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Note: This page contains sample records for the topic "reactors laboratory field" 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

Ames Laboratory Research Reactor Facility Ames, Iowa  

Office of Legacy Management (LM)

,, *' ; . Final Radiological Condition of the Ames Laboratory Research Reactor Facility Ames, Iowa _, . AGENCY: Office of Operational Safety, Department of Energy ' ACTION: Notice of Availability of Archival Information Package SUMMARY: The'Office of Operational Safety of the Department O i Energy (DOE) has reviewed documentation relating to the decontamination and decommissioning operations conducted at the Ames Laboratory Research Reactor Facility, Ames, Iowa and has prepared an archival informati0.n package to permanently document the results of the action and the site conditions and use restriction placed on the . site at the tim e of release. This review is based on post-decontamination survey data and other pertinent documentation referenced in and included in the archival package. The material and

2

CRAD, Training - Oak Ridge National Laboratory High Flux Isotope Reactor |  

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

Reactor Reactor CRAD, Training - Oak Ridge National Laboratory High Flux Isotope Reactor February 2007 A section of Appendix C to DOE G 226.1-2 "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of Criteria Review and Approach Documents (CRADs) used for a February 2007 assessment of the Training Program in preparation for restart of the Oak Ridge National Laboratory High Flux Isotope Reactor. RADs provide a recommended approach and the types of information to gather to assess elements of a DOE contractor's programs. CRAD, Training - Oak Ridge National Laboratory High Flux Isotope Reactor More Documents & Publications CRAD, Nuclear Safety - Oak Ridge National Laboratory High Flux Isotope Reactor CRAD, Training - Oak Ridge National Laboratory High Flux Isotope Reactor

3

CRAD, Maintenance - Oak Ridge National Laboratory High Flux Isotope Reactor  

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

Reactor Reactor CRAD, Maintenance - Oak Ridge National Laboratory High Flux Isotope Reactor February 2007 A section of Appendix C to DOE G 226.1-2 "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of Criteria Review and Approach Documents (CRADs) used for a February 2007 assessment of the Maintenance Program in preparation for restart of the Oak Ridge National Laboratory High Flux Isotope Reactor. CRADs provide a recommended approach and the types of information to gather to assess elements of a DOE contractor's programs. CRAD, Maintenance - Oak Ridge National Laboratory High Flux Isotope Reactor More Documents & Publications CRAD, Safety Basis - Oak Ridge National Laboratory High Flux Isotope Reactor CRAD, Maintenance - Oak Ridge National Laboratory High Flux Isotope Reactor

4

CRAD, Engineering - Oak Ridge National Laboratory High Flux Isotope Reactor  

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

Engineering - Oak Ridge National Laboratory High Flux Isotope Engineering - Oak Ridge National Laboratory High Flux Isotope Reactor CRAD, Engineering - Oak Ridge National Laboratory High Flux Isotope Reactor February 2007 A section of Appendix C to DOE G 226.1-2 "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of Criteria Review and Approach Documents (CRADs) used for a February 2007 assessment of the Engineering Program in preparation for restart of the Oak Ridge National Laboratory High Flux Isotope Reactor. CRADs provide a recommended approach and the types of information to gather to assess elements of a DOE contractor's programs. CRAD, Engineering - Oak Ridge National Laboratory High Flux Isotope Reactor More Documents & Publications CRAD, Engineering - Oak Ridge National Laboratory High Flux Isotope Reactor

5

Overview of Sandia National Laboratories pulse nuclear reactors  

SciTech Connect (OSTI)

Sandia National Laboratories has designed, constructed and operated bare metal Godiva-type and pool-type pulse reactors since 1961. The reactor facilities were designed to support a wide spectrum of research, development, and testing activities associated with weapon and reactor systems.

Schmidt, T.R. [Sandia National Labs., Albuquerque, NM (United States); Reuscher, J.A. [Texas A& M Univ., College Station, TX (United States)

1994-10-01T23:59:59.000Z

6

CRAD, Maintenance - Oak Ridge National Laboratory High Flux Isotope Reactor  

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

Reactor Contractor ORR Reactor Contractor ORR CRAD, Maintenance - Oak Ridge National Laboratory High Flux Isotope Reactor Contractor ORR February 2007 A section of Appendix C to DOE G 226.1-2 "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of Criteria Review and Approach Documents (CRADs) used for a February 2007 assessment of the Maintenance Program portion of an Operational Readiness Review of the Oak Ridge National Laboratory High Flux Isotope Reactor. CRADs provide a recommended approach and the types of information to gather to assess elements of a DOE contractor's programs. CRAD, Maintenance - Oak Ridge National Laboratory High Flux Isotope Reactor Contractor ORR More Documents & Publications CRAD, Engineering - Oak Ridge National Laboratory High Flux Isotope Reactor

7

Idaho National Laboratory Advanced Test Reactor Probabilistic Risk  

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

Idaho National Laboratory Advanced Test Reactor Probabilistic Risk Idaho National Laboratory Advanced Test Reactor Probabilistic Risk Assessment Idaho National Laboratory Advanced Test Reactor Probabilistic Risk Assessment September 19, 2012 Presenter: Bentley Harwood, Advanced Test Reactor Nuclear Safety Engineer Battelle Energy Alliance Idaho National Laboratory Topics covered: PRA studies began in the late 1980s 1989, ATR PRA published as a summary report 1991, ATR PRA full report 1994 and 2004 various model changes 2011, Consolidation, update and improvement of previous PRA work 2012/2013, PRA risk monitor implementation Idaho National Laboratory Advanced Test Reactor Probabilistic Risk Assessment More Documents & Publications DOE's Approach to Nuclear Facility Safety Analysis and Management Nuclear Regulatory Commission Handling of Beyond Design Basis Events for

8

CRAD, Management- Oak Ridge National Laboratory High Flux Isotope Reactor |  

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

Management- Oak Ridge National Laboratory High Flux Isotope Management- Oak Ridge National Laboratory High Flux Isotope Reactor CRAD, Management- Oak Ridge National Laboratory High Flux Isotope Reactor February 2007 A section of Appendix C to DOE G 226.1-2 "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of Criteria Review and Approach Documents (CRADs) used for a February 2007 assessment of the Management in preparation for restart of the Oak Ridge National Laboratory High Flux Isotope Reactor. CRADs provide a recommended approach and the types of information to gather to assess elements of a DOE contractor's programs. CRAD, Management- Oak Ridge National Laboratory High Flux Isotope Reactor More Documents & Publications CRAD, Nuclear Safety - Oak Ridge National Laboratory High Flux Isotope

9

CRAD, Training - Oak Ridge National Laboratory High Flux Isotope Reactor  

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

Reactor Contractor ORR Reactor Contractor ORR CRAD, Training - Oak Ridge National Laboratory High Flux Isotope Reactor Contractor ORR February 2007 A section of Appendix C to DOE G 226.1-2 "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of Criteria Review and Approach Documents (CRADs) used for a February 2007 assessment of the Training Program portion of an Operational Readiness Review of the Oak Ridge National Laboratory High Flux Isotope Reactor. CRADs provide a recommended approach and the types of information to gather to assess elements of a DOE contractor's programs. CRAD, Training - Oak Ridge National Laboratory High Flux Isotope Reactor Contractor ORR More Documents & Publications CRAD, Conduct of Operations - Oak Ridge National Laboratory High Flux

10

CRAD, Engineering - Oak Ridge National Laboratory High Flux Isotope Reactor  

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

Oak Ridge National Laboratory High Flux Isotope Oak Ridge National Laboratory High Flux Isotope Reactor Contractor ORR CRAD, Engineering - Oak Ridge National Laboratory High Flux Isotope Reactor Contractor ORR February 2007 A section of Appendix C to DOE G 226.1-2 "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of Criteria Review and Approach Documents (CRADs) used for a February 2007 assessment of the Engineering Program portion of an Operational Readiness Review of the Oak Ridge National Laboratory, High Flux Isotope Reactor. CRADs provide a recommended approach and the types of information to gather to assess elements of a DOE contractor's programs. CRAD, Engineering - Oak Ridge National Laboratory High Flux Isotope Reactor Contractor ORR More Documents & Publications

11

CRAD, Management - Oak Ridge National Laboratory High Flux Isotope Reactor  

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

Oak Ridge National Laboratory High Flux Isotope Oak Ridge National Laboratory High Flux Isotope Reactor Contractor ORR CRAD, Management - Oak Ridge National Laboratory High Flux Isotope Reactor Contractor ORR February 2007 A section of Appendix C to DOE G 226.1-2 "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of Criteria Review and Approach Documents (CRADs) used for a February 2007 assessment of the Management portion of an Operational Readiness Review of the Oak Ridge National Laboratory High Flux Isotope Reactor. CRADs provide a recommended approach and the types of information to gather to assess elements of a DOE contractor's programs. CRAD, Management - Oak Ridge National Laboratory High Flux Isotope Reactor Contractor ORR More Documents & Publications

12

CRAD, Engineering- Oak Ridge National Laboratory High Flux Isotope Reactor  

Broader source: Energy.gov [DOE]

A section of Appendix C to DOE G 226.1-2 "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of Criteria Review and Approach Documents (CRADs) used for a February 2007 assessment of the Engineering Program in preparation for restart of the Oak Ridge National Laboratory High Flux Isotope Reactor.

13

CRAD, Management- Oak Ridge National Laboratory High Flux Isotope Reactor  

Broader source: Energy.gov [DOE]

A section of Appendix C to DOE G 226.1-2 "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of Criteria Review and Approach Documents (CRADs) used for a February 2007 assessment of the Management in preparation for restart of the Oak Ridge National Laboratory High Flux Isotope Reactor.

14

CRAD, Training- Oak Ridge National Laboratory High Flux Isotope Reactor  

Broader source: Energy.gov [DOE]

A section of Appendix C to DOE G 226.1-2 "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of Criteria Review and Approach Documents (CRADs) used for a February 2007 assessment of the Training Program in preparation for restart of the Oak Ridge National Laboratory High Flux Isotope Reactor.

15

LABORATORY II ELECTRIC FIELDS AND ELECTRIC POTENTIALS  

E-Print Network [OSTI]

Lab II - 1 LABORATORY II ELECTRIC FIELDS AND ELECTRIC POTENTIALS In this lab you will continue to investigate the abstract concept of electric field. If you know the electric field at a point in space, you). With this simulation you can construct a complicated charge configuration and read out the resulting electric field

Minnesota, University of

16

Polymer Reaction Engineering Laboratory -University of Maryland at College Park Reactor Dynamics, Control, Optimization  

E-Print Network [OSTI]

, Control, Optimization Exothermic polymerization reactions in continuous flow reactors may cause complexPolymer Reaction Engineering Laboratory - University of Maryland at College Park Reactor Dynamics nonlinear steady state and transient behaviors. The topic of reactor dynamics has been the subject

Rubloff, Gary W.

17

Risk management at the Oak Ridge National Laboratory research reactors  

SciTech Connect (OSTI)

In November of 1986, the High Flux Isotope Reactor (HFIR) was shut down by Oak Ridge National Laboratory (ORNL) due to a concern regarding embrittlement of the reactor vessel. A massive review effort was undertaken by ORNL and the Department of Energy (DOE). This review resulted in an extensive list of analyses and design modifications to be completed before restart could take place. The review also focused on the improvement of management practices including implementation of several of the Institute of Nuclear Power Operations (INPO) requirements. One of the early items identified was the need to perform a Probabilistic Risk Assessment (PRA) on the reactor. It was decided by ORNL management that this PRA would not be just an exercise to assess the ``bottom`` line in order to restart, but would be used to improve the overall safety of the reactor, especially since resources (both manpower and dollars) were severely limited. The PRA would become a basic safety tool to be used instead of a more standard deterministic approach to safety used in commercial reactor power plants. This approach was further reinforced, because the reactor was nearly 25 years old at this time, and the design standards and regulations had changed significantly since the original design, and many of the safety issues could not be addressed by compliance to codes and standards.

Flanagan, G.F.; Linn, M.A.; Proctor, L.D.; Cook, D.H.

1994-12-31T23:59:59.000Z

18

The integral fast reactor fuels reprocessing laboratory at Argonne National Laboratory, Illinois  

SciTech Connect (OSTI)

The processing of Integral Fast Reactor (IFR) metal fuel utilizes pyrochemical fuel reprocessing steps. These steps include separation of the fission products from uranium and plutonium by electrorefining in a fused salt, subsequent concentration of uranium and plutonium for reuse, removal, concentration, and packaging of the waste material. Approximately two years ago a facility became operational at Argonne National Laboratory-Illinois to establish the chemical feasibility of proposed reprocessing and consolidation processes. Sensitivity of the pyroprocessing melts to air oxidation necessitated operation in atmosphere-controlled enclosures. The Integral Fast Reactor Fuels Reprocessing Laboratory is described.

Wolson, R.D.; Tomczuk, Z.; Fischer, D.F.; Slawecki, M.A.; Miller, W.E.

1986-09-01T23:59:59.000Z

19

Field test of the Rapid Transuranic Monitoring Laboratory  

SciTech Connect (OSTI)

A field test of the Rapid Transuranic Monitoring Laboratory (RTML) developed at the Idaho National Engineering Laboratory (INEL) was conducted as part of a demonstration sponsored by the Buried Waste Integrated Demonstration (BWID). The RTML is a mobile, field- deployable laboratory developed for use at buried radioactive waste remediation sites to allow onsite preparation and analysis of soil, smear, and air filter samples for alpha and gamma-emitting contaminants. Analytical instruments installed in the RTML include an extended range, germanium photon analysis spectrometer with an automatic sample changer, two large-area ionization chamber alpha spectrometers, and four alpha continuous air monitors. The performance of the RTML was tested at the Test Reactor Area and Cold Test Pit near the Radioactive Waste Management Complex at the INEL. Objectives, experimental procedures, and an evaluation of the performance of the RTML are presented.

McIsaac, C.V.; Sill, C.W.; Gehrke, R.J.; Killian, E.W.; Watts, K.D.; Amaro, C.R.

1993-12-01T23:59:59.000Z

20

Early Exploration - Reactors designed/built by Argonne National Laboratory  

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

Early Exploration Early Exploration 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

Note: This page contains sample records for the topic "reactors laboratory field" 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

A field laboratory for improved oil recovery  

SciTech Connect (OSTI)

The purpose of Annex III of the Memorandum of Understanding, undertaken by the Houston Petroleum Research Center at the University of Houston, was to develop a field laboratory for research in improved oil recovery using a Gulf Coast reservoir in Texas. The participants: (1) make a field site selection and conducted a high resolution seismic survey in the demonstration field, (2) obtained characteristics of the reservoir (3) developed an evaluation of local flood efficiency in different parts of the demonstration reservoir, (4) used diverse methodology to evaluate the potential recovery of the remaining oil in the test reservoir, (5) developed cross-well seismic tomography, and (6) will transfer the learned technologies to oil operators through publication and workshops. This abstract is an overview of these tasks.

Hildebrandt, A.F.; McDonald, J.; Claridge, E.; Killough, J.

1992-09-01T23:59:59.000Z

22

Creation of a neutrino laboratory for search for sterile neutrino at SM-3 reactor  

E-Print Network [OSTI]

In connection with the question of possible existence of sterile neutrino the laboratory on the basis of SM-3 reactor was created to search for oscillations of reactor antineutrino. A prototype of a neutrino detector with scintillator volume of 400 l can be moved at the distance of 6-11 m from the reactor core. The measurements of background conditions have been made. It is shown that the main experimental problem is associated with cosmic radiation background. Test measurements of dependence of a reactor antineutrino flux on the distance from a reactor core have been made. The prospects of search for oscillations of reactor antineutrino at short distances are discussed.

Serebrov, A P; Samoylov, R M; Fomin, A K; Zinoviev, V G; Neustroev, P V; Golovtsov, V L; Gruzinsky, N V; Solovey, V A; Cherniy, A V; Zherebtsov, O M; Martemyanov, V P; Zinoev, V G; Tarasenkov, V G; Aleshin, V I; Petelin, A L; Pavlov, S V; Izhutov, A L; Sazontov, S A; Ryazanov, D K; Gromov, M O; Afanasiev, V V; Matrosov, L N; Matrosova, M Yu

2015-01-01T23:59:59.000Z

23

Probing Molecular Associations of Field-Collected and Laboratory...  

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

Molecular Associations of Field-Collected and Laboratory-Generated SOA with Nano-DESI High-Resolution Mass Spectrometry. Probing Molecular Associations of Field-Collected and...

24

National Laboratories: Focused Goals and Field Work Hinted Under DOE  

Science Journals Connector (OSTI)

...in which field contact will...expected to give field support for...assignments of the laboratories in the new...devoted to nuclear work will...fu-sion) development are the Bettis...breeder c Santa Susanna, California, Brunswick Laboratory, the Pri...producing nuclear warhea fense...ofthe DOE Field and Laboratory...

WILLIAM D. METZ

1977-12-02T23:59:59.000Z

25

Sandia National Laboratories: Research: Facilities: Sandia Pulsed Reactor  

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

Sandia Pulsed Reactor Facility - Critical Experiments Sandia Pulsed Reactor Facility - Critical Experiments Sandia scientist John Ford places fuel rods in the Seven Percent Critical Experiment (7uPCX) at the Sandia Pulsed Reactor Facility Critical Experiments (SPRF/CX) test reactor - a reactor stripped down to its simplest form. The Sandia Pulsed Reactor Facility - Critical Experiments (SPRF/CX) provides a flexible, shielded location for performing critical experiments that employ different reactor core configurations and fuel types. The facility is also available for hands-on nuclear criticality safety training. Research and other activities The 7% series, an evaluation of various core characteristics for higher commercial-fuel enrichment, is currently under way at the SPRF/CX. Past critical experiments at the SPRF/CX have included the Burnup Credit

26

The High Flux Isotope Reactor at Oak Ridge National Laboratory  

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

The High Flux Isotope Reactor at ORNL The High Flux Isotope Reactor at ORNL Aerial of the High Flux Isotope Reactor Site The High Flux Isotope Reactor site is located on the south side of the ORNL campus and is about a three-minute drive from her sister neutron facility, the Spallation Neutron Source. Operating at 85 MW, HFIR is the highest flux reactor-based source of neutrons for research in the United States, and it provides one of the highest steady-state neutron fluxes of any research reactor in the world. The thermal and cold neutrons produced by HFIR are used to study physics, chemistry, materials science, engineering, and biology. The intense neutron flux, constant power density, and constant-length fuel cycles are used by more than 500 researchers each year for neutron scattering research into

27

National High Magnetic Field Laboratory: Superconductors  

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

opposes the magnetic field generating the current. In a perfect diamagnet, the magnetic field lines produced exactly mirror those of the changing magnetic field that induce them,...

28

Vertical Pretreatment Reactor System (Poster), NREL (National Renewable Energy Laboratory)  

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

Vertical Pretreatment Reactor System Vertical Pretreatment Reactor System Two-vessel system for primary and secondary pretreatment at diff erent temperatures * Biomass is heated by steam injection to temperatures of 120°C to 210°C in the pressurized mixing tube * Preheated, premixed biomass is retained for specified residence time in vertical holding vessel; material continuously moves by gravity from top to bottom of reactor in plug-fl ow fashion * Residence time is adjusted by changing amount of material held in vertical vessel relative to continuous fl ow of material entering and exiting vessel * Optional additional reactor vessel allows for secondary pretreatment at lower temperatures-120°C to 180°C-with potential to add other chemical catalysts * First vessel can operate at residence

29

National High Magnetic Field Laboratory: Geochemistry Facilities  

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

section equipment. Laboratory for light isotope sample preparation Including two vacuum lines for preparation of various samples for carbon, oxygen and hydrogen isotopic analyses....

30

Horizontal Pretreatment Reactor System (Poster), NREL (National Renewable Energy Laboratory)  

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

Diff Diff erent pretreatment chemistry/ residence time combinations are possible using these multiple horizontal-tube reactors * Each tube is indirectly and directly steam heated to temperatures of 150 0 C to 210 0 C * Residence time is varied by changing the speed of the auger that moves the biomass through each tube reactor * Tubes are used individually or in combination to achieve diff erent pretreatment residence times * Smaller tubes made from Hastelloy, an acid-resistant material, are used with more corrosive chemicals and residence times from 3 to 20 minutes * Larger tubes made from 316 stainless steel are used for residence times from 20 to 120 minutes Horizontal Pretreatment Reactor System Versatile pretreatment system for a wide range of pretreatment chemistries

31

Independent Confirmatory Survey Report for the University of Arizona Nuclear Reactor Laboratory, Tucson, Arizona  

SciTech Connect (OSTI)

The University of Arizona (University) research reactor is a TRIGA swimming pool type reactor designed by General Atomics and constructed at the University in 1958. The reactor first went into operation in December of 1958 under U.S. Nuclear Regulatory Commission (NRC) license R-52 until final shut down on May 18, 2010. Initial site characterization activities were conducted in February 2009 during ongoing reactor operations to assess the radiological status of the Nuclear Reactor Laboratory (NRL) excluding the reactor tank, associated components, and operating systems. Additional post-shutdown characterization activities were performed to complete characterization activities as well as verify assumptions made in the Decommissioning Plan (DP) that were based on a separate activation analysis (ESI 2009 and WMG 2009). Final status survey (FSS) activities began shortly after the issuance of the FSS plan in May 2011. The contractor completed measurement and sampling activities during the week of August 29, 2011.

Nick A. Altic

2011-11-11T23:59:59.000Z

32

Los Alamos National Laboratory Omega West Reactor restart  

SciTech Connect (OSTI)

This report is a critical evaluation of the effort for the restart of the Omega West reactor. It is divided into the following areas: progress made; difficulties in restart effort; current needs; and suggested detailed steps for improvement. A brief discussion is given for each area of study.

NONE

1993-08-27T23:59:59.000Z

33

An evaluation of alternative reactor vessel cutting technologies for the experimental boiling water reactor at Argonne National Laboratory  

SciTech Connect (OSTI)

Metal cutting techniques that can be used to segment the reactor pressure vessel of the Experimental Boiling Water Reactor (EBWR) at Argonne National Laboratory (ANL) have been evaluated by Nuclear Energy Services. Twelve cutting technologies are described in terms of their ability to perform the required task, their performance characteristics, environmental and radiological impacts, and cost and schedule considerations. Specific recommendations regarding which technology should ultimately be used by ANL are included. The selection of a cutting method was the responsibility of the decommissioning staff at ANL, who included a relative weighting of the parameters described in this document in their evaluation process. 73 refs., 26 figs., 69 tabs.

Boing, L.E.; Henley, D.R. (Argonne National Lab., IL (USA)); Manion, W.J.; Gordon, J.W. (Nuclear Energy Services, Inc., Danbury, CT (USA))

1989-12-01T23:59:59.000Z

34

DOE - Office of Legacy Management -- Santa Susana Field Laboratory - CA 09  

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

Santa Susana Field Laboratory - CA Santa Susana Field Laboratory - CA 09 FUSRAP Considered Sites Site: SANTA SUSANA FIELD LABORATORY (CA.09 ) Eliminated from consideration under FUSRAP - Remediation and certification complete Designated Name: Not Designated Alternate Name: Rockwell International, Energy Systems Group Atomics International CA.09-1 CA.09-2 Location: Chatsworth , California CA.09-3 Evaluation Year: 1985 CA.09-3 Site Operations: Conducted sodium reactor, irradiation and fuel burn up experimentation. CA.09-3 Site Disposition: Eliminated - Certification of remedial action completed CA.09-1 CA.09-3 Radioactive Materials Handled: Yes Primary Radioactive Materials Handled: Uranium CA.09-2 Radiological Survey(s): Yes CA.09-3 CA.09-4 Site Status: Eliminated from consideration under FUSRAP - Remediation and certification complete CA.09-5

35

Presented by the National High Magnetic Field Laboratory  

E-Print Network [OSTI]

Magnets These lines show the magnetic field created by the bar magnet. Look, this magnetic field looks like an apple! Field Lines #12;Scientists at the Magnet Lab use a special kind of magnet calledPresented by the National High Magnetic Field Laboratory Learning About Name #12;A magnet

Weston, Ken

36

Research reactor usage at the Idaho National Engineering Laboratory in support of university research and education  

SciTech Connect (OSTI)

The Idaho National Engineering Laboratory is a US Department of Energy laboratory which has a substantial history of research and development in nuclear reactor technologies. There are a number of available nuclear reactor facilities which have been incorporated into the research and training needs of university nuclear engineering programs. This paper addresses the utilization of the Advanced Reactivity Measurement Facility (ARMF) and the Coupled Fast Reactivity Measurement Facility (CFRMF) for thesis and dissertation research in the PhD program in Nuclear Science and Engineering by the University of Idaho and Idaho State University. Other reactors at the INEL are also being used by various members of the academic community for thesis and dissertation research, as well as for research to advance the state of knowledge in innovative nuclear technologies, with the EBR-II facility playing an essential role in liquid metal breeder reactor research. 3 refs.

Woodall, D.M.; Dolan, T.J.; Stephens, A.G. (Idaho National Engineering Lab., Idaho Falls, ID (USA))

1990-01-01T23:59:59.000Z

37

EIS-0291: High Flux Beam Reactor (HFBR) Transition Project at the Brookhaven National Laboratory, Upton, New York  

Broader source: Energy.gov [DOE]

The EIS evaluates the range of reasonable alternatives and their impacts regarding the future management of the High Flux Beam Reactor (HFBR) at Brookhaven National Laboratory (BNL).

38

INDEPENDENT VERIFICATION SURVEY OF THE HIGH FLUX BEAM REACTOR DECOMMISSIONING PROJECT OUTSIDE AREAS BROOKHAVEN NATIONAL LABORATORY UPTON, NEW YORK  

SciTech Connect (OSTI)

5098-SR-03-0 FINAL REPORT- INDEPENDENT VERIFICATION SURVEY OF THE HIGH FLUX BEAM REACTOR DECOMMISSIONING PROJECT OUTSIDE AREAS, BROOKHAVEN NATIONAL LABORATORY

P.C. Weaver

2010-12-15T23:59:59.000Z

39

Modern Status of Neutrino Experiments at the Underground Neutrino Laboratory of Kurchatov Institute Near Krasnoyarsk Nuclear Reactor  

E-Print Network [OSTI]

The investigation of antineutrino-deuteron interaction at Krasnoyarsk reactor are discussed. The characteristics of the installation ''Deuteron'', present results and perspectives of Krasnoyarsk neutrino laboratory are presented.

Yu. V. Kozlov; S. V. Khalturtsev; I. N. Machulin; A. V. Martemyanov; V. P. Martemyanov; A. A. Sabelnikov; S. V. Sukhotin; V. G. Tarasenkov; E. V. Turbin; V. N. Vyrodov

1998-11-11T23:59:59.000Z

40

National High Magnetic Field Laboratory - Publications  

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

Lett. Physica B Physica C Physica E Polymer Polymer J. Proc. Physical Phenomena at High Magnetic Fields - IV Protein Science PROTEINS: Structure, Function and Genetics Rapid...

Note: This page contains sample records for the topic "reactors laboratory field" 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

National High Magnetic Field Laboratory: Metallic Superlattices  

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

Many years would pass, however, before thin films became a major focus in the field of physics. The introduction of computers and the search for practical methods of data storage...

42

Dark Field Microscopy for Analytical Laboratory Courses  

Science Journals Connector (OSTI)

An innovative and inexpensive optical microscopy experiment for a quantitative analysis or an instrumental analysis chemistry course is described. The students have hands-on experience with a dark field microscope and investigate the wavelength dependence ...

Ashley E. Augspurger; Anthony S. Stender; Kyle Marchuk; Thomas J. Greenbowe; Ning Fang

2014-05-01T23:59:59.000Z

43

National High Magnetic Field Laboratory - Applied Superconductivity...  

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

the coupling between the gaps, and whether this produces new properties when quantized field lines move along grain boundaries or when MgB2 is exposed to microwave radiation. The...

44

National High Magnetic Field Laboratory - Electron Interaction...  

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

c). Plot of the CNT sample conductance versus the gate voltage and the axial magnetic field. A dark arrow indicates the value of B0 , where the energy gap has a minimum (metallic...

45

National High Magnetic Field Laboratory: Superconducting Wire  

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

of the particles has an effect on the pinning along various directions of magnetic field lines. The conductive capacity of 2G HTS wire is similarly affected by the...

46

Dynamic Impregnator Reactor System (Poster), NREL (National Renewable Energy Laboratory)  

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

Several unit operations are combined into Several unit operations are combined into one robust system, off ering fl exible and staged process confi gurations in one vessel. Spraying, soaking, low-severity pretreat- ment, enzymatic hydrolysis, fermentation, concentration/evaporation, and distillation are amongst its many capabilities. * 1,900 L Horizontal Paddle Blender Vessel with Sidewall Liquid Drains * 6-60 rpm / 50 HP Tri-Directional Agitator * 3.4 bar & Vacuum ASME Design, 316L Stainless Steel * Heating/Cooling Jacket using Water or Steam * 150 L Chemical Mix Tank & Pump with Spray Injectors * Vent Condenser with Collection Tank and Vacuum Pump Dynamic Impregnator Reactor System Multifaceted system designed for complex feedstock impregnation and processing Integrated Biorefi nery Research Facility | NREL * Golden, Colorado | December 15, 2011 | NREL/PO-5100-56156

47

Gregory S. Boebinger, National High Magnetic Field Laboratory  

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

Ring Coil for Neuroimaging at 21.1 T Gregory S. Boebinger, National High Magnetic Field Laboratory DMR-Award 0654118 NMR Facility - 900MHz UWB Magnet While today s clinical...

48

Field and laboratory investigations of selenium transformation  

SciTech Connect (OSTI)

This quarterly report discusses the preparation and results of a field investigation of a selected coal mine site in Oklahoma. The field investigation has been on-going since July 1990. An analysis of this data would be useful in providing information for potential Se mobility from a coal mine site and the distribution of Se in a soil profile of reclaimed land. Also, included is the investigation and preliminary results of SeO{sub 3}{sup 2{minus}} adsorption and desorption using different soil media, including coal mine spoils (overburden).

Atalay, A.; Koll, K.J.

1990-12-01T23:59:59.000Z

49

CRAD, Management- Oak Ridge National Laboratory High Flux Isotope Reactor Contractor ORR  

Broader source: Energy.gov [DOE]

A section of Appendix C to DOE G 226.1-2 "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of Criteria Review and Approach Documents (CRADs) used for a February 2007 assessment of the Management portion of an Operational Readiness Review of the Oak Ridge National Laboratory High Flux Isotope Reactor.

50

CRAD, Environmental Protection- Oak Ridge National Laboratory High Flux Isotope Reactor  

Broader source: Energy.gov [DOE]

A section of Appendix C to DOE G 226.1-2 "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of Criteria Review and Approach Documents (CRADs) used for a February 2007 assessment of the Environmental Compliance Program in preparation for restart of the Oak Ridge National Laboratory High Flux Isotope Reactor.

51

CRAD, Configuration Management- Oak Ridge National Laboratory High Flux Isotope Reactor Contractor ORR  

Broader source: Energy.gov [DOE]

A section of Appendix C to DOE G 226.1-2 "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of Criteria Review and Approach Documents (CRADs) used for a February 2007 assessment of the Configuration Management Program portion of an Operational Readiness Review of the Oak Ridge National Laboratory, High Flux Isotope Reactor.

52

CRAD, Occupational Safety & Health- Oak Ridge National Laboratory High Flux Isotope Reactor  

Broader source: Energy.gov [DOE]

A section of Appendix C to DOE G 226.1-2 "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of Criteria Review and Approach Documents (CRADs) used for a February 2007 assessment of the Industrial Safety and Hygiene Program in preparation for restart of the Oak Ridge National Laboratory High Flux Isotope Reactor.

53

CRAD, Configuration Management- Oak Ridge National Laboratory High Flux Isotope Reactor  

Broader source: Energy.gov [DOE]

A section of Appendix C to DOE G 226.1-2 "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of Criteria Review and Approach Documents (CRADs) used for a February 2007 assessment of the Configuration Management Program in preparation for restart of the Oak Ridge National Laboratory, High Flux Isotope Reactor.

54

CRAD, Emergency Management- Oak Ridge National Laboratory High Flux Isotope Reactor  

Broader source: Energy.gov [DOE]

A section of Appendix C to DOE G 226.1-2 "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of Criteria Review and Approach Documents (CRADs) used for a February 2007 assessment of the Emergency Management Program in preparation for restart of the Oak Ridge National Laboratory High Flux Isotope Reactor.

55

Analyses in support of the Laboratory Microfusion Facility and ICF commercial reactor designs  

SciTech Connect (OSTI)

Our work on this contract was divided into two major categories; two thirds of the total effort was in support of the Laboratory Microfusion Facility (LMF), and one third of the effort was in support of Inertial Confinement Fusion (ICF) commercial reactors. This final report includes copies of the formal reports, memoranda, and viewgraph presentations that were completed under this contract.

Meier, W.R.; Monsler, M.J.

1988-12-28T23:59:59.000Z

56

CRAD, Conduct of Operations- Oak Ridge National Laboratory High Flux Isotope Reactor  

Broader source: Energy.gov [DOE]

A section of Appendix C to DOE G 226.1-2 "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of Criteria Review and Approach Documents (CRADs) used for a February, 2007 assessment of the Conduct of Operations Program in preparation for restart of the Oak Ridge National Laboratory, High Flux Isotope Reactor.

57

CRAD, Conduct of Operations- Oak Ridge National Laboratory High Flux Isotope Reactor Contractor ORR  

Broader source: Energy.gov [DOE]

A section of Appendix C to DOE G 226.1-2 "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of Criteria Review and Approach Documents (CRADs) used for a February, 2007 assessment of the Conduct of Operations Program portion of an Operational Readiness Review of the Oak Ridge National Laboratory, High Flux Isotope Reactor.

58

CRAD, Training- Oak Ridge National Laboratory High Flux Isotope Reactor Contractor ORR  

Broader source: Energy.gov [DOE]

A section of Appendix C to DOE G 226.1-2 "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of Criteria Review and Approach Documents (CRADs) used for a February 2007 assessment of the Training Program portion of an Operational Readiness Review of the Oak Ridge National Laboratory High Flux Isotope Reactor.

59

CRAD, Radiological Controls- Oak Ridge National Laboratory High Flux Isotope Reactor  

Broader source: Energy.gov [DOE]

A section of Appendix C to DOE G 226.1-2 "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of Criteria Review and Approach Documents (CRADs) used for a February 2007 assessment of the Radiation Protection Program in preparation for restart of the Oak Ridge National Laboratory High Flux Isotope Reactor.

60

CRAD, Safety Basis- Oak Ridge National Laboratory High Flux Isotope Reactor Contractor ORR  

Broader source: Energy.gov [DOE]

A section of Appendix C to DOE G 226.1-2 "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of Criteria Review and Approach Documents (CRADs) used for a February 2007 assessment of the Safety Basis portion of an Operational Readiness Review of the Oak Ridge National Laboratory High Flux Isotope Reactor.

Note: This page contains sample records for the topic "reactors laboratory field" 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

CRAD, Safety Basis- Oak Ridge National Laboratory High Flux Isotope Reactor  

Broader source: Energy.gov [DOE]

A section of Appendix C to DOE G 226.1-2 "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of Criteria Review and Approach Documents (CRADs) used for a February 2007 assessment of the Safety Basis in preparation for restart of the Oak Ridge National Laboratory High Flux Isotope Reactor.

62

CRAD, Maintenance- Oak Ridge National Laboratory High Flux Isotope Reactor Contractor ORR  

Broader source: Energy.gov [DOE]

A section of Appendix C to DOE G 226.1-2 "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of Criteria Review and Approach Documents (CRADs) used for a February 2007 assessment of the Maintenance Program portion of an Operational Readiness Review of the Oak Ridge National Laboratory High Flux Isotope Reactor.

63

CRAD, Occupational Safety & Health- Oak Ridge National Laboratory High Flux Isotope Reactor Contractor ORR  

Broader source: Energy.gov [DOE]

A section of Appendix C to DOE G 226.1-2 "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of Criteria Review and Approach Documents (CRADs) used for a February 2007 assessment of the Occupational Safety and Health Program portion of an Operational Readiness Review of the Oak Ridge National Laboratory High Flux Isotope Reactor.

64

CRAD, Nuclear Safety- Oak Ridge National Laboratory High Flux Isotope Reactor  

Broader source: Energy.gov [DOE]

A section of Appendix C to DOE G 226.1-2 "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of Criteria Review and Approach Documents (CRADs) used for a February 2007 assessment of the Nuclear Safety Program in preparation for restart of the Oak Ridge National Laboratory High Flux Isotope Reactor.

65

CRAD, Quality Assurance- Oak Ridge National Laboratory High Flux Isotope Reactor  

Broader source: Energy.gov [DOE]

A section of Appendix C to DOE G 226.1-2 "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of Criteria Review and Approach Documents (CRADs) used for a February 2007 assessment of the Quality Assurance Program in preparation for restart of the Oak Ridge National Laboratory High Flux Isotope Reactor.

66

Reference site selection report for the advanced liquid metal reactor at the Idaho National Engineering Laboratory  

SciTech Connect (OSTI)

This Reference Site Selection Report was prepared by EG G, Idaho Inc., for General Electric (GE) to provide information for use by the Department of Energy (DOE) in selecting a Safety Test Site for an Advanced Liquid Metal Reactor. Similar Evaluation studies are planned to be conducted at other potential DOE sites. The Power Reactor Innovative Small Module (PRISM) Concept was developed for ALMR by GE. A ALMR Safety Test is planned to be performed on a DOE site to demonstrate features and meet Nuclear Regulatory Commission Requirements. This study considered possible locations at the Idaho National Engineering Laboratory that met the ALMR Prototype Site Selection Methodology and Criteria. Four sites were identified, after further evaluation one site was eliminated. Each of the remaining three sites satisfied the criteria and was graded. The results were relatively close. Thus concluding that the Idaho National Engineering Laboratory is a suitable location for an Advanced Liquid Metal Reactor Safety Test. 23 refs., 13 figs., 9 tabs.

Sivill, R.L.

1990-03-01T23:59:59.000Z

67

Compact Reversed-Field Pinch Reactors (CRFPR): preliminary engineering considerations  

SciTech Connect (OSTI)

The unique confinement physics of the Reversed-Field Pinch (RFP) projects to a compact, high-power-density fusion reactor that promises a significant reduction in the cost of electricity. The compact reactor also promises a factor-of-two reduction in the fraction of total cost devoted to the reactor plant equipment (i.e., fusion power core (FPC) plus support systems). In addition to operational and developmental benefits, these physically smaller systems can operate economically over a range of total power output. After giving an extended background and rationale for the compact fusion approaches, key FPC subsystems for the Compact RFP Reactor (CRFPR) are developed, designed, and integrated for a minimum-cost, 1000-MWe(net) system. Both the problems and promise of the compact, high-power-density fusion reactor are quantitatively evaluated on the basis of this conceptual design. The material presented in this report both forms a framework for a broader, more expanded conceptual design as well as suggests directions and emphases for related research and development.

Hagenson, R.L.; Krakowski, R.A.; Bathke, C.G.; Miller, R.L.; Embrechts, M.J.; Schnurr, N.M.; Battat, M.E.; LaBauve, R.J.; Davidson, J.W.

1984-08-01T23:59:59.000Z

68

National High Magnetic Field Laboratory - Visualizing Field Lines...  

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

Now You See It: Visualizing Field Lines Try This At Home The magnetic field is the area around the magnet where the magnetic forces act. Actually, magnets are made up of many, many...

69

National High Magnetic Field Laboratory - Drawing Field Lines...  

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

A Portrait of Magnetism: Drawing Field Lines Try This At Home Magnets have two poles; the field lines spread out from the north pole and circle back around to the south pole. In...

70

Study of the catalyst deactivation in an industrial gasoil HDS reactor using a mini-scale laboratory reactor  

Science Journals Connector (OSTI)

The activity of a hydrodesulphurization catalyst loaded in an industrial hydrotreater is studied at start up and end of run. Catalyst initial and final activity was determined by performing HDS experiments at industrial conditions in a laboratory mini-scale hydrotreater. The results show that the deactivation of the catalyst samples collected from three different places of the industrial reactor do not vary significantly, the maximum difference among the catalyst samples, being less than 4%. The experimentally determined deactivation level of the catalyst samples is compared with the deactivation estimated for the same industrial reactor and the same load using a hybrid neural network model trained with operational data of the industrial and the results are in close agreement. Catalyst deactivation appears to be faster for hydrogen consumption reactions than for hydrodesulphurization reactions indicating a decreasing hydrogen consumption trend with time in operation for specific sulphur content in the product.

L.E. Kallinikos; G.D. Bellos; N.G. Papayannakos

2008-01-01T23:59:59.000Z

71

Modular Pebble-Bed Reactor Project: Laboratory-Directed Research and Development Program FY 2002 Annual Report  

SciTech Connect (OSTI)

This report documents the results of our research in FY-02 on pebble-bed reactor technology under our Laboratory Directed Research and Development (LDRD) project entitled the Modular Pebble-Bed Reactor. The MPBR is an advanced reactor concept that can meet the energy and environmental needs of future generations under DOEs Generation IV initiative. Our work is focused in three areas: neutronics, core design and fuel cycle; reactor safety and thermal hydraulics; and fuel performance.

Petti, David Andrew; Dolan, Thomas James; Miller, Gregory Kent; Moore, Richard Leroy; Terry, William Knox; Ougouag, Abderrafi Mohammed-El-Ami; Oh, Chang H; Gougar, Hans D

2002-11-01T23:59:59.000Z

72

Laboratory Toxicity and Field Effects of a Complex Mixture: Oil-field Produced Water.  

E-Print Network [OSTI]

??This dissertation investigated how organisms in the field and the laboratory responded to complex mixtures or combinations of stressors. Organisms are continually exposed to natural (more)

Fisher, Jonathan C.

2010-01-01T23:59:59.000Z

73

Field Operations Management .:. Lawrence Berkeley National Laboratory  

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

Home OCFO Financial Calendar Home OCFO Financial Calendar Quicklinks: A-Z Index for the OCFO Berkeley Lab Home Contact Us: By Group Contact Us: By Subject Contact Us: Full Listing Employment Financial Systems Modernization (F$M) Fiscal Close Forms: By Group Forms: Full Listing Glossary OCFO EH&S OCFO HR OCFO Home Policies Signature Authority ---------------------------------- UCOP University of California DOE CFO U.S. Department of Energy --------------------------------- Cost Accounting Standards DOE Accounting Handbook Federal Accounting Standards Generally Accepted Accounting Principles OMB Circular Regulations & Procedures Manual (RPM) UC Accounting Manual UC/DOE Prime Contract (Contract 31) CFO Departments: Budget Office Business Systems Analysis Conference Services Controller's Office Field Operations Management Financial Policy & Assurance Procurement & Property Office of Sponsored Projects & Industry Partnerships Training Travel Office

74

Materials Physics Applications: The National High Magnetic Field Laboratory  

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

Search Search National High Magnetic Field Laboratory, NHMFL Home About Us Organization DIVISION Materials Physics and Applications Division GROUPS Superconductivity Technology Center Condensed Matter and Magnet Science Center for Integrated Nanotechnologies Sensors & Electrochemical Devices Materials Chemistry CONTACTS Group Leader Mike Hundley Director, NHMFL-PFF/Deputy Group Leader Chuck Mielke Head of Users Program Operations Jon Betts Professional Staff Assistant Julie T. Gallegos TA-03 Group Office TA-03, Building 0034, Room 101 Office Administrator Juanita Armijo TA-35 Group Office TA-35, Building 0127, Room C117 Office Administrator Angeline Willow 505-667-5032 National High Magnetic Field Laboratory, Pulsed Field Facility The Pulsed Field Facility at Los Alamos National Laboratory in Los Alamos, New Mexico, is one of three campuses of the National High Magnetic Field Laboratory (NHMFL), the other two being at Florida State University, Tallahassee (continuous fields, magnetic resonance, and general headquarters) and the University of Florida ,Gainesville(ultra-low temperatures at high magnetic fields). The NHMFL is sponsored primarily by the National Science Foundation, Division of Materials Research, with additional support from the State of Florida and the US Department of Energy.

75

The National High Magnetic Field Laboratory: Condensed Matter Science in Continuous Magnetic Fields  

Science Journals Connector (OSTI)

The National High Magnetic Field Laboratory (NHMFL) operates three facilities ... Tallahassee, Florida, the ultra-low-temperature high-magnetic-field facilities are located at the University ... scientific achiev...

M. D. Bird; J. E. Crow; P. Schlottmann

2003-10-01T23:59:59.000Z

76

Review of the Oak Ridge National Laboratory High Flux Isotope Reactor Implementation Verification Review Processes  

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

Independent Oversight Review of the Independent Oversight Review of the Oak Ridge National Laboratory High Flux Isotope Reactor Implementation Verification Review Processes May 2011 January 2013 Office of Safety and Emergency Management Evaluations Office of Enforcement and Oversight Office of Health, Safety and Security U. S. Department of Energy Table of Contents 1.0 Purpose ................................................................................................................................................. 1 2.0 Background........................................................................................................................................... 1 3.0 Scope..................................................................................................................................................... 2

77

Review of the Oak Ridge National Laboratory High Flux Isotope Reactor Implementation Verification Review Processes  

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

Independent Oversight Review of the Independent Oversight Review of the Oak Ridge National Laboratory High Flux Isotope Reactor Implementation Verification Review Processes May 2011 January 2013 Office of Safety and Emergency Management Evaluations Office of Enforcement and Oversight Office of Health, Safety and Security U. S. Department of Energy Table of Contents 1.0 Purpose ................................................................................................................................................. 1 2.0 Background........................................................................................................................................... 1 3.0 Scope..................................................................................................................................................... 2

78

Environmental Assessment for Decontamination and Decommissioning of the Juggernaut Reactor at Argonne National Laboratory … East Argonne, Illinois  

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

DOE/EA-1483 DOE/EA-1483 Environmental Assessment for Decontamination and Decommissioning of the Juggernaut Reactor at Argonne National Laboratory - East Argonne, Illinois March 2004 U.S. Department of Energy Chicago Operations Office Argonne Area Office Argonne, Illinois Environmental Assessment for Decontamination and Decommissioning of the Juggernaut Reactor at Argonne National Laboratory - East Argonne, Illinois Table of Contents Acronyms....................................................................................................................................... iii 1.0 Background ..........................................................................................................................1 1.1 Facility History ........................................................................................................1

79

Memorandum Approval of a Permanenet Variance Regarding Static Magnetic Fields at Brookhaven National Laboratory (Variance 1021)  

Broader source: Energy.gov [DOE]

Approval of a Permanenet Variance Regarding Static Magnetic Fields at Brookhaven National Laboratory (Variance 1021)

80

A field laboratory for improved oil recovery. Final report  

SciTech Connect (OSTI)

The purpose of Annex III of the Memorandum of Understanding, undertaken by the Houston Petroleum Research Center at the University of Houston, was to develop a field laboratory for research in improved oil recovery using a Gulf Coast reservoir in Texas. The participants: (1) make a field site selection and conducted a high resolution seismic survey in the demonstration field, (2) obtained characteristics of the reservoir (3) developed an evaluation of local flood efficiency in different parts of the demonstration reservoir, (4) used diverse methodology to evaluate the potential recovery of the remaining oil in the test reservoir, (5) developed cross-well seismic tomography, and (6) will transfer the learned technologies to oil operators through publication and workshops. This abstract is an overview of these tasks.

Hildebrandt, A.F.; McDonald, J.; Claridge, E.; Killough, J.

1992-09-01T23:59:59.000Z

Note: This page contains sample records for the topic "reactors laboratory field" 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

PROJECT-SPECIFIC TYPE A VERIFICATION FOR THE HIGH FLUX BEAM REACTOR UNDERGROUND UTILITIES REMOVAL PHASE 3 TRENCH 5, BROOKHAVEN NATIONAL LABORATORY UPTON, NEW YORK  

SciTech Connect (OSTI)

5098-SR-04-0 PROJECT-SPECIFIC TYPE A VERIFICATION FOR THE HIGH FLUX BEAM REACTOR UNDERGROUND UTILITIES REMOVAL PHASE 3 TRENCH 5, BROOKHAVEN NATIONAL LABORATORY

P.C. Weaver

2010-11-03T23:59:59.000Z

82

PROJECT-SPECIFIC TYPE A VERIFICATION FOR THE HIGH FLUX BEAM REACTOR UNDERGROUND UTILITIES REMOVAL PHASE 3 TRENCH 1, BROOKHAVEN NATIONAL LABORATORY UPTON, NEW YORK  

SciTech Connect (OSTI)

5098-SR-05-0 PROJECT-SPECIFIC TYPE A VERIFICATION FOR THE HIGH FLUX BEAM REACTOR UNDERGROUND UTILITIES REMOVAL PHASE 3 TRENCH 1 BROOKHAVEN NATIONAL LABORATORY

E.M. Harpenau

2010-12-15T23:59:59.000Z

83

A laboratory and field investigation of naphthenic acid corrosion inhibition  

SciTech Connect (OSTI)

This paper presents results of a laboratory and field study of naphthenic acid corrosion and the development of an effective chemical inhibitor for this type of corrosive attack. In the laboratory corrosion test, which involved 20 hour weight loss measurements in high flash solvent with a total acid number (TAN) of 16 mg KOH/gm at a temperature of 600 F (316 C), blank corrosion rates averaged 140 to 150 mpy (3.56 to 3.81 mm/y). Inhibited rates averaged about 10 to 12 mpy (0.254 to 0.305 mm/y). The field test was carried out on a heavy vacuum gas oil (HVGO) stream at 550 F (288 C) . Blanks varied from a high of 425 mpy (10.79 mm/y) for a 24 hour test to a low of about 100 mpy (2.54 mm/y) for a 150 hour test. Both electrical resistance (ER) probes and weight loss coupons showed corrosion rates below 5 mpy (0.127 mm/y) as long as they were adequately passivated. Passivation consisted of exposing the coupons to a high inhibitor dosage for a relatively short time to establish a protective layer on the metal surface. Acceleration of corrosion rates by the interaction between some reportedly corrosive refinery fluids and HCl vapor is also demonstrated. A model, which represents naphthenic acid and other potentially corrosive materials as nonaqueous electrolytes, is presented.

Zetlmeisl, M.J. [Petrolite Corp., St. Louis, MO (United States)

1995-11-01T23:59:59.000Z

84

Environmental Assessment for Decontamination and Decommissioning of the Juggernaut Reactor at Argonne National Laboratory … East Argonne, Illinois  

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

Finding of No Significant Impact Finding of No Significant Impact Proposed Decontamination and Decommissioning of the Juggernaut Reactor at Argonne National Laboratory - East Argonne, Illinois AGENCY: U. S. Department of Energy (DOE) ACTION: Finding of No Significant Impact (FONSI) SUMMARY: DOE has prepared an Environmental Assessment (EA), DOE/EA-1483, evaluating the decontamination and decommissioning of the Juggernaut Reactor at Argonne National Laboratory-East (ANL-E), in Argonne, Illinois. The decontamination and decommissioning of the reactor is needed to ensure the protection of the health and safety of the public, DOE and contractor employees, and the environment, consistent with DOE Order 5400.5, Radiation Protection of the Public and the Environment. Based on the analysis in the EA, DOE has determined that the proposed action does not

85

Investigation of the November 8, 2011, Plutonium Contamination in the Zero Power Physics Reactor Facility, at the Idaho National Laboratory  

Broader source: Energy.gov [DOE]

On November 8, 2011, workers at the Idaho National Laboratory (INL) Materials and Fuels Complex (MFC) Zero Power Physics Reactor (ZPPR) Facility were packaging plutonium (Pu) reactor fuel plates. Two of the fuel storage containers had atypical labels indicating potential abnormalities with the fuel plates located inside. Upon opening one of the storage containers, the workers discovered a Pu fuel plate wrapped in plastic and tape. When the workers attempted to remove the wrapping material, an uncontrolled release of radioactive contaminants occurred, resulting in the contamination of 16 workers and the facility

86

Decontamination and decommissioning of the Experimental Boiling Water Reactor (EBWR): Project final report, Argonne National Laboratory  

SciTech Connect (OSTI)

The Final Report for the Decontamination and Decommissioning (D&D) of the Argonne National Laboratory - East (ANL-E) Experimental Boiling Water Reactor (EBWR) facility contains the descriptions and evaluations of the activities and the results of the EBWR D&D project. It provides the following information: (1) An overall description of the ANL-E site and EBWR facility. (2) The history of the EBWR facility. (3) A description of the D&D activities conducted during the EBWR project. (4) A summary of the final status of the facility, including the final and confirmation surveys. (5) A summary of the final cost, schedule, and personnel exposure associated with the project, including a summary of the total waste generated. This project report covers the entire EBWR D&D project, from the initiation of Phase I activities to final project closeout. After the confirmation survey, the EBWR facility was released as a {open_quotes}Radiologically Controlled Area,{close_quotes} noting residual elevated activity remains in inaccessible areas. However, exposure levels in accessible areas are at background levels. Personnel working in accessible areas do not need Radiation Work Permits, radiation monitors, or other radiological controls. Planned use for the containment structure is as an interim transuranic waste storage facility (after conversion).

Fellhauer, C.R.; Boing, L.E. [Argonne National Lab., IL (United States); Aldana, J. [NES, Inc., Danbury, CT (United States)

1997-03-01T23:59:59.000Z

87

Rocketdyne Division annual site environmental report Santa Susana Field Laboratory and Desoto sites 1995  

SciTech Connect (OSTI)

This annual report discusses environmental monitoring at two manufacturing and test operations sites operated in the Los Angeles area by the Rocketdyne Division of Rockwell International Corporation (Rocketdyne). These are identified as the Santa Susana Field Laboratory (SSFL) and the DeSoto site. The sites have been used for manufacturing, R&D, engineering, and testing in a broad range of technical fields, primarily rocket engine propulsion and nuclear reactor technology. The DeSoto site essentially comprises office space and light industry with no remaining radiological operations, and has little potential impact on the environment. The SSFL site, because of its large size (2,668 acres), warrants comprehensive monitoring to assure protection of the environment. SSFL consists of four administrative areas used for research, development, and test operations as well as a buffer zone. A portion of Area I and all of Area II are owned by the U.S. Government and assigned to the National Aeronautics and Space Administration (NASA). A portion of Area IV is under option for purchase by the Department of Energy (DOE).

NONE

1996-07-30T23:59:59.000Z

88

National High Magnetic Field Laboratory - Science Starts Here...  

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

Cedomir Petrovic Cedomir Petrovic Cedomir Petrovic. Name Cedomir Petrovic. Current position Physicist, Brookhaven National Laboratory, and Adjunct Assistant Professor of Physics,...

89

Memorandum, Approval of a Permanent Variance Regarding Static Magnetic Fields at Brookhaven National Laboratory (Variance 102 1)  

Broader source: Energy.gov [DOE]

Approval of a Permanenet Variance Regarding Static Magnetic Fields at Brookhaven National Laboratory (Variance 1021)

90

Verification Survey of the Building 315 Zero Power Reactor-6 Facility, Argonne National Laboratory-East, Argonne, Illinois  

SciTech Connect (OSTI)

Oak Ridge Institute for Science and Education (ORISE) conducted independent verification radiological survey activities at Argonne National Laboratorys Building 315, Zero Power Reactor-6 facility in Argonne, Illinois. Independent verification survey activities included document and data reviews, alpha plus beta and gamma surface scans, alpha and beta surface activity measurements, and instrumentation comparisons. An interim letter report and a draft report, documenting the verification survey findings, were submitted to the DOE on November 8, 2006 and February 22, 2007, respectively (ORISE 2006b and 2007).

W. C. Adams

2007-05-25T23:59:59.000Z

91

Compact-Toroid Fusion Reactor (CTOR) based on the Field-Reversed Theta Pinch  

SciTech Connect (OSTI)

Scoping studies of a translating Compact Torus Reactor (CTOR) have been made on the basis of a dynamic plasma model and an overall systems approach. This CTOR embodiment uses a Field-Reversed Theta Pinch as a plasma source. The field-reversed plasmoid would be formed and compressionally heated to ignition prior to injection into and translation through a linear burn chamber, thereby removing the high-technology plamoid source from the hostile reactor environment. Stabilization of the field-reversed plasmoid would be provided by a passive conducting shell located outside the high-temperature blanket but within the low-field superconducting magnets and associated radition shielding. On the basis of this batch-burn but thermally steady-state approach, a reactor concept emerges with a length below approx. 40 m that generates 300 to 400 MWe of net electrical power with a recirculating power fraction less than 0.15.

Hagenson, R.L.; Krakowski, R.A.

1981-01-01T23:59:59.000Z

92

National High Magnetic Field Laboratory: Museum of Electricity...  

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

chemistry. Related Electricity & Magnetism Pages Interactive Java Tutorials: Magnetic Field Lines Around a Wire Interactive Java Tutorials: Magnetic Field Lines Around a Wire, II...

93

National High Magnetic Field Laboratory: Museum of Electricity...  

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

Pages Interactive Java Tutorials: Galvanometer Interactive Java Tutorials: Magnetic Field Lines Around a Wire, I Interactive Java Tutorials: Magnetic Field Lines Around a Wire,...

94

National High Magnetic Field Laboratory - Science Starts Here...  

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

a better and much more productive scientist. I had the opportunity to learn unique high magnetic field experimental techniques from the top researchers in the field, in a...

95

National High Magnetic Field Laboratory: Museum of Electricity...  

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

strength of a magnetic field. He also made significant contributions to our understanding of the Earth's magnetic field. Related Electricity & Magnetism Pages Timeline: 1830 - 18...

96

National High Magnetic Field Laboratory: Museum of Electricity...  

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

of the Earths magnetic field to the research community. Related Electricity & Magnetism Pages Interactive Java Tutorials: Compasses in Magnetic Fields Interactive Java...

97

National High Magnetic Field Laboratory Audio Dictionary: Magnetic...  

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

Links Magnets from Mini to Mighty Meet the Magnets How to Make an Electromagnet (audio slideshow) Compasses in Magnetic Fields (interactive tutorial) Magnetic Field Around a...

98

Plan for fully decontaminating and decommissioning of the Westinghouse Advanced Reactors Division Fuel Laboratories at Cheswick, Revision 3  

SciTech Connect (OSTI)

The project scope of work included the complete decontamination and decommissioning (D and D) of the Westinghouse ARD Fuel Laboratories at the Cheswick Site in the shortest possible time. This has been accomplished in the following four phases: (1) preparation of documents and necessary paperwork; packaging and shipping of all special nuclear materials in an acceptable form to a reprocessing agency; (2) decontamination of all facilities, glove boxes and equipment; loading of generated waste into bins, barrels and strong wooden boxes; (3) shipping of all bins, barrels and boxes containing waste to the designated burial site; removal of all utility services from the laboratories; (4) final survey of remaining facilities and certification for nonrestricted use; preparation of final report. This volume contains the following 3 attachments: (1) Plan for Fully Decontamination and Decommissioning of the Westinghouse Advanced Reactors Division Fuel Laboratories at Cheswick; (2) Environmental Assessment for Decontamination and Decommissioning the Westinghouse Advanced Reactors Division Plutonium Fuel Laboratories, Cheswick, PA; and (3) WARD-386, Quality Assurance Program Description for Decontamination and Decommissioning Activities.

Not Available

1982-01-01T23:59:59.000Z

99

National High Magnetic Field Laboratory: An Introduction to Magnets...  

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

is a magnet); opposite poles attract, like poles repel. In all magnets, the magnetic field lines run from south to north, and these fields are what produce forces on other...

100

Validation of the neutron and gamma fields in the JSI TRIGA reactor using in-core fission and ionization chambers  

Science Journals Connector (OSTI)

Abstract CEA developed fission chambers and ionization chambers were utilized at the JSI TRIGA reactor to measure neutron and gamma fields. The measured axial fission rate distributions in the reactor core are generally in good agreement with the calculated values using the Monte Carlo model of the reactor thus verifying both the computational model and the fission chambers. In future, multiple absolutely calibrated fission chambers could be used for more accurate online reactor thermal power monitoring.

Gaper erovnik; Tanja Kaiba; Vladimir Radulovi?; Ane Jazbec; Sebastjan Rupnik; Loc Barbot; Damien Fourmentel; Luka Snoj

2015-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "reactors laboratory field" 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

National High Magnetic Field Laboratory: Museum of Electricity...  

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

diagnostic cardiology and even helped garner a Nobel Prize. Electrocardiograph The field of electrophysiology dates back to Italian physician Luigi Galvani, and scientists...

102

National High Magnetic Field Laboratory: Museum of Electricity...  

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

which at the receiving end flowed through an electromagnet. This created a magnetic field that caused the receivers metal key to be attracted to an underlying plate,...

103

National High Magnetic Field Laboratory Slideshow: Seeing Magnetic...  

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

more about magnets You can start here with a straightforward rundown. Compasses in Magnetic Fields Experiment with the compass in this tutorial to see how it responds to...

104

National High Magnetic Field Laboratory: Team Tesla - How we...  

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

resistive magnets (also called electromagnets or Bitter magnets), ranging in magnetic field from 20 tesla to 45 tesla, each in its own little cell. These magnets get so...

105

National High Magnetic Field Laboratory - Science Starts Here...  

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

correlated electron systems is neutron scattering, often in conjunction with applied magnetic fields. In his own words My experience at the Magnet Lab gave me an early...

106

National High Magnetic Field Laboratory: Museum of Electricity...  

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

navigate the seas, effectively changing the course of history. Related Electricity & Magnetism Pages Museum: Lodestone Timeline: 600 1599 Tutorial: Compasses in Magnetic Fields...

107

National High Magnetic Field Laboratory: Museum of Electricity...  

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

high-tech field, gradually being replaced by semiconductors. Related Electricity & Magnetism Pages Magnetic Core Memory: Interactive Java Tutorial Magnetic core memory was...

108

Plasma engineering design of a compact reversed-field pinch reactor (CRFPR)  

SciTech Connect (OSTI)

The rationale for and the characteristics of the high-power-density Compact Reversed-Field Pinch Reactor (CRFPR) are discussed. Particular emphasis is given to key plasma engineering aspects of the conceptual design, including plasma operations, current drive, and impurity/ash control by means of pumped limiters or magnetic divertors. A brief description of the Fusion-Power-Core integration is given.

Bathke, C.G.; Embrechts, M.J.; Hagenson, R.L.; Krakowski, R.A.; Miller, R.L.

1983-01-01T23:59:59.000Z

109

SRS Small Modular Reactors  

SciTech Connect (OSTI)

The small modular reactor program at the Savannah River Site and the Savannah River National Laboratory.

None

2012-04-27T23:59:59.000Z

110

SRS Small Modular Reactors  

ScienceCinema (OSTI)

The small modular reactor program at the Savannah River Site and the Savannah River National Laboratory.

None

2014-05-21T23:59:59.000Z

111

National High Magnetic Field Laboratory Slideshow: How to Make...  

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

easy, fun and most can be done with stuff you have around the house. Compasses in Magnetic Fields Experiment with the compass in this tutorial to see how it responds to...

112

National High Magnetic Field Laboratory: Museum of Electricity...  

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

of the composition of light. Light, of course, is a form of energy. A magnetic field changes the behavior of light - a phenomenon known as the Zeeman effect. The Zeeman...

113

National High Magnetic Field Laboratory - Magnets and Materials...  

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

W.D. and Weijers, H.W., Helium gas bubble trapped in liquid helium in high magnetic field, Appl. Phys. Lett., 104, 133511 (2014) read online 2 Bai, H.; Marshall, W.S.; Bird,...

114

National High Magnetic Field Laboratory - Flux: Volume 3, Issue...  

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

not Stephanie Law, who was practially an old-timer when she arrived at the Mag Lab. gauss lines Pregnancy to pacemakers: safety around high magnetic fields First things first......

115

National High Magnetic Field Laboratory - Try This at Home  

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

fun and most can be done with stuff you have around the house. Create your own magnetic field lines, expose the iron in your cereal, or make an electromagnet from scratch Your...

116

National High Magnetic Field Laboratory: An Introduction to Magnets...  

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

resistive magnet is here at the Magnet Lab: It can generate a sustained magnetic field of 35 tesla. (Were not counting here our world-record hybrid magnet or the stronger,...

117

National High Magnetic Field Laboratory Slideshow: Making an...  

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

Create your own magnetic field lines, expose the iron in your cereal, or make an electromagnet from scratch Your teachers or parents may even want to get in on the fun. Magnets...

118

National High Magnetic Field Laboratory - Ion Cyclotron Resonance...  

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

of Radial Ion Motion in RF-Only Multipole Ion Guides Immersed in a Strong Magnetic Field Gradient, J. Am. Soc. Mass Spectr., 22, 591-601 (2011) 2 Blakney, G.T.; Hendrickson,...

119

National High Magnetic Field Laboratory - Science Starts Here...  

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

technology. The Magnet Lab is a wonderful environment for nurturing students in high magnetic field research. The group that I worked in conducted leading-edge research in high...

120

National High Magnetic Field Laboratory - Making a Compass Activity  

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

the south pole of the other. This is why compasses work on the Earth. The Earths magnetic field is strong enough to make the north pole of a very light compass needle align...

Note: This page contains sample records for the topic "reactors laboratory field" 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

National High Magnetic Field Laboratory: Museum of Electricity...  

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

it lacked sophistication, he was able to use the model to formulate his own law of magnetism. Magnetometers are used in many different fields; they are used in geophysics,...

122

EIS-0402: Santa Susana Field Laboratory Area IV, California | Department of  

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

2: Santa Susana Field Laboratory Area IV, California 2: Santa Susana Field Laboratory Area IV, California EIS-0402: Santa Susana Field Laboratory Area IV, California Summary This EIS evaluates the environmental impacts of remediation of Area IV of the Santa Susana Field Laboratory (SSFL Area IV). SSFL Area IV, occupying approximately 290 acres of the total 2,852-acre SSFL site is located in the hills between Chatsworth and Simi Valley, CA, and was developed as a remote site to test rocket engines and conduct nuclear research. This EIS will evaluate alternatives for disposition of radiological facilities and support buildings, remediation of the affected environment, and disposal of all resulting waste at existing, approved sites. Public Comment Opportunities No public comment opportunities available at this time.

123

New Field Laboratories and Related Research To Help Promote Environmentally Prudent Development of Unconventional Resources  

Broader source: Energy.gov [DOE]

Today, the Department of Energy announced the selection of three multiyear, field laboratories and six other multiyear research projects for continued research to promote environmentally prudent development of unconventional oil and natural gas resources.

124

Field and laboratory investigations of selenium transformation. Quarterly report  

SciTech Connect (OSTI)

This quarterly report discusses the preparation and results of a field investigation of a selected coal mine site in Oklahoma. The field investigation has been on-going since July 1990. An analysis of this data would be useful in providing information for potential Se mobility from a coal mine site and the distribution of Se in a soil profile of reclaimed land. Also, included is the investigation and preliminary results of SeO{sub 3}{sup 2{minus}} adsorption and desorption using different soil media, including coal mine spoils (overburden).

Atalay, A.; Koll, K.J.

1990-12-01T23:59:59.000Z

125

Field versus laboratory characterization of clay deposits for use as in situ municipal landfill liners  

E-Print Network [OSTI]

FIELD VERSUS LABORATORY CHARACTERIZATION OF CLAY DEPOSITS FOR USE AS IN SITU MUNICIPAL LANDFILL LINERS A Thesis by SHARON ELIZABETH WECHSLER Submitted to the Office of Graduate Studies Texas Aa? University in partial fulfillment... of the requirement for the degree of . KASTER OF SCIENCE Nay 1990 Major Subject: Geology FIELD VERSUS LABORATORY CHARACTERIZATION OF CLAY DEPOSITS FOR USE AS IN SITU MUNICIPAL LANDFILL LINERS A Thesis by SHARON ELIZABETH WECHSLER Approved as to style...

Wechsler, Sharon Elizabeth

2012-06-07T23:59:59.000Z

126

Grazercollector facilitation hypothesis supported by laboratory but not field experiments  

E-Print Network [OSTI]

levels in flume water, but only Physa facilitated Hydropsyche growth. In the field, we manipulated Physa, despite high power to detect such interactions. We suspect that grazer�collector facilitation la facilitation brouteurs�collecteurs n'a pas �t� observ�e en nature car, contrairement � ce qui se

Heard, Stephen B.

127

Comparison of field and laboratory-simulated drill-off tests  

SciTech Connect (OSTI)

In this paper, field drill-off test results are compared with data from laboratory simulations. A simple theory for analyzing drill-off tests is developed. The weight-on bit (WOB) decay with time is close to exponential, but large threshold WOB's, resulting from poor weight transmission downhole, are sometimes observed in field tests.

Bourdon, J.C.; Peltier, B. (Sedco-Forex Technical Centre (USA)); Cooper, G.A. (Univ. of California, Berkley, CA (USA)); Curry, D.A. (International Drilling and Downhole Technology Centre in Aberdeen (Great Britian)); McCann, D. (Sedco-Forex Technical Centre (USA))

1989-12-01T23:59:59.000Z

128

Magnetic fields in fast breeder reactors: New results on thermoelectricity and dynamo effects  

SciTech Connect (OSTI)

This paper deals with magnetic field calculations in Liquid Metal Fast Breeder Reactors (LMFBR) in order to give a quantitative estimation of the possible origins of magnetohydrodynamic instability. In the first part, following an estimation made by previous researchers, two improved methods aimed at calculating the magnetic field generated by thermoelectric currents flowing in the reactor are presented: although very different, both give similar results. In the second part, dynamo action is investigated for a Ponomarenko model with nonhomogeneous material properties, allowing a more realistic estimate of critical conditions for self-excitation in a LMFBR. The results confirm the decrease of the critical magnetic Reynolds number when the external medium has either a high electrical conductivity or a high magnetic permeability.

Marty, Ph.; Ajakh, A. [Centre National de la Recherche Scientifique, Grenoble (France); Thess, A. [Forschungszentrum, Dresden (Germany)

1995-04-01T23:59:59.000Z

129

CRAD, DOE Oversight- Oak Ridge National Laboratory High Flux Isotope Reactor  

Broader source: Energy.gov [DOE]

A section of Appendix C to DOE G 226.1-2 "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of Criteria Review and Approach Documents (CRADs) used for a DOE independent oversight assessment of the Oak Ridge National Laboratory programs for oversight of its contractors.

130

Laboratory and pilot field-scale testing of surfactants for environmental restoration of chlorinated solvent DNAPLs  

SciTech Connect (OSTI)

This project is composed of two phases and has the objective of demonstrating surfactant-enhanced aquifer remediation (SEAR) as a practical remediation technology at DOE sites with ground water contaminated by dense, non-aqueous phase liquids (DNAPLs), in particular, chlorinated solvents. The first phase of this project, Laboratory and Pilot Field Scale Testing, which is the subject of the work so far, involves (1) laboratory experiments to examine the solubilization of multiple component DNAPLs, e.g., solvents such as perchloroethylene (PCE) and trichloroethylene (TCE), by dilute surfactant solutions, and (2) a field test to demonstrate SEAR technology on a small scale and in an existing well.

Jackson, R.E. [INTERA, Inc., Austin, TX (United States); Fountain, J.C. [State Univ. of New York, Buffalo, NY (United States)

1994-12-31T23:59:59.000Z

131

Outdoor field evaluation of passive tritiated water vapor samplers at Canadian power reactor sites  

SciTech Connect (OSTI)

Tritium is one of several radioactive nuclides routinely monitored in and around CANDU{reg_sign} (CANada Deuterium Uranium) power reactor facilities. Over the last ten years, passive samplers have replaced active sampling devices for sampling tritiated water vapor in the workplace at many CANDU stations. The potential of passive samplers for outdoor monitoring has also been realized. This paper presents the result of a 1-y field trial carried out at all five Canadian CANDU reactor sites. The results indicate that passive samplers can be used at most sampling locations to measure tritiated water vapor in air concentrations as low as 1 Bq m{sup -3} over a 30-d sampling period. Only in one of the five sampling locations was poor agreement observed between active and passive monitoring data. This location, however, was very windy and it is suspected that the gusty winds were the source of the discrepancies observed. 15 refs., 8 figs., 1 tab.

Wood, M.J. [Chalk River Lab., Chalk River, Ontario (Canada)

1996-02-01T23:59:59.000Z

132

The hybrid reactor project based on the straight field line mirror concept  

SciTech Connect (OSTI)

The straight field line mirror (SFLM) concept is aiming towards a steady-state compact fusion neutron source. Besides the possibility for steady state operation for a year or more, the geometry is chosen to avoid high loads on materials and plasma facing components. A comparatively small fusion hybrid device with 'semi-poor' plasma confinement (with a low fusion Q factor) may be developed for industrial transmutation and energy production from spent nuclear fuel. This opportunity arises from a large fission to fusion energy multiplication ratio, Q{sub r} = P{sub fis}/P{sub fus}>>1. The upper bound on Q{sub r} is primarily determined by geometry and reactor safety. For the SFLM, the upper bound is Q{sub r} Almost-Equal-To 150, corresponding to a neutron multiplicity of k{sub eff}=0.97. Power production in a mirror hybrid is predicted for a substantially lower electron temperature than the requirement T{sub e} Almost-Equal-To 10 keV for a fusion reactor. Power production in the SFLM seems possible with Q Almost-Equal-To 0.15, which is 10 times lower than typically anticipated for hybrids (and 100 times smaller than required for a fusion reactor). This relaxes plasma confinement demands, and broadens the range for use of plasmas with supra-thermal ions in hybrid reactors. The SFLM concept is based on a mirror machine stabilized by qudrupolar magnetic fields and large expander tanks beyond the confinement region. The purpose of the expander tanks is to distribute axial plasma loss flow over a sufficiently large area so that the receiving plates can withstand the heat. Plasma stability is not relying on a plasma flow into the expander regions. With a suppressed plasma flow into the expander tanks, a possibility arise for higher electron temperature. A brief presentation will be given on basic theory for the SFLM with plasma stability and electron temperature issues, RF heating computations with sloshing ion formation, neutron transport computations with reactor safety margins and material load estimates, magnetic coil designs as well as a discussion on the implications of the geometry for possible diagnostics. Reactor safety issues are addressed and a vertical orientation of the device could assist passive coolant circulation. Specific attention is put to a device with a 25 m long confinement region and 40 cm plasma radius in the mid-plane. In an optimal case (k{sub eff}= 0.97) with a fusion power of only 10 MW, such a device may be capable of producing a power of 1.5 GW{sub th}.

Agren, O.; Noack, K.; Moiseenko, V. E.; Hagnestal, A.; Kaellne, J.; Anglart, H. [Uppsala University, Angstroem Laboratory, Uppsala University, Box 534, SE-751 21 Uppsala (Sweden); Institute of Plasma Physics, National Science Center 'Kharkiv Institute of Physics and Technology', 61108 Kharkiv (Ukraine); Uppsala University, Angstroem Laboratory, Uppsala University, Box 534, SE-751 21 Uppsala (Sweden); Royal Institute of Technology, Nuclear Reactor Technology, SE 100 44 Stockholm (Sweden)

2012-06-19T23:59:59.000Z

133

Neutron Scattering Science User Office, neutronusers@ornl.gov or (865) 574-4600. Proposals for beam time at Oak Ridge National Laboratory's High Flux Isotope Reactor (HFIR)  

E-Print Network [OSTI]

Neutron Scattering Science User Office, neutronusers@ornl.gov or (865) 574-4600. Proposals for beam Wildgruber, wildgrubercu@ornl.gov. VISION CallforProposals neutrons.ornl.gov Neutron Scattering Science - Oak time at Oak Ridge National Laboratory's High Flux Isotope Reactor (HFIR) and Spallation Neutron Source

Pennycook, Steve

134

Google+ Virtual Field Trip on Vehicle Electrification at Argonne National Laboratory  

Broader source: Energy.gov [DOE]

Don't miss this exclusive peek into the U.S. Department of Energy's Argonne National Laboratory. Attendees will meet three researchers who will explain a different phase of vehicle electrification research. This field trip is very similar to the tou

135

Symmetry Breaking in Graphene Gregory S. Boebinger, National High Magnetic Field Laboratory  

E-Print Network [OSTI]

Symmetry Breaking in Graphene Gregory S. Boebinger, National High Magnetic Field Laboratory DMR. In this experiment, Landau levels in graphene were used to study the breaking of SU(4) symmetry--a higher dimensional states by their spin polarization. It was found that graphene turns into either a spin ferromagnet

Weston, Ken

136

Evaluations of Transgenic Potatoes for Resistance to Potato Tuberworm in the Laboratory and Field  

E-Print Network [OSTI]

Evaluations of Transgenic Potatoes for Resistance to Potato Tuberworm in the Laboratory and Field online: 7 October 2010 # Potato Association of America 2010 Abstract The potato variety `Spunta to potato tuberworm (Phthorimaea operculella Zeller). Because potato tuberworm is becoming a serious pest

Douches, David S.

137

2012 Annual Planning Summary for Fossil Energy, National Energy Technology Laboratory, RMOTC, and Strategic Petroleum Reserve Field Office  

Broader source: Energy.gov [DOE]

The ongoing and projected Environmental Assessments and Environmental Impact Statements for 2012 and 2013 within Fossil Energy, National Energy Technology Laboratory, RMOTC, and Strategic Petroleum Reserve Field Office.

138

2011 Annual Industrial Wastewater Reuse Report for the Idaho National Laboratory Site's Advanced Test Reactor Complex Cold Waste Pond  

SciTech Connect (OSTI)

This report describes conditions, as required by the state of Idaho Industrial Wastewater Reuse Permit (LA 000161 01, Modification B), for the wastewater land application site at the Idaho National Laboratory Site's Advanced Test Reactor Complex Cold Waste Pond from November 1, 2010 through October 31, 2011. The report contains the following information: Facility and system description Permit required effluent monitoring data and loading rates Groundwater monitoring data Status of compliance activities Noncompliance and other issues Discussion of the facility's environmental impacts During the 2011 permit year, approximately 166 million gallons of wastewater were discharged to the Cold Waste Pond. This is well below the maximum annual permit limit of 375 million gallons. As shown by the groundwater sampling data, sulfate and total dissolved solids concentrations are highest near the Cold Waste Pond and decrease rapidly as the distance from the Cold Waste Pond increases. Although concentrations of sulfate and total dissolved solids are elevated near the Cold Waste Pond, both parameters were below the Ground Water Quality Rule Secondary Constituent Standards in the down gradient monitoring wells.

Mike Lewis

2012-02-01T23:59:59.000Z

139

Laboratory and field testing of an aerosol-based duct-sealing technology  

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

Laboratory and field testing of an aerosol-based duct-sealing technology Laboratory and field testing of an aerosol-based duct-sealing technology for large commercial buildings. Title Laboratory and field testing of an aerosol-based duct-sealing technology for large commercial buildings. Publication Type Journal Article LBNL Report Number LBNL-44220 Year of Publication 2002 Authors Carrié, François Rémi, Ronnen M. Levinson, Tengfang T. Xu, Darryl J. Dickerhoff, William J. Fisk, Jennifer A. McWilliams, Mark P. Modera, and Duo Wang Journal ASHRAE Transactions Start Page Chapter Date Published January 2002 Abstract Laboratory and field experiments were performed to evaluate the feasibility of sealing leaks in commercial duct systems with an aerosol sealant. The method involves blowing an aerosol through the duct system to seal the leaks from the inside, the principle being that the aerosol particles deposit in the cracks as they try to escape under pressure. It was shown that the seals created with the current sealant material can withstand pressures far in excess of what is found in commercial-building duct systems. We also performed two field experiments in two large-commercial buildings. The ASHRAE leakage classes of the systems were reduced from 653 down to 103, and from 40 down to 3. Methods and devices specifically devised for this application proved to be very efficient at (a) increasing the sealing rate and (b) attaining state-of-the-art duct leakage classes. Additional research is needed to improve the aerosol injection and delivery processes.

140

Type A verification report for the high flux beam reactor stack and grounds, Brookhaven National Laboratory, Upton, New York  

SciTech Connect (OSTI)

The U.S. Department of Energy (DOE) Order 458.1 requires independent verification (IV) of DOE cleanup projects (DOE 2011). The Oak Ridge Institute for Science and Education (ORISE) has been designated as the responsible organization for IV of the High Flux Beam Reactor (HFBR) Stack and Grounds area at Brookhaven National Laboratory (BNL) in Upton, New York. The IV evaluation may consist of an in-process inspection with document and data reviews (Type A Verification) or a confirmatory survey of the site (Type B Verification). DOE and ORISE determined that a Type A verification of the documents and data for the HFBR Stack and Grounds: Survey Units (SU) 6, 7, and 8 was appropriate based on the initial survey unit classification, the walkover surveys, and the final analytical results provided by the Brookhaven Science Associates (BSA). The HFBR Stack and Grounds surveys began in June 2011 and were completed in September 2011. Survey activities by BSA included gamma walkover scans and sampling of the as-left soils in accordance with the BSA Work Procedure (BNL 2010a). The Field Sampling Plan - Stack and Remaining HFBR Outside Areas (FSP) stated that gamma walk-over surveys would be conducted with a bare sodium iodide (NaI) detector, and a collimated detector would be used to check areas with elevated count rates to locate the source of the high readings (BNL 2010b). BSA used the Mult- Agency Radiation Survey and Site Investigation Manual (MARSSIM) principles for determining the classifications of each survey unit. Therefore, SUs 6 and 7 were identified as Class 1 and SU 8 was deemed Class 2 (BNL 2010b). Gamma walkover surveys of SUs 6, 7, and 8 were completed using a 2?2 NaI detector coupled to a data-logger with a global positioning system (GPS). The 100% scan surveys conducted prior to the final status survey (FSS) sampling identified two general soil areas and two isolated soil locations with elevated radioactivity. The general areas of elevated activity identified were investigated further with a collimated NaI detector. The uncollimated average gamma count rate was less than 15,000 counts per minute (cpm) for the SU 6, 7, and 8 composite area (BNL 2011a). Elevated count rates were observed in portions of each survey unit. The general areas of elevated counts near the Building 801 ventilation and operations and the entry to the Stack were determined to be directly related to the radioactive processes in those structures. To compensate for this radioactive shine, a collimated or shielded detector was used to lower the background count rate (BNL 2011b and c). This allowed the surveyor(s) to distinguish between background and actual radioactive contamination. Collimated gamma survey count rates in these shine affected areas were below 9,000 cpm (BNL 2011a). The average background count rate of 7,500 cpm was reported by BSA for uncollimated NaI detectors (BNL 2011d). The average collimated background ranged from 4,500-6,500 cpm in the westernmost part of SU 8 and from 2,000-3,500 cpm in all other areas (BNL 2011e). Based on these data, no further investigations were necessary for these general areas. SU 8 was the only survey unit that exhibited verified elevated radioactivity levels. The first of two isolated locations of elevated radioactivity had an uncollimated direct measurement of 50,000 cpm with an area background of 7,500 cpm (BNL 2011f). The second small area exhibiting elevated radiation levels was identified at a depth of 6 inches from the surface. The maximum reported count rate of 28,000 cpm was observed during scanning (BNL 2011g). The affected areas were remediated, and the contaminated soils were placed in an intermodal container for disposal. BSA's post-remediation walkover surveys were expanded to include a 10-foot radius around the excavated locations, and it was determined that further investigation was not required for these areas (BNL 2011 f and g). The post-remediation soil samples were collected and analyzed with onsite gamma spectroscopy equipment. These samples were also included with the FSS s

Harpenau, Evan M.

2012-01-13T23:59:59.000Z

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


141

Test plan for preparing the Rapid Transuranic Monitoring Laboratory for field deployment  

SciTech Connect (OSTI)

This plan describes experimental work that will be performed during fiscal year 1994 to prepare the Rapid Transuranic Monitoring Laboratory (RTML) for routine field use by US Department of Energy (DOE) Environmental Restoration and Waste Management programs. The RTML is a mobile, field-deployable laboratory developed at the Idaho National Engineering Laboratory (INEL) that provides a rapid, cost-effective means of characterizing and monitoring radioactive waste remediation sites for low-level radioactive contaminants. Analytical instruments currently installed in the RTML include an extended-range, germanium photon analysis spectrometer with an automatic sample changer; two, large-area, ionization chamber alpha spectrometers; and four alpha continuous air monitors. The RTML was field tested at the INEL during June 1993 in conjunction with the Buried Waste Integrated Demonstration`s remote retrieval demonstration. The major tasks described in this test plan are to (a) evaluate the beta detectors for use in screening soil samples for {sup 90}Sr, (b) upgrade the alpha spectral analysis software programs, and (c) upgrade the photon spectral analysis software programs.

McIsaac, C.V.; Sill, C.W.; Gehrke, R.J.; Killian, E.W.; Watts, K.D.

1994-04-01T23:59:59.000Z

142

Scaling methane oxidation: From laboratory incubation experiments to landfill cover field conditions  

SciTech Connect (OSTI)

Evaluating field-scale methane oxidation in landfill cover soils using numerical models is gaining interest in the solid waste industry as research has made it clear that methane oxidation in the field is a complex function of climatic conditions, soil type, cover design, and incoming flux of landfill gas from the waste mass. Numerical models can account for these parameters as they change with time and space under field conditions. In this study, we developed temperature, and water content correction factors for methane oxidation parameters. We also introduced a possible correction to account for the different soil structure under field conditions. These parameters were defined in laboratory incubation experiments performed on homogenized soil specimens and were used to predict the actual methane oxidation rates to be expected under field conditions. Water content and temperature corrections factors were obtained for the methane oxidation rate parameter to be used when modeling methane oxidation in the field. To predict in situ measured rates of methane with the model it was necessary to set the half saturation constant of methane and oxygen, K{sub m}, to 5%, approximately five times larger than laboratory measured values. We hypothesize that this discrepancy reflects differences in soil structure between homogenized soil conditions in the lab and actual aggregated soil structure in the field. When all of these correction factors were re-introduced into the oxidation module of our model, it was able to reproduce surface emissions (as measured by static flux chambers) and percent oxidation (as measured by stable isotope techniques) within the range measured in the field.

Abichou, Tarek, E-mail: abichou@eng.fsu.edu [Florida State University, Tallahassee, FL 32311 (United States); Mahieu, Koenraad; Chanton, Jeff [Florida State University, Tallahassee, FL 32311 (United States); Romdhane, Mehrez; Mansouri, Imane [Unite de Recherche M.A.C.S., Ecole Nationale d'Ingenieurs de Gabes, Route de Medenine, 6029 Gabes (Tunisia)

2011-05-15T23:59:59.000Z

143

Near?fieldfar?field transition of a finite line source using incoherent light: A student laboratory experiment  

Science Journals Connector (OSTI)

A simple experiment employing low cost apparatus is presented which demonstrates the falloff of intensity with distance and the transition from the near field to the far field of a line source filament incandescent light bulb. A derivation of the Poynting vector as a function of the distance away from the filament is presented which shows an exact correspondence to the derivation for the electric field from a finite line charge source in electrostatics. The experimental data of power vs distance from the filament show an inverse first power of the distance falloff in the near field with a smooth transition to an inverse square law behavior in the far field in good agreement with the theoretical expression when corrections for the measured angular response of the detector are included. The experiment provides an illustration of the inverse square law falloff of intensity at large distances from the source experience with simple concepts and techniques of optical radiometry and incoherent light sources and the analogy between incoherent light sources and electrostatics in an undergraduate laboratory. An additional short experiment provides an illustration of electrical?to?optical power conversion efficiency and temperature dependent resistance associated with electronphonon scattering in metals. A derivation of isotropic unpolarized elementary radiators from anisotropic dipole radiation is presented in the Appendix.

Xincheng Yan; Yixin Yu; Louis Shen; Keith H. Wanser

1995-01-01T23:59:59.000Z

144

Ecological Assessment of Hazardous Waste Sites: A Field and Laboratory Reference  

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

Ecological Assessment of Ecological Assessment of Hazardous Waste Sites: A Field and Laboratory Reference U.S. Environmental Protection Agency Environmental Research Laboratory 200 S. W. 35th Street Corvallis, OR 97333 ECOLOGICAL ASSESSMENTS OF HAZARDOUS WASTE SITES: A FIELD AND LABORATORY REFERENCE DOCUMENT Edited By William Warren-Hicks l Benjamin R. Parkhurst 2 Samuel S. Baker, Jr. 1 1 Kilkelly Environmental Associates Highway 70 West - The Water Garden Raleigh, NC 27622 2 Western Aquatics, Inc. P.O. BOX 546 203 Grand Avenue Laramie, WY 82070 DISCLAIMER T h e i n f o r m a t i o n i n t h i s d o c u m e n t h a s b e e n f u n d e d b y t h e U n i t e d S t a t e s Environmental Protection Agent h by Contract Number 68-03-3439 to Kilkelly Environmenta] Associates, Raleig , NC 27622. It has been subject to the Agency's peer and administrative review, and it has been approved for publication as an EPA

145

CRAD, Configuration Management - Oak Ridge National Laboratory...  

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

Configuration Management - Oak Ridge National Laboratory High Flux Isotope Reactor CRAD, Configuration Management - Oak Ridge National Laboratory High Flux Isotope Reactor February...

146

An evaluation of new asphaltene inhibitors: Laboratory study and field testing  

SciTech Connect (OSTI)

Three candidate asphaltene inhibitors have been laboratory tested for their effectiveness on a canadian crude. One inhibitor, an oil-soluble polymeric dispersant developed by Shell Chemicals, showed superior behavior compared with the others; flocculation titrations with n-heptane resulted in an optimum concentration of 1,300 ppm. PVT calculations, however, indicated that the prevailing conditions downhole can be quite favorable with respect to the amount of effective inhibitor compared with the atmospheric laboratory titrations, which appear to be quite sever tests. Therefore, lower initial concentrations were recommended for a field trial. The chemical could be injected continuously through a capillary string, thereby avoiding the lost oil production associated with solvent-cleaning operations. It have proved to be very effective at concentrations as low as 66 ppm, resulting in both a technically and economically successful trial.

Bouts, M.N.; Samuel, A.J. [Koninklijke/Shell Research E and P Laboratorium, Rijswijk (Netherlands); Wiersma, R.J.; Muijs, H.M. [Koninklijke/Shell Laboratorium Amsterdam (Netherlands)

1995-09-01T23:59:59.000Z

147

An evaluation of new asphaltene inhibitors: Laboratory study and field testing  

SciTech Connect (OSTI)

Three candidate asphaltene inhibitors have been laboratory tested for their effectiveness on a Canadian crude. One inhibitor, an oil-soluble polymeric dispersant developed by Shell Chemicals, showed superior behavior compared to the others: flocculation titrations with n-heptane resulted in an optimum concentration of 1,300 ppm. PVT calculations, however, indicated that the prevailing conditions downhole can be quite favorable with respect to the amount of effective inhibitor compared to the atmospheric laboratory titrations which appear to be quite severe tests. Therefore, lower initial concentrations were recommended for a field trial. The chemical could be continuously injected through a capillary string, thereby avoiding the lost oil production associated with solvent cleaning operations. It has proved to be very effective at concentrations as low as 66 ppm, resulting in both a technically and an economically successful trial.

Bouts, M.N.; Wiersma, R.J.; Muijs, H.M.; Samuel, A.J.

1995-11-01T23:59:59.000Z

148

Impact of magnetic field inhomogeneity on electron cyclotron radiative loss in tokamak reactors  

SciTech Connect (OSTI)

The potential importance of electron cyclotron (EC) emission in the local electron power balance in the steady-state regimes of ITER operation with high temperatures, as well as in the DEMO reactor, requires accurate calculation of the one-dimensional (over magnetic surfaces) distribution of the net radiated power density, P{sub EC}({rho}). When the central electron temperature increases to {approx}30 keV, the local EC radiative loss comprises a substantial fraction of the heating power from fusion alphas and is close to the total auxiliary NBI heating power, P{sub EC}(0) Asymptotically-Equal-To 0.3P{sub {alpha}}(0) Asymptotically-Equal-To P{sub aux}(0). In the present paper, the model of EC radiative transport in an axisymmetric toroidal plasma is extended to the case of an inhomogeneous magnetic field B(R, Z). The impact of such inhomogeneity on local and total power losses is analyzed in the framework of this model by using the CYNEQ code. It is shown that, for the magnetic field B, temperature T{sub e}, density n{sub e}, and wall reflection coefficient R{sub w} expected in ITER and DEMO, accurate simulations of the EC radiative loss require self-consistent 1.5D transport analysis (i.e., one-dimensional simulations of plasma transport and two-dimensional simulations of plasma equilibrium). It is shown that EC radiative transport can be described with good accuracy in the 1D approximation with the surface-averaged magnetic field, B({rho}) = Left-Pointing-Angle-Bracket B(R, Z) Right-Pointing-Angle-Bracket {sub ms}. This makes it possible to substantially reduce the computational time required for time-dependent self-consistent 1.5D transport analysis. Benchmarking of the CYNEQ results with available results of the RAYTEC, EXACTEC, and CYTRAN codes is performed for various approximations of the magnetic field.

Kukushkin, A. B.; Minashin, P. V. [National Research Centre Kurchatov Institute, Tokamak Physics Institute (Russian Federation); Polevoi, A. R. [Route de Vinon sur Verdon, ITER Organization (France)

2012-03-15T23:59:59.000Z

149

Toroidal field coil replacement study for the International Thermonuclear Experimental Reactor (ITER)  

SciTech Connect (OSTI)

The objective of this study is to develop an estimate of the time required to replace a failed toroidal field (TF) coil in the International Thermonuclear Experimental Reactor (ITER). This estimate is based on the current ITER design which resulted from the Conceptual Design Activities began in spring of 1988 and ending in December 1990. Although the TF Coils in ITER are designated permanent components and expected to last the life of the plant, the history of failures of large coils in fusion devices has prompted an assessment of the down time that might be required for replacement of a failed TF coil in ITER. The difficulty of replacement of a TF Coil in ITER is compounded by the large physical size of ITER, and the radiation fields which necessitate the use of remote handling equipment for most maintenance activities. Since 10 out of 16 TF coils are adjacent to either a Neutral Beam Injector (NBI) port or a remote handling (RH) port, it is probable that a failed TF Coil will be in one of these inconvenient locations. For this study, TF coil number 3 is assumed to fail and its replacement will be evaluated as a typical case. TF coil number 3 is located between a remote handling port ({number sign}3) and a port allocated to the lower hybrid ({number sign}4).

Not Available

1991-08-01T23:59:59.000Z

150

Toroidal field coil replacement study for the International Thermonuclear Experimental Reactor (ITER)  

SciTech Connect (OSTI)

The objective of this study is to develop an estimate of the time required to replace a failed toroidal field (TF) coil in the International Thermonuclear Experimental Reactor (ITER). This estimate is based on the current ITER design which resulted from the Conceptual Design Activities began in spring of 1988 and ending in December 1990. Although the TF Coils in ITER are designated permanent components and expected to last the life of the plant, the history of failures of large coils in fusion devices has prompted an assessment of the down time that might be required for replacement of a failed TF coil in ITER. The difficulty of replacement of a TF Coil in ITER is compounded by the large physical size of ITER, and the radiation fields which necessitate the use of remote handling equipment for most maintenance activities. Since 10 out of 16 TF coils are adjacent to either a Neutral Beam Injector (NBI) port or a remote handling (RH) port, it is probable that a failed TF Coil will be in one of these inconvenient locations. For this study, TF coil number 3 is assumed to fail and its replacement will be evaluated as a typical case. TF coil number 3 is located between a remote handling port ({number_sign}3) and a port allocated to the lower hybrid ({number_sign}4).

Not Available

1991-08-01T23:59:59.000Z

151

Laboratory and Modeling Evaluations in Support of Field Testing for Desiccation at the Hanford Site  

SciTech Connect (OSTI)

The Deep Vadose Zone Treatability Test Plan for the Hanford Central Plateau includes testing of the desiccation technology as a potential technology to be used in conjunction with surface infiltration control to limit the flux of technetium and other contaminants in the vadose zone to the groundwater. Laboratory and modeling efforts were conducted to investigate technical uncertainties related to the desiccation process and its impact on contaminant transport. This information is intended to support planning, operation, and interpretation of a field test for desiccation in the Hanford Central Plateau.

Truex, Michael J.; Oostrom, Martinus; Freedman, Vicky L.; Strickland, Christopher E.; Wietsma, Thomas W.; Tartakovsky, Guzel D.; Ward, Anderson L.

2011-02-23T23:59:59.000Z

152

EIS-0402: Remediation of Area IV of the Santa Susana Field Laboratory, California  

Broader source: Energy.gov [DOE]

DOE is preparing an EIS for cleanup of Area IV, including the Energy Technology Engineering Center (ETEC), as well as the Northern Buffer Zone of the Santa Susana Field Laboratory (SSFL) in eastern Ventura County, California, approximately 29 miles north of downtown Los Angeles. (DOEs operations bordered the Northern Buffer Zone. DOE is responsible for soil cleanup in Area IV and the Northern Buffer Zone.) In the EIS, DOE will evaluate reasonable alternatives for disposition of radiological facilities and support buildings, remediation of contaminated soil and groundwater, and disposal of all resulting waste at permitted facilities.

153

Laboratory and field evaluation of several insecticides for control of the hickory shuckworm, Laspeyresia caryana (Fitch)  

E-Print Network [OSTI]

' s data azinphosc e& hy1 and Epk (at the rate r f 0. 5 lb AI/100 al water applied 3 ti&ies at 2 week . :&iter- vals starting August 15) i;ere recomr ended for control of th= hi&-gory shuckworm under Texas conditions. Althougl& phosp'namidon gave en...: azinphosmethyl (0. 5 lb AI/100 gal water) and uiazinon (0. 5 lb Ai/100 gal water). Prior to the 1968 field e. pezime~t, pzeliminary laboratory studies had been conducted with diazinon. This was the res. on foz its nckusion in the test. Azinphos...

Boethel, David John

1970-01-01T23:59:59.000Z

154

Large-Scale Field Study of Landfill Covers at Sandia National Laboratories  

SciTech Connect (OSTI)

A large-scale field demonstration comparing final landfill cover designs has been constructed and is currently being monitored at Sandia National Laboratories in Albuquerque, New Mexico. Two conventional designs (a RCRA Subtitle `D' Soil Cover and a RCRA Subtitle `C' Compacted Clay Cover) were constructed side-by-side with four alternative cover test plots designed for dry environments. The demonstration is intended to evaluate the various cover designs based on their respective water balance performance, ease and reliability of construction, and cost. This paper presents an overview of the ongoing demonstration.

Dwyer, S.F.

1998-09-01T23:59:59.000Z

155

Supported by the National Science Foundation and the State of Florida 1 REPORTSNATIONAL HIGH MAGNETIC FIELD LABORATORY  

E-Print Network [OSTI]

Supported by the National Science Foundation and the State of Florida 1 REPORTSNATIONAL HIGH MAGNETIC FIELD LABORATORY NHMFL SPRING 1997 Florida State University · University of Florida · Los Alamos National Laboratory the formation of convection currents in and NHMFL Magnets cont. on page 6 Recently

Weston, Ken

156

Importance of aerosol composition, mixing state, and morphology for heterogeneous ice nucleation: A combined field and laboratory approach  

E-Print Network [OSTI]

In this study chemical compositions of background aerosol and ice nuclei were examined through laboratory investigations using Raman spectroscopy and field measurements by single-particle mass spectrometry. Aerosol sampling ...

Baustian, Kelly J.

157

Other Locales Gulf Stream Locale -A Field Laboratory for Cloud Process  

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

Gulf Stream Locale -A Field Gulf Stream Locale -A Field Laboratory for Cloud Process S. Raman Department of Marine, Earth and Atmospheric Sciences North Carolina State University Raleigh, NC 27695-8028 Clouds associated with the Gulf Stream Locale, (Figure 1) are in general due to the cyclogenesis or redevelopments of the storms off the east coast of the United States in winters, movement along the coast of the storms that are generated over the Gulf of Mexico in the spring and fall and mesoscale convective circulations present in all seasons. During the summer and early fall ,this region is also susceptible to hurricanes moving from the south. There have been several attempts to reproduce some of the observed synoptic and mesoscale features of these sys- tems (e.g., Krei1zberg and Perkey 1977; Holt et al. 1990;

158

A comprehensive field and laboratory study of scale control and scale squeezes in Sumatra, Indonesia  

SciTech Connect (OSTI)

Scale squeezes were performed on thirteen wells in the Duri Field, Sumatra. At the time the squeezes were completed, seven were designed to be `Acid Squeezes` and six were designed to be `Neutral Squeezes.` In the course of preparing for the scale squeezes, produced waters were collected and analyzed. In addition, scale inhibitor evaluations, and inhibitor compatibility studies were completed. Simulated squeezes were done in the laboratory to predict field performance. The methodologies and results of the background work are reported. In addition, the relative effectiveness of the two sets of squeezes is discussed. The inhibitor flowback concentrations alter the squeezes, in all cases, can be explained using speciation chemistry and the amorphous and crystalline phase solubilities of the inhibitor used. The wells squeezed with a more acidic inhibitor have more predictable and uniform inhibitor return concentration curves than the wells squeezed with a more neutral scale inhibitor.

Oddo, J.E.; Reizer, J.M.; Sitz, C.D. [Champion Technologies, Inc., Houston, TX (United States); Setia, D.E.A. [FMT Production Duri P.T. Caltex Pacific Indonesia (Indonesia); Hinrichsen, C.J. [Texaco Panama, Bellaire, TX (United States); Sujana, W. [P.T. Champion Kumia Djaja Technologies, Jakarta (Indonesia)

1999-11-01T23:59:59.000Z

159

INDEPENDENT CONFIRMATORY SURVEY REPORT FOR THE REACTOR BUILDING, HOT LABORATORY, PRIMARY PUMP HOUSE, AND LAND AREAS AT THE PLUM BROOK REACTOR FACILITY, SANDUSKY, OHIO  

SciTech Connect (OSTI)

In 1941, the War Department acquired approximately 9,000 acres of land near Sandusky, Ohio and constructed a munitions plant. The Plum Brook Ordnance Works Plant produced munitions, such as TNT, until the end of World War II. Following the war, the land remained idle until the National Advisory Committee for Aeronautics later called the National Aeronautics and Space Administration (NASA) obtained 500 acres to construct a nuclear research reactor designed to study the effects of radiation on materials used in space flight. The research reactor was put into operation in 1961 and was the first of fifteen test facilities eventually built by NASA at the Plum Brook Station. By 1963, NASA had acquired the remaining land at Plum Brook for these additional test facilities

Erika N. Bailey

2011-10-10T23:59:59.000Z

160

Laboratory Studies of the Short-term Responses of Freshwater Fish to Electromagnetic Fields  

SciTech Connect (OSTI)

Hydrokinetic energy technologies are being proposed as an environmentally preferred means of generating electricity from river and tidal currents. Among the potential issues that must be investigated in order to resolve environmental concerns are the effects on aquatic organisms of electromagnetic fields created by underwater generators and transmission cables. The behavioral responses of common freshwater fishes to static and variable electromagnetic fields (EMF) that may be emitted by hydrokinetic projects were evaluated in laboratory experiments. Various fish species were exposed to either static (DC) EMF fields created by a permanent bar magnet or variable (AC) EMF fields created by a switched electromagnet for 48 h, fish locations were recorded with a digital imaging system, and changes in activity level and distribution relative to the magnet position were quantified at 5-min intervals. Experiments with fathead minnows, redear sunfish, striped bass, lake sturgeon, and channel catfish produced mixed results. Except for fathead minnows there was no effect on activity level. Only redear sunfish and channel catfish exhibited a change in distribution relative to the position of the magnet with an apparent attraction to the EMF source. In separate experiments, rapid behavioral responses of paddlefish and lake sturgeon to onset of the AC field were recorded with high-speed video. Paddlefish did not react to a variable, 60-Hz magnetic field like that which would be emitted by an AC generator or cable, but lake sturgeon consistently responded to the variable, AC-generated magnetic field with a variety of altered swimming behaviors. These results will be useful for determining under what circumstances cables or generators need to be positioned to minimize interactions with sensitive species.

Bevelhimer, Mark S [ORNL; Cada, Glenn F [ORNL; Fortner, Allison M [ORNL; Schweizer, Peter E [ORNL; Riemer, Kristina P [ORNL

2013-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "reactors laboratory field" 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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161

Use of chironomid deformities in field and laboratory assessments of contaminated sediments  

SciTech Connect (OSTI)

Benthic invertebrate samples were collected from 23 pools in the Upper Mississippi River (UMR), the Saint Croix River (SCR), Wisconsin, the Clark Fork River (CFR)/Milltown Reservoir (MR) Superfund Site, Montana, and three Great Lakes rivers classified as Areas of Concern (AOC). Contamination consisted of organic and inorganic contaminants at the UMR and AOC sites, and primarily heavy metals in the CFR/MR sites. Samples were collected with a ponar grab sampler from stations in Indiana Harbor, IN (n = 7), Buffalo River, NY (n = 10), Saginaw River, MI (1989 n = 7; 1990, n = 7), Upper Mississippi River (n = 24), Clark Fork River (n = 6), and Milltown Reservoir (n = 7). Compared to literature values for incidence of deformities in uncontaminated sediments, frequency of chironomid mouthpart deformities was significantly greater at most stations sampled from the AOC sites, with only a few stations sampled from the CFR/MR and UMR sites having significantly greater incidence of mouthpart deformities. Occurrence of mouthpart deformities ranged from 0 to 100% at stations from the AOC`S, 0 to 18% at CFR/MR stations, and 0 to 13% at UMR stations. Sediment contamination was generally lowest in UMR samples and highest in AOC samples. These data show organic contaminants may have a greater potential for causing teratogenic effects in chironomid mouthparts. Frequency of mouthpart deformities in Chironomus riparius laboratory exposures to contaminated sediments from all AOC and CFR sites were evaluated and analysis shows that frequency of mouthpart deformities from laboratory-exposed chironomids are generally lower than those found in field-collected samples. Additional analysis of chironomid laboratory cultures background deformity levels which must be addressed before laboratory evaluations can be used with reliability.

Canfield, T.J.; Kemble, N.E.; Ingersoll, C.G. [National Biological Service, Columbia, MO (United States)

1995-12-31T23:59:59.000Z

162

Review of the International Atomic Energy Agency International database on reactor pressure vessel materials and US Nuclear Regulatory Commission/Oak Ridge National Laboratory embrittlement data base  

SciTech Connect (OSTI)

The International Atomic Energy Agency (IAEA) has supported neutron radiation effects information exchange through meetings and conferences since the mid-1960s. Through an International Working Group on Reliability of Reactor Pressure Components, information exchange and research activities were fostered through the Coordinated Research Program (CRP) sponsored by the IAEA. The final CRP meeting was held in November 1993, where it was recommended that the IAEA coordinate the development of an International Database on Reactor Pressure Vessel Material (IDRPVM) as the first step in generating an International Database on Aging Management. The purpose of this study was to provide special technical assistance to the NRC in monitoring and evaluating the IAEA activities in developing the IAEA IDRPVM, and to compare the IDRPVM with the Nuclear Regulatory Commission (NRC) - Oak Ridge National Laboratory (ORNL) Power Reactor Embrittlement Data Base (PR-EDB) and provide recommendations for improving the PR-EDB. A first test version of the IDRPVM was distributed at the First Meeting of Liaison Officers to the IAEA IDRPVM, in November 1996. No power reactor surveillance data were included in this version; the testing data were mainly from CRP Phase III data. Therefore, because of insufficient data and a lack of power reactor surveillance data received from the IAEA IDRPVM, the comparison is made based only on the structure of the IDRPVM. In general, the IDRPVM and the EDB have very similar data structure and data format. One anticipates that because the IDRPVM data will be collected from so many different sources, quality assurance of the data will be a difficult task. The consistency of experimental test results will be an important issue. A very wide spectrum of material characteristics of RPV steels and irradiation environments exists among the various countries. Hence the development of embrittlement prediction models will be a formidable task. 4 refs., 2 figs., 4 tabs.

Wang, J.A.; Kam, F.B.K.

1998-02-01T23:59:59.000Z

163

Identification and evaluation of alternatives for the disposition of fluoride fuel and flush salts from the molten salt reactor experiment at Oak Ridge National Laboratory, Oak Ridge, Tennessee  

SciTech Connect (OSTI)

This document presents an initial identification and evaluation of the alternatives for disposition of the fluoride fuel and flush salts stored in the drain tanks at the Molten Salt Reactor Experiment (MSRE) at Oak Ridge National Laboratory (ORNL). It will serve as a resource for the U.S. Department of Energy contractor preparing the feasibility study for this activity under the Comprehensive Environmental Response, Compensation and Liability Act (CERCLA). This document will also facilitate further discussion on the range of credible alternatives, and the relative merits of alternatives, throughout the time that a final alternative is selected under the CERCLA process.

NONE

1996-08-15T23:59:59.000Z

164

PROJECT-SPECIFIC TYPE A VERIFICATION FOR THE BROOKHAVEN GRAPHITE RESEARCH REACTOR ENGINEERED CAP, BROOKHAVEN NATIONAL LABORATORY UPTON, NEW YORK DCN 5098-SR-07-0  

SciTech Connect (OSTI)

The Oak Ridge Institute for Science and Education (ORISE) has reviewed the project documentation and data for the Brookhaven Graphite Research Reactor (BGRR) Engineered Cap at Brookhaven National Laboratory (BNL) in Upton, New York. The Brookhaven Science Associates (BSA) have completed removal of affected soils and performed as-left surveys by BSA associated with the BGRR Engineered Cap. Sample results have been submitted, as required, to demonstrate that remediation efforts comply with the cleanup goal of {approx}15 mrem/yr above background to a resident in 50 years (BNL 2011a).

Evan Harpenau

2011-07-15T23:59:59.000Z

165

Field and Laboratory Certification Testing for Compliance with the New York City Building Code  

Science Journals Connector (OSTI)

The Noise Control Section of the New York City Building Code contains specific acoustical requirements for indoor and outdoor mechanical equipment servicing multi?family dwellings. Acoustical requirements are also specified for partition and floor?ceiling constructions separating dwelling units from each other and from corridors and mechanical equipment spaces. As of 19 June 1972 the Housing and Development Administration New York City Department of Buildings issued a directive specifying the methods of compliance with the Noise Control Section of the New York City Building Code. The methods outlined are field testing or laboratory certification for Building Department approval to obtain a certificate of occupancy. An examination of both methods will be emphasized with selection and application of the most likely test method for compliance with the New York City Building Code and other federal state or local EPA codes.

Steven Wolf

1973-01-01T23:59:59.000Z

166

Scientific Image Gallery from the Applied Superconductivity Center at the National High Magnetic Field Laboratory  

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

The Applied Superconductivity Center (ASC) is nested with the National High Magnetic Field Laboratory. Originally located at the University of Wisconsin, ASC transferred to NHMFL or Magnet Lab in 2003. ASC investigates both low and high-temperature materials. Focus areas include grain boundaries; coated conductors, BSCCO, and a new superconductor known as MgB2. The ASC Image Gallery provides graphs with text descriptions and single images with captions. The single images are organized into collections under scientific titles, such as MgB2 mentioned above. Click on the Videos link to see two 3D videos and be sure to check out the link to image collections at other organizations performing superconductivity research.

167

Grant Awarded to California for Oversight of Santa Susana Field Laboratory  

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

Contacts Contacts Bill Taylor bill.taylor@srs.gov 803-952-8564 Cincinnati - The Department of Energy today awarded a grant to the State of California Department of Toxic Substance Control (DTSC) for regulatory functions necessary to oversee investigation and cleanup at the Energy Technology Engineering Center (ETEC) project at the Santa Susana Field Laboratory (SSFL), Canoga Park, California. The $5.6 million grant has five one-year performance periods. DOE must comply with the requirements for characterization and cleanup in the 2007 Consent Order with the State of California for groundwater and the 2010 Administrative Order on Consent for soils. ETEC's historic mission involved nuclear research and development for the U.S. Atomic Energy Commission, a predecessor to DOE. In the mid-1950s, a

168

Grant Awarded to California for Oversight of Santa Susana Field Laboratory  

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

Contact Contact Bill Taylor, 803-952-8564 bill.taylor@srs.gov Cincinnati - The Department of Energy today awarded a grant to the State of California Department of Toxic Substance Control (DTSC) for regulatory functions necessary to oversee investigation and cleanup at the Energy Technology Engineering Center (ETEC) project at the Santa Susana Field Laboratory (SSFL), Canoga Park, California. The $5.6 million grant has five one-year performance periods. DOE must comply with the requirements for characterization and cleanup in the 2007 Consent Order with the State of California for groundwater and the 2010 Administrative Order on Consent for soils. ETEC's historic mission involved nuclear research and development for the U.S. Atomic Energy Commission, a predecessor to DOE. In the mid-1950s, a

169

Characterization of the Neutron Fields in the Lawrence Livermore National Laboratory (LLNL) Radiation Calibration Laboratory Low Scatter Calibration Facility  

SciTech Connect (OSTI)

In June 2007, the Department of Energy (DOE) revised its rule on Occupational Radiation Protection, Part 10 CFR 835. A significant aspect of the revision was the adoption of the recommendations outlined in International Commission on Radiological Protection (ICRP) Report 60 (ICRP-60), including new radiation weighting factors for neutrons, updated internal dosimetric models, and dose terms consistent with the newer ICRP recommendations. ICRP-60 uses the quantities defined by the International Commission on Radiation Units and Measurements (ICRU) for personnel and area monitoring including the ambient dose equivalent H*(d). A Joint Task Group of ICRU and ICRP has developed various fluence-to-dose conversion coefficients which are published in ICRP-74 for both protection and operational quantities. In February 2008, Lawrence Livermore National Laboratory (LLNL) replaced its old pneumatic transport neutron irradiation system in the Radiation Calibration Laboratory (RCL) Low Scatter Calibration Facility (B255, Room 183A) with a Hopewell Designs irradiator model N40. The exposure tube for the Hopewell system is located close to, but not in exactly the same position as the exposure tube for the pneumatic system. Additionally, the sources for the Hopewell system are stored in Room 183A where, prior to the change, they were stored in a separate room (Room 183C). The new source configuration and revision of the 10 CFR 835 radiation weighting factors necessitate a re-evaluation of the neutron dose rates in B255 Room 183A. This report deals only with the changes in the operational quantities ambient dose equivalent and ambient dose rate equivalent for neutrons as a result of the implementation of the revised 10 CFR 835. In the report, the terms 'neutron dose' and 'neutron dose rate' will be used for convenience for ambient neutron dose equivalent and ambient neutron dose rate equivalent unless otherwise stated.

Radev, R

2009-09-04T23:59:59.000Z

170

naval reactors  

National Nuclear Security Administration (NNSA)

After operating for 34 years and training over 14,000 sailors, the Department of Energy S1C Prototype Reactor Site in Windsor, Connecticut, was returned to "green field"...

171

Preliminary Results of an On-Line, Multi-Spectrometer Fission Product Monitoring System to Support Advanced Gas Reactor Fuel Testing and Qualification in the Advanced Test Reactor at the Idaho National Laboratory  

SciTech Connect (OSTI)

The Advanced Gas Reactor -1 (AGR-1) experiment is the first experiment in a series of eight separate low enriched uranium (LEU) oxycarbide (UCO) tri-isotropic (TRISO) particle fuel (in compact form) experiments scheduled for placement in the Advanced Test Reactor (ATR) located at the Idaho National Laboratory (INL). The experiment began irradiation in the ATR with a cycle that reached full power on December 26, 2006 and will continue irradiation for about 2.5 years. During this time six separate capsules, will be irradiated in an inert sweep gas atmosphere with individual on-line fission product monitoring on its effluent to track performance of the fuel in each individual capsule during irradiation. The goals of the irradiation experiment is to provide irradiation performance data to support fuel process development, to qualify fuel for normal operating conditions, to support development and validation of fuel, and to provide irradiated fuel and materials for post irradiation examination (PIE) and safety testing. This paper presents the preliminary test details of the fuel performance, as measured by the control and acquisition software.

Dawn M. Scates; John K. Hartwell; John B. Walter; Mark W. Drigert

2007-10-01T23:59:59.000Z

172

CRAD, Fire Protection - Oak Ridge National Laboratory High Flux...  

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

Fire Protection - Oak Ridge National Laboratory High Flux Isotope Reactor CRAD, Fire Protection - Oak Ridge National Laboratory High Flux Isotope Reactor February 2006 A section of...

173

CRAD, Engineering - Oak Ridge National Laboratory High Flux Isotope...  

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

Oak Ridge National Laboratory High Flux Isotope Reactor CRAD, Engineering - Oak Ridge National Laboratory High Flux Isotope Reactor February 2007 A section of Appendix C to DOE G...

174

CRAD, Maintenance - Oak Ridge National Laboratory High Flux Isotope...  

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

Maintenance - Oak Ridge National Laboratory High Flux Isotope Reactor CRAD, Maintenance - Oak Ridge National Laboratory High Flux Isotope Reactor February 2007 A section of...

175

CRAD, Emergency Management - Oak Ridge National Laboratory High...  

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

Emergency Management - Oak Ridge National Laboratory High Flux Isotope Reactor Contractor ORR CRAD, Emergency Management - Oak Ridge National Laboratory High Flux Isotope Reactor...

176

CRAD, Emergency Management - Oak Ridge National Laboratory High...  

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

Emergency Management - Oak Ridge National Laboratory High Flux Isotope Reactor CRAD, Emergency Management - Oak Ridge National Laboratory High Flux Isotope Reactor February 2007 A...

177

CRAD, Nuclear Safety - Oak Ridge National Laboratory High Flux...  

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

Nuclear Safety - Oak Ridge National Laboratory High Flux Isotope Reactor CRAD, Nuclear Safety - Oak Ridge National Laboratory High Flux Isotope Reactor February 2007 A section of...

178

CRAD, Safety Basis - Oak Ridge National Laboratory High Flux...  

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

Oak Ridge National Laboratory High Flux Isotope Reactor Contractor ORR CRAD, Safety Basis - Oak Ridge National Laboratory High Flux Isotope Reactor Contractor ORR February 2007 A...

179

CRAD, Engineering - Oak Ridge National Laboratory High Flux Isotope...  

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

Engineering - Oak Ridge National Laboratory High Flux Isotope Reactor Contractor ORR CRAD, Engineering - Oak Ridge National Laboratory High Flux Isotope Reactor Contractor ORR...

180

CRAD, Radiological Controls - Oak Ridge National Laboratory High...  

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

Oak Ridge National Laboratory High Flux Isotope Reactor CRAD, Radiological Controls - Oak Ridge National Laboratory High Flux Isotope Reactor February 2007 A section of Appendix C...

Note: This page contains sample records for the topic "reactors laboratory field" 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

CRAD, Maintenance - Oak Ridge National Laboratory High Flux Isotope...  

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

Maintenance - Oak Ridge National Laboratory High Flux Isotope Reactor Contractor ORR CRAD, Maintenance - Oak Ridge National Laboratory High Flux Isotope Reactor Contractor ORR...

182

CRAD, Management- Oak Ridge National Laboratory High Flux Isotope...  

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

Management- Oak Ridge National Laboratory High Flux Isotope Reactor CRAD, Management- Oak Ridge National Laboratory High Flux Isotope Reactor February 2007 A section of Appendix C...

183

CRAD, Conduct of Operations - Oak Ridge National Laboratory High...  

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

Oak Ridge National Laboratory High Flux Isotope Reactor Contractor ORR CRAD, Conduct of Operations - Oak Ridge National Laboratory High Flux Isotope Reactor Contractor ORR February...

184

CRAD, Occupational Safety & Health - Oak Ridge National Laboratory...  

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

Occupational Safety & Health - Oak Ridge National Laboratory High Flux Isotope Reactor CRAD, Occupational Safety & Health - Oak Ridge National Laboratory High Flux Isotope Reactor...

185

DOE - Office of Legacy Management -- Ames Laboratory Research...  

Office of Legacy Management (LM)

Ames Laboratory Research Reactor Facility - IA 03 FUSRAP Considered Sites Site: Ames Laboratory Research Reactor Facility (IA.03) Designated Name: Alternate Name: Location:...

186

TYPE A VERIFICATION REPORT FOR THE HIGH FLUX BEAM REACTOR STACK AND GROUNDS, BROOKHAVEN NATIONAL LABORATORY, UPTON, NEW YORK DCN 5098-SR-08-0  

SciTech Connect (OSTI)

The U.S. Department of Energy (DOE) Order 458.1 requires independent verification (IV) of DOE cleanup projects (DOE 2011). The Oak Ridge Institute for Science and Education (ORISE) has been designated as the responsible organization for IV of the High Flux Beam Reactor (HFBR) Stack and Grounds area at Brookhaven National Laboratory (BNL) in Upton, New York. The IV evaluation may consist of an in-process inspection with document and data reviews (Type A Verification) or a confirmatory survey of the site (Type B Verification). DOE and ORISE determined that a Type A verification of the documents and data for the HFBR Stack and Grounds: Survey Units (SU) 6, 7, and 8 was appropriate based on the initial survey unit classification, the walkover surveys, and the final analytical results provided by the Brookhaven Science Associates (BSA).

Evan Harpenau

2011-11-30T23:59:59.000Z

187

A TEN MEGAWATT BOILING HETEROGENEOUS PACKAGE POWER REACTOR. Reactor...  

Office of Scientific and Technical Information (OSTI)

A TEN MEGAWATT BOILING HETEROGENEOUS PACKAGE POWER REACTOR. Reactor Design and Feasibility Problem Re-direct Destination: Temp Data Fields Rosen, M. A.; Coburn, D. B.; Flynn, T....

188

Advanced Test Reactor Tour  

SciTech Connect (OSTI)

The Advanced Test Reactor at Idaho National Laboratory is the foremost nuclear materials test reactor in the world. This virtual tour describes the reactor, how experiments are conducted, and how spent nuclear fuel is handled and stored. For more information about INL research, visit http://www.facebook.com/idahonationallaboratory.

Miley, Don

2011-01-01T23:59:59.000Z

189

Advanced Test Reactor Tour  

ScienceCinema (OSTI)

The Advanced Test Reactor at Idaho National Laboratory is the foremost nuclear materials test reactor in the world. This virtual tour describes the reactor, how experiments are conducted, and how spent nuclear fuel is handled and stored. For more information about INL research, visit http://www.facebook.com/idahonationallaboratory.

Miley, Don

2013-05-28T23:59:59.000Z

190

Program management plan for the Molten Salt Reactor Experiment Remediation Project at Oak Ridge National Laboratory, Oak Ridge, Tennessee  

SciTech Connect (OSTI)

The primary mission of the Molten Salt Reactor Experiment (MSRE) Remediation Project is to effectively implement the risk-reduction strategies and technical plans to stabilize and prevent further migration of uranium within the MSRE facility, remove the uranium and fuel salts from the system, and dispose of the fuel and flush salts by storage in appropriate depositories to bring the facility to a surveillance and maintenance condition before decontamination and decommissioning. This Project Management Plan (PMP) for the MSRE Remediation Project details project purpose; technical objectives, milestones, and cost objectives; work plan; work breakdown structure (WBS); schedule; management organization and responsibilities; project management performance measurement planning, and control; conduct of operations; configuration management; environmental, safety, and health compliance; quality assurance; operational readiness reviews; and training.

NONE

1996-09-01T23:59:59.000Z

191

Field Demonstration of High Efficiency Ultra-Low-Temperature Laboratory Freezers  

Broader source: Energy.gov [DOE]

Ultra-low temperature laboratory freezers (ULTs) are some of the most energy-intensive pieces of equipment in a scientific research laboratory, yet there are several barriers to user acceptance and adoption of high-efficiency ULTs. One significant barrier is a relative lack of information on ULT efficiency to help purchasers make informed decisions with respect to efficient products.

192

Technology transfer of an innovative remediation technology from the laboratory to the field: a case study of in situ aerobic cometabolic bioremediation  

Science Journals Connector (OSTI)

Scaling-up an environmental remediation technology from the laboratory to the field ... in order to demonstrate and evaluate a new remediation technology in the field. Finally, to commercialize an innovative tech...

M. N. Goltz; G. C. Mandalas; G. D. Hopkins

1998-06-01T23:59:59.000Z

193

Crack growth rates and metallographic examinations of Alloy 600 and Alloy 82/182 from field components and laboratory materials tested in PWR environments.  

SciTech Connect (OSTI)

In light water reactors, components made of nickel-base alloys are susceptible to environmentally assisted cracking. This report summarizes the crack growth rate results and related metallography for field and laboratory-procured Alloy 600 and its weld alloys tested in pressurized water reactor (PWR) environments. The report also presents crack growth rate (CGR) results for a shielded-metal-arc weld of Alloy 182 in a simulated PWR environment as a function of temperature between 290 C and 350 C. These data were used to determine the activation energy for crack growth in Alloy 182 welds. The tests were performed by measuring the changes in the stress corrosion CGR as the temperatures were varied during the test. The difference in electrochemical potential between the specimen and the Ni/NiO line was maintained constant at each temperature by adjusting the hydrogen overpressure on the water supply tank. The CGR data as a function of temperature yielded activation energies of 252 kJ/mol for a double-J weld and 189 kJ/mol for a deep-groove weld. These values are in good agreement with the data reported in the literature. The data reported here and those in the literature suggest that the average activation energy for Alloy 182 welds is on the order of 220-230 kJ/mol, higher than the 130 kJ/mol commonly used for Alloy 600. The consequences of using a larger value of activation energy for SCC CGR data analysis are discussed.

Alexandreanu, B.; Chopra, O. K.; Shack, W. J.

2008-05-05T23:59:59.000Z

194

Laboratory Fellows  

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

were confirmed by the Laboratory Director. Brenda Dingus has pioneered work in gamma-ray bursts and is a major contributor to the relatively young scientific field of...

195

The Mobility of Hydrocarbons at Unsaturated Water Conductivity Under Field and Laboratory Conditions  

Science Journals Connector (OSTI)

The goal of this examination is to develop a procedure, as in a labrotory test, to determine the mobility of non-polar organic contaminants in soils. The data of the laboratory tests will be compared with the ...

I. Drachenberg; D. Goetz

1995-01-01T23:59:59.000Z

196

Quantitative Study Of Guide Field Effects on Hall Reconnection In A Laboratory Plasma  

SciTech Connect (OSTI)

The effect of guide field on magnetic reconnection is quantitatively studied by systematically varying an applied guide field in the Magnetic Reconnection Experiment (MRX). The quadrupole field, a signature of two-fluid reconnection at zero guide field, is significantly altered by a finite guide field. It is shown that the reconnection rate is significantly reduced with increasing guide field, and this dependence is explained by a combination of local and global physics: locally, the in-plane Hall currents are reduced, while globally guide field compression produces an increased pressure both within and downstream of the reconnection region. __________________________________________________

T. D. Tharp, M. Yamada, H. Ji, E. Lawrence, S. Dorfman, C. Myers, and J. Yoo

2012-04-17T23:59:59.000Z

197

Independent Oversight Review, Oak Ridge National Laboratory- January 2013  

Broader source: Energy.gov [DOE]

Review of the Oak Ridge National Laboratory High Flux Isotope Reactor Implementation Verification Review Processes

198

Independent Oversight Inspection, Idaho National Laboratory- June 2005  

Broader source: Energy.gov [DOE]

Inspection of Environment, Safety, and Health Programs at the Idaho National Laboratory Advanced Test Reactor

199

Hands-on Training through the University of Florida Living Extension IPM Field Laboratory  

E-Print Network [OSTI]

, reduction of pesticides were also utilized. Training workshops were taught to County Agents, clientele (farmers and homeowners) and partners. A 330-acre farm at the Suwannee Valley Agricultural Extension Center into this concept. Experiential learning opportunities of on-farm laboratories are an effective method of training

Jawitz, James W.

200

Laboratory and Field Evaluations of Oviposition Responses of Aedes albopictus and Aedes triseriatus (Diptera: Culicidae)  

E-Print Network [OSTI]

(Diptera: Culicidae) to Oak Leaf Infusions JONATHAN D. TREXLER, CHARLES S. APPERSON, AND COBY SCHAL. 35(6): 967-976 (1998) ABSTRACT Organic infusions created by fermenting white oak (Quercus alba L for gravid Aedes albopictus (Skuse) and Aedes triseriatus (Say). Infusions were bioassayed in the laboratory

Note: This page contains sample records for the topic "reactors laboratory field" 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

A Transient Numerical Simulation of Perched Ground-Water Flow at the Test Reactor Area, Idaho National Engineering and Environmental Laboratory, Idaho, 1952-94  

SciTech Connect (OSTI)

Studies of flow through the unsaturated zone and perched ground-water zones above the Snake River Plain aquifer are part of the overall assessment of ground-water flow and determination of the fate and transport of contaminants in the subsurface at the Idaho National Engineering and Environmental Laboratory (INEEL). These studies include definition of the hydrologic controls on the formation of perched ground-water zones and description of the transport and fate of wastewater constituents as they moved through the unsaturated zone. The definition of hydrologic controls requires stratigraphic correlation of basalt flows and sedimentary interbeds within the saturated zone, analysis of hydraulic properties of unsaturated-zone rocks, numerical modeling of the formation of perched ground-water zones, and batch and column experiments to determine rock-water geochemical processes. This report describes the development of a transient numerical simulation that was used to evaluate a conceptual model of flow through perched ground-water zones beneath wastewater infiltration ponds at the Test Reactor Area (TRA).

B. R. Orr (USGS)

1999-11-01T23:59:59.000Z

202

Modeling and analysis framework for core damage propagation during flow-blockage-initiated accidents in the Advanced Neutron Source Reactor at Oak Ridge National Laboratory  

SciTech Connect (OSTI)

This paper describes modeling and analysis to evaluate the extent of core damage during flow blockage events in the Advanced Neutron Source (ANS) reactor planned to be built at the Oak Ridge National Laboratory (ORNL). Damage propagation is postulated to occur from thermal conduction between damaged and undamaged plates due to direct thermal contact. Such direct thermal contact may occur because of fuel plate swelling during fission product vapor release or plate buckling. Complex phenomena of damage propagation were modeled using a one-dimensional heat transfer model. A scoping study was conducted to learn what parameters are important for core damage propagation, and to obtain initial estimates of core melt mass for addressing recriticality and steam explosion events. The study included investigating the effects of the plate contact area, the convective heat transfer coefficient, thermal conductivity upon fuel swelling, and the initial temperature of the plate being contacted by the damaged plate. Also, the side support plates were modeled to account for their effects on damage propagation. The results provide useful insights into how various uncertain parameters affect damage propagation.

Kim, S.H.; Taleyarkhan, R.P.; Navarro-Valenti, S.; Georgevich, V.

1995-09-01T23:59:59.000Z

203

2010 Annual Industrial Wastewater Reuse Report for the Idaho National Laboratory Sites Advanced Test Reactor Complex Cold Waste Pond  

SciTech Connect (OSTI)

This report describes conditions, as required by the state of Idaho Industrial Wastewater Reuse Permit (#LA 000161 01, Modification B), for the wastewater land application site at the Idaho National Laboratory Sites Advanced Test Reactor Complex Cold Waste Pond from November 1, 2009 through October 31, 2010. The report contains the following information: Facility and system description Permit required effluent monitoring data and loading rates Groundwater monitoring data Status of compliance activities Discussion of the facilitys environmental impacts During the 2010 permit year, approximately 164 million gallons of wastewater were discharged to the Cold Waste Pond. As shown by the groundwater sampling data, sulfate and total dissolved solids concentrations are highest near the Cold Waste Pond and decrease rapidly as the distance from the Cold Waste Pond increases. Although concentrations of sulfate and total dissolved solids are elevated near the Cold Waste Pond, both parameters were below the Ground Water Quality Rule Secondary Constituent Standards in the down gradient monitoring wells.

mike lewis

2011-02-01T23:59:59.000Z

204

2013 Annual Industrial Wastewater Reuse Report for the Idaho National Laboratory Sites Advanced Test Reactor Complex Cold Waste Pond  

SciTech Connect (OSTI)

This report describes conditions, as required by the state of Idaho Industrial Wastewater Reuse Permit (#LA 000161 01, Modification B), for the wastewater land application site at the Idaho National Laboratory Sites Advanced Test Reactor Complex Cold Waste Pond from November 1, 2012October 31, 2013. The report contains the following information: Facility and system description Permit required effluent monitoring data and loading rates Groundwater monitoring data Status of compliance activities Noncompliance issues Discussion of the facilitys environmental impacts. During the 2013 permit year, approximately 238 million gallons of wastewater was discharged to the Cold Waste Pond. This is well below the maximum annual permit limit of 375 million gallons. As shown by the groundwater sampling data, sulfate and total dissolved solids concentrations are highest near the Cold Waste Pond and decrease rapidly as the distance from the Cold Waste Pond increases. Although concentrations of sulfate and total dissolved solids are elevated near the Cold Waste Pond, both parameters are below the Ground Water Quality Rule Secondary Constituent Standards in the down gradient monitoring wells.

Mike Lewis

2014-02-01T23:59:59.000Z

205

Critical Heat Flux -CHF in Liquid Metal in Presence of a Magnetic Field with Particular Reference to Fusion Reactor Project  

Science Journals Connector (OSTI)

Knowledge of the critical heat flux q??crit is a cornerstone of reactor design fission, but as will demonstrate also in fusion reactors. This quantity cannot be deduced directly,...

F. J. Arias

2010-04-01T23:59:59.000Z

206

Molecular Analysis of Microbial Community Structures in Pristine and Contaminated Aquifers: Field and Laboratory Microcosm Experiments  

Science Journals Connector (OSTI)

...Phylogeny Toluene metabolism Water Microbiology Water Pollutants, Chemical metabolism...studies field studies geochemistry ground water hydrocarbons hydrochemistry...compounds pollutants pollution remediation spatial distribution toluene...

Y. Shi; M. D. Zwolinski; M. E. Schreiber; J. M. Bahr; G. W. Sewell; W. J. Hickey

1999-05-01T23:59:59.000Z

207

An integrated approach to seismic stimulation of oil reservoirs: laboratory, field and theoretical results from DOE/industry collaborations.  

SciTech Connect (OSTI)

It has been observed repeatedly that low-frequency (10-500 Hz) seismic stress waves can enhance oil production from depleted reservoirs . Until recently, the majority of these observations have been anecdotal or at the proof-of-concept level. The physics coupling stress waves to multiphase fluid flow behavior in porous media is still poorly understood, even though numerous underlying physical mechanisms have been proposed to explain the observations . Basic research on the phenomenon is being conducted through a U .S. Department of Energy funded collaboration between Lawrence Berkeley National Laboratory, the University of California at Berkeley, Los Alamos National Laboratory and the U .S . oil and gas industry . The project has focused on three main areas of research: (1) laboratory core flow experiments, (2) field seismic monitoring of downhole stimulation tests, and (3) theoretical modeling of the coupled stress/flow phenomenon . The major goal is to obtain a comprehensive scientific understanding of the seismic stimulation phenomenon so that field application technologies can be improved. Initial developments and experimental results in all three research focus areas confirm historic observations that the stimulated flow phenomenon is real and that a fundamental scientific understanding can be obtained through continued research . Examples of project results and developments are presented here.

Roberts, P. M. (Peter M.); Majer, Ernest Luther; Lo, W. C. (Wei-Cheng); Sposito, Garrison,; Daley, T. M. (Thomas M.)

2003-01-01T23:59:59.000Z

208

High-Temperature Superconducting Cable Testing Gregory S. Boebinger, National High Magnetic Field Laboratory  

E-Print Network [OSTI]

High-Temperature Superconducting Cable Testing Gregory S. Boebinger, National High Magnetic Field-Temperature Superconducting (HTS) Cables are desirable for application in large high-field magnets (>20 T), especially when). Of the three HTS magnet cable concepts emerging, the Conductor On Round Core was the first that was tested

Weston, Ken

209

CRAD, Configuration Management - Oak Ridge National Laboratory...  

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

Configuration Management - Oak Ridge National Laboratory High Flux Isotope Reactor Contractor ORR CRAD, Configuration Management - Oak Ridge National Laboratory High Flux Isotope...

210

U.S. domestic reactor conversion program  

SciTech Connect (OSTI)

The RERTR U.S. Domestic Conversion program continues in its support of the Global Treat Reduction Initiative (GTRI) to convert seven U.S reactors to low enriched uranium (LEU) by 2010. These reactors are located at the University of Florida, Texas A and M University, Purdue University, Washington State University, Oregon State University, the University of Wisconsin, and the Idaho National Laboratory. The reactors located at the University of Florida and Texas A and M Nuclear Science Center were successfully converted to LEU in September of 2006 through an integrated and collaborative effort involving INL, Argonne National Laboratory (ANL), DOE (headquarters and the field office), the Nuclear Regulatory Commission (NRC), the universities, and the contractors involved in analyses, fuel design and fabrication, and spent nuclear fuel (SNF) shipping and disposition. With this work completed and in anticipation of other impending conversion projects, a meeting was established to engage the project participants in a structured discussion to capture the lessons learned. The objectives of this meeting were to document the observations, insights, issues, concerns, and ideas of those involved in the reactor conversions so that future efforts could be conducted with greater effectiveness, efficiency, and with fewer challenges. The lessons learned from completing the University of Florida and Texas A and M conversions, the Purdue reactor conversion status, and an overview of the upcoming reactor conversions will be presented at the meeting. (author)

Meyer, Dana M.; Woolstenhulme, Eric C. [Idaho National Laboratory, Idaho Falls, Idaho 83415 (United States)

2008-07-15T23:59:59.000Z

211

Giant Viscosity Enhancement in a Spin-Polarized Fermi Liquid National High Magnetic Field Laboratory  

E-Print Network [OSTI]

electrons, ultra-cold atoms, and 3He-4He mixtures. If the magnetic field is sufficiently high so~ 15 T, T~ 2mk), for which the spin polarization attains values greater than 99%. Akimoto, H.; Xia, J

Weston, Ken

212

Laboratory measured characteristics of hot-mix asphaltic concrete as related to field performance  

E-Print Network [OSTI]

characteristics as related to field performance. New York State Study A study ( 9 ) was initiated four years ago 'oy the New York State Department of Public Works to investigate the bituminous mixes being supplied to state highway projects. The current... characteristics as related to field performance. New York State Study A study ( 9 ) was initiated four years ago 'oy the New York State Department of Public Works to investigate the bituminous mixes being supplied to state highway projects. The current...

TenBrook, James Joseph

2012-06-07T23:59:59.000Z

213

Ecology of Neoschongastia americana (Hirst): laboratory life cycle, developmental period in the field and influence of selected external factors.  

E-Print Network [OSTI]

date of sperm production Sept. 18 Nov. 20 Feb. 20 Jan. 26 Nov. 11 Nov. 30 Oct. 10 Sept. 11 March 2 Dec. 29 March 2 Feb. 23 Oct. 10 Oct. 17 Oct. 31 March 2 Dec. 29 Feb. 2 Dec. 9 Dec. 22 Dec. 14 Total days sperm product&. on 79...): Laboratory Life Cycle, Developmental Period in the Field and Influence of Selected External Factors (August 1974 ) Jerry Real Cunningham, B. S. , Texas A8cw University Chairman of Advisory Committees Prof. Manning AD Price In the summers of 1971 and 1972...

Cunningham, Jerry Real

1974-01-01T23:59:59.000Z

214

Visualizing electromagnetic fields in laser-produced counter-streaming plasma experiments for collisionless shock laboratory astrophysics  

SciTech Connect (OSTI)

Collisionless shocks are often observed in fast-moving astrophysical plasmas, formed by non-classical viscosity that is believed to originate from collective electromagnetic fields driven by kinetic plasma instabilities. However, the development of small-scale plasma processes into large-scale structures, such as a collisionless shock, is not well understood. It is also unknown to what extent collisionless shocks contain macroscopic fields with a long coherence length. For these reasons, it is valuable to explore collisionless shock formation, including the growth and self-organization of fields, in laboratory plasmas. The experimental results presented here show at a glance with proton imaging how macroscopic fields can emerge from a system of supersonic counter-streaming plasmas produced at the OMEGA EP laser. Interpretation of these results, plans for additional measurements, and the difficulty of achieving truly collisionless conditions are discussed. Future experiments at the National Ignition Facility are expected to create fully formed collisionless shocks in plasmas with no pre-imposed magnetic field.

Kugland, N. L.; Ross, J. S.; Glenzer, S. H.; Huntington, C.; Martinez, D.; Plechaty, C.; Remington, B. A.; Ryutov, D. D.; Park, H.-S. [Lawrence Livermore National Laboratory, P.O. Box 808, Livermore, California 94550 (United States)] [Lawrence Livermore National Laboratory, P.O. Box 808, Livermore, California 94550 (United States); Chang, P.-Y.; Fiksel, G.; Froula, D. H. [Laboratory for Laser Energetics, University of Rochester, 250 E. River Road, Rochester, New York 14636 (United States)] [Laboratory for Laser Energetics, University of Rochester, 250 E. River Road, Rochester, New York 14636 (United States); Drake, R. P.; Grosskopf, M.; Kuranz, C. [Department of Atmospheric, Oceanic, and Space Sciences, University of Michigan, Ann Arbor, Michigan 48109 (United States)] [Department of Atmospheric, Oceanic, and Space Sciences, University of Michigan, Ann Arbor, Michigan 48109 (United States); Gregori, G.; Meinecke, J.; Reville, B. [Department of Physics, University of Oxford, Parks Road, Oxford OX1 3PU (United Kingdom)] [Department of Physics, University of Oxford, Parks Road, Oxford OX1 3PU (United Kingdom); Koenig, M.; Pelka, A. [Laboratoire pour l'Utilisation des Lasers Intenses (LULI), cole Polytechnique-Univ, Paris VI, 91128 Palaiseau (France)] [Laboratoire pour l'Utilisation des Lasers Intenses (LULI), cole Polytechnique-Univ, Paris VI, 91128 Palaiseau (France); and others

2013-05-15T23:59:59.000Z

215

Laboratory formation of a scaled protostellar jet by coaligned poloidal magnetic field  

Science Journals Connector (OSTI)

...magnetic field, and thermal energy dominates over diffusive...experiment, if the deposition of energy was continuous, the location of the...the red dot at the tip of the green arrow), has a luminosity and a distance...Supersonic-jet experiments using a high-energy laser . Phys. Rev. Lett...

B. Albertazzi; A. Ciardi; M. Nakatsutsumi; T. Vinci; J. Bard; R. Bonito; J. Billette; M. Borghesi; Z. Burkley; S. N. Chen; T. E. Cowan; T. Herrmannsdrfer; D. P. Higginson; F. Kroll; S. A. Pikuz; K. Naughton; L. Romagnani; C. Riconda; G. Revet; R. Riquier; H.-P. Schlenvoigt; I. Yu. Skobelev; A.Ya. Faenov; A. Soloviev; M. Huarte-Espinosa; A. Frank; O. Portugall; H. Ppin; J. Fuchs

2014-10-17T23:59:59.000Z

216

Laboratory formation of a scaled protostellar jet by coaligned poloidal magnetic field  

Science Journals Connector (OSTI)

...We varied the wind and field parameters...An isotropic wind of H from the combined...disk system with a mass ejection rate of 10 ?8 M? /year and velocity 200 km/s is embedded...A) (x-z) mass density (log 10...telescope. The color map ranges from white...100 AU from the wind source (see Fig...

B. Albertazzi; A. Ciardi; M. Nakatsutsumi; T. Vinci; J. Bard; R. Bonito; J. Billette; M. Borghesi; Z. Burkley; S. N. Chen; T. E. Cowan; T. Herrmannsdrfer; D. P. Higginson; F. Kroll; S. A. Pikuz; K. Naughton; L. Romagnani; C. Riconda; G. Revet; R. Riquier; H.-P. Schlenvoigt; I. Yu. Skobelev; A.Ya. Faenov; A. Soloviev; M. Huarte-Espinosa; A. Frank; O. Portugall; H. Ppin; J. Fuchs

2014-10-17T23:59:59.000Z

217

Bose Glass of Quasiparticles in Doped Quantum Magnet Gregory S. Boebinger, National High Magnetic Field Laboratory  

E-Print Network [OSTI]

Bose Glass of Quasiparticles in Doped Quantum Magnet Gregory S. Boebinger, National High Magnetic. This BEC can localize in the presence of disorder caused by Br- doping to form a Bose Glass. The BEC-Bose Glass (BEC-BG) transition can be carefully controlled by magnetic field, allowing us to sensitively

Weston, Ken

218

FIELD EXPERIMENTATION OF COTS-BASED UAV NETWORKING Air Force Research Laboratory  

E-Print Network [OSTI]

, UAVs could act as relays between ground objects that could not otherwise communicate due to distance ongoing field experi- ments and initial results. Lastly, we briefly describe future testing plans as well, these include considerations concerning link measurement, communications and networking proto- cols, test

Kung, H. T.

219

Assessing chironomid deformities in field- and laboratory-exposed organisms from organic- and metal-contaminated sediments  

SciTech Connect (OSTI)

Benthic invertebrate samples were collected from three Great Lakes harbors classified as Areas of concern (AOC) and from the Clark Fork River Superfund Site (CFR) in Montana. Contamination consists of organic and inorganic contaminants at the AOC sites and primarily heavy metal tailings and mining wastes in the CFR sites. Samples were collected with a ponar grab sampler from stations in Indiana Harbor, IN (1989, n = 7), the Buffalo River, NY (1989, n = 10), the Saginaw River, MI (1989, n = 7; 1990, n = 7), and the Clark Fork River (1991, n = 13). Compared to literature values for incidence of deformities in uncontaminated sediments, frequency of Chironomid mouthpart deformities was significantly greater at most stations sampled from the AOC sites. In contrast, only a few stations sampled from the CFR sites had significantly greater incidence of mouthpart deformities. Occurrence of mouthpart deformities ranged from 0 to 100% at the stations from the AOC`s and from 0 to 18% at the CFR stations. These mouthpart deformities in Chironomus riparius laboratory exposures to contaminated sediments from all AOC and CFR sites were evaluated and compared to frequencies found in field collected samples. Preliminary analysis indicates that frequency of mouthpart deformities from laboratory exposed chironomids are generally lower than those found in field collected samples.

Canfield, T.J.; Kemble, N.E.; Ingersoll, C.G. [National Biological Survey, Columbia, MO (United States)

1994-12-31T23:59:59.000Z

220

In situ vitrification application to buried waste: Final report of intermediate field tests at Idaho National Engineering Laboratory  

SciTech Connect (OSTI)

This report describes two in situ vitrification field tests conducted on simulated buried waste pits during June and July 1990 at the Idaho National Engineering Laboratory. In situ vitrification, an emerging technology for in place conversion of contaminated soils into a durable glass and crystalline waste form, is being investigated as a potential remediation technology for buried waste. The overall objective of the two tests was to access the general suitability of the process to remediate waste structures representative of buried waste found at Idaho National Engineering Laboratory. In particular, these tests, as part of a treatability study, were designed to provide essential information on the field performance of the process under conditions of significant combustible and metal wastes and to test a newly developed electrode feed technology. The tests were successfully completed, and the electrode feed technology successfully processed the high metal content waste. Test results indicate the process is a feasible technology for application to buried waste. 33 refs., 109 figs., 39 tabs.

Callow, R.A.; Weidner, J.R.; Loehr, C.A.; Bates, S.O. (EG and G Idaho, Inc., Idaho Falls, ID (United States)); Thompson, L.E.; McGrail, B.P. (Pacific Northwest Lab., Richland, WA (United States))

1991-08-01T23:59:59.000Z

Note: This page contains sample records for the topic "reactors laboratory field" 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

IDAHO NATIONAL LABORATORY  

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

History of the Idaho National Laboratory (INL) History of the Idaho National Laboratory (INL) You are here: DOE-ID Home > Inside ID > Brief History Site History The Idaho National Laboratory (INL), an 890-square-mile section of desert in southeast Idaho, was established in 1949 as the National Reactor Testing Station. Initially, the missions at the INL were the development of civilian and defense nuclear reactor technologies and management of spent nuclear fuel. Fifty-two reactors—most of them first-of-a-kind—were built, including the Navy’s first prototype nuclear propulsion plant. Of the 52 reactors, three remain in operation at the site. In 1951, the INL achieved one of the most significant scientific accomplishments of the century—the first use of nuclear fission to produce a usable quantity of electricity at the Experimental Breeder Reactor No.

222

Laboratory and field studies related to the Hydrology/Radionuclide Migration Project  

SciTech Connect (OSTI)

This annual report describes research conducted in FY 1990 by Los Alamos National Laboratory for the Hydrology/Radionuclide Migration Project. This multi-agency project measures the underground movement of radionuclides related to nuclear testing at the Nevada Test Site. This project continues the long-term experiment at the site of the Cambric nuclear test. Water pumped from a well adjacent to the explosion cavity continues to show decreasing amounts of tritium and Krypton 85 but no Cesium 139. Analyses of drillback debris shows a distinction between refractory and volatile materials in respect to both their location in the test cavity and their leachability with groundwater. We surveyed materials used during nuclear testing to evaluate any post-test hazard; we concluded that most such materials pose a minimal hazard. The Los Alamos drilling program provided an opportunity for us to sample a collapsed zone above the cavity of a test, which was fired 2 years ago. We continue our research in colloid characterization and in detection of low levels of Technetium 99 in Nevada Test Site water. During FY 1990, we drilled a new hole in the Yucca Flat area to study radionuclide migration. This report also describes Los Alamos management and planning activities in support of this project. 20 refs., 2 figs., 14 tabs.

Thompson, J.L. (comp.)

1991-05-01T23:59:59.000Z

223

Nuclear Reactor (atomic reactor)  

Science Journals Connector (OSTI)

A nuclear reactor splits Uranium or Plutonium nuclei, and the...235 is fissionable but more than 99% of the naturally occurring Uranium is U238 that makes enrichment mandatory. In some reactors U238 and Thorium23...

2008-01-01T23:59:59.000Z

224

Geoscience Perspectives in Carbon Sequestration - Educational Training and Research Through Classroom, Field, and Laboratory Investigations  

SciTech Connect (OSTI)

The most effective mechanism to limit CO{sub 2} release from underground Geologic Carbon Sequestration (GCS) sites over multi-century time scales will be to convert the CO{sub 2} into solid carbonate minerals. This report describes the results from four independent research investigations on carbonate mineralization: 1) Colloidal calcite particles forming in Maramec Spring, Missouri, provide a natural analog to evaluate reactions that may occur in a leaking GCS site. The calcite crystals form as a result of physiochemical changes that occur as the spring water rises from a depth of more than 190'?. The resultant pressure decrease induces a loss of CO{sub 2} from the water, rise in pH, lowering of the solubility of Ca{sup 2+} and CO{sub 3}{sup 2-}, and calcite precipitation. Equilibrium modelling of the spring water resulted in a calculated undersaturated state with respect to calcite. The discontinuity between the observed occurrence of calcite and the model result predicting undersaturated conditions can be explained if bicarbonate ions (HCO{sub 3}{sup -}) are directly involved in precipitation process rather than just carbonate ions (CO{sub 3}{sup 2-}). 2) Sedimentary rocks in the Oronto Group of the Midcontinent Rift (MCR) system contain an abundance of labile Ca-, Mg-, and Fe-silicate minerals that will neutralize carbonic acid and provide alkaline earth ions for carbonate mineralization. One of the challenges in using MCR rocks for GCS results from their low porosity and permeability. Oronto Group samples were reacted with both CO{sub 2}-saturated deionized water at 90C, and a mildly acidic leachant solution in flow-through core-flooding reactor vessels at room temperature. Resulting leachate solutions often exceeded the saturation limit for calcite. Carbonate crystals were also detected in as little as six days of reaction with Oronto Group rocks at 90oC, as well as experiments with forsterite-olivine and augite, both being common minerals this sequence. The Oronto Group samples have poor reservoir rock characteristics, none ever exceeded a permeability value of 2.0 mD even after extensive dissolution of calcite cement during the experiments. The overlying Bayfield Group Jacobsville Formation sandstones averaged 13.4 4.3% porosity and a single sample tested by core-flooding revealed a permeability of ~340 mD. The high porosity-permeability characteristics of these sandstones will allow them to be used for GCS as a continuous aquifer unit with the overlying Mt. Simon Formation. 3) Anaerobic sulfate reducing bacteria (SRB) can enhance the conversion rate of CO{sub 2} into solid minerals and thereby improve long-term storage. SRB accelerated carbonate mineralization reactions between pCO{sub 2} values of 0.0059 and 14.7 psi. Hydrogen, lactate and formate served as suitable electron donors for SRB metabolism. The use of a {sup 13}CO{sub 2} spiked gas source also produced carbonate minerals with ~53% of the carbon being derived from the gas phase. The sulfate reducing activity of the microbial community was limited, however, at 20 psi pCO{sub 2} and carbonate mineralization did not occur. Inhibition of bacterial metabolism may have resulted from the acidic conditions or CO{sub 2} toxicity. 4) Microbialite communities forming in the high turbidity and hypersaline water of Storrs Lake, San Salvador Island, The Bahamas, were investigated for their distribution, mineralogy and microbial diversity. Molecular analysis of the organic mats on the microbialites indicate only a trace amount of cyanobacteria, while anaerobic and photosynthetic non-sulfur bacteria of the phyla Chloroflexi and purple sulfur bacteria of class Gammaproteobacteria were abundant.

Wronkiewicz, David; Paul, Varum; Abousif, Alsedik; Ryback, Kyle

2013-09-30T23:59:59.000Z

225

R Reactor seepage basins soil moisture and resistivity field investigation using cone penetrometer technology, Savannah River Site, Aiken, South Carolina  

SciTech Connect (OSTI)

The focus of this report is the summer 1999 investigation of the shallow groundwater system using cone penetrometer technology characterization methods to determine if the water table is perched beneath the R Reactor Seepage Basins (RRSBs).

Harris, M.K.

2000-02-17T23:59:59.000Z

226

Generation -IV Reactor Concepts  

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

Generation-IV Reactor Concepts Generation-IV Reactor Concepts Thomas H. Fanning Argonne National Laboratory 9700 South Cass Avenue Argonne, Illinois 60439, USA The Generation-IV International Forum (GIF) is a multi-national research and development (R&D) collaboration. The GIF pursues the development of advanced, next generation reactor technology with goals to improve: a) sustainability (effective fuel utilization and minimization of waste) b) economics (competitiveness with respect to other energy sources) c) safety and reliability (e.g., no need for offsite emergency response), and d) proliferation resistance and physical protection The GIF Technology Roadmap exercise selected six generic systems for further study: the Gas- cooled Fast Reactor (GFR), the Lead-cooled Fast Reactor (LFR), the Molten Salt Reactor (MSR),

227

A laboratory and pilot plant scaled continuous stirred reactor separator for the production of ethanol from sugars, corn grits/starch or biomass streams  

SciTech Connect (OSTI)

An improved bio-reactor has been developed to allow the high speed, continues, low energy conversion of various substrates to ethanol. The Continuous Stirred Reactor Separator (CSRS) incorporates gas stripping of the ethanol using a recalculating gas stream between cascading stirred reactors in series. We have operated a 4 liter lab scale unit, and built and operated a 24,000 liter pilot scale version of the bioreactor. High rates of fermentation are maintained in the reactor stages using a highly flocculent yeast strain. Ethanol is recovered from the stripping gas using a hydrophobic solvent absorber (isothermal), after which the gas is returned to the bioreactor. Ethanol can then be removed from the solvent to recover a highly concentrated ethanol product. We have applied the lab scale CSRS to sugars (glucose/sucrose), molasses, and raw starch with simultaneous saccharification and fermentation of the starch granules (SSF). The pilot scale CSRS has been operated as a cascade reactor using dextrins as a feed. Operating data from both the lab and pilot scale CSRS are presented. Details of how the system might be applied to cellulosics, with some preliminary data are also given.

Dale, M.C.; Lei, Shuiwang; Zhou, Chongde

1995-10-01T23:59:59.000Z

228

Thomas Wallner | Argonne National Laboratory  

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

Argonne National Laboratory's Omnivorous Engine Argonne National Laboratory's Omnivorous Engine Argonne National Laboratory's Omnivorous Engine Argonne National Laboratory's Omnivorous Engine Browse by Topic Energy Energy efficiency Vehicles Alternative fuels Automotive engineering Biofuels Diesel Fuel economy Fuel injection Heavy-duty vehicles Hybrid & electric vehicles Hydrogen & fuel cells Internal combustion Powertrain research Vehicle testing Building design Manufacturing Energy sources Renewable energy Bioenergy Solar energy Wind energy Fossil fuels Oil Nuclear energy Nuclear energy modeling & simulation Nuclear fuel cycle Geology & disposal Reactors Nuclear reactor safety Nuclear reactor materials Energy usage Energy life-cycle analysis Energy storage Batteries Lithium-ion batteries Lithium-air batteries Smart Grid

229

Advanced Reactor Technologies | Department of Energy  

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

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

230

Air filters from HVAC systems as possible source of volatile organic compounds (VOC) laboratory and field assays  

Science Journals Connector (OSTI)

The emission of volatile organic compounds (VOC) from air filters of HVAC systems was to be evaluated. In a first study carbonyl compounds (14 aldehydes and two ketones) were measured by reacting them with 2,4-dinitrophenylhydrazine (DNPH). Analysis was done by HPLC and UV detection. In laboratory experiments pieces of used and unused HVAC filters were incubated in test chambers. Filters to be investigated were taken from a filter bank of a large HVAC system in the centre of Berlin. First results show that among those compounds formaldehyde and acetone were found in higher concentrations in the test chambers filled with used filters in comparison to those with unused filters. Parallel field measurements were carried out at the prefilter and main filter banks of the two HVAC systems. Here measurements were carried out simultaneously before and after the filters to investigate whether those aldehydes or ketones arise from the filter material on site. Formaldehyde and acetone significantly increased in concentration after the filters of one HVAC system. In parallel experiments microorganisms were proved to be able to survive on air filters. Therefore, a possible source of formaldehyde and acetone might be microbes.

Hans Schleibinger; Henning Rden

1999-01-01T23:59:59.000Z

231

CRAD, Safety Basis - Oak Ridge National Laboratory High Flux...  

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

Oak Ridge National Laboratory High Flux Isotope Reactor CRAD, Safety Basis - Oak Ridge National Laboratory High Flux Isotope Reactor February 2007 A section of Appendix C to DOE G...

232

Department of Energy Designates the Idaho National Laboratory...  

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

Designates the Idaho National Laboratory Advanced Test Reactor as a National Scientific User Facility Department of Energy Designates the Idaho National Laboratory Advanced Test...

233

CRAD, Occupational Safety & Health - Oak Ridge National Laboratory...  

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

Occupational Safety & Health - Oak Ridge National Laboratory High Flux Isotope Reactor Contractor ORR CRAD, Occupational Safety & Health - Oak Ridge National Laboratory High Flux...

234

Kelly, R. B., Houlsby, G. T. & Byrne, B. W. (2006). Geotechnique 56, No. 9, 617626 A comparison of field and laboratory tests of caisson foundations in  

E-Print Network [OSTI]

Kelly, R. B., Houlsby, G. T. & Byrne, B. W. (2006). Ge´otechnique 56, No. 9, 617­626 617 A comparison of field and laboratory tests of caisson foundations in sand and clay R. B. KELLY ? , G. T. (2002, 2003), Kelly et al. (2003, 2004) and Houlsby et al. (2005, 2006). Suction caissons for offshore

Byrne, Byron

235

Handbook of Reactor Physics  

Science Journals Connector (OSTI)

... THIS handbook is one volume in a series sponsored by the United States Atomic Energy Commission with ... data and reference information in the field of reactors. The volume is devoted to reactor physics and radiation shielding, the latter subject occupying approximately a quarter of the book.

PETER W. MUMMERY

1956-08-25T23:59:59.000Z

236

Rapid multiplexed data acquisition: Application to three-dimensional magnetic field measurements in a turbulent laboratory plasma  

E-Print Network [OSTI]

acquisition at the Swarthmore Spheromak Experiment SSX and Redmond Plasma Physics Laboratory. An application. The Swarthmore Spheromak Experiment SSX 3 has re- cently completed construction, calibration, and testing

Brown, Michael R.

237

Reactor Safety Research Programs  

SciTech Connect (OSTI)

This document summarizes the work performed by Pacific Northwest Laboratory (PNL) from January 1 through March 31, 1981, for the Division of Reactor Safety Research within the U.S. Nuclear Regulatory Commission (NRC). Evaluations of nondestructive examination (NDE) techniques and instrumentation are reported; areas of investigation include demonstrating the feasibility of determining the strength of structural graphite, evaluating the feasibility of detecting and analyzing flaw growth in reactor pressure boundary systems, examining NDE reliability and probabilistic fracture mechanics, and assessing the integrity of pressurized water reactor (PWR) steam generator tubes where service-induced degradation has been indicated. Experimental data and analytical models are being provided to aid in decision-making regarding pipeto- pipe impacts following postulated breaks in high-energy fluid system piping. Core thermal models are being developed to provide better digital codes to compute the behavior of full-scale reactor systems under postulated accident conditions. Fuel assemblies and analytical support are being provided for experimental programs at other facilities. These programs include loss-ofcoolant accident (LOCA) simulation tests at the NRU reactor, Chalk River, Canada; fuel rod deformation, severe fuel damage, and postaccident coolability tests for the ESSOR reactor Super Sara Test Program, Ispra, Italy; the instrumented fuel assembly irradiation program at Halden, Norway; and experimental programs at the Power Burst Facility, Idaho National Engineering Laboratory (INEL). These programs will provide data for computer modeling of reactor system and fuel performance during various abnormal operating conditions.

Edler, S. K.

1981-07-01T23:59:59.000Z

238

Mirror Advanced Reactor Study (MARS) final report summary  

SciTech Connect (OSTI)

The Mirror Advanced Reactor Study (MARS) has resulted in an overview of a first-generation tandem mirror reactor. The central cell fusion plasma is self-sustained by alpha heating (ignition), while electron-cyclotron resonance heating and negative ion beams maintain the electrostatic confining potentials in the end plugs. Plug injection power is reduced by the use of high-field choke coils and thermal barriers, concepts to be tested in the Tandem Mirror Experiment-Upgrade (TMX-U) and Mirror Fusion Test Facility (MFTF-B) at Lawrence Livermore National Laboratory.

Henning, C.D.; Logan, B.G.; Carlson, G.A.; Perkins, L.J.; Werner, R.W.; Gordon, J.D.; Parmer, J.F.; Bilton, J.R.; Glancy, J.E.; Kulcinski, G.L.

1983-12-08T23:59:59.000Z

239

Final Report Independent Verification Survey of the High Flux Beam Reactor, Building 802 Fan House Brookhaven National Laboratory Upton, New York  

SciTech Connect (OSTI)

The Separations Process Research Unit (SPRU) complex located on the Knolls Atomic Power Laboratory (KAPL) site in Niskayuna, New York, was constructed in the late 1940s to research the chemical separation of plutonium and uranium (Figure A-1). SPRU operated as a laboratory scale research facility between February 1950 and October 1953. The research activities ceased following the successful development of the reduction oxidation and plutonium/uranium extraction processes. The oxidation and extraction processes were subsequently developed for large scale use by the Hanford and Savannah River sites (aRc 2008a). Decommissioning of the SPRU facilities began in October 1953 and continued through the 1990s.

Evan Harpeneau

2011-06-24T23:59:59.000Z

240

Savannah River Laboratory monthly report, September 1991  

SciTech Connect (OSTI)

This document details monthly activities at the Savannah River Laboratory. Topics addressed are reactor operation, tritium facilities and production; separation operations; environmental concerns; and waste management. (FI)

Ferrell, J.M. [comp.

1991-12-31T23:59:59.000Z

Note: This page contains sample records for the topic "reactors laboratory field" 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

Sandia National Laboratories Technology Marketing Summaries ...  

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

Sandia National Laboratories 04052013 Industrial Technologies Find More Like This Small-Scale Reactor for the Production of Medical Isotopes Currently, there is a severe...

242

Savannah River Laboratory monthly report, November 1991  

SciTech Connect (OSTI)

This document details monthly activities at the Savannah River Laboratory. Topics addressed are reactor operation; tritium facilities and production; separation operations; environmental concerns; and waste management. (FI)

Ferrell, J.M. (comp.)

1991-01-01T23:59:59.000Z

243

Savannah River Laboratory monthly report, November 1991  

SciTech Connect (OSTI)

This document details monthly activities at the Savannah River Laboratory. Topics addressed are reactor operation; tritium facilities and production; separation operations; environmental concerns; and waste management. (FI)

Ferrell, J.M. [comp.

1991-12-31T23:59:59.000Z

244

Savannah River Laboratory monthly report, August 1991  

SciTech Connect (OSTI)

This document details monthly activities at the Savannah River Laboratory. Topics addressed are reactor operation, tritium facilities and production; separation operations; environmental concerns; and waste management. (FI)

Ferrell, J.M. (comp.)

1991-01-01T23:59:59.000Z

245

Savannah River Laboratory monthly report, August 1991  

SciTech Connect (OSTI)

This document details monthly activities at the Savannah River Laboratory. Topics addressed are reactor operation, tritium facilities and production; separation operations; environmental concerns; and waste management. (FI)

Ferrell, J.M. [comp.

1991-12-31T23:59:59.000Z

246

Spherical torus fusion reactor  

DOE Patents [OSTI]

The object of this invention is to provide a compact torus fusion reactor with dramatic simplification of plasma confinement design. Another object of this invention is to provide a compact torus fusion reactor with low magnetic field and small aspect ratio stable plasma confinement. In accordance with the principles of this invention there is provided a compact toroidal-type plasma confinement fusion reactor in which only the indispensable components inboard of a tokamak type of plasma confinement region, mainly a current conducting medium which carries electrical current for producing a toroidal magnet confinement field about the toroidal plasma region, are retained.

Martin Peng, Y.K.M.

1985-10-03T23:59:59.000Z

247

Special Analysis for the Disposal of the Idaho National Laboratory Unirradiated Light Water Breeder Reactor Rods and Pellets Waste Stream at the Area 5 Radioactive Waste Management Site, Nevada National Security Site, Nye County, Nevada  

SciTech Connect (OSTI)

The purpose of this special analysis (SA) is to determine if the Idaho National Laboratory (INL) Unirradiated Light Water Breeder Reactor (LWBR) Rods and Pellets waste stream (INEL103597TR2, Revision 2) is suitable for disposal by shallow land burial (SLB) at the Area 5 Radioactive Waste Management Site (RWMS). The INL Unirradiated LWBR Rods and Pellets waste stream consists of 24 containers with unirradiated fabricated rods and pellets composed of uranium oxide (UO2) and thorium oxide (ThO2) fuel in zirconium cladding. The INL Unirradiated LWBR Rods and Pellets waste stream requires an SA because the 229Th, 230Th, 232U, 233U, and 234U activity concentrations exceed the Nevada National Security Site (NNSS) Waste Acceptance Criteria (WAC) Action Levels.

Shott, Gregory [NSTec

2014-08-31T23:59:59.000Z

248

Laboratory and Field Testing of Commercially Available Detectors for the Identification of Chemicals of Interest in the Nuclear Fuel Cycle for the Detection of Undeclared Activities  

SciTech Connect (OSTI)

Traditionally, IAEA inspectors have focused on the detection of nuclear indicators as part of infield inspection activities. The ability to rapidly detect and identify chemical as well as nuclear signatures can increase the ability of IAEA inspectors to detect undeclared activities at a site. Identification of chemical indicators have been limited to use in the analysis of environmental samples. Although IAEA analytical laboratories are highly effective, environmental sample processing does not allow for immediate or real-time results to an IAEA inspector at a facility. During a complementary access inspection, under the Additional Protocol, the use of fieldable technologies that can quickly provide accurate information on chemicals that may be indicative of undeclared activities can increase the ability of IAEA to effectively and efficiently complete their mission. The Complementary Access Working Group (CAWG) is a multi-laboratory team with members from Brookhaven National Laboratory, Idaho National Laboratory, Los Alamos National Laboratory, and Sandia National Laboratory. The team identified chemicals at each stage of the nuclear fuel cycle that may provide IAEA inspectors with indications that proliferation activities may be occurring. The group eliminated all indicators related to equipment, technology and training, developing a list of by-products/effluents, non-nuclear materials, nuclear materials, and other observables. These proliferation indicators were prioritized based on detectability from a conduct of operations (CONOPS) perspective of a CA inspection (for example, whether an inspector actually can access the S&O or whether it is in process with no physical access), and the IAEAs interest in the detection technology in conjunction with radiation detectors. The list was consolidated to general categories (nuclear materials from a chemical detection technique, inorganic chemicals, organic chemicals, halogens, and miscellaneous materials). The team then identified commercial off the shelf (COTS) chemical detectors that may detect the chemicals of interest. Three chemical detectors were selected and tested both in laboratory settings and in field operations settings at Idaho National Laboratory. The instruments selected are: Thermo Scientific TruDefender FT (FTIR), Thermo Scientific FirstDefender RM (Raman), and Bruker Tracer III SD (XRF). Functional specifications, operability, and chemical detectability, selectivity, and limits of detection were determined. Results from the laboratory and field tests will be presented. This work is supported by the Next Generation Safeguards Initiative, Office of Nonproliferation and International Security, National Nuclear Security Administration.

Carla Miller; Mary Adamic; Stacey Barker; Barry Siskind; Joe Brady; Warren Stern; Heidi Smartt; Mike McDaniel; Mike Stern; Rollin Lakis

2014-07-01T23:59:59.000Z

249

Nuclear power reactor education and training at the Ford nuclear reactor  

SciTech Connect (OSTI)

Since 1977, staff members of the University of Michigan's Ford nuclear reactor have provided courses and reactor laboratory training programs for reactor operators, engineers, and technicians from seven electric utilities, including Cleveland Electric Illuminating, Consumers Power, Detroit Edison, Indiana and Michigan Electric, Nebraska Public Power, Texas Utilities Generating Company, and Toledo Edison. Reactor laboratories, instrument technician training, and reactor physics courses have been conducted at the university. Courses conducted at plant sites include reactor physics, thermal sciences, materials sciences, and health physics and radiation protection.

Burn, R.R.

1989-01-01T23:59:59.000Z

250

Phototransformation of Triclosan in Surface Waters:? A Relevant Elimination Process for This Widely Used BiocideLaboratory Studies, Field Measurements, and Modeling  

Science Journals Connector (OSTI)

Phototransformation of Triclosan in Surface Waters:? A Relevant Elimination Process for This Widely Used BiocideLaboratory Studies, Field Measurements, and Modeling ... The phototransformation of the widely used biocide triclosan (5-chloro-2-(2,4-dichlorophenoxy)phenol) was quantified for surface waters using artificial UV light and sunlight irradiation. ... The pH of surface waters, commonly ranging from 7 to 9, determines the speciation of triclosan (pKa = 8.1) and therefore its absorption of sunlight. ...

Cline Tixier; Heinz P. Singer; Silvio Canonica; Stephan R. Mller

2002-07-10T23:59:59.000Z

251

Modeling and analysis framework for core damage propagation during flow-blockage-initiated accidents in the Advanced Neutron Source reactor at Oak Ridge National Laboratory  

SciTech Connect (OSTI)

This paper describes modeling and analysis to evaluate the extent of core damage during flow blockage events in the Advanced Neutron Source (ANS) reactor planned to be built at ORNL. Damage propagation is postulated to occur from thermal conduction between dmaged and undamaged plates due to direct thermal contact. Such direct thermal contact may occur beause of fuel plate swelling during fission product vapor release or plate buckling. Complex phenomena of damage propagation were modeled using a one-dimensional heat transfer model. A parametric study was done for several uncertain variables. The study included investigating effects of plate contact area, convective heat transfer coefficient, thermal conductivity on fuel swelling, and initial temperature of the plate being contacted by the damaged plate. Also, the side support plates were modeled to account for their effects of damage propagation. Results provide useful insights into how variouss uncertain parameters affect damage propagation.

Kim, S.H.; Taleyarkhan, R.P.; Navarro-Valenti, S.; Georgevich, V.

1995-12-31T23:59:59.000Z

252

Reactor Thermal-Hydraulics  

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

Thermal-Hydraulics Thermal-Hydraulics Dr. Tanju Sofu, Argonne National Laboratory In a power reactor, the energy produced in fission reaction manifests itself as heat to be removed by a coolant and utilized in a thermodynamic energy conversion cycle to produce electricity. A simplified schematic of a typical nuclear power plant is shown in the diagram below. Primary coolant loop Steam Reactor Heat exchanger Primary pump Secondary pump Condenser Turbine Water Although this process is essentially the same as in any other steam plant configuration, the power density in a nuclear reactor core is typically four orders of magnitude higher than a fossil fueled plant and therefore it poses significant heat transfer challenges. Maximum power that can be obtained from a nuclear reactor is often limited by the

253

Decommissioning of the Tokamak Fusion Test Reactor  

SciTech Connect (OSTI)

The Tokamak Fusion Test Reactor (TFTR) at the Princeton Plasma Physics Laboratory was operated from 1982 until 1997. The last several years included operations with mixtures of deuterium and tritium. In September 2002, the three year Decontamination and Decommissioning (D&D) Project for TFTR was successfully completed. The need to deal with tritium contamination as well as activated materials led to the adaptation of many techniques from the maintenance work during TFTR operations to the D&D effort. In addition, techniques from the decommissioning of fission reactors were adapted to the D&D of TFTR and several new technologies, most notably the development of a diamond wire cutting process for complex metal structures, were developed. These techniques, along with a project management system that closely linked the field crews to the engineering staff who developed the techniques and procedures via a Work Control Center, resulted in a project that was completed safely, on time, and well below budget.

E. Perry; J. Chrzanowski; C. Gentile; R. Parsells; K. Rule; R. Strykowsky; M. Viola

2003-10-28T23:59:59.000Z

254

Achievements: Nuclear Reactors designed/built by Argonne National  

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

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

255

Los Alamos National Laboratory  

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

that's the hallmark of the Laboratory. This year's stories include alternative energy research, world record magnetic fields, disease tracking, the study of Mars, climate...

256

Evaluation of Alternate Materials for Coated Particle Fuels for the Gas-Cooled Fast Reactor. Laboratory Directed Research and Development Program FY 2006 Final Report  

SciTech Connect (OSTI)

Candidate ceramic materials were studied to determine their suitability as Gas-Cooled Fast Reactor particle fuel coatings. The ceramics examined in this work were: TiC, TiN, ZrC, ZrN, AlN, and SiC. The studies focused on (i) chemical reactivity of the ceramics with fission products palladium and rhodium, (ii) the thermomechanical stresses that develop in the fuel coatings from a variety of causes during burnup, and (iii) the radiation resiliency of the materials. The chemical reactivity of TiC, TiN, ZrC, and ZrN with Pd and Rh were all found to be much lower than that of SiC. A number of important chemical behaviors were observed at the ceramic-metal interfaces, including the formation of specific intermetallic phases and a variation in reaction rates for the different ceramics investigated. Based on the data collected in this work, the nitride ceramics (TiN and ZrN) exhibit chemical behavior that is characterized by lower reaction rates with Pd and Rh than the carbides TiC and ZrC. The thermomechanical stresses in spherical fuel particle ceramic coatings were modeled using finite element analysis, and included contributions from differential thermal expansion, fission gas pressure, fuel kernel swelling, and thermal creep. In general the tangential stresses in the coatings during full reactor operation are tensile, with ZrC showing the lowest values among TiC, ZrC, and SiC (TiN and ZrN were excluded from the comprehensive calculations due to a lack of available materials data). The work has highlighted the fact that thermal creep plays a critical role in the development of the stress state of the coatings by relaxing many of the stresses at high temperatures. To perform ion irradiations of sample materials, an irradiation beamline and high-temperature sample irradiation stage was constructed at the University of Wisconsins 1.7MV Tandem Accelerator Facility. This facility is now capable of irradiating of materials to high dose while controlling sample temperature up to 800C.

Paul A. Demkowicz; Karen Wright; Jian Gan; David Petti; Todd Allen; Jake Blanchard

2006-09-01T23:59:59.000Z

257

Field and laboratory investigations of coring-induced damage in core recovered from Marker Bed 139 at the waste isolation pilot plant underground facility  

SciTech Connect (OSTI)

A combined laboratory and field investigation was carried out to determine the extent of coring-induced damage done to samples cored from Marker Bed 139 at the WIPP site. Coring-induced damage, if present, has the potential to significantly change the properties of the material used for laboratory testing relative to the in situ material properties, resulting in misleading conclusions. In particular, connected, crack-like damage could make the permeability of cored samples orders of magnitude greater than the in situ permeabilities. Our approach compared in situ velocity and resistivity measurements with laboratory measurements of the same properties. Differences between in situ and laboratory results could be attributed to differences in the porosity due to cracks. The question of the origin of the changes could not be answered directly from the results of the measurements. Pre-existing cracks, held closed by the in situ stress, could open when the core was cut free, or new cracks could be generated by coring-induced damage. We used core from closely spaced boreholes at three orientations (0{degree}, {plus_minus}45{degrees} relative to vertical) to address the origin of cracks. The absolute orientation of pre-existing cracks would be constant, independent of the borehole orientation. In contrast, cracks induced by coring were expected to show an orientation dependent on that of the source borehole.

Holcomb, D.J.; Zeuch, D.H.; Morin, K.; Hardy, R.; Tormey, T.V.

1995-09-01T23:59:59.000Z

258

Argonne National Laboratory's Nondestructive  

E-Print Network [OSTI]

the safe operationof advanced nuclear reactors. Argonne's World-Class Nondestructive Evaluation and other government laboratories to develop new techniques and assess the reliability of conventional and electromagnetic interaction with complex media as well as advanced signal processing and data analysis

Kemner, Ken

259

The deployment of three prototype detectors for reactor monitoring and safeguards  

Science Journals Connector (OSTI)

Fission reactors emit large numbers of antineutrinos and this flux may be useful for the measurement of two quantities of interest for reactor safeguards: the reactor's power and plutonium inventory throughout its cycle. The high antineutrino flux and relatively low background rates means that simple cubic meter scale detectors at tens of meters standoff can record hundreds or thousands of antineutrino events per day. Such antineutrino detectors would add online, quasi-real-time bulk material accountancy to the set of reactor monitoring tools available to the IAEA and other safeguards agencies with minimal impact on reactor operations. Our LLNL/SNL collaboration has deployed a total of three prototype safeguards detectors at a reactor in Southern California in order to test both the method and the practicality of its implementation in the field. Results from these detectors will be presented, and their respective advantages and disadvantages described. LLNL-POST-404014 This work was performed under the auspices of the U.S. Department of Energy by Lawrence Livermore National Laboratory in part under Contract W-7405-Eng-48 and in part under Contract DE-AC52-07NA27344. Sandia National Laboratories is a multiprogram laboratory operated by Sandia Corporation, a Lockheed Martin Company, for the United States Department of Energy under contract DE-AC04-94AL85000.

N S Bowden; A Bernstein; S Dazeley; J Lund; D Reyna; L Sadler; R Svoboda

2008-01-01T23:59:59.000Z

260

field  

National Nuclear Security Administration (NNSA)

9%2A en Ten-Year Site Plans (TYSP) http:nnsa.energy.govaboutusouroperationsinfopsinfopstysp

field field-type-text field-field-page-name">

Note: This page contains sample records for the topic "reactors laboratory field" 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

Radiation from Small-Scale Magnetic Field Turbulence: Implications for Gamma-Ray Bursts and Laboratory Astrophysical Plasmas  

E-Print Network [OSTI]

a region of current filamentation, and show that the jitter radiation may be used as a radiative diagnostic to determine features of the magnetic field distribution within this region. For gamma-ray bursts, this instability may play a significant...

Reynolds, Sarah J

2012-05-31T23:59:59.000Z

262

Effects of local microbial bioaugmentation and biostimulation on the bioremediation of total petroleum hydrocarbons (TPH) in crude oil contaminated soil based on laboratory and field observations  

Science Journals Connector (OSTI)

Abstract This study investigated factors enhancing the performance of the bioremediation of Total Petroleum Hydrocarbons (TPHs) in crude oil-contaminated soil in laboratory and field observations. The bioaugmentation process used local microbial consortia (MC1, MC2 and MC3) combined with the biostimulation processes of nutrient addition (mineralsalt medium, MSM and NPK) and enhanced air stimulation (air supply and Oxygen Releasing Compound (ORC)). The microcosm tests were conducted in tank and soil column setups, whereas the field test was performed in test plots inside an oil and gas facility in Malaysia. In the microcosm tank experiment, the combination of bioaugmentation (10% inoculum size of MC3) and MSM biostimulation yielded the highest TPH degradation of 79% of the total. In the column experiments, the degradation of \\{TPHs\\} in the top soil was highest in columns combining bioaugmentation and nutrient addition, whereas in the bottom soil, the degradation of \\{TPHs\\} was highest in columns combining bioaugmentation with the addition of both nutrients and ORCs. In the field demonstration, 97% of the \\{TPHs\\} were degraded in the top soil (01m) when bioaugmented with MC2. The kinetic analysis study of the microcosm tank showed that a combination of both biostimulation and bioaugmentation in the soil column achieved the fastest rate constant of 0.0390day?1. The field test also demonstrated a comparable rate constant of 0.0339day?1. The kinetic rate constants in both the laboratory and field indicated that the best treatment method for the contaminated site is a combination of MC3 bioaugmentation and nutrient biostimulation.

Fatihah Suja; Fazli Rahim; Mohd Raihan Taha; Nuraini Hambali; M. Rizal Razali; Alia Khalid; Ainon Hamzah

2014-01-01T23:59:59.000Z

263

Spherical torus fusion reactor  

DOE Patents [OSTI]

A fusion reactor is provided having a near spherical-shaped plasma with a modest central opening through which straight segments of toroidal field coils extend that carry electrical current for generating a toroidal magnet plasma confinement fields. By retaining only the indispensable components inboard of the plasma torus, principally the cooled toroidal field conductors and in some cases a vacuum containment vessel wall, the fusion reactor features an exceptionally small aspect ratio (typically about 1.5), a naturally elongated plasma cross section without extensive field shaping, requires low strength magnetic containment fields, small size and high beta. These features combine to produce a spherical torus plasma in a unique physics regime which permits compact fusion at low field and modest cost.

Peng, Yueng-Kay M. (Oak Ridge, TN)

1989-01-01T23:59:59.000Z

264

Chemical Concentrations in Field Mice from Open-Detonation Firing Sites TA-36 Minie and TA-39 Point 6 at Los Alamos National Laboratory  

SciTech Connect (OSTI)

Field mice (mostly Peromyscus spp.) were collected at two open-detonation (high explosive) firing sites - Minie at Technical Area (TA) 36 and Point 6 at TA-39 - at Los Alamos National Laboratory in August of 2010 and in February of 2011 for chemical analysis. Samples of whole body field mice from both sites were analyzed for target analyte list elements (mostly metals), dioxin/furans, polychlorinated biphenyl congeners, high explosives, and perchlorate. In addition, uranium isotopes were analyzed in a composite sample collected from TA-36 Minie. In general, all constituents, with the exception of lead at TA-39 Point 6, in whole body field mice samples collected from these two open-detonation firing sites were either not detected or they were detected below regional statistical reference levels (99% confidence level), biota dose screening levels, and/or soil ecological chemical screening levels. The amount of lead in field mice tissue collected from TA-39 Point 6 was higher than regional background, and some lead levels in the soil were higher than the ecological screening level for the field mouse; however, these levels are not expected to affect the viability of the populations over the site as a whole.

Fresquez, Philip R. [Los Alamos National Laboratory

2011-01-01T23:59:59.000Z

265

INFLATION OF A DIPOLE FIELD IN LABORATORY EXPERIMENTS: TOWARD AN UNDERSTANDING OF MAGNETODISK FORMATION IN THE MAGNETOSPHERE OF A HOT JUPITER  

SciTech Connect (OSTI)

Giant exoplanets at close orbits, or so-called hot Jupiters, are supposed to have an intensive escape of upper atmospheric material heated and ionized by the radiation of a host star. An interaction between outflowing atmospheric plasma and the intrinsic planetary magnetic dipole field leads to the formation of a crucial feature of a hot Jupiter's magnetosphere-an equatorial current-carrying magnetodisk. The presence of a magnetodisk has been shown to influence the topology of a hot Jupiter's magnetosphere and to change a standoff distance of the magnetopause. In this paper, the basic features of the formation of a hot Jupiter's magnetodisk are studied by means of a laboratory experiment. A localized central source produces plasma that expands outward from the surface of the dipole and inflates the magnetic field. The observed structure of magnetic fields, electric currents, and plasma density indicates the formation of a relatively thin current disk extending beyond the Alfvenic point. At the edge of the current disk, an induced magnetic field was found to be several times larger than the field of the initial dipole.

Antonov, V. M.; Boyarinsev, E. L.; Boyko, A. A.; Zakharov, Yu. P.; Melekhov, A. V.; Ponomarenko, A. G.; Posukh, V. G.; Shaikhislamov, I. F. [Institute of Laser Physics SB RAS, Novosibirsk (Russian Federation); Khodachenko, M. L.; Lammer, H., E-mail: maxim.khodachenko@oeaw.ac.at [Space Research Institute, Austrian Acad. Sci., Graz (Austria)

2013-05-20T23:59:59.000Z

266

History of Research Reactors at Brookhaven  

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

History of Research Reactors at Brookhaven History of Research Reactors at Brookhaven Brookhaven National Laboratory has three nuclear reactors on its site that were used for scientific research. The reactors are all shut down, and the Laboratory is addressing environmental issues associated with their operations. photo of BGRR Brookhaven Graphite Research Reactor - Beginning operations in 1950, the graphite reactor was used for research in medicine, biology, chemistry, physics and nuclear engineering. One of the most significant achievements at this facility was the development of technetium-99m, a radiopharmaceutical widely used to image almost any organ in the body. The graphite reactor was shut down in 1969. Parts of it have been decommissioned, with the remainder to be addressed by 2011. More history

267

University Reactor Conversion Lessons Learned Workshop for the University of Florida  

SciTech Connect (OSTI)

The Department of Energys (DOE) Idaho National Laboratory (INL), under its programmatic responsibility for managing the University Research Reactor Conversions, has completed the conversion of the reactor at the University of Florida. This project was successfully completed through an integrated and collaborative effort involving the INL, Argonne National Laboratory (ANL), DOE (Headquarters and Field Office), the Nuclear Regulatory Commission, the Universities, and contractors involved in analyses, fuel design and fabrication, and SNF shipping and disposition. With the work completed with these two universities, and in anticipation of other impending conversion projects, INL convened and engaged the project participants in a structured discussion to capture lessons learned. The objectives of this meeting were to capture the observations, insights, issues, concerns, and ideas of those involved in the reactor conversions so that future efforts can be conducted with greater effectiveness, efficiency, and with fewer challenges.

Eric C. Woolstenhulme; Dana M. Meyer

2007-04-01T23:59:59.000Z

268

Nuclear Energy Enabling Technologies (NEET) Reactor Materials  

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

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

269

Ris Report No. 372 5 Ris National Laboratory  

E-Print Network [OSTI]

generation in nuclear boiling water reactors is limited by a thermohydraulic phenomenon called burnout. When and Annuli at 30 to 90 bar by Jørgen Wurtz Risø National Laboratory Department of Reactor Technology Abstract

270

Riso Report No. 372 5 Riso National Laboratory  

E-Print Network [OSTI]

generation in nuclear boiling water reactors is limited by a thermohydraulic phenomenon called burnout. When and Annuli at 30 to 90 bar by J0rgen Wiirtz Ris0 National Laboratory Department of Reactor Technology

271

Experiments at The Virtual National Laboratory for Heavy Ion Fusion  

E-Print Network [OSTI]

Heavy Ion Beam Driven Fusion Reactor Study", KfK 3840,between the reactor chamber wall and the fusion target. Thereactor chambers. INTRODUCTION The USA Virtual National Laboratory for Heavy Ion Fusion

2000-01-01T23:59:59.000Z

272

Measurements of photon ionizing radiation fields in the reactor room of the 4th power-generating unit of the chernobyl nuclear power plant  

Science Journals Connector (OSTI)

A radiation examination of the reactor room of the damaged fourth unit of the Chernobyl nuclear power plant was performed. The most strongly radiating surfaces...

A. G. Volkovich; V. N. Potapov; S. V. Smirnov; L. I. Urutskoev

2000-03-01T23:59:59.000Z

273

University Reactor Conversion Lessons Learned Workshop for Purdue University Reactor  

SciTech Connect (OSTI)

The Department of Energys Idaho National Laboratory, under its programmatic responsibility for managing the University Research Reactor Conversions, has completed the conversion of the reactor at Purdue University Reactor. With this work completed and in anticipation of other impending conversion projects, the INL convened and engaged the project participants in a structured discussion to capture the lessons learned. The lessons learned process has allowed us to capture gaps, opportunities, and good practices, drawing from the project teams experiences. These lessons will be used to raise the standard of excellence, effectiveness, and efficiency in all future conversion projects.

Eric C. Woolstenhulme; Dana M. Hewit

2008-09-01T23:59:59.000Z

274

BNL | Our History: Reactors as Research Tools  

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

> See also: Accelerators > See also: Accelerators Brookhaven History: Using Reactors as Research Tools BGRR Brookhaven Graphite Research Reactor The Brookhaven Graphite Research Reactor (BGRR) was the Laboratory's first big machine and the first peace-time reactor built in the United States following World War II. The reactor's primary mission was to produce neutrons for scientific experimentation and to refine reactor technology. At the time, the BGRR could accommodate more simultaneous experiments than any other reactor. Scientists and engineers from every corner of the U.S. came to use the reactor, which was not only a source of neutrons for experiments, but also an excellent training facility. Researchers used the BGRR's neutrons as tools for studying atomic nuclei and the structure of solids, and to investigate many physical, chemical and

275

NUCLEAR REACTORS.  

E-Print Network [OSTI]

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

Belachew, Dessalegn

2010-01-01T23:59:59.000Z

276

Energy Secretary to Visit Georgia Nuclear Reactor Site and Tennessee...  

Energy Savers [EERE]

Energy Secretary to Visit Georgia Nuclear Reactor Site and Tennessee Laboratory to Highlight Administration Support for Nuclear Energy Energy Secretary to Visit Georgia Nuclear...

277

Light Water Reactor Sustainability Newsletter Thomas M. Rosseel  

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

Laboratory (ORNL), through the Department of Energy's (DOE) Light Water Reactor Sustainability (LWRS) Program, is coordinating and contracting with Zion Solutions, LLC (a...

278

Small Business Manager Oak Ridge National Laboratory  

E-Print Network [OSTI]

Keith Joy Small Business Manager Oak Ridge National Laboratory: Past, Present, and Future #12;2 OAK was the world's first continuously operated nuclear reactor Oak Ridge National Laboratory evolved from the Manhattan Project 2 OAK RIDGE NATIONAL LABORATORY U. S. DEPARTMENT OF ENERGY Overview_0604 #12;3 OAK RIDGE

279

Using laboratory flow experiments and reactive chemical transport modeling for designing waterflooding of the Agua Fria Reservoir, Poza Rica-Altamira Field, Mexico  

SciTech Connect (OSTI)

Waterflooding for enhanced oil recovery requires that injected waters must be chemically compatible with connate reservoir waters, in order to avoid mineral dissolution-and-precipitation cycles that could seriously degrade formation permeability and injectivity. Formation plugging is a concern especially in reservoirs with a large content of carbonates, such as calcite and dolomite, as such minerals typically react rapidly with an aqueous phase, and have strongly temperature-dependent solubility. Clay swelling can also pose problems. During a preliminary waterflooding pilot project, the Poza Rica-Altamira oil field, bordering the Gulf coast in the eastern part of Mexico, experienced injectivity loss after five months of reinjection of formation waters into well AF-847 in 1999. Acidizing with HCl restored injectivity. We report on laboratory experiments and reactive chemistry modeling studies that were undertaken in preparation for long-term waterflooding at Agua Frma. Using analogous core plugs obtained from the same reservoir interval, laboratory coreflood experiments were conducted to examine sensitivity of mineral dissolution and precipitation effects to water composition. Native reservoir water, chemically altered waters, and distilled water were used, and temporal changes in core permeability, mineral abundances and aqueous concentrations of solutes were monitored. The experiments were simulated with the multi-phase, nonisothermal reactive transport code TOUGHREACT, and reasonable to good agreement was obtained for changes in solute concentrations. Clay swelling caused an additional impact on permeability behavior during coreflood experiments, whereas the modeled permeability depends exclusively on chemical processes. TOUGHREACT was then used for reservoir-scale simulation of injecting ambient-temperature water (30 C, 86 F) into a reservoir with initial temperature of 80 C (176 F). Untreated native reservoir water was found to cause serious porosity and permeability reduction due to calcite precipitation, which is promoted by the retrograde solubility of this mineral. Using treated water that performed well in the laboratory flow experiments was found to avoid excessive precipitation, and allowed injection to proceed.

Birkle, P.; Pruess, K.; Xu, T.; Figueroa, R.A. Hernandez; Lopez, M. Diaz; Lopez, E. Contreras

2008-10-01T23:59:59.000Z

280

Independent Oversight Targeted Review, Oak Ridge National Laboratory- April 2014  

Broader source: Energy.gov [DOE]

Targeted Review of Radiological Controls Activity-Level Implementation at the Oak Ridge National Laboratory Radiochemical Engineering Development Center and High Flux Isotope Reactor Facilities

Note: This page contains sample records for the topic "reactors laboratory field" 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

Polynomial regression with derivative information in nuclear reactor uncertainty quantification*  

E-Print Network [OSTI]

, Argonne National Laboratory, Argonne, IL, USA b Nuclear Engineering Division, Argonne National Laboratory1 Polynomial regression with derivative information in nuclear reactor uncertainty quantification, Argonne, IL, USA Abstract. We introduce a novel technique of uncertainty quantification using polynomial

Anitescu, Mihai

282

Energistics Laboratory facility  

Science Journals Connector (OSTI)

Energistics Laboratory in Houston Texas is a leading laboratory for the testing of HVAC equipment. For over 15 years this facility has ensured the highest standards in leading?edge HVAC technology and architectural testing capabilities. Testing capabilities include both industry standard rating procedures and mock?up testing to simulate field conditions. The laboratory is open to developers owners architects engineers general contractors manufacturers and others who require independent component testing and evaluation.

2001-01-01T23:59:59.000Z

283

Sandia National Laboratories: Reactor Component Testing  

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

Doppler Velocimeter EC Top Publications A Comparison of Platform Options for Deep-water Floating Offshore Vertical Axis Wind Turbines: An Initial Study Nonlinear Time-Domain...

284

Argonne step closer to safer nuclear reactor  

Science Journals Connector (OSTI)

Argonne step closer to safer nuclear reactor ... "A key technological link" toward development of meltdown-immune nuclear reactors is now in the demonstration phase at Argonne National Laboratory near Chicago. ... The technique is part of Argonne's continuing interest in the sodium-cooled integral fast reactor (IFR), whose immunity to meltdown derives from molten sodium's function as a heat sink and the use of metallic fuel that conducts heat better than conventional oxide fuels. ...

WARD WORTHY

1988-05-30T23:59:59.000Z

285

LABORATORY V ELECTRIC CIRCUITS  

E-Print Network [OSTI]

Lab V -1 LABORATORY V ELECTRIC CIRCUITS Electrical devices are the cornerstones of our modern world understanding of them. In the previous laboratory, you studied the behavior of electric fields and their effect on the motion of electrons using a cathode ray tube (CRT). This beam of electrons is one example of an electric

Minnesota, University of

286

Sandia National Laboratories: Magnetically Stimulated Flow Patterns...  

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

said, the technology could be practical in problems ranging from reactor cooling to microfluidics, a multidisciplinary field used, for example, in designing systems that handle...

287

Brookhaven National Laboratory | Department of Energy  

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

Brookhaven National Laboratory Brookhaven National Laboratory Brookhaven National Laboratory Site Overview The Brookhaven National Laboratory (BNL) was established in 1947 by the Atomic Energy Commission (AEC) (predecessor to U.S. Department of Energy [DOE]). Formerly Camp Upton, a U.S. Army installation site, Brookhaven is located on 5,263-acre site on Long Island in Upton, New York, approximately 60 miles east of New York City. Historically, BNL was involved in the construction of accelerators and research reactors such as the Cosmotron, the High Flux Beam Reactor (HFBR) and the Brookhaven Graphite Research Reactor (BGRR). These accelerators and reactors lead the way in high-energy physics experiments and subsequent discoveries. To complete the EM BNL mission the following must be completed, all

288

DOE - Office of Legacy Management -- Argonne National Laboratory - West -  

Office of Legacy Management (LM)

Argonne National Laboratory - West Argonne National Laboratory - West - 014 FUSRAP Considered Sites Site: Argonne National Laboratory - West (014) Designated Name: Alternate Name: Location: Evaluation Year: Site Operations: Site Disposition: Radioactive Materials Handled: Primary Radioactive Materials Handled: Radiological Survey(s): Site Status: The primary mission of the Argonne National Laboratory-West was to support liquid metal reactor research and development for the Department of Energy¿s Integral Fast Reactor Program, but the program was terminated. Activities at the Laboratory now include technology development for spent nuclear fuel and waste treatment, reactor and fuel cycle safety, and facility decommissioning. The decommissioning and other clean up is being

289

A next-generation reactor concept: The Integral Fast Reactor (IFR)  

SciTech Connect (OSTI)

The Integral Fast Reactor (IFR) is an advanced liquid metal reactor concept being developed at Argonne National Laboratory as reactor technology for the 21st century. It seeks to specifically exploit the inherent properties of liquid metal cooling and metallic fuel in a way that leads to substantial improvements in the characteristics of the complete reactor system, in particular passive safety and waste management. The IFR concept consists of four technical features: (1) liquid sodium cooling, (2) pool-type reactor configuration, (3) metallic fuel, and (4) fuel cycle closure based on pyroprocessing.

Chang, Y.I.

1992-01-01T23:59:59.000Z

290

A next-generation reactor concept: The Integral Fast Reactor (IFR)  

SciTech Connect (OSTI)

The Integral Fast Reactor (IFR) is an advanced liquid metal reactor concept being developed at Argonne National Laboratory as reactor technology for the 21st century. It seeks to specifically exploit the inherent properties of liquid metal cooling and metallic fuel in a way that leads to substantial improvements in the characteristics of the complete reactor system, in particular passive safety and waste management. The IFR concept consists of four technical features: (1) liquid sodium cooling, (2) pool-type reactor configuration, (3) metallic fuel, and (4) fuel cycle closure based on pyroprocessing.

Chang, Y.I.

1992-07-01T23:59:59.000Z

291

CRAD, Nuclear Safety - Oak Ridge National Laboratory High Flux Isotope  

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

CRAD, Nuclear Safety - Oak Ridge National Laboratory High Flux CRAD, Nuclear Safety - Oak Ridge National Laboratory High Flux Isotope Reactor CRAD, Nuclear Safety - Oak Ridge National Laboratory High Flux Isotope Reactor February 2007 A section of Appendix C to DOE G 226.1-2 "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of Criteria Review and Approach Documents (CRADs) used for a February 2007 assessment of the Nuclear Safety Program in preparation for restart of the Oak Ridge National Laboratory High Flux Isotope Reactor. CRADs provide a recommended approach and the types of information to gather to assess elements of a DOE contractor's programs. CRAD, Nuclear Safety - Oak Ridge National Laboratory High Flux Isotope Reactor More Documents & Publications CRAD, Engineering - Oak Ridge National Laboratory High Flux Isotope Reactor

292

Field Sampling and Analysis Plan for the Remedial Investigation of Waste Area Grouping 2 at Oak Ridge National Laboratory, Oak Ridge, Tennessee. Responses to comments  

SciTech Connect (OSTI)

This report provides responses to US Environmental Protection Agency Region IV EPA-M and Tennessee Department of Environment and Conservation Oversite Division (TDEC-O) comments on report ORNL/ER-58, Field Sampling and Analysis Plan for the Remedial Investigation of Waste Area Grouping 2 at Oak Ridge National Laboratory, Oak Ridge, Tennessee. Waste Area Grouping (WAG) 2 consists of the White Oak Creek (WOC) drainage system downgradient of the major ORNL WAGs in the WOC watershed. A strategy for the remedial investigation (RI) of WAG2 was developed in report ES/ER-14&Dl, Remedial Investigation Plan for Waste Area Grouping 2 at Oak Ridge National Laboratory, Oak Ridge, Tennessee. This strategy takes full advantage of WAG2`s role as an integrator of contaminant releases from the ORNL WAGs in the WOC watershed, and takes full advantage of WAG2`s role as a conduit for contaminants from the ORNL site to the Clinch River. The strategy calls for a multimedia environmental monitoring and characterization program to be conducted in WAG2 while upgradient contaminant sources are being remediated. This monitoring and characterization program will (1) identify and quantify contaminant fluxes, (2) identify pathways of greatest concern for human health and environmental risk, (3) improve conceptual models of contaminant movement, (4) support the evaluation of remedial alternatives, (5) support efforts to prioritize sites for remediation, (6) document the reduction in contaminant fluxes following remediation, and (7) support the eventual remediation of WAG2. Following this strategy, WAG2 has been termed an ``integrator WAG,`` and efforts in WAG2 over the short term are directed toward supporting efforts to remediate the contaminant ``source WAGS`` at ORNL.

Not Available

1992-10-01T23:59:59.000Z

293

Ground-water characterization field activities for 1995--1996 Laboratory for Energy-Related Health Research, University of California, Davis  

SciTech Connect (OSTI)

This report documents ground-water characterization field activities completed from August to December 1995 and in January 1996 at the Laboratory for Energy-Related Health Research (LEHR) in Davis, California. The ground water at LEHR is one of several operable units under investigation by Pacific Northwest National Laboratory for the US Department of Energy. The purpose of this work was to further characterize the hydrogeology beneath the LEHR site, with the primary focus on ground water. The objectives were to estimate hydraulic properties for the two uppermost saturated hydrogeologic units (i.e., HSU-1 and HSU-2), and to determine distributions of contaminants of concern in these units. Activities undertaken to accomplish these objectives include well installation, geophysical logging, well development, ground-water sampling, slug testing, Westbay ground-water monitoring system installation, continuous water-level monitoring, Hydropunch installation, and surveying. Ground-water samples were collected from 61 Hydropunch locations. Analytical results from these locations and the wells indicate high chloroform concentrations trending from west/southwest to east/northeast in the lower portion of HSU-1 and in the upper and middle portions of HSU-2. The chloroform appears to originate near Landfill 2. Tritium was not found above the MCL in any of the well or Hydropunch samples. Hexavalent chromium was found at four locations with concentrations above the MCL in HSU-1 and at one location in HSU-2. One well in HSU-1 had a total chromium concentration above the MCL. Nitrate-nitrogen above the MCL was found at several Hydropunch locations in both HSU-1 and HSU-2.

Liikala, T.L.; Lanigan, D.C.; Last, G.V. [and others

1996-05-01T23:59:59.000Z

294

Light Water Reactor Sustainability (LWRS) Program | Department of Energy  

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

Light Water Reactor Light Water Reactor Sustainability (LWRS) Program Light Water Reactor Sustainability (LWRS) Program Light Water Reactor Sustainability (LWRS) Program The Light Water Reactor Sustainability (LWRS) Program is developing the scientific basis to extend existing nuclear power plant operating life beyond the current 60-year licensing period and ensure long-term reliability, productivity, safety, and security. The program is conducted in collaboration with national laboratories, universities, industry, and international partners. Idaho National Laboratory serves as the Technical Integration Office and coordinates the research and development (R&D) projects in the following pathways: Materials Aging and Degradation Assessment, Advanced Instrumentation, Information, and Control Systems

295

Alamos National Laboratory  

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

record neutron beam at Los record neutron beam at Los Alamos National Laboratory July 10, 2012 New method has potential to advance materials measurement LOS ALAMOS, New Mexico, July 10, 2012-Using a one-of-a-kind laser system at Los Alamos National Laboratory, scientists have created the largest neutron beam ever made by a short-pulse laser, breaking a world record. Neutron beams are usually made with particle accelerators or nuclear reactors and are commonly used in a wide variety of scientific research, particularly in advanced materials science. Using the TRIDENT laser, a unique and powerful 200 trillion-watt short-pulse laser, scientists from Los Alamos, the Technical University of Darmstadt, Germany, and Sandia National Laboratories focus high-intensity light on an ultra-thin plastic sheet

296

Research | Savannah River Ecology Laboratory  

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

SREL scientists pursue a wide variety of ecological research, from molecular to landscape-scale processes, field and laboratory focused, basic and applied. Such an integrated...

297

Sandia National Laboratories: Heliostat Field  

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

Engine Test Facility Central Receiver Test Facility Power Towers for Utilities Solar Furnace Dish Test Facility Optics Lab Parabolic Dishes Work For Others (WFO) User...

298

Research reactors - an overview  

SciTech Connect (OSTI)

A broad overview of different types of research and type reactors is provided in this paper. Reactor designs and operating conditions are briefly described for four reactors. The reactor types described include swimming pool reactors, the High Flux Isotope Reactor, the Mark I TRIGA reactor, and the Advanced Neutron Source reactor. Emphasis in the descriptions is placed on safety-related features of the reactors. 7 refs., 7 figs., 2 tabs.

West, C.D.

1997-03-01T23:59:59.000Z

299

Accident Investigation of the June 17, 2012, Construction Accident- Structural Steel Collapse at The Over pack Storage Expansion #2 at the Naval Reactors Facility at the Idaho National Laboratory, Idaho Falls, Idaho  

Broader source: Energy.gov [DOE]

This report documents the Naval Reactors investigation into the collapse ofa partially-erected spent fuel storage building, Overpack Storage Expansion #2 (OSE2), at the Naval Reactors Facility. The Accident Investigation Board inspected the scene, collected physical and photographic evidence, interviewed involved personnel, and reviewed relevant documents to determine the key causes of the accident. Based on the information gathered during the investigation, the Board identified several engineering and safety deficiencies that need to be addressed to prevent recurrence.

300

Light Water Reactor Sustainability  

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

4 Light Water Reactor Sustainability ACCOMPLISHMENTS REPORT 2014 Accomplishments Report | Light Water Reactor Sustainability 2 T he mission of the Light Water Reactor...

Note: This page contains sample records for the topic "reactors laboratory field" 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

Physics of nuclear reactor safety  

Science Journals Connector (OSTI)

Provides a concise review of the physical aspects of safety of nuclear fission reactors. It covers the developments of roughly the last decade. The introductory chapter contains an analysis of the changes in safety philosophy that are characteristic of the last decade and that have given rise to an increased importance of physical aspects because of the emphasis on passive or natural safety. The second chapter focuses on the basics of reactor safety, identifying the main risk sources and the main principles for a safe design. The third chapter concerns a systematic treatment of the physical processes that are fundamental for the properties of fission chain reacting processes and the control of those processes. Because of the rather specialized nature of the field of reactor physics, each paragraph contains a very concise description of the theory of the phenomenon under consideration, before presenting a review of the developments. Chapter 4 contains a short review of the thermal aspects of reactor safety, restricted to those aspects that are characteristic of the nuclear reactor field, because thermal hydraulics of fission reactors is not principally different from that of other physical systems. In chapter 5 the consequences of the physics treated in the preceding chapters for the dynamics and safety of actual reactors are reviewed. The systematics of the treatment is mainly based on a division of reactors into three categories according to the type of coolant, which to a large extent determines the safety properties of the reactors. The last chapter contains a physical analysis of the Chernobyl accident that occurred in 1986. The reason for an attempt to give a review of this accident, as complete as possible within the space limits set by the editors, is twofold: the Chernobyl accident is the most severe accident in history and physical properties of the reactor played a decisive role, thereby serving as an illustration of the material of the preceding chapters.

H van Dam

1992-01-01T23:59:59.000Z

302

Advanced Test Reactor National Scientific User Facility  

SciTech Connect (OSTI)

The Advanced Test Reactor (ATR), at the Idaho National Laboratory (INL), is a large test reactor for providing the capability for studying the effects of intense neutron and gamma radiation on reactor materials and fuels. The ATR is a pressurized, light-water, high flux test reactor with a maximum operating power of 250 MWth. The INL also has several hot cells and other laboratories in which irradiated material can be examined to study material irradiation effects. In 2007 the US Department of Energy (DOE) designated the ATR as a National Scientific User Facility (NSUF) to facilitate greater access to the ATR and the associated INL laboratories for material testing research by a broader user community. This paper highlights the ATR NSUF research program and the associated educational initiatives.

Frances M. Marshall; Jeff Benson; Mary Catherine Thelen

2011-08-01T23:59:59.000Z

303

National Laboratory Poornima Upadhya  

E-Print Network [OSTI]

-program national laboratory operated by Brookhaven Science Associates for the U.S. Department of Energy is not detrimentally affected by the magnetic fields produced by the MRI scanner. The technology allows one which includes a magnet for producing a magnetic field suitable for magnetic resonance imaging

304

CRAD, Safety Basis - Oak Ridge National Laboratory High Flux Isotope  

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

Reactor Contractor ORR Reactor Contractor ORR CRAD, Safety Basis - Oak Ridge National Laboratory High Flux Isotope Reactor Contractor ORR February 2007 A section of Appendix C to DOE G 226.1-2 "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of Criteria Review and Approach Documents (CRADs) used for a February 2007 assessment of the Safety Basis portion of an Operational Readiness Review of the Oak Ridge National Laboratory High Flux Isotope Reactor. CRADs provide a recommended approach and the types of information to gather to assess elements of a DOE contractor's programs. CRAD, Safety Basis - Oak Ridge National Laboratory High Flux Isotope Reactor Contractor ORR More Documents & Publications CRAD, Engineering - Oak Ridge National Laboratory High Flux Isotope Reactor

305

PROTEUS - Simulation Toolset for Reactor Physics and Fuel Cycle Analysis  

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

Simulation Toolset for Simulation Toolset for Reactor Physics and Fuel Cycle Analysis PROTEUS Faster and more accurate neutronics calculations enable optimum reactor design... Argonne National Laboratory's powerful reactor physics toolset, PROTEUS, empowers users to create optimal reactor designs quickly, reliably and accurately. ...Reducing costs for designers of fast spectrum reactors. PROTEUS' long history of validation provides confidence in predictive simulations Argonne's simulation tools have more than 30 years of validation history against numerous experiments and measurements. The tools within PROTEUS work together, using the same interface files for easier integration of calculations. Multi-group Fast Reactor Cross Section Processing: MC 2 -3 No other fast spectrum multigroup generation tool

306

Catalytic reactor  

DOE Patents [OSTI]

A catalytic reactor is provided with one or more reaction zones each formed of set(s) of reaction tubes containing a catalyst to promote chemical reaction within a feed stream. The reaction tubes are of helical configuration and are arranged in a substantially coaxial relationship to form a coil-like structure. Heat exchangers and steam generators can be formed by similar tube arrangements. In such manner, the reaction zone(s) and hence, the reactor is compact and the pressure drop through components is minimized. The resultant compact form has improved heat transfer characteristics and is far easier to thermally insulate than prior art compact reactor designs. Various chemical reactions are contemplated within such coil-like structures such that as steam methane reforming followed by water-gas shift. The coil-like structures can be housed within annular chambers of a cylindrical housing that also provide flow paths for various heat exchange fluids to heat and cool components.

Aaron, Timothy Mark (East Amherst, NY); Shah, Minish Mahendra (East Amherst, NY); Jibb, Richard John (Amherst, NY)

2009-03-10T23:59:59.000Z

307

Alternate-fuel reactor studies  

SciTech Connect (OSTI)

A number of studies related to improvements and/or greater understanding of alternate-fueled reactors is presented. These studies cover the areas of non-Maxwellian distributions, materials and lifetime analysis, a /sup 3/He-breeding blanket, tritium-rich startup effects, high field magnet support, and reactor operation spanning the range from full D-T operation to operation with no tritium breeding.

Evans, K. Jr.; Ehst, D.A.; Gohar, Y.; Jung, J.; Mattas, R.F.; Turner, L.R.

1983-02-01T23:59:59.000Z

308

TRAC-PF1: an advanced best-estimate computer program for pressurized water reactor analysis  

SciTech Connect (OSTI)

The Transient Reactor Analysis Code (TRAC) is being developed at the Los Alamos National Laboratory to provide advanced best-estimate predictions of postulated accidents in light water reactors. The TRAC-PF1 program provides this capability for pressurized water reactors and for many thermal-hydraulic experimental facilities. The code features either a one-dimensional or a three-dimensional treatment of the pressure vessel and its associated internals; a two-phase, two-fluid nonequilibrium hydrodynamics model with a noncondensable gas field; flow-regime-dependent constitutive equation treatment; optional reflood tracking capability for both bottom flood and falling-film quench fronts; and consistent treatment of entire accident sequences including the generation of consistent initial conditions. This report describes the thermal-hydraulic models and the numerical solution methods used in the code. Detailed programming and user information also are provided.

Liles, D.R.; Mahaffy, J.H.

1984-02-01T23:59:59.000Z

309

Sandia National Laboratories is a multi-program laboratory operated by Sandia Co  

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

Sandia National Laboratories is a multi-program laboratory operated by Sandia Corporation, a wholly owned subsidiary of Lockheed Martin Sandia National Laboratories is a multi-program laboratory operated by Sandia Corporation, a wholly owned subsidiary of Lockheed Martin company, for the U.S. Department of Energy's National Nuclear Security Administration. With main facilities in Albuquerque, N.M., and Livermore, Calif., Sandia has major R&D responsibilities in national security, energy and environmental technologies and economic competitiveness. Annular Core Research Reactor Facility At the Annular Core Research Reactor (ACRR) facility, Sandia researchers can subject various test objects to a

310

Assessment of torsatrons as reactors  

SciTech Connect (OSTI)

Stellarators have significant operational advantages over tokamaks as ignited steady-state reactors because stellarators have no dangerous disruptions and no need for continuous current drive or power recirculated to the plasma, both easing the first wall, blanket, and shield design; less severe constraints on the plasma parameters and profiles; and better access for maintenance. This study shows that a reactor based on the torsatron configuration (a stellarator variant) could also have up to double the mass utilization efficiency (MUE) and a significantly lower cost of electricity (COE) than a conventional tokamak reactor (ARIES-I) for a range of assumptions. Torsatron reactors can have much smaller coil systems than tokamak reactors because the coils are closer to the plasma and they have a smaller cross section (higher average current density because of the lower magnetic field). The reactor optimization approach and the costing and component models are those used in the current stage of the ARIES-I tokamak reactor study. Typical reactor parameters for a 1-GW(e) Compact Torsatron reactor example are major radius R[sub 0] = 6.6-8.8 m, on-axis magnetic field B[sup 0] = 4.8-7.5 T, B[sub max] (on coils) = 16 T, MUE 140-210 kW(e)/tonne, and COE (in constant 1990 dollars) = 67-79 mill/kW(e)h. The results are relatively sensitive to assumptions on the level of confinement improvement and the blanket thickness under the inboard half of the helical windings but relatively insensitive to other assumptions.

Lyon, J.F. (Oak Ridge National Lab., TN (United States)) [Oak Ridge National Lab., TN (United States); Painter, S.L. (Australian National Univ., Canberra, ACT (Australia)) [Australian National Univ., Canberra, ACT (Australia)

1992-12-01T23:59:59.000Z

311

Assessment of torsatrons as reactors  

SciTech Connect (OSTI)

Stellarators have significant operational advantages over tokamaks as ignited steady-state reactors because stellarators have no dangerous disruptions and no need for continuous current drive or power recirculated to the plasma, both easing the first wall, blanket, and shield design; less severe constraints on the plasma parameters and profiles; and better access for maintenance. This study shows that a reactor based on the torsatron configuration (a stellarator variant) could also have up to double the mass utilization efficiency (MUE) and a significantly lower cost of electricity (COE) than a conventional tokamak reactor (ARIES-I) for a range of assumptions. Torsatron reactors can have much smaller coil systems than tokamak reactors because the coils are closer to the plasma and they have a smaller cross section (higher average current density because of the lower magnetic field). The reactor optimization approach and the costing and component models are those used in the current stage of the ARIES-I tokamak reactor study. Typical reactor parameters for a 1-GW(e) Compact Torsatron reactor example are major radius R{sub 0} = 6.6-8.8 m, on-axis magnetic field B{sup 0} = 4.8-7.5 T, B{sub max} (on coils) = 16 T, MUE 140-210 kW(e)/tonne, and COE (in constant 1990 dollars) = 67-79 mill/kW(e)h. The results are relatively sensitive to assumptions on the level of confinement improvement and the blanket thickness under the inboard half of the helical windings but relatively insensitive to other assumptions.

Lyon, J.F. [Oak Ridge National Lab., TN (United States); Painter, S.L. [Australian National Univ., Canberra, ACT (Australia)

1992-12-01T23:59:59.000Z

312

Reactor antineutrino monitoring with a plastic scintillator array as a new safeguards method  

E-Print Network [OSTI]

We developed a segmented reactor-antineutrino detector made of plastic scintillators for application as a tool in nuclear safeguards inspection and performed mostly unmanned field operations at a commercial power plant reactor. At a position outside the reactor building, we measured the difference in reactor antineutrino flux above the ground when the reactor was active and inactive.

S. Oguri; Y. Kuroda; Y. Kato; R. Nakata; Y. Inoue; C. Ito; M. Minowa

2014-05-23T23:59:59.000Z

313

Reactor antineutrino monitoring with a plastic scintillator array as a new safeguards method  

Science Journals Connector (OSTI)

Abstract We developed a segmented reactor-antineutrino detector made of plastic scintillators for application as a tool in nuclear safeguards inspection and performed mostly unmanned field operations at a commercial power plant reactor. At a position outside the reactor building, we measured the difference in reactor antineutrino flux above the ground when the reactor was active and inactive.

S. Oguri; Y. Kuroda; Y. Kato; R. Nakata; Y. Inoue; C. Ito; M. Minowa

2014-01-01T23:59:59.000Z

314

Wireless Transmission of Monitoring Data out of an Underground Repository: Results of Field Demonstrations Performed at the HADES Underground Laboratory - 13589  

SciTech Connect (OSTI)

As part of the European 7. framework project MoDeRn, Nuclear Research and Consultancy Group (NRG) performed experiments in order to demonstrate the feasibility of wireless data transmission through the subsurface over large distances by low frequency magnetic fields in the framework of the geological disposal of radioactive waste. The main objective of NRG's contribution is to characterize and optimize the energy use of this technique within the specific context of post-closure monitoring of a repository. For that, measurements have been performed in the HADES Underground Research Laboratory (URL) located at Mol, Belgium, at 225 m depth. The experimental set-up utilizes a loop antenna for the transmitter that has been matched to the existing infrastructure of the HADES. Between 2010 and 2012 NRG carried out several experiments at the HADES URL in order to test the technical set-up and to characterize the propagation behavior of the geological medium and the local background noise pattern. Transmission channels have been identified and data transmission has been demonstrated at several frequencies, with data rates up to 10 bit/s and bit error rates <1%. A mathematical model description that includes the most relevant characteristics of the transmitter, transmission path, and receiver has been developed and applied to analyze possible options to optimize the set-up. With respect to the energy-efficiency, results so far have shown that data transmission over larger distances through the subsurface is a feasible option. To support the conclusions on the energy need per bit of transmitted data, additional experiments are foreseen. (authors)

Schroeder, T.J.; Rosca-Bocancea, E.; Hart, J. [Nuclear Research and Consultancy Group (NRG), P.O. Box 25, NL-1755 ZG Petten (Netherlands)] [Nuclear Research and Consultancy Group (NRG), P.O. Box 25, NL-1755 ZG Petten (Netherlands)

2013-07-01T23:59:59.000Z

315

Advanced Safeguards Approaches for New Fast Reactors  

SciTech Connect (OSTI)

This third report in the series reviews possible safeguards approaches for new fast reactors in general, and the ABR in particular. Fast-neutron spectrum reactors have been used since the early 1960s on an experimental and developmental level, generally with fertile blanket fuels to breed nuclear fuel such as plutonium. Whether the reactor is designed to breed plutonium, or transmute and burn actinides depends mainly on the design of the reactor neutron reflector and the whether the blanket fuel is fertile or suitable for transmutation. However, the safeguards issues are very similar, since they pertain mainly to the receipt, shipment and storage of fresh and spent plutonium and actinide-bearing TRU-fuel. For these reasons, the design of existing fast reactors and details concerning how they have been safeguarded were studied in developing advanced safeguards approaches for the new fast reactors. In this regard, the design of the Experimental Breeder Reactor-II EBR-II at the Idaho National Laboratory (INL) was of interest, because it was designed as a collocated fast reactor with a pyrometallurgical reprocessing and fuel fabrication line a design option being considered for the ABR. Similarly, the design of the Fast Flux Facility (FFTF) on the Hanford Site was studied, because it was a successful prototype fast reactor that ran for two decades to evaluate fuels and the design for commercial-scale fast reactors.

Durst, Philip C.; Therios, Ike; Bean, Robert; Dougan, A.; Boyer, Brian; Wallace, Rick L.; Ehinger, Michael H.; Kovacic, Don N.; Tolk, K.

2007-12-15T23:59:59.000Z

316

CRAD, Emergency Management - Oak Ridge National Laboratory High Flux  

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

Oak Ridge National Laboratory High Oak Ridge National Laboratory High Flux Isotope Reactor CRAD, Emergency Management - Oak Ridge National Laboratory High Flux Isotope Reactor February 2007 A section of Appendix C to DOE G 226.1-2 "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of Criteria Review and Approach Documents (CRADs) used for a February 2007 assessment of the Emergency Management Program in preparation for restart of the Oak Ridge National Laboratory High Flux Isotope Reactor. CRADs provide a recommended approach and the types of information to gather to assess elements of a DOE contractor's programs. CRAD, Emergency Management - Oak Ridge National Laboratory High Flux Isotope Reactor More Documents & Publications CRAD, Emergency Management - Oak Ridge National Laboratory High Flux

317

CRAD, DOE Oversight - Oak Ridge National Laboratory High Flux Isotope  

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

Oak Ridge National Laboratory High Flux Oak Ridge National Laboratory High Flux Isotope Reactor CRAD, DOE Oversight - Oak Ridge National Laboratory High Flux Isotope Reactor A section of Appendix C to DOE G 226.1-2 "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of Criteria Review and Approach Documents (CRADs) used for a DOE independent oversight assessment of the Oak Ridge National Laboratory programs for oversight of its contractors. CRADs provide a recommended approach and the types of information to gather to assess elements of a DOE contractor's programs. CRAD, DOE Oversight - Oak Ridge National Laboratory High Flux Isotope Reactor More Documents & Publications CRAD, Nuclear Safety - Oak Ridge National Laboratory High Flux Isotope Reactor

318

Safeguards Laboratory (SL) | ORNL  

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

Safeguards Laboratory Safeguards Laboratory May 30, 2013 The Safeguards Laboratory is a Department of Energy user facility equipped with a comprehensive set of field-deployable instrumentation for safeguards system development and personnel training. Mock-ups using industrial equipment and reference nuclear materials simulate real-world conditions for training, testing, and evaluations. The lab's openness and availability to the private sector enable development of new technologies that combat the proliferation of weapons of mass destruction. Applications Training and International Outreach Nondestructive Analysis Measurements Instrument Evaluations Integrated Safeguards Methodologies Measurement Technique Development Specifications Gamma and X-ray detection systems Handheld survey instruments

319

Laboratory Operations  

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

hydrological controls on carbon cycling in flood plain ecosystems into Earth System Models. - 5814 A neutron detector like this one at Los Alamos National Laboratory is...

320

Fusion reactor systems  

Science Journals Connector (OSTI)

In this review we consider deuterium-tritium (D-T) fusion reactors based on four different plasma-confinement and heating approaches: the tokamak, the theta-pinch, the magnetic-mirror, and the laser-pellet system. We begin with a discussion of the dynamics of reacting plasmas and basic considerations of reactor power balance. The essential plasma physical aspects of each system are summarized, and the main characteristics of the corresponding conceptual power plants are described. In tokamak reactors the plasma densities are about 1020 m-3, and the ? values (ratio of plasma pressure to confining magnetic pressure) are approximately 5%. Plasma burning times are of the order of 100-1000 sec. Large superconducting dc magnets furnish the toroidal magnetic field, and 2-m thick blankets and shields prevent heat deposition in the superconductor. Radially diffusing plasma is diverted away from the first wall by means of null singularities in the poloidal (or transverse) component of the confining magnetic field. The toroidal theta-pinch reactor has a much smaller minor diameter and a much larger major diameter, and operates on a 10-sec cycle with 0.1-sec burning pulses. It utilizes shock heating from high-voltage sources and adabatic-compression heating powered by low-voltage, pulsed cryogenic magnetic or inertial energy stores, outside the reactor core. The plasma has a density of about 1022 m-3 and ? values of nearly unity. In the power balance of the reactor, direct-conversion energy obtained by expansion of the burning high-? plasma against the containing magnetic field is an important factor. No divertor is necessary since neutral-gas flow cools and replaces the "spent" plasma between pulses. The open-ended mirror reactor uses both thermal conversion of neutron energy and direct conversion of end-loss plasma energy to dc electrical power. A fraction of this direct-convertor power is then fed back to the ioninjection system to sustain the reaction and maintain the plasma. The average ion energy is 600 keV, plasma diameter 6 m, and the plasma beta 85%. The power levels of the three magnetic-confinement devices are in the 500-2000 MWe range, with the exception of the mirror reactor, for which the output is approximately 200 MWe. In Laser-Pellet reactors, frozen D-T pellets are ignited in a cavity which absorbs the electromagnetic, charged particle, and neutron energy from the fusion reaction. The confinement is "inertial," since the fusion reaction occurs during the disassembly of the heated pellet. A pellet-cavity unit would produce about 200 MWt in pulses with a repetition rate of the order of 10 sec-1. Such units could be clustered to give power plants with outputs in the range of 1000 MWe.

F. L. Ribe

1975-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "reactors laboratory field" 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

Light Water Reactors Technology Development - Nuclear Reactors  

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

322

Graphite Reactor | ornl.gov  

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

Graphite Reactor Graphite Reactor 'In the early, desperate days of World War II, the United States launched the top-secret, top-priority Manhattan Project...' In the early, desperate days of U.S. involvement in World War II, American scientists began to fear that the German discovery of uranium fission in 1939 might enable the Nazis to develop a super bomb. Afraid of losing this crucial race, the United States launched the top-secret, top-priority Manhattan Project. The plan was to create two atomic weapons-one fueled by plutonium, the other by enriched uranium. Hanford, Washington, was selected as the site for plutonium production, but before large reactors could be built there, a pilot plant was necessary to prove the feasibility of scaling up from laboratory experiments. A secluded, rural area near Clinton, Tennessee, was

323

Advanced ultrasonic imaging of piping in Dresden and Vermont Yankee reactors  

SciTech Connect (OSTI)

Pacific Northwest Laboratory (PNL) has been developing the synthetic aperture focusing technique for ultrasonic testing (SAFT-UT) for the US Nuclear Regulatory Commission (NRC). Objectives are to make a real-time field system for performing all required inservice inpsections on nuclear power plants. The NRC funded the laboratory phase of the work at the University of Michigan. The PNL role is to transfer the technology to the field. This paper reports on the experience gained during 1984 involving the inspection of two boiling water reactor (BWR) plants in the United States. These field trials were very successful and demonstrated the advantages of using a flexible, high resolution imaging system to aid in detecting and interpreting ultrasonic reflectors.

Doctor, S.R.; Hall, T.E.; Crawford, S.L.

1985-03-01T23:59:59.000Z

324

Development and validation of a real-time SAFT-UT system for the inspection of light water reactor components. Semiannual report, April 1984-September 1984. Volume 1  

SciTech Connect (OSTI)

The Pacific Northwest Laboratory is working to design, fabricate, and evaluate a real-time flaw detection and characterization system based on the synthetic aperture focusing technique for ultrasonic testing (SAFT-UT). The system is for inservice inspection of light water reactor components. Included objectives of this program for the Nuclear Regulatory Commission are to develop procedures for system calibration and field operation, to validate the system through laboratory and field inspections, and to generate an engineering data base to support ASME Code acceptance of the technology. This process report covers the programmatic work from April 1984 through September 1984. 58 figs.

Doctor, S.R.; Busse, L.J.; Crawford, S.L.; Hall, T.E.; Gribble, R.P.; Baldwin, A.J.; Van Houten, L.P.

1986-05-01T23:59:59.000Z

325

Development and validation of a real-time SAFT-UT system for the inspection of light water reactor components: Annual report, October 1984-September 1985  

SciTech Connect (OSTI)

The Pacific Northwest Laboratory is working to design, fabricate, and evaluate a real-time flaw detection and characterization system based on the synthetic aperture focusing technique for ultrasonic testing (SAFT-UT). The system is designed to perform inservice inspection of light-water reactor components. Included objectives of this program for the Nuclear Regulatory Commission are to develop procedures for system calibration and field operation, to validate the system through laboratory and field inspections, and to generate an engineering data base to support ASME Code acceptance of the technology. This progress report covers the programmatic work from October 1984 through September 1985.

Doctor, S.R.; Hall, T.E.; Reid, L.D.; Crawford, S.L.; Littlefield, R.J.; Gilbert, R.W.

1987-06-01T23:59:59.000Z

326

CRAD, Radiological Controls - Oak Ridge National Laboratory High Flux  

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

High High Flux Isotope Reactor CRAD, Radiological Controls - Oak Ridge National Laboratory High Flux Isotope Reactor February 2007 A section of Appendix C to DOE G 226.1-2 "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of Criteria Review and Approach Documents (CRADs) used for a February 2007 assessment of the Radiation Protection Program in preparation for restart of the Oak Ridge National Laboratory High Flux Isotope Reactor. CRADs provide a recommended approach and the types of information to gather to assess elements of a DOE contractor's programs. CRAD, Radiological Controls - Oak Ridge National Laboratory High Flux Isotope Reactor More Documents & Publications CRAD, Engineering - Oak Ridge National Laboratory High Flux Isotope Reactor

327

CRAD, Conduct of Operations - Oak Ridge National Laboratory High Flux  

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

Reactor Reactor CRAD, Conduct of Operations - Oak Ridge National Laboratory High Flux Isotope Reactor February 2007 A section of Appendix C to DOE G 226.1-2 "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of Criteria Review and Approach Documents (CRADs) used for a February, 2007 assessment of the Conduct of Operations Program in preparation for restart of the Oak Ridge National Laboratory, High Flux Isotope Reactor. CRADs provide a recommended approach and the types of information to gather to assess elements of a DOE contractor's programs. CRAD, Conduct of Operations - Oak Ridge National Laboratory High Flux Isotope Reactor More Documents & Publications CRAD, Fire Protection - Oak Ridge National Laboratory High Flux Isotope

328

Photo of the Week: The Sixth Zero Power Reactor | Department of Energy  

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

The Sixth Zero Power Reactor The Sixth Zero Power Reactor Photo of the Week: The Sixth Zero Power Reactor November 13, 2013 - 4:41pm Addthis In 1958, Argonne National Laboratory began the construction of several zero-power reactors (ZPRs), which are nuclear fission reactors that don't actually generate any power. Scientists developed ZPRs to assess the performance of various reactor core configurations before actually building a full nuclear reactor. A series of ZPRs were built leading up to the construction of the Experimental Breeder Reactor-II, a sodium-cooled fast reactor power plant. In this 1970 photo, an Argonne scientist is loading the matrices of the ZPR-VI reactor prior to its first operation using plutonium fuel. | Photo courtesy of the Department of Energy. In 1958, Argonne National Laboratory began the construction of several

329

Superconducting magnets for toroidal fusion reactors  

SciTech Connect (OSTI)

Fusion reactors will soon be employing superconducting magnets to confine plasma in which deuterium and tritium (D-T) are fused to produce usable energy. At present there is one small confinement experiment with superconducting toroidal field (TF) coils: Tokamak 7 (T-7), in the USSR, which operates at 4 T. By 1983, six different 2.5 x 3.5-m D-shaped coils from six manufacturers in four countries will be assembled in a toroidal array in the Large Coil Test Facility (LCTF) at Oak Ridge National Laboratory (ORNL) for testing at fields up to 8 T. Soon afterwards ELMO Bumpy Torus (EBT-P) will begin operation at Oak Ridge with superconducting TF coils. At the same time there will be tokamaks with superconducting TF coils 2 to 3 m in diameter in the USSR and France. Toroidal field strength in these machines will range from 6 to 9 T. NbTi and Nb/sub 3/Sn, bath cooling and forced flow, cryostable and metastable - various designs are being tried in this period when this new application of superconductivity is growing and maturing.

Haubenreich, P.N.

1980-01-01T23:59:59.000Z

330

Independent Activity Report, Sandia National Laboratories - March 2013 |  

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

Sandia National Laboratories - March Sandia National Laboratories - March 2013 Independent Activity Report, Sandia National Laboratories - March 2013 March 2013 Operational Awareness Oversight of Sandia National Laboratories [HIAR SNL-2013-03-18] The purpose of this Office of Health, Safety and Security (HSS) Independent Oversight activity was to perform an operational awareness site visit to Sandia National Laboratories (SNL) to discuss Annular Core Research Reactor (ACRR) issues and improvement plan. SNL management also briefed Independent Oversight on engineered safety implementation. Independent Activity Report, Sandia National Laboratories - March 2013 More Documents & Publications Independent Activity Report, Sandia National Laboratories - April 2012 Independent Oversight Targeted Review, Sandia National Laboratories -

331

Recovery Act Workers Clear Reactor Shields from Brookhaven Lab | Department  

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

Workers Clear Reactor Shields from Brookhaven Lab Workers Clear Reactor Shields from Brookhaven Lab Recovery Act Workers Clear Reactor Shields from Brookhaven Lab American Recovery and Reinvestment Act workers are in the final stage of decommissioning a nuclear reactor after they recently removed thick steel shields once used to absorb neutrons produced for research. The Brookhaven National Laboratory is using $39 million from the Recovery Act to decommission the Brookhaven Graphite Research Reactor, the world's first reactor built solely for peaceful research purposes. Recovery Act Workers Clear Reactor Shields from Brookhaven Lab More Documents & Publications Brookhaven Graphite Research Reactor Workshop 2011 ARRA Newsletters Idaho Crews Overcome Challenges to Safely Dispose 1-Million-Pound Hot Cell

332

High Flux Beam Reactor | Environmental Restoration Projects | BNL  

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

Environmental Protection Division Environmental Protection Division Home Reactor Projects Celebrating DOE's Cleanup Accomplishments (PDF) Brookhaven Graphite Research Reactor(BGRR) BGRR Overview BGRR Complex Description Decommissioning Decision BGRR Complex Cleanup Actions BGRR Documents BGRR Science & Accomplishments High Flux Beam Reactor (HFBR) HFBR Overview HFBR Complex Description Decommissioning Decision HFBR Complex Cleanup Actions HFBR Documents HFBR Science & Accomplishments Groundwater Protection Group Environmental Protection Division Contact > See also: HFBR Science & Accomplishments High Flux Beam Reactor Under the U.S. Department of Energy (DOE), the High Flux Beam Reactor (HFBR) at Brookhaven National Laboratory (BNL) underwent stabilization and partial decommissioning to prepare the HFBR confinement for long-term safe

333

Solar Thermochemical Advanced Reactor System, Wins R&D 100 Award...  

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

National Laboratory, the Solar Thermochemical Advanced Reactor System, or STARS, converts natural gas and sunlight into a more energy-rich fuel called syngas, which power plants...

334

Improved Design of Nuclear Reactor Control System | U.S. DOE...  

Office of Science (SC) Website

instrumentation: Improved Design of Nuclear Reactor Control System Developed at: Oak Ridge National Laboratory, Holifield Radioactive Ion Beam Facility (HRIBF) Developed...

335

E-Print Network 3.0 - argonaut bilbao reactor Sample Search Results  

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

reprocessing and transmutation... with industry, national laboratories, and universities; upgrading and sharing of research reactors Source: Laughlin, Robert B. - Department of...

336

CRAD, Environmental Protection - Oak Ridge National Laboratory High Flux  

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

Environmental Protection - Oak Ridge National Laboratory High Environmental Protection - Oak Ridge National Laboratory High Flux Isotope Reactor CRAD, Environmental Protection - Oak Ridge National Laboratory High Flux Isotope Reactor February 2007 A section of Appendix C to DOE G 226.1-2 "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of Criteria Review and Approach Documents (CRADs) used for a February 2007 assessment of the Environmental Compliance Program in preparation for restart of the Oak Ridge National Laboratory High Flux Isotope Reactor. CRADs provide a recommended approach and the types of information to gather to assess elements of a DOE contractor's programs. CRAD, Environmental Protection - Oak Ridge National Laboratory High Flux Isotope Reactor More Documents & Publications

337

CRAD, Configuration Management - Oak Ridge National Laboratory High Flux  

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

Configuration Management - Oak Ridge National Laboratory High Configuration Management - Oak Ridge National Laboratory High Flux Isotope Reactor CRAD, Configuration Management - Oak Ridge National Laboratory High Flux Isotope Reactor February 2007 A section of Appendix C to DOE G 226.1-2 "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of Criteria Review and Approach Documents (CRADs) used for a February 2007 assessment of the Configuration Management Program in preparation for restart of the Oak Ridge National Laboratory, High Flux Isotope Reactor. CRADs provide a recommended approach and the types of information to gather to assess elements of a DOE contractor's programs. CRAD, Configuration Management - Oak Ridge National Laboratory High Flux Isotope Reactor More Documents & Publications

338

CRAD, Emergency Management - Oak Ridge National Laboratory High Flux  

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

Oak Ridge National Laboratory High Oak Ridge National Laboratory High Flux Isotope Reactor Contractor ORR CRAD, Emergency Management - Oak Ridge National Laboratory High Flux Isotope Reactor Contractor ORR February 2007 A section of Appendix C to DOE G 226.1-2 "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of Criteria Review and Approach Documents (CRADs) used for a February 2007 assessment of the Emergency Management Program portion of an Operational Readiness Review of the Oak Ridge National Laboratory High Flux Isotope Reactor. CRADs provide a recommended approach and the types of information to gather to assess elements of a DOE contractor's programs. CRAD, Emergency Management - Oak Ridge National Laboratory High Flux Isotope Reactor Contractor ORR

339

Photocatalytic reactor  

DOE Patents [OSTI]

A photocatalytic reactor is described for processing selected reactants from a fluid medium comprising at least one permeable photocatalytic membrane having a photocatalytic material. The material forms an area of chemically active sites when illuminated by light at selected wavelengths. When the fluid medium is passed through the illuminated membrane, the reactants are processed at these sites separating the processed fluid from the unprocessed fluid. A light source is provided and a light transmitting means, including an optical fiber, for transmitting light from the light source to the membrane. 4 figs.

Bischoff, B.L.; Fain, D.E.; Stockdale, J.A.D.

1999-01-19T23:59:59.000Z

340

Italian hybrid and fission reactors scenario analysis  

SciTech Connect (OSTI)

Italy is a country where a long tradition of studies both in the fission and fusion field is consolidated; nevertheless a strong public opinion concerned with the destination of the Spent Nuclear Fuel hinders the development of nuclear power. The possibility to a severe reduction of the NSF mass generated from a fleet of nuclear reactors employing an hypothetical fusionfission hybrid reactor has been investigated in the Italian framework. The possibility to produce nuclear fuel for the fission nuclear reactors with the hybrid reactor was analyzed too.

Ciotti, M.; Manzano, J.; Sepielli, M. [ENEA CR Frascati, Via Enrico Fermi, 45, 00044, Frascati, Roma (Italy); ENEA CR casaccia, Via Anguillarese, 301, 00123, Santa Maria di Galeria, Roma (Italy)

2012-06-19T23:59:59.000Z

Note: This page contains sample records for the topic "reactors laboratory field" 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

EPR/PTFE dosimetry for test reactor environments  

SciTech Connect (OSTI)

The use of Electron Paramagnetic Resonance (EPR) spectroscopy with materials such as alanine is well established as a technique for measurement of ionizing radiation absorbed dose in photon and electron fields such as Co-60, high-energy bremsstrahlung and electron-beam fields [1]. In fact, EPR/Alanine dosimetry has become a routine transfer standard for national standards bodies such as NIST and NPL. In 1992 the Radiation Metrology Laboratory (RML) at Sandia National Laboratories implemented EPR/Alanine capabilities for use in routine and calibration activities at its Co-60 and pulsed-power facilities. At that time it also investigated the usefulness of the system for measurement of absorbed dose in the mixed neutron/photon environments of reactors such as the Sandia Pulsed Reactor and the Annular Core Research Reactor used for hardness testing of electronics. The RML concluded that the neutron response of alanine was a sufficiently high fraction of the overall dosimeter response that the resulting uncertainties in the photon dose would be unacceptably large for silicon-device testing. However, it also suggested that non-hydrogenous materials such as polytetrafluoroethylene (PTFE) would exhibit smaller neutron response and might be useful in mixed environments. Preliminary research with PTFE in photon environments indicated considerable promise, but further development was not pursued at that time. Because of renewed interest in absorbed dose measurements that could better define the individual contributions of photon and neutron components to the overall dose delivered to a test object, the RML has re-initiated the development of an EPR/PTFE dosimetry system. This effort consists of three stages: 1) Identification of PTFE materials that may be suitable for dosimetry applications. It was speculated that the inconsistency of EPR signatures in the earlier samples may have been due to variability in PTFE manufacturing processes. 2) Characterization of dosimetry in photon-only environments. This is necessary to establish requirements for sample preparation, operating parameters and limitations for use in well-defined and predictable environments prior to deployment in the less well-defined mixed environments of test reactors. 3) Characterization of the EPR responses obtained with PTFE in mixed neutron/photon fields. This includes evaluation of the neutron and photon contributions to response, determination of applicable of neutron fluence and photon dose ranges. This paper presents a summary of the research, a description of the EPR/PTFE dosimetry system, and recommendations for preparation and fielding of the dosimetry in photon and mixed neutron/photon environments. (authors)

Vehar, D.W.; Griffin, P.J.; Quirk, T.J. [Sandia National Laboratories, Albuquerque, NM 87185-1146 (United States)

2011-07-01T23:59:59.000Z

342

Laboratory directed research and development  

SciTech Connect (OSTI)

The purposes of Argonne's Laboratory Directed Research and Development (LDRD) Program are to encourage the development of novel concepts, enhance the Laboratory's R D capabilities, and further the development of its strategic initiatives. Among the aims of the projects supported by the Program are establishment of engineering proof-of-principle''; development of an instrumental prototype, method, or system; or discovery in fundamental science. Several of these project are closely associated with major strategic thrusts of the Laboratory as described in Argonne's Five Year Institutional Plan, although the scientific implications of the achieved results extend well beyond Laboratory plans and objectives. The projects supported by the Program are distributed across the major programmatic areas at Argonne. Areas of emphasis are (1) advanced accelerator and detector technology, (2) x-ray techniques in biological and physical sciences, (3) advanced reactor technology, (4) materials science, computational science, biological sciences and environmental sciences. Individual reports summarizing the purpose, approach, and results of projects are presented.

Not Available

1991-11-15T23:59:59.000Z

343

Laboratory Directors  

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

S. Hecker (1985-1997) Donald M. Kerr (1979-1985) Harold M. Agnew (1970-1979) Norris Bradbury (1945-1970) J. Robert Oppenheimer (1943-1945) Laboratory Directors Harold M. Agnew...

344

MICROSYSTEMS LABORATORIES  

E-Print Network [OSTI]

15 nm MICROSYSTEMS TECHNOLOGY LABORATORIES ANNUAL RESEARCH REPORT 2014 MASSACHUSETTS INSTITUTE OF TECHNOLOGY CAMBRIDGE, MA AUGUST 2014 #12;MTL Annual Research Report 2014 Director Jesús A. del Alamo Project........................................................................ 47 Energy: Photovoltaics, Energy Harvesting, Batteries, Fuel Cells

Culpepper, Martin L.

345

Nozzle for electric dispersion reactor  

DOE Patents [OSTI]

A nozzle for an electric dispersion reactor includes two concentric electrodes, the inner one of the two delivering disperse phase fluid into a continuous phase fluid. A potential difference generated by a voltage source creates a dispersing electric field at the end of the inner electrode.

Sisson, Warren G. (Oak Ridge, TN); Basaran, Osman A. (Oak Ridge, TN); Harris, Michael T. (Knoxville, TN)

1998-01-01T23:59:59.000Z

346

Nozzle for electric dispersion reactor  

DOE Patents [OSTI]

A nozzle for an electric dispersion reactor includes two concentric electrodes, the inner one of the two delivering disperse phase fluid into a continuous phase fluid. A potential difference generated by a voltage source creates a dispersing electric field at the end of the inner electrode. 4 figs.

Sisson, W.G.; Basaran, O.A.; Harris, M.T.

1998-04-14T23:59:59.000Z

347

Evaluation of Torsatrons as reactors  

SciTech Connect (OSTI)

Stellarators have significant operational advantages over tokamaks as ignited steady-state reactors. This scoping study, which uses an integrated cost-minimization code that incorporates costing and reactor component models self-consistently with a 1-D energy transport calculation, shows that a torsatron reactor could also be economically competitive with a tokamak reactor. The projected cost of electricity (COE) estimated using the Advanced Reactor Innovation and Evaluation Studies (ARIES) costing algorithms is 65.6 mill/kW(e)h in constant 1992 dollars for a reference 1-GW(e) Compact Torsatron reactor case. The COE is relatively insensitive (<10% variation) over a wide range of assumptions, including variations in the maximum field allowed on the coils, the coil elongation, the shape of the density profile, the beta limit, the confinement multiplier, and the presence of a large loss region for alpha particles. The largest variations in the COE occur for variations in the electrical power output demanded and the plasma-coil separation ratio.

Lyon, J.F. [Oak Ridge National Lab., TN (United States); Gulec, K. [Univ. of Tennessee, Knoxville, TN (United States); Miller, R.L. [Los Alamos National Lab., NM (United States); El-Guebaly, L. [Univ. of Wisconsin, Madison, WI (United States)

1994-03-01T23:59:59.000Z

348

Hybrid adsorptive membrane reactor  

DOE Patents [OSTI]

A hybrid adsorbent-membrane reactor in which the chemical reaction, membrane separation, and product adsorption are coupled. Also disclosed are a dual-reactor apparatus and a process using the reactor or the apparatus.

Tsotsis, Theodore T. (Huntington Beach, CA); Sahimi, Muhammad (Altadena, CA); Fayyaz-Najafi, Babak (Richmond, CA); Harale, Aadesh (Los Angeles, CA); Park, Byoung-Gi (Yeosu, KR); Liu, Paul K. T. (Lafayette Hill, PA)

2011-03-01T23:59:59.000Z

349

GEN-IV Reactors  

Science Journals Connector (OSTI)

Generation-IV reactors are a set of nuclear reactors currently being developed under international collaborations targeting ... economics, proliferation resistance, and physical protection of nuclear energy. Nuclear

Taek K. Kim

2013-01-01T23:59:59.000Z

350

The Netherlands Reactor Centre  

Science Journals Connector (OSTI)

... Two illustrated brochures in English have recently J. been issued by the Netherlands Reactor Centre ( ... Centre (Reactor Centrum Nederland). The first* gives a general survey of the ...

S. WEINTROUB

1964-04-04T23:59:59.000Z

351

Laminar Entrained Flow Reactor (Fact Sheet), National Bioenergy...  

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

Flow Reactor Investigating the core principles of in situ and ex situ catalytic fast pyrolysis of biomass NREL is a national laboratory of the U.S. Department of Energy,...

352

Using laboratory flow experiments and reactive chemical transport modeling for designing waterflooding of the Agua Fria Reservoir, Poza Rica-Altamira Field, Mexico  

E-Print Network [OSTI]

1. Williams, P. : Mexico, Oil and Gas Investor (July 2003)oil field, bordering the Gulf coast in the eastern part of Mexico,

Birkle, P.

2009-01-01T23:59:59.000Z

353

Possibility of using active secondary charge-exchange particle diagnostics for measuring the magnetic field direction in the plasma of a magnetic fusion reactor  

Science Journals Connector (OSTI)

An active particle diagnostic method based on the secondary charge exchange of hydrogen atoms of a probing (diagnostic) beam is proposed for local measurements of the magnetic field direction in the plasma of a t...

A. A. Medvedev; V. S. Strelkov

2006-05-01T23:59:59.000Z

354

Aerosol Laboratory - Nuclear Engineering Division (Argonne)  

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

Capabilities > Engineering Capabilities > Engineering Experimentation > Aerosol Laboratory Capabilities Engineering Experimentation Reactor Safety Experimentation Aerosol Experiments System Components Laser Applications Robots Applications Other Facilities Other Capabilities Work with Argonne Contact us For Employees Site Map Help Join us on Facebook Follow us on Twitter NE on Flickr Aerosol Laboratory The Aerosol Laboratory (AL) houses equipment to measure and record the physical parameters necessary to characterize the formation and transport of aerosols. Bookmark and Share The Aerosol Laboratory (AL) has extensive analytic and experimental capabilities to characterize the formation and transport of aerosols formed from the condensation of vapors. Computer codes have been developed to

355

Categorical Exclusion Determination Form Program or Field Office: Advanced Research Projects Agency -  

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

nergy nergy Categorical Exclusion Determination Form Program or Field Office: Advanced Research Projects Agency - Energy Project Title: (0471-1544) Sheetak Inc. - Thermoelectric Reactors for Efficient Automotive Thermal Storage Location: *- Multiple States - New York, Pennsylvania, Texas Proposed Action or Project Description: American Recovery and Reinvestment Act: D Funding will support development of a novel system of thermoelectric reactors for efficient automotive thermal energy storage (TREATS) in electric vehicle and plug-in hybrid electric vehicle Heating, Ventilation, and Cooling (HVAC) systems. Proposed work consists of indoor laboratory-based research and development, including (1) experimentation and analysis to assess the mechanics and dynamics of thermoelectric reactors, (2) design, fabrication, testing, and analysis of hot and cold reactors, (3) design, fabrication, testing, and

356

Federal Laboratory Consortium | The Ames Laboratory  

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

Federal Laboratory Consortium The Federal Laboratory Consortium for Technology Transfer (FLC) is the nationwide network of federal laboratories that provides the forum to develop...

357

CRAD, Conduct of Operations - Oak Ridge National Laboratory High Flux  

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

Reactor Contractor ORR Reactor Contractor ORR CRAD, Conduct of Operations - Oak Ridge National Laboratory High Flux Isotope Reactor Contractor ORR February 2007 A section of Appendix C to DOE G 226.1-2 "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of Criteria Review and Approach Documents (CRADs) used for a February, 2007 assessment of the Conduct of Operations Program portion of an Operational Readiness Review of the Oak Ridge National Laboratory, High Flux Isotope Reactor. CRADs provide a recommended approach and the types of information to gather to assess elements of a DOE contractor's programs. CRAD, Conduct of Operations - Oak Ridge National Laboratory High Flux Isotope Reactor Contractor ORR More Documents & Publications

358

Science @WIPP: Underground Laboratory  

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

WIPP WIPP Underground Laboratory Double Beta Decay Dark Matter Biology Repository Science Renewable Energy Underground Laboratory The deep geologic repository at WIPP provides an ideal environment for experiments in many scientific disciplines, including particle astrophysics, waste repository science, mining technology, low radiation dose physics, fissile materials accountability and transparency, and deep geophysics. The designation of the Carlsbad Department of Energy office as a "field" office has allowed WIPP to offer its mine operations infrastructure and space in the underground to researchers requiring a deep underground setting with dry conditions and very low levels of naturally occurring radioactive materials. Please contact Roger Nelson, chief scientist of the Department of

359

NREL Launches Collaborative Resource for Field Test Best Practices (Fact Sheet), NREL Highlights, Research & Development, NREL (National Renewable Energy Laboratory)  

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

Dynamic portal documents and shares state-of-the-art Dynamic portal documents and shares state-of-the-art residential field test tools and techniques. Field testing is a science and an art-a tricky process that develops through a lot of trial and error. Researchers in the Advanced Residential Buildings group at the National Renewable Energy Labora- tory (NREL) regularly conduct field experiments and long-term monitoring in occupied and unoc- cupied houses throughout the United States. The goal is to capture real-world performance of energy- efficient systems, in support of the U.S. Department of Energy's Build- ing America program. In addition to the technical challenges of making accurate field measurements, NREL researchers realized another problem: the vast body of field test know-how based on years of collective experience is currently scattered throughout the

360

Laboratory Access | Sample Preparation Laboratories  

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

Access Access Planning Ahead Planning Ahead Please complete the Beam Time Request (BTR) and Support Request forms thourgh the User Portal. Thorough chemical and sample information must be included in your BTR. Support Request forms include a list of collaborators that require laboratory access and your group's laboratory equipment requests. Researcher safety is taken seriously at SLAC. Please remember that radioactive materials, nanomaterials, and biohazardous materials have additional safety requirements. Refer to the SSRL or LCLS Safety Offices for further guidance. Upon Arrival Upon Arrival Once you arrive you must complete training and access forms before accessing the Sample Preparation Laboratories (SPL). All Sample Prep Lab doors are locked with access key codes. Once your SPL

Note: This page contains sample records for the topic "reactors laboratory field" 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

Evaluation of LLNL's Nuclear Accident Dosimeters at the CALIBAN Reactor September 2010  

SciTech Connect (OSTI)

The Lawrence Livermore National Laboratory uses neutron activation elements in a Panasonic TLD holder as a personnel nuclear accident dosimeter (PNAD). The LLNL PNAD has periodically been tested using a Cf-252 neutron source, however until 2009, it was more than 25 years since the PNAD has been tested against a source of neutrons that arise from a reactor generated neutron spectrum that simulates a criticality. In October 2009, LLNL participated in an intercomparison of nuclear accident dosimeters at the CEA Valduc Silene reactor (Hickman, et.al. 2010). In September 2010, LLNL participated in a second intercomparison of nuclear accident dosimeters at CEA Valduc. The reactor generated neutron irradiations for the 2010 exercise were performed at the Caliban reactor. The Caliban results are described in this report. The procedure for measuring the nuclear accident dosimeters in the event of an accident has a solid foundation based on many experimental results and comparisons. The entire process, from receiving the activated NADs to collecting and storing them after counting was executed successfully in a field based operation. Under normal conditions at LLNL, detectors are ready and available 24/7 to perform the necessary measurement of nuclear accident components. Likewise LLNL maintains processing laboratories that are separated from the areas where measurements occur, but contained within the same facility for easy movement from processing area to measurement area. In the event of a loss of LLNL permanent facilities, the Caliban and previous Silene exercises have demonstrated that LLNL can establish field operations that will very good nuclear accident dosimetry results. There are still several aspects of LLNL's nuclear accident dosimetry program that have not been tested or confirmed. For instance, LLNL's method for using of biological samples (blood and hair) has not been verified since the method was first developed in the 1980's. Because LLNL and the other DOE participants were limited in what they were allowed to do at the Caliban and Silene exercises and testing of various elements of the nuclear accident dosimetry programs cannot always be performed as guests at other sites, it has become evident that DOE needs its own capability to test nuclear accident dosimeters. Angular dependence determination and correction factors for NADs desperately need testing as well as more evaluation regarding the correct determination of gamma doses. It will be critical to properly design any testing facility so that the necessary experiments can be performed by DOE laboratories as well as guest laboratories. Alternate methods of dose assessment such as using various metals commonly found in pockets and clothing have yet to be evaluated. The DOE is planning to utilize the Godiva or Flattop reactor for testing nuclear accident dosimeters. LLNL has been assigned the primary operational authority for such testing. Proper testing of nuclear accident dosimeters will require highly specific characterization of the pulse fields. Just as important as the characterization of the pulsed fields will be the design of facilities used to process the NADs. Appropriate facilities will be needed to allow for early access to dosimeters to test and develop quick sorting techniques. These facilities will need appropriate laboratory preparation space and an area for measurements. Finally, such a facility will allow greater numbers of LLNL and DOE laboratory personnel to train on the processing and interpretation of nuclear accident dosimeters and results. Until this facility is fully operational for test purposes, DOE laboratories may need to continue periodic testing as guests of other reactor facilities such as Silene and Caliban.

Hickman, D P; Wysong, A R; Heinrichs, D P; Wong, C T; Merritt, M J; Topper, J D; Gressmann, F A; Madden, D J

2011-06-21T23:59:59.000Z

362

Sandia National Laboratories: Federal Laboratory Consortium Regional...  

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

& CapabilitiesCapabilitiesFederal Laboratory Consortium Regional Technology-Transfer Awards Salute Innovation, Commercialization at Sandia Federal Laboratory...

363

Field Laboratory in the Osage Reservation -- Determination of the Status of Oil and Gas Operations: Task 1. Development of Survey Procedures and Protocols  

SciTech Connect (OSTI)

Procedures and protocols were developed for the determination of the status of oil, gas, and other mineral operations on the Osage Mineral Reservation Estate. The strategy for surveying Osage County, Oklahoma, was developed and then tested in the field. Two Osage Tribal Council members and two Native American college students (who are members of the Osage Tribe) were trained in the field as a test of the procedures and protocols developed in Task 1. Active and inactive surface mining operations, industrial sites, and hydrocarbon-producing fields were located on maps of the county, which was divided into four more or less equal areas for future investigation. Field testing of the procedures, protocols, and training was successful. No significant damage was found at petroleum production operations in a relatively new production operation and in a mature waterflood operation.

Carroll, Herbert B.; Johnson, William I.

1999-04-27T23:59:59.000Z

364

Spatial distribution of eruptive centers about the Idaho National Laboratory  

E-Print Network [OSTI]

volcanic hazard assessment. The Idaho National Laboratory (INL) comprises several nuclear facilities, in- cluding the oldest power reactor in the world (see Chapman et al., Chapter 1, this volume). The INL of volcanism in the central ESRP at and near the INL is important due to the presence of nuclear reactors

Wetmore, Paul H.

365

ORGANISATIONAL CHART 2009 Laboratory: Research, Development and Services  

E-Print Network [OSTI]

LABORATORY C. Housiadas Dynamic Reliability of Complex System & Decision Analysis I.A. Papazoglou of the Centre REACTOR SAFETY COMMITTEE Chairman: I.A. Papazoglou ADMINISTRATIVE SUPPORT SECRETARIAT: I. Marketou. Kainourgiakis RADIATION PROTECTION & HEALTH PHYSICS OF THE REACTOR F. Tzika SUPPORT TO GAEC I. A. Papazoglou

366

Fusion Reactors as Future Energy Sources  

Science Journals Connector (OSTI)

...Other conceptual Tokamak reactors have been designed in the United States by grotups at the Princeton Plasma Physics Laboratory (PPPL) (2) and the University of Wisconsin (3). In these designs, in order to main-tain a low level of 4He in the plasma and...

R. F. Post; F. L. Ribe

1974-11-01T23:59:59.000Z

367

The CANDU Reactor System: An Appropriate Technology  

Science Journals Connector (OSTI)

...apparent. The devel-opment of Zircaloy-2 by the U.S. Bettis Laboratory in Pittsburgh, made this con-cept practicable...necessary to base a reactor de-sign on Zircaloy-2 had not Bettis work-ers been testing the material in NRX as part of a collaborative...

J. A. L. Robertson

1978-02-10T23:59:59.000Z

368

Nuclear reactor  

DOE Patents [OSTI]

A nuclear reactor comprising a cylindrical pressure vessel, an elongated annular core centrally disposed within and spaced from the pressure vessel, and a plurality of ducts disposed longitudinally of the pressure vessel about the periphery thereof, said core comprising an annular active portion, an annular reflector just inside the active portion, and an annular reflector just outside the active a portion, said annular active portion comprising rectangular slab, porous fuel elements radially disposed around the inner reflector and extending the length of the active portion, wedge-shaped, porous moderator elements disposed adjacent one face of each fuel element and extending the length of the fuel element, the fuel and moderator elements being oriented so that the fuel elements face each other and the moderator elements do likewise, adjacent moderator elements being spaced to provide air inlet channels, and adjacent fuel elements being spaced to provide air outlet channels which communicate with the interior of the peripheral ducts, and means for introducing air into the air inlet channels which passes through the porous moderator elements and porous fuel elements to the outlet channel.

Thomson, Wallace B. (Severna Park, MD)

2004-03-16T23:59:59.000Z

369

Advanced Computational Thermal Fluid Physics (CTFP) and Its Assessment for Light Water Reactors and Supercritical Reactors  

SciTech Connect (OSTI)

Background: The ultimate goal of the study is the improvement of predictive methods for safety analyses and design of Generation IV reactor systems such as supercritical water reactors (SCWR) for higher efficiency, improved performance and operation, design simplification, enhanced safety and reduced waste and cost. The objective of this Korean / US / laboratory / university collaboration of coupled fundamental computational and experimental studies is to develop the supporting knowledge needed for improved predictive techniques for use in the technology development of Generation IV reactor concepts and their passive safety systems. The present study emphasizes SCWR concepts in the Generation IV program.

D.M. McEligot; K. G. Condie; G. E. McCreery; H. M. McIlroy; R. J. Pink; L.E. Hochreiter; J.D. Jackson; R.H. Pletcher; B.L. Smith; P. Vukoslavcevic; J.M. Wallace; J.Y. Yoo; J.S. Lee; S.T. Ro; S.O. Park

2005-10-01T23:59:59.000Z

370

Development and validation of a real-time SAFT-UT (synthetic aperture focusing technique for ultrasonic testing) system for the inspection of light water reactor components: Annual report, October 1985-September 1986  

SciTech Connect (OSTI)

The Pacific Northwest Laboratory is working to design, fabricate, and evaluate a real-time flaw detection and characterization system based on the synthetic aperture focusing technique for ultrasonic testing (SAFT-UT). The system is designed to perform inservice inspection of light-water reactor components. Included objectives of this program for the Nuclear Regulatory Commission are to develop procedures for system calibration and field operation, to validate the system through laboratory and field inspections, and to generate an engineering data base to support ASME Code acceptance of the technology. This progress report covers the programmatic work from October 1985 through September 1986. 45 figs., 8 tabs.

Doctor, S.R.; Hall, T.E.; Reid, L.D.; Mart, G.A.

1987-07-01T23:59:59.000Z

371

SHARP: Reactor Performance and Safety Simulation Suite  

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

SHARP SHARP Argonne National Laboratory's Reactor Performance and Safety Simulation Suite SHARP could save millions in nuclear reactor design and development... The Simulation-based High-efficiency Advanced Reactor Prototyping (SHARP) suite of codes enables virtual design and engineering of nuclear plant behavior that would be impractical from a traditional experimental approach. ...by leveraging the computational power of one of the world's most powerful supercomputers. Exploiting the power of Argonne Leadership Computing Facility's near-petascale computers, researchers have developed a set of simulation tools that provide a highly detailed description of the reactor core and the nuclear plant behavior. This enables the efficient and precise design of tomorrow's safe and clean nuclear energy sources.

372

Reactor Safety Research: Semiannual report, January-June 1986: Reactor Safety Research Program  

SciTech Connect (OSTI)

Sandia National Laboratories is conducting, under USNRC sponsorship, phenomenological research related to the safety of commercial nuclear power reactors. The research includes experiments to simulate the phenomenology of accident conditions and the development of analytical models, verified by experiment, which can be used to predict reactor and safety systems performance behavior under abnormal conditions. The objective of this work is to provide NRC requisite data bases and analytical methods to (1) identify and define safety issues, (2) understand the progression of risk-significant accident sequences, and (3) conduct safety assessments. The collective NRC-sponsored effort at Sandia National Laboratories is directed at enhancing the technology base supporting licensing decisions.

Not Available

1987-05-01T23:59:59.000Z

373

National Laboratory  

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

Homesteading on the Pajarito Plateau Homesteading on the Pajarito Plateau topic of inaugural lecture at Los Alamos National Laboratory January 4, 2013 Lecture series begins yearlong commemoration of 70th anniversary LOS ALAMOS, NEW MEXICO, Jan. 3, 2013-In commemoration of its 70th anniversary, Los Alamos National Laboratory kicks off a yearlong lecture series on Wednesday, Jan. 9, at 5:30 p.m. with a presentation about homesteading on the Pajarito Plateau at the Bradbury Science Museum, 1350 Central Avenue, Los Alamos. - 2 - The inaugural lecture is based on a book by local writers Dorothy Hoard, Judy Machen and Ellen McGehee about the area's settlement between 1887 and 1942. On hikes across the Pajarito Plateau, Hoard envisioned the Los Alamos area before modern roads and bridges made transportation much easier. The trails she walked

374

SULI at Ames Laboratory  

SciTech Connect (OSTI)

A video snapshot of the Science Undergraduate Laboratory Internship (SULI) program at Ames Laboratory.

None

2011-01-01T23:59:59.000Z

375

CRAD, Occupational Safety & Health - Oak Ridge National Laboratory High  

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

Oak Ridge National Laboratory Oak Ridge National Laboratory High Flux Isotope Reactor Contractor ORR CRAD, Occupational Safety & Health - Oak Ridge National Laboratory High Flux Isotope Reactor Contractor ORR February 2007 A section of Appendix C to DOE G 226.1-2 "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of Criteria Review and Approach Documents (CRADs) used for a February 2007 assessment of the Occupational Safety and Health Program portion of an Operational Readiness Review of the Oak Ridge National Laboratory High Flux Isotope Reactor. CRADs provide a recommended approach and the types of information to gather to assess elements of a DOE contractor's programs. CRAD, Occupational Safety & Health - Oak Ridge National Laboratory High

376

Department of Energy Designates the Idaho National Laboratory Advanced Test  

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

Designates the Idaho National Laboratory Designates the Idaho National Laboratory Advanced Test Reactor as a National Scientific User Facility Department of Energy Designates the Idaho National Laboratory Advanced Test Reactor as a National Scientific User Facility April 23, 2007 - 12:36pm Addthis WASHINGTON, DC - The U.S. Department of Energy (DOE) today designated the Idaho National Laboratory's (INL) Advanced Test Reactor (ATR) as a National Scientific User Facility. Establishing the ATR as a National Scientific User Facility will help assert U.S. leadership in nuclear science and technology, and will attract new users - universities, laboratories and industry - to conduct research at the ATR. This facility will support basic and applied nuclear research and development (R&D), furthering

377

CRAD, Configuration Management - Oak Ridge National Laboratory High Flux  

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

Oak Ridge National Laboratory High Oak Ridge National Laboratory High Flux Isotope Reactor Contractor ORR CRAD, Configuration Management - Oak Ridge National Laboratory High Flux Isotope Reactor Contractor ORR February 2007, A section of Appendix C to DOE G 226.1-2 "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of Criteria Review and Approach Documents (CRADs) used for a February 2007 assessment of the Configuration Managment Program portion of an Operational Readiness Review of the Oak Ridge National Laboratory, High Flux Isotope Reactor. CRADs provide a recommended approach and the types of information to gather to assess elements of a DOE contractor's programs. CRAD, Configuration Management - Oak Ridge National Laboratory High Flux

378

CRAD, Fire Protection - Oak Ridge National Laboratory High Flux Isotope  

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

Fire Protection - Oak Ridge National Laboratory High Flux Fire Protection - Oak Ridge National Laboratory High Flux Isotope Reactor CRAD, Fire Protection - Oak Ridge National Laboratory High Flux Isotope Reactor February 2006 A section of Appendix C to DOE G 226.1-2 "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of Criteria Review and Approach Documents (CRADs) used for a February 2006 Commencement of Operations assessment of the Fire Protection program at the Idaho National Laboratory, Idaho Accelerated Retrieval Project Phase II. CRADs provide a recommended approach and the types of information to gather to assess elements of a DOE contractor's programs. CRAD, Fire Protection - Oak Ridge National Laboratory High Flux Isotope Reactor More Documents & Publications

379

CRAD, Occupational Safety & Health - Oak Ridge National Laboratory High  

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

Occupational Safety & Health - Oak Ridge National Laboratory Occupational Safety & Health - Oak Ridge National Laboratory High Flux Isotope Reactor CRAD, Occupational Safety & Health - Oak Ridge National Laboratory High Flux Isotope Reactor February 2007 A section of Appendix C to DOE G 226.1-2 "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of Criteria Review and Approach Documents (CRADs) used for a February 2007 assessment of the Industrial Safety and Hygiene Program in preparation for restart of the Oak Ridge National Laboratory High Flux Isotope Reactor. CRADs provide a recommended approach and the types of information to gather to assess elements of a DOE contractor's programs. CRAD, Occupational Safety & Health - Oak Ridge National Laboratory High

380

Final report. U.S. Department of Energy University Reactor Sharing Program  

SciTech Connect (OSTI)

Activities supported at the MIT Nuclear Reactor Laboratory under the U.S. DOE University Reactor Sharing Program are reported for Grant DE FG02-95NE38121 (September 16, 1995 through May 31, 2002). These activities fell under four subcategories: support for research at thesis and post-doctoral levels, support for college-level laboratory exercises, support for reactor tours/lectures on nuclear energy, and support for science fair participants.

Bernard, John A.

2003-01-21T23:59:59.000Z

Note: This page contains sample records for the topic "reactors laboratory field" 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

Argonne National Laboratory 9700 S. Cass Avenue  

E-Print Network [OSTI]

­ Sustainable Nuclear Energy for the 21st Century IAEA/Argonne Workshop on Developing the Safety Infrastructure for a Research Reactor in an Emerging Nuclear Power State (Argonne, IL : March 7-11, 2011) Meetings & CareersArgonne National Laboratory 9700 S. Cass Avenue Argonne, IL 60439 630.252.2525 International

Kemner, Ken

382

Princeton Plasma Physics Laboratory NSTX Experimental Proposal  

E-Print Network [OSTI]

Princeton Plasma Physics Laboratory NSTX Experimental Proposal Title: Dependence of ELM size Thermonuclear Experimental Reactor (ITER) have yielded a pedestal energy loss fraction between 5% and 20 with resonant magnetic perturbations2 or by access to small ELM regimes. Fig. 1 from reference1 , where

Princeton Plasma Physics Laboratory

383

Princeton Plasma Physics Laboratory NSTX Experimental Proposal  

E-Print Network [OSTI]

Princeton Plasma Physics Laboratory NSTX Experimental Proposal Title: Dependence of ELM size Projections1 of the energy loss from Type I ELMs for the International Thermonuclear Experimental Reactor perturbations2 or by access to small ELM regimes. Fig. 1 from reference1 , where extrapolation to ITER is done

Princeton Plasma Physics Laboratory

384

Savannah River Laboratory monthly report, February 1992  

SciTech Connect (OSTI)

This report is a progress report for the Savannah River Laboratory for the month of February 1992. The progress and activities in six categories were described in the report. The categories are reactor, tritium, separations, environmental, waste management, and general. Each category described numerous and varied activities. Some examples of these activities described are such things as radiation monitoring, maintenance, modifications, and remedial action.

Ferrell, J.M. (comp.); Ice, L.W. (ed.)

1992-02-01T23:59:59.000Z

385

LETTER REPORT INDEPENDENT VERIFICATION OF THE HIGH FLUX BEAM REACTOR DECOMMISSIONING PROJECT FAN HOUSE, BUILDING 704 BNL  

SciTech Connect (OSTI)

5098-LR-01-0 -LETTER REPORT INDEPENDENT VERIFICATION OF THE HIGH FLUX BEAM REACTOR DECOMMISSIONING PROJECT FAN HOUSE, BUILDING 704 BROOKHAVEN NATIONAL LABORATORY

P.C. Weaver

2010-10-22T23:59:59.000Z

386

Independent Activity Report, Sandia National Laboratories - March 2013 |  

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

March March 2013 Independent Activity Report, Sandia National Laboratories - March 2013 March 2013 Operational Awareness Oversight of Sandia National Laboratories [HIAR SNL-2013-03-18] The purpose of this Office of Health, Safety and Security (HSS) Independent Oversight activity was to perform an operational awareness site visit to Sandia National Laboratories (SNL) to discuss Annular Core Research Reactor (ACRR) issues and improvement plan. SNL management also briefed Independent Oversight on engineered safety implementation. Independent Activity Report, Sandia National Laboratories - March 2013 More Documents & Publications Independent Activity Report, Sandia National Laboratories - April 2012 Independent Oversight Targeted Review, Sandia National Laboratories -

387

Relap5-3d model validation and benchmark exercises for advanced gas cooled reactor application  

E-Print Network [OSTI]

HTTR High Temperature engineering Test Reactor INET Institute of Nuclear Energy Technology LWR Light Water Reactor OKBM Test Design Bureau for Machine Building ORNL Oak Ridge National Laboratory RCCS Reactor Cavity Cooling System... to be at right angles to each other, ignoring an angular distribution of radiant heat.7 MORECA, used by ORNL, simulates accident scenarios for certain gas-cooled reactor types.7 INET conducts their analysis using Thermix, which performs two...

Moore, Eugene James Thomas

2006-08-16T23:59:59.000Z

388

Robotics Laboratory - Nuclear Engineering Division (Argonne)  

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

Capabilities > Engineering Capabilities > Engineering Experimentation > Robotics Laboratory Capabilities Engineering Experimentation Reactor Safety Experimentation Aerosol Experiments System Components Laser Applications Robots Applications Other Facilities Other Capabilities Work with Argonne Contact us For Employees Site Map Help Join us on Facebook Follow us on Twitter NE on Flickr Robotics Laboratory The Robotics Laboratory (RL) houses various remote manipulator systems, including the Dual Arm Work Platform, to support enhancements to teleoperation of remote systems for nuclear applications. Bookmark and Share Argonne scientists are using computer simulation and robot task programming tools to enhance the safety and efficiency of telerobotics in applications such as the decontamination and decommissioning (D&D) of nuclear power

389

Toxicity and the fractional distribution of trace metals accumulated from contaminated sediments by the clam Scrobicularia plana exposed in the laboratory and the field  

Science Journals Connector (OSTI)

Abstract The relationship between the subcellular distribution of accumulated toxic metals into five operational fractions (subsequently combined into presumed detoxified and non-detoxified components) and toxicity in the clam Scrobicularia plana was investigated under different laboratory exposures. Clams were exposed to metal contaminated media (water and diet) and analysed for the partitioning of accumulated As, Cu and Zn into subcellular fractions. In general, metallothionein-like proteins, metal-rich granules and cellular debris in different proportions acted as main storage sites of accumulated metals in the clam soft tissues for these three metals. No significant differences were noted in the accumulation rates of As, Cu and Zn of groups of individuals with or without apparent signs of toxicity after up to 30days of exposure to naturally contaminated sediment mixtures. There was, however, an increased proportional accumulation of Cu in the non-detoxified fraction with increased Cu accumulation rate in the clams, suggesting that the Cu uptake rate from contaminated sediments exceeded the combined rates of elimination and detoxification of Cu, with the subsequent likelihood for toxic effects in the clams.

J. Kalman; E. Bonnail-Miguel; B.D. Smith; N.R. Bury; P.S. Rainbow

2015-01-01T23:59:59.000Z

390

Attrition reactor system  

DOE Patents [OSTI]

A reactor vessel for reacting a solid particulate with a liquid reactant has a centrifugal pump in circulatory flow communication with the reactor vessel for providing particulate attrition, resulting in additional fresh surface where the reaction can occur. 2 figures.

Scott, C.D.; Davison, B.H.

1993-09-28T23:59:59.000Z

391

Elementary Reactor Physics  

Science Journals Connector (OSTI)

... THERE are few subjects which have developed at the rate at which reactor physics and ... physics and reactor theory have done. This, of course, is largely due to the circumstances in ...

J. F. HILL

1962-02-10T23:59:59.000Z

392

Colliding Beam Fusion Reactors  

Science Journals Connector (OSTI)

The recirculating power for virtually all types of fusion reactors has previously been calculated [1] with the FokkerPlanck equation. The reactors involve non-Maxwellian plasmas. The calculations are ... the rec...

Norman Rostoker; Artan Qerushi; Michl Binderbauer

2003-06-01T23:59:59.000Z

393

STATEMENT OF CONSIDERATIONS Advance Test Reactor Class Waiver  

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

Advance Test Reactor Class Waiver Advance Test Reactor Class Waiver W(C)-2008-004 The Advanced Test Reactor (A TR) is a pressurized water test reactor at the Idaho National Laboratory (INL) that operates at low pressure and temperature. The ATR was originally designed to study the effects of intense radiation on reactor material and fuels . It has a "Four Leaf Clover" design that allows a diverse array of testing locations. The unique design allows for different flux in various locations and specialized systems also allow for certain experiments to be run at their own temperature and pressure. The U.S. Department of Energy (DOE) designated the Advanced Test Reactor (ATR) as a National Scientific User Facility (NSUF) in April 2007. This designation will allow the ATR to

394

High Flux Beam Reactor | Environmental Restoration Projects | BNL  

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

Why is the High Flux Beam Reactor Being Decommissioned? Why is the High Flux Beam Reactor Being Decommissioned? HFBR The High Flux Beam Reactor (HFBR) at Brookhaven National Laboratory (BNL) is being decommissioned because the Department of Energy (DOE) decided in 1999 that it would be permanently closed. The reactor was shut down in 1997 after tritium from a leak in the spent-fuel pool was found in the groundwater. The HFBR, which had operated from 1965 to 1996, was used solely for scientific research, providing neutrons for materials science, chemistry, biology, and physics experiments. The reactor was shut down for routine maintenance in November of 1996. In January 1997, tritium, a radioactive form of hydrogen and a by-product of reactor operations, was found in groundwater monitoring wells immediately south of the HFBR. The tritium

395

Probabilistic risk assessment of N Reactor using NUREG-1150 methods  

SciTech Connect (OSTI)

A Level III probabilistic risk assessment (PRA) has been performed for N Reactor, a US Department of Energy (DOE) Category A production reactor. The main contractor is Westinghouse Hanford Company (Westinghouse Hanford). The PRA methodology developed for the US Nuclear Regulatory Commission (NRC) by Sandia National Laboratories (SNL) in support of the NUREG-1150 (Reference 1) effort were used for this analysis. N Reactor is a graphite-moderated pressurized water reactor designed by General Electric. The dual-purpose 4000 MWt nuclear plant is located within the Hanford Site in the south-central part of the State of Washington. In addition to producing special materials for the DOE, N Reactor generates 860 MWe for the Washington Public Power Supply System. The reactor has been operated successfully and safely since 1963, and was put into standby status in 1988 due to the changing need in special nuclear material. 3 refs., 4 tabs.

Wang, O.S.; Baxter, J.T.; Coles, G.A.; Powers, T.B.; Zentner, M.D.

1989-11-01T23:59:59.000Z

396

Irradiated Fuels Examination Laboratory (IFEL) | ORNL  

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

Irradiated Fuels Examination Laboratory Irradiated Fuels Examination Laboratory May 30, 2013 The Irradiated Fuels Examination Laboratory (IFEL) was initially designed and constructed to permit the safe handling of increasing levels of radiation in the chemical, physical, and metallurgical examination of nuclear reactor fuel elements and reactor parts. The IFEL was constructed in 1963 and is a two-story brick building with a partial basement. The front or northern-most section is a single-story office area. The two story area to the immediate rear houses the cell complex, the operating areas, and other supporting activities. The office area is isolated from the main part of the building, so the office area can be excluded from the secondary containment zone. The facility has a gross floor area of about 27,000 ft2.

397

Laboratories, Oxide Molecular Beam Epitaxy Group, Condensed Matter Physics  

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

Laboratories: Photo Tour Laboratories: Photo Tour MBE Laboratory MBE Laboratory MBE Chamber MBE Chamber Temperature Controllers MBE Computers and Servers Pneumatic Hoses Transport between MBE Laboratory and Nano-Lithography Laboratory Backside of MBE chamber during growth, lit by Nano-Lithography Laboratory Nano-Lithography Laboratory Processing Chamber Laminar Flow Hood Mask Aligner Profilometer Probe Station Wire Bonder X-Ray Diffraction and Chemistry Laboratory X-Ray Diffraction System X-Ray Diffraction System X-Ray Diffraction System Chemistry Laboratory Chemistry Laboratory Mutual Inductance, Transport and Field Effect Laboratory Field Effect Measurement system Liquid Helium-4 Dipstick for Mutual Inductance Transport Measurement System COMBI Hall Effect, COMBI Transport and Mutual Inductance Measurements Laboratory

398

Prospects for spheromak fusion reactors  

Science Journals Connector (OSTI)

The reactor study of Hagenson and Krakowski demonstrated the attractiveness of the spheromak as a compact fusion reactor, based on...

T. K. Fowler; D. D. Hua

1995-06-01T23:59:59.000Z

399

Improved vortex reactor system  

DOE Patents [OSTI]

An improved vortex reactor system for affecting fast pyrolysis of biomass and Refuse Derived Fuel (RDF) feed materials comprising: a vortex reactor having its axis vertically disposed in relation to a jet of a horizontally disposed steam ejector that impels feed materials from a feeder and solids from a recycle loop along with a motive gas into a top part of said reactor.

Diebold, James P. (Lakewood, CO); Scahill, John W. (Evergreen, CO)

1995-01-01T23:59:59.000Z

400

Sandia National Laboratories: Advanced Materials Laboratory  

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

Advanced Materials Laboratory Sandia Researchers Win CSP:ELEMENTS Funding Award On June 4, 2014, in Advanced Materials Laboratory, Concentrating Solar Power, Energy, Energy...

Note: This page contains sample records for the topic "reactors laboratory field" 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

SAFT-UT field experience  

SciTech Connect (OSTI)

This paper reports on a three-year program at the Battelle Pacific Northwest Laboratory to transfer the synthetic aperture focusing technique (SAFT) technology that was developed at the University of Michigan into the field. A brief overview is given of the program and the field system is described. The main portion of the paper is devoted to the experience of using the SAFT system in a third-party role to aid in resolving inspection inconsistencies between several different UT inservice inspections results for intergranular stress corrosion cracks (IGSCC) in boiling water reactor (BWR) piping. A new method of scanning using a modified tandem technique (called TSAFT) was also developed and successfully employed in the field. The SAFT images made cracks easy to identify and the TSAFT data were easy to interpret for depth sizing. However, the most significant fact about the system is that it did work very well under field conditions even though a number of improvements were identified as a result of each field trip. These improvements are discussed in the paper. 6 refs., 15 figs.

Doctor, S.R.; Crawford, S.L.; Hall, T.E.

1985-03-01T23:59:59.000Z

402

Design options for a bunsen reactor.  

SciTech Connect (OSTI)

This work is being performed for Matt Channon Consulting as part of the Sandia National Laboratories New Mexico Small Business Assistance Program (NMSBA). Matt Channon Consulting has requested Sandia's assistance in the design of a chemical Bunsen reactor for the reaction of SO2, I2 and H2O to produce H2SO4 and HI with a SO2 feed rate to the reactor of 50 kg/hour. Based on this value, an assumed reactor efficiency of 33%, and kinetic data from the literature, a plug flow reactor approximately 1%E2%80%9D diameter and and 12 inches long would be needed to meet the specification of the project. Because the Bunsen reaction is exothermic, heat in the amount of approximately 128,000 kJ/hr would need to be removed using a cooling jacket placed around the tubular reactor. The available literature information on Bunsen reactor design and operation, certain support equipment needed for process operation and a design that meet the specification of Matt Channon Consulting are presented.

Moore, Robert Charles

2013-10-01T23:59:59.000Z

403

DOE - Office of Legacy Management -- Bettis Atomic Power Laboratories - PA  

Office of Legacy Management (LM)

Bettis Atomic Power Laboratories - Bettis Atomic Power Laboratories - PA 44 FUSRAP Considered Sites Site: Bettis Atomic Power Laboratories (PA.44 ) Eliminated from further consideration under FUSRAP Designated Name: Not Designated Alternate Name: None Location: Allegheny County , West Mifflin , Pennsylvania PA.44-1 Evaluation Year: Circa 1987 PA.44-2 Site Operations: Conducted activities directed toward the design, development, testing, and operational follow of nuclear reactor propulsion plants for Naval surface and submarine vessels. PA.44-1 Site Disposition: Eliminated - Active DOE facility PA.44-2 Radioactive Materials Handled: Yes Primary Radioactive Materials Handled: Radioactive Materials Associated with Reactor Operation PA.44-3 Radiological Survey(s): None Indicated

404

Thermal Scout Pinpoints Hard-to-Find Problems in CSP Fields (Fact Sheet), Highlights in Research & Development, NREL (National Renewable Energy Laboratory)  

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

receiver survey system uses an infrared camera, receiver survey system uses an infrared camera, GPS technology, and computer software to rapidly analyze concentrating solar power fields and locate defective receivers. In a parabolic trough concentrating solar power (CSP) system, collectors reflect the sun's rays onto long, tubular receivers that convert the sunlight into heat that is used to gener- ate electricity. The long-term performance of these receivers-designed to minimize heat loss to the environment while absorbing as much sunlight as possible-is critical for high efficiency and sustained performance. Traditionally, locating problems with receivers has been a costly, time-consuming, and labor- intensive effort, often requiring manual inspection of tens of thousands of receiver tubes. In most cases, operators must assess the entire output of a plant and roughly estimate the

405

SP - 19 Magnetic Field Safety  

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

19 Page 1 Revision 02 August 6, 2007 NATIONAL HIGH MAGNETIC FIELD LABORATORY NHMFL FLORIDA STATE UNIVERSITY SAFETY PROCEDURE SP-19 MAGNETIC FIELD SAFETY ...

406

The Argonaut Reactor - Reactors designed/built by Argonne National  

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

Achievements > Achievements > Argonne Reactors > Training 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

407

Reactor vessel support system  

DOE Patents [OSTI]

A reactor vessel support system includes a support ring at the reactor top supported through a box ring on a ledge of the reactor containment. The box ring includes an annular space in the center of its cross-section to reduce heat flow and is keyed to the support ledge to transmit seismic forces from the reactor vessel to the containment structure. A coolant channel is provided at the outside circumference of the support ring to supply coolant gas through the keyways to channels between the reactor vessel and support ledge into the containment space.

Golden, Martin P. (Trafford, PA); Holley, John C. (McKeesport, PA)

1982-01-01T23:59:59.000Z

408

Enforcement Documents - Idaho National Laboratory | Department of Energy  

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

Idaho National Laboratory Idaho National Laboratory Enforcement Documents - Idaho National Laboratory October 4, 2012 Preliminary Notice of Violation, Battelle Energy Alliance, LLC - NEA-2012-01 Issued to Battelle Energy Alliance, LLC related to an elevated extremity dose at the Hot Fuel Examination Facility and the plutonium contamination at the Zero Power Physics Reactor facility. January 13, 2012 Consent Order, Battelle Energy Alliance - NCO-2012-01 Issued to Battelle Energy Alliance, LLC, related to the Reactor Coolant Draining Event at the Idaho National Laboratory Advanced Test Reactor October 13, 2011 Consent Order, URS Energy & Construction, Inc. - NCO-2011-02 Issued to URS Energy & Construction, Inc., related to Quality Improvement and Work Control Program Deficiencies associated with Construction of the

409

Materials Degradation in Light Water Reactors: Life After 60 | Department  

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

Materials Degradation in Light Water Reactors: Life After 60 Materials Degradation in Light Water Reactors: Life After 60 Materials Degradation in Light Water Reactors: Life After 60 Nuclear reactors present a very harsh environment for components service. Components within a reactor core must tolerate high temperature water, stress, vibration, and an intense neutron field. Degradation of materials in this environment can lead to reduced performance, and in some cases, sudden failure. A recent EPRI-led study interviewed 47 US nuclear utility executives to gauge perspectives on long-term operation of nuclear reactors. Nearly 90% indicated that extensions of reactor lifetimes to beyond 60 years were likely. When polled on the most challenging issues facing further life extension, two-thirds cited plant reliability as the

410

Materials Degradation in Light Water Reactors: Life After 60 | Department  

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

Materials Degradation in Light Water Reactors: Life After 60 Materials Degradation in Light Water Reactors: Life After 60 Materials Degradation in Light Water Reactors: Life After 60 Nuclear reactors present a very harsh environment for components service. Components within a reactor core must tolerate high temperature water, stress, vibration, and an intense neutron field. Degradation of materials in this environment can lead to reduced performance, and in some cases, sudden failure. A recent EPRI-led study interviewed 47 US nuclear utility executives to gauge perspectives on long-term operation of nuclear reactors. Nearly 90% indicated that extensions of reactor lifetimes to beyond 60 years were likely. When polled on the most challenging issues facing further life extension, two-thirds cited plant reliability as the

411

Advanced Test Reactor National Scientific User Facility: Addressing advanced nuclear materials research  

SciTech Connect (OSTI)

The Advanced Test Reactor National Scientific User Facility (ATR NSUF), based at the Idaho National Laboratory in the United States, is supporting Department of Energy and industry research efforts to ensure the properties of materials in light water reactors are well understood. The ATR NSUF is providing this support through three main efforts: establishing unique infrastructure necessary to conduct research on highly radioactive materials, conducting research in conjunction with industry partners on life extension relevant topics, and providing training courses to encourage more U.S. researchers to understand and address LWR materials issues. In 2010 and 2011, several advanced instruments with capability focused on resolving nuclear material performance issues through analysis on the micro (10-6 m) to atomic (10-10 m) scales were installed primarily at the Center for Advanced Energy Studies (CAES) in Idaho Falls, Idaho. These instruments included a local electrode atom probe (LEAP), a field-emission gun scanning transmission electron microscope (FEG-STEM), a focused ion beam (FIB) system, a Raman spectrometer, and an nanoindentor/atomic force microscope. Ongoing capability enhancements intended to support industry efforts include completion of two shielded, irradiation assisted stress corrosion cracking (IASCC) test loops, the first of which will come online in early calendar year 2013, a pressurized and controlled chemistry water loop for the ATR center flux trap, and a dedicated facility intended to house post irradiation examination equipment. In addition to capability enhancements at the main site in Idaho, the ATR NSUF also welcomed two new partner facilities in 2011 and two new partner facilities in 2012; the Oak Ridge National Laboratory, High Flux Isotope Reactor (HFIR) and associated hot cells and the University California Berkeley capabilities in irradiated materials analysis were added in 2011. In 2012, Purdue Universitys Interaction of Materials with Particles and Components Testing (IMPACT) facility and the Pacific Northwest Nuclear Laboratory (PNNL) Radiochemistry Processing Laboratory (RPL) and PIE facilities were added. The ATR NSUF annually hosts a weeklong event called Users Week in which students and faculty from universities as well as other interested parties from regulatory agencies or industry convene in Idaho Falls, Idaho to see presentations from ATR NSUF staff as well as select researchers from the materials research field. Users week provides an overview of current materials research topics of interest and an opportunity for young researchers to understand the process of performing work through ATR NSUF. Additionally, to increase the number of researchers engaged in LWR materials issues, a series of workshops are in progress to introduce research staff to stress corrosion cracking, zirconium alloy degradation, and uranium dioxide degradation during in-reactor use.

John Jackson; Todd Allen; Frances Marshall; Jim Cole

2013-03-01T23:59:59.000Z

412

Reactor water cleanup system  

DOE Patents [OSTI]

A reactor water cleanup system includes a reactor pressure vessel containing a reactor core submerged in reactor water. First and second parallel cleanup trains are provided for extracting portions of the reactor water from the pressure vessel, cleaning the extracted water, and returning the cleaned water to the pressure vessel. Each of the cleanup trains includes a heat exchanger for cooling the reactor water, and a cleaner for cleaning the cooled reactor water. A return line is disposed between the cleaner and the pressure vessel for channeling the cleaned water thereto in a first mode of operation. A portion of the cooled water is bypassed around the cleaner during a second mode of operation and returned through the pressure vessel for shutdown cooling.

Gluntz, Douglas M. (San Jose, CA); Taft, William E. (Los Gatos, CA)

1994-01-01T23:59:59.000Z

413

Reactor water cleanup system  

DOE Patents [OSTI]

A reactor water cleanup system includes a reactor pressure vessel containing a reactor core submerged in reactor water. First and second parallel cleanup trains are provided for extracting portions of the reactor water from the pressure vessel, cleaning the extracted water, and returning the cleaned water to the pressure vessel. Each of the cleanup trains includes a heat exchanger for cooling the reactor water, and a cleaner for cleaning the cooled reactor water. A return line is disposed between the cleaner and the pressure vessel for channeling the cleaned water thereto in a first mode of operation. A portion of the cooled water is bypassed around the cleaner during a second mode of operation and returned through the pressure vessel for shutdown cooling. 1 figure.

Gluntz, D.M.; Taft, W.E.

1994-12-20T23:59:59.000Z

414

Lawrence Livermore National Laboratory  

Broader source: Energy.gov [DOE]

Lawrence Livermore National Laboratorys (LLNL) primary mission is research and development in support of national security.

415

Sandia National Laboratories: photovoltaic  

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

PV Facilities On November 10, 2010, in Photovoltaic System Evaluation Laboratory Distributed Energy Technologies Laboratory Microsystems and Engineering Sciences Applications...

416

Facilities | Argonne National Laboratory  

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

Engineering Research Facility Distributed Energy Research Center Engine Research Facility Heat Transfer Laboratory Tribology Laboratory Transportation Beamline at the Advanced...

417

DOE Designated User Facilities Multiple Laboratories * ARM Climate Research Facility  

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

Designated User Facilities Designated User Facilities Multiple Laboratories * ARM Climate Research Facility Argonne National Laboratory * Advanced Photon Source (APS) * Electron Microscopy Center for Materials Research * Argonne Tandem Linac Accelerator System (ATLAS) * Center for Nanoscale Materials (CNM) * Argonne Leadership Computing Facility (ALCF) * Brookhaven National Laboratory * National Synchrotron Light Source (NSLS) * Accelerator Test Facility (ATF) * Relativistic Heavy Ion Collider (RHIC) * Center for Functional Nanomaterials (CFN) * National Synchrotron Light Source II (NSLS-II ) (under construction) Fermi National Accelerator Laboratory * Fermilab Accelerator Complex Idaho National Laboratory * Advanced Test Reactor ** * Wireless National User Facility (WNUF)

418

Alkali deposits found in biomass boilers: The behavior of inorganic material in biomass-fired power boilers -- Field and laboratory experiences. Volume 2  

SciTech Connect (OSTI)

This report documents the major findings of the Alkali Deposits Investigation, a collaborative effort to understand the causes of unmanageable ash deposits in biomass-fired electric power boilers. Volume 1 of this report provide an overview of the project, with selected highlights. This volume provides more detail and discussion of the data and implications. This document includes six sections. The first, the introduction, provides the motivation, context, and focus for the investigation. The remaining sections discuss fuel properties, bench-scale combustion tests, a framework for considering ash deposition processes, pilot-scale tests of biomass fuels, and field tests in commercially operating biomass power generation stations. Detailed chemical analyses of eleven biomass fuels representing a broad cross-section of commercially available fuels reveal their properties that relate to ash deposition tendencies. The fuels fall into three broad categories: (1) straws and grasses (herbaceous materials); (2) pits, shells, hulls and other agricultural byproducts of a generally ligneous nature; and (3) woods and waste fuels of commercial interest. This report presents a systematic and reasonably detailed analysis of fuel property, operating condition, and boiler design issues that dictate ash deposit formation and property development. The span of investigations from bench-top experiments to commercial operation and observations including both practical illustrations and theoretical background provide a self-consistent and reasonably robust basis to understand the qualitative nature of ash deposit formation in biomass boilers. While there remain many quantitative details to be pursued, this project encapsulates essentially all of the conceptual aspects of the issue. It provides a basis for understanding and potentially resolving the technical and environmental issues associated with ash deposition during biomass combustion. 81 refs., 124 figs., 76 tabs.

Baxter, L.L. [Sandia National Labs., Livermore, CA (United States). Combustion Research Facility; Miles, T.R.; Miles, T.R. Jr. [Miles (Thomas R.), Portland, OR (United States); Jenkins, B.M. [California Univ., Davis, CA (United States); Dayton, D.C.; Milne, T.A. [National Renewable Energy Lab., Golden, CO (United States); Bryers, R.W. [Foster Wheeler Development Corp., Livingston, NJ (United States); Oden, L.L. [Bureau of Mines, Albany, OR (United States). Albany Research Center

1996-03-01T23:59:59.000Z

419

Categorical Exclusion Determinations: National Energy Technology Laboratory  

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

National Energy Technology National Energy Technology Laboratory Categorical Exclusion Determinations: National Energy Technology Laboratory Categorical Exclusion Determinations issued by National Energy Technology Laboratory. DOCUMENTS AVAILABLE FOR DOWNLOAD September 25, 2013 CX-010917: Categorical Exclusion Determination Fate of Methane Emitted from Dissociating Marine Hydrates: Modeling, Laboratory, and Field Constraints CX(s) Applied: A1, A9, B3.6 Date: 09/25/2013 Location(s): Massachusetts Offices(s): National Energy Technology Laboratory September 25, 2013 CX-010916: Categorical Exclusion Determination Fate of Methane Emitted from Dissociating Marine Hydrates: Modeling, Laboratory, and Field Constraints CX(s) Applied: A1, A9, B3.6 Date: 09/25/2013 Location(s): Massachusetts Offices(s): National Energy Technology Laboratory

420

2012_AdvReactor_Factsheet.indd  

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

nuclear.gov nuclear.gov February 15, 2011 A ADVANCED REACTOR CONCEPTS DVANCED REACTOR CONCEPTS The U.S. Department of Energy's Offi ce of Nuclear Energy T he Advanced Reactor Concepts (ARC) program, an expanded version of the Generation IV research, development and demonstration (RD&D) program, sponsors research, development and deployment activities leading to further safety, technical, economical, and environmental advancements of innovative nuclear energy technologies. The Office of Nuclear Energy (NE) will pursue these advancements through RD&D activities at the Department of Energy (DOE) national laboratories and U.S. universities, as well as through collaboration with nuclear industry and international partners. These activities will focus on advancing

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421

Gas Reactor Technology R&D  

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

U.S. Department of Energy to Invest U.S. Department of Energy to Invest up to $7.3 Million for "Deep-Burn" Gas-Reactor Technology R&D Artist's rendering of Nuclear Plant An artist's rendering of the Next Generation Nuclear Plant concept. The U.S. Department of Energy today announced a Funding Opportunity Announcement (FOA) valued at $7.3 million for universities, commercial entities, National Laboratories with expertise in the concept of nuclear fuel "Deep-Burn" in which plutonium and higher transuranics recycled from spent nuclear fuel are destroyed. The funding opportunity seeks to establish the technological foundations that will support the role of the very-high-temperature, gas-cooled reactor (VHTR) in the nuclear fuel cycle -- which is one of the prototype reactors being researched/developed under

422

Measurement of advective soil gas flux: Results of field and...  

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

Measurement of advective soil gas flux: Results of field and laboratory experiments with CO2. Measurement of advective soil gas flux: Results of field and laboratory experiments...

423

Reactor prospect of spheromak concept by electrostatic helicity injection  

Science Journals Connector (OSTI)

The highest performing spheromaks in the laboratory are formed by electrostatic helicity injection. Discharges with up to 1 MA plasma current and core electron temperature as high as 500 eV have been recently obtained. For such a scheme to scale-up to a reactor however a much higher current multiplication factor (plasma current over injector current) must be achieved. It is shown here that spheromak current multiplication is linearly proportional to flux amplification (ratio of poloidal fluxes inside and outside the separatrix of the mean field). Hence spheromak optimization is centered around achieving high flux amplification which is provided by linear or nonlinear resonant coupling between helicity injector and the spheromak force-free eigenmode. The nonlinear resonant field amplification is the most promising route to high flux amplification in a realistic plasma that often significantly deviates from the Taylor state. Accessing such nonlinear resonant field amplification can be facilitated by auxiliary current drive around the magnetic axis and auxiliary heating to break the electron temperature constraint on flux amplification.

X. Z. Tang; A. H. Boozer

2008-01-01T23:59:59.000Z

424

Multi-physics Reactor Performance and Safety Simulations - Argonne National  

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

Engineering Computation Engineering Computation and Design > Multi-physics Reactor Performance and Safety Simulations Capabilities Engineering Computation and Design Engineering and Structural Mechanics Systems/Component Design, Engineering and Drafting Heat Transfer and Fluid Mechanics Multi-physics Reactor Performance and Safety Simulations Other Capabilities Work with Argonne Contact us For Employees Site Map Help Join us on Facebook Follow us on Twitter NE on Flickr Multi-physics Reactor Performance and Safety Simulations Bookmark and Share Contact Keith S. Bradley, Ph.D. Technical Director, Nuclear Engineering Division Argonne National Laboratory Email address protected by JavaScript. Please enable JavaScript The SHARP simulation suite development team, led by Argonne National Laboratory, includes other leading national laboratories and research universities. SHARP is developed under the auspices of the U.S. Department of Energy, Office of Nuclear Energy, Nuclear Energy Advanced Modeling and Simulation Program (NEAMS).

425

Energy Secretary to Visit Georgia Nuclear Reactor Site and Tennessee  

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

Secretary to Visit Georgia Nuclear Reactor Site and Secretary to Visit Georgia Nuclear Reactor Site and Tennessee Laboratory to Highlight Administration Support for Nuclear Energy Energy Secretary to Visit Georgia Nuclear Reactor Site and Tennessee Laboratory to Highlight Administration Support for Nuclear Energy February 13, 2012 - 6:16pm Addthis WASHINGTON, D.C. - U.S. Secretary of Energy Secretary Steven Chu will visit the Vogtle nuclear power plant in Waynesboro, Georgia, and Oak Ridge National Laboratory on Wednesday, February 15 to highlight steps the Obama Administration is taking to restart America's nuclear energy industry. In Waynesboro, Secretary Chu will join Southern Company CEO Thomas A. Fanning, Georgia Power CEO W. Paul Bowers, and local leaders for a tour of Vogtle units 3 and 4 -- the site of the first two new nuclear power units

426

Independent Oversight Targeted Review, Sandia National Laboratories -  

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

Targeted Review, Sandia National Laboratories Targeted Review, Sandia National Laboratories - November 2013 Independent Oversight Targeted Review, Sandia National Laboratories - November 2013 December 2013 Targeted Review of Activity-Level Implementation of Radiological Controls at Sandia National Laboratories This report documents the results of an independent oversight targeted review of radiological protection program activity-level implementation for Sandia National Laboratories (SNL), Technical Area V facilities. SNL is managed by Sandia Corporation, a wholly owned subsidiary of Lockheed Martin Corporation, under contract to the Department of Energy (DOE) and is overseen by the National Nuclear Security Administration and its Sandia Field Office. This targeted review was performed at SNL September 23-27,

427

Power Reactor Progress  

Science Journals Connector (OSTI)

Argonne kicks off EBWR; Allis-Chalmers plans power reactor using both nuclear and conventional fuels ... NUCLEAR POWER took two giant steps last week. ... Just as the first nuclear power system in the U. S. designed and built solely for the generation of electric power went into full operation at Argonne, Allis-Chalmers came up with a new twist in power reactorsa controlled recirculation boiling reactor (CRBR) using both nuclear and conventional fuels (C&EN, Feb. 18, page 7). ...

1957-02-25T23:59:59.000Z

428

Improved vortex reactor system  

DOE Patents [OSTI]

An improved vortex reactor system is described for affecting fast pyrolysis of biomass and Refuse Derived Fuel (RDF) feed materials comprising: a vortex reactor having its axis vertically disposed in relation to a jet of a horizontally disposed steam ejector that impels feed materials from a feeder and solids from a recycle loop along with a motive gas into a top part of said reactor. 12 figs.

Diebold, J.P.; Scahill, J.W.

1995-05-09T23:59:59.000Z

429

Reliability Engineering Approach to Probabilistic Proliferation Resistance Analysis of the Example Sodium Fast Reactor Fuel Cycle Facility  

E-Print Network [OSTI]

-cooled fast reactor and pyroprocessing facility were designed by Argonne National Laboratory (ANL) for the purpose of facilitating discussion on the subject of fast reactor and pyroprocessing safeguards in the absence of a safeguards confidential design... proliferators due to the presence of bulk nuclear material and the ability to acquire plutonium in a form easier to convert to a weapon. The ESFR design includes four 800 MWth (300 MWe) reactors (Argonne National Laboratory 2006) and an on...

Cronholm, Lillian Marie

2012-10-19T23:59:59.000Z

430

SUPPLEMENT ANALYSIS OF FOREIGN RESEARCH REACTOR srENT NUCLEAR FUEL  

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

FOREIGN RESEARCH REACTOR srENT NUCLEAR FUEL FOREIGN RESEARCH REACTOR srENT NUCLEAR FUEL TRANSPORTATION ALONG OTHER THAN~. PRESENTATIVE ROUTE FROM CONCORD NAVAL WEAPO~~ STATION TO IDAHO NATIONAL ENGINEERING AND ENVIRONMENTAL LADORA TORY Introduction The Department of Energy is planning to transport foreign research reactor spent nuclear fuel by rail from the Concord Naval Weapons Station (CNWS), Concord, California, to the Idaho National Engineering and Environmental Laboratory (INEEL). The environmental analysis supporting the decision to transport, by rail or truck, foreign research reactor spent nuclear fuel from CNWS to the INEEL is contained in +he Final Environmental Impact Statement on a Proposed Nuclear Weapons Nonproliftration Policy Concerning Foreign Research Reactor

431

Action Memorandum for the Engineering Test Reactor under the Idaho Cleanup Project  

SciTech Connect (OSTI)

This Action Memorandum documents the selected alternative for decommissioning of the Engineering Test Reactor at the Idaho National Laboratory under the Idaho Cleanup Project. Since the missions of the Engineering Test Reactor Complex have been completed, an engineering evaluation/cost analysis that evaluated alternatives to accomplish the decommissioning of the Engineering Test Reactor Complex was prepared adn released for public comment. The scope of this Action Memorandum is to encompass the final end state of the Complex and disposal of the Engineering Test Reactor vessol. The selected removal action includes removing and disposing of the vessel at the Idaho CERCLA Disposal Facility and demolishing the reactor building to ground surface.

A. B. Culp

2007-01-26T23:59:59.000Z

432

AEC Pushes Fusion Reactors  

Science Journals Connector (OSTI)

AEC Pushes Fusion Reactors ... Project Sherwood, as the study program is called, began in 1951-52 soon after the first successful thermonuclear explosion in the Pacific. ...

1955-10-10T23:59:59.000Z

433

Tokamak reactor first wall  

DOE Patents [OSTI]

This invention relates to an improved first wall construction for a tokamak fusion reactor vessel, or other vessels subjected to similar pressure and thermal stresses.

Creedon, R.L.; Levine, H.E.; Wong, C.; Battaglia, J.

1984-11-20T23:59:59.000Z

434

Advanced Nuclear Research Reactor  

SciTech Connect (OSTI)

This report describes technical modifications implemented by INVAP to improve the safety of the Research Reactors the company designs and builds.

Lolich, J.V.

2004-10-06T23:59:59.000Z

435

LABORATORY VI ELECTRICITY FROM MAGNETISM  

E-Print Network [OSTI]

LABORATORY VI ELECTRICITY FROM MAGNETISM Lab VI - 1 In the previous problems you explored by electric currents. This lab will carry that investigation one step further, determining how changing magnetic fields can give rise to electric currents. This is the effect that allows the generation

Minnesota, University of

436

LABORATORY VI ELECTRICITY FROM MAGNETISM  

E-Print Network [OSTI]

LABORATORY VI ELECTRICITY FROM MAGNETISM Lab VI - 1 In the previous problems you explored the magnetic field and its effect on moving charges. You also saw how electric currents could create magnetic can give rise to electric currents. This is the effect that allows the generation of electricity

Minnesota, University of

437

Strengthening the nuclear-reactor fuel cycle against proliferation  

SciTech Connect (OSTI)

Argonne National Laboratory (ANL) conducts several research programs that serve to reduce the risks of fissile-material diversion from the nuclear-reactor fuel cycle. The objectives are to provide economical and efficient neutron or power generation with the minimum of inherent risks, and to further minimize risks by utilizing sophisticated techniques to detect attempts at material diversion. This paper will discuss the Reduced Enrichment Research and Test Reactor (RERTR) Program, the Isotope Correlation Technique (ICT), and Proliferation-Resistant Closed-Cycle Reactors. The first two are sponsored by the DOE Office of Arms Control and Nonproliferation.

Travelli, A.; Snelgrove, J.; Persiani, P. [Argonne National Lab., IL (United States). Arms Control and Nonproliferation Program

1992-12-31T23:59:59.000Z

438

Ames Laboratory Logos | The Ames Laboratory  

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

Ames Laboratory Logos The Ames Laboratory Logo comes in several formats. EPS files are vector graphics created in Adobe Illustrator and saved with a tiff preview so they will...

439

Idaho National Engineering Laboratory waste area groups 1--7 and 10 Technology Logic Diagram. Volume 1  

SciTech Connect (OSTI)

The Technology Logic Diagram was developed to provide technical alternatives for environmental restoration projects at the Idaho National Engineering Laboratory. The diagram (three volumes) documents suggested solutions to the characterization, retrieval, and treatment phases of cleanup activities at contaminated sites within 8 of the laboratory`s 10 waste area groups. Contaminated sites at the laboratory`s Naval Reactor Facility and Argonne National Laboratory-West are not included in this diagram.

O`Brien, M.C.; Meservey, R.H.; Little, M.; Ferguson, J.S.; Gilmore, M.C.

1993-09-01T23:59:59.000Z

440

Modifications to the NRAD Reactor, 1977 to present  

SciTech Connect (OSTI)

Argonne National Laboratory-West, operated by the University of Chicago, is located near Idaho Falls, ID, on the Idaho National Engineering laboratory Site. ANL-West performs work in support of the Liquid Metal Fast Breeder Reactor Program (LMFBR) sponsored by the United States Department of Energy. The NRAD reactor is located at the Argonne Site within the Hot Fuel Examination Facility/North, a large hot cell facility where both non-destructive and destructive examinations are performed on highly irradiated reactor fuels and materials in support of the LMFBR program. The NRAD facility utilizes a 250-kW TRIGA reactor and is completely dedicated to neutron radiography and the development of radiography techniques. Criticality was first achieved at the NRAD reactor in October of 1977. Since that time, a number of modifications have been implemented to improve operational efficiency and radiography production. This paper describes the modifications and changes that significantly improved operational efficiency and reliability of the reactor and the essential auxiliary reactor systems.

Weeks, A.A.; Pruett, D.P.; Heidel, C.C.

1986-01-01T23:59:59.000Z

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


441

Micro -Thermonuclear AB-Reactors for Aerospace  

E-Print Network [OSTI]

The author offers several innovations that he first suggested publicly early in 1983 for the AB multi-reflex engine, space propulsion, getting energy from plasma, etc. (see: A. Bolonkin, Non-Rocket Space Launch and Flight, Elsevier, London, 2006, Chapters 12, 3A). It is the micro-thermonuclear AB-Reactors. That is new micro-thermonuclear reactor with very small fuel pellet that uses plasma confinement generated by multi-reflection of laser beam or its own magnetic field. The Lawson criterion increases by hundreds of times. The author also suggests a new method of heating the power-making fuel pellet by outer electric current as well as new direct method of transformation of ion kinetic energy into harvestable electricity. These offered innovations dramatically decrease the size, weight and cost of thermonuclear reactor, installation, propulsion system and electric generator. Non-industrial countries can produce these researches and constructions. Currently, the author is researching the efficiency of these innovations for two types of the micro-thermonuclear reactors: multi-reflection reactor (ICF) and self-magnetic reactor (MCF).

Alexander Bolonkin

2007-01-08T23:59:59.000Z

442

Portfolio for fast reactor collaboration  

SciTech Connect (OSTI)

The development of the LMFBR type reactor in the United Kingdom is reviewed. Design characteristics of a commercial demonstration fast reactor are presented and compared with the Super Phenix reactor.

Rippon, S.

1981-12-01T23:59:59.000Z

443

STRESS WAVE EMISSION AND FRACTURE OF PRESTRESSED CONCRETE REACTOR...  

Office of Scientific and Technical Information (OSTI)

PRESTRESSED CONCRETE REACTOR VESSEL MATERIALS. Re-direct Destination: Temp Data Fields Green, A.T. Temp Data Storage 3: Aerojet-General Corp., Sacramento, Calif. Short URL for...

444

Advanced Test Reactor National Scientific User Facility Partnerships  

SciTech Connect (OSTI)

In 2007, the United States Department of Energy designated the Advanced Test Reactor (ATR), located at Idaho National Laboratory, as a National Scientific User Facility (NSUF). This designation made test space within the ATR and post-irradiation examination (PIE) equipment at INL available for use by researchers via a proposal and peer review process. The goal of the ATR NSUF is to provide researchers with the best ideas access to the most advanced test capability, regardless of the proposer's physical location. Since 2007, the ATR NSUF has expanded its available reactor test space, and obtained access to additional PIE equipment. Recognizing that INL may not have all the desired PIE equipment, or that some equipment may become oversubscribed, the ATR NSUF established a Partnership Program. This program enables and facilitates user access to several university and national laboratories. So far, seven universities and one national laboratory have been added to the ATR NSUF with capability that includes reactor-testing space, PIE equipment, and ion beam irradiation facilities. With the addition of these universities, irradiation can occur in multiple reactors and post-irradiation exams can be performed at multiple universities. In each case, the choice of facilities is based on the user's technical needs. Universities and laboratories included in the ATR NSUF partnership program are as follows: (1) Nuclear Services Laboratories at North Carolina State University; (2) PULSTAR Reactor Facility at North Carolina State University; (3) Michigan Ion Beam Laboratory (1.7 MV Tandetron accelerator) at the University of Michigan; (4) Irradiated Materials at the University of Michigan; (5) Harry Reid Center Radiochemistry Laboratories at University of Nevada, Las Vegas; (6) Characterization Laboratory for Irradiated Materials at the University of Wisconsin-Madison; (7) Tandem Accelerator Ion Beam. (1.7 MV terminal voltage tandem ion accelerator) at the University of Wisconsin-Madison; (8) Illinois Institute of Technology (IIT) Materials Research Collaborative Access Team (MRCAT) beamline at Argonne National Laboratory's Advanced Photon Source; and (9) Nanoindenter in the University of California at Berkeley (UCB) Nuclear Engineering laboratory Materials have been analyzed for ATR NSUF users at the Advanced Photon Source at the MRCAT beam, the NIST Center for Neutron Research in Gaithersburg, MD, the Los Alamos Neutron Science Center, and the SHaRE user facility at Oak Ridge National Laboratory (ORNL). Additionally, ORNL has been accepted as a partner facility to enable ATR NSUF users to access the facilities at the High Flux Isotope Reactor and related facilities.

Frances M. Marshall; Todd R. Allen; Jeff B. Benson; James I. Cole; Mary Catherine Thelen

2012-03-01T23:59:59.000Z

445

National High Magnetic Field Laboratory - Superconducting Magnet...  

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

Interface SCM2 Straight Probe Drawing (PDF) Other Cryostats, Dewars, Probes and Sample Holders General Purpose 3He and 4He Systems 3He System B Portable Dilution Refrigerator SCM1...

446

National High Magnetic Field Laboratory: Geochemistry Publications  

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

Marcus, M.A.; Stroud, R.M. and Tamura, N., Simeio: An Ultra Ni-Poor Metal Particle From Comet 81pWild2, Meteoritics & Planetary Science, 47, A408 (2012) 16 Zhang, C.; Wang, Y.;...

447

National High Magnetic Field Laboratory - Applied Superconductivity...  

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

viable present materials for superconducting application to electric power transmission lines, fault current limiters, transformers, electromagnets and motors. UW-Madison has...

448

National High Magnetic Field Laboratory - Applied Superconductivity...  

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

viable present materials for superconducting application to electric power transmission lines, fault current limiters, transformers, electromagnets and motors. Coated Conductors We...

449

National High Magnetic Field Laboratory - Mission  

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

research to serve an interdisciplinary scientific user community spanning materials science, condensed matter physics, magnet technology, chemistry, and biology. Provide...

450

National High Magnetic Field Laboratory - Basic Science  

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

fruits of Faraday's discovery of electromagnetic induction. A more recent example is magnetic resonance imaging (MRI), which originated in basic research that started in the...

451

National High Magnetic Field Laboratory - Science Council  

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

Organization Arrow Science Council The Science Council was established in 2005 to help set and guide the lab's scientific agenda. Populated by a group of distinguished research...

452

National High Magnetic Field Laboratory - Scientist Profiles...  

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

in studying a range of inorganic oxide materials and in particular electrolytes for solid oxide fuel cell (SOFC) applications in order to understand both the anionic mobility and...

453

National High Magnetic Field Laboratory - Recent Publications...  

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

13 (2014) 33 Dobrosavljevic, V., Shock waves and commutation speed of memristors, Physics Seminar at the MIT Creative Research Center, ETRI, Daejeon, South Korea, Aug. 13 (2014) 34...

454

National High Magnetic Field Laboratory - Travel Information...  

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

or (850) 984-0180. Shell Point Lovely, small peninsula surrounded by St. Marks National Wildlife Refuge. Secluded beach and clear water. Popular for sailing and wind surfing....

455

National High Magnetic Field Laboratory - Scientist Profiles...  

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

"Spatially resolved electronic structure inside and outside the vortex cores of a high-temperature superconductor", Nature 413, 501-504 (2001). 30. V. F. Mitrovi, E. E....

456

National High Magnetic Field Laboratory - Optical Microscopy...  

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

and Kinetic Evaluations, Inorg. Chem., 20 (52), 5838-5850 (2013) read online 16 Stricker, J.; Beckham, Y.; Davidson, M.W. and Gardel, M.L., Myosin II-Mediated Focal Adhesion...

457

National High Magnetic Field Laboratory - Online Tour  

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

Audio Slideshows Arrow Online Tour Welcome to the Mag Lab's online tour. As we show you around the Florida State University branch of the world's biggest magnet lab, our scientists...

458

Solar Thermal Reactor Materials Characterization  

SciTech Connect (OSTI)

Current research into hydrogen production through high temperature metal oxide water splitting cycles has created a need for robust high temperature materials. Such cycles are further enhanced by the use of concentrated solar energy as a power source. However, samples subjected to concentrated solar radiation exhibited lifetimes much shorter than expected. Characterization of the power and flux distributions representative of the High Flux Solar Furnace(HFSF) at the National Renewable Energy Laboratory(NREL) were compared to ray trace modeling of the facility. In addition, samples of candidate reactor materials were thermally cycled at the HFSF and tensile failure testing was performed to quantify material degradation. Thermal cycling tests have been completed on super alloy Haynes 214 samples and results indicate that maximum temperature plays a significant role in reduction of strength. The number of cycles was too small to establish long term failure trends for this material due to the high ductility of the material.

Lichty, P. R.; Scott, A. M.; Perkins, C. M.; Bingham, C.; Weimer, A. W.

2008-03-01T23:59:59.000Z

459

Fast reactor safety  

Science Journals Connector (OSTI)

... SIR, - In his article on fast reactor safety (26 July, page 270) Norman Dombey claims to introduce to non-specialists ... , page 270) Norman Dombey claims to introduce to non-specialists some features of fast reactors that are not available outside the technical literature. The non-specialist would do well ...

R.D. SMITH

1979-08-23T23:59:59.000Z

460

Instrumentation of Nuclear Reactors  

Science Journals Connector (OSTI)

... s Lecture Theatre on January 8, a symposium of papers on the instrumentation of nuclear reactors was organized, at which about five hundred members and visitors attended, including guests from ... the Institution, took the chair and introduced Sir John Cockcroft, whose lecture on "Nuclear Reactors and their Applications" provided a general background for the three specialized papers which followed. ...

1953-03-07T23:59:59.000Z

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


461

Nuclear Research Reactors  

Science Journals Connector (OSTI)

... their countries for the advent of nuclear power. A few countries had built large research reactors for the production of isotopes and to study the behaviour of nuclear fuel, but ... production of isotopes and to study the behaviour of nuclear fuel, but the small training reactor had not been developed. Since then, research ...

T. E. ALLIBONE

1963-07-20T23:59:59.000Z

462

Laboratory Equipment & Supplies | Sample Preparation Laboratories  

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

Equipment & Supplies Equipment & Supplies John Bargar, SSRL Scientist Equipment is available to serve disciplines from biology to material science. All laboratories contain the following standard laboratory equipment: pH meters with standard buffers, analytical balances, microcentrifuges, vortex mixers, ultrasonic cleaning baths, magnetic stirrers, hot plates, and glassware. Most laboratories offer ice machines and cold rooms. Specialty storage areas for samples include a -80 freezer, argon and nitrogen glove boxes, radiation contamination areas, inert atmosphere chambers, and cold rooms. For specific information please see: Equipment Inventory Checkout Equipment & Supplies To view equipment inventory by laboratory, refer to the following pages: Biology Chemistry & Material Science Laboratory 1 Inventory

463

The physics of magnetic fusion reactors  

Science Journals Connector (OSTI)

During the past two decades there have been substantial advances in magnetic fusion research. On the experimental front, progress has been led by the mainline tokamaks, which have achieved reactor-level values of temperature and plasma pressure. Comparable progress, when allowance is made for their smaller programs, has been made in complementary configurations such as the stellarator, reversed-field pinch and field-reversed configuration. In this paper, the status of understanding of the physics of toroidal plasmas is reviewed. It is shown how the physics performance, constrained by technological and economic realities, determines the form of reference toroidal reactors. A comparative study of example reactors is not made, because the level of confidence in projections of their performance varies widely, reflecting the vastly different levels of support which each has received. Success with the tokamak has led to the initiation of the International Thermonuclear Experimental Reactor project. It is designed to produce 1500 MW of fusion power from a deuterium-tritium plasma for pulses of 1000 s or longer and to demonstrate the integration of the plasma and nuclear technologies needed for a demonstration reactor.

John Sheffield

1994-07-01T23:59:59.000Z

464

CASL milestone validates reactor model using TVA data | ornl.gov  

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

Ron Walli Ron Walli Communications 865.576.0226 CASL milestone validates reactor model using TVA data This CASL visualization shows the thermal distribution of neutrons in Watts Bar Unit 1 Cycle 1 reactor core at initial criticality, as calculated by the VERA program. Image courtesy of Oak Ridge National Laboratory. This CASL visualization shows the thermal distribution of neutrons in Watts Bar Unit 1 Cycle 1 reactor core at initial criticality, as calculated by the VERA program. Image courtesy of Oak Ridge National Laboratory. (hi-res image) OAK RIDGE, Tenn., July 10, 2013 -Today, the Consortium for Advanced Simulation of Light Water Reactors announced that its scientists have successfully completed their first full-scale simulation of an operating nuclear reactor. CASL is modeling nuclear reactors on supercomputers to

465

An improved weighted average reactor temperature estimation for simulation of adiabatic industrial hydrotreaters  

Science Journals Connector (OSTI)

A study on the improvement of the representative operating temperature from the temperature profile of an industrial adiabatic reactor is presented. This temperature is used to simulate the reactor performance by small scale laboratory isothermal reactors. An improved methodology for the estimation of a Weighted Average Bed Temperature (WABT) was elaborated to simulate an industrial multi-bed HDS reactor. The improved WABT, so called Weighted Average Reactor Temperature (WART), was compared with the most usually used WABT in a wide range of operational conditions as well as of kinetic parameters. In case of a multi-bed industrial hydrotreater, where quench zones are located between the beds and the H2 flow rate, which enters each bed, is different, the optimal gas to oil ratio was estimated for the laboratory-scale reactor.

G.D. Stefanidis; G.D. Bellos; N.G. Papayannakos

2005-01-01T23:59:59.000Z

466

Canadian university research reactors  

SciTech Connect (OSTI)

In Canada there are seven university research reactors: one medium-power (2-MW) swimming pool reactor at McMaster University and six low-power (20-kW) SLOWPOKE reactors at Dalhousie University, Ecole Polytechnique, the Royal Military College, the University of Toronto, the University of Saskatchewan, and the University of Alberta. This paper describes primarily the McMaster Nuclear Reactor (MNR), which operates on a wider scale than the SLOWPOKE reactors. The MNR has over a hundred user groups and is a very broad-based tool. The main applications are in the following areas: (1) neutron activation analysis (NAA); (2) isotope production; (3) neutron beam research; (4) nuclear engineering; (5) neutron radiography; and (6) nuclear physics.

Ernst, P.C.; Collins, M.F.

1989-11-01T23:59:59.000Z

467

Reactor & Nuclear Systems Publications | ORNL  

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

Nuclear Science Home | Science & Discovery | Nuclear Science | Publications and Reports | Reactor and Nuclear Systems Publications SHARE Reactor and Nuclear Systems Publications...

468

Climate Change Science Institute at Oak Ridge National Laboratory  

E-Print Network [OSTI]

Climate Change Science Institute at Oak Ridge National Laboratory A multidisciplinary research fields. The Climate Change Science Institute at Oak Ridge National Laboratory routinely partners simulations to improve regional modeling of climate extremes - Partners from Oak Ridge, Lawrence Berkeley

469

News | Argonne National Laboratory  

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

News Argonne Laboratory Director Peter Littlewood (left) talks with a small business owner during the second annual "Doing Business with Argonne and Fermi National Laboratories"...

470

jevans | The Ames Laboratory  

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

jevans Ames Laboratory Profile James Evans Associate 315 Wilhelm Phone Number: 515-294-1638 Email Address: evans@ameslab.gov Ames Laboratory Associate and Professor, Iowa State...

471

Sustainability | The Ames Laboratory  

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

Sustainability Ames Laboratory is committed to environmental sustainability in all of its operations as outlined in the Laboratory's Site Sustainability Plan. Executive orders set...

472

Laboratories and Facilities | Department of Energy  

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

Laboratories and Facilities Laboratories and Facilities Laboratories and Facilities Laboratories and Facilities National Energy Technology Laboratory - The National Energy Technology Laboratory (NETL) is the lead field center for the Office of Fossil Energy's research and development program. Scientists at its Pittsburgh, PA, and Morgantown, WV, campuses conduct onsite research while contract administrators oversee nearly 700 federally-sponsored projects conducted by private sector research partners. The Houston, TX, office is part of the Laboratory's Strategic Center for Natural Gas and Oil. NETL's Arctic Energy Office in Anchorage, AK, facilitates energy research related to fossil energy resources and remote electrical power generation to address the State of Alaska's unique energy needs. Researchers at NETL-Albany, in

473

Independent Activity Report, Sandia National Laboratories - September 2012  

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

September 2012 Independent Activity Report, Sandia National Laboratories - September 2012 September 2012 Operational Awareness Oversight of Sandia National Laboratories [HIAR SNL-2012-09-13] The purpose of this Office of Health, Safety and Security (HSS) activity was to perform an operational awareness site visit to the Sandia Site Office (SSO) and Sandia National Laboratories (SNL) operated by Sandia Corporation, a wholly owned subsidiary of Lockheed Martin Corporation, primarily to discuss the Annular Core Research Reactor Facility (ACRRF) improvement plan developed by SNL in response to recent safety basis and software quality assurance concerns raised by the Defense Nuclear Facilities Safety Board (DNFSB). Independent Activity Report, Sandia National Laboratories - September 2012

474

AERONAUTICS The Guggenheim Aeronautical Laboratory, the Krmn  

E-Print Network [OSTI]

. Physics of Fluids. Fluid dynamics as a discipline is as much a part of physics as of engineering. PhysicsAERONAUTICS The Guggenheim Aeronautical Laboratory, the Kármán Laboratory of Fluid Mechanics the broad field known as aeronautics and space engineering. Areas of Research Aeronautics has evolved

Greer, Julia R.

475

ASSOCIATED LABORATORY PLASMA PHYSICS AND ENGINEERING  

E-Print Network [OSTI]

Units of excellence in Europe, in the fields of Nuclear Fusion, Plasma Physics and Technologies in the frame of the so-called Broader Approach to Fusion Energy; · Collaboration on Nuclear Fusion the present apparatus and Laboratories: Tokamak ISTTOK, Multi-TeraWatt Laser System, Laboratory of Microwave

Lisboa, Universidade Técnica de

476

Design Windows for a He Cooled Fusion Reactor* Dai-Kai Sze and Ahmed Hassanein  

E-Print Network [OSTI]

Design Windows for a He Cooled Fusion Reactor* Dai-Kai Sze and Ahmed Hassanein Argonne National Laboratory 9700 South Cass Avenue, Argonne, IL 60439 EQUATIONDERIVATION ABSTRACT A design window concept is developed for a He-cooled fusion reactor blanket and divertor design. This concept allows study

Harilal, S. S.

477

Parallel Reacting Flow Calculations for Chemical Vapor Deposition Reactor Design 1  

E-Print Network [OSTI]

National Laboratories Albuquerque, NM 87185­1111 (To be published in Proceedings of the International at the synthesis of two important research areas: 3D flow and transport modeling of reactors and the simulationParallel Reacting Flow Calculations for Chemical Vapor Deposition Reactor Design 1 Andrew G

Devine, Karen

478

Computational Analysis and Optimization of a Chemical Vapor Deposition Reactor with  

E-Print Network [OSTI]

Computational Analysis and Optimization of a Chemical Vapor Deposition Reactor with Large and optimization of a three- dimensional model of a horizontal chemical vapor deposition (CVD) reactor used National Laboratories February 9, 2004 Abstract A computational analysis and optimization is presented

479

Nuclear reactor control column  

DOE Patents [OSTI]

The nuclear reactor control column comprises a column disposed within the nuclear reactor core having a variable cross-section hollow channel and containing balls whose vertical location is determined by the flow of the reactor coolant through the column. The control column is divided into three basic sections wherein each of the sections has a different cross-sectional area. The uppermost section of the control column has the greatest cross-sectional area, the intermediate section of the control column has the smallest cross-sectional area, and the lowermost section of the control column has the intermediate cross-sectional area. In this manner, the area of the uppermost section can be established such that when the reactor coolant is flowing under normal conditions therethrough, the absorber balls will be lifted and suspended in a fluidized bed manner in the upper section. However, when the reactor coolant flow falls below a predetermined value, the absorber balls will fall through the intermediate section and into the lowermost section, thereby reducing the reactivity of the reactor core and shutting down the reactor.

Bachovchin, Dennis M. (Plum Borough, PA)

1982-01-01T23:59:59.000Z

480

ACTIVITIES AND FUTURE PLANS AT LNF INFN, Laboratori Nazionali di Frascati, C.P. 13, 00044 Frascati (Roma), Italy  

E-Print Network [OSTI]

at another important National Laboratory of INFN, the underground facility at Gran Sasso. In the field

Istituto Nazionale di Fisica Nucleare (INFN)

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


481

Nuclear reactor reflector  

DOE Patents [OSTI]

A nuclear reactor reflector is disclosed that comprises a stack of reflector blocks with vertical water flow passages to cool the reflector. The interface between blocks is opposite support points for reactor fuel rods. Water flows between the reflector and the reactor barrel from passages in a bottom block. The top block contains a flange to limit this flow and the flange has a slot to receive an alignment pin that is welded to the barrel. The pin is held in the slot by two removable shims. Alignment bars extend the length of the stack in slots machined in each block when the stack is assembled.

Hopkins, Ronald J. (Pensacola, FL); Land, John T. (Pensacola, FL); Misvel, Michael C. (Pensacola, FL)

1994-01-01T23:59:59.000Z

482

Commercial Fisheries Biological Laboratory  

E-Print Network [OSTI]

scientists; a substation with a laboratory on Chincoteague Bay; and a sampling substation at Point Pleasant

483

Argonne National Laboratory | Argonne National Laboratory  

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

Argonne National Laboratory Fighting friction Graphene offers dramatic improvement over conventional mechanical lubricants Read More Forecasting supply Researchers use real-world...

484

Sandia National Laboratories: Advanced Materials Laboratory  

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

Funding Award On June 4, 2014, in Advanced Materials Laboratory, Concentrating Solar Power, Energy, Energy Storage, Facilities, National Solar Thermal Test Facility,...

485

Heat Transfer Laboratory | Argonne National Laboratory  

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

Heat Transfer Laboratory Materials in solids or fluid forms play an important role in a wide range of mechanical systems and vehicle cooling applications. Understanding how...

486

Sandia National Laboratories: National Renewable Energy Laboratory  

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

Systems Evaluation Laboratory (PSEL), Renewable Energy, Solar, Solar Newsletter, SunShot, Systems Analysis The solar industry is now more than 60% of the way toward achieving...

487

Sandia National Laboratories: Idaho National Laboratory  

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

Idaho National Laboratory Biofuels Blend Right In: Researchers Show Ionic Liquids Effective for Pretreating Mixed Blends of Biofuel Feedstocks On February 26, 2013, in Biofuels,...

488

Development of advanced strain diagnostic techniques for reactor environments.  

SciTech Connect (OSTI)

The following research is operated as a Laboratory Directed Research and Development (LDRD) initiative at Sandia National Laboratories. The long-term goals of the program include sophisticated diagnostics of advanced fuels testing for nuclear reactors for the Department of Energy (DOE) Gen IV program, with the future capability to provide real-time measurement of strain in fuel rod cladding during operation in situ at any research or power reactor in the United States. By quantifying the stress and strain in fuel rods, it is possible to significantly improve fuel rod design, and consequently, to improve the performance and lifetime of the cladding. During the past year of this program, two sets of experiments were performed: small-scale tests to ensure reliability of the gages, and reactor pulse experiments involving the most viable samples in the Annulated Core Research Reactor (ACRR), located onsite at Sandia. Strain measurement techniques that can provide useful data in the extreme environment of a nuclear reactor core are needed to characterize nuclear fuel rods. This report documents the progression of solutions to this issue that were explored for feasibility in FY12 at Sandia National Laboratories, Albuquerque, NM.

Fleming, Darryn D.; Holschuh, Thomas Vernon,; Miller, Timothy J.; Hall, Aaron Christopher; Urrea, David Anthony,; Parma, Edward J.,

2013-02-01T23:59:59.000Z

489

Secretary Moniz Visits Oak Ridge National Laboratory | Department of Energy  

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

Visits Oak Ridge National Laboratory Visits Oak Ridge National Laboratory Secretary Moniz Visits Oak Ridge National Laboratory June 5, 2013 - 3:18pm Addthis Energy Secretary Moniz at CASL 1 of 25 Energy Secretary Moniz at CASL Secretary Moniz tours the Consortium for Advanced Simulation of Light Water Reactors (CASL) facility at Oak Ridge National Laboratory (ORNL). CASL is one of the Energy Department's Energy Innovation Hubs. Date taken: 2013-06-03 12:04 Energy Secretary Moniz at CASL 2 of 25 Energy Secretary Moniz at CASL (From left, foreground) Deputy Secretary of Energy Daniel Poneman, Secretary of Energy Ernest Moniz and Rep. Chuck Fleischmann tour the CASL facility at ORNL. ORNL researcher Andrew Godfrey explains a reactor simulation in a CASL visualization lab. Date taken: 2013-06-03 12:04

490

SLIDESHOW: Secretary Moniz Visits Oak Ridge National Laboratory |  

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

Secretary Moniz Visits Oak Ridge National Laboratory Secretary Moniz Visits Oak Ridge National Laboratory SLIDESHOW: Secretary Moniz Visits Oak Ridge National Laboratory Addthis Energy Secretary Moniz at CASL 1 of 25 Energy Secretary Moniz at CASL Secretary Moniz tours the Consortium for Advanced Simulation of Light Water Reactors (CASL) facility at Oak Ridge National Laboratory (ORNL). CASL is one of the Energy Department's Energy Innovation Hubs. Date taken: 2013-06-03 12:04 Energy Secretary Moniz at CASL 2 of 25 Energy Secretary Moniz at CASL (From left, foreground) Deputy Secretary of Energy Daniel Poneman, Secretary of Energy Ernest Moniz and Rep. Chuck Fleischmann tour the CASL facility at ORNL. ORNL researcher Andrew Godfrey explains a reactor simulation in a CASL visualization lab. Date taken: 2013-06-03 12:04

491

Reactor Safety Research Programs Quarterly Report October - December 1981  

SciTech Connect (OSTI)

This document summarizes the work performed by Pacific Northwest laboratory (PNL) from October 1 through December 31, 1981, for the Division of Accident Evaluation, U.S. Nuclear Regulatory Commission (NRC). Evaluations of nondestructive examination (NDE) techniques and instrumentation are reported; areas of investigation include demonstrating the feasibility of determining the strength of structural graphite, evaluating the feasibility of detecting and analyzing flaw growth in reactor pressure boundary systems, examining NDE reliability and probabilistic fracture mechanics, and assessing the integrity of pressurized water reactor (PWR) steam generator tubes where serviceinduced degradation has been indicated. Experimental data and analytical models are being provided to aid in decision-making regarding pipe-to-pipe impacts following postulated breaks in high-energy fluid system piping. Core thermal models are being developed to provide better digital codes to compute the behavior of full-scale reactor systems under postulated accident conditions. Fuel assemblies and analytical support are being provided for experimental programs at other facilities. These programs include loss-of-coolant accident (LOCA) simulation tests at the NRU reactor, Chalk River, Canada; fuel rod deformation, severe fuel damage, and post accident coolability tests for the ESSOR reactor Super Sara Test Program, lspra, Italy; the instrumented fuel assembly irradiation program at Halden, Norway; and experimental programs at the Power Burst Facility, Idaho National Engineering Laboratory (INEL), Idaho Falls, Idaho. These programs will provide data for computer modeling of reactor system and fuel performance during various abnormal operating conditions.

Edler, S. K.

1982-03-01T23:59:59.000Z

492

Hybrid Plasma Reactor/Filter for Transportable Collective Protection Systems  

SciTech Connect (OSTI)

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

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

2011-04-06T23:59:59.000Z

493

Sandia National Laboratories: Research: Facilities: Technology Deployment  

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

Engineering Sciences Experimental Facilities (ESEF) Engineering Sciences Experimental Facilities (ESEF) Technology Deployment Centers Advanced Power Sources Laboratory Engineering Sciences Experimental Facilities (ESEF) Trisonic Wind Tunnel Hypersonic Wind Tunnel High Altitude Chamber Explosive Components Facility Ion Beam Laboratory Materials Science and Engineering Center Pulsed Power and Systems Validation Facility Radiation Detection Materials Characterization Laboratory Shock Thermodynamic Applied Research Facility (STAR) Weapon and Force Protection Center Design, Evaluation and Test Technology Facility Research Engineering Sciences Experimental Facilities (ESEF) The ESEF complex contains several independent laboratories for experiments and advanced diagnostics in the fields of thermodynamics, heat transfer,

494

Effect of neutral gas heating on the wave magnetic fields of a low pressure 13.56?MHz planar coil inductively coupled argon discharge  

SciTech Connect (OSTI)

The axial and radial magnetic field profiles in a 13.56?MHz (radio frequency) laboratory 6 turn planar coil inductively coupled plasma reactor are simulated with the consideration of the effect of neutral gas heating. Spatially resolved electron densities, electron temperatures, and neutral gas temperatures were obtained for simulation using empirically fitted electron density and electron temperature and heuristically determined neutral gas temperature. Comparison between simulated results and measured fields indicates that neutral gas heating plays an important role in determining the skin depth of the magnetic fields.

Jayapalan, Kanesh K., E-mail: kane-karnage@yahoo.com; Chin, Oi-Hoong, E-mail: ohchin@um.edu.my [Plasma Technology Research Centre, Department of Physics, University of Malaya, 50603 Kuala Lumpur (Malaysia)] [Plasma Technology Research Centre, Department of Physics, University of Malaya, 50603 Kuala Lumpur (Malaysia)

2014-04-15T23:59:59.000Z

495

Talk explores Laboratory's 50 years of space research  

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

Talk explores Laboratory's 50 years of space research Talk explores Laboratory's 50 years of space research Talk explores Laboratory's 50 years of space research The talk, titled "Los Alamos National Laboratory's 50 Years in Space," will highlight the Laboratory's significant discoveries and events in the field. October 3, 2013 Laboratory fellow and astrophysicist Ed Fenimore, and Laboratory planetary scientist and principal investigator of the ChemCam team Roger Wiens, will talk about Los Alamos National Laboratory's 50 years of space research and exploration. Laboratory fellow and astrophysicist Ed Fenimore, and Laboratory planetary scientist and principal investigator of the ChemCam team Roger Wiens, will talk about Los Alamos National Laboratory's 50 years of space research and exploration.

496

Radiation effects on reactor pressure vessel supports  

SciTech Connect (OSTI)

The purpose of this report is to present the findings from the work done in accordance with the Task Action Plan developed to resolve the Nuclear Regulatory Commission (NRC) Generic Safety Issue No. 15, (GSI-15). GSI-15 was established to evaluate the potential for low-temperature, low-flux-level neutron irradiation to embrittle reactor pressure vessel (RPV) supports to the point of compromising plant safety. An evaluation of surveillance samples from the High Flux Isotope Reactor (HFIR) at the Oak Ridge National Laboratory (ORNL) had suggested that some materials used for RPV supports in pressurized-water reactors could exhibit higher than expected embrittlement rates. However, further tests designed to evaluate the applicability of the HFIR data to reactor RPV supports under operating conditions led to the conclusion that RPV supports could be evaluated using traditional method. It was found that the unique HFIR radiation environment allowed the gamma radiation to contribute significantly to the embrittlement. The shielding provided by the thick steel RPV shell ensures that degradation of RPV supports from gamma irradiation is improbable or minimal. The findings reported herein were used, in part, as the basis for technical resolution of the issue.

Johnson, R.E. [Nuclear Regulatory Commission, Washington, DC (United States). Div. of Engineering Technology; Lipinski, R.E. [Idaho National Engineering Lab., Rockville, MD (United States)

1996-05-01T23:59:59.000Z

497

Reactor hot spot analysis  

SciTech Connect (OSTI)

The principle methods for performing reactor hot spot analysis are reviewed and examined for potential use in the Applied Physics Division. The semistatistical horizontal method is recommended for future work and is now available as an option in the SE2-ANL core thermal hydraulic code. The semistatistical horizontal method is applied to a small LMR to illustrate the calculation of cladding midwall and fuel centerline hot spot temperatures. The example includes a listing of uncertainties, estimates for their magnitudes, computation of hot spot subfactor values and calculation of two sigma temperatures. A review of the uncertainties that affect liquid metal fast reactors is also presented. It was found that hot spot subfactor magnitudes are strongly dependent on the reactor design and therefore reactor specific details must be carefully studied. 13 refs., 1 fig., 5 tabs.

Vilim, R.B.

1985-08-01T23:59:59.000Z

498

Neutron capture therapy at the MEPhI reactor  

Science Journals Connector (OSTI)

The article discusses the results of the creation and development of the irradiation base for Neutron Capture Therapy (NCT) at the MEPhI Reactor, development and studies of boron- and gadolinium-containing compounds, and presents the results of pre-clinical NCT studies in large laboratory animals ?? dogs with spontaneous melanoma.

K.N. Zaitsev; A.A. Portnov; O.V. Mishcherina; V.N. Kulakov; V.F. Khokhlov; I.N. Sheino; V.V. Meshcherikova; V.N. Mitin; N.G. Kozlovskaya; I.A. Shikunova

2004-01-01T23:59:59.000Z

499

Molten metal reactors  

DOE Patents [OSTI]

A molten metal reactor for converting a carbon material and steam into a gas comprising hydrogen, carbon monoxide, and carbon dioxide is disclosed. The reactor includes an interior crucible having a portion contained within an exterior crucible. The interior crucible includes an inlet and an outlet; the outlet leads to the exterior crucible and may comprise a diffuser. The exterior crucible may contain a molten alkaline metal compound. Contained between the exterior crucible and the interior crucible is at least one baffle.

Bingham, Dennis N; Klingler, Kerry M; Turner, Terry D; Wilding, Bruce M

2013-11-05T23:59:59.000Z

500

Fabrication and Characterization of Uranium-based High Temperature Reactor  

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

Fabrication and Characterization of Uranium-based High Temperature Reactor Fabrication and Characterization of Uranium-based High Temperature Reactor Fuel June 01, 2013 The Uranium Fuel Development Laboratory is a modern R&D scale lab for the fabrication and characterization of uranium-based high temperature reactor fuel. A laboratory-scale coater manufactures tri-isotropic (TRISO) coated fuel particles (CFPs), state-of-the-art materials property characterization is performed, and the CFPs are then pressed into fuel compacts for irradiation testing, all under a NQA-1 compliant Quality Assurance Program. After fuel kernel size and shape are measured by optical shadow imaging, the TRISO coatings are deposited via fluidized bed chemical vapor deposition in a 50-mm diameter conical chamber within the coating furnace. Computer control of temperature and gas composition ensures reproducibility