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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.


1

Nuclear Filter Technology | Open Energy Information  

Open Energy Info (EERE)

located in Golden, CO. References Retrieved from "http:en.openei.orgwindex.php?titleNuclearFilterTechnology&oldid379255" Categories: Clean Energy Organizations Companies...

2

Nuclear Science & Technology  

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

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

3

Nuclear Energy Enabling Technologies | Department of Energy  

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

Energy Enabling Technologies Nuclear Energy Enabling Technologies Nuclear Reactor Technologies Fuel Cycle Technologies International Nuclear Energy Policy and Cooperation Nuclear...

4

Plasma Mass Filters For Nuclear Waste Reprocessing  

SciTech Connect

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

Abraham J. Fetterman and Nathaniel J. Fisch

2011-05-26T23:59:59.000Z

5

Oil Bypass Filter Technology Evaluation - Fourth Quarterly Report...  

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

ABSTRACT 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...

6

Nuclear Energy Enabling Technologies | Department of Energy  

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

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

7

Reactor Technology | Nuclear Science | ORNL  

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

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

8

Global Nuclear Security Technology Division (GNSTD)  

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

Systems Nonproliferation Technology Nuclear Material Detection & Characterization Nuclear Security Advanced Technologies Safeguards & Security Technology Threat Reduction...

9

Oil Bypass filter technology evaluation final report  

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

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

10

Nuclear Systems Technology | Nuclear Science | ORNL  

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

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

11

Nuclear Reactors and Technology  

SciTech Connect

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

12

Oil Bypass Filter Technology Evaluation - Second Quarterly Report...  

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

INEELEXT-03-00620 U.S. Department of Energy FreedomCAR & Vehicle Technologies Oil Bypass Filter Technology Evaluation Second Quarterly Report January - March 2003 Larry Zirker...

13

Oil Bypass Filter Technology Evaluation - Fifth Quarterly Report...  

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

INEELEXT-04-01618 U.S. Department of Energy FreedomCAR & Vehicle Technologies Program Oil Bypass Filter Technology Evaluation Fifth Quarterly Report October - December 2003...

14

Oil Bypass Filter Technology Evaluation - Eighth Quarterly Report...  

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

INEELEXT-04-02486 U.S. Department of Energy FreedomCAR & Vehicle Technologies Program Oil Bypass Filter Technology Evaluation Eighth Quarterly Report July-September 2004...

15

Demonstrated Petroleum Reduction Using Oil Bypass Filter Technology...  

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

Energy FreedomCAR & Vehicle Technologies Program Demonstrated Petroleum Reduction Using Oil Bypass Filter Technology on Heavy and Light Vehicles James Francfort (PI) Timothy...

16

Oil Bypass Filter Technology Performance Evaluation - First Quarterly...  

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

INEELEXT-03-00129 U.S. Department of Energy FreedomCAR & Vehicle Technologies Oil Bypass Filter Technology Performance Evaluation First Quarterly Report Larry Zirker James...

17

Oil Bypass Filter Technology Evaluation - Sixth Quarterly Report...  

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

INEELEXT-04-02004 U.S. Department of Energy FreedomCAR & Vehicle Technologies Program Oil Bypass Filter Technology Evaluation Sixth Quarterly Report January - March 2004...

18

Security Science & Technology | Nuclear Science | ORNL  

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

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

19

Nuclear Technology Programs  

SciTech Connect

This document reports on the work done by the Nuclear Technology Programs of the Chemical Technology Division, Argonne National Laboratory, in the period April--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

20

2012 Nuclear Energy Enabling Technology Factsheet | Department...  

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

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

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

GARS | Nuclear Science and Technology Department  

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

Nuclear Science and Technology Department Exploring Nuclear Technologies for Our Energy Future Brookhaven National Laboratory's Department of Nuclear Science and Technology...

22

Defense and nuclear technologies  

SciTech Connect

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

NONE

1995-01-01T23:59:59.000Z

23

Oil Bypass Filter Technology Evaluation - Tenth Quarterly Report...  

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

INLEXT-05-00381 U.S. Department of Energy FreedomCAR & Vehicle Technologies Program Oil Bypass Filter Technology Evaluation Tenth Quarterly Report January-March 2005 TECHNICAL...

24

Oil Bypass Filter Technology Evaluation - Third Quarterly Report...  

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

INEELEXT-03-00974 U.S. Department of Energy FreedomCAR & Vehicle Technologies Oil Bypass Filter Technology Evaluation Third Quarterly Report April-June 2003 Larry Zirker James...

25

Oil Bypass Filter Technology Evaluation - Ninth Quarterly Report...  

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

INLEXT-05-00040 U.S. Department of Energy FreedomCAR & Vehicle Technologies Program Oil Bypass Filter Technology Evaluation Ninth Quarterly Report October-December 2004 TECHNICAL...

26

NUCLEAR RADIATION DOSIMETER USING COMPOSITE FILTER AND A SINGLE ELEMENT FILTER  

DOE Patents (OSTI)

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

Storm, E.; Shlaer, S.

1964-04-21T23:59:59.000Z

27

Nuclear Reactor Technologies | Department of Energy  

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

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

28

Nuclear Waste Management using Electrometallurgical Technology - Nuclear  

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

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

29

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

30

Available Technologies: Island Vane Macroparticle Filter for ...  

Energy Efficiency; Energy Storage and Recovery; Renewable Energy; Environmental Technologies. Monitoring and Imaging; Remediation; Modeling; Imaging ...

31

Nuclear Proliferation Technology Trends Analysis  

SciTech Connect

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

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

2005-10-04T23:59:59.000Z

32

Promethean Boldness - Argonne's Nuclear Science and Technology...  

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

Reactor Argonne Reactor Tree CP-1 70th Anniversary CP-1 70th Anniversary Argonne's Nuclear Science and Technology Legacy Argonne's Nuclear Science and Technology Legacy...

33

Nuclear Reactors and Technology; (USA)  

SciTech Connect

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

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

1991-01-01T23:59:59.000Z

34

Nuclear Energy Enabling Technologies | Department of Energy  

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

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

35

Performance-Based Technology Selection Filter description report  

SciTech Connect

A formal methodology has been developed for identifying technology gaps and assessing innovative or postulated technologies for inclusion in proposed Buried Waste Integrated Demonstration (BWID) remediation systems. Called the Performance-Based Technology Selection Filter, the methodology provides a formalized selection process where technologies and systems are rated and assessments made based on performance measures, and regulatory and technical requirements. The results are auditable, and can be validated with field data. This analysis methodology will be applied to the remedial action of transuranic contaminated waste pits and trenches buried at the Idaho National Engineering Laboratory (INEL).

O' Brien, M.C.; Morrison, J.L.; Morneau, R.A.; Rudin, M.J.; Richardson, J.G.

1992-05-01T23:59:59.000Z

36

Nuclear Reactors and Technology; (USA)  

SciTech Connect

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

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

1991-01-01T23:59:59.000Z

37

University Program in Advanced Technology | National Nuclear...  

National Nuclear Security Administration (NNSA)

University Program in Advanced Technology | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency...

38

Nuclear power high technology colloquium: proceedings  

Science Conference Proceedings (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

39

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

40

Argonne's Nuclear Science and Technology Legacy  

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

Achievements > Argonne's Nuclear Science and Technology Legacy About Director's Welcome Organization Achievements Highlights Fact Sheets, Brochures & Other Documents Multimedia...

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

ADVANCED NUCLEAR TRANSFORMATION TECHNOLOGY SUBCOMMITTEE  

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

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

42

Improved HEPA Filter Technology for Flexible and Rigid Containment Barriers  

SciTech Connect

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

P. A. Pinson

1998-07-01T23:59:59.000Z

43

Program on Technology Innovation: Advanced Filter Concepts: PMScreen  

Science Conference Proceedings (OSTI)

EPRI has been developing technologies to enable power generators to meet more stringent particulate matter (PM) emission requirements for units equipped with underperforming electrostatic precipitators (ESPs). PMScreen makes use of novel filter materials and the electrical charging supplied by the ESP to achieve supplemental PM capture at the ESP outlet at minimal pressure drop. This report summarizes results of slipstream proof-of-concept testing at a power plant site.

2009-03-16T23:59:59.000Z

44

Rugate Technology For Thermophotovoltaic (TPV) Applications: A New Approach To Near Perfect Filter Performance  

Science Conference Proceedings (OSTI)

Rugate filter technology is relatively unknown to the Solar PV? and the TPV community. The objective of this paper is to draw attention to Rugate filters as an enabling technology that may help to realize unprecedented conversion efficiencies in each respective field. Rugate filters are advanced optical interference filters with a continuously varied refractive index that changes periodically in the direction perpendicular to the film plane. The near noise free transmission and reflection quality of these filters

Ugur Ortabasi; Bertrand Bovard

2003-01-01T23:59:59.000Z

45

Production Technology | National Nuclear Security Administration  

National Nuclear Security Administration (NNSA)

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

46

Light Water Reactors Technology Development - Nuclear Reactors  

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

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

47

Nuclear Science and Technology Division - Home page  

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

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

48

Nuclear Systems Technologies - Nuclear Engineering Division ...  

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

Departments involved: Research & Test Reactor | Engineering Development and Applications "Decommissioning of Nuclear Facilities" training courses Argonne Decommissioning Training...

49

WEB RESOURCE: Nuclear Science and Technology  

Science Conference Proceedings (OSTI)

Feb 19, 2007 ... This page offers lecture notes and presentations from a course on nuclear science and technology. Presentation slides and audio files are also...

50

Oil Bypass Filter Technology Performance Evaluation - First Quarterly Report  

DOE Green Energy (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

51

Evaluation of Oil Bypass Filter Technology on Heavy-Duty Vehicles  

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

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

52

The nuclear materials control technology briefing book  

SciTech Connect

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

53

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

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

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

54

Program on Technology Innovation: Nuclear Power Generation Technologies  

Science Conference Proceedings (OSTI)

The United States and other countries are currently planning to expand their nuclear power electrical generation base in order to provide energy security and price stability while reducing greenhouse gas emissions. Since the existing fleet of nuclear plants was built during or before the 1970s, new plants will incorporate more advanced designs. This report documents the current status and potential for advanced nuclear power technology development and/or commercialization over the next 5 to 15 years.

2007-06-20T23:59:59.000Z

55

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

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

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

56

DOE NHI: Progress in Nuclear Connection Technologies  

DOE Green Energy (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

57

Non-Nuclear Energy - Idaho National Laboratory - Technology ...  

Non-Nuclear Energy Cermet Materials, Self-Cleaning Cermet Filters. Related Patents: 6918941; 7,470,393; 7,468,089. Contact: David R. Anderson

58

Nuclear Separations Technologies Workshop Report 2011  

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

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

59

Energy: Nuclear Energy Technology - Symposium @ Northwestern...  

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

12-14, 2011 (http:ses2011.org) Fluid, Thermal and Energy Track Symposium 2.6, Energy: Nuclear Energy Technology Chair: Roger Blomquist Thursday, Oct 13 Time Topic & description...

60

Nuclear Reactor Technologies | Department of Energy  

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

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

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


61

Nuclear Fuel Cycle and Waste Management Technologies - Nuclear Engineering  

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

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

62

Spent Nuclear Fuel Alternative Technology Decision Analysis  

SciTech Connect

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

Shedrow, C.B.

1999-11-29T23:59:59.000Z

63

Current Abstracts Nuclear Reactors and Technology  

SciTech Connect

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

64

Nuclear Power Technology for the Future  

DOE Green Energy (OSTI)

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

Sackett, John I. (ANL)

2003-07-23T23:59:59.000Z

65

Fuel Cycle Science & Technology | Nuclear Science | ORNL  

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

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

66

STATE OF NUCLEAR TECHNOLOGY-JANUARY 1962  

SciTech Connect

Events in nuclear technology in 1961 are reviewed. The SL-1 incident, operation of the Yankee plant, restarting of the Dresden plant, contributions to the state of water reactor technology, transitions to private industry, dry criticality in EBR-II, startup of Los Alamos Molten Plutonium Reactor Experiment (LAMPRE), successful Tory tests, performance of SNAP reactor tests, and use of radioisotope-powered electric source in Transit IV A are discussed. (M.C.G.)

Crewe, A.; Lawreski, S.; Spinrad, B.I.

1961-11-01T23:59:59.000Z

67

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

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

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

68

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

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

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

69

Fuel Cycle Technologies Program - Nuclear Engineering Division...  

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

Nuclear Safety Materials Disposition Decontamination & Decommissioning Nuclear Criticality Safety Nuclear Data Program Nuclear Waste Form Modeling Departments Engineering...

70

The market viability of nuclear hydrogen technologies.  

DOE Green Energy (OSTI)

The Department of Energy Office of Nuclear Energy is supporting system studies 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 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. One of the objectives of the current analysis phase is to determine how nuclear hydrogen technologies could evolve under a number of different futures. The outputs of our work will eventually be used in a larger hydrogen infrastructure and market analysis conducted for DOE-EE using a system-level market simulation tool now underway. This report expands on our previous work by moving beyond simple levelized cost calculations and looking at profitability, risk, and uncertainty from an investor's perspective. We analyze a number of technologies and quantify the value of certain technology and operating characteristics. Our model to assess the profitability of the above technologies is based on Real Options Theory and calculates the discounted profits from investing in each of the production facilities. We use Monte-Carlo simulations to represent the uncertainty in hydrogen and electricity prices. The model computes both the expected value and the distribution of discounted profits from a production plant. We also quantify the value of the option to switch between hydrogen and electricity production in order to maximize investor profits. Uncertainty in electricity and hydrogen prices can be represented with two different stochastic processes: Geometric Brownian Motion (GBM) and Mean Reversion (MR). Our analysis finds that the flexibility to switch between hydrogen and electricity leads to significantly different results in regards to the relative profitability of the different technologies and configurations. This is the case both with a deterministic and a stochastic analysis, as shown in the tables below. The flexibility in output products clearly adds substantial value to the HPE-ALWR and HTE-HTGR plants. In fact, under the GBM assumption for prices, the HTE-HTGR plant becomes more profitable than the SI-HTGR configuration, although SI-HTGR has a much lower levelized cost. For the HTE-HTGR plant it is also profitable to invest in additional electric turbine capacity (Case b) in order to fully utilize the heat from the nuclear reactor for electricity production when this is more profitable than producing hydrogen. The technologies are all at the research and development stage, so there are significant uncertainties regarding the technology cost and performance assumptions used in this analysis. As the technologies advance, the designers need to refine the cost and performance evaluation to provide a more reliable set of input for a more rigorous analysis. In addition, the durability of the catalytic activity of the materials at the hydrogen plant during repetitive price cycling is of prime importance concerning the flexibility of switching from hydrogen to electricity production. However, given the potential significant economic benefit that can be brought from cogeneration with the flexibility to quickly react to market signals, DOE should consider R&D efforts towards developing durable materials and processes that can enable this type of operation. Our future work will focus on analyzing a range of hydrogen production technologies associated with an extension of the financial analysis framework presented here. We are planning to address a variety of additional risks and options, such as the value of modular expansion in addition to the co-generation capability (i.e., a modular increase in the hydrogen production capacity of a plant in a given market with rising hydrogen demand), and contrast that with economies-of-scale of large-unit designs.

Botterud, A.; Conzelmann, G.; Petri, M. C.; Yildiz, B.

2007-04-06T23:59:59.000Z

71

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

Abdou, Mohamed

72

Oil Bypass Filter Technology Evaluation - Seventh Quarterly Report...  

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

Technology Laboratory-WV National Renewable Energy Laboratory Naval Petroleum and Oil Shale Reserves CO, UT, WY Nevada Site Office Nevada Test Site Oak Ridge Institute for...

73

Oil Bypass Filter Technology Evaluation Seventh Quarterly Report...  

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

Technology Laboratory-WV National Renewable Energy Laboratory Naval Petroleum and Oil Shale Reserves CO, UT, WY Nevada Site Office Nevada Test Site Oak Ridge Institute for...

74

Available Technologies: Channelized Filter Inlets or Strippers for ...  

APPLICATIONS OF TECHNOLOGY: Formaldehyde measurement devices; Air pollution monitoring/industrial hygiene; Medical research, e.g., monitoring breath for biomarkers of ...

75

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

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

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

76

NREL: Technology Transfer - NREL Collaborates to Commercialize ...  

Natural gas. Nuclear waste. Nuclear Filter Technology is also licensing several NREL inventions related to the fiber optic and thin film materials that sense the ...

77

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

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

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

78

Nuclear Separations Technologies Workshop Report | Department of Energy  

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

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

79

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

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

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

80

Radiation imaging technology for nuclear materials safeguards  

SciTech Connect

Gamma-ray and neutron imaging technology is emerging as a useful tool for nuclear materials safeguards. Principal applications include improvement in accuracy for nondestructive assay of heterogeneous material (e.g., residues) and wide-area imaging of nuclear material in facilities (e.g., holdup). Portable gamma cameras with gamma-ray spectroscopy are available commercially and are being applied to holdup measurements. The technology has the potential to significantly reduce effort and exposure in holdup campaigns; and, with imaging, some of the limiting assumptions required for conventional holdup analysis can be relaxed, resulting in a more general analysis. Methods to analyze spectroscopic-imaging data to assay plutonium and uranium in processing equipment are being development. Results of holdup measurements using a commercial, portable gamma-cameras are presented. The authors are also developing fast neutron imaging techniques for NDA, search, and holdup. Fast neutron imaging provides a direct measurement of the source of neutrons and is relatively insensitive to surroundings when compared to thermal or epithermal neutron imaging. The technology is well-suited for in-process inventory measurements and verification of materials in interim storage, for which gamma-ray measurements may be inadequate due to self-shielding. Results of numerical simulations to predict the performance of fast-neutron telescopes for safeguards applications are presented.

Prettyman, T.H.; Russo, P.A.; Cheung, C.C.; Christianson, A.D.; Feldman, W.C.; Gavron, A.

1997-12-01T23:59:59.000Z

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.


81

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

Science Conference Proceedings (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 Energys 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 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

82

Performance-Based Technology Selection Filter description report. INEL Buried Waste Integrated Demonstration System Analysis project  

SciTech Connect

A formal methodology has been developed for identifying technology gaps and assessing innovative or postulated technologies for inclusion in proposed Buried Waste Integrated Demonstration (BWID) remediation systems. Called the Performance-Based Technology Selection Filter, the methodology provides a formalized selection process where technologies and systems are rated and assessments made based on performance measures, and regulatory and technical requirements. The results are auditable, and can be validated with field data. This analysis methodology will be applied to the remedial action of transuranic contaminated waste pits and trenches buried at the Idaho National Engineering Laboratory (INEL).

O`Brien, M.C.; Morrison, J.L.; Morneau, R.A.; Rudin, M.J.; Richardson, J.G.

1992-05-01T23:59:59.000Z

83

Oil Bypass Filter Technology Evaluation Ninth Quarterly Report OctoberDecember 2004  

SciTech Connect

This Oil Bypass Filter Technology Evaluation quarterly report (OctoberDecember 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 Energys 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

84

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

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

R&D in the Waste Processing R&D in the Waste Processing Technology Development & Deployment Program Presentation to the DOE High Level Waste Corporate Board July 29, 2009 Al Baione Office of Waste Processing DOE-EM Office of Engineering & Technology 2 Outline Nuclear Safety Research & Development Overview Summary of EM- NSR&D Presentations from February 2009 Evaluating Performance of Nuclear Grade HEPA Filters under Fire/Smoke Challenge Conditions Structural Integrity Initiative for HLW Tanks Pipeline Plugging and Prevention Advanced Mixing Models Basic Science Opportunities in HLW Storage and Processing Safety Cementitious Barriers Partnership 3 Nuclear Safety Research & Development Overview DNFSB 2004-1 identified need for renewed DOE attention to nuclear safety R&D

85

March 2006, Report of the ADVANCED NUCLEAR TRANSFORMATION TECHNOLOGY  

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

March 2006, Report of the ADVANCED NUCLEAR TRANSFORMATION March 2006, Report of the ADVANCED NUCLEAR TRANSFORMATION TECHNOLOGY SUBCOMMITTEE of the NUCLEAR ENERGY RESEARCH ADVISORY COMMITTEE March 2006, Report of the ADVANCED NUCLEAR TRANSFORMATION TECHNOLOGY SUBCOMMITTEE of the NUCLEAR ENERGY RESEARCH ADVISORY COMMITTEE The Global Nuclear Energy Partnership (GNEP) marks a major change in the direction of the DOE's nuclear energy R&D program. It is a coherent plan to test technologies that promise to markedly reduce the problem of nuclear waste treatment and to reduce the proliferation risk in a world with a greatly expanded nuclear power program. It brings the U.S. program into much closer alignment with that of the other major nuclear energy states. GNEP proposes to take spent fuel from existing light water reactors (LWRs),

86

Thomas Miller Office of Nuclear Energy, Science and Technology  

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

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

87

Space nuclear power, propulsion, and related technologies.  

SciTech Connect

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

88

Space nuclear power, propulsion, and related technologies.  

SciTech Connect

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

89

Production Technology | National Nuclear Security Administration  

National Nuclear Security Administration (NNSA)

Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure...

90

Enabling Technologies | National Nuclear Security Administration  

National Nuclear Security Administration (NNSA)

Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure...

91

Future AI and Robotics Technology for Nuclear Plants Decommissioning  

E-Print Network (OSTI)

Robotics Program The Robotics Program within the Nuclear Engineering Division is developing new technologies. Currently, we are exploring opportunities in applications for nuclear reactor operation, maintenance of remote energy installations, decontamination and decommissioning, and minimally invasive surgery

Hu, Huosheng

92

Summary, Long-Term Nuclear Technology Research and Development Plan  

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

In 1998, DOE established the Nuclear Energy Research Advisory Committee (NERAC) to provide advice to the Secretary and to the Director, Office of Nuclear Energy, Science, and Technology (NE), on...

93

Nuclear Separations Technologies Workshop Report | Department of Energy  

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

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

94

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

National Nuclear Security Administration (NNSA)

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

95

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

National Nuclear Security Administration (NNSA)

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

96

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

National Nuclear Security Administration (NNSA)

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

97

Non-Nuclear Energy - Idaho National Laboratory - Technology ...  

Idaho National Laboratory Technologies Available for Licensing ... Non-Nuclear Energy Nanoantenna Electromagnetic Collectors. Related Patents: 7,792,644; 8,071,931; ...

98

Non-Nuclear Energy - Idaho National Laboratory - Technology ...  

Fossil Energy; Information Technology; Manufacturing ; Materials; ... Non-Nuclear Energy Method of Producing Hydrogen. Related Patents: 7153489; 7,665,328; 7078012.

99

Non-Nuclear Energy - Idaho National Laboratory - Technology ...  

Fossil Energy; Information Technology; Manufacturing ... The Idaho National Laboratory is operated for the U.S. Department of Energy's Office of Nuclear Energy, ...

100

New RFID technology tracks and monitors nuclear materials | Argonne...  

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

New RFID technology tracks and monitors nuclear materials By Jared Sagoff * March 24, 2009 Tweet EmailPrint Advancement has applications in many areas involving remote sensing...

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

University Program in Advanced Technology | National Nuclear Security  

National Nuclear Security Administration (NNSA)

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

102

Technologies  

Technologies Materials. Aggregate Spray for Air Particulate; Actuators Made From Nanoporous Materials; Ceramic Filters; Energy Absorbing Material; Diode Arrays for ...

103

January 2003, Report of the ADVANCED NUCLEAR TRANSFORMATION TECHNOLOGY  

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

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

104

NUCLEAR PROPULSION--AN EMERGING TECHNOLOGY  

SciTech Connect

The use of nuclear energy in the space programs is discussed. Nuclear rocket development is reviewed, and the Nevada rocket development station, nuclear electric propulsion and power generation, and advanced research projects are discussed. (J.R.D.)

Finger, H.B.

1963-01-01T23:59:59.000Z

105

Advanced Reactor Development and Technology - Nuclear Engineering...  

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

Capabilities Nuclear Systems Modeling and Design Analysis Reactor Physics and Fuel Cycle Analysis Nuclear Data Program Advanced Reactor Development Overview Advanced Fast Reactor...

106

The Los Alamos nuclear safeguards and nonproliferation technology development program  

SciTech Connect

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

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

1994-04-01T23:59:59.000Z

107

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

National Nuclear Security Administration (NNSA)

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

108

Idaho Nuclear Technology and Engineering Center Tank Farm Facility |  

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

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

109

Observations on A Technology Roadmap for Generation IV Nuclear Energy  

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

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

110

Office of Nuclear Energy, Science and Technology Executive Summary  

E-Print Network (OSTI)

-effective, advanced nuclear plant designs and develop gas-cooled reactor technologies in order to pave the way projects to usher forth next-generation nuclear reactors and fuel cycles based on the results that enable used nuclear fuels to be recycled back into the reactors as fresh fuel. The Advanced Fuel Cycle

111

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

112

Guidance for Deployment of Mobile Technologies for Nuclear Power Plant  

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

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

113

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

114

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

National Nuclear Security Administration (NNSA)

Apply for Our Jobs Our Jobs Working at NNSA Blog Future Science & Technology Programs Home > About Us > Our Programs > Defense Programs > Future Science & Technology Programs...

115

New sensor technology detects chemical, biological, nuclear and explosive  

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

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

116

Transportation Technologies Studies - Nuclear Engineering Division...  

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

Facilities > Computer Facilities > Advanced Computation & Visualization > Transportation Technologies Studies Computer Facilities Overview Advanced Computation & Visualization...

117

Configuration and technology implications of potential nuclear hydrogen system applications.  

DOE Green Energy (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

118

Configuration and technology implications of potential nuclear hydrogen system applications.  

SciTech Connect

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

119

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

SciTech Connect

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

120

Nuclear technology: power to the people  

Science Conference Proceedings (OSTI)

The peaceful application of atomic energy has a special place in independent India's technology development efforts, having been one of the first strategic technologies pursued on a grand scale for the sake of national self-sufficiency. To electrify ...

R. Chidambaram; A. Kakodkar; P. Rodriguez

1994-03-01T23:59:59.000Z

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


121

Program on Technology Innovation: The Next Generation Nuclear Plant  

Science Conference Proceedings (OSTI)

This Technology Update documents the Next Generation Nuclear Plant (NGNP) project, which will demonstrate the design, licensing, construction, and operation of a new nuclear energy source using high-temperature gas-cooled reactor (HTGR) technology. This new non-emitting energy source is applicable to a broad range of uses, from generating electricity to providing high-temperature industrial process heat to producing hydrogen. The NGNP project is sponsored as part of the Energy Policy Act of 2005 and envi...

2008-12-15T23:59:59.000Z

122

October 2003, Report of the ADVANCED NUCLEAR TRANSFORMATION TECHNOLOGY  

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

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

123

October 2006, Report of the ADVANCED NUCLEAR TRANSFORMATION TECHNOLOGY  

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

6, Report of the ADVANCED NUCLEAR TRANSFORMATION 6, Report of the ADVANCED NUCLEAR TRANSFORMATION TECHNOLOGY SUBCOMMITTEE of the NUCLEAR ENERGY RESEARCH ADVISORY COMMITTEE October 2006, Report of the ADVANCED NUCLEAR TRANSFORMATION TECHNOLOGY SUBCOMMITTEE of the NUCLEAR ENERGY RESEARCH ADVISORY COMMITTEE The Global Nuclear Energy Partnership (GNEP) program is still evolving. Since our report of March 22, 2006 the DOE has sought to gauge industry interest in participation in the program from its very beginning. At the time the ANTT committee met, August 30- 31, 2006, responses had not yet been received from industry to the DOE's request for Expressions of Interest. This report is based on the assumption that the program outlined recently, which does not include an Advanced Burner Test Reactor, is what

124

University Program in Advanced Technology | National Nuclear...  

National Nuclear Security Administration (NNSA)

& Technology Programs > Office of Advanced Simulation and Computing and Institutional R&D Programs > Institutional Research & Development > University Program in Advanced...

125

Nuclear Energy - Idaho National Laboratory - Technology Transfer ...  

Nuclear Energy Hydrogen Production Using Reduced Temperature. Related Patents: 8,132,410. Contact: David R. Anderson . Phone: (208) 526-0837 . E-mail: Send E-mail

126

Korea Hydro & Nuclear Power Co., Ltd. Nuclear Power Plants: Construction and Technology Experience  

Science Conference Proceedings (OSTI)

The Korean nuclear power industry has grown rapidly since Kori Unit 1, the first Korean nuclear power plant (NPP), which began operation in April 1978. Following the technology developments of the nuclear power industry in 1980s, the first standard Korean nuclear plants (Ulchin Units 3 and 4) were constructed in the 1990s. At present, 20 NPP units operate in Korea16 pressurized water reactor (PWR) plants and four pressurized heavy water reactor (PHWR) plants; eight PWR units are under construction. This ...

2011-09-21T23:59:59.000Z

127

Advanced Nuclear Technology: Embedded Sensors in Concrete  

Science Conference Proceedings (OSTI)

One of the greatest hindrances to concrete inspection in nuclear power plants is the lack of accessibility to many concrete structures. This report aims to address the use of embedded sensors in future power plants to allow for inspection of inaccessible structures and to facilitate continuous monitoring of the critical concrete structures of the power plants. Monitoring these structures using embedded sensors is especially important because many large concrete structures in nuclear power plants are not ...

2011-11-30T23:59:59.000Z

128

Program on Technology Innovation: Nuclear Power Emergency Power Alternative Technology Investigations  

Science Conference Proceedings (OSTI)

Strategies for the use of advanced electrical energy storage and generation technologies for providing direct current (dc) and alternating current (ac) emergency power for nuclear power plants were investigated and a screening evaluation of these technologies for use in these strategies was conducted. Potential near-term and longer term possibilities were considered in the screening of the technologies that ...

2013-11-13T23:59:59.000Z

129

Cost estimate guidelines for advanced nuclear power technologies  

SciTech Connect

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

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

1990-03-01T23:59:59.000Z

130

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

SciTech Connect

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

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

2005-01-01T23:59:59.000Z

131

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

SciTech Connect

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

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

2005-01-01T23:59:59.000Z

132

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

SciTech Connect

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

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

2005-01-01T23:59:59.000Z

133

Energy: Nuclear Technology Status - Symposium at Northwestern University  

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

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

134

Nuclear Energy Enabling Technologies (NEET) Reactor Materials  

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

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

135

Global Nuclear Energy Partnership Technology Development Plan  

Science Conference Proceedings (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

136

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

137

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

138

Nuclear Criticality Technology and Safety Project parameter study database  

SciTech Connect

A computerized, knowledge-screened, comprehensive database of the nuclear criticality safety documentation has been assembled as part of the Nuclear Criticality Technology and Safety (NCTS) Project. The database is focused on nuclear criticality parameter studies. The database has been computerized using dBASE III Plus and can be used on a personal computer or a workstation. More than 1300 documents have been reviewed by nuclear criticality specialists over the last 5 years to produce over 800 database entries. Nuclear criticality specialists will be able to access the database and retrieve information about topical parameter studies, authors, and chronology. The database places the accumulated knowledge in the nuclear criticality area over the last 50 years at the fingertips of a criticality analyst.

Toffer, H.; Erickson, D.G.; Samuel, T.J. [Westinghouse Hanford Co., Richland, WA (United States); Pearson, J.S. [Lawrence Livermore National Lab., CA (United States)

1993-03-01T23:59:59.000Z

139

Program on Technology Innovation: Advanced Nuclear Technology--Component Margins and Monitoring Database  

Science Conference Proceedings (OSTI)

The Advanced Nuclear Technology Margins and Monitoring Database, available to EPRI members, documents a consensus of experts on issues relating to equipment design margins and monitoring recommendations for large capital, balance-of-plant (BOP) components important to power production.

2008-04-21T23:59:59.000Z

140

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

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

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

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
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141

Executive Summary: Research in Nuclear PowerWorkshop on the Needs of the Next Generation of Nuclear Power Technology  

Science Conference Proceedings (OSTI)

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

A. David Rossin; Kunmo Chung; K. L. Peddicord

142

Analysis of nuclear proliferation resistance reprocessing and recycling technologies  

Science Conference Proceedings (OSTI)

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

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

2011-05-01T23:59:59.000Z

143

Nuclear waste repository transparency technology test bed demonstrations at WIPP  

SciTech Connect

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

144

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

Science Conference Proceedings (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 states perceived loss of energy independence. This paper proposes alternative economic development incentives that could help countries decide to forgo development of sensitive nuclear technologies. The incentives are created through a nuclear-centered industrial complex with symbiotic links to indigenous economic opportunities. This paper also describes a practical tool called the Nuclear Materials Exchange for identifying these opportunities.

David Shropshire

2009-09-01T23:59:59.000Z

145

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

SciTech Connect

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

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

1994-06-01T23:59:59.000Z

146

Proceedings of the Nuclear Criticality Technology and Safety Project Workshop  

Science Conference Proceedings (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

147

Standards in nuclear science and technology. A bibliography  

SciTech Connect

Abstracts of 1803 U. S. and non-U. S. publications concerning a broad range of standards used in nuclear science and technology are included. The publication dates span the period 1962 through 1972, inclusive. Abstracts are arranged chronologically within four categories entitled Reactors and Engineering, Instruments and Calibration, Radiation and Radiation Protection, and Miscellaneous. A subject index is also included. (auth)

1973-09-01T23:59:59.000Z

148

April 2013 Most Viewed Documents for Fission And Nuclear Technologies |  

Office of Scientific and Technical Information (OSTI)

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

149

(Safety and reliability of nuclear power plant technology)  

SciTech Connect

The traveler attended the 16th MPA Seminar on the Safety and Reliability of Plant Technology with Special Emphasis on Nuclear Technology. The objective of the trip was to gather information and data that could prove useful to the US Nuclear Regulatory Commission (USNRC) sponsored Heavy-Section Steel Irradiation (HSSI) and Heavy-Section Steel Technology (HSST) Programs and to present a paper entitled, Effects of Irradiation on Initiation and Crack-Arrest Toughness of Two High-Copper Welds and on Stainless Steel Cladding. This paper summarizes results from the 5th, 6th, and 7th Irradiation Series of experiments performed within the HSSI Program by the Metals and Ceramics Division at Oak Ridge National Laboratory (ORNL).

Dickson, T.L.

1990-10-22T23:59:59.000Z

150

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

SciTech Connect

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

151

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

Science Conference Proceedings (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

152

Nuclear technology programs semiannual progress report, April--September 1989  

SciTech Connect

This document reports on the work done by the Nuclear Technology Program of the Chemical Technology Division, Argonne National Laboratory, in the period April--September 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 developing a process for separating the organic and inorganic constitutents of the red-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. 154 refs., 154 figs., 100 tabs.

Harmon, J.E. (ed.)

1991-08-01T23:59:59.000Z

153

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

Science Conference Proceedings (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

154

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

Science Conference Proceedings (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

155

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

SciTech Connect

This document reports on the work done by the Nuclear Technology Programs of the Chemical Technology Division, Argonne National Laboratory, in the period April--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

156

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

Science Conference Proceedings (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

157

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

SciTech Connect

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

1992-12-01T23:59:59.000Z

158

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

SciTech Connect

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

159

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 of nuclear reactors: current practices in a nutshell Christophe Demazière Department of Applied Physics, Division of Nuclear Engineering, Chalmers University of Technology, SE-412 96 Gothenburg, Sweden Email

Demazière, Christophe

160

New and Underutilized Technology: Air-side Economizers and Filters for Data Centers  

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

The following information outlines key deployment considerations for air-side economizers and filters for data centers within the Federal sector.

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

Program on Technology Innovation: Security Technology Evaluation for New Nuclear Power Plants  

Science Conference Proceedings (OSTI)

This report provides a summary of the state-of-the-art technologies available for perimeter surveillance and intrusion detection systems. These technologies are applicable to the planning and implementation of security measures for the next generation of nuclear power plants. In the absence of intelligence information, the first indication of a potential attack would be from an intrusion into a facility. This intrusion would be detected by a properly designed and deployed perimeter security system. The a...

2007-10-22T23:59:59.000Z

162

Technology Pathways Toward Nuclear Energy in a Sustainable Energy System: Interim Report  

Science Conference Proceedings (OSTI)

This study investigates the potential role of nuclear power and advanced nuclear reactor and fuel system technologies in the context of the global energy system and climate change. It extends the capabilities of an integrated assessment model, and it explores long-term scenarios in which nuclear technology evolves and advances along various pathways, with and without constraints on carbon emissions. Work focuses on how the choice of nuclear fuel cycle, the cost of nuclear technologies, and the presence o...

2005-05-24T23:59:59.000Z

163

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

SciTech Connect

OAK-B135 Development of Advanced Technologies to Reduce Design, Fabrication and Construction for Future Nuclear Power Plants

O' Connell, J. Michael

2002-01-01T23:59:59.000Z

164

September 2013 Most Viewed Documents for Fission And Nuclear Technologies |  

Office of Scientific and Technical Information (OSTI)

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

165

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

166

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

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

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

167

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

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

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

168

History of the Development of NERVA Nuclear Rocket Engine Technology  

Science Conference Proceedings (OSTI)

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

David L. Black

2000-06-04T23:59:59.000Z

169

Nuclear Technology Programs semiannual progress report, April--September 1987  

Science Conference Proceedings (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 1987. Work in applied physical chemistry included 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 storage 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. 15 refs., 60 figs., 40 tabs.

Harmon, J.E. (ed.)

1989-07-01T23:59:59.000Z

170

Nuclear Technology Programs semiannual progress report, October 1987--March 1988  

SciTech Connect

This document reports on the work done by the Nuclear Technology Programs of the Chemical Technology Division, Argonne National Laboratory, in the period October 1987--March 1988. Work in applied physical chemistry included 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.

Harmon, J.E. (ed.)

1990-08-01T23:59:59.000Z

171

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

172

Photofission-Based, Nuclear Material Detection: Technology Demonstration  

SciTech Connect

The Idaho National Engineering and Environmental Laboratory (INEEL), the Los Alamos National Laboratory (LANL), and the Advanced Research and Applications Corporation (ARACOR) [Sunnyvale, California] performed a photonuclear technology demonstration for shielded nuclear material detection during August 2122, 2002, at the LANL TA-18 facility. The demonstration used the Pulsed Photonuclear Assessment Technique (PPAT) that focused on the application of a photofission-based, nuclear material detection method as a viable complement to the ARACOR Eagle inspection platform. The Eagle is a mobile and fully operational truck and cargo inspection system that uses a 6-MeV electron accelerator to perform real-time radiography. This imaging is performed using an approved radiation-safe or cabinet safe operation relative to the operators, inspectors, and any stowaways within the inspected vehicles. While the PPAT has been primarily developed for active interrogation, its neutron detection system also maintains a complete and effective passive detection capability.

Jones, James Litton; Yoon, Woo Yong; Haskell, Kevin James; Norman, Daren Reeve; Moss, C. E.; Goulding, C. A.; Hollas, C. L.; Myers, W. L.; Franco, Ed

2002-12-01T23:59:59.000Z

173

Proceedings of the Nuclear Criticality Technology Safety Workshop  

SciTech Connect

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

174

Ceramic HEPA Filter Program  

SciTech Connect

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

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

2012-04-30T23:59:59.000Z

175

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 organizations and various branches of industry - including the nuclear, financial services and medical sectors configurations will contribute to an improved design, safety, and operation of nuclear reactors. In relation

Lindken, Ralph

176

Program on Technology Innovation: Evaluation of a Commercially Available Harmonic Filter  

Science Conference Proceedings (OSTI)

Emissions tests were conducted to analyze common and differential noise, harmonics, and current draw characteristics in the electrical systems of a typical household. A test setup was constructed to simulate the circuits of this typical household in order to determine how the STETZERiZER Filters might affect the electric currents and voltages these circuits. Testing was performed in a frequency range of 3 kHz - 150 kHz to measure the effect of these filters on power draw and power quality, as ...

2013-10-04T23:59:59.000Z

177

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

SciTech Connect

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

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

2002-09-26T23:59:59.000Z

178

Program on Technology Innovation: Nuclear Energy in a Carbon-Constrained World  

Science Conference Proceedings (OSTI)

This report explores the economic value of advanced nuclear reactor and fuel system technologies in addressing global warming in a carbon-constrained world. Under a range of reasonable assumptions, the projected value of advanced nuclear technology options is in the trillions of dollars even in scenarios that take into account competing technologies such as carbon capture and storage (CCS).

2005-12-14T23:59:59.000Z

179

CERNA WORKING PAPER SERIES What drives innovation in nuclear reactors technologies?  

E-Print Network (OSTI)

, rapidly shifted toward the development of nuclear reactor design technologies especially as NPPs designs evolved toward more standardized technologies (e.g., Light Water Reactors (LWRs)) by the late 1960s (OECD organizations is especially strong for nuclear reactors technology development (OECD/NEA, 2007). 19 Forward

Paris-Sud XI, Université de

180

Technology Insights and Perspectives for Nuclear Fuel Cycle Concepts  

SciTech Connect

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

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

2010-09-01T23:59:59.000Z

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

Bachelor of Science in Nuclear Medicine Technology NAME:________________________________ OLD DOMINION UNIVERSITY UID___________________________________  

E-Print Network (OSTI)

Bachelor of Science in Nuclear Medicine Technology NAME:________________________________ OLD________________________________ Entrance Writing Sample Placement Test:_________________ LOWER DIVISION GENERAL EDUCATION Credits/Grade A____________________ Students must complete the following courses (or equivalent) prior to entering the nuclear medicine

182

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

SciTech Connect

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

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

2006-10-02T23:59:59.000Z

183

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

184

COURSE NOTES: Nuclear Science and Technology Part I/II - TMS  

Science Conference Proceedings (OSTI)

Oct 22, 2007 ... Citation: W. Udo Schrder, "Nuclear Science and Technology Part I/II Chm466/ 566/Phy446/546," University of Rochester, 2007. Access Course

185

Proceedings of the nuclear criticality technology safety project  

SciTech Connect

This document contains summaries of the most of the papers presented at the 1994 Nuclear Criticality Technology Safety Project (NCTSP) meeting, which was held May 10 and 11 at Williamsburg, Va. The meeting was broken up into seven sessions, which covered the following topics: (1) Validation and Application of Calculations; (2) Relevant Experiments for Criticality Safety; (3) Experimental Facilities and Capabilities; (4) Rad-Waste and Weapons Disassembly; (5) Criticality Safety Software and Development; (6) Criticality Safety Studies at Universities; and (7) Training. The minutes and list of participants of the Critical Experiment Needs Identification Workgroup meeting, which was held on May 9 at the same venue, has been included as an appendix. A second appendix contains the names and addresses of all NCTSP meeting participants. Separate abstracts have been indexed to the database for contributions to this proceedings.

Sanchez, R.G. [comp.

1997-06-01T23:59:59.000Z

186

Advanced Vehicle Testing Activity: Oil Bypass Filter  

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

Oil Bypass Filter The Idaho National Laboratory (INL) is evaluating oil bypass filter technology for the U.S. Department of Energy's (DOE's) Vehicle Technologies Office. Eight...

187

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

Office of Science (SC) Website

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

188

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

189

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

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

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

190

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

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

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

191

Girls, choose a career in Nuclear Science and Technology!  

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

'Atomic Fission Fun with the American Nuclear Society', Jan. 26, 2013 Getting to know nuclear energy: the past, the present & the future - free public lecture (Nov. 15, 2012,...

192

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

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

safeguards and nonproliferation, environmental management and waste cleanup, and Navy nuclear propulsion systems development resides outside the Office of Nuclear Energy, Science...

193

Einstein's Letter- Argonne's Nuclear Science and Technology Legacy  

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

Highlights Fact Sheets, Brochures & Other Documents Multimedia Library Visit Argonne Work with Argonne Contact us Nuclear Energy Why Nuclear Energy? Why are some people...

194

Advanced Nuclear Technology: Impact of EPRI Pre-Operational and Operational Configuration Management Report (1022684) on the Nuclear Industry  

Science Conference Proceedings (OSTI)

EPRI Technical Report 1022684, Elements of Pre-Operational and Operational Configuration Management for a New Nuclear Facility, was developed by an EPRI Advanced Nuclear Technology (ANT) technical advisory group whose mission was to develop guidance for establishing a comprehensive configuration management (CM) program for the unique challenges of a new nuclear facility. The program elements developed for the pre-operation phase would then be in place to manage the configuration for the ...

2013-03-20T23:59:59.000Z

195

Design Features and Technology Uncertainties for the Next Generation Nuclear Plant  

Science Conference Proceedings (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

196

Chemical cleaning of porous stainless steel cross-flow filter elements for nuclear waste applications  

Science Conference Proceedings (OSTI)

The Waste Treatment and Immobilization Plant (WTP) currently under construction for treatment of High-Level Waste (HLW) at the Hanford Site will rely on cross-flow ultrafiltration to provide solids-liquid separation as a core part of the treatment process. To optimize process throughput, periodic chemical cleaning of the porous stainless steel filter elements has been incorporated into the design of the plant. It is currently specified that chemical cleaning with nitric acid will occur after significant irreversible membrane fouling is observed. Irreversible fouling is defined as fouling that cannot be removed by backpulsing the filter. PNNL has investigated chemical cleaning processes as part of integrated tests with HLW simulants and with actual Hanford tank wastes. To quantify the effectiveness of chemical cleaning, the residual membrane resistance after cleaning was compared against the initial membrane resistance for each test in a series of long-term fouling tests. The impact of the small amount of residual resistance in these tests could not be separated from other parameters and the historical benchmark of >1 GPM/ft2 for clean water flux was determined to be an adequate metric for chemical cleaning. Using the results from these tests, a process optimization strategy is presented suggesting that for the simulant material under test, the value of chemical cleaning may be suspect. The period of enhanced filtration may not be enough to offset the down time required for chemical cleaning, without respect to the other associated costs.

Billing, Justin M.; Daniel, Richard C.; Hallen, Richard T.; Schonewill, Philip P.; Shimskey, Rick W.; Peterson, Reid A.

2011-05-10T23:59:59.000Z

197

High Energy Nuclear Database: A Testbed for Nuclear Data Information Technology  

SciTech Connect

We describe the development of an on-line high-energy heavy-ion experimental database. When completed, the database will be searchable and cross-indexed with relevant publications, including published detector descriptions. While this effort is relatively new, it will eventually contain all published data from older heavy-ion programs as well as published data from current and future facilities. These data include all measured observables in proton-proton, proton-nucleus and nucleus-nucleus collisions. Once in general use, this database will have tremendous scientific payoff as it makes systematic studies easier and allows simpler benchmarking of theoretical models for a broad range of experiments. Furthermore, there is a growing need for compilations of high-energy nuclear data for applications including stockpile stewardship, technology development for inertial confinement fusion, target and source development for upcoming facilities such as the International Linear Collider and homeland security. This database is part of a larger proposal that includes the production of periodic data evaluations and topical reviews. These reviews would provide an alternative and impartial mechanism to resolve discrepancies between published data from rival experiments and between theory and experiment. Since this database will be a community resource, it requires the high-energy nuclear physics community's financial and manpower support. This project serves as a testbed for the further development of an object-oriented nuclear data format and database system. By using ''off-the-shelf'' software tools and techniques, the system is simple, robust, and extensible. Eventually we envision a ''Grand Unified Nuclear Format'' encapsulating data types used in the ENSDF, ENDF/B, EXFOR, NSR and other formats, including processed data formats.

Brown, D A; Vogt, R; Beck, B; Pruet, J

2007-04-18T23:59:59.000Z

198

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

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

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

199

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  

Science Conference Proceedings (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

200

NUCLEAR SCIENCE AND TECHNOLOGY DIVISION OAK RIDGE NATIONAL LABORATORY  

E-Print Network (OSTI)

, engineering, construction. operation, transmission and distribution of nuclear electricity, decommissioning from $O.Ol/kWh ($1982) at l%/yr to $O.O165/kWh in year 50, decommissioning and nuclear waste reserved Copyright 0 1988 Pergamon Journals Ltd THE NET-ENERGY YIELD OF NUCLEAR POWER GENETYNER SR,~ ROBERT

McDonald, Kirk

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

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

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

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

202

INEEL HEPA Filter Leach System: A Mixed Waste Solution  

SciTech Connect

Calciner operations and the fuel dissolution process at the Idaho National Engineering and Environmental Laboratory have generated many mixed waste high-efficiency particulate air (HEPA) filters. The HEPA Filter Leach System located at the Idaho Nuclear Technology and Engineering Center lowers radiation contamination levels and reduces cadmium, chromium, and mercury concentrations on spent HEPA filter media to below disposal limits set by the Resource Conservation and Recovery Act (RCRA). The treated HEPA filters are disposed as low-level radioactive waste. The technical basis for the existing system was established and optimized in initial studies using simulants in 1992. The treatment concept was validated for EPA approval in 1994 by leaching six New Waste Calcining Facility spent HEPA filters. Post-leach filter media sampling results for all six filters showed that both hazardous and radiological constituent levels were reduced so the filters could be disposed of as low-level radioactive waste. Since the validation tests the HEPA Filter Leach System has processed 78 filters in 1997 and 1998. The Idaho National Engineering and Environmental Laboratory HEPA Filter Leach System is the only mixed waste HEPA treatment system in the DOE complex. This process is of interest to many of the other DOE facilities and commercial companies that have generated mixed waste HEPA filters but currently do not have a treatment option available.

Argyle, Mark Don; Demmer, Ricky Lynn; Archibald, Kip Ernest; Brewer, Ken Neal; Pierson, Kenneth Alan; Shackelford, Kimberlee Rene; Kline, Kelli Suzanne

1999-03-01T23:59:59.000Z

203

INEEL HEPA Filter Leach System: A Mixed Waste Solution  

SciTech Connect

Calciner operations and the fuel dissolution process at the Idaho National Engineering and Environmental Laboratory have generated many mixed waste high-efficiency particulate air (HEPA)filters. The HEPA Filter Leach System located at the Idaho Nuclear Technology and Engineering Center lowers radiation contamination levels and reduces cadmium, chromium, and mercury concentrations on spent HEPA filter media to below disposal limits set by the Resource Conservation and Recovery Act (RCRA). The treated HEPA filters are disposed as low-level radioactive waste. The technical basis for the existing system was established and optimized in initial studies using simulants in 1992. The treatment concept was validated for EPA approval in 1994 by leaching six New Waste Calcining Facility spent HEPA filters. Post-leach filter media sampling results for all six filters showed that both hazardous and radiological constituent levels were reduced so the filters could be disposed of as low-level radioactive waste. Since the validation tests the HEPA Filter Leach System has processed 78 filters in 1997 and 1998. The Idaho National Engineering and Environmental Laboratory HEPA Filter Leach System is the only mixed waste HEPA treatment system in the DOE complex. This process is of interest to many of the other DOE facilities and commercial companies that have generated mixed waste HEPA filters but currently do not have a treatment option available.

K. Archibald; K. Brewer; K. Kline; K. Pierson; K. Shackelford; M. Argyle; R. Demmer

1999-02-01T23:59:59.000Z

204

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

E-Print Network (OSTI)

in Nuclear Science & Engineering ­ Development of novel techniques/tools using particle transport theory including reactors, nuclear security and safeguards systems and medical devices. His work is recognized methodologies with Alireza Haghighat, Nuclear Engineering Program, Mechanical Engineering Department Virginia

Beex, A. A. "Louis"

205

Fusion Nuclear Science | ORNL  

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

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

206

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

E-Print Network (OSTI)

of operating NPP; · NPP decommissioning and waste treatment; · Novel reactor concepts and Nuclear Fuel Cycle

207

Advanced Nuclear Technology: Potential Modification to Source Term Requirements  

Science Conference Proceedings (OSTI)

The U.S. Nuclear Regulatory Commissions Regulatory Guide 1.183 (RG1.183), Alternative Radiological Source Terms for Evaluating Design Basis Accidents at Nuclear Power Reactors describes a method that the staff of the Nuclear Regulatory Commission considers acceptable in complying with alternative source term regulations for design basis accident dose consequence analysis. RG1.183 establishes the alternative source term based onNUREG-1465, Accident ...

2013-03-27T23:59:59.000Z

208

Non-Nuclear Energy - Idaho National Laboratory - Technology ...  

Non-Nuclear Energy Reducing Contact Resistance in Tubular Fuel Cell and Electrolysis Cell Geometry Bundles. Related Patents: 8,389,180. Contact: David R. Anderson

209

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

Office of Scientific and Technical Information (OSTI)

media Xu, Tianfu; Pruess, Karsten (2001) 75 System Definition and Analysis: Power Plant Design and Layout NONE (1996) 68 LWR nuclear fuel bundle data for use in fuel...

210

Dilemmas of Nuclear Materials and Technology: From Los Alamos ...  

Science Conference Proceedings (OSTI)

In the form of nuclear weapons, governments have acquired the capacity to destroy civilization; on the other hand, in the form of electricity-generating plants, ...

211

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

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

and nonproliferation activities, environmental management and waste cleanup, and Navy nuclear propulsion systems development.1 The department has a lead role in insuring that...

212

Program on Technology Innovation: Cladding and Structural Materials for Advanced Nuclear Energy Systems  

Science Conference Proceedings (OSTI)

This EPRI technical update gives an overview of the initial work being done under a 3-year research program on cladding and structural materials for advanced nuclear energy systems. This research is part of EPRI's Program on Technology Innovation.

2008-12-23T23:59:59.000Z

213

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

DOE Green Energy (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

214

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

SciTech Connect

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

215

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

E-Print Network (OSTI)

Entropy and black holes Binney, Prof James ES21 Winter, Emma Balliol The importance of energy storage22 Colman, Jake St Peter's Accelerator driven Nuclear Reactors Jelley, Prof Nick CO38 Cullen, Emma Podsiadlowski, Prof Philipp ES0305 Ghelani, Shanil University The Challenges and Promise of Nuclear Fusion

216

Technology Innovation: Fiber Bragg Gratings for Pressure Monitoring in Nuclear Power Plants  

Science Conference Proceedings (OSTI)

To create a reliable power generation network, emerging nuclear energy reactor designs require reliable pressure-measurement technology that is not presently available. Because of their operating conditions, pressure transducers currently used in the power generation industry offer a limited usable life. An improved transducer design would have the opportunity to improve maintenance efficiencies and reliability. The usable life of current pressure-measurement technology used for nuclear power plant appli...

2012-07-16T23:59:59.000Z

217

Calcined Waste Storage at the Idaho Nuclear Technology and Engineering Center  

Science Conference Proceedings (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 M. C. Swenson

2007-06-01T23:59:59.000Z

218

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 organizations and various branches of industry - including the nuclear, financial services and medical sectors: Better prediction of the flow and heat transfer in liquid metal cooled nuclear reactors will contribute

Lindken, Ralph

219

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

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

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

220

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

National Nuclear Security Administration (NNSA)

Y-12 Earn 11 R&D 100 Awards Jul 2, 2013 US, International Partners Remove Last Remaining HEU from Vietnam, Set Nuclear Security Milestone View All > Timeline Curious about NNSA...

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

Observations on A Technology Roadmap for Generation IV Nuclear...  

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

the U.S. will depend greatly on the continued success of currently operating light water nuclear power plants and the ordering of new installations in the short term. DOE needs to...

222

Welding and Repair Technology Center: Nuclear Weld Overlay Training  

Science Conference Proceedings (OSTI)

A major goal for nuclear utilities is to reduce overall operations and maintenance costs. The Nuclear Weld Overlay Training provided in this report supports this goal by informing member utilities that are preparing for a weld overlay campaign. This technical report reflects EPRIs commitment to serving its members by developing practical tools and guidance in response to specific needs of the industry.ObjectivesThis document is intended to be used by ...

2013-11-27T23:59:59.000Z

223

Cordierite silicon nitride filters  

SciTech Connect

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

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

1992-02-01T23:59:59.000Z

224

The roles and functions of a lunar base Nuclear Technology Center  

SciTech Connect

This paper describes the roles and functions of a special Nuclear Technology Center which is developed as an integral part of a permanent lunar base. Numerous contemporary studies clearly point out that nuclear energy technology will play a major role in any successful lunar/Mars initiative program and in the overall establishment of humanity's solar system civilization. The key role of nuclear energy in the providing power has been recognized. A Nuclear Technology Center developed as part of of a permanent lunar base can also help bring about many other nuclear technology applications, such as producing radioisotopes for self-illumination, food preservation, waste sterilization, and medical treatment; providing thermal energy for mining, materials processing and agricultural; and as a source of emergency habitat power. Designing such a center will involve the deployment, operation, servicing and waste product management and disposal of megawatt class reactor power plants. This challenge must be met with a minimum of direct human support at the facility. Furthermore, to support the timely, efficient integration of this Nuclear Technology Center in the evolving lunar base infrastructure, an analog of such a facility will be needed here on Earth. 12 refs., 4 figs., 1 tab.

Buden, D. (EG and G Idaho, Inc., Idaho Falls, ID (United States)); Angelo, J.A. Jr. (Science Applications International Corp., Melbourne, FL (United States))

1991-01-01T23:59:59.000Z

225

Basis for Section 3116 Determination for the Idaho Nuclear Technology and  

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

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

226

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

SciTech Connect

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

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

1991-02-01T23:59:59.000Z

227

Advanced Technologies for Groundwater Monitoring and Remediation at Nuclear Power Plants  

Science Conference Proceedings (OSTI)

As part of the industry Groundwater Protection Initiative, EPRI has been investigating groundwater monitoring and remediation technologies that have potential for implementation at nuclear power plant sites. This report explores groundwater monitoring and remediation technologies under development or implemented at other industrial and U.S. Department of Energy sites, for both radionuclide and non-radionuclide contaminants. The report documents the potential for development of these technologies for impl...

2008-12-03T23:59:59.000Z

228

Review and Demonstration of Korea Hydro & Nuclear Power (KHNP) Vitrification Technology for Low Level Waste Treatment  

Science Conference Proceedings (OSTI)

Vitrification is the process of stabilizing nuclides in a glass matrix in order to enhance disposal options. A mature technology, vitrification has been applied to high level radioactive waste (HLW) for more than 40 years. As disposal costs and public concern for the environment increase, vitrification is considered to be a promising technology for low level waste (LLW) stabilization. This report covers the characteristics of LLW generated from nuclear power plants, current melter technologies ...

2013-08-14T23:59:59.000Z

229

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

Science Conference Proceedings (OSTI)

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

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

1991-07-01T23:59:59.000Z

230

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.287­298. Biographical notes, energy and temporal distribution of the neutron density throughout the nuclear core depends

Demazière, Christophe

231

Nuclear rocket performance based on Rover/NERVA technology  

Science Conference Proceedings (OSTI)

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

Kirk, W.L.

1990-01-01T23:59:59.000Z

232

Work for the DOE Office of Transportation Technologies - Nuclear  

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

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

233

Advanced Nuclear Technology: Equipment Reliability for New Nuclear Plants: Industry Recommendations for Design  

Science Conference Proceedings (OSTI)

The initial and continued good operating performance of the current build of new nuclear plants is critical to the rebirth of the nuclear option in many countries. Good initial and continued performance is vital to the companies making the large investments required for new nuclear plants. One of the foundations of good performance is a sound process for establishing and sustaining plant equipment reliability (ER).

2010-08-26T23:59:59.000Z

234

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

SciTech Connect

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

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

2011-04-01T23:59:59.000Z

235

ULTRA-COMPACT ACCELERATOR TECHNOLOGIES FOR APPLICATION IN NUCLEAR TECHNIQUES  

Science Conference Proceedings (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

236

Program on Technology Innovation: Nuclear Concrete Structures Aging Reference Manual  

Science Conference Proceedings (OSTI)

EPRI has been proactive in researching concrete degradation in nuclear plants in recent years, with a focus on anticipated future regulatory mandates regarding relicensing beyond 60 years operation (long-term operation). The comprehensive treatment of concrete degradation provided in this report will be used to guide research and development activities. EPRI is currently working to address such issues to benefit the industry and will continue to do so.

2011-10-14T23:59:59.000Z

237

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

E-Print Network (OSTI)

the feasibility of integrating a nuclear power plant with Steam- Assisted Gravity Drainage (SAGD), an oil region enhance the feasibility of using nuclear power plants to meet the energy needs [5]. Both mining Electricity A second production scenario is the cogeneration of thermal power and electricity to meet the #12

238

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

SciTech Connect

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

239

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

SciTech Connect

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

240

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

SciTech Connect

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

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

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

SciTech Connect

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

242

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

SciTech Connect

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

243

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

SciTech Connect

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

244

Nuclear criticality safety evaluation of the passage of decontaminated salt solution from the ITP filters into tank 50H for interim storage  

SciTech Connect

This report assesses the nuclear criticality safety associated with the decontaminated salt solution after passing through the In-Tank Precipitation (ITP) filters, through the stripper columns and into Tank 50H for interim storage until transfer to the Saltstone facility. The criticality safety basis for the ITP process is documented. Criticality safety in the ITP filtrate has been analyzed under normal and process upset conditions. This report evaluates the potential for criticality due to the precipitation or crystallization of fissionable material from solution and an ITP process filter failure in which insoluble material carryover from salt dissolution is present. It is concluded that no single inadvertent error will cause criticality and that the process will remain subcritical under normal and credible abnormal conditions.

Hobbs, D.T.; Davis, J.R.

1994-05-27T23:59:59.000Z

245

Program on Technology Innovation: Summary of 2012 EPRI Nuclear Fuel Cycle Assessment Workshop  

Science Conference Proceedings (OSTI)

Government, industry, and academic stakeholders met at an EPRI-sponsored Nuclear Fuel Cycle Assessment Workshop, held July 2324, 2012, to exchange perspectives, plans, and insights concerning how fuel cycle technology options should be evaluated for the purposes of research, development, and demonstration (RD&D) as well as eventual deployment. The workshop reviewed efforts in the screening and assessment of advanced nuclear fuel cycle options for future energy systems and focused on the ...

2012-12-07T23:59:59.000Z

246

Program on Technology Innovation: An Evaluation of Surface Stress Improvement Technologies for PWSCC Mitigation of Alloy 600 Nuclear Components  

Science Conference Proceedings (OSTI)

This report documents the progress for 2005 on a new project to evaluate surface stress improvement methods to mitigate the initiation of PWSCC in Alloy 600 nuclear plant components. The first potential application for these various surface stress improvement technologies for SCC mitigation in PWR Alloy 600 components was identified as the bottom mounted nozzle (BMN). Mitigation will be demonstrated by creating both sufficient compressive surface stress and depth of the compressive stress on the ID and O...

2006-03-31T23:59:59.000Z

247

Program on Technology Innovation: Manufacture of Large Nuclear and Fossil Components Using Powder Metallurgy and Hot Isostatic Processing Technologies  

Science Conference Proceedings (OSTI)

An alternative manufacturing method, powder metallurgy coupled with hot isostatic processing (PM/HIP), is being explored for the manufacture of large, pressure-retaining components that will be required to meet the demanding needs of nuclear, fossil, combined cycle, ultra-supercritical, and oxy-combustion power applications over the next few decades. This report provides an in-depth review of the new manufacturing process, discusses why the PM/HIP technology is ripe for the power industry to consider, hi...

2012-05-10T23:59:59.000Z

248

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

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

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

249

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

SciTech Connect

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

250

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

SciTech Connect

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

251

Advanced Nuclear Technology: Quality Control of Concrete During Construction - Voids Detection  

Science Conference Proceedings (OSTI)

The main type of degradation of concrete structures during the construction of nuclear power plants has been the existence of honeycombs and voids due to inadequate concrete design and placement. The detection of these honeycombs and voids in concrete structures has been attempted with nondestructive evaluation technologies with limited success. The addition of steel-concrete construction techniques further complicates the ability of these technologies to ...

2012-12-22T23:59:59.000Z

252

Technolog  

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

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

253

Next Generation CANDU Technology: Competitive Design for the Nuclear Renaissance  

SciTech Connect

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

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

2002-07-01T23:59:59.000Z

254

High Efficiency Particulate Air Filters  

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

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

255

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

SciTech Connect

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

256

Innovation in Nuclear Technology for the Least Product Price and Cost  

SciTech Connect

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

Duffey, Romney

2003-09-01T23:59:59.000Z

257

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

Science Conference Proceedings (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

258

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

SciTech Connect

This report describes the results of the work performed by the Technology Transfer Task Team on Modularization. This work was performed as part of the Technology Transfer work being performed under Department of Energy Contract 54-7WM-335406, between December, 1984 and February, 1985. The purpose of this task team effort was to briefly survey the current use of modularization in the nuclear and non-nuclear industries and to assess and evaluate the techniques available for potential application to nuclear power. A key conclusion of the evaluation was that there was a need for a study to establish guidelines for the future development of Light Water Reactor, High Temperature Gas Reactor and Liquid Metal Reactor plants. The guidelines should identify how modularization can improve construction, maintenance, life extension and decommissioning.

1985-06-01T23:59:59.000Z

259

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

SciTech Connect

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

260

High Temperature Electrolysis for Hydrogen Production from Nuclear Energy TechnologySummary  

DOE Green Energy (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

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

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

Office of Scientific and Technical Information (OSTI)

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

262

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

SciTech Connect

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

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

2012-05-15T23:59:59.000Z

263

Advanced Nuclear Technology: Supplier Quality Management for New Nuclear Plant Construction Projects  

Science Conference Proceedings (OSTI)

This report provides guidance for new nuclear power plant construction projects on supplier quality-related risks associated with the procurement of materials, equipment, and services intended for use in a safety-related plant application. This guidance takes an in-depth look into the procurement-related challenges that new construction projects face and at measures for overcoming these challenges. A methodology is provided for identifying, managing, evaluating, and mitigating quality-related risks ...

2013-06-26T23:59:59.000Z

264

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

Science Conference Proceedings (OSTI)

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

Yusibani, Elin [Research Center for Hydrogen Industrial Use and Storage, AIST (Japan); Department of Physics, Universitas Syiah Kuala (Indonesia); Kamil, Insan; Suud, Zaki [Department of Physics, Institut Teknologi Bandung (Indonesia)

2010-06-22T23:59:59.000Z

265

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

E-Print Network (OSTI)

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

Tsutomu Fukuda

2009-10-17T23:59:59.000Z

266

Calcine Waste Storage at the Idaho Nuclear Technology and Engineering Center  

SciTech Connect

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

Staiger, Merle Daniel; M. C. Swenson

2005-01-01T23:59:59.000Z

267

METAL MEDIA FILTERS, AG-1 SECTION FI  

Science Conference Proceedings (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

268

Disposition of Nuclear Waste Using Subcritical Accelerator-Driven Systems: Technology Choices and Implementation Scenarios  

SciTech Connect

Los Alamos National Laboratory has led the development of accelerator-driven transmutation of waste (ATW) to provide an alternative technological solution to the disposition of nuclear waste. While ATW will not eliminate the need for a high-level waste repository, it offers a new technology option for altering the nature of nuclear waste and enhancing the capability of a repository. The basic concept of ATW focuses on reducing the time horizon for the radiological risk from hundreds of thousands of years to a few hundred years and on reducing the thermal loading. As such, ATW will greatly reduce the amount of transuranic elements that will be disposed of in a high-level waste repository. The goal of the ATW nuclear subsystem is to produce three orders of magnitude reduction in the long-term radiotoxicity of the waste sent to a repository, including losses through processing. If the goal is met, the radiotoxicity of ATW-treated waste after 300 yr would be less than that of untreated waste after 100 000 yr.These objectives can be achieved through the use of high neutron fluxes produced in accelerator-driven subcritical systems. While critical fission reactors can produce high neutron fluxes to destroy actinides and select fission products, the effectiveness of the destruction is limited by the criticality requirement. Furthermore, a substantial amount of excess reactivity would have to be supplied initially and compensated for by control poisons. To overcome these intrinsic limitations, we searched for solutions in subcritical systems freed from the criticality requirement by taking advantage of the recent breakthroughs in accelerator technology and the release of liquid lead/bismuth nuclear coolant technology from Russia. The effort led to the selection of an accelerator-driven subcritical system that results in the destruction of the actinides and fission products of concern as well as permitting easy operational control through the external control of the neutron source.

Venneri, Francesco; Williamson, Mark A.; Li Ning; Houts, Michael G.; Morley, Richard A.; Beller, Denis E.; Sailor, William; Lawrence, George [Los Alamos National Laboratory (United States)

2000-10-15T23:59:59.000Z

269

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

Science Conference Proceedings (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

270

Program on Technology Innovation: Comparative Radiological Risk Assessment of Advanced Nuclear Fuel Cycles  

Science Conference Proceedings (OSTI)

The Electric Power Research Institute (EPRI) is working to develop tools to support long-term strategic planning for research, development, and demonstration (RDD) of advanced nuclear fuel cycle technologies for electricity generation. The research described in this EPRI progress report supports the larger decision framework endeavor and intends to provide a standalone usable tool. Two strategic issues are addressed: radioactive and chemical waste management and safety (both radiological and chemical). U...

2012-05-21T23:59:59.000Z

271

Assessment of DC Backup Power Technology Options for Nuclear Power Generation Stations  

Science Conference Proceedings (OSTI)

The March 2011 Fukushima nuclear power plant accident in Japan created a renewed industry interest in examining potential improvements for backup power options to support plant accident scenarios in both near-term and long-term implementation time periods. This report assesses technology options that can be considered in improving DC backup power. Options with near-term applicability were considered and reviewed. Certain energy storage systems and hydrogen power fuel cells were identified that could ...

2013-10-15T23:59:59.000Z

272

Hydrogen Detection in Nuclear Power Plants: Comparison of Potential, Existing, and Innovative Technologies  

Science Conference Proceedings (OSTI)

The ability to monitor hydrogen volumes accurately and quickly within containment environments at nuclear power plants is a critical capability, especially during accident conditions where hydrogen generation may be occurring within the reactor vessel. Since the initial installation of hydrogen monitoring systems in plants following the Three Mile Island accident in 1979, new technologies have been developed and offer performance advantages when compared with existing installed sensors. In addition ...

2013-12-13T23:59:59.000Z

273

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

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

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

274

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

SciTech Connect

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

275

Cermet Filters  

INLs cermet filter is self-cleaning and reduces pollutant emissions, e.g. NOx in vehicles, which can be harmful in heavier duty diesel trucks. This filter lasts far longer compared to other filters because it is self-cleaning, which avoids plugging.

276

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

SciTech Connect

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

277

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

SciTech Connect

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

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

2010-09-21T23:59:59.000Z

278

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

Science Conference Proceedings (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

279

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

SciTech Connect

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

280

Granular filter  

SciTech Connect

The invention described and claimed in this application relates to granular filters and, more particularly, to continuously regenerate granular filters operatable at high temperature and pressure which are particularly suited for cleaning gas used to operate a gas turbine. The filter is of relatively small size and by nature of its operation couples high filtering efficiency with maximum practicable protection to downstream equipment from ash from combustion of the solid fuel and from small particle of the filtering medium entrained in the flowing gas, which would case deposit buildup and erosion to the turbine blades.

Lear, D.E. Jr; Schmid, A.H.; Wigton, H.F.H.

1977-07-12T23:59:59.000Z

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.


281

Nuclear materials control technology in the post-cold war world: Radiation-based methods and information management systems  

SciTech Connect

The end of the cold war is providing both opportunities and requirements for improving the control of nuclear materials around the world. The dismantlement of nuclear weapons and the growth of nuclear power, including the use of plutonium in light water reactors and breeder reactor programs, coupled with enhanced proliferation concerns, drive the need for improved nuclear materials control. We describe nuclear materials control and the role of technology in making controls more effective and efficient. The current use and anticipated development in selected radiation-based methods and related information management systems am described briefly.

Tape, J.W.; Eccleston, G.W.; Ensslin, N.; Markin, J.T.

1993-06-01T23:59:59.000Z

282

Proceedings of seventh symposium on sharing of computer programs and technology in nuclear medicine, computer assisted data processing  

SciTech Connect

The Council on Computers (CC) of the Society of Nuclear Medicine (SNM) annually publishes the Proceedings of its Symposium on the Sharing of Computer Programs and Technology in Nuclear Medicine. This is the seventh such volume and has been organized by topic, with the exception of the invited papers and the discussion following them. An index arranged by author and by subject is included.

Howard, B.Y.; McClain, W.J.; Landay, M. (comps.)

1977-01-01T23:59:59.000Z

283

Development of a Pulp Process Treating Contaminated HEPA Filters (III)  

SciTech Connect

The Pulp Process (PP) Treatment option was conceived as a replacement for the current Filter Leaching System (FLS). The FLS has operated at the Idaho Nuclear Technology and Engineering Center of the Idaho National Engineering and Environmental Laboratory since 1995 to treat radioactive, mixed waste HEPA filters. In recent years, the FLS has exhibited difficulty in removing mercury from the HEPA filters as the concentration of mercury in the spent HEPA filters has increased. The FLS leaches and washes the whole filter without any preparation or modification. The filter media and the trapped calcine particles are confined in a heavy filter housing that contributes to poor mixing zones around the edges of the filter, low media permeability, channeling of the liquid through cracks and tears in the filter media, and liquid retention between leach and rinse cycles. In the PP, the filter media and the trapped calcine particles are separated from the filter housing and treated as a pulp, taking advantage of improved contact with the leach solution that cannot be achieved when the media is still in the HEPA filter housing. In addition to removing the mercury more effectively, the PP generates less volume of liquid waste, requires a shorter leach cycle time, and possesses the versatility for treating filters of different sizes. A series of tests have been performed in the laboratory to demonstrate the advantages of the PP concept. These tests compare the PP with the FLS under controlled conditions that simulate the current operating parameters. A prior study using blended feed, a mixture of shredded clean HEPA filter media and non-radioactive calcine particles, indicated that the PP would significantly increases the calcine dissolution percentages. In this study, hazardous-metal contaminated HEPA filter media was studied. The results of side-by-side tests indicated that the PP increased the mercury removal percentage by 80% and might be a solution to the mercury removal problem encountered by the current FLS. A patent application has been filed for the PP and the patent is pending. In order to validate the PP and collect information for engineering design and economical feasibility studies, pilot plant scale tests are planned.

Hu, J. S.; Ramer, J.; Argyle, M. D.; Demmer, R. L.

2002-02-28T23:59:59.000Z

284

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

SciTech Connect

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

285

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

Science Conference Proceedings (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

286

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

287

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

288

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

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

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

289

An Advanced Reverse Osmosis Technology For Application in Nuclear Desalination Facilities  

SciTech Connect

The lack of adequate supplies of clean, safe water is a growing global problem that has reached crisis proportions in many parts of the world. It is estimated that 1.5 billion people do not have access to adequate supplies of safe water, and that as a result nearly 10,000 people die every day and thousands more suffer from a range of debilitating illnesses due to water related diseases. Included in this total is an estimated 2.2 million child deaths annually. As the world's need for additional sources of fresh water continues to grow, seawater and brackish water desalination are providing an increasingly important contribution to the solution of this problem. Because desalination is an energy intensive process, nuclear desalination provides an economically attractive and environmentally sound alternative to the burning of fossil fuels for desalination. Nevertheless, the enormity of the problem dictates that additional steps must be taken to improve the efficiency of energy utilization and reduce the cost of water production in order to reduce the financial and environmental burden to communities in need. An advanced reverse osmosis (RO) desalination technology has been developed that emphasizes a nontraditional approach to system design and operation, and makes use of a sophisticated design optimization process that can lead to highly optimized design configurations and operating regimes. The technology can be coupled with a nuclear generating station (NGS) to provide an integrated facility for the co-generation of both water and electricity. Waste heat from the NGS allows the use of 'preheated' feedwater into the RO system, improving the efficiency of the RO process and reducing the cost of water production. Because waste heat, rather than process heat, is used the desalination system can be readily coupled to any existing or advanced reactor technology with little or no impact on reactor design and operation and without introducing additional reactor safety considerations. Analyses of nuclear desalination systems employing this advanced RO technology under a variety of seawater feed conditions have consistently shown that the cost of potable water production can be reduced by as much as 15-20% relative to systems designed in a more traditional manner. Demonstration testing has been carried out using a trailer mounted system producing up to 150 m{sup 3}/d of potable water. Experimental results from the demonstration testing are behaving as expected based on the analytical performance models, validating the advanced design concept and confirming that the performance improvements indicated by the analyses can be achieved in operating systems. Further demonstration testing is planned using a 1000 m{sup 3}/d containerized system, currently under design, coupled to an existing nuclear power reactor. (authors)

Humphries, J.R.; Davies, K.; Ackert, J.A. [CANDESAL Technologies Limited, Ottawa (Canada)

2002-07-01T23:59:59.000Z

290

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

SciTech Connect

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; Peng, Yueng Kay Martin [ORNL

1995-01-01T23:59:59.000Z

291

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

292

High-speed hardware efficient FIR compensation filter for Delta-Sigma modulator analog-to-digital converter in 0.13 m CMOS technology  

Science Conference Proceedings (OSTI)

A high-speed hardware efficient 41-tap, 15-bit word length Finite Impulse Response (FIR) Compensation Filter has been designed as a component in a Delta-Sigma Modulator (DSM) Analog-to-Digital Converter (ADC). The filter is targeted for high-throughput ... Keywords: ADC, FIR filter, compensation, delta-sigma, high-speed

Boon-Siang Cheah; Ray Siferd

2005-11-01T23:59:59.000Z

293

Storage of spent fuel from the nation`s nuclear reactors: Status, technology, and policy options  

SciTech Connect

Since the beginning of the commercial nuclear electric power industry, it has been recognized that spent nuclear reactor fuel must be able to be readily removed from the reactor vessel in the plant and safely stored on-site. The need for adjacent ready storage is first for safety. In the event of an emergency, or necessary maintenance that requires the removal of irradiated fuel from the reactor vessel, cooled reserve storage capacity for the full amount of fuel from the reactor core must be available. Also, the uranium fuel in the reactor eventually reaches the point where its heat generation is below the planned efficiency for steam production which drives the turbines and generators. It then must be replaced by fresh uranium fuel, with the ``spent fuel`` elements being removed to a safe and convenient storage location near the reactor vessel. The federal nuclear waste repository program, even without delays in the current schedule of disposal becoming available in 2003, will result in a large percentage of the 111 existing operable commercial reactors requiring expansion of their spent fuel storage capacity. How that need can and will be met raises issues of both technology and policy that will be reviewed in this report.

1989-10-01T23:59:59.000Z

294

Production of Hydrogen by Nuclear Energy - The Enabling Technology for the Hydrogen Economy (A24178)  

E-Print Network (OSTI)

Proc. Of American Nuclear Symposium, Miami, Florida, 2002; To Be PublishedAmerican Nuclear Symposium Miami Florida, US, 2002999608605

Schultz, K.R.

2002-11-06T23:59:59.000Z

295

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

Science Conference Proceedings (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

296

Advanced Nuclear Technology: Equipment Reliability for New Nuclear Plant Projects: Industry Recommendations for Storage, Construction, and Testing  

Science Conference Proceedings (OSTI)

The initial and continued good operating performance of the current build of new nuclear plants is critical to the rebirth of the nuclear option in many countries and vital to the companies making the large investments required for new nuclear plants. One of the foundations of good performance is a sound process for establishing and sustaining plant equipment reliability (ER).

2010-08-26T23:59:59.000Z

297

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

Science Conference Proceedings (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

298

Program on Technology Innovation: A Quantitative Radiological Risk Analysis of the U.S. Once-Through Nuclear Fuel Cycle  

Science Conference Proceedings (OSTI)

EPRI is sponsoring the development of tools to support long-term strategic planning for research, development, and demonstration (RD&D) of nuclear fuel cycle technologies and options. This report describes progress and results to date on the development of a novel comparative risk assessment tool and its application to the baseline once-through nuclear fuel cycle (OTC) in its present incarnation in the United States. An updated detailed description of the U.S. OTC reveals far greater complexity ...

2013-05-30T23:59:59.000Z

299

Accelerator technology for the Los Alamos ATW (accelerator transmutation of nuclear waste) system  

SciTech Connect

The Los Alamos concept for accelerator transmutation of nuclear waste (ATW) employs a high-power proton linear accelerator to generate intense fluxes of thermal neutrons (>10{sup 16} n/cm{sup 2}-s) through spallation on a lead-bismuth target. The nominal beam energy for an ATW accelerator is 1.6 GeV, with average current requirements ranging from 250 mA to 30 mA, depending on application specifics. A recent study of accelerator production of tritium (APT) led to the development of a detailed point design for a 1.6 GeV, 250 mA cw proton linac. The accelerator design was reviewed by the Energy Research Advisory Board (ERAB) and found to be technically sound. The Panel concluded that linac of this power level could now be implemented within the existing technology base, given an adequate component development program and an integrated engineering demonstration of the front end.

Lawrence, G.P.

1991-01-01T23:59:59.000Z

300

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

SciTech Connect

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

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

Calcine Waste Storage at the Idaho Nuclear Technology and Engineering Center  

Science Conference Proceedings (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

302

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

SciTech Connect

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

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

2009-10-12T23:59:59.000Z

303

The Advanced Test Reactor National Scientific User Facility Advancing Nuclear Technology  

Science Conference Proceedings (OSTI)

To help ensure the long-term viability of nuclear energy through a robust and sustained research and development effort, the U.S. Department of Energy (DOE) designated the Advanced Test Reactor and associated post-irradiation examination facilities a National Scientific User Facility (ATR NSUF), allowing broader access to nuclear energy researchers. The mission of the ATR NSUF is to provide access to world-class nuclear research facilities, thereby facilitating the advancement of nuclear science and technology. The ATR NSUF seeks to create an engaged academic and industrial user community that routinely conducts reactor-based research. Cost free access to the ATR and PIE facilities is granted based on technical merit to U.S. university-led experiment teams conducting non-proprietary research. Proposals are selected via independent technical peer review and relevance to DOE mission. Extensive publication of research results is expected as a condition for access. During FY 2008, the first full year of ATR NSUF operation, five university-led experiments were awarded access to the ATR and associated post-irradiation examination facilities. The ATR NSUF has awarded four new experiments in early FY 2009, and anticipates awarding additional experiments in the fall of 2009 as the results of the second 2009 proposal call. As the ATR NSUF program mature over the next two years, the capability to perform irradiation research of increasing complexity will become available. These capabilities include instrumented irradiation experiments and post-irradiation examinations on materials previously irradiated in U.S. reactor material test programs. The ATR critical facility will also be made available to researchers. An important component of the ATR NSUF an education program focused on the reactor-based tools available for resolving nuclear science and technology issues. The ATR NSUF provides education programs including a summer short course, internships, faculty-student team projects and faculty/staff exchanges. In June of 2008, the first week-long ATR NSUF Summer Session was attended by 68 students, university faculty and industry representatives. The Summer Session featured presentations by 19 technical experts from across the country and covered topics including irradiation damage mechanisms, degradation of reactor materials, LWR and gas reactor fuels, and non-destructive evaluation. High impact research results from leveraging the entire research infrastructure, including universities, industry, small business, and the national laboratories. To increase overall research capability, ATR NSUF seeks to form strategic partnerships with university facilities that add significant nuclear research capability to the ATR NSUF and are accessible to all ATR NSUF users. Current partner facilities include the MIT Reactor, the University of Michigan Irradiated Materials Testing Laboratory, the University of Wisconsin Characterization Laboratory, and the University of Nevada, Las Vegas transmission Electron Microscope User Facility. Needs for irradiation of material specimens at tightly controlled temperatures are being met by dedication of a large in-pile pressurized water loop facility for use by ATR NSUF users. Several environmental mechanical testing systems are under construction to determine crack growth rates and fracture toughness on irradiated test systems.

T. R. Allen; J. B. Benson; J. A. Foster; F. M. Marshall; M. K. Meyer; M. C. Thelen

2009-05-01T23:59:59.000Z

304

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

Science Conference Proceedings (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

305

Nuclear power and nuclear weapons  

SciTech Connect

The proliferation of nuclear weapons and the expanded use of nuclear energy for the production of electricity and other peaceful uses are compared. The difference in technologies associated with nuclear weapons and nuclear power plants are described.

Vaughen, V.C.A.

1983-01-01T23:59:59.000Z

306

Nonreactor Nuclear Facilities Division  

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

role in developing science and technology for nuclear power programs, nuclear propulsion, nuclear medicine, and the nation's nuclear weapon program among others. Many...

307

Technologies  

Operated by Lawrence Livermore National Security, LLC, for the Department of Energy's National Nuclear Security Administration

308

Specific filter designs for PFBC  

SciTech Connect

Bubbling bed PFBC technology is currently being demonstrated at commercial scale. Economic and performance improvements in these first generation type PFBC plants can be realized with the application of hot gas particulate filters. Both the secondary cyclone(s) and stack gas ESP(s) could be eliminated saving costs and providing lower system pressure losses. The cleaner gas (basically ash free) provided with the hot gas filter, also permits a wider selection of gas turbines with potentially higher performance. For these bubbling bed PFBC applications, the hot gas filter must operate at temperatures of 1580{degree}F and system pressures of 175 psia (conditions typical of the Tidd PFBC plant). Inlet dust loadings to the filter are estimated to be about 500 to 1000 ppm with mass mean particle diameters ranging from 1.5 to 3 {mu}m. For commercial applications typical of the 70 MW{sub e} Tidd PFBC demonstration unit, the filter must treat up to 56,600 acfm of gas flow. Scaleup of this design to about 320 MW{sub e} would require filtering over 160,000 acfm gas flow. For these commercial scale systems, multiple filter vessels are required. Thus, the filter design should be modular for scaling. An alternative to the bubbling bed PFBC is the circulating bed concept. In this process the hot gas filter will in general be exposed to higher operating temperatures (1650{degree}F) and significantly higher (factor of 10 or more) particle loading.

Lippert, T.E.; Bruck, G.J.; Newby, R.A.; Smeltzer, E.E.

1993-09-01T23:59:59.000Z

309

Ethernet filter  

DOE Patents (OSTI)

This invention is comprised of an apparatus and method that prevents access to unauthorized data in a local area network, such as Ethernet, in which information is transmitted from a transceiver to at least one workstation. Encoded data packets transmitted from the transceiver are filtered by splitting the packet into two signals. One signal contains the data that was transmitted, while the other signal contains tainted data. The filter determines whether a workstation is authorized to access the data, and then delivers either the tainted data to unauthorized workstations, or the data that was transmitted to authorized workstations.

Charney, E.J.; Tanzella, A.J.; Wujcik, J.G.

1990-11-09T23:59:59.000Z

310

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

SciTech Connect

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

311

Nuclear Deployment Scorecards | Department of Energy  

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

Initiatives Nuclear Reactor Technologies Nuclear Deployment Scorecards Nuclear Deployment Scorecards January 1, 2014 Quarterly Nuclear Deployment Scorecard - January 2014 The...

312

Idaho National Laboratory - Technology Transfer - Technologies ...  

Idaho National Laboratory Technologies Available for Licensing ... National Security; Non-Nuclear Energy; Nuclear Energy; Robotics; Transportation;

313

Capabilities - Nuclear Engineering Division (Argonne)  

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

Nuclear Waste Form and Repository Performance Modeling Nuclear Systems Technologies Nuclear Criticality Safety Research Reactor Analysis System Process Monitoring,...

314

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

Science Conference Proceedings (OSTI)

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

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

2012-01-01T23:59:59.000Z

315

Calcined Waste Storage at the Idaho Nuclear Technology and Engineering Center  

Science Conference Proceedings (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

316

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

Science Conference Proceedings (OSTI)

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

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

2004-05-01T23:59:59.000Z

317

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

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

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

318

Idaho National Laboratory - Technology Transfer - Technologies ...  

Idaho National Laboratory Technologies Available for Licensing ... Fossil Energy; Information Technology; Manufacturing ; Materials; National Security; Non-Nuclear ...

319

Cordierite silicon nitride filters. Final report  

SciTech Connect

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

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

1992-02-01T23:59:59.000Z

320

Nuclear Resonance Fluorescence for Nuclear Materials Assay  

E-Print Network (OSTI)

Energy Transmission say for Nuclear Fuel Assemblies 4.1Facilities Spent nuclear fuel is another example wherein intact spent nuclear fuel would be a technological

Quiter, Brian Joseph

2010-01-01T23:59:59.000Z

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.


321

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

DOE Green Energy (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

322

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

SciTech Connect

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

English, R.E.

1986-02-01T23:59:59.000Z

323

Structural Integrity Program for the Calcined Solids Storage Facilities at the Idaho Nuclear Technology and Engineering Center  

SciTech Connect

This report documents the activities of the structural integrity program at the Idaho Nuclear Technology and Engineering Center relevant to the high-level waste Calcined Solids Storage Facilities and associated equipment, as required by DOE M 435.1-1, ''Radioactive Waste Management Manual.'' Based on the evaluation documented in this report, the Calcined Solids Storage Facilities are not leaking and are structurally sound for continued service. Recommendations are provided for continued monitoring of the Calcined Solids Storage Facilities.

Bryant, J.W.; Nenni, J.A.

2003-05-22T23:59:59.000Z

324

Nuclear fuels technologies fiscal year 1998 research and development test plan  

Science Conference Proceedings (OSTI)

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

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

1998-06-01T23:59:59.000Z

325

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

SciTech Connect

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

Ansley, Shannon L.

2002-02-20T23:59:59.000Z

326

Enhanced-safety underground nuclear power plants based on the use of proven ship-building equipment and technology  

SciTech Connect

Investigations performed in the last few years by the State Science Center of the Russian Federation - Academician A. N. Krylov Central Scientific-Research Institute, together with specialized enterprises of the Ministry of Atomic Energy of the Russian Federation, Sudprom, and other agencies of Russia, have shown the promise of marine nuclear power plants for producing underground nuclear power plants with a higher degree of protection from external and internal actions of different intensity. The concept was developed on the basis of an analysis of the energy supply in different regions of Russia and the near-abroad using fossil fuels (lignite, oil, natural gas). The change in the international environment, which makes it possible to convert the military technology, frees the industrial potential and skilled workers in Russia for development of products for the national economy. Stricter international standards and rules for increased safety and protection of nuclear power plants made it necessary to develop a new generation of reactors for ground-based power plants, which under the modern economic conditions cannot be implemented within the time periods acceptable for economics for most of the countries surrounding Russia. In the development of a new generation of ground-based nuclear power plants, the intense improvement of the aviation and space technology must be taken into account. This is connected with the increase in the catastrophes and the threat they present to the safety of unprotected power plants. This article is an abstract of the entire report.

Pashin, V.M.; Petrov, E.L.; Khazov, B.S.

1995-10-01T23:59:59.000Z

327

Technologies  

Weapons & Complex Integration. News Center. News Center. Around the Lab. ... Gamma-Ray Systems; ... for the Department of Energy's National Nuclear Security ...

328

Technologies  

Science & Technology. Weapons & Complex Integration. News Center. News Center. Around the Lab. Contacts. For Reporters. Livermore Lab Report. ...

329

Technologies  

Technologies Energy. Advanced Carbon Aerogels for Energy Applications; Distributed Automated Demand Response; Electrostatic Generator/Motor; Modular Electromechanical ...

330

Technologies  

Technologies Energy, Utilities, & Power Systems. Advanced Carbon Aerogels for Energy Applications; Distributed Automated Demand Response; Electrostatic Generator/Motor

331

Technologies  

Technologies Research Tools. Cell-Free Assembly of NanoLipoprotein Particles; Chemical Prism; Lawrence Livermore Microbial Detection Array (LLMDA) ...

332

Program on Technology Innovation: Information Integration for Equipment Reliability at Nuclear Plants  

Science Conference Proceedings (OSTI)

This report investigates the status of information integration for equipment reliability (ER) at nuclear power plants. ER consists of a comprehensive set of processes that span the organization and require extensive data gathering, retrieval, and information integration. To assist nuclear operators, the Institute of Nuclear Power Operations (INPO) issued AP-913, Equipment Reliability Process Description, as a standard approach to implement effective ER processes among its members. Despite the success tha...

2009-04-30T23:59:59.000Z

333

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

Science Conference Proceedings (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

334

Technologies - Lawrence Livermore National Laboratory  

home \\ technologies. Technologies: Ready-to-Sign Licenses: Software: Patents: Technologies ... for the Department of Energy's National Nuclear Security Administration

335

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

E-Print Network (OSTI)

IEA. "Innovative Nuclear Reactor Development: OpportunitiesIEA. "Innovative Nuclear Reactor Development: OpportunitiesIEA. "Innovative Nuclear Reactor Development: Opportunities

Grigoriadis, Theocharis N

2009-01-01T23:59:59.000Z

336

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

337

Program on Technology Innovation: Controlled Recycling of Contaminated Materials for Nuclear Industry Uses  

Science Conference Proceedings (OSTI)

This report addresses opportunities to recycle materials in radioactive waste by decontamination and fabrication into new components for use in the nuclear industry. In particular, a novel approach called "controlled recycling" involves a procedure that controls the material during decontamination, metal processing and remanufacture into components for reuse in the nuclear industry.

2006-11-09T23:59:59.000Z

338

A Technology Roadmap for Generation IV Nuclear Energy Systems Executive Summary  

SciTech Connect

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.

2003-03-01T23:59:59.000Z

339

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

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

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

340

SRNL - Technology Transfer - Home  

Technology Transfer. Research and Development Savannah River Nuclear Solutions, LLC (SRNS) scientists and engineers develop technologies designed to improve ...

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

Midwest Nuclear Compact (Iowa)  

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

The Midwest Nuclear Compact establishes a Midwest Nuclear Board to cooperatively evaluate and make recommendations regarding the development of nuclear technology, distribute information about...

342

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

SciTech Connect

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

Arthur, E.D.

1993-10-01T23:59:59.000Z

343

Condensate Filter Demineralizer Performance Improvement Program  

Science Conference Proceedings (OSTI)

Upgrading condensate filter demineralizer (CFD) performance poses a complex, challenging utility task. This report summarizes the major factors that impact CFD performance and defines a comprehensive improvement program. In specific, the report discusses hardware, filter media, and operating practices, describing each area in terms of the underlying technology, approach to optimization, and utility experience.

1997-07-21T23:59:59.000Z

344

Technologies  

High Performance Computing (HPC) Technologies; Industrial Partnerships Office P.O. Box 808, L-795 Livermore, CA 94551 Phone: (925) 422-6416 Fax: (925) ...

345

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

346

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

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

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

347

Research and Development in Tritium Technology at the Institute of Radiochemistry, Nuclear Research Center Karlsruhe  

Science Conference Proceedings (OSTI)

Research and Development / Proceedings of the Second National Topical Meeting on Tritium Technology in Fission, Fusion and Isotopic Applications (Dayton, Ohio, April 30 to May 2, 1985)

Prof. Dr. H. J. Ache

348

Use of probabilistic inversion to model qualitative expert input when selecting a new nuclear reactor technology.  

E-Print Network (OSTI)

?? Complex investment decisions by corporate executives often require the comparison of dissimilar attributes and competing technologies. A technique to evaluate qualitative input from experts (more)

Merritt, Charles R., Jr.

2008-01-01T23:59:59.000Z

349

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

E-Print Network (OSTI)

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

Czerniewski, Sarah

2009-01-01T23:59:59.000Z

350

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

DOE Green Energy (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

351

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

SciTech Connect

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

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

2002-06-01T23:59:59.000Z

352

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

E-Print Network (OSTI)

and the economic merits of centralized versus distributed production units. #12;Page 2 Programme B. Nuclear Fuel natural polymers. New marketable advanced materials (using, for example, the concept of nanomaterials

De Cindio, Fiorella

353

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

354

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

E-Print Network (OSTI)

nuclear waste disposal and decommissioning while underminingbetween the cost of decommissioning and nuclear waste

Grigoriadis, Theocharis N

2009-01-01T23:59:59.000Z

355

Advanced Nuclear Technology Advanced Light Water Reactor Utility Requirements Document, Revision 12  

Science Conference Proceedings (OSTI)

The utility requirement document (URD) is an industry-developed technical foundation for the design of advanced light water reactors (ALWRs). It was created with the objective of providing a comprehensive set of plant functional requirements that are considered important to utilities considering the construction of a nuclear plant and in ensuring successful deployment and operation of the plant. The scope of the URD is broad, addressing the entire plant (including the nuclear steam supply system, ...

2013-12-16T23:59:59.000Z

356

Advanced Nuclear Technology: EPRI Utility Requirements Document (URD) Fukushima Lessons-Learned Treatment  

Science Conference Proceedings (OSTI)

The Fukushima accident of March 2011 resulted in critical lessons learned for both current and future nuclear plants. As part of an ongoing review and update of the EPRI Utility Requirements Document (URD) for New Nuclear Plants, a specific review of Fukushima lessons learned was undertaken.This report provides background information on the process for accomplishing the Fukushima review. It also provides the unique changes that were made to the EPRI URD along with specific linkage back ...

2013-12-13T23:59:59.000Z

357

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

358

Filter systems for IGCC applications  

SciTech Connect

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

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

1995-11-01T23:59:59.000Z

359

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

Science Conference Proceedings (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

360

Structural Integrity Program for the Calcined Solids Storage Facilities at the Idaho Nuclear Technology and Engineering Center  

SciTech Connect

This report documents the activities of the structural integrity program at the Idaho Nuclear Technology and Engineering Center relevant to the high-level waste Calcined Solids Storage Facilities and associated equipment, as required by DOE M 435.1-1, ''Radioactive Waste Management Manual.'' Based on the evaluation documented in this report, the Calcined Solids Storage Facilities are not leaking and are structurally sound for continued service. Recommendations are provided for continued monitoring of the Calcined Solids Storage Facilities.

Bryant, J.W.; Nenni, J.A.

2003-05-22T23:59:59.000Z

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.


361

Technology  

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

Technology Computers and the internet play an increasingly larger role in the lives of students. In this activity, students must use various web sites to locate specific pieces of...

362

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

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

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

363

FILTER COMPONENT ASSESSMENT--CERAMIC CANDLES--  

SciTech Connect

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

364

Nuclear Maintenance Applications Center: Establishing an Effective Plant Fluid Sealing Technology Program  

Science Conference Proceedings (OSTI)

This report represents a comprehensive update and revision of the Electric Power Research Institute's (EPRI's) initial fluid sealing technology program guidance, Establishing an Effective Fluid Leak Management Program (TR-114761), which was published in December 2000.

2009-08-13T23:59:59.000Z

365

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

SciTech Connect

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

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

2003-01-01T23:59:59.000Z

366

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

367

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

E-Print Network (OSTI)

and Reprocessing of Spent Nuclear Fuel", Science, Vol. 293,sustainability of the nuclear fuel cycle as well as safetyand Reprocessing of Spent Nuclear Fuel", Science, Vol. 293,

Grigoriadis, Theocharis N

2009-01-01T23:59:59.000Z

368

FUNDAMENTALS IN THE OPERATION OF NUCLEAR TEST REACTORS. VOLUME 1. REACTOR SCIENCE AND TECHNOLOGY  

SciTech Connect

A resume of nuclear physics basic to reactor operation precedes discussion of aspects of reactor physics, engineering, chemistry, metallurgy, instrumentation, control, kinetics, and safety. The object is to provide an approach to and understanding of problems in irradiation test programs in the Materials Testing and Engineering Test Reactors. (D.C.W.)

1963-06-01T23:59:59.000Z

369

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

SciTech Connect

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

370

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

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

371

Storage of spent fuel from the nation's nuclear reactors: Status, technology, and policy options  

SciTech Connect

Since the beginning of the commercial nuclear electric power industry, it has been recognized that spent nuclear reactor fuel must be able to be readily removed from the reactor vessel in the plant and safely stored on-site. The need for adjacent ready storage is first for safety. In the event of an emergency, or necessary maintenance that requires the removal of irradiated fuel from the reactor vessel, cooled reserve storage capacity for the full amount of fuel from the reactor core must be available. Also, the uranium fuel in the reactor eventually reaches the point where its heat generation is below the planned efficiency for steam production which drives the turbines and generators. It then must be replaced by fresh uranium fuel, with the spent fuel'' elements being removed to a safe and convenient storage location near the reactor vessel. The federal nuclear waste repository program, even without delays in the current schedule of disposal becoming available in 2003, will result in a large percentage of the 111 existing operable commercial reactors requiring expansion of their spent fuel storage capacity. How that need can and will be met raises issues of both technology and policy that will be reviewed in this report.

1989-10-01T23:59:59.000Z

372

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

373

Recirculating electric air filter  

DOE Patents (OSTI)

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

Bergman, Werner (Pleasanton, CA)

1986-01-01T23:59:59.000Z

374

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

375

HEPA filter dissolution process  

DOE Patents (OSTI)

This invention is comprised of 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, K.N.; Murphy, J.A.

1992-12-31T23:59:59.000Z

376

The use of filtered bags to increase waste payload capacity  

DOE Green Energy (OSTI)

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

Dustin, D.F.; Thorp, D.T. [Safe Sites of Colorado, Golden, CO (United States); Rivera, M.A. [Los Alamos Technical Associates, Albuquerque, NM (United States)

1998-03-03T23:59:59.000Z

377

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

378

New technology for purging the steam generators of nuclear power plants  

Science Conference Proceedings (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

379

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

SciTech Connect

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

380

Passive and inherent safety technologies for light-water nuclear reactors  

SciTech Connect

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

Forsberg, C.W.

1990-07-01T23:59:59.000Z

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


381

Recapturing Graphite-Based Fuel Element Technology for Nuclear Thermal Propulsion  

SciTech Connect

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

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

2013-01-01T23:59:59.000Z

382

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

SciTech Connect

Safety and Cost Information is developed for the conceptual decommissioning of two representative licensed nuclear research and test reactors. Three decommissioning alternatives are studied to obtain comparisons between costs (in 1981 dollars), occupational radiation doses, potential radiation dose to the public, and other safety impacts. The alternatives considered are: DECON (immediate decontamination), SAFSTOR (safe storage followed by deferred decontamination), and ENTOMB (entombment). The study results are presented in two volumes. Volume 1 (Main Report) contains the results in summary form.

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

1982-03-01T23:59:59.000Z

383

Program on Technology Innovation: EPRI Framework for Assessment of Nuclear Fuel Cycle Options  

Science Conference Proceedings (OSTI)

EPRI is building a suite of tools for assessing nuclear fuel cycle options based on a platform of software, simplified relationships, and explicit decision-making and evaluation guidelines. This report describes a decision-support framework for assembling and structuring information for transparent auditable assessments as well as knowledge capture and transfer.The EPRI framework comprises evaluation and analysis at strategic, tactical, and readiness levels in regard to transformational ...

2013-03-28T23:59:59.000Z

384

Program on Technology Innovation: Nuclear Hydrogen Assessment and Evaluation of SuperGrid Demonstration  

Science Conference Proceedings (OSTI)

The hydrogen economy is a response to concerns about greenhouse gas emissions and the national security consequences of over-reliance on foreign petroleum imports. Hydrogen can replace petroleum as a transportation fuel, yield nothing but water from the tailpipe, and can be produced with little to no greenhouse gas emissions. Nuclear power will play a key role in energizing a future hydrogen economy. A new generation of High Temperature Gas-cooled Reactors (HTGRs) is being developed that can generate el...

2007-12-13T23:59:59.000Z

385

Program on Technology Innovation: A Preliminary Study on Decision Support for the Nuclear Power Industry  

Science Conference Proceedings (OSTI)

License renewals allow many nuclear plants to operate well beyond their originally planned lives. Several studies have encouraged these extensions from economic and environmental perspectives because continuous operation of these plants is more financially feasible than building new ones. The increasing customer demand for electricity can be met by this low-cost energy alternative to fossil fuels, which also reduces CO2. However, extended plant life also presents serious challenges.

2008-07-21T23:59:59.000Z

386

Advanced Nuclear Technology: Final Test Results on 80% Service Test and Implementation Plans  

Science Conference Proceedings (OSTI)

Current practice within the nuclear power industry is to use performance discharge tests for condition monitoring to determine when a battery has reached 80% of its rated capacity, which is considered the end of its service life. A service test is now used every refueling outage to verify that a battery can satisfy its design basis function as defined by the battery duty cycle. A modified performance test is used at ...

2013-04-03T23:59:59.000Z

387

Advanced Nuclear Technology: Regulatory Performance Requirements for Safety-Related Instrumentation, Revision 1  

Science Conference Proceedings (OSTI)

This report proposes an acceptable methodology to apply to safety-related instrumentation to demonstrate 95% probability and 95% confidence (95/95) uncertainties in support of the requirements of Nuclear Regulatory Commission Regulatory Guide (RG) 1.105 Revision 3. This methodology should serve as a means to specify testing and analysis requirements to instrumentation manufacturers and suppliers for their use in meeting the RG 1.105 Revision 3 95% probability and 95% confidence requirements. A ...

2013-08-07T23:59:59.000Z

388

Technology@TMS: Online Article - Materials Technology @ TMS  

Science Conference Proceedings (OSTI)

Mining and extraction technologies; Nuclear reactor systems; Waste ... for used nuclear fuel; Decommissioning, late and early options, and decontamination.

389

Mike Furey | Technology Commercialization and Partnerships  

Nonproliferation & National Security; Nuclear Science & Technology; Technology Commercialization & Partnerships; Sustainable Energy ...

390

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

SciTech Connect

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

Wittenbrock, N. G.

1982-01-01T23:59:59.000Z

391

Developments of Spent Nuclear Fuel Pyroprocessing Technology at Idaho National Laboratory  

SciTech Connect

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

Michael F. Simpson

2012-03-01T23:59:59.000Z

392

ELECTROSTATICALLY ENHANCED BARRIER FILTER COLLECTION  

SciTech Connect

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

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

2003-06-01T23:59:59.000Z

393

The Nuclear Revolution, Relative Gains, and International Nuclear Assistance  

E-Print Network (OSTI)

coupled and complex systems like nuclear weapons arsenals.The complex technology required to build nuclear weapons is

Kroenig, Matthew

2006-01-01T23:59:59.000Z

394

ARRANGEMENT FOR REPLACING FILTERS  

DOE Patents (OSTI)

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

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

1957-08-27T23:59:59.000Z

395

Welding and Repair Technology Center: Assessment of Friction Stir Welding for Nuclear Applications  

Science Conference Proceedings (OSTI)

This report describes a study that was conducted to determine the usability of friction stir welding (FSW) for the repair of nuclear power plant components. The first phase of the study has performinged in air and underwater welding on 304 SS, 308L SS, Alloy182, and Alloy 600 test plates. In addition, crack sealing tests were carried out using electric discharge machining notches in these test plates. A patch seal test was also added to the test matrix to determine if a flat plate could be ...

2012-12-12T23:59:59.000Z

396

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

SciTech Connect

Safety and Cost Information is developed for the conceptual decommissioning of two representative licensed nuclear research and test reactors. Three decommissioning alternatives are studied to obtain comparisons between costs (in 1981 dollars), occupational radiation doses, potential radiation dose to the public, and other safety impacts. The alternatives considered are: DECON (immediate decontamination), SAFSTOR (safe storage followed by deferred decontamination), and 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

397

Use of Modern Digital, Information, and Communication Technologies for Nuclear Power Plant Maintenance Activities  

Science Conference Proceedings (OSTI)

The use of modern digital, information, and communications technology (DT, IT, and CT)) capabilities provides tremendous opportunities for developing beneficial applications for improving plant and human performance in operating plants, including opportunities for replacing aging and obsolete functionality and for providing new support applications. These capabilities can also provide improved functionality that will support the high expectations for the performance of new plants. The Electric Power Rese...

2011-06-21T23:59:59.000Z

398

Engineering Development & Applications - Nuclear Engineering...  

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

Technologies (FCT) Generation IV (Gen IV) Nuclear Energy Program Decontamination and Decommissioning Nuclear Regulatory Research Facilities Environmentally Assisted Cracking...

399

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

SciTech Connect

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

G. Palmiotti

2011-12-01T23:59:59.000Z

400

Modeling, analysis and experiments for fusion nuclear technology: FNT progress report: Modeling and FINESSE  

Science Conference Proceedings (OSTI)

This document is a progress report on two technical studies carried out during 1986, both of which relate to the implementation phase of FNT. The first, which is a follow-up to FINESSE, focuses on specific key questions for: (1) very near-term (0 to 3 years) non-fusion experiments and facilities, and (2) FNT testing in a fusion facility. The second is the initial stage of a detailed effort to develop theory, models and computer codes for predicting the performance of nuclear components. Chapters are presented on (1) introduction and chapter summaries, (2) non-fusion experiments and facilities, (3) fusion testing issues, and (4) theory and modeling. Chapter 2 is an assessment of the relative advantages of many solid breeders, neutron multipliers and configurations. Various issues affecting design and cost of the blanket are examined in Chapter 3. Chapter 4 reports on the progress of the initial stage of an effort to develop theory and analytical and numerical models for nuclear components. A major part of the effort has focused on modeling of MHD effects for liquid metal blankets. Progress has also been made on modeling tritium transport and inventory in solid breeder blankets and the thermomechanical behavior of liquid-metal-cooled limiters. (MOW)

Abdou, M.A.; Tillack, M.S.; Raffray, A.R.; Hadid, A.H.; Bartlit, J.R.; Bell, C.E.C.; Gierszewski, P.J.; Gordon, J.D.; Iizuka, T.; Kim, C.N.

1987-01-01T23:59:59.000Z

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.


401

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

DOE Green Energy (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

402

Rigid porous filter  

DOE Patents (OSTI)

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

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

2000-01-01T23:59:59.000Z

403

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

SciTech Connect

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

1980-12-31T23:59:59.000Z

404

A review of nuclear data needs and their status for fusion reactor technology with some suggestions on a strategy to satisfy the requirements  

Science Conference Proceedings (OSTI)

A review was performed on the needs and status of nuclear data for fusion-reactor technology. Generally, the status of nuclear data for fusion has been improved during the past two decades due to the dedicated effort of the nuclear data developers. However, there are still deficiencies in the nuclear data base, particularly in the areas of activation and neutron scattering cross sections. Activation cross sections were found to be unsatisfactory in 83 of the 153 reactions reviewed. The scattering cross sections for fluorine and boron will need to be improved at energies above 1 MeV. Suggestions concerning a strategy to address the specific fusion nuclear data needs for dosimetry and activation are also provided.

Smith, D.L. (Argonne National Lab., IL (United States)); Cheng, E.T. (TSI Research, Inc., Solana Beach, CA (United States))

1991-09-01T23:59:59.000Z

405

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, whereafter the sections are subsequently combined for the purpose of simultaneously interrogating the sections to detect the presence of a contaminant.

Miley, Harry S. (219 Rockwood Dr., Richland, WA 99352); Thompson, Robert C. (5313 Phoebe La., West Richland, WA 99352); Hubbard, Charles W. (1900 Stevens, Apt. 526, Richland, WA 99352); Perkins, Richard W. (1413 Sunset, Richland, WA 99352)

1997-01-01T23:59:59.000Z

406

Instrumentation and Control, Human System Interface, and Information Technology Requirements Project Plan for Nuclear Power Plant Lo ng-Term Operation  

Science Conference Proceedings (OSTI)

Nuclear power plant owners are looking to extend the operating life of their plants to 80 years and potentially longer. Instrumentation and control, human system interface, and information technologies have changed drastically since the plants were built and will change even more drastically before the plants reach the end of their operating life. A project plan to develop requirements for these technologies is defined here. These requirements will enable plants to better identify future solutions that w...

2010-02-03T23:59:59.000Z

407

HEPA Filter Vulnerability Assessment  

SciTech Connect

This assessment of High Efficiency Particulate Air (HEPA) filter vulnerability was requested by the USDOE Office of River Protection (ORP) to satisfy a DOE-HQ directive to evaluate the effect of filter degradation on the facility authorization basis assumptions. Within the scope of this assessment are ventilation system HEPA filters that are classified as Safety-Class (SC) or Safety-Significant (SS) components that perform an accident mitigation function. The objective of the assessment is to verify whether HEPA filters that perform a safety function during an accident are likely to perform as intended to limit release of hazardous or radioactive materials, considering factors that could degrade the filters. Filter degradation factors considered include aging, wetting of filters, exposure to high temperature, exposure to corrosive or reactive chemicals, and exposure to radiation. Screening and evaluation criteria were developed by a site-wide group of HVAC engineers and HEPA filter experts from published empirical data. For River Protection Project (RPP) filters, the only degradation factor that exceeded the screening threshold was for filter aging. Subsequent evaluation of the effect of filter aging on the filter strength was conducted, and the results were compared with required performance to meet the conditions assumed in the RPP Authorization Basis (AB). It was found that the reduction in filter strength due to aging does not affect the filter performance requirements as specified in the AB. A portion of the HEPA filter vulnerability assessment is being conducted by the ORP and is not part of the scope of this study. The ORP is conducting an assessment of the existing policies and programs relating to maintenance, testing, and change-out of HEPA filters used for SC/SS service. This document presents the results of a HEPA filter vulnerability assessment conducted for the River protection project as requested by the DOE Office of River Protection.

GUSTAVSON, R.D.

2000-05-11T23:59:59.000Z

408

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

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

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

409

Fail Save Shut Off Valve for Filtering Systems Employing Candle Filters  

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

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

410

Climate Change, Nuclear Power and Nuclear  

E-Print Network (OSTI)

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

411

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

E-Print Network (OSTI)

Jose and Mireia Piera. "Nuclear fission sustainability withJose and Mireia Piera. "Nuclear fission sustainability withnuclear energy redistribution in Russia and France; the substitution of fission

Grigoriadis, Theocharis N

2009-01-01T23:59:59.000Z

412

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

SciTech Connect

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

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

2003-08-01T23:59:59.000Z

413

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

SciTech Connect

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

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

2011-07-01T23:59:59.000Z

414

Nanoscale View of Shock Wave Propagation in Single Crystal Fe, W, and Ta for Nuclear Fusion Technology  

Science Conference Proceedings (OSTI)

IFE Design & Technology / Proceedings of the Nineteenth Topical Meeting on the Technology of Fusion Energy (TOFE) (Part 2)

Santiago Cuesta-Lopez; J. M. Perlado

415

Research Areas | Nuclear Science | ORNL  

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

Simulation & Validation Nuclear Systems Technology Reactor Technology Research Highlights Facilities and Capabilities Educational Outreach Publications and Reports News and Awards...

416

Technology Transfer: Available Technologies  

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

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

417

Nuclear Nonproliferation Programs | ORNL  

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

and development to 'boots-on-the-ground' implementation. This work ranges from uranium fuel cycle research to detection technologies and nuclear forensics. The nuclear...

418

QUANTUM STOCHASTIC CALCULUS AND QUANTUM NONLINEAR FILTERING  

E-Print Network (OSTI)

QUANTUM STOCHASTIC CALCULUS AND QUANTUM NONLINEAR FILTERING V. P. BELAVKIN Abstract. A ?­algebraic inde...nite structure of quantum stochastic (QS) cal- culus is introduced and a continuity property...nitely dimensional nuclear space. The class of nondemolition output QS processes in quantum open systems

Belavkin, Viacheslav P.

419

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

Science Conference Proceedings (OSTI)

The ENDF/B-VII.1 library is our latest recommended evaluated nuclear data file for use in nuclear science and technology applications, and incorporates advances made in the five years since the release of ENDF/B-VII.0. These advances focus on neutron cross sections, covariances, fission product yields and decay data, and represent work by the US Cross Section Evaluation Working Group (CSEWG) in nuclear data evaluation that utilizes developments in nuclear theory, modeling, simulation, and experiment. The principal advances in the new library are: (1) An increase in the breadth of neutron reaction cross section coverage, extending from 393 nuclides to 423 nuclides; (2) Covariance uncertainty data for 190 of the most important nuclides, as documented in companion papers in this edition; (3) R-matrix analyses of neutron reactions on light nuclei, including isotopes of He; Li, and Be; (4) Resonance parameter analyses at lower energies and statistical high energy reactions for isotopes of Cl; K; Ti, V, Mn, Cr, Ni, Zr and W; (5) Modifications to thermal neutron reactions on fission products (isotopes of Mo, Tc, Rh, Ag, Cs, Nd, Sm, Eu) and neutron absorber materials (Cd, Gd); (6) Improved minor actinide evaluations for isotopes of U, Np, Pu, and Am (we are not making changes to the major actinides (235,238)U and (239)Pu at this point, except for delayed neutron data and covariances, and instead we intend to update them after a further period of research in experiment and theory), and our adoption of JENDL-4.0 evaluations for isotopes of Cm, Bk, Cf, Es; Fm; and some other minor actinides; (7) Fission energy release evaluations; (8) Fission product yield advances for fission-spectrum neutrons and 14 MeV neutrons incident on (239)Pu; and (9) A new decay data sublibrary. Integral validation testing of the ENDF/B-VII.1 library is provided for a variety of quantities: For nuclear criticality, the VII.1 library maintains the generally-good performance seen for VII.0 for a wide range of MCNP simulations of criticality benchmarks, with improved performance coming from new structural material evaluations, especially for Ti, Mn, Cr, Zr and W. For Be we see some improvements although the fast assembly data appear to be mutually inconsistent. Actinide cross section updates are also assessed through comparisons of fission and capture reaction rate measurements in critical assemblies and fast reactors, and improvements are evident. Maxwellian-averaged capture cross sections at 30 keV are also provided for astrophysics applications. We describe the cross section evaluations that have been updated for ENDF/B-VII.1 and the measured data and calculations that motivated the changes, and therefore this paper augments the ENDF/B-VII.0 publication [H.

Chadwick, M. B. [Los Alamos National Laboratory (LANL); Herman, Micheal W [Brookhaven National Laboratory (BNL); Oblozinsky, Pavel [Brookhaven National Laboratory (BNL); Dunn, Michael E [ORNL; Danon, Y. [Rensselaer Polytechnic Institute (RPI); Kahler, A. [Los Alamos National Laboratory (LANL); Smith, Donald L. [Argonne National Laboratory (ANL); Pritychenko, B [Brookhaven National Laboratory (BNL); Arbanas, Goran [ORNL; Arcilla, r [Brookhaven National Laboratory (BNL); Brewer, R [Los Alamos National Laboratory (LANL); Brown, D A [Brookhaven National Laboratory (BNL); Capote, R. [International Atomic Energy Agency (IAEA); Carlson, A. D. [National Institute of Standards and Technology (NIST); Cho, Y S [Korea Atomic Energy Research Institute; Derrien, Herve [ORNL; Guber, Klaus H [ORNL; Hale, G. M. [Los Alamos National Laboratory (LANL); Hoblit, S [Brookhaven National Laboratory (BNL); Holloway, Shannon T. [Los Alamos National Laboratory (LANL); Johnson, T D [Brookhaven National Laboratory (BNL); Kawano, T. [Los Alamos National Laboratory (LANL); Kiedrowski, B C [Los Alamos National Laboratory (LANL); Kim, H [Korea Atomic Energy Research Institute; Kunieda, S [Los Alamos National Laboratory (LANL); Larson, Nancy M [ORNL; Leal, Luiz C [ORNL; Lestone, J P [Los Alamos National Laboratory (LANL); Little, R C [Los Alamos National Laboratory (LANL); Mccutchan, E A [Brookhaven National Laboratory (BNL); Macfarlane, R E [Los Alamos National Laboratory (LANL); MacInnes, M [Los Alamos National Laboratory (LANL); Matton, C M [Lawrence Livermore National Laboratory (LLNL); Mcknight, R D [Argonne National Laboratory (ANL); Mughabghab, S F [Brookhaven National Laboratory (BNL); Nobre, G P [Brookhaven National Laboratory (BNL); Palmiotti, G [Idaho National Laboratory (INL); Palumbo, A [Brookhaven National Laboratory (BNL); Pigni, Marco T [ORNL; Pronyaev, V. G. [Institute of Physics and Power Engineering (IPPE), Obninsk, Russia; Sayer, Royce O [ORNL; Sonzogni, A A [Brookhaven National Laboratory (BNL); Summers, N C [Lawrence Livermore National Laboratory (LLNL); Talou, P [Los Alamos National Laboratory (LANL); Thompson, I J [Lawrence Livermore National Laboratory (LLNL); Trkov, A. [Jozef Stefan Institute, Slovenia; Vogt, R L [Lawrence Livermore National Laboratory (LLNL); Van der Marck, S S [Nucl Res & Consultancy Grp, Petten, Netherlands; Wallner, A [University of Vienna, Austria; White, M C [Los Alamos National Laboratory (LANL); Wiarda, Dorothea [ORNL; Young, P C [Los Alamos National Laboratory (LANL)

2011-01-01T23:59:59.000Z

420

Cermet Filters To Reduce Diesel Engine Emissions  

DOE Green Energy (OSTI)

Pollution from diesel engines is a significant part of our nation's air-quality problem. Even under the more stringent standards for heavy-duty engines set to take effect in 2004, these engines will continue to emit large amounts of nitrogen oxides and particulate matter, both of which affect public health. To address this problem, the Idaho National Engineering and Environmental Laboratory (INEEL) invented a self-cleaning, high temperature, cermet filter that reduces heavy-duty diesel engine emissions. The main advantage of the INEEL cermet filter, compared to current technology, is its ability to destroy carbon particles and NOx in diesel engine exhaust. As a result, this technology is expected to improve our nation's environmental quality by meeting the need for heavy-duty diesel engine emissions control. This paper describes the cermet filter technology and the initial research and development effort.Diesel engines currently emit soot and NOx that pollute our air. It is expected that the U.S. Environmental Protection Agency (EPA) will begin tightening the regulatory requirements to control these emissions. The INEEL's self-cleaning, high temperature cermet filter provides a technology to clean heavy-duty diesel engine emissions. Under high engine exhaust temperatures, the cermet filter simultaneously removes carbon particles and NOx from the exhaust gas. The cermet filter is made from inexpensive starting materials, via net shape bulk forming and a single-step combustion synthesis process, and can be brazed to existing structures. It is self-cleaning, lightweight, mechanically strong, thermal shock resistant, and has a high melting temperature, high heat capacity, and controllable thermal expansion coefficient. The filter's porosity is controlled to provide high removal efficiency for carbon particulate. It can be made catalytic to oxidize CO, H2, and hydrocarbons, and reduce NOx. When activated by engine exhaust, the filter produces NH3 and light hydrocarbon gases that can effectively destroy the NOx in the exhaust. The following sections describe cermet filter technology and properties of the INEEL filter.

Kong, Peter

2001-08-05T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear filter technology" from the National Library of EnergyBeta (NLEBeta).
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421

Nonlinear image filtering within IDP++  

Science Conference Proceedings (OSTI)

IDP++, image and data processing in C++, is a set of a signal processing libraries written in C++. It is a multi-dimension (up to four dimensions), multi-data type (implemented through templates) signal processing extension to C++. IDP++ takes advantage of the object-oriented compiler technology to provide ``information hiding.`` Users need only know C, not C++. Signals or data sets are treated like any other variable with a defined set of operators and functions. We here some examples of the nonlinear filter library within IDP++. Specifically, the results of MIN, MAX median, {alpha}-trimmed mean, and edge-trimmed mean filters as applied to a real aperture radar (RR) and synthetic aperture radar (SAR) data set.

Lehman, S.K.; Wieting, M.G.; Brase, J.M.

1995-02-09T23:59:59.000Z

422

Nuclear-Renewables Energy System for Hydrogen and Electricity Production  

Science Conference Proceedings (OSTI)

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

Geoffrey Haratyk; Charles W. Forsberg

423

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

424

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

Science Conference Proceedings (OSTI)

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

Holcomb, David Eugene [ORNL

2007-01-01T23:59:59.000Z

425

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

426

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

E-Print Network (OSTI)

The main purpose of this dissertation was to address key issues in the design and analysis of RF/microwave filters for wireless applications. Since RF/microwave filters are one of the bulkiest parts of communication systems, their miniaturization is one of the most important technological challenges for the development of compact transceivers. In this work, novel miniaturization techniques were investigated for single-band, dual-band, ultra-wideband and tunable bandpass filters. In single-band filters, the use of cross-shaped fractals in half-mode substrate-integrated-waveguide bandpass filters resulted in a 37 percent size reduction. A compact bandpass filter that occupies an area of 0.315 mm2 is implemented in 90-nm CMOS technology for 20 GHz applications. For dual-band filters, using half-mode substrate-integrated-waveguides resulted in a filter that is six times smaller than its full-mode counterpart. For ultra-wideband filters, using slow-wave capacitively-loaded coplanar-waveguides resulted in a filter with improved stopband performance and frequency notch, while being 25 percent smaller in size. A major part of this work also dealt with the concept of 'hybrid' RF MEMS tunable filters where packaged, off-the-shelf RF MEMS switches were used to implement high-performance tunable filters using substrate-integrated-waveguide technology. These 'hybrid' filters are very easily fabricated compared to current state-of-the-art RF MEMS tunable filters because they do not require a clean-room facility. Both the full-mode and half-mode substrate-integrated waveguide tunable filters reported in this work have the best Q-factors (93 - 132 and 75 - 140, respectively) compared to any 'hybrid' RF MEMS tunable filter reported in current literature. Also, the half-mode substrate-integrated waveguide tunable filter is 2.5 times smaller than its full-mode counterpart while having similar performance. This dissertation also presented detailed analytical and simulation-based studies of nonlinear noise phenomena induced by Brownian motion in all-pole RF MEMS tunable filters. Two independent mathematical methods are proposed to calculate phase noise in RF MEMS tunable filters: (1) pole-perturbation approach, and (2) admittance-approach. These methods are compared to each other and to harmonic balance noise simulations using the CAD-model of the RF MEMS switch. To account for the switch nonlinearity in the mathematical methods, a nonlinear nodal analysis technique for tunable filters is also presented. In summary, it is shown that output signal-to-noise ratio degradation due to Brownian motion is maximum for low fractional bandwidth, high order and high quality factor RF MEMS tunable filters. Finally, a self-sustained microwave platform to detect the dielectric constant of organic liquids is presented in this dissertation. The main idea is to use a voltage- controlled negative-resistance oscillator whose frequency of oscillation varies according to the organic liquid under test. To make the system self-sustained, the oscillator is embedded in a frequency synthesizer system, which is then digitally interfaced to a computer for calculation of dielectric constant. Such a system has potential uses in a variety of applications in medicine, agriculture and pharmaceuticals.

Sekar, Vikram

2011-08-01T23:59:59.000Z

427

Linear phase compressive filter  

DOE Patents (OSTI)

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

McEwan, Thomas E. (Livermore, CA)

1995-01-01T23:59:59.000Z

428

Nuclear Hydrogen Initiative  

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

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

429

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

E-Print Network (OSTI)

-3 PWR', to be submitted to Nucl. Tech. Bell, G.I. and Glasstone, S. (1970) Nuclear Reactor Theory@nephy.chalmers.se Abstract: A specificity of nuclear reactors is their multiphysics and multiscale character of nuclear reactors and are presented in this paper. The use of such techniques for both time

Demazière, Christophe

430

Evaluation of a Cyclone and Hot Gas Filter System  

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

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

431

Materials Technology @ TMS  

Science Conference Proceedings (OSTI)

ESTABLISHED MATERIALS TECHNOLOGIES ... Specifically, digital resources are available relating to materials for nuclear power, materials sustainability, and ...

432

Filter holder and gasket assembly for candle or tube filters  

DOE Patents (OSTI)

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

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

1999-03-02T23:59:59.000Z

433

Moving granular-bed filter development program. Topical report  

Science Conference Proceedings (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

434

Nuclear Isotopic Dilution of Highly-Enriched Uranium-235 and Uranium-233 by Dry Blending via the RM-2 Mill Technology  

SciTech Connect

The United States Department of Energy has initiated numerous activities to identify strategies to disposition various excess fissile materials. Two such materials are the off-specification highly enriched uranium-235 oxide powder and the uranium-233 contained in unirradiated nuclear fuel both currently stored at the Idaho National Engineering and Environmental Laboratory. This report describes the development of a technology that could dilute these materials to levels categorized as low-enriched uranium, or further dilute the materials to a level categorized as waste. This dilution technology opens additional pathways for the disposition of these excess fissile materials as existing processing infrastructure continues to be retired.

N. A. Chipman; R. N. Henry; R. K. Rajamani; S. Latchireddi; V. Devrani; H. Sethi; J. L. Malhotra

2004-02-01T23:59:59.000Z

435

Global Nuclear Energy Partnership Fact Sheet - Develop Enhanced Nuclear  

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

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

436

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

SciTech Connect

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

Bergman, W. [Lawrence Livermore National Lab., CA (United States); First, M.W. [Harvard School of Public Health, Boston, MA (United States); Anderson, W.L. [Consultant, LaPlata, MD (United States); Gilbert, H. [Consultant, McLean, VA (United States); Jacox, J.W. [Consultant, Columbus, OH (United States)

1994-12-01T23:59:59.000Z

437

Environmentally Assisted Cracking: Nuclear  

Science Conference Proceedings (OSTI)

About this Symposium. Meeting, Materials Science & Technology 2014. Symposium, Environmentally Assisted Cracking: Nuclear. Sponsorship. Organizer(s)...

438

WIPP Nuclear Facilities Transparency  

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

Transparency Technologies Other Transparency Activities Sandia National Laboratories Cooperative Monitoring Center (CMC) in conjunction with WIPP is providing this Nuclear...

439

In-place HEPA filter penetration test  

SciTech Connect

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

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

1997-01-01T23:59:59.000Z

440

Advanced Nuclear Technology: EPRI Materials Management Matrix ProjectToshiba Advanced Boiling Water Reactor Materials Managem ent Table Report, Revision 0  

Science Conference Proceedings (OSTI)

Experience gained through years of operating nuclear plants has shown that materials performance issues can be a significant concern related to economic and safe long-term plant operations. Although concerns remain, industry efforts to address materials performance issues at operating plants have led to several important advances in both the underlying scientific understanding of materials degradation and the implementation of practical mitigation and management technologies. The Electric Power Research...

2010-02-09T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear filter technology" from the National Library of EnergyBeta (NLEBeta).
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to obtain the most current and comprehensive results.


441

Technology Commercialization and Partnerships | BSA 07-32 ...  

Nonproliferation & National Security; Nuclear Science & Technology; Technology Commercialization & Partnerships; Sustainable Energy ...

442

Electrostatic precipitators vs. fabric filters: A symposium and debate  

SciTech Connect

Nine papers were presented at the Electrostatic Precipitators vs. Fabric Filters: A Symposium and Debate held March 22, 1994 at the Sheraton Crystal City Hotel in Arlington, Virginia. The Symposium was intended to take a frank look at the comparative advantages of electrostatic precipitators and fabric filters. A separate abstract was prepared for each paper for inclusion in the Energy Science and Technology Database.

1994-12-31T23:59:59.000Z

443

Development of Technologies on Innovative-Simplified Nuclear Power Plant Using High-Efficiency Steam Injectors (9) System Outline and Endurance Test of Low-Pressure Steam Injectors  

Science Conference Proceedings (OSTI)

A Steam Injector (SI) is a simple, compact and passive pump and also acts as a high-performance direct-contact compact heater. This provides SI with capability to serve also as a direct-contact feedwater heater that heats up feedwater by using extracted steam from the turbine. We are developing technology for 'Innovative Simplified Nuclear Power Plants' in order to further improve the economy and safety of nuclear power plants. Our technology development aims to significantly simplify equipment and reduce physical quantities by applying 'High-Efficiency SI', which are applicable to a wide range of operation regimes beyond the performance and applicable range of existing SIs and enables unprecedented multistage and parallel operation, to the low-pressure feedwater heaters and Emergency Core Cooling Systems (ECCS) of nuclear power plants, as well as achieve high inherent safety to prevent severe accidents by keeping the core covered with water (a Severe Accident-Free Concept). The innovative-simplified nuclear power plant consists of a simplified feedwater heating system, a passive core injection system and a passive containment cooling system. This report describes the results of the endurance and performance tests of low-pressure SIs for feedwater heaters with Jet-deaerator and core injection system. A part of this report are fruits of research which is carried out by Tokyo Electric Power Company (TEPCO), Toshiba, and 7 Universities in Japan, funded from the Ministry of Economy, Trade and Industry (METI) of Japan as the national public research-funded program. (authors)

Shuichi Ohmori; Michitsugu Mori; Shoji Goto [Tokyo Electric Power Company (Japan); Tadashi Narabayashi [Hokkaido University, Kita-ku, Sapporo (Japan); Chikako Iwaki; Yutaka Asanuma [Toshiba Corporation (Japan)

2006-07-01T23:59:59.000Z

444

Architectural implications of spatial thermal filtering  

Science Conference Proceedings (OSTI)

Process technology scaling, lagging supply voltage scaling, and the resulting exponential increase in power density, have made temperature a first-class design constraint in today's microprocessors. Prior work has shown that the silicon substrate acts ... Keywords: Aspect ratio, Granularity, Many-core, Spatial filtering, Temperature, Thermal management

Karthik Sankaranarayanan; Brett H. Meyer; Wei Huang; Robert Ribando; Hossein Haj-Hariri; Mircea R. Stan; Kevin Skadron

2013-01-01T23:59:59.000Z

445

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

446

Sintered composite filter  

DOE Patents (OSTI)

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

Bergman, W.

1986-05-02T23:59:59.000Z

447

Available Technologies: Two Synergistic Pharmacons for ...  

APPLICATIONS OF TECHNOLOGY: Treatment of radionuclide exposure from . Nuclear power plants; Mining; Nuclear research; Military or homeland security ...

448

Future Directions [Irradiation Performance] - Nuclear Engineering...  

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

Achievements Awards Patents Argonne Distinguished Fellows Professional Societies About Nuclear Energy Reactors Designed by Argonne Argonne's Nuclear Science and Technology...

449

Other Current Activities [Irradiation Performance] - Nuclear...  

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

Achievements Awards Patents Argonne Distinguished Fellows Professional Societies About Nuclear Energy Reactors Designed by Argonne Argonne's Nuclear Science and Technology...

450

Isotope Development & Production | Nuclear Science | ORNL  

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Medical Radioisotope Radiochemical Separation & Processing Strategic Isotope Production Super Heavy Element Discovery Nuclear Security Science & Technology Nuclear Systems...

451

Diagnostic and Advisory Systems - Nuclear Engineering Division...  

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Diagnostic and Advisory Systems Capabilities Nuclear Systems Technologies Nuclear Criticality Safety Research Reactor Analysis Decontamination and Decommissioning SystemsProcess...

452

Artificial Intelligence / Expert Systems Expertise - Nuclear...  

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

Intelligence Expert Systems Expertise Capabilities Nuclear Systems Technologies Nuclear Criticality Safety Research Reactor Analysis Decontamination and Decommissioning...