies  

SciTech Connect (OSTI)

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

35

Nuclear fission and nuclear safeguards: Common technologies and challenges  

SciTech Connect (OSTI)

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

Keepin, G.R.

1989-01-01T23:59:59.000Z

36

Improved Technology To Prevent Nuclear Proliferation And Counter Nuclear Terrorism  

SciTech Connect (OSTI)

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

37

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

38

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

39

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

40

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

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

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

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

Freeze Technology for Nuclear Applications - 13590  

SciTech Connect (OSTI)

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

42

ANALYSIS OF VAPORS FROM METHYLENE CHLORIDE EXTRACTS OF NUCLEAR GRADE HEPA FILTER FIBERGLASS SAMPLES  

SciTech Connect (OSTI)

While several organic compounds were detected in the vapor samples used in the reenactment of the preparation of mounts from the extracts of nuclear grade high-efficiency particulate air filter fiberglass samples, the most significant species present in the samples were methylene chloride, phenol, phenol-d6, and 2-fluorophenol. These species were all known to be present in the extracts, but were expected to have evaporated during the preparation of the mounts, as the mounts appeared to be dry before any vapor was collected. These species were present at the following percentages of their respective occupational exposure limits: methylene chloride, 2%; phenol, 0.4%; and phenol-d6, 0.6%. However, there is no established limit for 2-fluorophenol. Several other compounds were detected at low levels for which, as in the case of 2-fluorophenol, there are no established permissible exposure limits. These compounds include 2-chlorophenol; N-nitroso-1-propanamine; 2-fluoro-1,1{prime}-biphenyl; 1,2-dihydroacenaphthylene; 2,5-cyclohexadiene-1,4-dione,2,6-bis(1,1-dimethylethyl); trimethyl oxirane; n-propylpropanamine; 2-(Propylamino)ethanol; 4-methoxy-1-butene; 6-methyl-5-hepten-2-one; and 3,4-dimethylpyridine. Some of these were among those added as surrogates or spike standards as part ofthe Advanced Technologies and Laboratories International, Inc. preparation ofthe extract of the HEPA filter media and are indicated as such in the data tables in Section 2, Results; other compounds found were not previously known to be present. The main inorganic species detected (sulfate, sodium, and sulfur) are also consistent with species added in the preparation of the methylene chloride extract of the high-efficiency particulate air sample.

FRYE JM; ANASTOS HL; GUTIERREZ FC

2012-06-07T23:59:59.000Z

43

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

E-Print Network [OSTI]

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

Crawford, T. Daniel

44

Nuclear Separations Technologies Workshop Report 2011  

Office of Environmental Management (EM)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "of EnergyEnergyENERGY TAXBalanced ScorecardReactor Technology Subcommittee of NEACSummary Nucleari NUCLEAR

45

Fusion Nuclear Science and Technology (FNST) Challenges and Facilities  

E-Print Network [OSTI]

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

46

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

SciTech Connect (OSTI)

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

47

Space nuclear power, propulsion, and related technologies.  

SciTech Connect (OSTI)

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

Berman, Marshall

1992-01-01T23:59:59.000Z

48

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

E-Print Network [OSTI]

of operating NPP; 路 NPP decommissioning and waste treatment; 路 Novel reactor concepts and Nuclear Fuel CycleISTCISTC 16 years of successful projects in16 years of successful projects in Nuclear Science & TechnologyNuclear Science & Technology 13th CERNISTC SAC Seminar New Perspectives of High Energy Physics 01

49

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...

50

Operation technology of air treatment system in nuclear facilities  

E-Print Network [OSTI]

Effective operation techniques were reviewed on the air treatment system to protect the personnel in nuclear facilities from the contamination of radio-active particles and to keep the environment clear. Nuclear air treatment system consisted of the ventilation and filtering system was characterized by some test. Measurement of air velocity of blowing/exhaust fan in the ventilation system, leak tests of HEPA filters in the filtering, and measurement of pressure difference between the areas defined by radiation level were conducted. The results acquired form the measurements were reflected directly for the operation of air treatment. In the abnormal state of virus parts of devices composted of the system, the repairing method, maintenance and performance test were also employed in operating effectively the air treatment system. These measuring results and techniques can be available to the operation of air treatment system of PIEF as well as the other nuclear facilities in KAERI.

Chun, Y B; Hwong, Y H; Lee, H K; Min, D K; Park, K J; Uom, S H; Yang, S Y

2001-01-01T23:59:59.000Z

51

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

SciTech Connect (OSTI)

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

52

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"

53

Nuclear export and technology transfer controls  

SciTech Connect (OSTI)

A review of the U.S. implementation of nuclear export and technology transfer controls is undertaken to assess whether the U.S. controls is undertaken to assess whether the U.S. controls meet the full scope of the international commitment toward non-proliferation controls. The international non-proliferation controls have been incorporated into CoCom, the Coordinating Committee of the multinational organization established to protect the mutual interests of the participating countries in the area of strategic export controls. However, this CoCom list is classified and each participating country implements these controls pursuant to its own laws. A comparison to the non-proliferation controls promulgated by the U.K. is used to verify that the U.S. controls are at least as comprehensive as the British controls.

Hower, J.J.; Primeau, S.J. (Eagle Research Group, Inc., Arlington, VA (US))

1988-01-01T23:59:59.000Z

54

Oil Bypass Filter Technology Evaluation Tenth Quarterly Report January朚arch 2005  

SciTech Connect (OSTI)

This Oil Bypass Filter Technology Evaluation quarterly report (January March 2005) details the ongoing fleet evaluation of oil bypass filter technologies being conducted by the Idaho National Laboratory (INL) for the U.S. Department of Energy抯 FreedomCAR & Vehicle Technologies Program. Eleven INL fourcycle diesel-engine buses and six INL Chevrolet Tahoes with gasoline engines are equipped with oil bypass filter systems. Eight of the buses and the six Tahoes are equipped with oil bypass filters from the puraDYN Corporation; the remaining three buses are equipped with oil bypass filters from Refined Global Solutions. Both the puraDYN and Refined Global Solutions bypass filters have a heating chamber to remove liquid contaminates from the oil. During the January to March 2005 reporting quarter, the eleven diesel engine buses traveled 97,943 miles. As of March 31, 2005, the buses had accumulated 744,059 total test miles. During this quarter, four regularly scheduled 12,000-mile bus servicings were performed. The full-flow and bypass oil filters were changed and oil analysis samples were taken for the four buses. Bus 73446 had its oil changed due to a low total base number value. Bus 73450 had a major engine failure at the beginning of the quarter when one of its pushrods and valves were damaged. Buses 73432 and 73433 were removed from the bypass filter evaluation project and placed into the INL Diesel Engine Idling Wear-Rate Evaluation Test. While a total of nine oil changes on the INL buses occurred during the past 29 months, 53 oil changes have been avoided by using the oil bypass filters. The 53 avoided oil changes equates to 1,855 quarts (464 gallons) of new oil not consumed and 1,855 quarts of waste oil not generated. Therefore, over 85% of the oil normally required for oil-changes was not used, and, consequently, the evaluation achieved a greater than 85% reduction in the amount of waste oil normally generated by the buses. The six Tahoe test vehicles traveled 40,700 miles, and as of March 31, 2005, the Tahoes had accumulated 231,428 total test miles.

Larry Ziker; James Francfort

2005-06-01T23:59:59.000Z

55

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 Rennich, Phil Spampinato (spampinatop@ornl.gov, 865-576-5267) Equipment Decommissioning and Disposition September 1, 2004 Oak Ridge National Laboratory #12;2 NUCLEAR SCIENCE AND TECHNOLOGY DIVISION OAK RIDGE

McDonald, Kirk

56

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

57

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

58

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

59

ANS 2006 WINTER MEETING & Nuclear Technology Expo  

E-Print Network [OSTI]

; and Embedded Topical Meeting: NPIC&HMIT 2006 Alaron Corporation Ameren UE/Callaway Nuclear Plant Atomic Energy) EXCEL Services Corporation Florida Power & Light GE Nuclear Energy Idaho National Laboratory INVENSYS/Lockheed Martin Sargent & Lundy TVA U.S. Department of Energy, Nuclear Engineering U.S. Nuclear Regulatory

Krings, Axel W.

60

Technology Readiness Levels for Advanced Nuclear Fuels and Materials Development  

SciTech Connect (OSTI)

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

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

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

E-Print Network [OSTI]

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

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

2013-01-01T23:59:59.000Z

62

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

Broader source: Energy.gov [DOE]

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

63

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

E-Print Network [OSTI]

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

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

2013-06-21T23:59:59.000Z

64

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...

65

Configuration and technology implications of potential nuclear hydrogen system applications.  

SciTech Connect (OSTI)

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

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

2005-11-05T23:59:59.000Z

66

Ground-based Nuclear Detonation Detection (GNDD) Technology Roadmap  

SciTech Connect (OSTI)

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

Casey, Leslie A.

2014-01-13T23:59:59.000Z

67

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

E-Print Network [OSTI]

References #12;References R-3 REFERENCES ANS 1986. Glossary of Terms in Nuclear Science and Technology, American Nuclear Society. ANSI 1969. N13.1, Sampling Airborne Radioactive Materials in Nuclear for Application to Radioactive Dosimetry and Radiological Assessments, DOE/TIC-11026, U.S. Department of Energy

Pennycook, Steve

68

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

E-Print Network [OSTI]

References #12;References R-3 REFERENCES ANS 1986. Glossary of Terms in Nuclear Science and Technology, American Nuclear Society. ANSI 1969. N13.1, Sampling Airborne Radioactive Materials in Nuclear: A Handbook of Decay Data for Application to Radioactive Dosimetry and Radiological Assessments, DOE/TIC-11026

Pennycook, Steve

69

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...

70

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

SciTech Connect (OSTI)

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

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

2006-03-01T23:59:59.000Z

71

E-Print Network 3.0 - advanced nuclear technology Sample Search...  

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

: Objectives: Develop and demonstrate technologies for detecting the stages of a foreign nuclear weapons... and Testing Nonproliferation Enabling Technologies ... Source:...

72

E-Print Network 3.0 - advancing nuclear technology Sample Search...  

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

: Objectives: Develop and demonstrate technologies for detecting the stages of a foreign nuclear weapons... and Testing Nonproliferation Enabling Technologies ... Source:...

73

Nuclear Physics Technology Saves Lives | Jefferson Lab  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear Security Administration the ContributionsArms Control R&D ConsortiumNuclear PairsNuclear Physics

74

Advanced Technology Development and Mitigation | National Nuclear...  

National Nuclear Security Administration (NNSA)

Technology Development and Mitigation This sub-program includes laboratory code and computer engineering and science projects that pursue long-term simulation and computing goals...

75

Technologies for detection of nuclear materials  

SciTech Connect (OSTI)

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

76

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

77

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

78

Global Nuclear Energy Partnership Technology Development Plan  

SciTech Connect (OSTI)

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

David J. Hill

2007-07-01T23:59:59.000Z

79

Evaluating Russian space nuclear reactor technology for United States applications  

SciTech Connect (OSTI)

Space nuclear power and nuclear electric propulsion are considered important technologies for planetary exploration, as well as selected earth orbit applications. The Nuclear Electric Propulsion Space Test Program (NEPSTP) was intended to provide an early flight demonstration of these technologies at relatively low cost through extensive use of existing Russian technology. The key element of Russian technology employed in the program was the Topaz II reactor. Refocusing of the activities of the Ballistic Missile Defense Organization (BMDO), combined with budgetary pressures, forced the cancellation of the NEPSTP at the end of the 1993 fiscal year. The NEPSTP was faced with many unique flight qualification issues. In general, the launch of a spacecraft employing a nuclear reactor power system complicates many spacecraft qualification activities. However, the NEPSTP activities were further complicated because the reactor power system was a Russian design. Therefore, this program considered not only the unique flight qualification issues associated with space nuclear power, but also with differences between Russian and United States flight qualification procedures. This paper presents an overview of the NEPSTP. The program goals, the proposed mission, the spacecraft, and the Topaz II space nuclear power system are described. The subject of flight qualification is examined and the inherent difficulties of qualifying a space reactor are described. The differences between United States and Russian flight qualification procedures are explored. A plan is then described that was developed to determine an appropriate flight qualification program for the Topaz II reactor to support a possible NEPSTP launch.

Polansky, G.F. [Phillips Lab., Albuquerque, NM (United States); Schmidt, G.L. [New Mexico Engineering Research Institute, Albuquerque, NM (United States); Voss, S.S. [Los Alamos National Lab., NM (United States); Reynolds, E.L. [Applied Physics Lab., Laurel, MD (United States)

1994-08-01T23:59:59.000Z

80

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

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

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

SciTech Connect (OSTI)

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

David Shropshire

2009-09-01T23:59:59.000Z

82

Nuclear waste repository transparency technology test bed demonstrations at WIPP  

SciTech Connect (OSTI)

Secretary of Energy, Bill Richardson, has stated that one of the nuclear waste legacy issues is ``The challenge of managing the fuel cycle's back end and assuring the safe use of nuclear power.'' Waste management (i.e., the back end) is a domestic and international issue that must be addressed. A key tool in gaining acceptance of nuclear waste repository technologies is transparency. Transparency provides information to outside parties for independent assessment of safety, security, and legitimate use of materials. Transparency is a combination of technologies and processes that apply to all elements of the development, operation, and closure of a repository system. A test bed for nuclear repository transparency technologies has been proposed to develop a broad-based set of concepts and strategies for transparency monitoring of nuclear materials at the back end of the fuel/weapons cycle. WIPP is the world's first complete geologic repository system for nuclear materials at the back end of the cycle. While it is understood that WIPP does not currently require this type of transparency, this repository has been proposed as realistic demonstration site to generate and test ideas, methods, and technologies about what transparency may entail at the back end of the nuclear materials cycle, and which could be applicable to other international repository developments. An integrated set of transparency demonstrations was developed and deployed during the summer, and fall of 1999 as a proof-of-concept of the repository transparency technology concept. These demonstrations also provided valuable experience and insight into the implementation of future transparency technology development and application. These demonstrations included: Container Monitoring Rocky Flats to WIPP; Underground Container Monitoring; Real-Time Radiation and Environmental Monitoring; Integrated level of confidence in the system and information provided. As the world's only operating deep geologic repository, the Waste Isolation Pilot Plant (WIPP) offers a unique opportunity to serve as an international cooperative test bed for developing and demonstrating technologies and processes in a fully operational repository system setting. To address the substantial national security implications for the US resulting from the lack of integrated, transparent management and disposition of nuclear materials at the back-end of the nuclear fuel and weapons cycles, it is proposed that WIPP be used as a test bed to develop and demonstrate technologies that will enable the transparent and proliferation-resistant geologic isolation of nuclear materials. The objectives of this initiative are to: (1) enhance public confidence in safe, secure geologic isolation of nuclear materials; (2) develop, test, and demonstrate transparency measures and technologies for the back-end of nuclear fuel cycle; and (3) foster international collaborations leading to workable, effective, globally-accepted standards for the transparent monitoring of geological repositories for nuclear materials. Test-bed activities include: development and testing of monitoring measures and technologies; international demonstration experiments; transparency workshops; visiting scientist exchanges; and educational outreach. These activities are proposed to be managed by the Department of Energy/Carlsbad Area Office (DOE/CAO) as part of The Center for Applied Repository and Underground Studies (CARUS).

BETSILL,J. DAVID; ELKINS,NED Z.; WU,CHUAN-FU; MEWHINNEY,JAMES D.; AAMODT,PAUL

2000-01-27T23:59:59.000Z

83

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

SciTech Connect (OSTI)

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

84

Sandia National Laboratories: Nuclear Energy Safety Technologies  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear Security Administration the1 -theErik Spoerke SSLSMolten-Salt StorageNo More Green WasteThe

85

Security Science & Technology | Nuclear Science | ORNL  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May JunDatastreamsmmcrcalgovInstrumentsrucLas ConchasPassiveSubmitted forHighlights Nuclear PhysicsDoDepartment ofSecretsCommodityNREL

86

Nuclear Reactor Technology Subcommittee of NEAC  

Office of Environmental Management (EM)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "of EnergyEnergyENERGY TAXBalanced ScorecardReactor Technology Subcommittee of NEAC Mujid Kazimi (Chair),

87

NASA/DOE/DOD nuclear propulsion technology planning: Summary of FY 1991 interagency panel results  

SciTech Connect (OSTI)

Interagency (NASA/DOE/DOD) technical panels worked in 1991 to evaluate critical nuclear propulsion issues, compare nuclear propulsion concepts for a manned Mars mission on a consistent basis, and to continue planning a technology development project for the Space Exploration Initiative (SEI). Panels were formed to address mission analysis, nuclear facilities, safety policy, nuclear fuels and materials, nuclear electric propulsion technology, and nuclear thermal propulsion technology. A summary of the results and recommendations of the panels is presented.

Clark, J.S.; Wickenheiser, T.J.; Doherty, M.P.; Marshall, A.; Bhattacharryya, S.K.; Warren, J.

1992-01-01T23:59:59.000Z

88

Proceedings of the Nuclear Criticality Technology and Safety Project Workshop  

SciTech Connect (OSTI)

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

89

E-Print Network 3.0 - annual nuclear technology Sample Search...  

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

Summary: of electricity from nuclear power plants is far less than any of the alternative energy technologies now contem... Nuclear Engineering Undergraduate Program...

90

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

SciTech Connect (OSTI)

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

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

2012-09-01T23:59:59.000Z

91

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

SciTech Connect (OSTI)

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

92

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

SciTech Connect (OSTI)

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

93

Important technology considerations for space nuclear power systems  

SciTech Connect (OSTI)

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

94

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

95

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

SciTech Connect (OSTI)

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

96

Technological Transfer from Research Nuclear Reactors to New Generation Nuclear Power Reactors  

SciTech Connect (OSTI)

The goal of this paper is the analysis of the technological transfer role in the nuclear field, with particular emphasis on nuclear reactors domain. The presentation is sustained by historical arguments. In this frame, it is very important to start with the achievements of the first nuclear systems, for instant those with natural uranium as fuel and heavy water as moderator, following in time through the history until the New Generation Nuclear Power Reactors.Starting with 1940, the accelerated development of the industry has implied the increase of the global demand for energy. In this respect, the nuclear energy could play an important role, being essentially an unlimited source of energy. However, the nuclear option faces the challenges of increasingly demanding safety requirements, economic competitiveness and public acceptance. Worldwide, a significant amount of experience has been accumulated during development, licensing, construction, and operation of nuclear power reactors. The experience gained is a strong basis for further improvements. Actually, the nuclear programs of many countries are addressing the development of advanced reactors, which are intended to have better economics, higher reliability, improved safety, and proliferation-resistant characteristics in order to overcome the current concerns about nuclear power. Advanced reactors, now under development, may help to meet the demand for energy power of both developed and developing countries as well as for district heating, desalination and for process heat.The paper gives historical examples that illustrate the steps pursued from first research nuclear reactors to present advanced power reactors. Emphasis was laid upon the fact that the progress is due to the great discoveries of the nuclear scientists using the technological transfer.

Radulescu, Laura ['Horia Hulubei' National Institute of Nuclear Physics and Engineering, PO BOX MG-6, Bucharest 077125 (Romania); Pavelescu, Margarit [Academy of Romanian Scientists, Bucharest (Romania)

2010-01-21T23:59:59.000Z

97

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

SciTech Connect (OSTI)

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

Harmon, J.E. [ed.

1992-06-01T23:59:59.000Z

98

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

SciTech Connect (OSTI)

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

Harmon, J.E. (ed.)

1992-06-01T23:59:59.000Z

99

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

SciTech Connect (OSTI)

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

100

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

SciTech Connect (OSTI)

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

Harmon, J.E. [ed.

1992-01-01T23:59:59.000Z

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

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

SciTech Connect (OSTI)

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

102

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

SciTech Connect (OSTI)

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

103

Refractory alloy technology for space nuclear power applications  

SciTech Connect (OSTI)

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

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

1984-01-01T23:59:59.000Z

104

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

105

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

Broader source: Energy.gov [DOE]

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

106

Innovative applications of technology for nuclear power plant productivity improvements  

SciTech Connect (OSTI)

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

107

2012 Nuclear Energy Enabling Technology Factsheet | Department of Energy  

Energy Savers [EERE]

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious RankCombustionImprovement Awardflash2007-42attachment1.pdfmodule(EE)2012 Nuclear Energy Enabling Technology

108

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

109

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

110

Proceedings of the Nuclear Criticality Technology Safety Workshop  

SciTech Connect (OSTI)

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

Rene G. Sanchez

1998-04-01T23:59:59.000Z

111

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

112

Overview of Fusion Nuclear Technology in the US  

SciTech Connect (OSTI)

Fusion Nuclear Technology (FNT) research in the United States encompasses many activities and requires expertise and capabilities in many different disciplines. The US Enabling Technology program is divided into several task areas, with aspects of fusion nuclear technology being addressed mainly in the Plasma Chamber, Neutronics, Safety, Materials, Tritium and Plasma Facing Component Programs. These various programs work together to address key FNT topics, including support for the ITER basic machine and the ITER Test Blanket Module, support for domestic plasma experiments, and development of DEMO relevant material and technological systems for blankets, shields, and plasma facing components. While it is difficult to describe all these activities in adequate detail, this paper gives an overview of critical FNT activities. With the recent return of the US to the ITER collaboration, several activities in support of the ITER machine have been initiated, including development of the first wall shielding blanket baffle module (module 18), testing of plasma facing components, ITER tokamak exhaust tritium processing system development, and 3-D neutronics and activation code advances. The ITER test blanket module development activity has also been restarted in the US, and critical R&D is proceeding on ceramic breeder thermomechanical systems and lead-lithium breeder systems utilizing SiC composite flow channel inserts for thermal and MHD electrical insulation. Novel research on free surface liquid metal divertors is also continuing, with the goal of fielding a lithium free surface divertor in the National Spherical Torus eXperimental device (NSTX) and aiding the development of the Lithium Tokamak Experiment at Princeton. Materials research in the long term is focused on coupled computational materials science and carefully designed experiments to determine the underlying mechanisms that control the mechanical and physical behavior of advanced body-centered cubic metals and ceramic composites in the harsh fusion environment. In addition, two inertial fusion energy (IFE) research programs conducting FNT-related research for IFE are also described.

Morley, Neil B.; Abdou, Mohamed A.; Anderson, Mark; Calderoni, P.; Kurtz, Richard J.; Nygren, R N.; Raffray, R; Sawan, M.; Sharpe, Peter J.; Smolentsev, S.; Willms, Scott; Ying, A Y.

2006-02-01T23:59:59.000Z

113

Ceramic HEPA Filter Program  

SciTech Connect (OSTI)

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

114

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

SciTech Connect (OSTI)

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

115

Technology Insights and Perspectives for Nuclear Fuel Cycle Concepts  

SciTech Connect (OSTI)

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

116

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

117

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

118

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

E-Print Network [OSTI]

technology that is clean, cost-effective, long-term sustainable, and safe. Currently undeveloped technologiesHow to Proceed with the Thorium Nuclear Technology: a Real Options Analysis Afzal Siddiqui Stein: +44 207 3834703 Department of Industrial Economics and Technology Management, Norwegian University

Guillas, Serge

119

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

120

Design Features and Technology Uncertainties for the Next Generation Nuclear Plant  

SciTech Connect (OSTI)

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

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

2004-06-01T23:59:59.000Z

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

Leasing of Nuclear Power Plants With Using Floating Technologies  

SciTech Connect (OSTI)

The proposal to organize and realize the international program on leasing of Nuclear Power Plant (NPP) reactor compartments is brought to the notice of potential partners. The proposal is oriented to the construction of new NPPs or to replacement of worked-out reactor units of the NPPs in operation on the sites situated near water area and to the use of afloat technologies for construction, mounting and transportation of reactor units as a Reactor Compartment Block Module (RCBM). According to the offered project the RCBM is fabricated in factory conditions at the largest Russian defense shipbuilding plant - State Unitary Enterprise 'Industrial Association SEVMASHPREDPRIYATIE' (SEVMASH) in the city of Severodvinsk of the Arkhangelsk region. After completion of assembling, testing and preliminary licensing the RCBM is given buoyancy by means of hermetic sealing and using pontoons and barges. The RCBM delivery to the NPP site situated near water area is performed by sea route. The RCBM is brought to the place of its installation with the use of appropriate hydraulic structures (canals, shipping locks), then is lowered on the basement constructed beforehand and incorporated into NPP scheme, of which the components are installed in advance. Floating means can be detached from the RCBM and used repeatedly for other RCBMs. Further procedure of NPP commissioning and its operation is carried out according to traditional method by power company in the framework of RCBM leasing with enlisting the services of firm-manufacturer's specialists either to provide reactor plant operation and concomitant processes or to perform author's supervision of operation. After completion of lifetime and reactor unloading the RCBM is dismantled with using the same afloat technology and taken away from NPP site to sea area entirely, together with its structures (reactor vessel, heat exchangers, pumps, pipelines and other equipment). Then RCBM is transported by shipping route to a firm-manufacturer, for subsequent reprocessing, utilization and storage. Nuclear fuel and radioactive wastes are removed from NPP site also. Use of leasing method removes legal problems connected with the transportation of radioactive materials through state borders as the RCBM remains a property of the state-producer at all stages of its life cycle. (authors)

Kuznetsov, Yu.N.; Gabaraev, B.A.; Reshetov, V.A.; Moskin, V.A. [Federal State Unitary Enterprise, N.A. Dollezhal' Scientific-Research and Design Institute of Power Engineering (Russian Federation)

2002-07-01T23:59:59.000Z

122

Design of high order switched resistor momolithic filters using NMOS technology  

E-Print Network [OSTI]

-aliasing filter is used to band-limit the input signal. 3 Switched Capacitor representation of a resistor, a) Switched Capacitor, b) Fixed Resistor. . . . . . . . . . Basic Switched Resistor Block. a) Switched Resistor, b) Fixed Resistor. 5 Switched.... VBS for depletion and enhancement transistors. 18 9 IO vs YDS curves for depletion (a, c), and enhancement (b, d) transistors (YBS= 0 V). a) II/L= 1, b) M/L= 1, c) Vi/L= . 5, d) V(/L= 5 19 10 DC resistance for an NMOS transistor vs. VGS (W/L= . 3...

Aguilar, Raul Antonio

1983-01-01T23:59:59.000Z

123

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

E-Print Network [OSTI]

information from experi- mental cross-section data, integral data (critical assemblies), and nuclear models#12;2 Science and Technology of Nuclear Installations the nuclear data are added in a speci c format to so-called evaluated nuclear data les, such as ENDF-6 (Evaluated Nuclear Data File-6). e

Demazi猫re, Christophe

124

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

125

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

SciTech Connect (OSTI)

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

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

1994-04-01T23:59:59.000Z

126

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.;...

127

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)...

128

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

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

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

129

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

SciTech Connect (OSTI)

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

Per F. Peterson

2010-03-01T23:59:59.000Z

130

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

SciTech Connect (OSTI)

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

John Collins

2009-01-01T23:59:59.000Z

131

5th International Symposium on Fusion Nuclear Technology Rome, September 19 -24 1999  

E-Print Network [OSTI]

5th International Symposium on Fusion Nuclear Technology Rome, September 19 - 24 1999 In as the working gas (and later with a mixture of 10 % oxygen in helium), purging the vacuum vessel with dry

132

Calcined Waste Storage at the Idaho Nuclear Technology and Engineering Center  

SciTech Connect (OSTI)

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

133

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

SciTech Connect (OSTI)

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

134

NEXT GENERATION NUCLEAR PLANT NGNP Technology Development Roadmapping  

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

ISR Inner Side Reflector Kc Fracture Toughness kg Kilogram K-T Kepner-Tregoe KTA German nuclear technical committee kW Kilowatt LANL Los Alamos National Laboratory LBE Licensing...

135

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

E-Print Network [OSTI]

) project. The general scope of the work was to determine possible applications of smart materials DoE facilities. The project started with the selection of types of smart materials and technologies1 The Use of Smart Materials Technologies in Radiation Environment and Nuclear Industry Victor

Giurgiutiu, Victor

136

Overview of Fusion Nuclear Technology in the US  

E-Print Network [OSTI]

/ Shield Module 18 颅 Tokamak Exhaust Plant IFE Technology Research 颅 High Average Power Laser 颅 Z Studies 颅 Neutronics Simulation Tools ITER Project Office and US Contributions to ITER 颅 First wall) Department of Energy (DOE) Enabling Technologies Program ITER Project Office (US-IPO) High Average Power

137

Isotope Development & Production | Nuclear Science | ORNL  

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

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

138

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

E-Print Network [OSTI]

259NUCLEAR ENGINEERING AND TECHNOLOGY, VOL.38 NO.3 APRIL 2006 NuSEE: AN INTEGRATED ENVIRONMENT and Technology 1 Department of Nuclear and Quantum Engineering 2 Department of Electrical Engineering & Computer. In safety-critical systems such as a Nuclear Power Plant (NPP), extremely high- confidence for software

139

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

E-Print Network [OSTI]

Search 11.11.2004 08:48:00 GMT China aims to employ nuclear fusion technology in power generation to employ nuclear fusion technologies in power generation by 2050. China will adopt a three-step strategy with thermonuclear reactors; the second step aims to raise the utilization rate of nuclear fuels from the current 1

140

Nuclear Materials Research and Technology/Los Alamos National Laboratory  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear Security Administration the ContributionsArms Control R&D Consortium includesEnergy Nuclear011 DRAFT

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

Nuclear Materials Research and Technology/Los Alamos National Laboratory  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear Security Administration the ContributionsArms Control R&D Consortium includesEnergy Nuclear011

142

Nuclear Materials Research and Technology/Los Alamos National Laboratory  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear Security Administration the ContributionsArms Control R&D Consortium includesEnergy Nuclear011Researchers

143

Fusion Nuclear Science and Technology (FNST) Mohamed Abdou  

E-Print Network [OSTI]

Material degradation by radiation and other damage Fabrication and joining for reliable components at IFE pulse repetition rate 路 Incremental effects of repetitive pulses (e.g., radiation damage Components divertor, limiter and nuclear aspects of plasma heating/fueling and IFE final optics Blanket

144

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

E-Print Network [OSTI]

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

Motta, Arthur T.

145

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

146

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

SciTech Connect (OSTI)

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

147

ULTRA-COMPACT ACCELERATOR TECHNOLOGIES FOR APPLICATION IN NUCLEAR TECHNIQUES  

SciTech Connect (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 {approx}10 MV/m gradients for 10s of nanoseconds pulses and to {approx}100 MV/m gradients for {approx}1 ns systems. As a post verifier for supplementing existing x-ray equipment, this system can remain in a charged, stand-by state with little or no energy consumption. We detail the progress of our overall component development effort with the multilayer dielectric wall insulators (i.e., the accelerator wall), compact power supply technology, kHz repetition-rate surface flashover ion sources, and the prompt pulse generation system consisting of wide-bandgap switches and high performance dielectric materials.

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

2009-06-11T23:59:59.000Z

148

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]

of overheating of the nuclear reactor core during a severe accident, large amount of hydrogen are generatedNuclear 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

Vuik, Kees

149

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

150

Idaho Nuclear Technology and Engineering Center Low-Activity Waste Process Technology Program FY-98 Status Report  

SciTech Connect (OSTI)

The Low-Activity Waste Process Technology Program at the Idaho Nuclear Technology and Engineering Center (INTEC) anticipates that large volumes of low-level/low-activity wastes will need to be grouted prior to near-surface disposal. During fiscal year 1998, three grout formulations were studied for low-activity wastes derived from INTEC liquid sodium-bearing waste. Compressive strength and leach results are presented for phosphate bonding cement, acidic grout, and alkaline grout formulations. In an additional study, grout formulations are recommended for stabilization of the INTEC underground storage tank residual heels.

Herbst, Alan Keith; Mc Cray, John Alan; Rogers, Adam Zachary; Simmons, R. F.; Palethorpe, S. J.

1999-03-01T23:59:59.000Z

151

Idaho Nuclear Technology and Engineering Center Low-Activity Waste Process Technology Program, FY-98 Status Report  

SciTech Connect (OSTI)

The Low-Activity Waste Process Technology Program at the Idaho Nuclear Technology and Engineering Center (INTEC) anticipates that large volumes of low-level/low-activity wastes will need to be grouted prior to near-surface disposal. During fiscal year 1998, three grout formulations were studied for low-activity wastes derived from INTEC liquid sodium-bearing waste. Compressive strength and leach results are presented for phosphate bonding cement, acidic grout, and alkaline grout formulations. In an additional study, grout formulations are recommended for stabilization of the INTEC underground storage tank residual heels.

Herbst, A.K.; Rogers, A.Z.; McCray, J.A.; Simmons, R.F.; Palethorpe, S.J.

1999-03-01T23:59:59.000Z

152

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

SciTech Connect (OSTI)

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

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

2000-11-01T23:59:59.000Z

153

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

SciTech Connect (OSTI)

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

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

2000-10-31T23:59:59.000Z

154

Idaho Nuclear Technology and Engineering Center Low-Activity Waste Process Technology Program FY-99 Status Report  

SciTech Connect (OSTI)

The Low-Activity Waste Process Technology Program at the Idaho Nuclear Technology and Engineering Center (INTEC) anticipates that large volumes of low-level/low-activity wastes will need to be grouted prior to near-surface disposal. During fiscal year 1999, grout formulations were studied for transuranic waste derived from INTEC liquid sodium-bearing waste and for projected newly generated low-level liquid waste. Additional studies were completed on radionuclide leaching, microbial degradation, waste neutralization, and a small mockup for grouting the INTEC underground storage tank residual heels.

A. K. Herbst; J. A. McCray; R. J. Kirkham; J. Pao; S. H. Hinckley

1999-09-30T23:59:59.000Z

155

Idaho Nuclear Technology and Engineering Center Low-Activity Waste Process Technology Program FY-99 Status Report  

SciTech Connect (OSTI)

The Low-Activity Waste Process Technology Program at the Idaho Nuclear Technology and Engineering Center (INTEC) anticipates that large volumes of low-level/low-activity wastes will need to be grouted prior to near-surface disposal. During fiscal year 1999, grout formulations were studied for transuranic waste derived from INTEC liquid sodium-bearing waste and for projected newly generated low-level liquid waste. Additional studies were completed on radionuclide leaching, microbial degradation, waste neutralization, and a small mockup for grouting the INTEC underground storage tank residual heels.

Herbst, Alan Keith; Mc Cray, John Alan; Kirkham, Robert John; Pao, Jenn Hai; Hinckley, Steve Harold

1999-10-01T23:59:59.000Z

156

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

SciTech Connect (OSTI)

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

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

2012-07-17T23:59:59.000Z

157

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

SciTech Connect (OSTI)

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

Heather D. Medema; Ronald K. Farris

2012-09-01T23:59:59.000Z

158

Preventing Proliferation of Nuclear Materials and Technology | National  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May JunDatastreamsmmcrcalgovInstrumentsrucLas ConchasPassive Solar Home DesignPresentations Presentations Sort by:atNEWS0,0,Nuclear

159

Nuclear Materials Technology Division/Los Alamos National Laboratory  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear Security Administration the ContributionsArms Control R&D Consortium includesEnergyWinter 1994 Los Alamos

160

Nuclear Materials Technology Division/Los Alamos National Laboratory  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear Security Administration the ContributionsArms Control R&D Consortium includesEnergyWinter 1994 Los

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

Nuclear Materials Technology Division/Los Alamos National Laboratory  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear Security Administration the ContributionsArms Control R&D Consortium includesEnergyWinter 1994 LosSummer

162

Nuclear Materials Technology Division/Los Alamos National Laboratory  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear Security Administration the ContributionsArms Control R&D Consortium includesEnergyWinter 1994

163

Nuclear Materials Technology Division/Los Alamos National Laboratory  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear Security Administration the ContributionsArms Control R&D Consortium includesEnergyWinter 1994Spring 1996

164

Nuclear Materials Technology Division/Los Alamos National Laboratory  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear Security Administration the ContributionsArms Control R&D Consortium includesEnergyWinter 1994Spring

165

Nuclear Materials Technology Division/Los Alamos National Laboratory  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear Security Administration the ContributionsArms Control R&D Consortium includesEnergyWinter 1994Spring6 Los

166

Nuclear Materials Technology Division/Los Alamos National Laboratory  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear Security Administration the ContributionsArms Control R&D Consortium includesEnergyWinter 1994Spring6

167

Nuclear Materials Technology Division/Los Alamos National Laboratory  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear Security Administration the ContributionsArms Control R&D Consortium includesEnergyWinter

168

Nuclear Materials Technology/Los Alamos National Laboratory  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear Security Administration the ContributionsArms Control R&D Consortium includesEnergyWinterLos Alamos

169

Nuclear Materials Technology/Los Alamos National Laboratory  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear Security Administration the ContributionsArms Control R&D Consortium includesEnergyWinterLos

170

SRNS signs on as industry partner for Nuclear Engineering Technology  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear Security Administration the1 -the Mid-Infrared0 ResourceAwards SAGE Awards ,#2446SmallnAboutEducation | National

171

Nuclear Separations Technologies Workshop Report | Department of Energy  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious Rank EERE:Year in3.pdfEnergyDepartment of Energy Advanced1, 2014NuclearCommission,Science

172

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

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear Security Administration the1 - September 2006 TheSteven Ashby Dr. Steven Ashbystation |

173

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

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmospheric Optical Depth7-1D: Vegetation ProposedUsing ZirconiaPolicy andExsolutionFES6 PerformanceBudget 禄 FY 2009NuclearFiscal

174

Los Alamos Lab: International and Applied Technology Division, IAT: Nuclear  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmospheric Optical Depth7-1D: VegetationEquipment Surfaces and Interfaces Sample6,LocalNuclear SecurityOffice >Counterterrorism

175

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

SciTech Connect (OSTI)

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

176

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.

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

2014-01-01T23:59:59.000Z

177

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

178

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

SciTech Connect (OSTI)

OAK-B135 This report presents a summation of the third and final year of a three-year investigation into methods and technologies for substantially reducing the capital costs and total schedule for future nuclear plants. In addition, this is the final technical report for the three-year period of studies.

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

2002-11-30T23:59:59.000Z

179

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

SciTech Connect (OSTI)

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

Garaizar, X

2010-01-06T23:59:59.000Z

180

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

SciTech Connect (OSTI)

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

Farfan, E.; Foley, T.

2010-02-11T23:59:59.000Z

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.


181

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

SciTech Connect (OSTI)

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

182

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 materials and technology, with the potential for providing energy security for many centuries. This paper

183

High Temperature Electrolysis for Hydrogen Production from Nuclear Energy TechnologySummary  

SciTech Connect (OSTI)

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

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

2010-02-01T23:59:59.000Z

184

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

185

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

E-Print Network [OSTI]

109 7 Nuclear Power and Its Fuel Cycle No technological system more dramatically illustrates of ignoring the social, political, and environmental dimensions of innovation - than nuclear power. Once widely seen as an energy source of almost unlimited potential, nuclear power is today expanding in just

Kammen, Daniel M.

186

Nuclear Data for Fusion Energy Technologies: Requests, Status and Development Needs  

SciTech Connect (OSTI)

The current status of nuclear data evaluations for fusion technologies is reviewed. Well-qualified data are available for neutronics and activation calculations of fusion power reactors and the next-step device ITER, the International Thermonuclear Experimental Reactor. Major challenges for the further development of fusion nuclear data arise from the needs of the long-term fusion programme. In particular, co-variance data are required for uncertainty assessments of nuclear responses. Further, the nuclear data libraries need to be extended to higher energies above 20 MeV to enable neutronics and activation calculations of IFMIF, the International Fusion Material Irradiation Facility. A significant experimental effort is required in this field to provide a reliable and sound database for the evaluation of cross-section data in the higher energy range.

Fischer, U. [Association FZK-Euratom, Forschungszentrum Karlsruhe, Institut fuer Reaktorsicherheit, Postfach 3640, D-76021 Karlsruhe (Germany); Batistoni, P. [Associazione Euratom-ENEA sulla Fusione, ENEA Fusion Divison, Via E. Fermi 27, I-00044 Frascati (Italy); Cheng, E. [TSI Research, Inc., P.O. Box 2754, Rancho Santa Fe, CA 92067 (United States); Forrest, R.A. [Euratom/UKAEA Fusion Association, Culham Science Centre, Abingdon, Oxfordshire OX14 3DB (United Kingdom); Nishitani, T. [Fusion Neutronics Laboratory, JAERI, Tokai-mura, Naka-gun, Ibaraki-ken 319-1195 (Japan)

2005-05-24T23:59:59.000Z

187

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

Broader source: Energy.gov [DOE]

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

188

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

189

Technology status in support of refined technical baseline for the Spent Nuclear Fuel project. Revision 1  

SciTech Connect (OSTI)

The Spent Nuclear Fuel Project (SNFP) has undertaken technology acquisition activities focused on supporting the technical basis for the removal of the N Reactor fuel from the K Basins to an interim storage facility. The purpose of these technology acquisition activities has been to identify technology issues impacting design or safety approval, to establish the strategy for obtaining the necessary information through either existing project activities, or the assignment of new work. A set of specific path options has been identified for each major action proposed for placing the N Reactor fuel into a ``stabilized`` form for interim storage as part of this refined technical basis. This report summarizes the status of technology information acquisition as it relates to key decisions impacting the selection of specific path options. The following specific categories were chosen to characterize and partition the technology information status: hydride issues and ignition, corrosion, hydrogen generation, drying and conditioning, thermal performance, criticality and materials accountability, canister/fuel particulate behavior, and MCO integrity. This report represents a preliminary assessment of the technology information supporting the SNFP. As our understanding of the N Reactor fuel performance develops the technology information supporting the SNFP will be updated and documented in later revisions to this report. Revision 1 represents the incorporation of peer review comments into the original document. The substantive evolution in our understanding of the technical status for the SNFP (except section 3) since July 1995 have not been incorporated into this revision.

Puigh, R.J.; Toffer, H.; Heard, F.J.; Irvin, J.J.; Cooper, T.D.

1995-10-20T23:59:59.000Z

190

Argonne National Laboratory contributions to the International Symposium on Fusion Nuclear Technology (ISFNT)  

SciTech Connect (OSTI)

A total of sixteen papers with authors from Argonne National Laboratory were presented at the First International Symposium on Fusion Nuclear Technology (ISFNT), held in Tokyo, Japan, in April 1988. The papers cover the results of recent investigations in blanket design and analysis, fusion neutronics, materials experiments in liquid metal corrosion and solid breeders, tritium recovery analysis, experiments and analysis for liquid metal MHD, reactor safety and economic analysis, and transient electromagnetic analysis.

Not Available

1988-10-01T23:59:59.000Z

191

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

SciTech Connect (OSTI)

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

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

2010-11-01T23:59:59.000Z

192

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

SciTech Connect (OSTI)

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

193

METAL MEDIA FILTERS, AG-1 SECTION FI  

SciTech Connect (OSTI)

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

194

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

SciTech Connect (OSTI)

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

195

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

SciTech Connect (OSTI)

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

196

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

SciTech Connect (OSTI)

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

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

2006-09-19T23:59:59.000Z

197

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

SciTech Connect (OSTI)

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

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

2007-09-25T23:59:59.000Z

198

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

SciTech Connect (OSTI)

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

199

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

SciTech Connect (OSTI)

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

200

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

E-Print Network [OSTI]

Abstract. The problem of controlled nuclear fusion (CNF) is a colossal scientific and technological the feasibility of building a magnetic thermonuclear reactor''. The three papers below briefly outline the history044n08ABEH001068 The initial period in the history of nuclear fusion research at the Kurchatov

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

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

SciTech Connect (OSTI)

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

202

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

Broader source: Energy.gov [DOE]

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

203

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

SciTech Connect (OSTI)

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

204

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

SciTech Connect (OSTI)

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

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

2005-09-20T23:59:59.000Z

205

OPTIMIZATION OF ADVANCED FILTER SYSTEMS  

SciTech Connect (OSTI)

Two advanced, hot gas, barrier filter system concepts have been proposed by the Siemens Westinghouse Power Corporation to improve the reliability and availability of barrier filter systems in applications such as PFBC and IGCC power generation. The two hot gas, barrier filter system concepts, the inverted candle filter system and the sheet filter system, were the focus of bench-scale testing, data evaluations, and commercial cost evaluations to assess their feasibility as viable barrier filter systems. The program results show that the inverted candle filter system has high potential to be a highly reliable, commercially successful, hot gas, barrier filter system. Some types of thin-walled, standard candle filter elements can be used directly as inverted candle filter elements, and the development of a new type of filter element is not a requirement of this technology. Six types of inverted candle filter elements were procured and assessed in the program in cold flow and high-temperature test campaigns. The thin-walled McDermott 610 CFCC inverted candle filter elements, and the thin-walled Pall iron aluminide inverted candle filter elements are the best candidates for demonstration of the technology. Although the capital cost of the inverted candle filter system is estimated to range from about 0 to 15% greater than the capital cost of the standard candle filter system, the operating cost and life-cycle cost of the inverted candle filter system is expected to be superior to that of the standard candle filter system. Improved hot gas, barrier filter system availability will result in improved overall power plant economics. The inverted candle filter system is recommended for continued development through larger-scale testing in a coal-fueled test facility, and inverted candle containment equipment has been fabricated and shipped to a gasifier development site for potential future testing. Two types of sheet filter elements were procured and assessed in the program through cold flow and high-temperature testing. The Blasch, mullite-bonded alumina sheet filter element is the only candidate currently approaching qualification for demonstration, although this oxide-based, monolithic sheet filter element may be restricted to operating temperatures of 538 C (1000 F) or less. Many other types of ceramic and intermetallic sheet filter elements could be fabricated. The estimated capital cost of the sheet filter system is comparable to the capital cost of the standard candle filter system, although this cost estimate is very uncertain because the commercial price of sheet filter element manufacturing has not been established. The development of the sheet filter system could result in a higher reliability and availability than the standard candle filter system, but not as high as that of the inverted candle filter system. The sheet filter system has not reached the same level of development as the inverted candle filter system, and it will require more design development, filter element fabrication development, small-scale testing and evaluation before larger-scale testing could be recommended.

R.A. Newby; M.A. Alvin; G.J. Bruck; T.E. Lippert; E.E. Smeltzer; M.E. Stampahar

2002-06-30T23:59:59.000Z

206

(International symposium on fusion nuclear technology, Tokyo, Japan, April 10, 1988): Foreign trip report  

SciTech Connect (OSTI)

A presentation entitled ''Experimental and Analytical Investigations of Mass Transfer Processes of /sup 12/Cr-1MoVW Steel in Thermally-Convected Lithium Systems'' was made by G.E. Bell (coauthors M.A. Abdou (UCLA) and P.F. Tortorelli (ORNL)) at a poster session of the International Symposium on Fusion Nuclear Technology (ISFNT). The results presented were taken from work performed while Mr. Bell was an Oak Ridge Associated Universities Fellow at ORNL from October 1986 to March 1988. A consistent theme throughout the conference was the need for collaboration within and among national efforts to achieve the goal of an engineering test reactor.

Bell, G.E.

1988-05-24T23:59:59.000Z

207

Requirements and Design Envelope for Volumetric Neutron Source Fusion Facilities for Fusion Nuclear Technology Development  

SciTech Connect (OSTI)

The paper shows that timely development of fusion nuclear technology (FNT) components, e.g. blanket, for DEMO requires the construction and operation of a fusion facility parallel to ITER. This facility, called VNS, will be dedicated to testing, developing and qualifying FNT components and material combinations. Without VNS, i.e. with ITER alone, the confidence level in achieving DEMO operating goals has been quantified and is unacceptably low (< 1 %). An attractive design envelope for VNS exists. Tokamak VNS designs with driven plasma (Q ~ 1-3), steady state plasma operation and normal copper toroidal field coils lead to small sized devices with moderate cost.

Abdou, M [University of California, Los Angeles] [University of California, Los Angeles; Peng, Yueng Kay Martin [ORNL] [ORNL

1995-01-01T23:59:59.000Z

208

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

209

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

SciTech Connect (OSTI)

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

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

2009-04-01T23:59:59.000Z

210

Development of Fusion Nuclear Technologies at Japan Atomic Energy Research Institute  

SciTech Connect (OSTI)

An overview of the present status of development of fusion nuclear technologies at Japan Atomic Energy Research Institute is presented. A tritium handling system for the ITER was designed, and the technology for each component of this system was demonstrated successfully. An ultraviolet laser with a wavelength of 193 nm was found quite effective for removing tritium from in-vessel components of D-T fusion reactors. Blanket technologies have been developed for the test blanket module of the ITER and for advanced blankets for DEMO reactors. This blanket is composed of ceramic Li{sub 2}TiO{sub 3} breeder pebbles and neutron multiplier beryllium pebbles, whose diameter ranges from 0.2 to 2 mm, contained in a box structure made of a reduced-activation ferritic steel, F82H. Mechanical properties of F82H under a thermal neutron irradiation at up to 50 displacements per atom (dpa) were obtained in a temperature range from 200 to 500 deg. C. Design of the International Fusion Materials Irradiation Facility (IFMIF) has been developed to obtain engineering data for candidate materials for DEMO reactors under a simulated fusion neutron irradiation up to 100 to 200 dpa, and basic development of the key technologies to construct the IFMIF is now under way as an International Energy Agency international collaboration.

Seki, Masahiro; Yamanishi, Toshihiko; Shu, Wataru; Nishi, Masataka; Hatano, Toshihisa; Akiba, Masato; Takeuchi, Hiroshi; Nakamura, Kazuyuki; Sugimoto, Masayoshi; Shiba, Kiyoyuki; Jitsukawa, Shiro; Ishitsuka, Etsuo; Tsuji, Hiroshi [Japan Atomic Energy Research Institute (Japan)

2002-07-15T23:59:59.000Z

211

Filtering apparatus  

DOE Patents [OSTI]

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

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

1992-09-01T23:59:59.000Z

212

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

213

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

SciTech Connect (OSTI)

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

214

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

SciTech Connect (OSTI)

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

215

Calcine Waste Storage at the Idaho Nuclear Technology and Engineering Center  

SciTech Connect (OSTI)

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

216

Idaho Nuclear Technology and Engineering Center (INTEC) Sodium Bearing Waste - Waste Incidental to Reprocessing Determination  

SciTech Connect (OSTI)

U.S. Department of Energy Manual 435.1-1, Radioactive Waste Management, Section I.1.C, requires that all radioactive waste subject to Department of Energy Order 435.1 be managed as high-level radioactive waste, transuranic waste, or low-level radioactive waste. Determining the radiological classification of the sodium-bearing waste currently in the Idaho Nuclear Technology and Engineering Center Tank Farm Facility inventory is important to its proper treatment and disposition. This report presents the technical basis for making the determination that the sodium-bearing waste is waste incidental to spent fuel reprocessing and should be managed as mixed transuranic waste. This report focuses on the radiological characteristics of the sodiumbearing waste. The report does not address characterization of the nonradiological, hazardous constituents of the waste in accordance with Resource Conservation and Recovery Act requirements.

Jacobson, Victor Levon

2002-08-01T23:59:59.000Z

217

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

SciTech Connect (OSTI)

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

Ian McKirdy

2011-07-01T23:59:59.000Z

218

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

SciTech Connect (OSTI)

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

219

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

SciTech Connect (OSTI)

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

220

active filter employing: Topics by E-print Network  

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

type). Traditional design Wilamowski, Bogdan Maciej 25 Virtual active filters for HVDC networks using V2G technology F.R. Islam Engineering Websites Summary: ) technology is...

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

167Int. J. Nuclear Energy Science and Technology, Vol. 2, No. 3, 2006 Analysis methods for the determination of possible  

E-Print Network [OSTI]

167Int. J. Nuclear Energy Science and Technology, Vol. 2, No. 3, 2006 Analysis methods-dependence due to the localised character of the perturbation. Several techniques relying on the analysis. Keywords: neutron noise analysis; Boiling Water Reactor (BWR); stability; Decay Ratio (DR); space

Demazi猫re, Christophe

222

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

E-Print Network [OSTI]

, use of electric primary propulsion in flight systems has been limited to low-power, solar electric thruster output power are identified. Design evolutions are presented for three thrusters that would1 Technology Survey and Performance Scaling for the Design of High Power Nuclear Electric Power

223

Operational safety enhancement of Soviet-designed nuclear reactors via development of nuclear power plant simulators and transfer of related technology  

SciTech Connect (OSTI)

The US Department of Energy (DOE), under the US government`s International Nuclear Safety Program (INSP), is implementing a program of developing and providing simulators for many of the Russian and Ukrainian Nuclear Power Plants (NPPs). Pacific Northwest National Laboratory (PNNL) and Brookhaven National Laboratory (BNL) manage and provide technical oversight of the various INSP simulator projects for DOE. The program also includes a simulator technology transfer process to simulator design organizations in Russia and Ukraine. Training programs, installation of new simulators, and enhancements in existing simulators are viewed as providing a relatively fast and cost-effective technology transfer that will result in measurable improvement in the safety culture and operation of NPPs. A review of this program, its present status, and its accomplishments are provided in this paper.

Kohut, P.; Epel, L.G.; Tutu, N.K. [and others

1998-08-01T23:59:59.000Z

224

Joanna McFarlane, Refuyat Ashen, and K.C. Cushman Separations and Materials Research Group, Nuclear Science and Technology Division  

E-Print Network [OSTI]

, Nuclear Science and Technology Division Oak Ridge National Laboratory, P. O. Box 2008, MS-6008, Oak Ridge, Nuclear Science and Technology Division Oak Ridge National Laboratory, P. O. Box 2008, MS-6008, Oak Ridge. Fuel mixtures that were considered included: biodiesel and standard diesel fuel, methyl-butanoate and n

Pennycook, Steve

225

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

Broader source: Energy.gov [DOE]

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

226

Filter apparatus  

DOE Patents [OSTI]

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

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

1984-01-01T23:59:59.000Z

227

Calcined Waste Storage at the Idaho Nuclear Technology and Engineering Center  

SciTech Connect (OSTI)

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

Staiger, M. Daniel, Swenson, Michael C.

2011-09-01T23:59:59.000Z

228

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

Broader source: Energy.gov [DOE]

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

229

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

Broader source: Energy.gov [DOE]

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

230

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 (OSTI)

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

231

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

SciTech Connect (OSTI)

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

232

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

SciTech Connect (OSTI)

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

233

Global Nuclear Security  

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

Global Nuclear Security Both DOE and the National Nuclear Security Administration are working to reduce the risk of nuclear proliferation and provide technologies to improve...

234

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

E-Print Network [OSTI]

American Nuclear Society 2013 Student Conference 颅 Massachusetts Institute of Technology Boston, Massachusetts, USA, April 4-6, 2013, on CD-ROM, American Nuclear Society, LaGrange Park, IL (2013) A DETECTOR. Troy, NY 12180 mcderb@rpi.edu 1. INTRODUCTION Reactor design and criticality safety calculations

Danon, Yaron

235

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

E-Print Network [OSTI]

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

Grigoriadis, Theocharis N

2009-01-01T23:59:59.000Z

236

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

E-Print Network [OSTI]

Essentials, March 2007. OECD/Nuclear Energy Agency. "Nuclear Energy and the Kyoto Protocol"OECD/IEA Report OECD/Nuclear Energy Agency. "Nuclear Energy

Grigoriadis, Theocharis N

2009-01-01T23:59:59.000Z

237

ADVANCED HOT GAS FILTER DEVELOPMENT  

SciTech Connect (OSTI)

DuPont Lanxide Composites, Inc. undertook a sixty-month program, under DOE Contract DEAC21-94MC31214, in order to develop hot gas candle filters from a patented material technology know as PRD-66. The goal of this program was to extend the development of this material as a filter element and fully assess the capability of this technology to meet the needs of Pressurized Fluidized Bed Combustion (PFBC) and Integrated Gasification Combined Cycle (IGCC) power generation systems at commercial scale. The principal objective of Task 3 was to build on the initial PRD-66 filter development, optimize its structure, and evaluate basic material properties relevant to the hot gas filter application. Initially, this consisted of an evaluation of an advanced filament-wound core structure that had been designed to produce an effective bulk filter underneath the barrier filter formed by the outer membrane. The basic material properties to be evaluated (as established by the DOE/METC materials working group) would include mechanical, thermal, and fracture toughness parameters for both new and used material, for the purpose of building a material database consistent with what is being done for the alternative candle filter systems. Task 3 was later expanded to include analysis of PRD-66 candle filters, which had been exposed to actual PFBC conditions, development of an improved membrane, and installation of equipment necessary for the processing of a modified composition. Task 4 would address essential technical issues involving the scale-up of PRD-66 candle filter manufacturing from prototype production to commercial scale manufacturing. The focus would be on capacity (as it affects the ability to deliver commercial order quantities), process specification (as it affects yields, quality, and costs), and manufacturing systems (e.g. QA/QC, materials handling, parts flow, and cost data acquisition). Any filters fabricated during this task would be used for product qualification tests being conducted by Westinghouse at Foster-Wheeler's Pressurized Circulating Fluidized Bed (PCFBC) test facility in Karhula, Finland. Task 5 was designed to demonstrate the improvements implemented in Task 4 by fabricating fifty 1.5-meter hot gas filters. These filters were to be made available for DOE-sponsored field trials at the Power Systems Development Facility (PSDF), operated by Southern Company Services in Wilsonville, Alabama.

E.S. Connolly; G.D. Forsythe

2000-09-30T23:59:59.000Z

238

A Technology Roadmap for Generation IV Nuclear Energy Systems Executive Summary  

SciTech Connect (OSTI)

To meet future energy needs, ten countries--Argentina, Brazil, Canada, France, Japan, the Republic of Korea, the Republic of South Africa, Switzerland, the United Kingdom, and the United States--have agreed on a framework for international cooperation in research for an advanced generation of nuclear energy systems, known as Generation IV. These ten countries have joined together to form the Generation IV International Forum (GIF) to develop future-generation nuclear energy systems that can be licensed, constructed, and operated in a manner that will provide competitively priced and reliable energy products while satisfactorily addressing nuclear safety, waste, proliferation, and public perception concerns. The objective for Generation IV nuclear energy systems is to be available for international deployment before the year 2030, when many of the world's currently operating nuclear power plants will be at or near the end of their operating licenses.

None

2003-03-01T23:59:59.000Z

239

Journal of NUCLEAR SCIENCE and TECHNOLOGY, 21[1] pp.1~9 (January 1984). 1 Present Status of Study on Extraction  

E-Print Network [OSTI]

of the development of nuclear power generation has not been changed because of maldistribution of the fossil energy resources, their ultimate shortage and the harmful effect of their burnings upon the environment. AccordingJournal of NUCLEAR SCIENCE and TECHNOLOGY, 21[1] pp.1~9 (January 1984). 1 REVIEW Present Status

Laughlin, Robert B.

240

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

SciTech Connect (OSTI)

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

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

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

E-Print Network [OSTI]

for nuclear waste disposal and decommissioning whilethe cost of decommissioning and nuclear waste disposal on

Grigoriadis, Theocharis N

2009-01-01T23:59:59.000Z

242

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

243

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

SciTech Connect (OSTI)

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

244

An improved visualization of diesel particulate filter/  

E-Print Network [OSTI]

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

Boehm, Kevin (Kevin W.)

2011-01-01T23:59:59.000Z

245

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

SciTech Connect (OSTI)

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

246

Diesel Soot Filter Characterization and Modeling for Advanced...  

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

Automotive) Diesel Soot Filter Characterization and Modeling for Advanced Substrates (CRADA with DOW Automotive) Presentation from the U.S. DOE Office of Vehicle Technologies...

247

Diesel Soot Filter Characterization and Modeling for Advanced...  

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

Automotive) Diesel Soot Filter Characterization and Modeling for Advanced Substrates (CRADA and DOW Automotive) Presentation from the U.S. DOE Office of Vehicle Technologies...

248

Filter systems for IGCC applications  

SciTech Connect (OSTI)

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

249

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

250

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

251

FILTER COMPONENT ASSESSMENT--CERAMIC CANDLES--  

SciTech Connect (OSTI)

Efforts at Siemens Westinghouse Power Corporation (SWPC) have been focused on development of hot gas filter systems as an enabling technology for advanced coal and biomass-based gas turbine power generation applications. 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 summarizes the results of SWPC's filter component assessment efforts, identifying the performance and stability of porous monolithic, fiber reinforced, and filament wound ceramic hot gas candle filters, potentially for {ge}3 years of viable pressurized fluidized-bed combustion (PFBC) service operating life.

M.A. Alvin

2004-04-23T23:59:59.000Z

252

?1 Trend Filtering  

E-Print Network [OSTI]

jump process approach, the LP approach, and median filtering are linear filtering ..... In signal processing, the idea of ?1 regularization comes up in several...

2007-09-28T23:59:59.000Z

253

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

254

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

SciTech Connect (OSTI)

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

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

1994-01-01T23:59:59.000Z

255

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

E-Print Network [OSTI]

Instrumentation & Control Systems Remote Maintenance Components Heat Transport & Power Conversion Systems In-vessel Components Plasma Facing Components divertor, limiter, heating/fueling and final optics, etc. Blanket, heat/particle fluxes, magnetic field, etc.) with high magnitude and steep gradients. 路 Nuclear heating

Abdou, Mohamed

256

Technology Evaluations Related to Mercury, Technetium, and Chloride in Treatment of Wastes at the Idaho Nuclear Technology and Engineering Center of the Idaho National Engineering and Environmental Laboratory  

SciTech Connect (OSTI)

The Idaho High-Level Waste and Facility Disposition Environmental Impact Statement defines alternative for treating and disposing of wastes stored at the Idaho Nuclear Technology and Engineering Center. Development is required for several technologies under consideration for treatment of these wastes. This report contains evaluations of whether specific treatment is needed and if so, by what methods, to remove mercury, technetium, and chlorides in proposed Environmental Impact Statement treatment processes. The evaluations of mercury include a review of regulatory requirements that would apply to mercury wastes in separations processes, an evaluation of the sensitivity of mercury flowrates and concentrations to changes in separations processing schemes and conditions, test results from laboratory-scale experiments of precipitation of mercury by sulfide precipitation agents from the TRUEX carbonate wash effluent, and evaluations of methods to remove mercury from New Waste Calcining Facility liquid and gaseous streams. The evaluation of technetium relates to the need for technetium removal and alternative methods to remove technetium from streams in separations processes. The need for removal of chlorides from New Waste Calcining Facility scrub solution is also evaluated.

C. M. Barnes; D. D. Taylor; S. C. Ashworth; J. B. Bosley; D. R. Haefner

1999-10-01T23:59:59.000Z

257

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

258

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

259

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

SciTech Connect (OSTI)

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

NONE

1993-12-31T23:59:59.000Z

260

New technology for purging the steam generators of nuclear power plants  

SciTech Connect (OSTI)

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

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

nuclear controls  

National Nuclear Security Administration (NNSA)

the Office of Nonproliferation and International Security (NIS) is to prevent the proliferation of nuclear weapons, materials, technology, and expertise. NIS applies technical...

262

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

SciTech Connect (OSTI)

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

263

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

SciTech Connect (OSTI)

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

264

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

265

HEPA filter dissolution process  

DOE Patents [OSTI]

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

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

1994-02-22T23:59:59.000Z

266

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

267

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

SciTech Connect (OSTI)

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

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

1982-03-01T23:59:59.000Z

268

Nuclear Materials Science:Materials Science Technology:MST-16:LANL:Los  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear Security Administration the ContributionsArms Control R&D Consortium includesEnergy

269

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

SciTech Connect (OSTI)

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

270

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

SciTech Connect (OSTI)

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

271

ELECTROSTATICALLY ENHANCED BARRIER FILTER COLLECTION  

SciTech Connect (OSTI)

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

272

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]

of twenty FFUs collected from the market were tested, including thirteen 1220 mm x 610 mm (or 4 ft x 2 ft technology with architecture and natural resources. Cleanroom HVAC systems account for a large portion of energy use in cleanrooms. Improving energy efficiency of HVAC systems and their components can contribute

273

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

274

Nuclear Waste Reduction  

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

Nuclear Waste Reduction Pyroprocessing is a promising technology for recycling used nuclear fuel and improving the associated waste management options. The process...

275

Journal of NUCLEAR SCIENCE and TECHNOLOGY, Vol. 39, No. 11, p. 11691181 (November 2002) Conceptual Design of a Modular Island Core Fast Breeder Reactor "RAPID-M"  

E-Print Network [OSTI]

Journal of NUCLEAR SCIENCE and TECHNOLOGY, Vol. 39, No. 11, p. 1169颅1181 (November 2002) Conceptual Design of a Modular Island Core Fast Breeder Reactor "RAPID-M" Mitsuru KAMBE Central Research Institute and accepted September 10, 2002) A metal fueled modular island core sodium cooled fast breeder reactor concept

Laughlin, Robert B.

276

Technology  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May JunDatastreamsmmcrcalgovInstrumentsrucLas ConchasPassiveSubmittedStatus TomAboutManusScience and InnovationexperimentsTechnology

277

VNS: A volumetric neutron source for fusion nuclear technology testing and development  

SciTech Connect (OSTI)

Recent progress in fusion plasma research and the initiation of the Engineering Design Activity for ITER provide incentives to seriously explore technically sound and logically consistent pathways toward development of fusion as a practical and attractive energy source. A critical goal is the successful construction and operation of a fusion power demonstration plant (DEMO). Major world program strategies call for DEMO operation by the year 2025. Such a date is important in order for fusion to play a significant role in the energy supply market in the second half of the twenty-first century. Without such a DEMO goal, it will be very hard to justify major financial commitments in the near term for major projects such as ITER. The major question is whether a DEMO goal by the year 2025 is attainable from a technical standpoint. This has been the central question being addressed in a study, called VENUS. Results to date show that a DEMO by the year 2025 can be realized if three major facilities begin operation in parallel by the year 2005. These facilities are: (1) ITER, (2) VNS, and (3) IFMIF. Results show that VNS is a necessary element toward DEMO in a strategy consistent with present world program plans. The key requirements to test and develop fusion nuclear components (e.g. blanket) are 1 MW/m{sup 2} neutron wall load, >10 m{sup 2} of test area at the first wall, steady state or long burn plasma operation, fluence of {approx}6MWy/m{sup 2} at the first wall in {approx}10-12 year period, and duty cycle x availability factor of {approx}0.3. Results of the study show that an attractive design envelope for VNS that satisfies the nuclear testing and development requirements exists. Within this design envelope, the most attractive design points for VNS appear to be driven plasma (Q{approx}1) in tokamak configuration with normal toroidal-field copper coils, major radius 1.5-2.0m, fusion power {approx}100MW, and neutron wall load {approx}1.5MW/m{sup 2}.

Abdou, M.A.; Peng, Y.K.; Ying, A.Y. [Univ. of California, Los Angeles, CA (United States)] [and others

1994-12-31T23:59:59.000Z

278

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

SciTech Connect (OSTI)

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

279

Filter type gas sampler with filter consolidation  

DOE Patents [OSTI]

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

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

1997-03-25T23:59:59.000Z

280

Review of Diesel Emission Control Technology  

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

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

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

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

282

HEPA filter encapsulation  

DOE Patents [OSTI]

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

Gates-Anderson, Dianne D. (Union City, CA); Kidd, Scott D. (Brentwood, CA); Bowers, John S. (Manteca, CA); Attebery, Ronald W. (San Lorenzo, CA)

2003-01-01T23:59:59.000Z

283

AEGIS technology demonstration for a nuclear waste repository in basalt. Assessment of effectiveness of geologic isolation systems  

SciTech Connect (OSTI)

A technology demonstration of current performance assessment techniques as applied to a nuclear waste repository in the Columbia Plateau Basalts was conducted. Hypothetical repository coordinates were selected for an actual geographical setting on the Hanford Reservation in the state of Washington. Published hydrologic and geologic data used in the analyses were gathered in 1979 or earlier. The following report documents the technology demonstration in basalt. Available information has been used to establish the data base and initial hydrologic and geologic interpretations for this site-specific application. A simplified diagram of the AEGIS analyses is shown. Because an understanding of the dynamics of ground-water flow is essential to the development of release scenarios and consequence analyses, a key step in the demonstration is the systems characterization contained in the conceptual model. Regional and local ground-water movement patterns have been defined with the aid of hydrologic computer models. Hypothetical release scenarios have been developed and evaluated by a process involving expert opinion and a Geologic Simulation Model for basalt. (The Geologic Simulation Model can also be used to forecast future boundary conditions for the hydrologic simulation.) Chemical reactivity of the basalt with ground water will influence the leaching and transport of radionuclides; solubility equilibria based on available data are estimated with geochemical models. After the radionuclide concentrations are mathematically introduced into the ground-water movement patterns, waste movement patterns are outlined over elapsed time. Contaminant transport results are summarized for significant radionuclides that are hypothetically released to the accessible environment and to the biosphere.

Dove, F.H.; Cole, C.R.; Foley, M.G.

1982-09-01T23:59:59.000Z

284

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

E-Print Network [OSTI]

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

Swanton, Andrew A

2008-01-01T23:59:59.000Z

285

Technology To Realize  

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

in Technology To Realize Fusion Energy in the International Context Kathryn A. McCarthy Deputy Associate Laboratory Director Nuclear Science & Technology Idaho National Laboratory...

286

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

SciTech Connect (OSTI)

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

287

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

288

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

SciTech Connect (OSTI)

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

289

Moving granular-bed filter development program. Topical report  

SciTech Connect (OSTI)

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

290

Technology and apparatus for solidification of radioactive wastes from nuclear fuel cycle by high temperature adsorption of metals on inorganic matrices  

SciTech Connect (OSTI)

This study deals with the investigation of high-level waste (HLW) solidification by high-temperature adsorption of radionuclides on porous inorganic matrices. An appropriate drum-type apparatus using magnetic gear drive was designed and tested. The report contains the test results of the solidification process of high-level radioactive raffinate from the first regeneration extraction cycle of irradiated fuel elements from nuclear power plants. Industrial-scale tests of the HLW solidification process (technology and equipment) are planned.

Nardova, A.K.; Philipov, E.A.; Kudriavtsev, Y.G.; Dzekun, E.G.; Parfanovitch, B.N. [Russian Research Inst. of Chemical Technology, Moscow (Russian Federation)

1993-12-31T23:59:59.000Z

291

Contactor/filter improvements  

DOE Patents [OSTI]

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

Stelman, D.

1988-06-30T23:59:59.000Z

292

Filter holder and gasket assembly for candle or tube filters  

DOE Patents [OSTI]

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

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

1999-03-02T23:59:59.000Z

293

INSTITUTE OF NUCLEAR TECHNOLOGY  

E-Print Network [OSTI]

CENTER FOR SCIENTIFIC RESEARCH #12;1 1. Research Reactor Laboratory (RRL) 1. PEER-REVIEWED JOURNALS 1. Mourtzanos, K., Housiadas, C., Antonopoulos-Domis, M., "Calculation of the moderator temperature coefficient of reactivity for water moderated reactors", Ann. Nucl. Energy, 28, 1773-1782, (2001). 4. Housiadas, C

294

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

295

Micromechanical optical filters for spectrometry Hakon Sagberg  

E-Print Network [OSTI]

This thesis presents a study of optical filters that are fabricated as micro-electro- mechanical systems (MEMS. Experiments show that sensitive microphones can be made with this technology. The thesis consists partner. He has posed critical questions and saved me from spending too much time in blind alleys

Johansen, Tom Henning

296

Nitride-bonded silicon carbide composite filter  

SciTech Connect (OSTI)

The objective of this program is to develop and demonstrate an advanced hot gas filter, using ceramic component technology, with enhanced durability to provide increased resistance to thermal fatigue and crack propagation. The material is silicon carbide fiber reinforced nitride bonded silicon carbide.

Thomson, B.N.; DiPietro, S.G.

1995-12-01T23:59:59.000Z

297

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

298

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

E-Print Network [OSTI]

Energy Policy, Vol. 34 Generation IV International Forum. 揑ntroduction to Generation IV Nuclear Energy Systems and theIII Plus 2030-onward Generation IV 2030-onward 2030-onward

Grigoriadis, Theocharis N

2009-01-01T23:59:59.000Z

299

22.314J / 1.56J / 2.084J Structural Mechanics in Nuclear Power Technology, Spring 2004  

E-Print Network [OSTI]

Structural components in nuclear power plant systems, their functional purposes, operating conditions, and mechanical-structural design requirements. Combines mechanics techniques with models of material behavior to determine ...

Kazimi, Mujid S.

300

Evaluation of Alternative Filter Media for the Rotary Microfilter  

SciTech Connect (OSTI)

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

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

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

SciTech Connect (OSTI)

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

302

Sub-micron filter  

DOE Patents [OSTI]

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

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

2009-10-13T23:59:59.000Z

303

FINESSE: study of the issues, experiments and facilities for fusion nuclear technology research and development. Interim report. Volume I  

SciTech Connect (OSTI)

The following chapters are included in this study: (1) fusion nuclear issues, (2) survey of experimental needs, (3) requirements of the experiments, (4) non-fusion facilities, (5) fusion facilities for nuclear experiments, and (6) fusion research and development scenarios. (MOW)

Abdou, M.

1984-10-01T23:59:59.000Z

304

METAL FILTERS FOR PRESSURIZED FLUID BED COMBUSTION (PFBC) APPLICATIONS  

SciTech Connect (OSTI)

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

305

Development of Technologies for the Simultaneous Separation of Cesium and Strontium from Spent Nuclear Fuel as Part of an Advanced Fuel Cycle  

SciTech Connect (OSTI)

As part of the Advanced Fuel Cycle Initiative, two solvent extraction technologies are being developed to simultaneously separate cesium and strontium from dissolved spent nuclear fuel. The first process utilizes a solvent consisting of chlorinated cobalt dicarbollide and polyethylene glycol extractants in a phenyltrifluoromethyl sulfone diluent. Recent improvements to the process include development of a new, non-nitroaromatic diluent and development of new stripping reagents, including a regenerable strip reagent that can be recovered and recycled. Countercurrent flowsheets have been designed and tested on simulated and actual spent nuclear fuel feed streams with both cesium and strontium removal efficiencies of greater than 99 %. The second process developed to simultaneously separate cesium and strontium from spent nuclear fuel is based on two highly-specific extractants: 4,4',(5')-Di-(t-butyldicyclo-hexano)-18-crown-6 (DtBuCH18C6) and Calix[4]arene-bis-(tert-octylbenzo-crown-6) (BOBCalixC6). The DtBuCH18C6 extractant is selective for strontium and the BOBCalixC6 extractant is selective for cesium. A solvent composition has been developed that enables both elements to be removed together and, in fact, a synergistic effect was observed with strontium distributions in the combined solvent that are much higher that in the strontium extraction (SREX) process. Initial laboratory test results of the new combined cesium and strontium extraction process indicate good extraction and stripping performance. A flowsheet for treatment of spent nuclear fuel is currently being developed.

Jack D. Law; R. Scott HErbst; David H. Meikrantz; Dean R. Peterman; Catherine L. Riddle; Richard D. Tillotson; Terry A. Todd

2005-04-01T23:59:59.000Z

306

Development of NDE methods for hot gas filters.  

SciTech Connect (OSTI)

Ceramic hot gas candle filters are currently under development for hot gas particulate cleanup in advanced coal-based power systems. The ceramic materials for these filters include nonoxide monolithic, nonoxide-fiber-reinforced composites, and nonoxide reticulated foam. A concern is the lack of reliable data on which to base decisions for reusing or replacing hot gas filters during plant shutdowns. The work in this project is aimed at developing nondestructive evaluation (FIDE) technology to allow detection, and determination of extent, of life-limiting characteristics such as thermal fatigue, oxidation, damage from ash bridging such as localized cracking, damage from local burning, and elongation at elevated temperature. Although in-situ NDE methods are desirable in order to avoid disassembly of the candle filter vessels, the current vessel designs, the presence of filter cakes and possible ash bridging, and the state of NDE technology prevent this. Candle filter producers use a variety of NDE methods to ensure as-produced quality. While impact acoustic resonance offers initial promise for examining new as-produced filters and for detecting damage in some monolithic filters when removed from service, it presents difficulties in data interpretation, it lacks localization capability, and its applicability to composites has yet to be demonstrated. Additional NDE technologies being developed and evaluated in this program and whose applicability to both monolithics and composites has been demonstrated include (a) full-scale thermal imaging for analyzing thermal property variations; (b) fret, high-spatial-resolution X-ray imaging for detecting density variations and dimensional changes; (c) air-coupled ultrasonic methods for determining through-thickness compositional variations; and (d) acoustic emission technology with mechanical loading for detecting localized bulk damage. New and exposed clay-bonded SiC filters and CVI-SiC composite filters have been tested with these additional NDE methods.

Deemer, C.; Ellingson, W. A.; Koehl, E. R.; Lee, H.; Spohnholtz, T.; Sun, J. G.

1999-07-21T23:59:59.000Z

307

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

308

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

E-Print Network [OSTI]

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

White, Daniel B., Jr

2011-01-01T23:59:59.000Z

309

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

SciTech Connect (OSTI)

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

Hofmann, P.L. (ed.)

1982-01-01T23:59:59.000Z

310

Westinghouse filter update  

SciTech Connect (OSTI)

Hot gas filters have been implemented and operated in four different test facilities: Subpilot scale entrained gasifier, located at the Texaco Montebello Research facilities in California, Foster Wheeler Advanced Pressurized Fluidized Bed Combustion pilot plant facilities, located in Livingston, New Jersey, Slipstream of the American Electric Power (AEP) 70 MW (electric) Tidd-PFBC, located in Brilliant, Ohio, and in the Ahlstrom 10 MW (thermal) Circulating PFBC facility, located in Karhula, Finland. Candle filter testing has occurred at all four facilities; cross flow filter testing has occurred at the Texaco and Foster Wheeler facilities. Table 1 identifies and summarizes the key operating characteristics of these facilities and the type and scale of filter unit tested. A brief description of each project is given.

Lippert, T.E.; Bruck, G.J.; Smeltzer, E.E.; Newby, R.A.; Bachovchin, D.M. [Westinghouse Electric Corp., Pittsburgh, PA (United States). Science and Technology Center

1993-09-01T23:59:59.000Z

311

Differential Filtering and Detexturing  

E-Print Network [OSTI]

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

He, Lei

2014-08-18T23:59:59.000Z

312

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

SciTech Connect (OSTI)

This report provides a record of the Structural Integrity Program for the 300,000-gal liquid waste storage tanks and associated equipment at the Idaho Nuclear Technology and Engineering Center, as required by U.S. Department of Energy M 435.1-1, ''Radioactive Waste Management Manual.'' This equipment is known collectively as the Tank Farm Facility. 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, J.W.; Nenni, J.A.; Yoder, T.S.

2003-04-22T23:59:59.000Z

313

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

SciTech Connect (OSTI)

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. 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 Whealdon; Nenni, Joseph A; Timothy S. Yoder

2003-04-01T23:59:59.000Z

314

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

SciTech Connect (OSTI)

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

315

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

1980-01-01T23:59:59.000Z

316

Moving Granular Bed Filter Development Program  

SciTech Connect (OSTI)

For coal-fired power plants utilizing a gas turbine, the removal of ash particles is necessary to protect the turbine and to meet emission standards. Advantages are also evident for a filter system that can remove other coal-derived contaminants such as alkali, halogens, and ammonia. With most particulates and other contaminants removed, erosion and corrosion of turbine materials, as well as deposition of particles within the turbine, are reduced to acceptable levels. The granular bed filter is suitable for this task in a pressurized gasification or combustion environment. The objective of the base contract was to develop conceptual designs of moving granular bed filter (GBF) and ceramic candle filter technologies for control of particles from integrated gasification combined cycle (IGCC), pressurized fluidized-bed combustion (PFBC), and direct coal-fueled turbine (DCFT) systems. The results of this study showed that the GBF design compared favorably with the candle filter. Three program options followed the base contract. The objective of Option I, Component Testing, was to identify and resolve technical issues regarding GBF development for IGCC and PFBC environments. This program was recently completed. The objective of Option II, Filter Proof Tests, is to test and evaluate the moving GBF system at a government-furnished hot-gas cleanup test facility. This facility is located at Southern Company Services (SCS), Inc., Wilsonville, Alabama. The objective of Option III, Multicontaminant Control Using a GBF, is to develop a chemically reactive filter material that will remove particulates plus one or more of the following coal-derived contaminants: alkali, halogens, and ammonia.

Wilson, K.B.; Haas, J.C. [Combustion Power Co., San Mateo, CA (United States); Gupta, R.P.; Turk, B.S. [Research Triangle Inst., Research Triangle Park, NC (United States)

1996-12-31T23:59:59.000Z

317

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

318

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

319

Moving granular-bed filter development program topical report  

SciTech Connect (OSTI)

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

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

1991-10-17T23:59:59.000Z

320

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

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

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

SciTech Connect (OSTI)

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

John Collins

2009-08-01T23:59:59.000Z

322

Evaluation of Alternative Filter Media for the Rotary Microfilter  

SciTech Connect (OSTI)

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

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

2011-11-09T23:59:59.000Z

323

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

SciTech Connect (OSTI)

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

324

Designing a Practical Data Filter Cache to Improve Both Energy Efficiency and Performance  

E-Print Network [OSTI]

A Designing a Practical Data Filter Cache to Improve Both Energy Efficiency and Performance Alen Bardizbanyan, Chalmers University of Technology Magnus Sj篓alander, Florida State University David Whalley, Florida State University Per Larsson-Edefors, Chalmers University of Technology Conventional data filter

Whalley, David

325

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

326

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

SciTech Connect (OSTI)

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

327

Filter component assessment  

SciTech Connect (OSTI)

The objectives of this program are to provide a more ruggedized filter system that utilizes porous ceramic filters which have improved resistance to damage resulting from crack propagation, thermal fatigue and/or thermal excursions during plant or process transient conditions, and/or mechanical ash bridging events within the candle filter array. As part of the current Phase 1, Task 1, effort of this program, Westinghouse is evaluating the filtration characteristics, mechanical integrity, and corrosion resistance of the following advanced or second generation candle filters for use in advanced coal-fired process applications: 3M CVI-SiC composite--chemical vapor infiltration of silicon carbide into an aluminosilicate Nextel{trademark} 312 fiber preform; DuPont PRD-66--filament wound candle filter structure containing corundum, cordierite, cristobalite, and mullite; DuPont SiC-SiC--chemical infiltration of silicon carbide into a silicon carbide Nicalon{trademark} fiber mat or felt preform; and IF and P Fibrosic{trademark}--vacuum infiltrated oxide-based chopped fibrous matrix. Results to date are presented.

Alvin, M.A.; Lippert, T.E.; Diaz, E.S.; Smeltzer, E.W. [Westinghouse Electric Corp., Pittsburgh, PA (United States). Science and Technology Center

1995-11-01T23:59:59.000Z

328

Response of HEPA filters to simulated-accident conditions  

SciTech Connect (OSTI)

High-efficiency particulate air (HEPA) filters have been subjected to simulated accident conditions to determine their response to abnormal operating events. Both domestic and European standard and high-capacity filters have been evaluated to determine their response to simulated fire, explosion, and tornado conditions. The HEPA filter structural limitations for tornado and explosive loadings are discussed. In addition, filtration efficiencies during these accident conditions are reported for the first time. Our data indicate efficiencies between 80% and 90% for shock loadings below the structural limit level. We describe two types of testing for ineffective filtration - clean filters exposed to pulse-entrained aerosol and dirty filters exposed to tornado and shock pulses. Efficiency and material loss data are described. Also, the resonse of standard HEPA filters to simulated fire conditions is presented. We describe a unique method of measuring accumulated combustion products on the filter. Additionally, data relating to pressure drop vs accumulated mass during plugging are reported for simulated combustion aerosols. The effects of concentration and moisture levels on filter plugging were evaluated. We are obtaining all of the above data so that mathematical models can be developed for fire, explosion, and tornado accident analysis computer codes. These computer codes can be used to assess the response of nuclear air cleaning systems to accident conditions.

Gregory, W.S.; Martin, R.A.; Smith, P.R.; Fenton, D.E.

1982-01-01T23:59:59.000Z

329

Development of ceramic composite hot-gas filters  

SciTech Connect (OSTI)

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

Judkins, R.R.; Stinton, D.P. [Oak Ridge National Lab., TN (United States); Smith, R.G.; Fischer, E.M.; Eaton, J.H.; Weaver, B.L.; Kahnke, J.L.; Pysher, D.J. [3M Co., St. Paul, MN (United States)

1995-04-01T23:59:59.000Z

330

A Critical Analysis of Technological Innovation and Economic Development in Southern California's Urban Water Reuse And Recycling Industry  

E-Print Network [OSTI]

Richardson, Mark 2009. Siemens Water Technologies Company2011. www. 3news.co.nz Siemens Water Technologies, 2012.conglomerations, US Filter, now Siemens Water Technologies

Pilip-Florea, Shadrach Jay

2012-01-01T23:59:59.000Z

331

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

SciTech Connect (OSTI)

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

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

2014-05-09T23:59:59.000Z

332

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

333

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...

334

Digital Sensor Technology  

SciTech Connect (OSTI)

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

Ted Quinn; Jerry Mauck; Richard Bockhorst; Ken Thomas

2013-07-01T23:59:59.000Z

335

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

336

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

337

DEVELOPMENT OF AN ADHESIVE CANDLE FILTER SAFEGUARD DEVICE  

SciTech Connect (OSTI)

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

338

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,...

339

Web Content Filtering 1 User Guidelines Web content filter guidelines  

E-Print Network [OSTI]

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

340

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

SciTech Connect (OSTI)

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

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

Quick-change filter cartridge  

DOE Patents [OSTI]

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

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

1995-01-01T23:59:59.000Z

342

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

SciTech Connect (OSTI)

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

343

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

SciTech Connect (OSTI)

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

344

ADVANCED SECOND GENERATION CERAMIC CANDLE FILTERS  

SciTech Connect (OSTI)

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

M.A. Alvin

2002-01-31T23:59:59.000Z

345

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

SciTech Connect (OSTI)

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

346

Siphon filter assessment for Northern Ghana  

E-Print Network [OSTI]

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

Ziff, Sara Elizabeth

2009-01-01T23:59:59.000Z

347

A decision analysis framework to support long-term planning for nuclear fuel cycle technology research, development, demonstration and deployment  

SciTech Connect (OSTI)

To address challenges and gaps in nuclear fuel cycle option assessment and to support research, develop and demonstration programs oriented toward commercial deployment, EPRI (Electric Power Research Institute) is seeking to develop and maintain an independent analysis and assessment capability by building a suite of assessment tools based on a platform of software, simplified relationships, and explicit decision-making and evaluation guidelines. As a demonstration of the decision-support framework, EPRI examines a relatively near-term fuel cycle option, i.e., use of reactor-grade mixed-oxide fuel (MOX) in U.S. light water reactors. The results appear as a list of significant concerns (like cooling of spent fuels, criticality risk...) that have to be taken into account for the final decision.

Sowder, A.G.; Machiels, A.J. [Electric Power Research Institute, 1300 West. W.T Harris Boulevard, Charlotte, NC 28262 (United States); Dykes, A.A.; Johnson, D.H. [ABSG Consulting Inc., 300 Commerce, Suite 200, Irvine, CA 92602 (United States)

2013-07-01T23:59:59.000Z

348

Emergency Preparedness technology support to the Health and Safety Executive (HSE), Nuclear Installations Inspectorate (NII) of the United Kingdom. Appendix A  

SciTech Connect (OSTI)

The Nuclear Installations Inspectorate (NII) of the United Kingdom (UK) suggested the use of an accident progression logic model method developed by Westinghouse Savannah River Company (WSRC) and Science Applications International Corporation (SAIC) for K Reactor to predict the magnitude and timing of radioactivity releases (the source term) based on an advanced logic model methodology. Predicted releases are output from the personal computer-based model in a level-of-confidence format. Additional technical discussions eventually led to a request from the NII to develop a proposal for assembling a similar technology to predict source terms for the UK`s advanced gas-cooled reactor (AGR) type. To respond to this request, WSRC is submitting a proposal to provide contractual assistance as specified in the Scope of Work. The work will produce, document, and transfer technology associated with a Decision-Oriented Source Term Estimator for Emergency Preparedness (DOSE-EP) for the NII to apply to AGRs in the United Kingdom. This document, Appendix A is a part of this proposal.

O`Kula, K.R.

1994-03-01T23:59:59.000Z

349

Regenerable particulate filter  

DOE Patents [OSTI]

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

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

2009-05-05T23:59:59.000Z

350

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.

351

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

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

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

352

Electrically-Assisted Diesel Particulate Filter Regeneration...  

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

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

353

Volatilization of Fission Products from Metallic Melts in the Melt-Dilute Treatment Technology Development for Al-Based DOE Spent Nuclear Fuels  

SciTech Connect (OSTI)

The melt-dilute treatment technology is being developed to facilitate the ultimate disposition of highly enriched Al-Base DOE spent nuclear fuels in a geologic repository such as that proposed for Yucca Mountain. Currently, approximately 28 MTHM is expected to be returned to the Savannah River Site from domestic and foreign research reactors. The melt-dilute treatment technology will melt the fuel assemblies to reduce their volume and alloys them with depleted uranium to isotopically dilute the 235U concentration. The resulting alloy is cast into a form for long term geologic repository storage. Benefits accrued from the melt-dilute process include the potential for significant volume reduction; reduced criticality potential, and proliferation concerns. A critical technology element in the development of the melt-dilute process is the development of offgas system requirements. The volatilization of radioactive species during the melting stage of the process primarily constitutes the offgas in this process. Several of the species present following irradiation of a fuel assembly have been shown to be volatile or semi-volatile under reactor core melt-down conditions. Some of the key species that have previously been studied are krypton, iodine, and cesium. All of these species have been shown to volatilize during melting experiments however, the degree to which they are released is highly dependent upon atmosphere, fuel burnup, temperature, and fuel composition. With this in mind an analytical and experimental program has been undertaken to assess the volatility and capture of species under the melt-dilute operating conditions.

Adams, T.

1999-11-18T23:59:59.000Z

354

In-service filter testing  

SciTech Connect (OSTI)

This report contains the observations, test results, and conclusions of three separate in-service tests beginning in November 1979 and concluding in September 1983. The in-service tests described in this report produced encouraging results on filters constructed with fiberglass medium containing 5% Nomex and separators of aluminum foil coated with a thin film of vinyl-epoxy polymer. Filters containing medium with Kevlar fiber additives demonstrated they merited further evaluation. Other types of filters tested include separatorless filters (Flanders SuperFlow) and one filter with fiberglass separators. Asbestos-containing filters were used for comparison until their supply was exhausted. All filters tested were judged to have performed satisfactorily under the test conditions.

Terada, K.; Woodard, R.W.; Jensen, R.T.

1985-04-29T23:59:59.000Z

355

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

SciTech Connect (OSTI)

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

CHARBONEAU, S.L.

2006-02-01T23:59:59.000Z

356

NUCLEAR PLANT OPERATIONS AND  

E-Print Network [OSTI]

NUCLEAR PLANT OPERATIONS AND CONTROL KEYWORDS: moderator temper ature coefficient, reactivity co reactor Unit 4 of the Ringhals Nuclear Power Plant (Sweden) during fuel cycle 16 is analyzed absorption cross-section behavior. Consequently, if NUCLEAR TECHNOLOGY VOL. 140 NOV. 2002 147 #12;Demazi鑢e

Demazi鑢e, Christophe

357

NUCLEAR PLANT OPERATIONS AND  

E-Print Network [OSTI]

NUCLEAR PLANT OPERATIONS AND CONTROL KEYWORDS: moderator temper- ature coefficient, reactivity co reactor Unit 4 of the Ringhals Nuclear Power Plant (Sweden) during fuel cycle 16 is analyzed. Consequently, if*E-mail: demaz@nephy.chalmers.se NUCLEAR TECHNOLOGY VOL. 140 NOV. 2002 147 #12;high-burnup fuel

P醶sit, Imre

358

DEVELOPMENT OF A CANDLE FILTER FAILURE SAFEGUARD DEVICE  

SciTech Connect (OSTI)

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

359

TESTING OF THE SECOND GENERATION SPINTEK ROTARY FILTER -11357  

SciTech Connect (OSTI)

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

360

Comparative survey on non linear filtering methods : the quantization and the particle filtering approaches  

E-Print Network [OSTI]

, importance sam- pling, Kalman filter, stochastic volatility, infinite dimension filter. 1 Introduction We models: the Kalman filter case, the canonical stochastic volatility model and the infinite dimension

Paris-Sud XI, Universit de

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

Note: Cryogenic coaxial microwave filters  

SciTech Connect (OSTI)

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

362

Some thoughts on the nonproliferation of nuclear weapons  

SciTech Connect (OSTI)

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

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

1996-05-01T23:59:59.000Z

363

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

SciTech Connect (OSTI)

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

364

filter + electrical Zeroforcing Electrical Filters for Direct Detection Optical Systems  

E-Print Network [OSTI]

signal envelope. The thermal noise n(t) from the electronics is assumed to be the dominant noise) = Re{p(t-iT )p # (t-jT )}, p(t) is the complex envelope of the received optical pulse taking璓erot interferometer We consider a Fabry璓erot filter as the optical demulti plexing filter [1]. The envelope

Humblet, Pierre A.

365

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

SciTech Connect (OSTI)

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

366

The nuclear marketplace and grand strategy: civilian nuclear cooperation and the bomb.  

E-Print Network [OSTI]

??This dissertation consists of two principal sections. The first portion explores the relationship between nuclear energy and nuclear weapons. Building on the "technological momentum" hypothesis, (more)

Fuhrmann, Matthew

2008-01-01T23:59:59.000Z

367

Mode Filtered Fiber Amplifier  

ScienceCinema (OSTI)

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

Sandia

2009-09-01T23:59:59.000Z

368

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

369

Removing Redundancy and Inconsistency in Memory-Based Collaborative Filtering  

E-Print Network [OSTI]

Removing Redundancy and Inconsistency in Memory- Based Collaborative Filtering Kai Yu Siemens AG, Corporate Technology & University of Munich, Germany kai.yu.external@mchp.siemens. de Xiaowei Xu Information Science Department University of Arkansas at Little Rock xwxu@ualr.edu Anton Schwaighofer Siemens AG

Tresp, Volker

370

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

371

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

372

Automated Intruder Tracking using Particle Filtering and a Network of Binary Motion Sensors  

E-Print Network [OSTI]

infrared (PIR) motion sensors that suggest that our estimator is effective and degrades gracefully with increasing sensor refractory periods. Index Terms - Security, Sensor Networks, Particle Filter, Tracking, Sensor Fusion. I. INTRODUCTION Many new technologies for automated security, wireless networks

Goldberg, Ken

373

National Nuclear Chemistry Summer School  

Broader source: Energy.gov [DOE]

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

374

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

375

Fuel Efficient Diesel Particulate Filter (DPF) Modeling and Development  

SciTech Connect (OSTI)

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

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

2010-08-01T23:59:59.000Z

376

Sintered composite medium and filter  

DOE Patents [OSTI]

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

Bergman, Werner (Pleasanton, CA)

1987-01-01T23:59:59.000Z

377

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

SciTech Connect (OSTI)

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

378

Backpulse and filter feed velocity effects on Norton filter performance  

SciTech Connect (OSTI)

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

379

Issues for New Nuclear Plants  

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

to produce heavy components and nuclear-grade equipment - Transportation of heavy components - Constructionoperation workforce - Cost of new plants Cooling Technology...

380

Spent Nuclear Fuel Fact Sheets  

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

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

Performance of ceramic membrane filters  

SciTech Connect (OSTI)

CeraMem Corp.`s ceramic-membrane coated, dead-end ceramic filters offer a promising alternative to ceramic candle filters providing long-term operational and reliability issues are resolved: regenerability of filter passages by back pulse cleaning, tolerance to alkali-containing combustion gas and thermal/chemical aging. ANL is responsible for analytical modeling of filtration and pulse cleaning operations, flow-through testing, and prediction of filter response to thermal cycling under realistic service conditions. A test apparatus was built to expose ceramic filter specimens to chemical environments simulating operation of pressurized fluidized bed and integrated gasification combined cycle plants. Four long-duration tests have been conducted in which 100-cpsi channel filters were exposed to ash collected downstream of the cyclone separator at the PFBC plant at Tidd. Results are discussed. Focus has now shifted to exposing the advanced candle filter specimens to reducing gas environments containing NaCl, H{sub 2}S, H{sub 2}O, and gasification ash.

Ahluwalia, R.K.; Im, K.H.; Geyer, H.K. [Argonne National Lab., IL (United States); Shelleman, D.L.; Tressler, R.E. [Pennsylvania State Univ., University Park, PA (United States)

1996-08-01T23:59:59.000Z

382

Spatial Filter with Volume Gratings for High-peak-power Multistage Laser Amplifiers  

E-Print Network [OSTI]

The regular spatial filters comprised of lens and pinhole are essential component in high power laser systems, such as lasers for inertial confinement fusion, nonlinear optical technology and directed-energy weapon. On the other hand the pinhole is treated as a bottleneck of high power laser due to harmful plasma created by the focusing beam. In this paper we present a spatial filter based on angular selectivity of Bragg diffraction grating to avoid the harmful focusing effect in the traditional pinhole filter. A spatial filter consisted of volume phase gratings in two-pass amplifier cavity were reported. Two-dimensional filter was proposed by using single Pi-phase-shifted Bragg grating, numerical simulation results shown that its angular spectrum bandwidth can be less than 160urad. The angular selectivity of photo-thermo-refractive glass and RUGATE film filters, construction stability, thermal stability and the effects of misalignments of gratings on the diffraction efficiencies under high-pulse-energy laser...

Tan, Yi-zhou; Zheng, Guang-wei; Shen, Ben-jian; Pan, Heng-yue; Li, Liu

2012-01-01T23:59:59.000Z

383

Nuclear Fabrication Consortium  

SciTech Connect (OSTI)

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

384

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

SciTech Connect (OSTI)

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

Herbst, Alan K.

2002-01-02T23:59:59.000Z

385

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

SciTech Connect (OSTI)

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

Herbst, Alan Keith

2002-01-01T23:59:59.000Z

386

Tunable Imaging Filters in Astronomy  

E-Print Network [OSTI]

While tunable filters are a recent development in night time astronomy, they have long been used in other physical sciences, e.g. solar physics, remote sensing and underwater communications. With their ability to tune precisely to a given wavelength using a bandpass optimized for the experiment, tunable filters are already producing some of the deepest narrowband images to date of astrophysical sources. Furthermore, some classes of tunable filters can be used in fast telescope beams and therefore allow for narrowband imaging over angular fields of more than a degree over the sky.

J. Bland-Hawthorn

2000-06-05T23:59:59.000Z

387

Energy Efficiency and Industrial Technology  

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

Next Generation Nuclear Plant Docs CONTACT US Center for Advanced Energy Studies Energy Efficiency and Industrial Technology The Department conducts research for DOE, other...

388

ADVANCED NUCLEAR TRANSFORMATION TECHNOLOGY SUBCOMMITTEE  

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

of spallation neutron spectra up to 20-25 MeV for 600 MeV proton and 50 MeV electron beams. However, the neutron flux is small. Even though studies of ADS will continue as part...

389

Nuclear waste incineration technology status  

SciTech Connect (OSTI)

The incinerators developed and/or used for radioactive waste combustion are discussed and suggestions are made for uses of incineration in radioactive waste management programs and for incinerators best suited for specific applications. Information on the amounts and types of radioactive wastes are included to indicate the scope of combustible wastes being generated and in existence. An analysis of recently developed radwaste incinerators is given to help those interested in choosing incinerators for specific applications. Operating information on US and foreign incinerators is also included to provide additional background information. Development needs are identified for extending incinerator applications and for establishing commercial acceptance.

Ziegler, D.L.; Lehmkuhl, G.D.; Meile, L.J.

1981-07-15T23:59:59.000Z

390

ADVANCED NUCLEAR TRANSFORMATION TECHNOLOGY SUBCOMMITTEE  

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

to evaluate the physics, startup, and operation of a coupled accelerator and subcritical system. Activities to support development of a target for ADSs. Transmutation...

391

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

SciTech Connect (OSTI)

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

392

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

393

The Filter Difference Spectrometer  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear SecurityTensile Strain Switched Ferromagnetism in Layered NbS2 and NbSe2Different ImpactsTheRolling Stone"TheThe

394

Nuclear disarmament verification  

SciTech Connect (OSTI)

Arms control treaties, unilateral actions, and cooperative activities -- reflecting the defusing of East-West tensions -- are causing nuclear weapons to be disarmed and dismantled worldwide. In order to provide for future reductions and to build confidence in the permanency of this disarmament, verification procedures and technologies would play an important role. This paper outlines arms-control objectives, treaty organization, and actions that could be undertaken. For the purposes of this Workshop on Verification, nuclear disarmament has been divided into five topical subareas: Converting nuclear-weapons production complexes, Eliminating and monitoring nuclear-weapons delivery systems, Disabling and destroying nuclear warheads, Demilitarizing or non-military utilization of special nuclear materials, and Inhibiting nuclear arms in non-nuclear-weapons states. This paper concludes with an overview of potential methods for verification.

DeVolpi, A.

1993-12-31T23:59:59.000Z

395

International Masters Program in Nuclear Security Human Capacity Building in Nuclear Security  

E-Print Network [OSTI]

1 TUDelft International Masters Program in Nuclear Security Human Capacity Building in Nuclear Security Dirk Jan van den Berg President Del2 University of Technology participants, Nuclear security requires highly skilled experts. Professionals, who are familiar

Langendoen, Koen

396

Trees as Filters of Radioactive Fallout from the Chernobyl Accident  

E-Print Network [OSTI]

This paper is a copy of an unpublished study of the filtering effect of red maple trees (acer rubrum) on fission product fallout near Binghamton, NY, USA following the 1986 Chernobyl accident. The conclusions of this work may offer some insight into what is happening in the forests exposed to fallout from the Fukushima Daiichi Nuclear Plant accident. This posting is in memory of Noel K. Yeh.

Brownridge, James D

2011-01-01T23:59:59.000Z

397

particle flow for nonlinear filters  

E-Print Network [OSTI]

particle flow for nonlinear filters Fred Daum 19 June 2012 Copyright 漏 2012 Raytheon Company. All rights reserved. Customer Success Is Our Mission is a trademark of Raytheon Company. 1 #12;discrete time

Dobigeon, Nicolas

398

Westinghouse advanced particle filter system  

SciTech Connect (OSTI)

Integrated Gasification Combined Cycles (IGCC), Pressurized Fluidized Bed Combustion (PFBC) and Advanced PFBC (APFB) are being developed and demonstrated for commercial power generation application. Hot gas particulate filters are key components for the successful implementation of IGCC, PFBC and APFB in power generation gas turbine cycles. The objective of this work is to develop and qualify through analysis and testing a practical hot gas ceramic barrier filter system that meets the performance and operational requirements of these advanced, solid fuel power generation cycles.

Lippert, T.E.; Bruck, G.J.; Sanjana, Z.N.; Newby, R.A.

1995-11-01T23:59:59.000Z

399

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

400

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

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

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

402

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

SciTech Connect (OSTI)

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

403

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

SciTech Connect (OSTI)

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

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

1991-10-17T23:59:59.000Z

404

Active dc filter for HVDC systems  

SciTech Connect (OSTI)

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

405

RAPID SEPARATION METHOD FOR ACTINIDES IN EMERGENCY AIR FILTER SAMPLES  

SciTech Connect (OSTI)

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

406

FUSION NUCLEAR SCIENCE PROGRAM & SUPPORTING FUSION NUCLEAR SCIENCE FACILITY (FNSF)  

E-Print Network [OSTI]

FUSION NUCLEAR SCIENCE PROGRAM & SUPPORTING FUSION NUCLEAR SCIENCE FACILITY (FNSF): UPDATE 路 It was well recognized there were also critical materials and technology issues that needed to be addressed in order to apply the knowledge we gained about burning plasma state #12;FUSION NUCLEAR SCIENCE PROGRAM

407

Summary of meeting on disposal of LET&D HEPA filters  

SciTech Connect (OSTI)

This report is a compilation of correspondence between Westinghouse Idaho Nuclear Company and the US EPA over a period of time from 1988 to 1992 (most from 1991-92) regarding waste management compliance with EPA regulations. Typical subjects include: compliance with satellite accumulation requirements; usage of ``Sure Shot`` containers in place of aerosol cans; notice of upcoming recyclable battery shipments; disposition of batteries; HEPA filter leach sampling and permit impacts; functional and operation requirements for the spent filter handling system; summary of meeting on disposal of LET and D HEPA filters; solvent substitution database report; and mercury vapor light analytical testing.

Not Available

1991-11-21T23:59:59.000Z

408

Moving granular-bed filter development program option I -- Component test facilities technical tradeoffs and issues. Topical report  

SciTech Connect (OSTI)

Advanced, coal-based, power plants, such as IGCC and Advanced-PFBC, are currently nearing commercial demonstration. These power plant technologies require hot gas filtration as part of their gas cleaning trains. Ceramic barrier filters are the major filter candidates being developed for these hot gas cleaning applications. While ceramic barrier filters achieve high levels of particle removal, there are concerns for their reliability and operability in these applications. An alternative hot gas filtration technology is the moving granular bed filter. These systems are at a lower state of development than ceramic barrier filters, and the current, moving granular-bed filter technologies are relatively large, complex, and costly systems in terms of their capital investment, their operating and maintenance cost, and their impact on the power plant efficiency. In addition, their effectiveness as filters is still in question. Their apparent attributes, relative to ceramic barrier filter systems, result from their much less severe mechanical design and materials constraints, and the potential for more reliable, failure-free particle removal operation. The Westinghouse Science & Technology Center has proposed a novel moving granular-bed filter concept, the Standleg Moving Granular-Bed Filter (SMGBF) system, that may overcome the inherent deficiencies of the current state-of-the-art moving granular-bed filter technology. The SMGBF is a compact unit that uses cocurrent gas-pellet contacting in an arrangement that greatly simplifies and enhances the distribution of dirty, process gas to the moving bed and allows effective disengagement of clean gas from the moving bed.

Newby, R.A.; Yang, W.C.; Smeltzer, E.E.; Lippert, T.E.; Gasparovic, A.C.; Kittle, W.F.; Schneider, G.N.; Fellers, A.W.

1994-06-01T23:59:59.000Z

409

Overview paper on nuclear power  

SciTech Connect (OSTI)

This paper was prepared as an input to ORNL's Strategic Planning Activity, ORNL National Energy Perspective (ONEP). It is intended to provide historical background on nuclear power, an analysis of the mission of nuclear power, a discussion of the issues, the technology choices, and the suggestion of a strategy for encouraging further growth of nuclear power.

Spiewak, I.; Cope, D.F.

1980-09-01T23:59:59.000Z

410

NUCLEAR DATA RESOURCES FOR ADVANCED ANALYSIS AND SIMULATION.  

SciTech Connect (OSTI)

The mission of the National Nuclear Data Center (NNDC) includes collection, evaluation, and dissemination of nuclear physics data for basic nuclear research and applied nuclear technologies. In 2004, to answer the needs of nuclear data users, NNDC completed a project to modernize storage and management of its databases and began offering new nuclear data Web services. Examples of nuclear reaction, nuclear structure and decay database applications along with a number of nuclear science codes are also presented.

PRITYCHENKO, B.

2006-06-05T23:59:59.000Z

411

Nuclear Science  

Office of Environmental Management (EM)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "of EnergyEnergyENERGY TAXBalanced ScorecardReactor Technology Subcommittee of NEACSummary Nuclear

412

Development of active porous medium filters based on plasma textiles  

SciTech Connect (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 (''plasma shield'') that kills bacterial agents coming in contact with the fabric. The research resulted in the development of a plasma textile that can be used for producing new types of self-decontaminating garments, fabrics, and filter materials, capable of activating a plasma sheath that would filter, capture, and destroy any bacteriological agent deposited on its surface. This new material relies on the unique antimicrobial and catalytic properties of cold (room temperature) plasma that is benign to people and does not cause thermal damage to many polymer textiles, such as Nomex and polypropylene. The uniqueness of cold plasma as a disinfecting agent lies in the inability of bacteria to develop resistance to plasma exposure, as they can for antibiotics. Plasma textiles could thus be utilized for microbial destruction in active antimicrobial filters (for continuous decontamination and disinfection of large amounts of air) as well as in self-decontaminating surfaces and antibacterial barriers (for example, for creating local antiseptic or sterile environments around wounds and burns).

Kuznetsov, Ivan A.; Saveliev, Alexei V.; Rasipuram, Srinivasan; Kuznetsov, Andrey V.; Brown, Alan; Jasper, Warren [Mechanical and Aerospace Engineering, North Carolina State University, Raleigh, NC 27695 (United States); Textile Engineering Chemistry and Science, North Carolina State University, Raleigh, NC 27695 (United States)

2012-05-15T23:59:59.000Z

413

Radiant zone heated particulate filter  

DOE Patents [OSTI]

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

Gonze, Eugene V [Pinckney, MI

2011-12-27T23:59:59.000Z

414

Hot gas cross flow filtering module  

DOE Patents [OSTI]

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

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

1988-01-01T23:59:59.000Z

415

Development of an extended-service coolant filter  

SciTech Connect (OSTI)

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

416

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

417

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

E-Print Network [OSTI]

Sixth American Nuclear Society International Topical Meeting on Nuclear Plant Instrumentation, on CD-ROM, American Nuclear Society, LaGrange Park, IL (2009) FUELASSEMBLY SELF SHIELDING Polytechnic Institute Department of Mechanical, Aerospace and Nuclear Engineering Romanc2@rpi.edu; Danony

Danon, Yaron

418

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

E-Print Network [OSTI]

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

Heljanko, Keijo

419

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

420

A rigid porous filter and filtration method  

SciTech Connect (OSTI)

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

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

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

422

Kalman filter analysis of delayed neutron nondestructive assay measurements.  

SciTech Connect (OSTI)

The ability to nondestructively determine the presence and quantity of fissile and fertile nuclei in various matrices is important in several nuclear applications including international and domestics safeguards, radioactive waste characterization and nuclear facility operations. Material irradiation followed by delayed neutron counting is a well known and useful nondestructive assay technique used to determine the fissile-effective content of assay samples. Previous studies have demonstrated the feasibility of using Kalman filters to unfold individual isotopic contributions to delayed neutron measurements resulting from the assay of mixes of uranium and plutonium isotopes. However, the studies in question used simulated measurement data and idealized parameters. We present the results of the Kalman filter analysis of several measurements of U/Pu mixes taken using Argonne National Laboratory's delayed neutron nondestructive assay device. The results demonstrate the use of Kalman filters as a signal processing tool to determine the fissile and fertile isotopic content of an assay sample from the aggregate delayed neutron response following neutron irradiation.

Aumeier, S. E.

1998-04-29T23:59:59.000Z

423

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

424

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

425

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

SciTech Connect (OSTI)

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

426

ADVANCED HOT GAS FILTER DEVELOPMENT  

SciTech Connect (OSTI)

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

427

Hydrogen Technology Research at SRNL  

SciTech Connect (OSTI)

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

428

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

429

DOE Announces Strategic Engineering and Technology Roadmap for...  

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

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

430

Sandia National Laboratories: SCO2 Brayton Cycle Technology Videos  

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

Energy Systems Laboratory (NESL) Brayton LabSCO2 Brayton Cycle Technology Videos SCO2 Brayton Cycle Technology Videos Tagged with: Advanced Nuclear Energy * Brayton...

431

(Environmental technology)  

SciTech Connect (OSTI)

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

432

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

433

A Brief History of Filter Methods  

E-Print Network [OSTI]

Oct 9, 2006 ... The transition of filter methods to fast local convergence had been an .... iterations. This strategy allows the filter to accept points that would otherwise be rejected. ..... Department of Energy, under Contract W-31-109-ENG-38.

2006-10-10T23:59:59.000Z

434

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

435

An energy recovery filter for HVDC systems  

SciTech Connect (OSTI)

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

436

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

SciTech Connect (OSTI)

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

437

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

438

Evaluated Nuclear Data  

SciTech Connect (OSTI)

This chapter describes the current status of evaluated nuclear data for nuclear technology applications. We start with evaluation procedures for neutron-induced reactions focusing on incident energies from the thermal energy up to 20 MeV, though higher energies are also mentioned. This is followed by examining the status of evaluated neutron data for actinides that play dominant role in most of the applications, followed by coolants/moderators, structural materials and fission products. We then discuss neutron covariance data that characterize uncertainties and correlations. We explain how modern nuclear evaluated data libraries are validated against an extensive set of integral benchmark experiments. Afterwards, we briefly examine other data of importance for nuclear technology, including fission yields, thermal neutron scattering and decay data. A description of three major evaluated nuclear data libraries is provided, including the latest version of the US library ENDF/B-VII.0, European JEFF-3.1 and Japanese JENDL-3.3. A brief introduction is made to current web retrieval systems that allow easy access to a vast amount of up-to-date evaluated nuclear data for nuclear technology applications.

Oblozinsky, P.; Oblozinsky,P.; Herman,M.; Mughabghab,S.F.

2010-10-01T23:59:59.000Z

439

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

440

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...

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

RENDERING FILTERS FOR CONTROLLING DETAIL AND  

E-Print Network [OSTI]

RENDERING FILTERS FOR CONTROLLING DETAIL AND CREATING EFFECTS CHRISTOPHER ROBERT DECORO may be unified under the general theme of the rendering filter. Generally stated, such a filter is a passive, stateless operator that acts upon a decomposition of terms in the rendering equation

442

Electrically heated particulate filter restart strategy  

DOE Patents [OSTI]

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

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

2011-07-12T23:59:59.000Z

443

Mercury Oxidation via Catalytic Barrier Filters Phase II  

SciTech Connect (OSTI)

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

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

2007-09-30T23:59:59.000Z

444

Nuclear Futures Analysis and Scenario Building  

SciTech Connect (OSTI)

This LDRD project created and used advanced analysis capabilities to postulate scenarios and identify issues, externalities, and technologies associated with future ''things nuclear''. ''Things nuclear'' include areas pertaining to nuclear weapons, nuclear materials, and nuclear energy, examined in the context of future domestic and international environments. Analysis tools development included adaptation and expansion of energy, environmental, and economics (E3) models to incorporate a robust description of the nuclear fuel cycle (both current and future technology pathways), creation of a beginning proliferation risk model (coupled to the (E3) model), and extension of traditional first strike stability models to conditions expected to exist in the future (smaller force sizes, multipolar engagement environments, inclusion of actual and latent nuclear weapons (capability)). Accomplishments include scenario development for regional and global nuclear energy, the creation of a beginning nuclear architecture designed to improve the proliferation resistance and environmental performance of the nuclear fuel cycle, and numerous results for future nuclear weapons scenarios.

Arthur, E.D.; Beller, D.; Canavan, G.H.; Krakowski, R.A.; Peterson, P.; Wagner, R.L.

1999-07-09T23:59:59.000Z

445

Filter for a drill string  

DOE Patents [OSTI]

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

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

2007-12-04T23:59:59.000Z

446

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

447

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

448

Hybrid Plasma Reactor/Filter for Transportable Collective Protection Systems  

SciTech Connect (OSTI)

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

449

The development of a porous silicon nitride crossflow filter; Final report, September 1988--September 1992  

SciTech Connect (OSTI)

This report summarizes the work performed in developing a permeable form of silicon nitride for application to ceramic crossflow filters for use in advanced coal-fired electric power plants. The program was sponsored by the Department of Energy Morgantown Energy Technology Center and consisted of a design analysis and material development phase and a filter manufacture and demonstration phase. The crossflow filter design and operating requirements were defined. A filter design meeting the requirements was developed and thermal and stress analyses were performed. Material development efforts focused initially on reaction-bonded silicon nitride material. This approach was not successful, and the materials effort was refocused on the development of a permeable form of sintered silicon nitride (SSN). This effort was successful. The SSN material was used for the second phase of the program, filter manufacture and evaluation. Four half-scale SAN filter modules were fabricated. Three of the modules were qualified for filter performance tests. Tests were performed on two of the three qualified modules in the High-Temperature, High-Pressure facility at the Westinghouse Science and Technology Center. The first module failed on test when it expanded into the clamping device, causing dust leakage through the filter. The second module performed well for a cumulative 150-hr test. It displayed excellent filtration capability during the test. The blowback pulse cleaning was highly effective, and the module apparently withstood the stresses induced by the periodic pulse cleaning. Testing of the module resumed, and when the flow of combustion gas through the filter was doubled, cracks developed and the test was concluded.

NONE

1992-09-01T23:59:59.000Z

450

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

451

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

452

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

453

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

454

Sandia National Laboratories: Nuclear Energy Systems Laboratory...  

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

(NESL) Brayton Lab SCO2 Brayton Cycle Technology Videos Heat Exchanger Development Diffusion Bonding Characterization Mechanical Testing Deep Borehole Disposal Nuclear...

455

2006 NUCLEAR ENERGY RESEARCH INITIATIVE AWARDS  

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

NUCLEAR ENERGY RESEARCH INITIATIVE AWARDS Lead Organization Project Title Collaborators Advanced Fuel Cycle Initiative Massachusetts Institute of Technology The Development and...

456

Design of switched-resistor monolithic filters using NMOS technology  

E-Print Network [OSTI]

MOS Capacitors 19 Parasitics Capacitances on MOS Transrstor 21 10 Typical plot of different value MOS Switch I vs. frequen s of V and W/ gs 23 cy for L = 0. 3 , . 22 SR basic element 25 12 Operation of switched-resistor nique tech- 27..., the individual capac- itors must be closely matched. The drawbacks of this tech- nique are several. First, it requires a large number of taps for interconnections which usually results in an in- crease of chip area. Second, there is an error caused...

Ngo, Dinh Tai

1981-01-01T23:59:59.000Z

457

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...

458

Development of Partial Filter Technology for HDD Retrofit | Department of  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious Rank EERE:YearRound-UpHeat Pump Models |Conduct, Parent CompanyaUSAMP AMD 602SchoolBatteriesNOxEnergy

459

Advanced Particulate Filter Technologies for Direct Injection Gasoline  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious Rank EERE:YearRound-Up fromDepartment of EnergyAdministrative2 DOE2011Department of

460

Demonstrated Petroleum Reduction Using Oil Bypass Filter Technology on  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious Rank EERE:YearRound-UpHeat Pump Models | Department1 Prepared1217 Release Notes Dekkerbegins on K-25'sHeavy

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

Requirements from Particulate Filter Technology for Commercial Vehicles:  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious RankCombustion | Department ofT ib l L dDepartmentnews-flashesEnergyRequestEnergy

462

Filter:Incentives by Eligible Technologies | Open Energy Information  

Open Energy Info (EERE)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home5b9fcbce19 No revision has beenFfe2fb55-352f-473b-a2dd-50ae8b27f0a6Theoretical vs Actual Data LessonType. Retrieved fromEligible

463

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

E-Print Network [OSTI]

Technology Consulting, Germany C.P.C. Wong, M. Friend, General Atomics S. Majumdar, Argonne National Blanket 681癈 616 癈 Mixer He 480癈 660 癈 HX 500 癈 500癈 Outboard to turbine 681癈 500 癈586 癈 681癈

464

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

465

Marine and Hydrokinetic Technology Database  

DOE Data Explorer [Office of Scientific and Technical Information (OSTI)]

DOE抯 Marine and Hydrokinetic Technology Database provides up-to-date information on marine and hydrokinetic renewable energy, both in the U.S. and around the world. The database includes wave, tidal, current, and ocean thermal energy, and contains information on the various energy conversion technologies, companies active in the field, and development of projects in the water. Depending on the needs of the user, the database can present a snapshot of projects in a given region, assess the progress of a certain technology type, or provide a comprehensive view of the entire marine and hydrokinetic energy industry. Results are displayed as a list of technologies, companies, or projects. Data can be filtered by a number of criteria, including country/region, technology type, generation capacity, and technology or project stage. The database was updated in 2009 to include ocean thermal energy technologies, companies, and projects.

466

National Securities Technologies _NSTec_ Livermore Operations...  

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

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

467

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

DOE Patents [OSTI]

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

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

2007-12-18T23:59:59.000Z

468

Monitoring international nuclear activity  

SciTech Connect (OSTI)

The LBNL Table of Isotopes website provides primary nuclearinformation to>150,000 different users annually. We have developedthe covert technology to identify users by IP address and country todetermine the kinds of nuclear information they are retrieving. Wepropose to develop pattern recognition software to provide an earlywarning system to identify Unusual nuclear activity by country or regionSpecific nuclear/radioactive material interests We have monitored nuclearinformation for over two years and provide this information to the FBIand LLNL. Intelligence is gleaned from the website log files. Thisproposal would expand our reporting capabilities.

Firestone, R.B.

2006-05-19T23:59:59.000Z

469

Development of Advanced Particulate Filters  

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

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

470

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

471

Digital Actuator Technology  

SciTech Connect (OSTI)

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 demo