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1

Vestibule and Cask Preparation Mechanical Handling Calculation  

SciTech Connect

The scope of this document is to develop the size, operational envelopes, and major requirements of the equipment to be used in the vestibule, cask preparation area, and the crane maintenance area of the Fuel Handling Facility. This calculation is intended to support the License Application (LA) submittal of December 2004, in accordance with the directive given by DOE correspondence received on the 27th of January 2004 entitled: ''Authorization for Bechtel SAIC Company L.L.C. to Include a Bare Fuel Handling Facility and Increased Aging Capacity in the License Application, Contract Number DE-AC28-01R W12101'' (Ref. 167124). This correspondence was appended by further correspondence received on the 19th of February 2004 entitled: ''Technical Direction to Bechtel SAIC Company L.L. C. for Surface Facility Improvements, Contract Number DE-AC28-01R W12101; TDL No. 04-024'' (Ref. 16875 1). These documents give the authorization for a Fuel Handling Facility to be included in the baseline. The limitations of this preliminary calculation lie within the assumptions of section 5 , as this calculation is part of an evolutionary design process.

N. Ambre

2004-05-26T23:59:59.000Z

2

Handling effluent from nuclear thermal propulsion system ground tests  

SciTech Connect

A variety of approaches for handling effluent from nuclear thermal propulsion system ground tests in an environmentally acceptable manner are discussed. The functional requirements of effluent treatment are defined and concept options are presented within the framework of these requirements. System concepts differ primarily in the choice of fission-product retention and waste handling concepts. The concept options considered range from closed cycle (venting the exhaust to a closed volume or recirculating the hydrogen in a closed loop) to open cycle (real time processing and venting of the effluent). This paper reviews the different methods to handle effluent from nuclear thermal propulsion system ground tests.

Shipers, L.R.; Allen, G.C.

1992-09-09T23:59:59.000Z

3

Method of preparing and handling chopped plant materials  

DOE Patents (OSTI)

The method improves efficiency of harvesting, storage, transport, and feeding of dry plant material to animals, and is a more efficient method for harvesting, handling and transporting dry plant material for industrial purposes, such as for production of bioenergy, and composite panels.

Bransby, David I. (2668 Wire Rd., Auburn, AL 36832)

2002-11-26T23:59:59.000Z

4

Test Preparation Options Free Test Prep Websites  

E-Print Network (OSTI)

Test Preparation Options Free Test Prep Websites ACT: http: http://www.collegeboard.com/student/testing/sat/prep_one/test.html http://www.number2.com://testprep.princetonreview.com/CourseSearch/Search.aspx?itemCode=17&productType=F&rid=1&zip=803 02 Test Prep Classes Front Range Community College: Classes

Stowell, Michael

5

Interim report spent nuclear fuel retrieval system fuel handling development testing  

Science Conference Proceedings (OSTI)

Fuel handling development testing was performed in support of the Fuel Retrieval System (FRS) Sub-Project at the Hanford Site. The project will retrieve spent nuclear fuel, clean and remove fuel from canisters, repackage fuel into baskets, and load fuel into a multi-canister overpack (MCO) for vacuum drying and interim dry storage. The FRS is required to retrieve basin fuel canisters, clean fuel elements sufficiently of uranium corrosion products (or sludge), empty fuel from canisters, sort debris and scrap from whole elements, and repackage fuel in baskets in preparation for MCO loading. The purpose of fuel handling development testing was to examine the systems ability to accomplish mission activities, optimization of equipment layouts for initial process definition, identification of special needs/tools, verification of required design changes to support performance specification development, and validation of estimated activity times/throughput. The test program was set up to accomplish this purpose through cold development testing using simulated and prototype equipment; cold demonstration testing using vendor expertise and systems; and graphical computer modeling to confirm feasibility and throughput. To test the fuel handling process, a test mockup that represented the process table was fabricated and installed. The test mockup included a Schilling HV series manipulator that was prototypic of the Schilling Hydra manipulator. The process table mockup included the tipping station, sorting area, disassembly and inspection zones, fuel staging areas, and basket loading stations. The test results clearly indicate that the Schilling Hydra arm cannot effectively perform the fuel handling tasks required unless it is attached to some device that can impart vertical translation, azimuth rotation, and X-Y translation. Other test results indicate the importance of camera locations and capabilities, and of the jaw and end effector tool design. 5 refs., 35 figs., 3 tabs.

Ketner, G.L.; Meeuwsen, P.V.; Potter, J.D.; Smalley, J.T.; Baker, C.P.; Jaquish, W.R.

1997-06-01T23:59:59.000Z

6

Field Test of Manufactured Gas Plant Remediation Technologies: Material Removal and Handling  

Science Conference Proceedings (OSTI)

Common manufactured gas plant (MGP) site structures are often sources of contamination and present a number of unique material removal and handling challenges. This report provides results from a field-scale study involving the excavation of the contents of a subgrade gas holder tank. Specifically discussed are the material handling activities needed to prepare MGP impacted soils and debris for remediation processes.

1996-02-02T23:59:59.000Z

7

Development of an Outdoor Concentrating Photovoltaic Module Testbed, Module Handling and Testing Procedures, and Initial Energy Production Results  

DOE Green Energy (OSTI)

This report addresses the various aspects of setting up a CPV testbed and procedures for handling and testing CPV modules.

Muller, M.

2009-09-01T23:59:59.000Z

8

Report on PV Test Sites and Test Prepared for the  

E-Print Network (OSTI)

Report on PV Test Sites and Test Protocols Prepared for the U.S. Department of Energy Office of Electricity Delivery and Energy Reliability Under Cooperative Agreement No. DE-FC26-06NT42847 Hawai`i Distributed Energy Resource Technologies for Energy Security Revised Task 8 Deliverable PV Test Sites and Test

9

SNS Target Test Facility: Prototype Hg Operations and Remote Handling Tests P. T. Spampinato, T. W. Burgess, J. B. Chesser, V. B. Graves, and S.L. Schrock  

E-Print Network (OSTI)

SNS Target Test Facility: Prototype Hg Operations and Remote Handling Tests P. T. Spampinato, T. W remote handling techniques and tools for replacing target system components. During the past year seal configuration to assess leak tightness and remote handling features. In addition, testing

McDonald, Kirk

10

Conceptual flow sheets development for coal conversion plant coal handling-preparation and ash/slag removal operations  

SciTech Connect

This report presents 14 conceptual flow sheets and major equipment lists for coal handling and preparation operations that could be required for future, commercial coal conversion plants. These flow sheets are based on converting 50,000 tons per day of clean coal representative of the Pittsburgh and Kentucky No. 9 coal seams. Flow sheets were used by Union Carbide Corporation, Oak Ridge National Laboratory, in a survey of coal handling/preparation equipment requirements for future coal conversion plants. Operations covered in this report include run-of-mine coal breaking, coarse coal cleaning, fine coal cleaning, live storage and blending, fine crushing (crushing to top sizes ranging from 1/4-inch to 20 mesh), drying, and grinding (70 percent minus 200 mesh). Two conceptual flow sheets and major equipment lists are also presented for handling ash or granulated slag and other solid wastes produced by nine leading coal conversion processes. These flow sheets provide for solid wastes transport to an environmentally acceptable disposal site as either dry solids or as a water slurry.

1979-07-01T23:59:59.000Z

11

Survey and conceptual flow sheets for coal conversion plant handling-preparation and ash/slag removal operations  

Science Conference Proceedings (OSTI)

This study was undertaken at the request of the Fossil Fuel Processing Division of the Department of Energy. The report includes a compilation of conceptual flow sheets, including major equipment lists, and the results of an availability survey of potential suppliers of equipment associated with the coal and ash/slag operations that will be required by future large coal conversion plant complexes. Conversion plant flow sheet operations and related equipment requirements were based on two representative bituminous coals - Pittsburgh and Kentucky No. 9 - and on nine coal conversion processes. It appears that almost all coal handling and preparation and ash/slag removal equipment covered by this survey, with the exception of some coal comminution equipment, either is on hand or can readily be fabricated to meet coal conversion plant capacity requirements of up to 50,000 short tons per day. Equipment capable of handling even larger capacities can be developed. This approach appears to be unjustified, however, because in many cases a reasonable or optimum number of trains of equipment must be considered when designing a conversion plant complex. The actual number of trains of equipment selected will be influenced by the total requied capacity of the complex, the minimum on-line capacity that can be tolerated in case of equipment failure, reliability of specific equipment types, and the number of reactors and related feed injection stations needed for the specific conversion process.

Zapp, F.C.; Thomas, O.W.; Silverman, M.D.; Dyslin, D.A.; Holmes, J.M.

1980-03-01T23:59:59.000Z

12

Preparations for deuterium--tritium experiments on the Tokamak Fusion Test Reactor*  

Science Conference Proceedings (OSTI)

The final hardware modifications for tritium operation have been completed for the Tokamak Fusion Test Reactor (TFTR) [Fusion Technol. [bold 21], 1324 (1992)]. These activities include preparation of the tritium gas handling system, installation of additional neutron shielding, conversion of the toroidal field coil cooling system from water to a Fluorinert[sup TM] system, modification of the vacuum system to handle tritium, preparation, and testing of the neutral beam system for tritium operation and a final deuterium--deuterium (D--D) run to simulate expected deuterium--tritium (D--T) operation. Testing of the tritium system with low concentration tritium has successfully begun. Simulation of trace and high power D--T experiments using D--D have been performed. The physics objectives of D--T operation are production of [approx]10 MW of fusion power, evaluation of confinement, and heating in deuterium--tritium plasmas, evaluation of [alpha]-particle heating of electrons, and collective effects driven by alpha particles and testing of diagnostics for confined [alpha] particles. Experimental results and theoretical modeling in support of the D--T experiments are reviewed.

Hawryluk, R.J.; Adler, H.; Alling, P.; Ancher, C.; Anderson, H.; Anderson, J.L.; Anderson, J.W.; Arunasalam, V.; Ascione, G.; Aschroft, D.; Barnes, C.W.; Barnes, G.; Batchelor, D.B.; Bateman, G.; Batha, S.; Baylor, L.A.; Beer, M.; Bell, M.G.; Biglow, T.S.; Bitter, M.; Blanchard, W.; Bonoli, P.; Bretz, N.L.; Brunkhorst, C.; Budny, R.; Burgess, T.; Bush, H.; Bush, C.E.; Camp, R.; Caorlin, M.; Carnevale, H.; Chang, Z.; Chen, L.; Cheng, C.Z.; Chrzanowski, J.; Collazo, I.; Collins, J.; Coward, G.; Cowley, S.; Cropper, M.; Darrow, D.S.; Daugert, R.; DeLooper, J.; Duong, H.; Dudek, L.; Durst, R.; Efthimion, P.C.; Ernst, D.; Faunce, J.; Fonck, R.J.; Fredd, E.; Fredrickson, E.; Fromm, N.; Fu, G.Y.; Furth, H.P.; Garzotto, V.; Gentile, C.; Gettelfinger, G.; Gilbert, J.; Gioia, J.; Goldfinger, R.C.; Golian, T.; Gorelenkov, N.; Gouge, M.J.; Grek, B.; Grisham, L.R.; Hammett, G.; Hanson, G.R.; Heidbrink, W.; Hermann, H.W.; Hill, K.W.; Hirshman, S.; Hoffman, D.J.; Hosea, J.; Hulse, R.A.; Hsuan, H.; Ja

1994-05-01T23:59:59.000Z

13

Extensive remote handling and conservative plasma conditions to enable fusion nuclear science R&D using a component testing facility  

E-Print Network (OSTI)

FT/P3-14 Page 1 Extensive remote handling and conservative plasma conditions to enable fusion modularization and remote handling, and allow conservative plasma assumptions including an extended divertor component modularization and capability for remote handling, and estimate the replacement times of various

Princeton Plasma Physics Laboratory

14

Remote Handling and Plasma Conditions to Enable Fusion Nuclear Science R&D Using a US Component Testing Facility  

Science Conference Proceedings (OSTI)

The use of a fusion component testing facility to study and establish, during the ITER era, the remaining scientific and technical knowledge needed by fusion Demo is considered and described in this paper. This use aims to lest components in an integrated fusion nuclear environment, for the first time, to discover and understand the underpinning physical properties, and to develop improved components for further testing, in a time-efficient manner. It requires a design with extensive modularization and remote handling of activated components, and flexible hot-cell laboratories. It further requires reliable plasma conditions to avoid disruptions and minimize their impact, and designs to reduce the divertor heat flux to the level of ITER design. As the plasma duration is extended through the planned ITER level (similar to 10(3) s) and beyond, physical properties with increasing time constants, progressively for similar to 10(4) s, similar to 10(5) s, and similar to 10(6) s, would become accessible for testing and R&D. The longest time constants of these are likely to be of the order of a week ( 106 S). Progressive stages of research operation are envisioned in deuterium, deuterium-tritium for the ITER duration, and deuterium-tritium with increasingly longer plasma durations. The fusion neutron fluence and operational duty factor anticipated for this "scientific exploration" phase of a component test facility are estimated to be up to 1 MW-yr/m(2) and up to 10%, respectively.

Peng, Yueng Kay Martin [ORNL; Burgess, Thomas W [ORNL; Carroll, Adam J [ORNL; Neumeyer, C. L. [Princeton Plasma Physics Laboratory (PPPL); Canik, John [ORNL; Cole, Michael J [ORNL; Dorland, W. D. [University of Maryland; Fogarty, P. J. [Oak Ridge National Laboratory (ORNL); Grisham, L. [Princeton Plasma Physics Laboratory (PPPL); Hillis, Donald Lee [ORNL; Katoh, Yutai [ORNL; Korsah, Kofi [ORNL; Kotschenreuther, M. [University of Texas, Austin; LaHaye, R. [General Atomics, San Diego; Mahajan, S. [University of Texas, Austin; Majeski, R. [Princeton Plasma Physics Laboratory (PPPL); Nelson, Brad E [ORNL; Patton, Bradley D [ORNL; Rasmussen, David A [ORNL; Sabbagh, S. A. [Columbia University; Sontag, Aaron C [ORNL; Stoller, Roger E [ORNL; Tsai, C. C. [Oak Ridge National Laboratory (ORNL); Vanlanju, P. [University of Texas, Austin; Wagner, Jill C [ORNL; Yoder, III, Graydon L [ORNL

2009-08-01T23:59:59.000Z

15

Process Knowledge Summary Report for Advanced Test Reactor Complex Contact-Handled Transuranic Waste Drum TRA010029  

SciTech Connect

This Process Knowledge Summary Report summarizes information collected to satisfy the transportation and waste acceptance requirements for the transfer of one drum containing contact-handled transuranic (TRU) actinide standards generated by the Idaho National Laboratory at the Advanced Test Reactor (ATR) Complex to the Advanced Mixed Waste Treatment Project (AMWTP) for storage and subsequent shipment to the Waste Isolation Pilot Plant for final disposal. The drum (i.e., Integrated Waste Tracking System Bar Code Number TRA010029) is currently stored at the Materials and Fuels Complex. The information collected includes documentation that addresses the requirements for AMWTP and applicable sections of their Resource Conservation and Recovery Act permits for receipt and disposal of this TRU waste generated from ATR. This Process Knowledge Summary Report includes information regarding, but not limited to, the generation process, the physical form, radiological characteristics, and chemical contaminants of the TRU waste, prohibited items, and packaging configuration. This report, along with the referenced supporting documents, will create a defensible and auditable record for this TRU waste originating from ATR.

B. R. Adams; R. P. Grant; P. R. Smith; J. L. Weisgerber

2013-09-01T23:59:59.000Z

16

Test plan for headspace gas sampling of remote-handled transuranic waste containers at Los Alamos National Laboratory  

DOE Green Energy (OSTI)

Seventeen remote-handled (RH) transuranic (TRU) waste canisters currently are stored in vertical, underground shafts at Technical Area (TA)-54, Area G, at Los Alamos National Laboratory (LANL). These 17 RH TRU waste canisters are destined to be shipped to the Waste Isolation Pilot Plant (WIPP) for permanent disposal in the geologic repository. As the RH TRU canister is likely to be the final payload container prior to placement into the 72-B cask and shipment to the WIPP, these waste canisters provide a unique opportunity to ascertain representative flammable gas concentrations in packaged RH-TRU waste. Hydrogen, which is produced by the radiolytic decomposition of hydrogenous constituents in the waste matrix, is the primary flammable gas of concern with RH TRU waste. The primary objectives of the experiment that is described by this test plan are to sample and analyze the waste canister headspace gases to determine the concentration of hydrogen in the headspace gas and to calculate the hydrogen gas generation rate for comparison to the applicable maximum allowable hydrogen generation rate (mole/sec) limits. It is a goal of this experiment to determine the headspace gas concentrations of other gases (e.g., oxygen, nitrogen, carbon dioxide, carbon monoxide, and volatile organic compounds (VOCs) with molecular weights less than 60 g/mole) that are produced by radiolysis or present when the waste was packaged. Additionally, the temperature, pressure, and flow rate of the headspace gas will be measured.

Field, L.R.; Villarreal, R. [Los Alamos National Lab., NM (United States)

1998-02-24T23:59:59.000Z

17

Prepared  

Office of Legacy Management (LM)

Prepared Prepared by Oak Ridge Associated Universities Prepared for Division of Remedial Action Projects U.S. Department of Energy COMPREHENSIVE RADIOLOGICAL SURVEY OFF-SITE PROPERTYM NIAGARA FALLS STORAGE SITE LEWISTON, NEW YORK B.P. ROCCO Radiological Site Assessment Program Manpower Education, Research, and Training Division FINAL REPORT May 1983 B.P. Rocco FINAL REPORT Prepared for A.M. pitt T.J. Sowell C.F. Weaver T.S. Yoo Project Staff Prepared by J.D. Berger R.D. Condra R.C. Gosslee J.A. Mattina OFF-SITE PROPERTY M NIAGARA FALLS STORAGE SITE LEWISTON, NEW YORK CO~WREHENSIVE RADIOLOGICAL SURVEY Radiological Site Assessment Program Manpower Education, Research, and Training Division Oak Ridge Associated Universities Oak Ridge, Tennessee 37830 U.S. Department of Energy as part of the Formerly Utilized Sites -- Remedial Action Program May 1983 -- til - This

18

Status of Centralized Environmental Creep Testing Facility Preparation and Upgrade  

SciTech Connect

Because the ASME Codes do not cover environmental issues that are crucial in the design and construction of VHTR system, investigation of long-term impure helium effects on metallurgical stability and properties becomes very important. The present report describes the development of centralized environmental creep testing facility, its close collaborations with the experiments in low velocity helium recirculation loop, important lessons learned, upgrades in system design in FY06, and current status of the development.

Ren, Weiju [ORNL; Battiste, Rick [ORNL

2006-10-01T23:59:59.000Z

19

Goethite Bench-scale and Large-scale Preparation Tests  

SciTech Connect

The Hanford Waste Treatment and Immobilization Plant (WTP) is the keystone for cleanup of high-level radioactive waste from our nation's nuclear defense program. The WTP will process high-level waste from the Hanford tanks and produce immobilized high-level waste glass for disposal at a national repository, low activity waste (LAW) glass, and liquid effluent from the vitrification off-gas scrubbers. The liquid effluent will be stabilized into a secondary waste form (e.g. grout-like material) and disposed on the Hanford site in the Integrated Disposal Facility (IDF) along with the low-activity waste glass. The major long-term environmental impact at Hanford results from technetium that volatilizes from the WTP melters and finally resides in the secondary waste. Laboratory studies have indicated that pertechnetate ({sup 99}TcO{sub 4}{sup -}) can be reduced and captured into a solid solution of {alpha}-FeOOH, goethite (Um 2010). Goethite is a stable mineral and can significantly retard the release of technetium to the environment from the IDF. The laboratory studies were conducted using reaction times of many days, which is typical of environmental subsurface reactions that were the genesis of this new process. This study was the first step in considering adaptation of the slow laboratory steps to a larger-scale and faster process that could be conducted either within the WTP or within the effluent treatment facility (ETF). Two levels of scale-up tests were conducted (25x and 400x). The largest scale-up produced slurries of Fe-rich precipitates that contained rhenium as a nonradioactive surrogate for {sup 99}Tc. The slurries were used in melter tests at Vitreous State Laboratory (VSL) to determine whether captured rhenium was less volatile in the vitrification process than rhenium in an unmodified feed. A critical step in the technetium immobilization process is to chemically reduce Tc(VII) in the pertechnetate (TcO{sub 4}{sup -}) to Tc(Iv)by reaction with the ferrous ion, Fe{sup 2+}-Fe{sup 2+} is oxidized to Fe{sup 3+} - in the presence of goethite seed particles. Rhenium does not mimic that process; it is not a strong enough reducing agent to duplicate the TcO{sub 4}{sup -}/Fe{sup 2+} redox reactions. Laboratory tests conducted in parallel with these scaled tests identified modifications to the liquid chemistry necessary to reduce ReO{sub 4}{sup -} and capture rhenium in the solids at levels similar to those achieved by Um (2010) for inclusion of Tc into goethite. By implementing these changes, Re was incorporated into Fe-rich solids for testing at VSL. The changes also changed the phase of iron that was in the slurry product: rather than forming goethite ({alpha}-FeOOH), the process produced magnetite (Fe{sub 3}O{sub 4}). Magnetite was considered by Pacific Northwest National Laboratory (PNNL) and VSL to probably be a better product to improve Re retention in the melter because it decomposes at a higher temperature than goethite (1538 C vs. 136 C). The feasibility tests at VSL were conducted using Re-rich magnetite. The tests did not indicate an improved retention of Re in the glass during vitrification, but they did indicate an improved melting rate (+60%), which could have significant impact on HLW processing. It is still to be shown whether the Re is a solid solution in the magnetite as {sup 99}Tc was determined to be in goethite.

Josephson, Gary B.; Westsik, Joseph H.

2011-10-23T23:59:59.000Z

20

Admission Test Preparation Admission test scores help professional and graduate programs determine who to admit (and, in some cases, to award merit-  

E-Print Network (OSTI)

Admission Test Preparation Admission test scores help professional and graduate programs determine-prepared for these tests. Some are tests of aptitude in quantitative skills, verbal and analytical reasoning and/or writing ability (e.g., GRE, LSAT, GMAT), while others are tests of content knowledge (e.g., GRE Subject Tests

Hampton, Randy

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


21

Nuclear Maintenance Applications Center: Nuclear Fuel Handling Equipment Application and Maintenance Guide: Fuel Handling Equipment Guide  

Science Conference Proceedings (OSTI)

Fuel handling is a critical task during a nuclear power plant refueling outage. The proper operation of fuel handling equipment (such as fuel handling machines, fuel upending machines, fuel transfer carriages, and fuel elevators) is important to a successful refueling outage and to preparing fuel for eventual disposal.BackgroundThe fuel handling system contains the components used to move fuel from the time that the new fuel is received until the spent fuel ...

2013-12-13T23:59:59.000Z

22

Demonstration Development Project: Evaluation of a Test Loop to Demonstrate Handling Properties of Liquid CO2-Coal Slurry  

Science Conference Proceedings (OSTI)

Integrated gasification combined cycle (IGCC) power plants employing liquid CO2 in lieu of water as the slurrying medium to feed coal to the gasifier are a promising option for carbon capture and storage (CCS). This report summarizes the design and cost estimate for a proposed CO2-coal slurry test loop system. The objective is to validate a cost estimate for the construction of a full scale CO2-coal slurry test loop and aid in technical aspects of working with ...

2014-01-07T23:59:59.000Z

23

HIGH SODIUM SIMULANT TESTING TO SUPPORT SB8 SLUDGE PREPARATION  

Science Conference Proceedings (OSTI)

Scoping studies were completed for high sodium simulant SRAT/SME cycles to determine any impact to CPC processing. Two SRAT/SME cycles were performed with simulant having sodium supernate concentration of 1.9M at 130% and 100% of the Koopman Minimum Acid requirement. Both of these failed to meet DWPF processing objectives related to nitrite destruction and hydrogen generation. Another set of SRAT/SME cycles were performed with simulant having a sodium supernate concentration of 1.6M at 130%, 125%, 110%, and 100% of the Koopman Minimum Acid requirement. Only the run at 110% met DWPF processing objectives. Neither simulant had a stoichiometric factor window of 30% between nitrite destruction and excessive hydrogen generation. Based on the 2M-110 results it was anticipated that the 2.5M stoichiometric window for processing would likely be smaller than from 110-130%, since it appeared that it would be necessary to increase the KMA factor by at least 10% above the minimum calculated requirement to achieve nitrite destruction due to the high oxalate content. The 2.5M-130 run exceeded the DWPF hydrogen limits in both the SRAT and SME cycle. Therefore, testing of this wash endpoint was halted. This wash endpoint with this minimum acid requirement and mercury-noble metal concentration profile appears to be something DWPF should not process due to an overly narrow window of stoichiometry. The 2M case was potentially processable in DWPF, but modifications would likely be needed in DWPF such as occasionally accepting SRAT batches with undestroyed nitrite for further acid addition and reprocessing, running near the bottom of the as yet ill-defined window of allowable stoichiometric factors, potentially extending the SRAT cycle to burn off unreacted formic acid before transferring to the SME cycle, and eliminating formic acid additions in the frit slurry.

Newell, J.

2012-09-19T23:59:59.000Z

24

Recycle Waste Collection Tank (RWCT) simulant testing in the PVTD feed preparation system  

Science Conference Proceedings (OSTI)

(This is part of the radwaste vitrification program at Hanford.) RWCT was to routinely receive final canister decontamination sand blast frit and rinse water, Decontamination Waste Treatment Tank bottoms, and melter off-gas Submerged Bed Scrubber filter cake. In order to address the design needs of the RWCT system to meet performance levels, the PNL Vitrification Technology (PVTD) program used the Feed Preparation Test System (FPTS) to evaluate its equipment and performance for a simulant of RWCT slurry. (FPTS is an adaptation of the Defense Waste Processing Facility feed preparation system and represents the initially proposed Hanford Waste Vitrification Plant feed preparation system designed by Fluor-Daniel, Inc.) The following were determined: mixing performance, pump priming, pump performance, simulant flow characterization, evaporator and condenser performance, and ammonia dispersion. The RWCT test had two runs, one with and one without tank baffles.

Abrigo, G.P.; Daume, J.T.; Halstead, S.D.; Myers, R.L.; Beckette, M.R.; Freeman, C.J.; Hatchell, B.K.

1996-03-01T23:59:59.000Z

25

Incident Handling Activities  

Science Conference Proceedings (OSTI)

[an error occurred while processing this directive] Incident Handling Activities. Since 1989 the National Institute of Standards ...

26

Spent Fuel Drying System Test Results (Dry-Run in Preparation for Run 8)  

Science Conference Proceedings (OSTI)

The water-filled K-Basins in the Hanford 100 Area have been used to store N-Reactor spent nuclear fuel (SNF) since the 1970s. Because some leaks in the basin have been detected and some of the fuel is breached due to handling damage and corrosion, efforts are underway to remove the fuel elements from wet storage. An Integrated Process Strategy (IPS) has been developed to package, dry, transport, and store these metallic uranium fuel elements in an interim storage facility on the Hanford Site (WHC 1995). Information required to support the development of the drying processes, and the required safety analyses, is being obtained from characterization tests conducted on fuel elements removed from the K-Basins. A series of whole element drying tests (reported in separate documents, see Section 7.0) have been conducted by Pacific Northwest National Laboratory (PNNL)(a)on several intact and damaged fuel elements recovered from both the K-East and K-West Basins. This report documents the results of a test ''dry-run'' conducted prior to the eighth and last of those tests, which was conducted on an N-Reactor outer fuel element removed from K-West canister6513U. The system used for the dry-run test was the Whole Element Furnace Testing System, described in Section 2.0, located in the Postirradiation Testing Laboratory (PTL, 327 Building). The test conditions and methodologies are given in Section 3.0. The experimental results are provided in Section 4.0 and discussed Section 5.0.

BM Oliver; GS Klinger; J Abrefah; SC Marschman; PJ MacFarlan; GA Ritter

1999-08-11T23:59:59.000Z

27

Vacuum Vessel Remote Handling  

E-Print Network (OSTI)

FIRE Vacuum Vessel and Remote Handling Overview B. Nelson, T. Burgess, T. Brown, H-M Fan, G. Jones #12;13 July 2002 Snowmass Review: FIRE Vacuum Vessel and Remote Handling 2 Presentation Outline · Remote Handling - Maintenance Approach & Component Classification - In-Vessel Transporter - Component

28

G-Tunnel pressurized slot-testing preparations; Yucca Mountain Site Characterization Project  

Science Conference Proceedings (OSTI)

Designers and analysts of radioactive waste repositories must be able to predict the mechanical behavior of the host rock. Sandia National laboratories elected to conduct a development program on pressurized slot testing and featured (1) development of an improved method to cut slots using a chain saw with diamond-tipped cutters, (2) measurements useful for determining in situ stresses normal to slots, (3) measurements applicable for determining the in situ modulus of deformation parallel to a drift surface, and (4) evaluations of the potentials of pressurized slot strength testing. This report describes the preparations leading to the measurements and evaluations.

Zimmerman, R.M.; Sifre-Soto, C. [Sandia National Labs., Albuquerque, NM (United States); Mann, K.L.; Bellman, R.A. Jr.; Luker, S. [Science Applications International Corp., Las Vegas, NV (United States); Dodds, D.J. [North Pacific Research, Portland, OR (United States)

1992-04-01T23:59:59.000Z

29

Analysis of core samples from the BPXA-DOE-USGS Mount Elbert gas hydrate stratigraphic test well: Insights into core disturbance and handling  

Science Conference Proceedings (OSTI)

Collecting and preserving undamaged core samples containing gas hydrates from depth is difficult because of the pressure and temperature changes encountered upon retrieval. Hydrate-bearing core samples were collected at the BPXA-DOE-USGS Mount Elbert Gas Hydrate Stratigraphic Test Well in February 2007. Coring was performed while using a custom oil-based drilling mud, and the cores were retrieved by a wireline. The samples were characterized and subsampled at the surface under ambient winter arctic conditions. Samples thought to be hydrate bearing were preserved either by immersion in liquid nitrogen (LN), or by storage under methane pressure at ambient arctic conditions, and later depressurized and immersed in LN. Eleven core samples from hydrate-bearing zones were scanned using x-ray computed tomography to examine core structure and homogeneity. Features observed include radial fractures, spalling-type fractures, and reduced density near the periphery. These features were induced during sample collection, handling, and preservation. Isotopic analysis of the methane from hydrate in an initially LN-preserved core and a pressure-preserved core indicate that secondary hydrate formation occurred throughout the pressurized core, whereas none occurred in the LN-preserved core, however no hydrate was found near the periphery of the LN-preserved core. To replicate some aspects of the preservation methods, natural and laboratory-made saturated porous media samples were frozen in a variety of ways, with radial fractures observed in some LN-frozen sands, and needle-like ice crystals forming in slowly frozen clay-rich sediments. Suggestions for hydrate-bearing core preservation are presented.

Kneafsey, Timothy J.; Lu, Hailong; Winters, William; Boswell, Ray; Hunter, Robert; Collett, Timothy S.

2009-09-01T23:59:59.000Z

30

EV America Skid Test Procedure  

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

6 6 Revision 2 Effective October 1, 2007 Braking Test Prepared by Electric Transportation Applications Prepared by: _______________________________ Date: _________ Roberta Brayer Approved by: _________________________________________________ Date: _______________ Donald Karner Procedure ETA-HTP06 Revision 2 i TABLE OF CONTENTS 1. Objectives 1 2. Purpose 1 3. Documentation 1 4. Initial Conditions and Prerequisites 1 5. Testing Activity Requirements 3 5.3 Dry Controlled Test 4 6. Glossary 5 7. References 7 Appendices Appendix A - Handling Pad Test Data Sheet 8

31

EVALUATION OF ARG-1 SAMPLES PREPARED BY CESIUM CARBONATE DISSOLUTION DURING THE ISOLOK SME ACCEPTABILITY TESTING  

Science Conference Proceedings (OSTI)

Evaluation of Defense Waste Processing Facility (DWPF) Chemical Process Cell (CPC) cycle time identified several opportunities to improve the CPC processing time. The Mechanical Systems & Custom Equipment Development (MS&CED) Section of the Savannah River National Laboratory (SRNL) recently completed the evaluation of one of these opportunities - the possibility of using an Isolok sampling valve as an alternative to the Hydragard valve for taking DWPF process samples at the Slurry Mix Evaporator (SME). The use of an Isolok for SME sampling has the potential to improve operability, reduce maintenance time, and decrease CPC cycle time. The SME acceptability testing for the Isolok was requested in Task Technical Request (TTR) HLW-DWPF-TTR-2010-0036 and was conducted as outlined in Task Technical and Quality Assurance Plan (TTQAP) SRNLRP-2011-00145. RW-0333P QA requirements applied to the task, and the results from the investigation were documented in SRNL-STI-2011-00693. Measurement of the chemical composition of study samples was a critical component of the SME acceptability testing of the Isolok. A sampling and analytical plan supported the investigation with the analytical plan directing that the study samples be prepared by a cesium carbonate (Cs{sub 2}CO{sub 3}) fusion dissolution method and analyzed by Inductively Coupled Plasma - Optical Emission Spectroscopy (ICP-OES). The use of the cesium carbonate preparation method for the Isolok testing provided an opportunity for an additional assessment of this dissolution method, which is being investigated as a potential replacement for the two methods (i.e., sodium peroxide fusion and mixed acid dissolution) that have been used at the DWPF for the analysis of SME samples. Earlier testing of the Cs{sub 2}CO{sub 3} method yielded promising results which led to a TTR from Savannah River Remediation, LLC (SRR) to SRNL for additional support and an associated TTQAP to direct the SRNL efforts. A technical report resulting from this work was issued that recommended that the mixed acid method be replaced by the Cs{sub 2}CO{sub 3} method for the measurement of magnesium (Mg), sodium (Na), and zirconium (Zr) with additional testing of the method by DWPF Laboratory being needed before further implementation of the Cs{sub 2}CO{sub 3} method at that laboratory. While the SME acceptability testing of the Isolok does not address any of the open issues remaining after the publication of the recommendation for the replacement of the mixed acid method by the Cs{sub 2}CO{sub 3} method (since those issues are to be addressed by the DWPF Laboratory), the Cs{sub 2}CO{sub 3} testing associated with the Isolok testing does provide additional insight into the performance of the method as conducted by SRNL. The performance is to be investigated by looking to the composition measurement data generated by the samples of a standard glass, the Analytical Reference Glass - 1 (ARG-1), that were prepared by the Cs{sub 2}CO{sub 3} method and included in the SME acceptability testing of the Isolok. The measurements of these samples were presented as part of the study results, but no statistical analysis of these measurements was conducted as part of those results. It is the purpose of this report to provide that analysis, which was supported using JMP Version 7.0.2.

Edwards, T.; Hera, K.; Coleman, C.

2011-12-05T23:59:59.000Z

32

Handling Pyrophoric Reagents  

SciTech Connect

Pyrophoric reagents are extremely hazardous. Special handling techniques are required to prevent contact with air and the resulting fire. This document provides several methods for working with pyrophoric reagents outside of an inert atmosphere.

Alnajjar, Mikhail S.; Haynie, Todd O.

2009-08-14T23:59:59.000Z

33

Preparation and Testing of the SRF Cavities for the CEBAF 12 GeV Upgrade  

SciTech Connect

Eighty new 7-cell, low-loss cell-shaped cavities are required for the CEBAF 12 GeV Upgrade project. In addition to ten pre-production units fabricated at JLab, the full set of commercially-produced cavities have been delivered. An efficient processing routine, which includes a controlled 30 micron electropolish, has been established to transform these cavities into qualified 8-cavity strings. This work began in 2010 and will run through the end of 2011. The realized cavity performance consistently exceeds project requirements and also the maximum useful gradient in CEBAF: 25 MV/m. We will describe the cavity processing and preparation protocols and summarize test results obtained to date.

Reilly, A. V.; Bass, T.; Burrill, A.; Davis, G. K.; Marhauser, F.; Reece, C. E.; Stirbet, M.

2011-07-01T23:59:59.000Z

34

Transportation and handling environment  

SciTech Connect

The elements of the environment relating to transportation and handling include temperature, solar radiation, precipitation, humidity, pressure, shock, and vibration. While each of these deserves consideration, the latter two, shock and vibration, are perhaps the least understood. The report discusses all of these elements, but concentrates largely on shock and vibration. Emphasis is upon the necessity of understanding both the product and the environment. To that end, descriptions of the environment which have been derived statistically are discussed. Land, sea, and air transport are considered. Current knowledge of the handling environment is indicated.

Gens, M.B.

1972-09-01T23:59:59.000Z

35

FUEL HANDLING MECHANISM  

DOE Patents (OSTI)

A remotely operable handling device specifically adapted for the handling of vertically disposed fuel rods in a nuclear reactor was developed. The device consists essentially of an elongated tubular member having a gripping device at the lower end of the pivoted jaw type adapted to grip an enlarged head on the upper end of the workpiece. The device includes a sensing element which engages the enlarged head and is displaced to remotely indicate when the workpiece is in the proper position to be engaged by the jaws.

Koch, L.J.; Hutter, E.

1960-02-01T23:59:59.000Z

36

SLUG HANDLING DEVICES  

DOE Patents (OSTI)

A device is described for handling fuel elements of a neutronic reactor. The device consists of two concentric telescoped contalners that may fit about the fuel element. A number of ratchet members, equally spaced about the entrance to the containers, are pivoted on the inner container and spring biased to the outer container so thnt they are forced to hear against and hold the fuel element, the weight of which tends to force the ratchets tighter against the fuel element. The ratchets are released from their hold by raising the inner container relative to the outer memeber. This device reduces the radiation hazard to the personnel handling the fuel elements.

Gentry, J.R.

1958-09-16T23:59:59.000Z

37

Application of the SAMGrid test-harness for performance evaluation and tuning of a distributed cluster implementation of data handling services  

SciTech Connect

The SAMGrid team has recently refactored its test harness suite for greater flexibility and easier configuration. This makes possible more interesting applications of the test harness, for component tests, integration tests, and stress tests. This new implementation of the test harness is a Python framework which uses XML for configuration and small plug-in python modules for specific test purposes We report on the architecture of the test harness and its recent application to stress tests of a new analysis cluster at Fermilab, to explore the extremes of analysis use cases and the relevant parameters for tuning in the SAMGrid station services. One current testing application is running on a 128-CPU analysis cluster with access to 6 TB distributed cache and also to a 2 TB centralized cache, permitting studies of different cache strategies. We have also studied the service parameters which affect the performance of retrieving data from tape storage. The use cases studied vary from those which will require rapid file delivery with short processing time per file, to the opposite extreme of long processing time per file. These results are interesting for their implications with regard to Grid operations, and illustrate the type of monitoring and test facilities required to accomplish such performance tuning.

Lyon, A.; Baranovski, A.; Garzoglio, G.; Loebel-Carpenter, L.; Herber, R.; Illingworth, R.; Kennedy, R.; Kreymer, A.; Kumar, A.; Lueking, L.; Merritt, W.; Terekhov, I.; Trumbo, J.; White, S.; Veseli, S.; /Fermilab; Burgon-Lyon, M.; St. Denis, R.; /Glasgow U.; Belforte, S.; /INFN, Trieste; Kerzel, U.; /Karlsruhe U.; Leslie, M.; Bartsch, V.; /Oxford U.

2004-12-01T23:59:59.000Z

38

Argonne Chemical Sciences & Engineering - Facilities - Remote Handling  

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

Facilities Facilities * Actinide * Analytical Chemistry * Premium Coal Samples * Electrochemical Analysis * Glovebox * Glassblowing Fundamental Interactions Catalysis & Energy Conversion Electrochemical Energy Storage Nuclear & Environmental Processes National Security Institute for Atom-Efficient Chemical Transformations Center for Electrical Energy Storage: Tailored Interfaces Contact Us CSE Intranet Remote Handling Mockup Facility Remote Handling Mockup Facility Radiochemist Art Guelis observes technician Kevin Quigley preparing to cut open a surrogate uranium target. Argonne designed and built a Remote Handling Mockup Facility to let engineers simulate the handling of radioactive materials in a non-radioactive environment. The ability to carry out the details of an

39

Storage and Handling | Department of Energy  

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

Storage and Handling Storage and Handling Storage and Handling Records Management Procedures for Storage, Transfer & Retrieval of Records from the Washington National Records Center (WNRC) or Legacy Management Business Center RETIREMENT OF RECORDS: 1. The Program Office is responsible for originating the Records Transmittal and Receipt Form SF-135 (PDF, 107KB), and sending it to IM-23 at doerha@hq.doe.gov for approval. 2. IM-23 reviews the SF-135 for completeness/correctness (Coordinates with the originating office by email if more information is required.). 3. IM-23 sends the SF-135 for approval to WNRC. PREPARING RECORDS FOR THE TRANSFER TO THE WNRC: 1. Use your organization's Records Information Disposition Schedule (RIDS) as a guide toward assessing records for storage. Refer to DOE O

40

Viability of Existing INL Facilities for Dry Storage Cask Handling  

SciTech Connect

This report evaluates existing capabilities at the INL to determine if a practical and cost effective method could be developed for opening and handling full-sized dry storage casks. The Idaho Nuclear Technology and Engineering Center (INTEC) CPP-603, Irradiated Spent Fuel Storage Facility, provides the infrastructure to support handling and examining casks and their contents. Based on a reasonable set of assumptions, it is possible to receive, open, inspect, remove samples, close, and reseal large bolted-lid dry storage casks at the INL. The capability can also be used to open and inspect casks that were last examined at the TAN Hot Shop over ten years ago. The Castor V/21 and REA-2023 casks can provide additional confirmatory information regarding the extended performance of low-burnup (<45 GWD/MTU) used nuclear fuel. Once a dry storage cask is opened inside CPP-603, used fuel retrieved from the cask can be packaged in a shipping cask, and sent to a laboratory for testing. Testing at the INL’s Materials and Fuels Complex (MFC) can occur starting with shipment of samples from CPP-603 over an on-site road, avoiding the need to use public highways. This reduces cost and reduces the risk to the public. The full suite of characterization methods needed to establish the condition of the fuel exists and MFC. Many other testing capabilities also exist at MFC, but when those capabilities are not adequate, samples can be prepared and shipped to other laboratories for testing. This report discusses how the casks would be handled, what work needs to be done to ready the facilities/capabilities, and what the work will cost.

Randy Bohachek; Charles Park; Bruce Wallace; Phil Winston; Steve Marschman

2013-04-01T23:59:59.000Z

Note: This page contains sample records for the topic "handling test prepared" 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

Uranium hexafluoride handling. Proceedings  

SciTech Connect

The United States Department of Energy, Oak Ridge Field Office, and Martin Marietta Energy Systems, Inc., are co-sponsoring this Second International Conference on Uranium Hexafluoride Handling. The conference is offered as a forum for the exchange of information and concepts regarding the technical and regulatory issues and the safety aspects which relate to the handling of uranium hexafluoride. Through the papers presented here, we attempt not only to share technological advances and lessons learned, but also to demonstrate that we are concerned about the health and safety of our workers and the public, and are good stewards of the environment in which we all work and live. These proceedings are a compilation of the work of many experts in that phase of world-wide industry which comprises the nuclear fuel cycle. Their experience spans the entire range over which uranium hexafluoride is involved in the fuel cycle, from the production of UF{sub 6} from the naturally-occurring oxide to its re-conversion to oxide for reactor fuels. The papers furnish insights into the chemical, physical, and nuclear properties of uranium hexafluoride as they influence its transport, storage, and the design and operation of plant-scale facilities for production, processing, and conversion to oxide. The papers demonstrate, in an industry often cited for its excellent safety record, continuing efforts to further improve safety in all areas of handling uranium hexafluoride. Selected papers were processed separately for inclusion in the Energy Science and Technology Database.

Not Available

1991-12-31T23:59:59.000Z

42

Ash Handling System Maintenance Guide  

Science Conference Proceedings (OSTI)

This Ash Handling System Maintenance Guide provides fossil plant maintenance personnel with current maintenance information on this system. This guide will assist plant maintenance personnel in improving the reliability and reducing the maintenance costs for the ash handling system.

2005-12-23T23:59:59.000Z

43

December 2005 PREVENTING AND HANDLING  

E-Print Network (OSTI)

, and remote access servers. NIST SP 800-61, Computer Security Incident Handling Guide, describes the fourDecember 2005 PREVENTING AND HANDLING MALWARE INCIDENTS: HOW TO PROTECT INFORMATION TECHNOLOGY SYSTEMS FROM MALICIOUS CODE AND SOFTWARE PREVENTING AND HANDLING MALWARE INCIDENTS: HOW TO PROTECT

44

Solid handling valve  

DOE Patents (OSTI)

The present invention is directed to a solids handling valve for use in combination with lock hoppers utilized for conveying pulverized coal to a coal gasifier. The valve comprises a fluid-actuated flow control piston disposed within a housing and provided with a tapered primary seal having a recessed seat on the housing and a radially expandable fluid-actuated secondary seal. The valve seals are highly resistive to corrosion, erosion and abrasion by the solids, liquids, and gases associated with the gasification process so as to minimize valve failure.

Williams, William R. (Morgantown, WV)

1979-01-01T23:59:59.000Z

45

Nuclear Maintenance Applications Center: Nuclear Fuel Handling Equipment Application and Maintenance Guide  

Science Conference Proceedings (OSTI)

Fuel handling is a critical item during a nuclear power plant refueling outage. The proper operation of fuel handling equipment, such as fuel handling machines, fuel upending machines, fuel transfer carriages, and fuel elevators, is important to a successful refueling outage and to preparing fuel for eventual disposal.

2007-12-21T23:59:59.000Z

46

Sectional device handling tool  

DOE Patents (OSTI)

Apparatus for remotely handling a device in an irradiated underwater environment includes a plurality of tubular sections interconnected end-to-end to form a handling structure, the bottom section being adapted for connection to the device. A support section is connected to the top tubular section and is adapted to be suspended from an overhead crane. Each section is flanged at its opposite ends. Axially retractable bolts in each bottom flange are threadedly engageable with holes in the top flange of an adjacent section, each bolt being biased to its retracted position and retained in place on the bottom flange. Guide pins on each top flange cooperate with mating holes on adjacent bottom flanges to guide movement of the parts to the proper interconnection orientation. Each section carries two hydraulic line segments provided with quick-connect/disconnect fittings at their opposite ends for connection to the segments of adjacent tubular sections upon interconnection thereof to form control lines which are connectable to the device and to an associated control console.

Candee, Clark B. (Monroeville, PA)

1988-07-12T23:59:59.000Z

47

Fabrication and Integrity Testing of a Korean ITER TBM FW Mock-Up in Preparation for High Heat Flux Test  

Science Conference Proceedings (OSTI)

Test Blanket, Fuel Cycle, and Breeding / Proceedings of the Twentieth Topical Meeting on the Technology of Fusion Energy (TOFE-2012) (Part 2) Nashville, Tennessee, August 27-31, 2012

Jae Sung Yoon; Suk Kwon Kim; Eo Hwak Lee; Seungyon Cho; Dong Won Lee

48

Laser-Triggered Lightning Laboratory Tests: Preparation for Testing at Mississippi State University High-Voltage Laboratory  

Science Conference Proceedings (OSTI)

Lightning diversion using laser technology could be operationally used in the power industry to protect sensitive facilities such as nuclear power plants and critical substations, control centers, and customer facilities. This report provides results to date and plans for large-scale, high-voltage laboratory testing of laser-triggered lightning technology.

1998-01-15T23:59:59.000Z

49

DISPOSAL CONTAINER HANDLING SYSTEM DESCRIPTION DOCUMENT  

Science Conference Proceedings (OSTI)

The Disposal Container Handling System receives and prepares new disposal containers (DCs) and transfers them to the Assembly Transfer System (ATS) or Canister Transfer System (CTS) for loading. The system receives the loaded DCs from ATS or CTS and welds the lids. When the welds are accepted the DCs are termed waste packages (WPs). The system may stage the WP for later transfer or transfer the WP directly to the Waste Emplacement/Retrieval System. The system can also transfer DCs/WPs to/from the Waste Package Remediation System. The Disposal Container Handling System begins with new DC preparation, which includes installing collars, tilting the DC upright, and outfitting the container for the specific fuel it is to receive. DCs and their lids are staged in the receipt area for transfer to the needed location. When called for, a DC is put on a cart and sent through an airlock into a hot cell. From this point on, all processes are done remotely. The DC transfer operation moves the DC to the ATS or CTS for loading and then receives the DC for welding. The DC welding operation receives loaded DCs directly from the waste handling lines or from interim lag storage for welding of the lids. The welding operation includes mounting the DC on a turntable, removing lid seals, and installing and welding the inner and outer lids. After the weld process and non-destructive examination are successfully completed, the WP is either staged or transferred to a tilting station. At the tilting station, the WP is tilted horizontally onto a cart and the collars removed. The cart is taken through an air lock where the WP is lifted, surveyed, decontaminated if required, and then moved into the Waste Emplacement/Retrieval System. DCs that do not meet the welding non-destructive examination criteria are transferred to the Waste Package Remediation System for weld preparation or removal of the lids. The Disposal Container Handling System is contained within the Waste Handling Building System. This includes the primary hot cell bounded by the receiving area and WP transport exit air locks; and isolation doors at ATS, CTS, and Waste Package Remediation. The hot cell includes areas for welding, various staging, tilting, and WP transporter loading. There are associated operating galleries and equipment maintenance areas outside the hot cell. These areas operate concurrently to accommodate the DC/WP throughput rates and support system maintenance. The new DC preparation area is located in an unshielded structure. The handling equipment includes DC/WP bridge cranes, tilting stations, and horizontal transfer carts. The welding area includes DC/WP welders and staging stations. Welding operations are supported by remotely operated equipment including a bridge crane and hoists, welder jib cranes, welding turntables, and manipulators. WP transfer includes a transfer/decontamination and transporter load area. The transfer operations are supported by a remotely operated horizontal lifting system, decontamination system, decontamination and inspection manipulator, and a WP horizontal transfer cart. All handling operations are supported by a suite of fixtures including collars, yokes, lift beams, and lid attachments. Remote equipment is designed to facilitate decontamination and maintenance. Interchangeable components are provided where appropriate. Set-aside areas are included, as required, for fixtures and tooling to support off-normal and recovery operations. Semi-automatic, manual, and backup control methods support normal, maintenance, and recovery operations. The system interfaces with the ATS and CTS to provide empty and receive loaded DCs. The Waste Emplacement/Retrieval System interfaces are for loading/unloading WPs on/from the transporter. The system also interfaces with the Waste Package Remediation System for DC/WP repair. The system is housed, shielded, supported, and has ventilation boundaries by the Waste Handling Building (WHB). The system is ventilated by the WHB Ventilation System, which in conjunction with ventilation boundaries ensure that ai

E. F. Loros

2000-06-30T23:59:59.000Z

50

REMOTE HANDLING ARRANGEMENTS  

DOE Patents (OSTI)

A means for handling remotely a sample pellet to be irradiated in a nuclear reactor is proposed. It is comprised essentially of an inlet tube extending through the outer shield of the reactor and being inclined so that its outer end is at a higher elevation than its inner end, an outlet tube extending through the outer shield being inclined so that its inner end is at a higher elevation than its outer end, the inner ends of these two tubes being interconnected, and a straight tube extending through the outer shield and into the reactor core between the inlet and outlet tubes and passing through the juncture of said inner ends. A rod-like member is rotatably and slidely operated within the central straight tube and has a receptacle on its inner end for receiving a sample pellet from the inlet tube. The rod member is operated to pick up a sample pellet from the inlet tube, carry the sample pellet into the irradiating position within the core, and return to the receiving position where it is rotated to dump the irradiated pellet into the outlet tube by which it is conveyed by gravity to the outside of the reactor. Stop members are provided in the inlet tube, and electrical operating devices are provided to control the sequence of the operation automatically.

Ginns, D.W.

1958-04-01T23:59:59.000Z

51

TEST - SECRETARY STEVEN CHU'S REMARKS AS PREPARED FOR DELIVERY TO THE DOE TRIBAL SUMMIT  

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

Tribal Summit Tribal Summit Secretary Steven Chu Remarks as Prepared for Delivery Thursday, May 5, 2011 Arlington, VA Good morning. Thank you all for joining us today, including those of you watching online. The Obama Administration is committed to strong engagement with Tribal Nations. As a sign of that commitment, you heard from Secretary Vilsack yesterday, and today you will also hear from Secretary Salazar, Administrator Jackson, and White House officials. When I started as Energy Secretary, I made a commitment to hold this summit because it's important to hear directly from you about our shared energy challenges and opportunities. The second commitment I made was to support the Department of Energy's Office of Indian Energy Policy and Programs, which was established under the 2005 Energy Policy Act.

52

Biodiesel Handling and Use Guidelines  

DOE Green Energy (OSTI)

This document is a field guide for end-users, distributors, and those involved in related activities. These guidelines cover fuel use and handling issues that could be anticipated or encountered in the field.

Tyson, S.

2001-09-05T23:59:59.000Z

53

Remote Inspection, Measurement and Handling for LHC  

E-Print Network (OSTI)

Personnel access to the LHC tunnel will be restricted to varying extents during the life of the machine due to radiation, cryogenic and pressure hazards. The ability to carry out visual inspection, measurement and handling activities remotely during periods when the LHC tunnel is potentially hazardous offers advantages in terms of safety, accelerator down time, and costs. The first applications identified were remote measurement of radiation levels at the start of shut-down, remote geometrical survey measurements in the collimation regions, and remote visual inspection during pressure testing and initial machine cool-down. In addition, for remote handling operations, it will be necessary to be able to transmit several real-time video images from the tunnel to the control room. The paper describes the design, development and use of a remotely controlled vehicle to demonstrate the feasibility of meeting the above requirements in the LHC tunnel. Design choices are explained along with operating experience to-dat...

Kershaw, K; Coin, A; Delsaux, F; Feniet, T; Grenard, J L; Valbuena, R

2007-01-01T23:59:59.000Z

54

Storage/Handling | Department of Energy  

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

StorageHandling StorageHandling Records Management Procedures for Storage, Transfer & Retrieval of Records from the Washington National Records Center (WNRC) or Legacy Management...

55

WEAR RESISTANT ALLOYS FOR COAL HANDLING EQUIPMENT  

E-Print Network (OSTI)

Proceedings of the Conference on Coal Feeding Systems, HeldWear Resistant Alloys for Coal Handling Equipment", proposalWear Resistant Alloys for Coal Handling Equi pment". The

Bhat, M.S.

2011-01-01T23:59:59.000Z

56

The Remote-Handled TRU Waste Program  

SciTech Connect

RH TRU Waste is radioactive waste that requires shielding in addition to that provided by the container to protect people nearby from radiation exposure. By definition, the radiation dose rate at the outer surface of the container is greater than 200 millirem per hour and less than 1,000 rem per hour. The DOE is proposing a process for the characterization of RH TRU waste planned for disposal in the WIPP. This characterization process represents a performance-driven approach that satisfies the requirements of the New Mexico Hazardous Waste Act, the Environmental Protection Agency (EPA) regulations for WIPP long-term performance, the transportation requirements of the Nuclear Regulatory Commission (NRC) and the Department of Transportation, as well as the technical safety requirements of RH TRU waste handling. The transportation, management and disposal of RH TRU waste is regulated by external government agencies as well as by the DOE itself. Externally, the characterization of RH-TRU waste for disposal at the WIPP is regulated by 20.4.1.500 New Mexico Administrative Code (incorporating 40 CFR 261.13) for the hazardous constituents and 40 CFR 194.24 for the radioactive constituents. The Nuclear Regulatory Commission certifies the shipping casks and the transportation system must meet DOT regulations. Internally, the DOE evaluates the environmental impacts of RH TRU waste transportation, handling and disposal through its National Environmental Policy Act program. The operational safety is assessed in the RH TRU Waste Safety Analysis Report, to be approved by the DOE. The WIPP has prepared a modification request to the Hazardous Waste Facility Permit that includes modifications to the WIPP facility for the safe receipt and handling of RH TRU waste and the addition of an RH TRU waste analysis plan. Modifications to the facility include systems and equipment for safe handling of RHTRU containers. Two shipping casks are to be used to optimize RH TRU was te throughput: the RH-72B and the CNS 10-160B transportation casks. Additionally, a draft Notification of Proposed Change to the EPA 40 CFR 194 Certification of the WIPP has been prepared, which contains a proposal for the RH TRU characterization program for compliance with the EPA requirements.

Gist, C. S.; Plum, H. L.; Wu, C. F.; Most, W. A.; Burrington, T. P.; Spangler, L. R.

2002-02-26T23:59:59.000Z

57

Propane gas: Handle with care  

SciTech Connect

Because of its chemical composition and combustion properties, this liquefied petroleum (LP) gas can be mixed with air and used as a direct replacement for natural gas with no burner or process equipment modifications. One major and growing use of propane is as a vehicle fuel. Growing industrial use of propane also has prompted the National Fire Protection Association (NFPA) to issue new codes. NFPA standard 58-95, Storing and Handling of Liquefied Petroleum Gases, stresses the need to adhere to safe work and handling practices whenever propane is involved. All employees directly handling the gas should be formally trained and certified, and recertified annually. Although the code applies only to those directly handling propane or operating propane equipment such as portable cylinder filling stations, all employees working around or with propane or other LP gases should understand the characteristics of LP gas and be aware of basic safe handling practices. The paper discusses what LP gas is, special safety concerns, the care required in refilling cylinders, and cylinder inspection.

Fernald, D. [Plant Systems, Inc., Berea, OH (United States)

1996-04-01T23:59:59.000Z

58

WIPP Remote Handled Waste Facility: Performance Dry Run Operations  

SciTech Connect

The Remote Handled (RH) TRU Waste Handling Facility at the Waste Isolation Pilot Plant (WIPP) was recently upgraded and modified in preparation for handling and disposal of RH Transuranic (TRU) waste. This modification will allow processing of RH-TRU waste arriving at the WIPP site in two different types of shielded road casks, the RH-TRU 72B and the CNS 10-160B. Washington TRU Solutions (WTS), the WIPP Management and Operation Contractor (MOC), conducted a performance dry run (PDR), beginning August 19, 2002 and successfully completed it on August 24, 2002. The PDR demonstrated that the RHTRU waste handling system works as designed and demonstrated the handling process for each cask, including underground disposal. The purpose of the PDR was to develop and implement a plan that would define in general terms how the WIPP RH-TRU waste handling process would be conducted and evaluated. The PDR demonstrated WIPP operations and support activities required to dispose of RH-TRU waste in the WIPP underground.

Burrington, T. P.; Britain, R. M.; Cassingham, S. T.

2003-02-24T23:59:59.000Z

59

Bulk materials storage handling and transportation  

Science Conference Proceedings (OSTI)

This book contains papers on bulk materials storage, handling, and transportation. Topic areas covered include: mechanical handling; pneumatic conveying; transportation; freight pipeliners; storage and discharge systems; integrated handling systems; automation; environment and sampling; feeders and flow control; structural design; large mobile machines; and grain handling.

Not Available

1983-01-01T23:59:59.000Z

60

Tritium Handling and Safe Storage  

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

SENSITIVE DOE-HDBK-1129-2007 March 2007 ____________________ DOE HANDBOOK TRITIUM HANDLING AND SAFE STORAGE U.S. Department of Energy AREA SAFT Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. DOE-HDBK-1129-2007

Note: This page contains sample records for the topic "handling test prepared" 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

Portable vacuum object handling device  

SciTech Connect

The disclosure relates to a portable device adapted to handle objects which are not to be touched by hand. A piston and bore wall form a vacuum chamber communicating with an adaptor sealably engageable with an object to be lifted. The piston is manually moved and set to establish vacuum. A valve is manually actuatable to apply the vacuum to lift the object.

Anderson, Gordon H. (Los Alamos, NM)

1983-08-09T23:59:59.000Z

62

Photon Sciences Material Handling Equipment  

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

Active Y Y Rhein Craig 20622 PSBC Active Y Y Page 3 of 80 List of Photon Sciences Mat'l Handling Equip 5242013 4:09:58 PM 725 UV East GE-56 PS-C01 Yale A-422-3749 2 ton...

63

Portable vacuum object handling device  

DOE Patents (OSTI)

The disclosure relates to a portable device adapted to handle objects which are not to be touched by hand. A piston and bore wall form a vacuum chamber communicating with an adaptor sealably engageable with an object to be lifted. The piston is manually moved and set to establish vacuum. A valve is manually actuable to apply the vacuum to lift the object.

Anderson, G.H.

1981-07-30T23:59:59.000Z

64

Pacific Northwest Laboratory (PNL) spent fuel transportation and handling facility models  

SciTech Connect

A spent fuel logistics study was conducted in support of the US DOE program to develop facilities for preparing spent unreprocessed fuel from commercial LWRs for geological storage. Two computerized logistics models were developed. The first one was the site evaluation model. Two studies of spent fuel handling facility and spent fuel disposal facility siting were completed; the first postulates a single spent fuel handling facility located at any of six DOE laboratory sites, while the second study examined siting strategies with the spent fuel repository relative to the spent fuel handling facility. A second model to conduct storage/handling facility simulations was developed. (DLC)

Andrews, W.B.; Bower, J.C.; Burnett, R.A.; Engel, R.L.; Rolland, C.W.

1979-09-01T23:59:59.000Z

65

Remote-Handled Low-Level Waste (RHLLW) Disposal Project Code of Record  

Science Conference Proceedings (OSTI)

The Remote-Handled Low-Level Waste Disposal Project addresses an anticipated shortfall in remote-handled LLW disposal capability following cessation of operations at the existing facility, which will continue until it is full or until it must be closed in preparation for final remediation of the Subsurface Disposal Area (approximately at the end of fiscal year 2015). Development of a new onsite disposal facility, the highest ranked alternative, will provide necessary remote handled LLW disposal capability and will ensure continuity of operations that generate remote-handled LLW. This report documents the Code of Record for design of a new LLW disposal capability.

S.L. Austad, P.E.; L.E. Guillen, P.E.; C. W. McKnight, P.E.; D. S. Ferguson, P.E.

2010-10-01T23:59:59.000Z

66

Status of ITER neutral beam cell remote handling system  

E-Print Network (OSTI)

The ITER neutral beam cell will contain up to three heating neutral beams and one diagnostic neutral beam, and four upper ports. Though manual maintenance work is envisaged within the cell, when containment is breached, or the radiological protection is removed the maintenance must be conducted remotely. This maintenance constitutes the removal and replacement of line replaceable units, and their transport to and from a cask docked to the cell. A design of the remote handling system has been prepared to concept level which this paper describes including the development of a beam line transporter, beam source remote handling equipment, upper port remote handling equipment and equipment for the maintenance of the neutral shield. This equipment has been developed complete the planned maintenance tasks for the components of the neutral beam cell and to have inherent flexibility to enable as yet unforeseen tasks and recovery operations to be performed.

Sykes, N; Choi, C-H; Crofts, O; Crowe, R; Damiani, C; Delavalle, S; Meredith, L; Mindham, T; Raimbach, J; Tesini, A; Van Uffelen, M

2013-01-01T23:59:59.000Z

67

Appendix A: Handling of Federal  

Gasoline and Diesel Fuel Update (EIA)

and selected State legislation and regulation in the AEO This page inTenTionally lefT blank 177 U.S. Energy Information Administration | Assumptions to the Annual Energy Outlook 2012 Appendix A: Handling of Federal and selected State legislation and regulation in the AEO Legislation Brief description AEO handling Basis Residential sector A. National Appliance Energy Conservation Act of 1987 Requires Secretary of Energy to set minimum efficiency standards for 10 appliance categories with periodic updates Included for categories represented in the AEO residential sector forecast. Public Law 100-12. a. Room air conditioners Sets standards for room air conditioners in 2014. Require new purchases of room air conditioners to meet the standard. Federal Register Notice

68

Tritium Handling and Safe Storage  

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

DOE-HDBK-1129-2008 December 2008 DOE HANDBOOK TRITIUM HANDLING AND SAFE STORAGE U.S. Department of Energy AREA SAFT Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. TS DOE-HDBK-1129-2008 ii This page is intentionally blank. DOE-HDBK-1129-2008 iii TABLE OF CONTENTS SECTION PAGE FOREWORD................................................................................................................................ ix ACRONYMS ................................................................................................................................ xi 1.0 INTRODUCTION ....................................................................................................................

69

Portable vacuum object handling device  

DOE Patents (OSTI)

The disclosure relates to a portable device adapted to handle objects which are not to be touched by hand. A piston and bore wall form a vacuum chamber communicating with an adaptor sealably engageable with an object to be lifted. The piston is manually moved and set to establish vacuum. A valve is manually actuatable to apply the vacuum to lift the object. 1 fig.

Anderson, G.H.

1983-08-09T23:59:59.000Z

70

Enhancing CIMOSA with Exception Handling  

E-Print Network (OSTI)

CIMOSA (Open System Architecture for CIM) [2], an architecture for the modelling of manufacturing applications, does not provide a facility for exception definition and handling. Exceptions, traditionally associated to programming language and operating systems, are necessary in all types of languages, including specification languages. Our contribution consists of the enhancement of the CIMOSA model with a complete facility and methodology for the specification of the system behaviour in case of exception.

Messina Pleinevaux Swiss; S. Messina; P. Pleinevaux

1996-01-01T23:59:59.000Z

71

Concentration of remote-handled, transuranic, sodium nitrate-based sludge using agitated thin-film evaporators  

SciTech Connect

The Waste Handling and Packaging Plant (WHPP) is being designed at Oak Ridge National Laboratory (ORNL) to prepared transuranic waste for final disposal. Once operational, this facility will process, package, and certify remote-handled transuranic waste for ultimate shipment and disposal at the Waste Isolation Pilot Plant (WIPP) in Carlsbad, New Mexico. One of the wastes that will be handled at WHIPP is the transuranic sludge currently stored at ORNL in eight 50,000-gal underground tanks. The use of an Agitated Thin-Film Evaporator (ATFE) for concentration of this waste is being investigated. Tests have shown that the ATFE can be used to produce a thick slurry, a powder, or a fused salt. A computer model developed at the Savannah River Plant (SRP) to simulate the operation of ATFE's on their waste is being modified for use on the ORNL transuranic sludge. This paper summarizes the results of the test with the ATFEs to date, discusses the changes in the SRP model necessary to use this model with the ORNL waste, and compares the results of the model with the actual data taken from the operation of ATFEs at vendors' test facilities. 8 refs., 1 fig., 3 tabs.

Walker, J.F. Jr.; Youngblood, E.L.; Berry, J.B. (Oak Ridge National Lab., TN (USA)); Pen, Ben-Li (Institute of Nuclear Energy Research, Lung-Tan (Taiwan))

1991-01-01T23:59:59.000Z

72

DOE N 435.1, Contact-Handled and Remote-Handled Transuranic Waste Packaging  

Directives, Delegations, and Requirements

Provides specific instructions for packaging and/or repackaging contact-handled transuranic (CH-TRU) and remote-handled transuranic (RH-TRU) waste in a manner ...

2011-08-15T23:59:59.000Z

73

FMAC: Coal-Handling Maintenance Guide  

Science Conference Proceedings (OSTI)

The Coal Handling System Maintenance Guide provides fossil plant maintenance personnel with current maintenance information on this system. This report will assist plant maintenance personnel in improving the reliability of and reducing the maintenance costs for the coal handling system.

2006-12-22T23:59:59.000Z

74

Overview on Hydrate Coring, Handling and Analysis  

SciTech Connect

Gas hydrates are crystalline, ice-like compounds of gas and water molecules that are formed under certain thermodynamic conditions. Hydrate deposits occur naturally within ocean sediments just below the sea floor at temperatures and pressures existing below about 500 meters water depth. Gas hydrate is also stable in conjunction with the permafrost in the Arctic. Most marine gas hydrate is formed of microbially generated gas. It binds huge amounts of methane into the sediments. Worldwide, gas hydrate is estimated to hold about 1016 kg of organic carbon in the form of methane (Kvenvolden et al., 1993). Gas hydrate is one of the fossil fuel resources that is yet untapped, but may play a major role in meeting the energy challenge of this century. In June 2002, Westport Technology Center was requested by the Department of Energy (DOE) to prepare a ''Best Practices Manual on Gas Hydrate Coring, Handling and Analysis'' under Award No. DE-FC26-02NT41327. The scope of the task was specifically targeted for coring sediments with hydrates in Alaska, the Gulf of Mexico (GOM) and from the present Ocean Drilling Program (ODP) drillship. The specific subjects under this scope were defined in 3 stages as follows: Stage 1: Collect information on coring sediments with hydrates, core handling, core preservation, sample transportation, analysis of the core, and long term preservation. Stage 2: Provide copies of the first draft to a list of experts and stakeholders designated by DOE. Stage 3: Produce a second draft of the manual with benefit of input from external review for delivery. The manual provides an overview of existing information available in the published literature and reports on coring, analysis, preservation and transport of gas hydrates for laboratory analysis as of June 2003. The manual was delivered as draft version 3 to the DOE Project Manager for distribution in July 2003. This Final Report is provided for records purposes.

Jon Burger; Deepak Gupta; Patrick Jacobs; John Shillinglaw

2003-06-30T23:59:59.000Z

75

ENDTOEND REQUEST HANDLING IN DISTRIBUTED VIDEOONDEMAND SYSTEMS  

E-Print Network (OSTI)

that adequate storage and stream handling capacities are present at the servers in the remote clusters. In addition, the remote sites act as sources of supplemental request handling capacity minimizing overall service is delivered only when the local cluster can­ not handle the load. Between the two remote clusters

Mundur, Padma

76

Depleted UF6 Production and Handling Slide Presentation  

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

Production and Handling Depleted UF6 Production and Handling Slide Presentation An online slide presentation about production and handling of depleted UF6, from mining of uranium...

77

CANISTER HANDLING FACILITY DESCRIPTION DOCUMENT  

Science Conference Proceedings (OSTI)

The purpose of this facility description document (FDD) is to establish requirements and associated bases that drive the design of the Canister Handling Facility (CHF), which will allow the design effort to proceed to license application. This FDD will be revised at strategic points as the design matures. This FDD identifies the requirements and describes the facility design, as it currently exists, with emphasis on attributes of the design provided to meet the requirements. This FDD is an engineering tool for design control; accordingly, the primary audience and users are design engineers. This FDD is part of an iterative design process. It leads the design process with regard to the flowdown of upper tier requirements onto the facility. Knowledge of these requirements is essential in performing the design process. The FDD follows the design with regard to the description of the facility. The description provided in this FDD reflects the current results of the design process.

J.F. Beesley

2005-04-21T23:59:59.000Z

78

Cask system design guidance for robotic handling  

SciTech Connect

Remote automated cask handling has the potential to reduce both the occupational exposure and the time required to process a nuclear waste transport cask at a handling facility. The ongoing Advanced Handling Technologies Project (AHTP) at Sandia National Laboratories is described. AHTP was initiated to explore the use of advanced robotic systems to perform cask handling operations at handling facilities for radioactive waste, and to provide guidance to cask designers regarding the impact of robotic handling on cask design. The proof-of-concept robotic systems developed in AHTP are intended to extrapolate from currently available commercial systems to the systems that will be available by the time that a repository would be open for operation. The project investigates those cask handling operations that would be performed at a nuclear waste repository facility during cask receiving and handling. The ongoing AHTP indicates that design guidance, rather than design specification, is appropriate, since the requirements for robotic handling do not place severe restrictions on cask design but rather focus on attention to detail and design for limited dexterity. The cask system design features that facilitate robotic handling operations are discussed, and results obtained from AHTP design and operation experience are summarized. The application of these design considerations is illustrated by discussion of the robot systems and their operation on cask feature mock-ups used in the AHTP project. 11 refs., 11 figs.

Griesmeyer, J.M.; Drotning, W.D.; Morimoto, A.K.; Bennett, P.C.

1990-10-01T23:59:59.000Z

79

CARRIER/CASK HANDLING SYSTEM DESCRIPTION DOCUMENT  

Science Conference Proceedings (OSTI)

The Carrier/Cask Handling System receives casks on railcars and legal-weight trucks (LWTs) (transporters) that transport loaded casks and empty overpacks to the Monitored Geologic Repository (MGR) from the Carrier/Cask Transport System. Casks that come to the MGR on heavy-haul trucks (HHTs) are transferred onto railcars before being brought into the Carrier/Cask Handling System. The system is the interfacing system between the railcars and LWTs and the Assembly Transfer System (ATS) and Canister Transfer System (CTS). The Carrier/Cask Handling System removes loaded casks from the cask transporters and transfers the casks to a transfer cart for either the ATS or CTS, as appropriate, based on cask contents. The Carrier/Cask Handling System receives the returned empty casks from the ATS and CTS and mounts the casks back onto the transporters for reshipment. If necessary, the Carrier/Cask Handling System can also mount loaded casks back onto the transporters and remove empty casks from the transporters. The Carrier/Cask Handling System receives overpacks from the ATS loaded with canisters that have been cut open and emptied and mounts the overpacks back onto the transporters for disposal. If necessary, the Carrier/Cask Handling System can also mount empty overpacks back onto the transporters and remove loaded overpacks from them. The Carrier/Cask Handling System is located within the Carrier Bay of the Waste Handling Building System. The system consists of cranes, hoists, manipulators, and supporting equipment. The Carrier/Cask Handling System is designed with the tooling and fixtures necessary for handling a variety of casks. The Carrier/Cask Handling System performance and reliability are sufficient to support the shipping and emplacement schedules for the MGR. The Carrier/Cask Handling System interfaces with the Carrier/Cask Transport System, ATS, and CTS as noted above. The Carrier/Cask Handling System interfaces with the Waste Handling Building System for building structures and space allocations. The Carrier/Cask Handling System interfaces with the Waste Handling Building Electrical System for electrical power.

E.F. Loros

2000-06-23T23:59:59.000Z

80

METHODS OF HANDLING AND LAUNDERING BERYLLIUM-CONTAMINATED GARMENTS  

SciTech Connect

In beryllium industries, it has been the general practice to supply workers with protective clothing. Problems in handling and laundering this clothing were investigated. These problems include: potential hazard to laundry workers and subsequent wearers of the clothing, special laundering techniques, methods to determine the degree of contamination on garments, and determining the most desirable types of garments for the purpose. Four methods to determine the degree of contamination discussed include the shake test, the vacuum test, the rinse test, and the smear test. Assuming conventional laundering procedures have been used, the potential hazard to subsequent wearers of the garment is minimal. Standards for determining adequacy of laundry are suggested. These ar 0.1 mu g Be/cm/sup 2/ as determined by the vacuum test, or 200 mu g Be/garment as determined by the rinse test. Possible hazard to those handling contaminated garments could be significant. This hazard is best controlled simply by use of wet methods. Included in this report is the summary of a survey conducted to determine how these problems are handled in other beryllium industries. (auth)

Cohen, J.J.

1963-04-01T23:59:59.000Z

Note: This page contains sample records for the topic "handling test prepared" 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

Scheduling coal handling processes using metaheuristics.  

E-Print Network (OSTI)

??The operational scheduling at coal handling facilities is of the utmost importance to ensure that the coal consuming processes are supplied with a constant feed… (more)

Conradie, David Gideon

2008-01-01T23:59:59.000Z

82

Waste management handling in Benin City.  

E-Print Network (OSTI)

??The researcher was inspired by the topic “Waste management handling” due to the ugly situa-tion of waste being littered all over the city, which have… (more)

Oseghale, Peter

2011-01-01T23:59:59.000Z

83

Improvement of storage, handling, and transportability of fine coal. Quarterly technical progress report number 8, October 1--December 31, 1995  

SciTech Connect

The Mulled Coal process was developed as a means of overcoming the adverse handling characteristics of wet fine coal without thermal drying. The process involves the addition of a low cost, harmless reagent to wet fine coal using off-the-shelf mixing equipment. Based on laboratory- and bench-scale testing, Mulled coal can be stored, shipped, and burned without causing any of the plugging, pasting, carryback and freezing problems normally associated with wet coal. On the other hand, Mulled Coal does not cause the fugitive and airborne dust problems normally associated with thermally dried coal. The objectives of this project are to demonstrate that: the Mulled Coal process, which has been proved to work on a wide range of wet fine coals at bench scale, will work equally well on a continuous basis, producing consistent quality, and at a convincing rate of production in a commercial coal preparation plant; the wet product from a fine coal cleaning circuit can be converted to a solid fuel form for ease of handling and cost savings in storage and rail car transportation; and a wet fine coal product thus converted to a solid fuel form, can be stored, shipped, and burned with conventional fuel handling, transportation, and combustion systems.

1996-03-15T23:59:59.000Z

84

Thermal decomposition study of hydroxylamine nitrate during storage and handling  

E-Print Network (OSTI)

Hydroxylamine nitrate (HAN), an important agent for the nuclear industry and the U.S. Army, has been involved in several costly incidents. To prevent similar incidents, the study of HAN safe storage and handling boundary has become extremely important for industries. However, HAN decomposition involves complicated reaction pathways due to its autocatalytic behavior and therefore presents a challenge for definition of safe boundaries of HAN storage and handling. This research focused on HAN decomposition behavior under various conditions and proposed isothermal aging testing and kinetic-based simulation to determine safety boundaries for HAN storage and handling. Specifically, HAN decomposition in the presence of glass, titanium, stainless steel with titanium, or stainless steel was examined in an Automatic Pressure Tracking Adiabatic Calorimeter (APTAC). n-th order kinetics was used for initial reaction rate estimation. Because stainless steel is a commonly used material for HAN containers, isothermal aging tests were conducted in a stainless steel cell to determine the maximum safe storage time of HAN. Moreover, by changing thermal inertia, data for HAN decomposition in the stainless steel cell were examined and the experimental results were simulated by the Thermal Safety Software package. This work offers useful guidance for industries that manufacture, handle, and store HAN. The experimental data acquired not only can help with aspects of process safety design, including emergency relief systems, process control, and process equipment selection, but also is a useful reference for the associated theoretical study of autocatalytic decomposition behavior.

Zhang, Chuanji

2003-05-01T23:59:59.000Z

85

Preliminary Hazard Analysis for the Remote-Handled Low-Level Waste Disposal Project  

Science Conference Proceedings (OSTI)

The need for remote handled low level waste (LLW) disposal capability has been identified. A new onsite, remote-handled LLW disposal facility has been identified as the highest ranked alternative for providing continued, uninterrupted remote-handled LLW disposal capability for remote-handled LLW that is generated as part of the nuclear mission of the Idaho National Laboratory and from spent nuclear fuel processing activities at the Naval Reactors Facility. Historically, this type of waste has been disposed of at the Radioactive Waste Management Complex. Disposal of remote-handled LLW in concrete disposal vaults at the Radioactive Waste Management Complex will continue until the facility is full or until it must be closed in preparation for final remediation of the Subsurface Disposal Area (approximately at the end of Fiscal Year 2017). This document supports the conceptual design for the proposed remote-handled LLW disposal facility by providing an initial nuclear facility hazard categorization and by identifying potential hazards for processes associated with onsite handling and disposal of remote-handled LLW.

Lisa Harvego; Mike Lehto

2010-10-01T23:59:59.000Z

86

Preliminary Hazard Analysis for the Remote-Handled Low-Level Waste Disposal Facility  

Science Conference Proceedings (OSTI)

The need for remote handled low level waste (LLW) disposal capability has been identified. A new onsite, remote-handled LLW disposal facility has been identified as the highest ranked alternative for providing continued, uninterrupted remote-handled LLW disposal capability for remote-handled LLW that is generated as part of the nuclear mission of the Idaho National Laboratory and from spent nuclear fuel processing activities at the Naval Reactors Facility. Historically, this type of waste has been disposed of at the Radioactive Waste Management Complex. Disposal of remote-handled LLW in concrete disposal vaults at the Radioactive Waste Management Complex will continue until the facility is full or until it must be closed in preparation for final remediation of the Subsurface Disposal Area (approximately at the end of Fiscal Year 2017). This document supports the conceptual design for the proposed remote-handled LLW disposal facility by providing an initial nuclear facility hazard categorization and by identifying potential hazards for processes associated with onsite handling and disposal of remote-handled LLW.

Lisa Harvego; Mike Lehto

2010-05-01T23:59:59.000Z

87

Preliminary Hazard Analysis for the Remote-Handled Low-Level Waste Disposal Facility  

Science Conference Proceedings (OSTI)

The need for remote handled low level waste (LLW) disposal capability has been identified. A new onsite, remote-handled LLW disposal facility has been identified as the highest ranked alternative for providing continued, uninterrupted remote-handled LLW disposal capability for remote-handled LLW that is generated as part of the nuclear mission of the Idaho National Laboratory and from spent nuclear fuel processing activities at the Naval Reactors Facility. Historically, this type of waste has been disposed of at the Radioactive Waste Management Complex. Disposal of remote-handled LLW in concrete disposal vaults at the Radioactive Waste Management Complex will continue until the facility is full or until it must be closed in preparation for final remediation of the Subsurface Disposal Area (approximately at the end of Fiscal Year 2017). This document supports the conceptual design for the proposed remote-handled LLW disposal facility by providing an initial nuclear facility hazard categorization and by identifying potential hazards for processes associated with onsite handling and disposal of remote-handled LLW.

Lisa Harvego; Mike Lehto

2010-02-01T23:59:59.000Z

88

WASTE HANDLING BUILDING ELECTRICAL SYSTEM DESCRIPTION DOCUMENT  

SciTech Connect

The Waste Handling Building Electrical System performs the function of receiving, distributing, transforming, monitoring, and controlling AC and DC power to all waste handling building electrical loads. The system distributes normal electrical power to support all loads that are within the Waste Handling Building (WHB). The system also generates and distributes emergency power to support designated emergency loads within the WHB within specified time limits. The system provides the capability to transfer between normal and emergency power. The system provides emergency power via independent and physically separated distribution feeds from the normal supply. The designated emergency electrical equipment will be designed to operate during and after design basis events (DBEs). The system also provides lighting, grounding, and lightning protection for the Waste Handling Building. The system is located in the Waste Handling Building System. The system consists of a diesel generator, power distribution cables, transformers, switch gear, motor controllers, power panel boards, lighting panel boards, lighting equipment, lightning protection equipment, control cabling, and grounding system. Emergency power is generated with a diesel generator located in a QL-2 structure and connected to the QL-2 bus. The Waste Handling Building Electrical System distributes and controls primary power to acceptable industry standards, and with a dependability compatible with waste handling building reliability objectives for non-safety electrical loads. It also generates and distributes emergency power to the designated emergency loads. The Waste Handling Building Electrical System receives power from the Site Electrical Power System. The primary material handling power interfaces include the Carrier/Cask Handling System, Canister Transfer System, Assembly Transfer System, Waste Package Remediation System, and Disposal Container Handling Systems. The system interfaces with the MGR Operations Monitoring and Control System for supervisory monitoring and control signals. The system interfaces with all facility support loads such as heating, ventilation, and air conditioning, office, fire protection, monitoring and control, safeguards and security, and communications subsystems.

S.C. Khamamkar

2000-06-23T23:59:59.000Z

89

Assessment of Coal Handling for Fuel Flexibility  

Science Conference Proceedings (OSTI)

To reduce total generating costs, power generators may use multiple solid fuels. This study is a preliminary investigation of the methods and costs of handling multiple solid fuels. An important byproduct of the study was some of the first-ever systematic comparisons of coal handling costs at a sample of plants.

1998-09-03T23:59:59.000Z

90

Constraint Handling in Particle Swarm Optimization  

Science Conference Proceedings (OSTI)

In this article, the authors propose a particle swarm optimization PSO for constrained optimization. The proposed PSO adopts a multiobjective approach to constraint handling. Procedures to update the feasible and infeasible personal best are designed ... Keywords: Constrained Optimization, Constraint Handling, Feasible Personal Best, Infeasible Personal Best, Multiobjective Optimization, Particle Swarm Optimization

Wen Fung Leong; Gary G. Yen

2010-01-01T23:59:59.000Z

91

NUREG/CR-6695 PNNL-13375 Hydrologic Uncertainty Assessment for Decommissioning Sites: Hypothetical Test Case Applications Prepared by  

E-Print Network (OSTI)

This report uses hypothetical decommissioning test cases to illustrate an uncertainty assessment methodology for dose assessments conducted as part of decommissioning analyses for NRC-licensed facilities. This methodology was presented previously in NUREG/CR-6656. The hypothetical test case source term and scenarios are based on an actual decommissioning case and the physical setting is based on the site of a field experiment carried out for the NRC in Arizona. The emphasis in the test case was on parameter uncertainty. The analysis is limited to the hydrologic aspects of the exposure pathway involving infiltration of water at the ground surface, leaching of contaminants, and transport of contaminants through the groundwater to a point of exposure. The methodology uses generic parameter distributions based on national or regional databases for estimating

P. D. Meyer; R. Y. Taira

2001-01-01T23:59:59.000Z

92

Draft Environmental Assessment on the Remote-handled Waste Disposition  

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

Draft Environmental Assessment on the Remote-handled Waste Disposition Project available for public review and comment Draft Environmental Assessment on the Remote-handled Waste Disposition Project available for public review and comment The U.S. Department of Energy invites the public to review and comment on a draft environmental assessment that the Department issued today, for a proposal to process approximately 327 cubic meters of remote-handled waste currently stored at the Idaho National Laboratory. An additional five cubic meters of waste stored at the Hanford Site near Richland, Washington is also evaluated since it is reasonably foreseeable that a decision may be made in the future to send that waste to Idaho for treatment. The project is necessary to prepare the waste for legally-required disposal. Under the Department�s preferred alternative, workers would use sealed rooms called hot cells at the Idaho Nuclear Technology and Engineering Center (INTEC) to process the waste, treat it as necessary and repackage it so that it is ready for disposal. The document describes the modifications necessary to hot cells to perform the work.

93

Recovery Efficiency Test Project: Phase 1, Activity report. Volume 1: Site selection, drill plan preparation, drilling, logging, and coring operations  

SciTech Connect

The recovery Efficiency Test well project addressed a number of technical issues. The primary objective was to determine the increased efficiency gas recovery of a long horizontal wellbore over that of a vertical wellbore and, more specifically, what improvements can be expected from inducing multiple hydraulic fractures from such a wellbore. BDM corporation located, planned, and drilled a long radius turn horizontal well in the Devonian shale Lower Huron section in Wayne County, West Virginia, demonstrating that state-of-the-art technology is capable of drilling such wells. BDM successfully tested drilling, coring, and logging in a horizontal well using air as the circulating medium; conducted reservoir modeling studies to protect flow rates and reserves in advance of drilling operations; observed two phase flow conditions in the wellbore not observed previously; cored a fracture zone which produced gas; observed that fractures in the core and the wellbore were not systematically spaced (varied from 5 to 68 feet in different parts of the wellbore); observed that highest gas show rates reported by the mud logger corresponded to zone with lowest fracture spacing (five feet) or high fracture frequency. Four and one-half inch casting was successfully installed in the borehole and was equipped to isolate the horizontal section into eight (8) zones for future testing and stimulation operations. 6 refs., 48 figs., 10 tabs.

Overbey, W.K. Jr.; Carden, R.S.; Kirr, J.N.

1987-04-01T23:59:59.000Z

94

Control of Test Conduct  

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

2 Revision 1 Effective June 2008 Control of Test Conduct Prepared by Electric Transportation Applications Prepared by: Date: Garrett P....

95

Review of Test Results  

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

GAC004 Revision 1 Effective June 2008 Review of Test Results Prepared by Electric Transportation Applications Prepared by: Date: Garrett...

96

Conceptual Safety Design Report for the Remote Handled Low-Level Waste Disposal Facility  

SciTech Connect

A new onsite, remote-handled LLW disposal facility has been identified as the highest ranked alternative for providing continued, uninterrupted remote-handled LLW disposal for remote-handled LLW from the Idaho National Laboratory and for spent nuclear fuel processing activities at the Naval Reactors Facility. Historically, this type of waste has been disposed of at the Radioactive Waste Management Complex. Disposal of remote-handled LLW in concrete disposal vaults at the Radioactive Waste Management Complex will continue until the facility is full or until it must be closed in preparation for final remediation of the Subsurface Disposal Area (approximately at the end of Fiscal Year 2017). This conceptual safety design report supports the design of a proposed onsite remote-handled LLW disposal facility by providing an initial nuclear facility hazard categorization, by identifying potential hazards for processes associated with onsite handling and disposal of remote-handled LLW, by evaluating consequences of postulated accidents, and by discussing the need for safety features that will become part of the facility design.

Boyd D. Christensen

2010-05-01T23:59:59.000Z

97

Conceptual Safety Design Report for the Remote Handled Low-Level Waste Disposal Facility  

Science Conference Proceedings (OSTI)

A new onsite, remote-handled LLW disposal facility has been identified as the highest ranked alternative for providing continued, uninterrupted remote-handled LLW disposal for remote-handled LLW from the Idaho National Laboratory and for spent nuclear fuel processing activities at the Naval Reactors Facility. Historically, this type of waste has been disposed of at the Radioactive Waste Management Complex. Disposal of remote-handled LLW in concrete disposal vaults at the Radioactive Waste Management Complex will continue until the facility is full or until it must be closed in preparation for final remediation of the Subsurface Disposal Area (approximately at the end of Fiscal Year 2017). This conceptual safety design report supports the design of a proposed onsite remote-handled LLW disposal facility by providing an initial nuclear facility hazard categorization, by identifying potential hazards for processes associated with onsite handling and disposal of remote-handled LLW, by evaluating consequences of postulated accidents, and by discussing the need for safety features that will become part of the facility design.

Boyd D. Christensen

2010-02-01T23:59:59.000Z

98

Preliminary Safety Design Report for Remote Handled Low-Level Waste Disposal Facility  

SciTech Connect

A new onsite, remote-handled low-level waste disposal facility has been identified as the highest ranked alternative for providing continued, uninterrupted remote-handled low-level waste disposal for remote-handled low-level waste from the Idaho National Laboratory and for nuclear fuel processing activities at the Naval Reactors Facility. Historically, this type of waste has been disposed of at the Radioactive Waste Management Complex. Disposal of remote-handled low-level waste in concrete disposal vaults at the Radioactive Waste Management Complex will continue until the facility is full or until it must be closed in preparation for final remediation of the Subsurface Disposal Area (approximately at the end of Fiscal Year 2017). This preliminary safety design report supports the design of a proposed onsite remote-handled low-level waste disposal facility by providing an initial nuclear facility hazard categorization, by discussing site characteristics that impact accident analysis, by providing the facility and process information necessary to support the hazard analysis, by identifying and evaluating potential hazards for processes associated with onsite handling and disposal of remote-handled low-level waste, and by discussing the need for safety features that will become part of the facility design.

Timothy Solack; Carol Mason

2012-03-01T23:59:59.000Z

99

Construction and operation of replacement hazardous waste handling facility at Lawrence Berkeley Laboratory. Environmental Assessment  

Science Conference Proceedings (OSTI)

The US Department of Energy (DOE) has prepared an environmental assessment (EA), DOE/EA-0423, for the construction and operation of a replacement hazardous waste handling facility (HWHF) and decontamination of the existing HWHF at Lawrence Berkeley Laboratory (LBL), Berkeley, California. The proposed facility would replace several older buildings and cargo containers currently being used for waste handling activities and consolidate the LBL`s existing waste handling activities in one location. The nature of the waste handling activities and the waste volume and characteristics would not change as a result of construction of the new facility. Based on the analysis in the EA, DOE has determined that the proposed action would not constitute a major Federal action significantly affecting the quality of the human environment within the meaning of the National Environmental Policy Act (NEPA) of 1969, 42 USC. 4321 et seq. Therefore, an environmental impact statement is not required.

Not Available

1992-09-01T23:59:59.000Z

100

Remote-Handled Low-Level Waste Disposal Project Code of Record  

Science Conference Proceedings (OSTI)

The Remote-Handled Low-Level Waste (LLW) Disposal Project addresses an anticipated shortfall in remote-handled LLW disposal capability following cessation of operations at the existing facility, which will continue until it is full or until it must be closed in preparation for final remediation of the Subsurface Disposal Area (approximately at the end of Fiscal Year 2017). Development of a new onsite disposal facility, the highest ranked alternative, will provide necessary remote-handled LLW disposal capability and will ensure continuity of operations that generate remote-handled LLW. This report documents the Code of Record for design of a new LLW disposal capability. The report is owned by the Design Authority, who can authorize revisions and exceptions. This report will be retained for the lifetime of the facility.

S.L. Austad, P.E.; L.E. Guillen, P.E.; C. W. McKnight, P.E.; D. S. Ferguson, P.E.

2011-04-01T23:59:59.000Z

Note: This page contains sample records for the topic "handling test prepared" 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

Remote-Handled Low-Level Waste Disposal Project Code of Record  

Science Conference Proceedings (OSTI)

The Remote-Handled Low-Level Waste (LLW) Disposal Project addresses an anticipated shortfall in remote-handled LLW disposal capability following cessation of operations at the existing facility, which will continue until it is full or until it must be closed in preparation for final remediation of the Subsurface Disposal Area (approximately at the end of Fiscal Year 2017). Development of a new onsite disposal facility will provide necessary remote-handled LLW disposal capability and will ensure continuity of operations that generate remote-handled LLW. This report documents the Code of Record for design of a new LLW disposal capability. The report is owned by the Design Authority, who can authorize revisions and exceptions. This report will be retained for the lifetime of the facility.

S.L. Austad, P.E.; L.E. Guillen, P.E.; C. W. McKnight, P.E.; D. S. Ferguson, P.E.

2012-06-01T23:59:59.000Z

102

Remote-Handled Low-Level Waste Disposal Project Code of Record  

Science Conference Proceedings (OSTI)

The Remote-Handled Low-Level Waste (LLW) Disposal Project addresses an anticipated shortfall in remote-handled LLW disposal capability following cessation of operations at the existing facility, which will continue until it is full or until it must be closed in preparation for final remediation of the Subsurface Disposal Area (approximately at the end of Fiscal Year 2017). Development of a new onsite disposal facility, the highest ranked alternative, will provide necessary remote-handled LLW disposal capability and will ensure continuity of operations that generate remote-handled LLW. This report documents the Code of Record for design of a new LLW disposal capability. The report is owned by the Design Authority, who can authorize revisions and exceptions. This report will be retained for the lifetime of the facility.

S.L. Austad, P.E.; L.E. Guillen, P.E.; C. W. McKnight, P.E.; D. S. Ferguson, P.E.

2011-01-01T23:59:59.000Z

103

Remote-Handled Low-Level Waste Disposal Project Code of Record  

Science Conference Proceedings (OSTI)

The Remote-Handled Low-Level Waste (LLW) Disposal Project addresses an anticipated shortfall in remote-handled LLW disposal capability following cessation of operations at the existing facility, which will continue until it is full or until it must be closed in preparation for final remediation of the Subsurface Disposal Area (approximately at the end of Fiscal Year 2017). Development of a new onsite disposal facility will provide necessary remote-handled LLW disposal capability and will ensure continuity of operations that generate remote-handled LLW. This report documents the Code of Record for design of a new LLW disposal capability. The report is owned by the Design Authority, who can authorize revisions and exceptions. This report will be retained for the lifetime of the facility.

S.L. Austad, P.E.; L.E. Guillen, P.E.; C. W. McKnight, P.E.; D. S. Ferguson, P.E.

2012-04-01T23:59:59.000Z

104

INTERNATIONAL SYMPOSIUM ON PROCESSING AND HANDLING ...  

Science Conference Proceedings (OSTI)

... Battle, DuPont White Pigments and Mineral Products, Edge Moor Plant, Edge Moor, ... PHYSICAL EXAMINATION AND HANDLING OF WET AND DRY C60: K. ... part of a modern ironmaking blast furnace with high pulverised coal injection, ...

105

Automatic Continuous Commissioning of Measurement Instruments in Air Handling Units  

E-Print Network (OSTI)

This paper presents a robust strategy based on a condition-based adaptive statistical method for automatic commissioning of measurement instruments typically employed in air-handling units (AHU). The multivariate statistic method, principal component analysis (PCA), is adopted and modified to monitor the air handling process. Two PCA models are built corresponding to the heat balance and pressure-flow balance of the air-handling process. Sensor faults can be detected and isolated using the Q-statistic and the Q-contribution plot. The fault isolation ability against typical component faults is improved using knowledge-based analysis. A novel condition-based adaptive scheme is developed to update the PCA models with the operation conditions for continuous online application. A commissioning tool is developed to implement the strategy. Simulation tests and field tests in a building in Hong Kong were conducted to validate the automatic commissioning strategy for typical AHU. The integration of the tool with a building management system (BMS) and its application is demonstrated.

Xiao, F.; Wang, S.

2006-01-01T23:59:59.000Z

106

Improvement of storage, handling, and transportability of fine coal. Quarterly technical progress report No. 7, July 1, 1995--September 30, 1995  

SciTech Connect

The Mulled Coal process was developed as a means of overcoming the adverse handling characteristics of wet fine coal without thermal drying. The process involves the addition of a low cost harmless reagent to wet fine coal using off-the-shelf mixing equipment. Based on laboratory- and bench-scale testing, Mulled Coal can be stored, shipped, and burned without causing any of the plugging, pasting, carryback and freezing problems normally associated with wet coal. The objectives of this project are to demonstrate that: The Mulled Coal process, which has been proven to work on a wide range of wet fine coals at bench scale, will work equally well in a commercial coal preparation plant. The wet product from a fine coal cleaning circuit can be converted to a solid fuel form for ease of handling and cost savings in storage and rail car transportation. A wet fine coal product thus converted to a solid fuel form can be stored, shipped, and burned with conventional fuel handling, transportation, and combustion systems. The Mulled Coal circuit was installed in an empty bay at the Chetopa Preparation Plant. Equipment has been installed to divert a 2.7 tonnes/hr (3 tons/hr) slipstream of the froth concentrate to a dewatering centrifuge. The concentrated wet coal fines from the centrifuge dropped through a chute directly into a surge hopper and feed system for the Mulled Coal circuit. The Mulled Coal product was gravity discharged from the circuit to a truck or product discharge area from which it will be hauled to a stockpile located at the edge of the clean coal stockpile area. During the 3-month operating period, the facility produced 870 tonnes (966 tons) of the Muffed Coal for evaluation in various storage, handling, and transportation equipment and operations. Immediately following the production demonstration, the circuit was disassembled and the facility was decommissioned.

1996-08-22T23:59:59.000Z

107

FUEL HANDLING FACILITY CRITICALITY SAFETY CALCULATIONS  

SciTech Connect

The purpose of this design calculation is to perform a criticality evaluation of the Fuel Handling Facility (FHF) and the operations and processes performed therein. The current intent of the FHF is to receive transportation casks whose contents will be unloaded and transferred to waste packages (WP) or MGR Specific Casks (MSC) in the fuel transfer bays. Further, the WPs will also be prepared in the FHF for transfer to the sub-surface facility (for disposal). The MSCs will be transferred to the Aging Facility for storage. The criticality evaluation of the FHF features the following: (I) Consider the types of waste to be received in the FHF as specified below: (1) Uncanistered commercial spent nuclear fuel (CSNF); (2) Canistered CSNF (with the exception of horizontal dual-purpose canister (DPC) and/or multi-purpose canisters (MPCs)); (3) Navy canistered SNF (long and short); (4) Department of Energy (DOE) canistered high-level waste (HLW); and (5) DOE canistered SNF (with the exception of MCOs). (II) Evaluate the criticality analyses previously performed for the existing Nuclear Regulatory Commission (NRC)-certified transportation casks (under 10 CFR 71) to be received in the FHF to ensure that these analyses address all FHF conditions including normal operations, and Category 1 and 2 event sequences. (III) Evaluate FHF criticality conditions resulting from various Category 1 and 2 event sequences. Note that there are currently no Category 1 and 2 event sequences identified for FHF. Consequently, potential hazards from a criticality point of view will be considered as identified in the ''Internal Hazards Analysis for License Application'' document (BSC 2004c, Section 6.6.4). (IV) Assess effects of potential moderator intrusion into the fuel transfer bay for defense in depth. The SNF/HLW waste transfer activity (i.e., assembly and canister transfer) that is being carried out in the FHF has been classified as safety category in the ''Q-list'' (BSC 2003, p. A-6). Therefore, this design calculation is subject to the requirements of the ''Quality Assurance Requirements and Description'' (DOE 2004), even though the FHF itself has not yet been classified in the Q-list. Performance of the work scope as described and development of the associated technical product conform to the procedure AP-3.124, ''Design Calculations and Analyses''.

C.E. Sanders

2005-06-30T23:59:59.000Z

108

LM Records Handling System (LMRHS01) - Rocky Flats Environmental...  

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

here Home LM Records Handling System (LMRHS01) - Rocky Flats Environmental Records Database, Office of Legacy Management LM Records Handling System (LMRHS01) - Rocky Flats...

109

LM Records Handling System (LMRHS01) - Electronic Records Keeping...  

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

Publications LM Records Handling System (LMRHS01) - Rocky Flats Environmental Records Database, Office of Legacy Management LM Records Handling System (LMRHS01) - Energy Employees...

110

T-656: Microsoft Office Visio DXF File Handling Arbitrary Code...  

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

6: Microsoft Office Visio DXF File Handling Arbitrary Code Execution Vulnerability T-656: Microsoft Office Visio DXF File Handling Arbitrary Code Execution Vulnerability June 28,...

111

Plutonium stabilization and handling (PuSH)  

SciTech Connect

This Functional Design Criteria (FDC) addresses construction of a Stabilization and Packaging System (SPS) to oxidize and package for long term storage remaining plutonium-bearing special nuclear materials currently in inventory at the Plutonium Finishing Plant (PFP), and modification of vault equipment to allow storage of resulting packages of stabilized SNM for up to fifty years. The major sections of the project are: site preparation; SPS Procurement, Installation, and Testing; storage vault modification; and characterization equipment additions. The SPS will be procured as part of a Department of Energy nationwide common procurement. Specific design crit1460eria for the SPS have been extracted from that contract and are contained in an appendix to this document.

Weiss, E.V.

1997-01-23T23:59:59.000Z

112

DOE handbook: Tritium handling and safe storage  

SciTech Connect

The DOE Handbook was developed as an educational supplement and reference for operations and maintenance personnel. Most of the tritium publications are written from a radiological protection perspective. This handbook provides more extensive guidance and advice on the null range of tritium operations. This handbook can be used by personnel involved in the full range of tritium handling from receipt to ultimate disposal. Compliance issues are addressed at each stage of handling. This handbook can also be used as a reference for those individuals involved in real time determination of bounding doses resulting from inadvertent tritium releases. This handbook provides useful information for establishing processes and procedures for the receipt, storage, assay, handling, packaging, and shipping of tritium and tritiated wastes. It includes discussions and advice on compliance-based issues and adds insight to those areas that currently possess unclear DOE guidance.

NONE

1999-03-01T23:59:59.000Z

113

WASTE HANDLING BUILDING VENTILATION SYSTEM DESCRIPTION DOCUMENT  

SciTech Connect

The Waste Handling Building Ventilation System provides heating, ventilation, and air conditioning (HVAC) for the contaminated, potentially contaminated, and uncontaminated areas of the Monitored Geologic Repository's (MGR) Waste Handling Building (WHB). In the uncontaminated areas, the non-confinement area ventilation system maintains the proper environmental conditions for equipment operation and personnel comfort. In the contaminated and potentially contaminated areas, in addition to maintaining the proper environmental conditions for equipment operation and personnel comfort, the contamination confinement area ventilation system directs potentially contaminated air away from personnel in the WHB and confines the contamination within high-efficiency particulate air (HEPA) filtration units. The contamination confinement areas ventilation system creates airflow paths and pressure zones to minimize the potential for spreading contamination within the building. The contamination confinement ventilation system also protects the environment and the public by limiting airborne releases of radioactive or other hazardous contaminants from the WHB. The Waste Handling Building Ventilation System is designed to perform its safety functions under accident conditions and other Design Basis Events (DBEs) (such as earthquakes, tornadoes, fires, and loss of the primary electric power). Additional system design features (such as compartmentalization with independent subsystems) limit the potential for cross-contamination within the WHB. The system provides status of important system parameters and equipment operation, and provides audible and/or visual indication of off-normal conditions and equipment failures. The Waste Handling Building Ventilation System confines the radioactive and hazardous material within the building such that the release rates comply with regulatory limits. The system design, operations, and maintenance activities incorporate ALARA (as low as is reasonably achievable) principles to maintain personnel radiation doses to all occupational workers below regulatory limits and as low as is reasonably achievable. The Waste Handling Building Ventilation System interfaces with the Waste Handling Building System by being located within the WHB and by maintaining specific pressures, temperatures, and humidity within the building. The system also depends on the WHB for water supply. The system interfaces with the Site Radiological Monitoring System for continuous monitoring of the exhaust air; the Waste Handling Building Fire Protection System for detection of fire and smoke; the Waste Handling Building Electrical System for normal, emergency, and standby power; and the Monitored Geologic Repository Operations Monitoring and Control System for monitoring and control of the system.

P.A. Kumar

2000-06-21T23:59:59.000Z

114

Recommendations for cask features for robotic handling from the Advanced Handling Technology Project  

SciTech Connect

This report describes the current status and recent progress in the Advanced Handling Technology Project (AHTP) initiated to explore the use of advanced robotic systems and handling technologies to perform automated cask handling operations at radioactive waste handling facilities, and to provide guidance to cask designers on the impact of robotic handling on cask design. Current AHTP tasks have developed system mock-ups to investigate robotic manipulation of impact limiters and cask tiedowns. In addition, cask uprighting and transport, using computer control of a bridge crane and robot, were performed to demonstrate the high speed cask transport operation possible under computer control. All of the current AHTP tasks involving manipulation of impact limiters and tiedowns require robotic operations using a torque wrench. To perform these operations, a pneumatic torque wrench and control system were integrated into the tool suite and control architecture of the gantry robot. The use of captured fasteners is briefly discussed as an area where alternative cask design preferences have resulted from the influence of guidance for robotic handling vs traditional operations experience. Specific robotic handling experiences with these system mock-ups highlight a number of continually recurring design principles: (1) robotic handling feasibility is improved by mechanical designs which emphasize operation with limited dexterity in constrained workspaces; (2) clearances, tolerances, and chamfers must allow for operations under actual conditions with consideration for misalignment and imprecise fixturing; (3) successful robotic handling is enhanced by including design detail in representations for model-based control; (4) robotic handling and overall quality assurance are improved by designs which eliminate the use of loose, disassembled parts. 8 refs., 15 figs.

Drotning, W.

1991-02-01T23:59:59.000Z

115

Results from Field Testing of Embedded Air Handling Unit and ...  

Science Conference Proceedings (OSTI)

... Tzone = zone temperature CSP = cooling set point HSP ... types, building uses, and weather conditions based on ... the faults and their impact on the ...

2006-11-13T23:59:59.000Z

116

Handling and Packaging a Potentially Radiologically Contaminated Patient |  

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

Handling and Packaging a Potentially Radiologically Contaminated Handling and Packaging a Potentially Radiologically Contaminated Patient Handling and Packaging a Potentially Radiologically Contaminated Patient The purpose of this procedure is to provide guidance to EMS care providers for properly handling and packaging potentially radiologically contaminated patients. This procedure applies to Emergency Medical Service care providers who respond to a radioactive material transportation incident that involves potentially contaminated injuries. Handling and Packaging a Potentially Radiologically Contaminated Patient.docx More Documents & Publications Pre-Hospital Practices for Handling a Radiologically Contaminated Patient Medical Examiner/Coroner on the Handling of a Body/Human Remains that are Potentially Radiologically Contaminated

117

Water Management in Ash-Handling Systems  

Science Conference Proceedings (OSTI)

In 1980, EPA proposed revisions to the effluent standards and guidelines for fly ash and bottom ash transport systems. This review of utility practices provides a comprehensive account of the operation of and problems experienced in wet handling of bottom and fly ash and suggests areas for further research.

1987-08-24T23:59:59.000Z

118

Safe Handling Of Nuclear Substances Undergraduate Laboratories  

E-Print Network (OSTI)

Safe Handling Of Nuclear Substances Undergraduate Laboratories There are three main hazards associated with working with unsealed sources of nuclear substances. These are: 1. Skin contamination and/or deposition of the nuclear substance in the body 2. Spread of contamination 3. External radiation In teaching

Beaumont, Christopher

119

TEST  

Science Conference Proceedings (OSTI)

This is an abstract. TEST Lorem ipsum dolor sit amet, consectetur adipiscing elit. Cras lacinia dui et est venenatis lacinia. Vestibulum lacus dolor, adipiscing id mattis sit amet, ultricies sed purus. Nulla consectetur aliquet feugiat. Maecenas ips

120

EV America Skid Test Procedure  

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

6 Revision 3 Effective February 1, 2008 Braking Test Prepared by Electric Transportation Applications Prepared by: Date: Derek Peterson...

Note: This page contains sample records for the topic "handling test prepared" 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

History of remote handling at LAMPF  

SciTech Connect

A portable remote-handling system (Monitor) has been developed for performing remote maintenance on radioactive experimental facilities at the Clinton P. Anderson Meson Physics Facility (LAMPF). This system has been continually improved since its implementation in 1976. The present system has performed highly sophisticated tasks in improving and maintaining the LAMPF experimental facility. Unlike conventional hot-cell remote-handling technology, the Monitor system is portable and highly flexible, thereby allowing quick response to unforeseen tasks with minimal planning and/or special tooling. In addition to performing routine maintenance and repairs, the Monitor system is capable of performing major revisions and improvements to current facilities, keeping pace with new experimental requirements.

Grisham, D.L.; Lambert, J.E.

1982-01-01T23:59:59.000Z

122

Fuel handling apparatus for a nuclear reactor  

DOE Patents (OSTI)

Fuel handling apparatus for transporting fuel elements into and out of a nuclear reactor and transporting them within the reactor vessel extends through a penetration in the side of the reactor vessel. A lateral transport device carries the fuel elements laterally within the vessel and through the opening in the side of the vessel, and a reversible lifting device raises and lowers the fuel elements. In the preferred embodiment, the lifting device is supported by a pair of pivot arms.

Hawke, Basil C. (Solana Beach, CA)

1987-01-01T23:59:59.000Z

123

Handling and Packaging a Potentially Radiologically Contaminated Patient |  

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

Handling and Packaging a Potentially Radiologically Contaminated Handling and Packaging a Potentially Radiologically Contaminated Patient Handling and Packaging a Potentially Radiologically Contaminated Patient The purpose of this procedure is to provide guidance to EMS care providers for properly handling and packaging potentially radiologically contaminated patients. This procedure applies to Emergency Medical Service care providers who respond to a radioactive material transportation incident that involves potentially contaminated injuries. Handling and Packaging a Potentially Radiologically Contaminated Patient.docx More Documents & Publications Pre-Hospital Practices for Handling a Radiologically Contaminated Patient Emergency Response to a Transportation Accident Involving Radioactive Material Radioactive Materials Transportation and Incident Response

124

Preparing Your  

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

of third party vendors, enter "international shipping and shopping carts" or similar search terms into an Internet search engine. 52 Preparing Your Business for Global...

125

Shielded Payload Containers Will Enhance the Safety and Efficiency of the DOE's Remote Handled Transuranic Waste Disposal Operations  

Science Conference Proceedings (OSTI)

The Waste Isolation Pilot Plant (WIPP) disposal operation currently employs two different disposal methods: one for Contact Handled (CH) waste and another for Remote Handled (RH) waste. CH waste is emplaced in a variety of payload container configurations on the floor of each disposal room. In contrast, RH waste is packaged into a single type of canister and emplaced in pre-drilled holes in the walls of disposal rooms. Emplacement of the RH waste in the walls must proceed in advance of CH waste emplacement. This poses a significant logistical constraint on waste handling operations by requiring significant coordination between waste characterization and preparations for shipping among the various generators. To improve operational efficiency, the Department of Energy (DOE) is proposing a new waste emplacement process for certain RH waste streams that can be safely managed in shielded containers. RH waste with relatively low gamma-emitting activity would be packaged in lead-lined containers, shipped to WIPP in existing certified transportation packages for CH waste, and emplaced in WIPP among the stacks of CH waste containers on the floor of a disposal room. RH waste with high gamma-emitting activity would continue to be emplaced in the boreholes along the walls. The new RH container appears essentially the same as a nominal 208-liter drum, but is built with about 2.5 cm of lead, sandwiched between thick steel sheet. The top and bottom are made of very thick plate steel, for strengthening the package to meet transportation requirements, and provide similar gamma attenuation. This robust configuration provides an overpack for waste that otherwise would be remotely handled. Up to a 3:1 reduction in number of shipments is projected if RH waste were transported in the proposed shielded containers. This paper describes the container design and testing, as well as the regulatory approach used to meet the requirements that apply to WIPP and its associated transportation system. This paper describes the RH transuranic waste inventory that may be candidates for packaging and emplacement in shielded containers. DOE does not propose to use shielded containers to increase the amount of RH waste allowed at WIPP. DOE's approach to gain approval for the transportation of shielded containers and to secure regulatory approval for use of shielded containers from WIPP regulators is discussed. Finally, the paper describes how DOE proposes to count the waste packaged into shielded containers against the RH waste inventory and how this will comply with the volume and radioactivity limitations imposed in the many and sometimes overlapping regulations that apply to WIPP. (authors)

Nelson, R.A. [U. S. Department of Energy, Carlsbad, New Mexico (United States); White, D.S. [Washington Group International, Carlsbad, New Mexico (United States)

2008-07-01T23:59:59.000Z

126

Advanced Vehicle Testing Activity - Hybrid Electric Vehicle and...  

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

max speed, braking, & handling DOE - Advanced Vehicle Testing Activity Hybrid Electric Vehicle Testing * Fleet and accelerated reliability testing - 6 Honda Insights...

127

Elimination of ``memory`` from sample handling and inlet system of a mass spectrometer  

DOE Patents (OSTI)

This paper describes a method for preparing the sample handling and inlet system of a mass spectrometer for analysis of a subsequent sample following analysis of a previous sample comprising the flushing of the system interior with supercritical CO{sub 2} and venting the interior. The method eliminates the effect of system ``memory`` on the subsequent analysis, especially following persistent samples such as xenon and krypton.

Chastgner, P.

1991-05-08T23:59:59.000Z

128

Human error contribution to nuclear materials-handling events  

E-Print Network (OSTI)

This thesis analyzes a sample of 15 fuel-handling events from the past ten years at commercial nuclear reactors with significant human error contributions in order to detail the contribution of human error to fuel-handling ...

Sutton, Bradley (Bradley Jordan)

2007-01-01T23:59:59.000Z

129

Innovative Methods for Corn Stover Collecting, Handling, Storing and Transporting  

DOE Green Energy (OSTI)

Investigation of innovative methods for collecting, handling, storing, and transporting corn stover for potential use for production of cellulosic ethanol.

Atchison, J. E.; Hettenhaus, J. R.

2003-03-01T23:59:59.000Z

130

Chris Densham T2K Target Remote Handling  

E-Print Network (OSTI)

Chris Densham T2K Target Remote Handling CJ Densham, MD Fitton, M Baldwin, M Woodward Rutherford are handled by remote controlled crane. Concrete shield Horns are shielded by iron and concrete shields A numerical controlled crane is used in the TS. A remote handling machine is attached to this crane. Crane

McDonald, Kirk

131

A sampling device with a capped body and detachable handle  

DOE Patents (OSTI)

The present invention relates to a device for sampling radioactive waste and more particularly to a device for sampling radioactive waste which prevents contamination of a sampled material and the environment surrounding the sampled material. During vitrification of nuclear wastes, it is necessary to remove contamination from the surfaces of canisters filled with radioactive glass. After removal of contamination, a sampling device is used to test the surface of the canister. The one piece sampling device currently in use creates a potential for spreading contamination during vitrification operations. During operations, the one piece sampling device is transferred into and out of the vitrification cell through a transfer drawer. Inside the cell, a remote control device handles the sampling device to wipe the surface of the canister. A one piece sampling device can be contaminated by the remote control device prior to use. Further, the sample device can also contaminate the transfer drawer producing false readings for radioactive material. The present invention overcomes this problem by enclosing the sampling pad in a cap. The removable handle is reused which reduces the amount of waste material.

Jezek, Gerd-Rainer

1997-12-01T23:59:59.000Z

132

System for handling and storing radioactive waste  

DOE Patents (OSTI)

A system and method for handling and storing spent reactor fuel and other solid radioactive waste, including canisters to contain the elements of solid waste, storage racks to hold a plurality of such canisters, storage bays to store these racks in isolation by means of shielded doors in the bays. This system also includes means for remotely positioning the racks in the bays and an access tunnel within which the remotely operated means is located to position a rack in a selected bay. The modular type of these bays will facilitate the construction of additional bays and access tunnel extension.

Anderson, John K. (San Diego, CA); Lindemann, Paul E. (Escondido, CA)

1984-01-01T23:59:59.000Z

133

Safety Advice for Storage and Handling of  

E-Print Network (OSTI)

"This document is intended for information only and sets out advice for the safe storage and handling of anhydrous titanium tetrachloride. The information contained in these guidelines is provided in good faith and, while it is accurate as far as the authors are aware, no representations or warranties are made with regards to its completeness. For guidance on individual circumstances specific advice should be sought and in all cases the applicable national, European and international regulations should always be complied with. No responsibility will be assumed by Cefic in relation to the information

unknown authors

2007-01-01T23:59:59.000Z

134

System for handling and storing radioactive waste  

DOE Patents (OSTI)

A system and method are claimed for handling and storing spent reactor fuel and other solid radioactive waste, including canisters to contain the elements of solid waste, storage racks to hold a plurality of such canisters, storage bays to store these racks in isolation by means of shielded doors in the bays. This system also includes means for remotely positioning the racks in the bays and an access tunnel within which the remotely operated means is located to position a rack in a selected bay. The modular type of these bays will facilitate the construction of additional bays and access tunnel extension.

Anderson, J.K.; Lindemann, P.E.

1982-07-19T23:59:59.000Z

135

National Environmental Policy Act Compliance Strategy for the Remote-Handled Low-level Waste Disposal Facility  

Science Conference Proceedings (OSTI)

The U.S. Department of Energy (DOE) needs to have disposal capability for remote-handled low level waste (LLW) generated at the Idaho National Laboratory (INL) at the time the existing disposal facility is full or must be closed in preparation for final remediation of the INL Subsurface Disposal Area in approximately the year 2017.

Peggy Hinman

2010-10-01T23:59:59.000Z

136

High Level Waste Remote Handling Equipment in the Melter Cave Support Handling System at the Hanford Waste Treatment Plant  

SciTech Connect

Cold war plutonium production led to extensive amounts of radioactive waste stored in tanks at the Department of Energy's (DOE) Hanford site. Bechtel National, Inc. is building the largest nuclear Waste Treatment Plant in the world located at the Department of Energy's Hanford site to immobilize the millions of gallons of radioactive waste. The site comprises five main facilities; Pretreatment, High Level Waste vitrification, Low Active Waste vitrification, an Analytical Lab and the Balance of Facilities. The pretreatment facilities will separate the high and low level waste. The high level waste will then proceed to the HLW facility for vitrification. Vitrification is a process of utilizing a melter to mix molten glass with radioactive waste to form a stable product for storage. The melter cave is designated as the High Level Waste Melter Cave Support Handling System (HSH). There are several key processes that occur in the HSH cell that are necessary for vitrification and include: feed preparation, mixing, pouring, cooling and all maintenance and repair of the process equipment. Due to the cell's high level radiation, remote handling equipment provided by PaR Systems, Inc. is required to install and remove all equipment in the HSH cell. The remote handling crane is composed of a bridge and trolley. The trolley supports a telescoping tube set that rigidly deploys a TR 4350 manipulator arm with seven degrees of freedom. A rotating, extending, and retracting slewing hoist is mounted to the bottom of the trolley and is centered about the telescoping tube set. Both the manipulator and slewer are unique to this cell. The slewer can reach into corners and the manipulator's cross pivoting wrist provides better operational dexterity and camera viewing angles at the end of the arm. Since the crane functions will be operated remotely, the entire cell and crane have been modeled with 3-D software. Model simulations have been used to confirm operational and maintenance functional and timing studies throughout the design process. Since no humans can go in or out of the cell, there are several recovery options that have been designed into the system including jack-down wheels for the bridge and trolley, recovery drums for the manipulator hoist, and a wire rope cable cutter for the slewer jib hoist. If the entire crane fails in cell, the large diameter cable reel that provides power, signal, and control to the crane can be used to retrieve the crane from the cell into the crane maintenance area. (authors)

Bardal, M.A. [PaR Systems, Inc., Shoreview, MN (United States); Darwen, N.J. [Bechtel National, Inc., Richland, WA (United States)

2008-07-01T23:59:59.000Z

137

Specimen Preparation  

Science Conference Proceedings (OSTI)

Table 1   Standard preparation conditions for structural ceramics (e.g., Si 3 N 4 , AlN, SiC and Al 2 O 3 ), semiautomatic

138

Fuel handling system for a nuclear reactor  

DOE Patents (OSTI)

A pool type nuclear fission reactor has a core, with a plurality of core elements and a redan which confines coolant as a hot pool at a first end of the core separated from a cold pool at a second end of the core by the redan. A fuel handling system for use with such reactors comprises a core element storage basket located outside of the redan in the cold pool. An access passage is formed in the redan with a gate for opening and closing the passage to maintain the temperature differential between the hot pool and the cold pool. A mechanism is provided for opening and closing the gate. A lifting arm is also provided for manipulating the fuel core elements through the access passage between the storage basket and the core when the redan gate is open.

Saiveau, James G. (Hickory Hills, IL); Kann, William J. (Park Ridge, IL); Burelbach, James P. (Glen Ellyn, IL)

1986-01-01T23:59:59.000Z

139

Primer on tritium safe handling practices  

Science Conference Proceedings (OSTI)

This Primer is designed for use by operations and maintenance personnel to improve their knowledge of tritium safe handling practices. It is applicable to many job classifications and can be used as a reference for classroom work or for self-study. It is presented in general terms for use throughout the DOE Complex. After reading it, one should be able to: describe methods of measuring airborne tritium concentration; list types of protective clothing effective against tritium uptake from surface and airborne contamination; name two methods of reducing the body dose after a tritium uptake; describe the most common method for determining amount of tritium uptake in the body; describe steps to take following an accidental release of airborne tritium; describe the damage to metals that results from absorption of tritium; explain how washing hands or showering in cold water helps reduce tritium uptake; and describe how tritium exchanges with normal hydrogen in water and hydrocarbons.

Not Available

1994-12-01T23:59:59.000Z

140

Method and system rapid piece handling  

DOE Patents (OSTI)

The advent of high-speed fabric cutters has made necessary the development of automated techniques for the collection and sorting of garment pieces into collated piles of pieces ready for assembly. The present invention enables a new method for such handling and sorting of garment parts, and to apparatus capable of carrying out this new method. The common thread is the application of computer-controlled shuttling bins, capable of picking up a desired piece of fabric and dropping it in collated order for assembly. Such apparatus with appropriate computer control relieves the bottleneck now presented by the sorting and collation procedure, thus greatly increasing the overall rate at which garments can be assembled.

Spletzer, Barry L. (9504 Arvilla, NE, Albuquerque, NM 87111)

1996-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "handling test prepared" 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

METHOD AND APPARATUS FOR HANDLING RADIOACTIVE PRODUCTS  

DOE Patents (OSTI)

A device is described for handling fuel elements being discharged from a nuclear reactor. The device is adapted to be disposed beneath a reactor within the storage canal for spent fuel elements. The device is comprised essentially of a cylinder pivotally mounted to a base for rotational motion between a vertical position. where the mouth of the cylinder is in the top portion of the container for receiving a fuel element discharged from a reactor into the cylinder, and a horizontal position where the mouth of the cylinder is remote from the top portion of the container and the fuel element is discharged from the cylinder into the storage canal. The device is operated by hydraulic pressure means and is provided with a means to prevent contaminated primary liquid coolant in the reactor system from entering the storage canal with the spent fuel element.

Nicoll, D.

1959-02-24T23:59:59.000Z

142

Welding Robot and Remote Handling System for the Yucca Mountain Waste Package Closure System  

SciTech Connect

In preparation for the license application and construction of a repository for housing the nation's spent nuclear fuel and high-level waste in Yucca Mountain, the Idaho National Laboratory (INL) has been charged with preparing a mock-up of a full-scale prototype system for sealing the waste packages (WP). Three critical pieces of the closure room include two PaR Systems TR4350 Telerobotic Manipulators and a PaR Systems XR100 Remote Handling System (RHS). The TR4350 Manipulators are 6-axis programmable robots that will be used to weld the WP lids and purge port cap as well as conduct nondestructive examinations. The XR100 Remote Handling System is a 4-axis programmable robot that will be used to transport the WP lids and process tools to the WP for operations and remove equipment for maintenance. The welding and RHS robots will be controlled using separate PaR 5/21 CIMROC Controllers capable of complex motion control tasks. A tele-operated PaR 4350 Manipulator will also be provided with the XR100 Remote Handling System. It will be used for maintenance and associated activities within the closure room. (authors)

Barker, M.E.; Holt, T.E.; LaValle, D.R. [PaR Systems, Inc., Shoreview, MN (United States); Pace, D.P.; Croft, K.M.; Shelton-Davis, C.V. [Battelle Energy Alliance, LLC/Idaho National Laboratory, Idaho Falls, ID (United States)

2008-07-01T23:59:59.000Z

143

PRE-HOSPITAL PRACTICES FOR HANDLING A RADIOLOGICALLY CONTAMINATED PATIENT  

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

Pre-hospital Practices for Handling a Pre-hospital Practices for Handling a Pre-hospital Practices for Handling a Pre-hospital Practices for Handling a Pre-hospital Practices for Handling a Pre-hospital Practices for Handling a Radiologically Contaminated Patient Radiologically Contaminated Patient Radiologically Contaminated Patient Radiologically Contaminated Patient Radiologically Contaminated Patient DISCLAIMER DISCLAIMER DISCLAIMER DISCLAIMER DISCLAIMER Viewing this video and completing the enclosed printed study material do not by themselves provide sufficient skills to safely engage in or perform duties related to emergency response to a transportation accident involving radioactive material. Meeting that goal is beyond the scope of this video and requires either additional specific areas of competency or more hours of training

144

Report Preparation  

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

been completed (as described in ETA-GAC002, "Control of Test Conduct") prior to the report being formally issued. 4.2 All necessary test documentation has been completed,...

145

Nuclear Maintenance Applications Center: Material Handling Application Guide  

Science Conference Proceedings (OSTI)

Although the majority of the material handling activities at nuclear power plant sites are similar to the material handling activities in many other industries, there are several differences unique to the nuclear power industry. This guide to material handling equipment and its safe and effective operation at nuclear plants covers basic common practices while taking into account those unique differences. Recent industry experiences provide context for the guidance in the report.

2007-11-30T23:59:59.000Z

146

Nuclear Maintenance Applications Center: Material Handling Application Guide  

Science Conference Proceedings (OSTI)

BackgroundDuring 2005 and 2006, there were nine Institute of Nuclear Power Operations (INPO) operating events (OEs) from material handling incidents. A fatality occurred at Browns Ferry on Oct. 1, 2005, when a small article radiation monitor overturned while being moved on a material handling cart (INPO OE21844).More than 50 serious OEs concerning material handling activities have occurred in the past 10 years. The majority of these incidents involved the ...

2012-09-28T23:59:59.000Z

147

TITLE III EVALUATION REPORT FOR THE MATERIAL AND PERSONNEL HANDLING SYSTEM  

Science Conference Proceedings (OSTI)

This Title III Evaluation Report (TER) provides the results of an evaluation that was conducted on the Material and Personnel Handling System. This TER has been written in accordance with the ''Technical Document Preparation Plan for the Mined Geologic Disposal System Title III Evaluation Reports'' (BA0000000-01717-4600-00005 REV 03). The objective of this evaluation is to provide recommendations to ensure consistency between the technical baseline requirements, baseline design, and the as-constructed Material and Personnel Handling System. Recommendations for resolving discrepancies between the as-constructed system, the technical baseline requirements, and the baseline design are included in this report. Cost and Schedule estimates are provided for all recommended modifications.

T. A. Misiak

1998-05-21T23:59:59.000Z

148

Conceptual Design Report for the Remote-Handled Low-Level Waste Disposal Project  

Science Conference Proceedings (OSTI)

This conceptual design report addresses development of replacement remote-handled low-level waste disposal capability for the Idaho National Laboratory. Current disposal capability at the Radioactive Waste Management Complex is planned until the facility is full or until it must be closed in preparation for final remediation (approximately at the end of Fiscal Year 2017). This conceptual design report includes key project assumptions; design options considered in development of the proposed onsite disposal facility (the highest ranked alternative for providing continued uninterrupted remote-handled low level waste disposal capability); process and facility descriptions; safety and environmental requirements that would apply to the proposed facility; and the proposed cost and schedule for funding, design, construction, and operation of the proposed onsite disposal facility.

Lisa Harvego; David Duncan; Joan Connolly; Margaret Hinman; Charles Marcinkiewicz; Gary Mecham

2011-03-01T23:59:59.000Z

149

Conceptual Design Report for the Remote-Handled Low-Level Waste Disposal Project  

SciTech Connect

This conceptual design report addresses development of replacement remote-handled low-level waste disposal capability for the Idaho National Laboratory. Current disposal capability at the Radioactive Waste Management Complex is planned until the facility is full or until it must be closed in preparation for final remediation (approximately at the end of Fiscal Year 2017). This conceptual design report includes key project assumptions; design options considered in development of the proposed onsite disposal facility (the highest ranked alternative for providing continued uninterrupted remote-handled low level waste disposal capability); process and facility descriptions; safety and environmental requirements that would apply to the proposed facility; and the proposed cost and schedule for funding, design, construction, and operation of the proposed onsite disposal facility.

David Duncan

2011-05-01T23:59:59.000Z

150

Conceptual Design Report for Remote-Handled Low-Level Waste Disposal Facility  

SciTech Connect

This conceptual design report addresses development of replacement remote-handled low-level waste disposal capability for the Idaho National Laboratory. Current disposal capability at the Radioactive Waste Management Complex is planned until the facility is full or until it must be closed in preparation for final remediation (approximately at the end of Fiscal Year 2017). This conceptual design report includes key project assumptions; design options considered in development of the proposed onsite disposal facility (the highest ranked alternative for providing continued uninterrupted remote-handled low level waste disposal capability); process and facility descriptions; safety and environmental requirements that would apply to the proposed facility; and the proposed cost and schedule for funding, design, construction, and operation of the proposed onsite disposal facility.

Lisa Harvego; David Duncan; Joan Connolly; Margaret Hinman; Charles Marcinkiewicz; Gary Mecham

2010-10-01T23:59:59.000Z

151

An Evaluation of the Total Cost of Ownership of Fuel Cell-Powered Material Handling Equipment  

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

Evaluation of the Total Cost Evaluation of the Total Cost of Ownership of Fuel Cell- Powered Material Handling Equipment Todd Ramsden National Renewable Energy Laboratory Technical Report NREL/TP-5600-56408 April 2013 NREL is a national laboratory of the U.S. Department of Energy, Office of Energy Efficiency & Renewable Energy, operated by the Alliance for Sustainable Energy, LLC. National Renewable Energy Laboratory 15013 Denver West Parkway Golden, Colorado 80401 303-275-3000 * www.nrel.gov Contract No. DE-AC36-08GO28308 An Evaluation of the Total Cost of Ownership of Fuel Cell- Powered Material Handling Equipment Todd Ramsden National Renewable Energy Laboratory Prepared under Task No. HT12.8610 Technical Report NREL/TP-5600-56408

152

Remote-Handled Transuranic Content Codes  

SciTech Connect

The Remote-Handled Transuranic (RH-TRU) Content Codes (RH-TRUCON) document describes the inventory of RH-TRU waste within the transportation parameters specified by the Remote-Handled Transuranic Waste Authorized Methods for Payload Control (RH-TRAMPAC).1 The RH-TRAMPAC defines the allowable payload for the RH-TRU 72-B. This document is a catalog of RH-TRU 72-B authorized contents by site. A content code is defined by the following components: • A two-letter site abbreviation that designates the physical location of the generated/stored waste (e.g., ID for Idaho National Laboratory [INL]). The site-specific letter designations for each of the sites are provided in Table 1. • A three-digit code that designates the physical and chemical form of the waste (e.g., content code 317 denotes TRU Metal Waste). For RH-TRU waste to be transported in the RH-TRU 72-B, the first number of this three-digit code is “3.” The second and third numbers of the three-digit code describe the physical and chemical form of the waste. Table 2 provides a brief description of each generic code. Content codes are further defined as subcodes by an alpha trailer after the three-digit code to allow segregation of wastes that differ in one or more parameter(s). For example, the alpha trailers of the subcodes ID 322A and ID 322B may be used to differentiate between waste packaging configurations. As detailed in the RH-TRAMPAC, compliance with flammable gas limits may be demonstrated through the evaluation of compliance with either a decay heat limit or flammable gas generation rate (FGGR) limit per container specified in approved content codes. As applicable, if a container meets the watt*year criteria specified by the RH-TRAMPAC, the decay heat limits based on the dose-dependent G value may be used as specified in an approved content code. If a site implements the administrative controls outlined in the RH-TRAMPAC and Appendix 2.4 of the RH-TRU Payload Appendices, the decay heat or FGGR limits based on a 10-day shipping period (rather than the standard 60-day shipping period) may be used as specified in an approved content code.

Washington TRU Solutions

2006-12-01T23:59:59.000Z

153

Handbook for Handling, Storing, and Dispensing E85  

DOE Green Energy (OSTI)

A guidebook that contains information about EPAct alternative fuels regulations for fleets, flexible fuel vehicles, E85 properties and specifications, and E85 handling and storage guidelines.

Not Available

2002-04-01T23:59:59.000Z

154

Production and Handling Slide 1: The Uranium Fuel Cycle  

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

and Handling The Uranium Fuel Cycle Skip Presentation Navigation Next Slide Last Presentation Table of Contents The Uranium Fuel Cycle Refer to caption below for image...

155

LM Records Handling System-Fernald Historical Records System...  

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

Management, LM Records Handling System (LMRHS01) - Rocky Flats Environmental Records Database, Office of Legacy Management Energy.gov Careers & Internships For Staff & Contractors...

156

Biodiesel Handling and Use Guide: Fourth Edition (Revised)  

DOE Green Energy (OSTI)

Intended for those who blend, distribute, and use biodiesel and its blends, this guide contains procedures for handling and using these fuels.

Not Available

2009-01-01T23:59:59.000Z

157

Handbook for Handling, Storing, and Dispensing E85  

DOE Green Energy (OSTI)

Guidebook contains information about EPAct alternative fuels regulations for fleets, flexible fuel vehicles, E85 properties and specifications, and E85 handling and storage guidelines.

Not Available

2008-04-01T23:59:59.000Z

158

Unit load and material handling considerations in facility layout design  

E-Print Network (OSTI)

Dec 1, 2002 ... In this paper, the integration of unit load and material handling considerations in facility layout design is presented. This integration is based on ...

159

Chromoblastomycosis associated with in a carpenter handling exotic woods  

E-Print Network (OSTI)

in a carpenter handling exotic woods Nuno Menezes 1 , Pauloas saprophytes in the soil, wood and vegetation [ 3 ]. Theyare normally made of tropical wood [ 9 ]. The inoculation

2008-01-01T23:59:59.000Z

160

Robust telerobotics - an integrated system for waste handling, characterization and sorting  

Science Conference Proceedings (OSTI)

The Mixed Waste Management Facility (MWMF) at the Lawrence Livermore National Laboratory was designed to serve as a national testbed to demonstrate integrated technologies for the treatment of low-level organic mixed waste at a pilot-plant scale. Pilot-scale demonstration serves to bridge the gap between mature, bench-scale proven technologies and full-scale treatment facilities by providing the infrastructure needed to evaluate technologies in an integrated, front-end to back-end facility. Consistent with the intent to focus on technologies that are ready for pilot scale deployment, the front-end handling and feed preparation of incoming waste material has been designed to demonstrate the application of emerging robotic and remotely operated handling systems. The selection of telerobotics for remote handling in MWMF was made based on a number of factors - personnel protection, waste generation, maturity, cost, flexibility and extendibility. Telerobotics, or shared control of a manipulator by an operator and a computer, provides the flexibility needed to vary the amount of automation or operator intervention according to task complexity. As part of the telerobotics design effort, the technical risk of deploying the technology was reduced through focused developments and demonstrations. The work involved integrating key tools (1) to make a robust telerobotic system that operates at speeds and reliability levels acceptable to waste handling operators and, (2) to demonstrate an efficient operator interface that minimizes the amount of special training and skills needed by the operator. This paper describes the design and operation of the prototype telerobotic waste handling and sorting system that was developed for MWMF.

Couture, S.A.; Hurd, R.L.; Wilhelmsen, K.C.

1997-01-01T23:59:59.000Z

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


161

ITER Engineering Design Activities -R & DITER-In-Vessel Remote Handling  

E-Print Network (OSTI)

ITER Engineering Design Activities - R & DITER- In-Vessel Remote Handling Blanket Module Remote Handling Project (L-6) Divertor Remote Handling Project (L-7) Objective To develop and demonstrate handling equipment, port handling equipment, auxiliary remote handling tools and a blanket mockup structure

162

Prepared Remarks  

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

Prepared Prepared Remarks of Brian Forshaw Connecticut Municipal Electric Energy Cooperative At U.S. DOE Workshop on Transmission Congestion Hartford, Connecticut July 9,2008 The Connecticut Municipal Electric Energy Cooperative was created by the publicly-owned electric systems in the State of Connecticut to enable the municipal systems to provide electric service to their customers at the lowest reasonable cost. Currently, CMEEC provides full requirements wholesale electric service to the State's eight public power systems as well as the Mohegan Tribal Utility Authority. As Director of Energy Markets, I am responsible for strategic planning activities and analysis of the impacts that wholesale markets will have on the municipal electric utilities. My responsibilities also include representing CMEEC in the ISO-NE stakeholder process, including the ISO-NE technical committees.

163

Mission Need Statement for the Idaho National Laboratory Remote-Handled Low-Level Waste Disposal Project  

SciTech Connect

The Idaho National Laboratory proposes to establish replacement remote-handled low-level waste disposal capability to meet Nuclear Energy and Naval Reactors mission-critical, remote-handled low-level waste disposal needs beyond planned cessation of existing disposal capability at the end of Fiscal Year 2015. Remote-handled low-level waste is generated from nuclear programs conducted at the Idaho National Laboratory, including spent nuclear fuel handling and operations at the Naval Reactors Facility and operations at the Advanced Test Reactor. Remote-handled low-level waste also will be generated by new programs and from segregation and treatment (as necessary) of remote-handled scrap and waste currently stored in the Radioactive Scrap and Waste Facility at the Materials and Fuels Complex. Replacement disposal capability must be in place by Fiscal Year 2016 to support uninterrupted Idaho operations. This mission need statement provides the basis for the laboratory’s recommendation to the Department of Energy to proceed with establishing the replacement remote-handled low-level waste disposal capability, project assumptions and constraints, and preliminary cost and schedule information for developing the proposed capability. Without continued remote-handled low-level waste disposal capability, Department of Energy missions at the Idaho National Laboratory would be jeopardized, including operations at the Naval Reactors Facility that are critical to effective execution of the Naval Nuclear Propulsion Program and national security. Remote-handled low-level waste disposal capability is also critical to the Department of Energy’s ability to meet obligations with the State of Idaho.

Lisa Harvego

2009-06-01T23:59:59.000Z

164

Reagent Storage and Handling for SCR and SNCR Systems  

Science Conference Proceedings (OSTI)

As utilities move to post-combustion nitrogen oxides (NOx) control technologies, the need to understand reagent storage and handling requirements for these systems increases. This report reviews various approaches to the storage and handling of anhydrous ammonia, aqueous ammonia, and urea. Systems that convert urea to ammonia also are included.

2002-05-30T23:59:59.000Z

165

HANDLING FRESH FISH REFRIGERATION OF FISH -PART 2  

E-Print Network (OSTI)

(Fishery Leaflet 427) Cold-Storage Design and Refrigeration Equipment Part 3 (Fisher y Leaflet 429) FactorsHANDLING FRESH FISH REFRIGERATION OF FISH - PART 2 UNITED STATES DEPARTMENT OF THE INTERIOR FISH 428 Washington 25, D, C. December 1956 REFRIGERATION OF FISH - PART TWO HANDLING FRESH FISH By Charles

166

MERCURY HANDLING FOR THE TARGET SYSTEM FOR A MUON COLLIDER  

E-Print Network (OSTI)

Cryostat 1. Remote handling The high radiation levels and presence of hazardous, ac- tivated mercury vaporsMERCURY HANDLING FOR THE TARGET SYSTEM FOR A MUON COLLIDER Van Graves , ORNL, Oak Ridge, TN 37830 placement within the Shielding Module in a remote environment. · Providing double containment of the mercury

McDonald, Kirk

167

Integrative path planning and motion control for handling large components  

Science Conference Proceedings (OSTI)

For handling large components a large workspace and high precision are required. In order to simplify the path planning for automated handling systems, this task can be divided into global, regional and local motions. Accordingly, different types of ... Keywords: integrative production, motion control, path planning, robotic assembly application

Rainer Müller; Martin Esser; Markus Janssen

2011-12-01T23:59:59.000Z

168

Dynamic manipulation inspired by the handling of a pizza peel  

Science Conference Proceedings (OSTI)

This paper discusses dynamic manipulation inspired by the handling mechanism of a pizza chef. The chef handles a tool called "pizza peel," where a plate is attached at the tip of a bar, and he remotely manipulates a pizza on the plate. We found that ... Keywords: dynamic manipulation, high-speed robot, robot skill

Mitsuru Higashimori; Keisuke Utsumi; Yasutaka Omoto; Makoto Kaneko

2009-08-01T23:59:59.000Z

169

An apparatus for remotely handling components  

DOE Patents (OSTI)

The inventive apparatus for remotely handling barlike components which define a longitudinal direction includes a gripper mechanism for gripping the component including first and second gripper members longitudinally fixedly spaced from each other and oriented parallel to each other in planes transverse to the longitudinal direction. Each gripper member includes a jaw having at least one V-groove with opposing surfaces intersecting at a base and extending radially relative to the longitudinal direction for receiving the component in an open end between the opposing surfaces. The V-grooves on the jaw plate of t he first and second gripper members are aligned in the longitudinal direction to support the component in the first and second gripper members. A jaw is rotatably mounted on and a part of each of the first and second gripper members for selectively assuming a retracted mode in which the open end of the V-groove is unobstructed and active mode in which the jaw spans the open end of the V-groove in the first and second gripper members. The jaw has a locking surface for contacting the component in the active mode to secure the component between the locking surface of the jaw and the opposing surfaces of the V-groove. The locking surface has a plurality of stepped portions, each defining a progressively decreasing radial distance between the base of the V-groove and the stepped portion opposing the base to accommodate varying sizes of components. In a preferred embodiment, the apparatus also includes a control mechanism for remotely controlling movement of the jaw in the locking mode to assume one of a plurality of locking positions corresponding to positioning one of the stepped portions opposite the base.

Szkrybalo, G.A.; Griffin, D.L.

1992-12-31T23:59:59.000Z

170

Pre-Hospital Practices for Handling a Radiologically Contaminated Patient |  

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

Pre-Hospital Practices for Handling a Radiologically Contaminated Pre-Hospital Practices for Handling a Radiologically Contaminated Patient Pre-Hospital Practices for Handling a Radiologically Contaminated Patient The purpose of this User's Guide is to provide instructors with an overview of the key points covered in the video. The Student Handout portion of this Guide is designed to assist the instructor in reviewing those points with students. The Student Handout should be distributed to students after the video is shown and the instructor should use the Guide to facilitate a discussion on key activities and duties at the scene. PRE-HOSPITAL PRACTICES FOR HANDLING A RADIOLOGICALLY CONTAMINATED PATIENT More Documents & Publications Emergency Response to a Transportation Accident Involving Radioactive Material Handling and Packaging a Potentially Radiologically Contaminated Patient

171

T-625: Opera Frameset Handling Memory Corruption Vulnerability | Department  

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

5: Opera Frameset Handling Memory Corruption Vulnerability 5: Opera Frameset Handling Memory Corruption Vulnerability T-625: Opera Frameset Handling Memory Corruption Vulnerability May 18, 2011 - 3:05pm Addthis PROBLEM: A vulnerability has been reported in Opera, which can be exploited by malicious people to compromise a user's system. PLATFORM: Opera versions prior to 11.11 ABSTRACT: The vulnerability is caused due to an error when handling certain frameset constructs during page unloading and can be exploited to corrupt memory via a specially crafted web page. reference LINKS: Secunia Advisory: SA44611 Opera Knowledge Base Opera 11.11 for Windows Opera Download Opera Mobile IMPACT ASSESSMENT: High Discussion: Framesets allow web pages to hold other pages inside them. Certain frameset constructs are not handled correctly when the page is unloaded, causing a

172

Conceptual design report, plutonium stabilization and handling,project W-460  

SciTech Connect

Project W-460, Plutonium Stabilization and Handling, encompasses procurement and installation of a Stabilization and Packaging System (SPS) to oxidize and package for long term storage remaining plutonium-bearing special nuclear materials currently in inventory at the Plutonium Finishing Plant (PFP), and modification of vault equipment to allow storage of resulting packages of stabilized SNM for up to fifty years. This Conceptual Design Report (CDR) provides conceptual design details for the vault modification, site preparation and site interface with the purchased SPS. Two concepts are described for vault configuration; acceleration of this phase of the project did not allow completion of analysis which would clearly identify a preferred approach.

Weiss, E.V.

1997-03-06T23:59:59.000Z

173

Remote-Handled Transuranic Content Codes  

SciTech Connect

The Remote-Handled Transuranic (RH-TRU) Content Codes (RH-TRUCON) document representsthe development of a uniform content code system for RH-TRU waste to be transported in the 72-Bcask. It will be used to convert existing waste form numbers, content codes, and site-specificidentification codes into a system that is uniform across the U.S. Department of Energy (DOE) sites.The existing waste codes at the sites can be grouped under uniform content codes without any lossof waste characterization information. The RH-TRUCON document provides an all-encompassing|description for each content code and compiles this information for all DOE sites. Compliance withwaste generation, processing, and certification procedures at the sites (outlined in this document foreach content code) ensures that prohibited waste forms are not present in the waste. The contentcode gives an overall description of the RH-TRU waste material in terms of processes and|packaging, as well as the generation location. This helps to provide cradle-to-grave traceability ofthe waste material so that the various actions required to assess its qualification as payload for the72-B cask can be performed. The content codes also impose restrictions and requirements on themanner in which a payload can be assembled.The RH-TRU Waste Authorized Methods for Payload Control (RH-TRAMPAC), Appendix 1.3.7of the 72-B Cask Safety Analysis Report (SAR), describes the current governing procedures|applicable for the qualification of waste as payload for the 72-B cask. The logic for this|classification is presented in the 72-B Cask SAR. Together, these documents (RH-TRUCON,|RH-TRAMPAC, and relevant sections of the 72-B Cask SAR) present the foundation and|justification for classifying RH-TRU waste into content codes. Only content codes described in thisdocument can be considered for transport in the 72-B cask. Revisions to this document will be madeas additional waste qualifies for transport. |Each content code uniquely identifies the generated waste and provides a system for tracking theprocess and packaging history. Each content code begins with a two-letter site abbreviation thatindicates the shipper of the RH-TRU waste. The site-specific letter designations for each of the|DOE sites are provided in Table 1. Not all of the sites listed in Table 1 have generated/stored RH-|TRU waste.

Washington TRU Solutions

2001-08-01T23:59:59.000Z

174

Siting Study for the Remote-Handled Low-Level Waste Disposal Project  

Science Conference Proceedings (OSTI)

The U.S. Department of Energy has identified a mission need for continued disposal capacity for remote-handled low-level waste (LLW) generated at the Idaho National Laboratory (INL). An alternatives analysis that was conducted to evaluate strategies to achieve this mission need identified two broad options for disposal of INL generated remote-handled LLW: (1) offsite disposal and (2) onsite disposal. The purpose of this study is to identify candidate sites or locations within INL boundaries for the alternative of an onsite remote handled LLW disposal facility and recommend the highest-ranked locations for consideration in the National Environmental Policy Act process. The study implements an evaluation based on consideration of five key elements: (1) regulations, (2) key assumptions, (3) conceptual design, (4) facility performance, and (5) previous INL siting study criteria, and uses a five-step process to identify, screen, evaluate, score, and rank 34 separate sites located across INL. The result of the evaluation is identification of two recommended alternative locations for siting an onsite remote-handled LLW disposal facility. The two alternative locations that best meet the evaluation criteria are (1) near the Advanced Test Reactor Complex and (2) west of the Idaho Comprehensive Environmental Response, Compensation, and Liability Act Disposal Facility.

Lisa Harvego; Joan Connolly; Lance Peterson; Brennon Orr; Bob Starr

2010-10-01T23:59:59.000Z

175

Prepared by  

E-Print Network (OSTI)

over additional byproduct material. This new byproduct material now also includes naturally occurring materials, such as discrete sources of Radium-226, and accelerator-produced radioactive materials (NARM). This revision of NUREG-1556, Vol. 13, adds guidance needed to license commercial radiopharmacies as a result of the regulatory changes made by the EPAct and the NARM rule, “Requirements for Expanded Definition of Byproduct Material.” This guidance document contains information that is intended to assist applicants for commercial radiopharmacy licenses in preparing their license applications. In particular, it describes the type of information needed to complete NRC Form 313, “Application for Materials License. ” This document both describes the methods acceptable to NRC license reviewers in implementing the regulations and the techniques used by the reviewers in evaluating the application to determine if the proposed activities are acceptable for licensing purposes. Paperwork Reduction Act Statement

Commercial Radiopharmacy Licenses; D. E. White; J. F. Katanic; D. B. Howe

2007-01-01T23:59:59.000Z

176

Prepared by:  

E-Print Network (OSTI)

report was prepared as an account of work sponsored by an agency of the United States Government. Neither the United States Government nor any agency thereof, nor any of their employees, makes any warranty, express or implied, or assumes any legal liability or responsibility for the accuracy, completeness, or usefulness of any information, apparatus, product, or process disclosed, or represents that its use would not infringe privately owned rights. Reference therein to any specific commercial product, process, or service by trade name, trademark, manufacturer, or otherwise does not necessarily constitute or imply its endorsement, recommendation, or favoring by the United States Government or any agency thereof. The views and opinions of authors expressed therein do not necessarily state or reflect those of the United States Government

Thermoelectric Plant Technologies; Phil Dipietro; Kristin Gerdes; Christopher Nichols

2008-01-01T23:59:59.000Z

177

Prepared by:  

E-Print Network (OSTI)

report was prepared as an account of work sponsored by an agency of the United States Government. Neither the United States Government nor any agency thereof, nor any of their employees, makes any warranty, express or implied, or assumes any legal liability or responsibility for the accuracy, completeness, or usefulness of any information, apparatus, product, or process disclosed, or represents that its use would not infringe privately owned rights. Reference therein to any specific commercial product, process, or service by trade name, trademark, manufacturer, or otherwise does not necessarily constitute or imply its endorsement, recommendation, or favoring by the United States Government or any agency thereof. The views and opinions of authors expressed therein do not necessarily state or reflect those of the United States Government or any agency thereof. Beluga Coal Gasification Feasibility Study

Brent Sheets; Robert Chaney

2006-01-01T23:59:59.000Z

178

Prepared by:  

E-Print Network (OSTI)

report was prepared as an account of work sponsored by an agency of the United States government. Neither the United States government nor any agency thereof, nor any of their employees, subcontractors, or affiliated partners makes any warranty, express or implied, or assumes any legal liability or responsibility for the accuracy, completeness, or usefulness of any information, apparatus, product, or process disclosed, or represents that its use would not infringe privately owned rights. Reference herein to any specific commercial product, process, or service by trade name, trademark, manufacturer, or otherwise does not necessarily constitute or imply its endorsement, recommendation, or favoring by the United States government or any agency thereof. The views and opinions of authors expressed herein do not necessarily state or reflect those of the United States government or any agency thereof. Available electronically at

Philip Kerrigan; In Paper; Philip Kerrigan

2012-01-01T23:59:59.000Z

179

Prepared for  

E-Print Network (OSTI)

This report was prepared as an account of work sponsored by an agency of the United States Government. Neither the United States Government nor any agency thereof, nor Battelle Memorial Institute, nor any of their employees, makes any warranty, express or implied, or assumes any legal liability or responsibility for the accuracy, completeness, or usefulness of any information, apparatus, product, or process disclosed, or represents that its use would not infringe privately owned rights. Reference herein to any specific commercial product, process, or service by trade name, trademark, manufacturer, or otherwise does not necessarily constitute or imply its endorsement, recommendation, or favoring by the United States Government or any agency thereof, or Battelle Memorial Institute. The views and opinions of authors expressed herein do not necessarily state or reflect those of the United States Government or any agency thereof. This effort is based on the continuation of work initiated under a collaborative “National Laboratory-University-industrial Three-party Program ” namely:

R. W. Goles; G. A. Whyatt; R. A. Merrill; D. K. Seiler; C. J. Freeman; D. A. Lamar; G. B. Josephson; R. W. Goles; G. A. Whyatt; R. A. Merrill; D. K. Seiler; C. J. Freeman; D. A. Lamar; G. B. Josephson

1998-01-01T23:59:59.000Z

180

Economizer Applications in Dual-Duct Air-Handling Units  

E-Print Network (OSTI)

This paper provides analytical tools and engineering methods to evaluate the feasibility of the economizer for dual-duct air-handling units. The results show that the economizer decreases cooling energy consumption without heating energy penalties for dual-fan, dual-duct air-handling units. The economizer has significant heating energy penalties for single-fan, dual-duct air-handling units. The penalties are higher than the cooling energy savings when the cold airflow is less than the hot airflow. Detailed engineering analyses are required to evaluate the feasibility of the economizer for single-fan, dual-duct systems.

Joo, I.; Liu, M.

2002-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "handling test prepared" 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

Pig shipping container test sequence  

SciTech Connect

This test plan outlines testing of the integrity of the pig shipping container. It is divided into four sections: (1) drop test requirements; (2) test preparations; (3) perform drop test; and (4) post-test examination.

Adkins, H.E. Jr.

1995-01-13T23:59:59.000Z

182

RW Prepared  

Office of Legacy Management (LM)

r tz r tz s /r;1 RW Prepared by Oak Ridge Associated Un iversities Prepared for Division of Remedial Action Projects U.S. Department of Energy C O M P R E H E N S I V E R A D I O L O G I C A L S U R V E Y O F F - S I T E P R O P E R T Y B N I A G A R A F A L L S S T O R A G E S I T E L E W I S T O N , N E W Y O R K J . D . B E R G E R R a d i o l o g i c a l S i t e A s s e s s m e n t p r o g r a m Manpower Education, Research, and Training Division FINAL REPORT M a y 1 9 8 4 COMPREEENSIVE RADIOLOGICAL SURVEY OFF-SITE PROPERTY B NIAGARA FAI"LS STORAGE SITE LE"I{ISTON, NE}I YoRK u. s. F o r m e r l y U t i l i z e d P r e p a r e d f o r Department of EnergY as Dart of the S i t e s - - R e m e d i a l A c t i o n P r o g r a u J . D . B e r g e r P r o j e c t J. Burden* R . D . C o n d r a J . S . E p l e r * P . l { . F r a m e l,l . O. Eelton R . C . G o s s l e e S t a f f t { . L . S n i t h * T . J . S o w e l l ' L . B . T a u s * C. F . Weaver B . S . Z a c h a r e k R a d i o l o g i c a l Manpower Educati-on, Oak Ridge O a k R

183

Biodiesel Handling and Use Guide | Open Energy Information  

Open Energy Info (EERE)

Biodiesel Handling and Use Guide Biodiesel Handling and Use Guide Jump to: navigation, search Tool Summary Name: Biodiesel Handling and Use Guide Agency/Company /Organization: National Renewable Energy Laboratory Focus Area: Fuels & Efficiency Topics: Best Practices Website: www.nrel.gov/vehiclesandfuels/npbf/pdfs/43672.pdf This document is a guide for those who blend, store, distribute, and use biodiesel. It is intended to help fleets, individual users, blenders, distributors, and those involved in related activities understand procedures for handling and using biodiesel fuels. How to Use This Tool This tool is most helpful when using these strategies: Avoid - Cut the need for travel Shift - Change to low-carbon modes Improve - Enhance infrastructure & policies Learn more about the avoid, shift, improve framework for limiting air

184

Material handling resource utilization simulation study for stamping plant  

Science Conference Proceedings (OSTI)

This paper describes the application of dynamic simulation to evaluate material handling resource utilization for a stamping plant in the automotive industry. The other objective of this study was evaluation of throughput relative to press schedules, ...

Edward J. Williams; Onur M. Ulgen; Sheldon Bailiff; Ravindra Lote

2006-12-01T23:59:59.000Z

185

Production and Handling Slide 20: Advantages of UF6  

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

UF6 Skip Presentation Navigation First Slide Previous Slide Next Slide Last Presentation Table of Contents Advantages of UF6 Only one isotope of F2 Can be handled at reasonable...

186

Input handling in agent-based micro-level simulators.  

E-Print Network (OSTI)

??In this thesis we presented a new direction for handling missing values in multi agent-based simulation (MABS) at micro-level by using truth tables and logical… (more)

Fayyaz, Muhammad

2010-01-01T23:59:59.000Z

187

Strategies for handling missing data in randomised trials  

E-Print Network (OSTI)

sensitivity analysis and how to handle missing baseline variables. Published: 13 December 2011 References 1. National Research Council: The prevention and treatment of missing data in clinical trials. The National Academies Press; Washington, DC; 2010 [http...

2011-12-13T23:59:59.000Z

188

V-217: Microsoft Windows NAT Driver ICMP Packet Handling Denial...  

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

SCUSSION: The vulnerability is caused due to an error within the Windows NAT Driver when handling ICMP packets and can be exploited to cause the system to stop responding IMPACT:...

189

V-079: ISC BIND AAAA Record Lookup Handling Assertion Failure...  

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

Lets Remote Users Deny Service T-633: BIND RRSIG RRsets Negative Caching Off-by-one Bug Lets Remote Users Deny Service U-183: ISC BIND DNS Resource Records Handling Vulnerability...

190

PRIME VALUE METHOD TO PRIORITIZE RISK HANDLING STRATEGIES  

Science Conference Proceedings (OSTI)

Funding for implementing risk handling strategies typically is allocated according to either the risk-averse approach (the worst risk first) or the cost-effective approach (the greatest risk reduction per implementation dollar first). This paper introduces a prime value approach in which risk handling strategies are prioritized according to how nearly they meet the goals of the organization that disburses funds for risk handling. The prime value approach factors in the importance of the project in which the risk has been identified, elements of both risk-averse and cost-effective approaches, and the time period in which the risk could happen. This paper also presents a prioritizer spreadsheet, which employs weighted criteria to calculate a relative rank for the handling strategy of each risk evaluated.

Noller, D

2007-10-31T23:59:59.000Z

191

Prepared by  

E-Print Network (OSTI)

adjust their physical inventory of source or special nuclear material (SNM) to document and report such activities. The reports are submitted using U.S. Department of Energy (DOE)/NRC Form 741. Licensees may need to provide additional information on some imports or exports of source or SNM. The additional information is reported using DOE/NRC Form 740M. This NUREG contains instructions for preparing these forms. Paperwork Reduction Act Statement The information collections contained in this NUREG are covered by DOE/NRC Forms 741 and 740M, which the Office of Management and Budget (OMB) approved under approval numbers 3150-0003 and 3150-0057. Public Protection Notification If a means used to impose an information collection does not display a currently valid OMB control number, the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection. iii NUREG/BR-0006, Rev. 7NUREG/BR-0006, Rev. 7 iv CONTENTS

C. Graves

2009-01-01T23:59:59.000Z

192

Prepared by:  

E-Print Network (OSTI)

This document was prepared as an account of work sponsored by the United States Government. While this document is believed to contain correct information, neither the United States Government nor any agency thereof, nor the Regents of the University of California, nor any of their employees, makes any warranty, express or implied, or assumes any legal responsibility for the accuracy, completeness, or usefulness of any information, apparatus, product, or process disclosed, or represents that its use would not infringe privately owned rights. Reference herein to any specific commercial product, process, or service by its trade name, trademark, manufacturer, or otherwise, does not necessarily constitute or imply its endorsement, recommendation, or favoring by the United States Government or any agency thereof, or the Regents of the University of California. The views and opinions of authors expressed herein do not necessarily state or reflect those of the United States Government or any agency thereof or the Regents of the University of California. Cover images: Upper left: offshore wind turbine, source: Large-Scale Offshore Wind Power in the United States,

F. Alexander (lanl; M. Anitescu (anl; D. Brown (lbnl; S. Mehrotra (northwestern; A. Pinar (snl; K. Willcox (mit

2011-01-01T23:59:59.000Z

193

Prepared for:  

E-Print Network (OSTI)

Important Disclaimer: The sole purpose of this document and associated services performed by CSIRO is to provide scientific knowledge to the South Australian Government. Work has been carried out in accordance with the scope of services identified in the agreement dated 22 October 2003, between South Australian Government through the EPA (‘the Client’) and the Commonwealth Scientific and Industrial Research Organisation (CSIRO). This document provides a review of environmental impacts of the in-situ acid leach uranium mining process. The material presented in this document has been derived from information supplied to CSIRO by the Client and from consultation with stakeholders and research conducted by CSIRO and other agencies and consultants. The passage of time, manifestation of latent conditions or impact of future events may require further exploration and re-evaluation of the findings, observations, conclusions, and recommendations expressed in this document. This document has been prepared on behalf of and for the exclusive use of the Client, and is subject to and issued in conjunction with the provisions of the agreement between CSIRO and the Client. CSIRO accepts no liability or responsibility whatsoever for or in respect of any use of or reliance upon this document by any third party.

Graham Taylor; Vic Farrington; Peter Woods; Robert Ring; Robert Molloy; Graham Taylor; Vic Farrington; Peter Woods; Robert Ring; Robert Molloy; Mr Peter Dolan; Adelaide Sa

2004-01-01T23:59:59.000Z

194

Prepared for  

E-Print Network (OSTI)

This report was prepared as an account of work sponsored by the United States Government. Neither the United States nor the United States Department of Energy, nor any of their employees, makes any warranty, expressed or implied, or assumes any legal liability or responsibility for the accuracy, completeness, or usefulness of any information, apparatus, product, or process disclosed, or represents that its use would not infringe privately owned rights. Reference herein to any specific commercial product, process, or service by trade name, mark, manufacturer, or otherwise, does not necessarily constitute or imply its endorsement, recommendation, or favoring by the United States Government or any agency thereof. The views and opinions of authors expressed herein do not necessarily state or reflect those of the United States Government or any agency thereof. In situ reheat is an alternative to traditional gas turbine reheat design in which fuel is fed through airfoils rather than in a bulky discrete combustor separating HP and LP turbines. The goals are to achieve increased power output and/or efficiency without higher emissions. In this program the scientific basis for achieving burnout with low emissions has been explored.

D. M. Bachovchin; R. A. Newby; Alafaya Trail; Charles Alsup

2004-01-01T23:59:59.000Z

195

Prepared for:  

E-Print Network (OSTI)

report was prepared as an account of work sponsored by an agency of the United States government. Neither the United States government nor any agency thereof, nor any of their employees, nor any of its contractors, subcontractors, nor their employees makes any warranty, express or implied, or assumes any legal liability or responsibility for the accuracy, completeness, or usefulness of any information, apparatus, product, or process disclosed, or represents that its use would not infringe upon privately owned rights. Reference herein to any specific commercial product, process, or service by trade name, trademark, manufacturer, or otherwise does not necessarily constitute or imply its endorsement, recommendation, or favoring by the United States government or any other agency thereof. The views and opinions of authors expressed herein do not necessarily state or reflect those of the United States government or any agency thereof. ARC-2007-D2540-032-04 In Situ Remediation and Stabilization Technologies for Mercury in Clay Soils The present study includes innovative in situ remediation technologies for the treatment and/or stabilization of mercury contaminated soils. It presents four green alternatives for the treatment

Elsa Cabrejo (doe Fellow; Doe Em; Oak Ridge Office

2010-01-01T23:59:59.000Z

196

Prepared by  

E-Print Network (OSTI)

This report does not contain any information that is proprietary to Westinghouse Electric Company. The U.S. Nuclear Regulatory Commission (NRC) has also prepared a proprietary version of this report for internal distribution. In order to conform to the Commission's regulations concerning the protection of proprietary information so submitted to the NRC, as set forth in Title 10, Section 2.790, of the Code of Federal Regulations (10 CFR 2.790), the proprietary information in the proprietary version of this document is contained within brackets and, where the proprietary information has been deleted in the non-proprietary version, only the brackets remain (the information within the brackets in the proprietary version having been deleted). The justification for claiming the information as proprietary is indicated in both versions by means of lower case letters (a) through (f), located as a superscript immediately following the brackets enclosing each bracketed item of proprietary information, or in the margin opposite such information. These lower case letters refer to the types of information Westinghouse customarily holds in confidence, as identified in Sections (4)(ii)(a) through (4)(ii)(f) of the affidavit accompanying the transmittal of these documents pursuant to 10 CFR 2.790(b)(1).

K. B. Welter; S. M. Bajorek; Jose Reyes; Brian Woods; John Groome; John Hopson; Eric Young; John Denoma; Kent Abel

2005-01-01T23:59:59.000Z

197

Prepared for:  

E-Print Network (OSTI)

This report was prepared as an account of work sponsored by an agency of the United States Government. Neither the United States Government nor any agency thereof, nor any of their employees, makes any warranty, express or implied, or assumes any legal liability or responsibility for the accuracy, completeness, or usefulness of any information, apparatus, product, or process disclosed, or represents that its use would not infringe privately owned rights. Reference herein to any specific commercial product, process, or service by trade name, trademark, manufacturer, or otherwise does not necessarily constitute or imply its endorsement, recommendation, or favoring by the United States Government or any agency thereof. The views and opinions of authors expressed herein do not necessarily state or reflect those of the United States Government or any agency thereof. This report presents and discusses results from the project “Fate of Mercury in Synthetic Gypsum Used for Wallboard Production, ” performed at five different full-scale commercial wallboard plants. Synthetic gypsum produced by wet flue gas desulfurization (FGD) systems on coal-fired power plants is commonly used in the manufacture of wallboard. This practice has

Jessica Sanderson; Gary M. Blythe; Mandi Richardson; Charles Miller

2008-01-01T23:59:59.000Z

198

Prepared By:  

E-Print Network (OSTI)

Team (VSCPT) since the last publication in 2004. Much has happened in Vermont schools, and in schools throughout the country, to warrant the production of a second edition of the Crisis Guide. School leaders and emergency responders have learned a great deal from planning, simulating and responding to real-life school emergencies over the past four years. The Crisis Team has incorporated this new learning within the updated Crisis Guide. The Crisis Guide contains new incident response forms for severe weather, infectious disease, power outages and other hazards that schools need to address in their safety plans. It includes information and an appendix full of useful assessments, ideas and references that the Crisis Team believes will make school response plans more focused, easier to implement and effective. The guidelines are meant to bring school leaders and emergency responders together to plan for school emergencies. In reviewing the past four years, one fact is obvious, school emergencies will happen. The question is, will your school and community be prepared to minimize property damage, reduce injuries and hopefully save lives. This work is too important to ignore. The Vermont School Crisis Planning Team’s work was crucial prior to and following the school shooting in Essex Town. Understanding that “It Can Happen Here”, school and community

unknown authors

2008-01-01T23:59:59.000Z

199

In-Plant Ash-Handling Reference Manual  

Science Conference Proceedings (OSTI)

Despite problems with ash-handling systems that have led to failures in electrostatic precipitators, there has been no extensive reference manual for specifying, operating, and maintaining such systems. The comprehensive manual compiled in this study serves as a reference for every phase of boiler bottom ash- and fly ash-handling systems design and operation as well as a primer for those unfamiliar with these systems.

1986-12-01T23:59:59.000Z

200

Uranium hexafluoride: A manual of good handling practices. Revision 7  

SciTech Connect

The United States Enrichment Corporation (USEC) is continuing the policy of the US Department of Energy (DOE) and its predecessor agencies in sharing with the nuclear industry their experience in the area of uranium hexafluoride (UF{sub 6}) shipping containers and handling procedures. The USEC has reviewed Revision 6 or ORO-651 and is issuing this new edition to assure that the document includes the most recent information on UF{sub 6} handling procedures and reflects the policies of the USEC. This manual updates the material contained in earlier issues. It covers the essential aspects of UF{sub 6} handling, cylinder filling and emptying, general principles of weighing and sampling, shipping, and the use of protective overpacks. The physical and chemical properties of UF{sub 6} are also described. The procedures and systems described for safe handling of UF{sub 6} presented in this document have been developed and evaluated during more than 40 years of handling vast quantities of UF{sub 6}. With proper consideration for its nuclear properties, UF{sub 6} may be safely handled in essentially the same manner as any other corrosive and/or toxic chemical.

NONE

1995-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "handling test prepared" 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

Efficieny handling effluent gases through chemical scrubbing  

SciTech Connect

This paper is presented as an information source for efficiencies of chemical scrubbing. In it, we will discuss the specific problems of scrubbing silane, disilane, diborane, phosphine, hydrogen selenide and arsine. We will explain the scrubber dynamics, gases and flow rates used along with liquid mediums. The equipment and procedures used for testing, as well as the determination of the results, will be discussed. We intend to give examples of possible reactions and documentation of our efficiencies. Installation and maintenance will be touched, as well as our experiments into accidental catastrophic releases. From all of this we will derive conclusions as to the best possible means of wet chemical scrubbing.

Herman, T.; Soden, S.

1988-07-15T23:59:59.000Z

202

Technology gap analysis on sodium-cooled reactor fuel handling system supporting advanced burner reactor development.  

Science Conference Proceedings (OSTI)

The goals of the Global Nuclear Energy Partnership (GNEP) are to expand the use of nuclear energy to meet increasing global energy demand in an environmentally sustainable manner, to address nuclear waste management issues without making separated plutonium, and to address nonproliferation concerns. The advanced burner reactor (ABR) is a fast reactor concept which supports the GNEP fuel cycle system. Since the integral fast reactor (IFR) and advanced liquid-metal reactor (ALMR) projects were terminated in 1994, there has been no major development on sodium-cooled fast reactors in the United States. Therefore, in support of the GNEP fast reactor program, the history of sodium-cooled reactor development was reviewed to support the initiation of this technology within the United States and to gain an understanding of the technology gaps that may still remain for sodium fast reactor technology. The fuel-handling system is a key element of any fast reactor design. The major functions of this system are to receive, test, store, and then load fresh fuel into the core; unload from the core; then clean, test, store, and ship spent fuel. Major requirements are that the system must be reliable and relatively easy to maintain. In addition, the system should be designed so that it does not adversely impact plant economics from the viewpoints of capital investment or plant operations. In this gap analysis, information on fuel-handling operating experiences in the following reactor plants was carefully reviewed: EBR-I, SRE, HNPF, Fermi, SEFOR, FFTF, CRBR, EBR-II, DFR, PFR, Rapsodie, Phenix, Superphenix, KNK, SNR-300, Joyo, and Monju. The results of this evaluation indicate that a standardized fuel-handling system for a commercial fast reactor is yet to be established. However, in the past sodium-cooled reactor plants, most major fuel-handling components-such as the rotatable plug, in-vessel fuel-handling machine, ex-vessel fuel transportation cask, ex-vessel sodium-cooled storage, and cleaning stations-have accumulated satisfactory construction and operation experiences. In addition, two special issues for future development are described in this report: large capacity interim storage and transuranic-bearing fuel handling.

Chikazawa, Y.; Farmer, M.; Grandy, C.; Nuclear Engineering Division

2009-03-01T23:59:59.000Z

203

Preparation of high temperature gas-cooled reactor fuel element  

DOE Patents (OSTI)

This invention relates to a method for the preparation of high temperature gas-cooled reactor (HTGR) fuel elements wherein uncarbonized fuel rods are inserted in appropriate channels of an HTGR fuel element block and the entire block is inserted in an autoclave for in situ carbonization under high pressure. The method is particularly applicable to remote handling techniques.

Bradley, Ronnie A. (Oak Ridge, TN); Sease, John D. (Knoxville, TN)

1976-01-01T23:59:59.000Z

204

Step-By-Step Guide for Waste Handling at WIPP - Fact Sheet  

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

the nation's nuclear waste disposal problem Step-By-Step Guide for Waste Handling at WIPP The handling and disposal of contact-handled transuranic waste at the Waste Isolation...

205

Conceptual design for remote handling methods using the HIP process in the Calcine Immobilization Program  

SciTech Connect

This report recommends the remote conceptual design philosophy for calcine immobilization using the hot isostatic press (HIP) process. Areas of remote handling operations discussed in this report include: (1) introducing the process can into the front end of the HIP process, (2) filling and compacting the calcine/frit mixture into the process can, (3) evacuating and sealing the process can, (4) non-destructive testing of the seal on the process can, (5) decontamination of the process can, (6) HIP furnace loading and unloading the process can for the HIPing operation, (7) loading an overpack canister with processed HIP cans, (8) sealing the canister, with associated non-destructive examination (NDE) and decontamination, and (9) handling canisters for interim storage at the Idaho Chemical Processing Plant (ICPP) located on the Idaho National Engineering Laboratory (INEL) site.

Berry, S.M.; Cox, C.G.; Hoover, M.A.

1994-03-01T23:59:59.000Z

206

WSDOT Test Method T 127 Preparation of Leachate Sample for Testing Toxicity of HECP Effluents 1. Scope This test method outlines the procedure for collecting leachate from a HECP sample. 2. References 2.1 EPA-821-R-02-012 Methods for Measuring Acute Toxic  

E-Print Network (OSTI)

3.1 Lay cheesecloth over clean topsoil 3.2 Apply the HECP to the cheesecloth at the following coverage: 3.2.1 HECP Long-Term or Moderate-Term Mulch 3,500 lbs per acre in two lifts with no more than 2000 # per acre in any one lift. 3.2.2 HECP Short-Term Mulch 2000 # per acre minimum, or manufacturer’s recommended rate may be used. 3.3 Allow material to cure for 48 hours 3.4 Pull cheesecloth up with mat of HECP, brush off any soil 3.5 Cut HECP into squares and provide 1.02 pounds of HECP to the laboratory. 4. Preparation of the Leachate (done by the laboratory) 4.1 Allow hydromulch product to soak in water for one hour 4.2 Remove hydromulch sheet from water 4.3 Filter water through a 60 micron filter – water may be pre-filtered through a 35 mesh and then a 120 mesh before using the 230 mesh/63 micron filter. Note: Leachate not immediately used for testing should be stored at 4 ° C in the dark until

unknown authors

2012-01-01T23:59:59.000Z

207

First semiannual report: Rocky Flats Small Wind Systems Test Center activities. Volume I. Description of the National Small Wind Systems Test Center  

DOE Green Energy (OSTI)

Information is presented concerning the Rocky Flats wind turbine test site; the philosophy of testing at Rocky Flats; test procedure development; atmospheric SWECS testing; SWECS component testing; data collection, handling, and analysis; reporting procedures; and future plans.

None

1978-09-28T23:59:59.000Z

208

GN470094 - Handling Chemicals at SNL/CA  

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

094, Handling Chemicals at SNL/CA 094, Handling Chemicals at SNL/CA Sponsor: Michael W. Hazen, 4000 Revision Date: October 31, 2008 Replaces Document Dated: October 16, 2007 This document is no longer a CPR. This document implements the requirements of Corporate procedure ESH100.2.IH.25, Control Chemical Hazards at SNL/CA. IMPORTANT NOTICE: A printed copy of this document may not be the document currently in effect. The official version is the online version located on the Sandia Restricted Network (SRN). GN470094 - HANDLING CHEMICALS AT SNL/CA Subject Matter Expert: Al Buerer GN470094, Issue E Revision Date: October 31, 2008; Replaces Document Dated: October 16, 2007 Change History 1.0 Purpose, Scope, and Ownership 2.0 Responsibilities 3.0 Definitions 4.0 Training 5.0 Protective Equipment 6.0 Procurement of Chemicals

209

Arrival condition of spent fuel after storage, handling, and transportation  

Science Conference Proceedings (OSTI)

This report presents the results of a study conducted to determine the probable arrival condition of spent light-water reactor (LWR) fuel after handling and interim storage in spent fuel storage pools and subsequent handling and accident-free transport operations under normal or slightly abnormal conditions. The objective of this study was to provide information on the expected condition of spent LWR fuel upon arrival at interim storage or fuel reprocessing facilities or at disposal facilities if the fuel is declared a waste. Results of a literature survey and data evaluation effort are discussed. Preliminary threshold limits for storing, handling, and transporting unconsolidated spent LWR fuel are presented. The difficulty in trying to anticipate the amount of corrosion products (crud) that may be on spent fuel in future shipments is also discussed, and potential areas for future work are listed. 95 references, 3 figures, 17 tables.

Bailey, W.J.; Pankaskie, P.J.; Langstaff, D.C.; Gilbert, E.R.; Rising, K.H.; Schreiber, R.E.

1982-11-01T23:59:59.000Z

210

Remote-Handled Low Level Waste Disposal Project Alternatives Analysis  

Science Conference Proceedings (OSTI)

This report identifies, evaluates, and compares alternatives for meeting the U.S. Department of Energy’s mission need for management of remote-handled low-level waste generated by the Idaho National Laboratory and its tenants. Each alternative identified in the Mission Need Statement for the Remote-Handled Low-Level Waste Treatment Project is described and evaluated for capability to fulfill the mission need. Alternatives that could meet the mission need are further evaluated and compared using criteria of cost, risk, complexity, stakeholder values, and regulatory compliance. The alternative for disposal of remote-handled low-level waste that has the highest confidence of meeting the mission need and represents best value to the government is to build a new disposal facility at the Idaho National Laboratory Site.

David Duncan

2010-10-01T23:59:59.000Z

211

Handbook for Handling, Storing, and Dispensing E85 | Open Energy  

Open Energy Info (EERE)

for Handling, Storing, and Dispensing E85 for Handling, Storing, and Dispensing E85 Jump to: navigation, search Tool Summary Name: Handbook for Handling, Storing, and Dispensing E85 Agency/Company /Organization: National Renewable Energy Laboratory Focus Area: Fuels & Efficiency Topics: Best Practices Website: www.afdc.energy.gov/afdc/pdfs/48162.pdf This document serves as a guide for blenders, distributors, sellers, and users of E85 as an alternative motor fuel. It provides basic information on the proper and safe use of E85 and offers supporting technical and policy references. How to Use This Tool This tool is most helpful when using these strategies: Avoid - Cut the need for travel Shift - Change to low-carbon modes Improve - Enhance infrastructure & policies Learn more about the avoid, shift, improve framework for limiting air

212

U-183: ISC BIND DNS Resource Records Handling Vulnerability | Department of  

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

3: ISC BIND DNS Resource Records Handling Vulnerability 3: ISC BIND DNS Resource Records Handling Vulnerability U-183: ISC BIND DNS Resource Records Handling Vulnerability June 5, 2012 - 7:00am Addthis PROBLEM: A vulnerability has been reported in ISC BIND, which can be exploited by malicious people to disclose potentially sensitive information or cause a DoS (Denial of Service). PLATFORM: Version(s): ISC BIND 9.2.x ISC BIND 9.3.x ISC BIND 9.4.x ISC BIND 9.5.x ISC BIND 9.6.x ISC BIND 9.7.x ISC BIND 9.8.x ISC BIND 9.9.x ABSTRACT: This problem was uncovered while testing with experimental DNS record types. It is possible to add records to BIND with null (zero length) rdata fields. Reference List: Secunia Advisory 49338 CVE-2012-1667 Original Advisory IMPACT ASSESSMENT: High Discussion: Recursive servers may crash or disclose some portion of memory to the

213

Certification plan transuranic waste: Hazardous Waste Handling Facility  

SciTech Connect

The purpose of this plan is to describe the organization and methodology for the certification of transuranic (TRU) waste handled in the Hazardous Waste Handling Facility at Lawrence Berkeley Laboratory (LBL). The plan incorporates the applicable elements of waste reduction, which include both up-front minimization and end-product treatment to reduce the volume and toxicity of the waste; segregation of the waste as it applies to certification; an executive summary of the Quality Assurance Implementing Management Plan (QAIMP) for the HWBF; and a list of the current and planned implementing procedures used in waste certification.

1992-06-01T23:59:59.000Z

214

Distributed Generation Biofuel Testing  

Science Conference Proceedings (OSTI)

This Technical Update report documents testing performed to assess aspects of using biofuel as an energy source for distributed generation. Specifically, the tests involved running Caterpillar Power Module compression ignition engines on palm methyl ester (PME) biofuel and comparing the emissions to those of the same engines running on ultra-low-sulfur diesel fuel. Fuel consumption and energy efficiency were also assessed, and some relevant storage and handling properties of the PME were noted. The tests...

2011-12-06T23:59:59.000Z

215

METHODS FOR THE SAFE STORAGE, HANDLING, AND DISPOSAL OF PYROPHORIC LIQUIDS AND SOLIDS IN THE LABORATORY  

DOE Green Energy (OSTI)

Pyrophoric reagents represent an important class of reactants because they can participate in many different types of reactions. They are very useful in organic synthesis and in industrial applications. The Occupational Safety and Health Administration (OSHA) and the National Fire Protection Association (NFPA) define Pyrophorics as substances that will self-ignite in air at temperatures of 130 F (54.4 C) or less. However, the U.S. Department of Transportation (DOT) uses criteria different from the auto-ignition temperature criterion. The DOT defines a pyrophoric material as a liquid or solid that, even in small quantities and without an external ignition source, can ignite within five minutes after coming in contact with air when tested according to the United Nations Manual of Tests and Criteria. The Environmental Protection Agency has adopted the DOT definition. Regardless of which definition is used, oxidation of the pyrophoric reagents by oxygen or exothermic reactions with moisture in the air (resulting in the generation of a flammable gas such as hydrogen) is so rapid that ignition occurs spontaneously. Due to the inherent nature of pyrophoric substances to ignite spontaneously upon exposure to air, special precautions must be taken to ensure their safe handling and use. Pyrophoric gases (such as diborane, dichloroborane, phosphine, etc.) are typically the easiest class of pyrophoric substances to handle since the gas can be plumbed directly to the application and used remotely. Pyrophoric solids and liquids, however, require the user to physically manipulate them when transferring them from one container to another. Failure to follow proper safety precautions could result in serious injury or unintended consequences to laboratory personnel. Because of this danger, pyrophorics should be handled only by experienced personnel. Users with limited experience must be trained on how to handle pyrophoric reagents and consult with a knowledgeable staff member prior to performing the experimental task. The purpose of this article is three fold: (1) to provide guidelines and general safety precautions to avoid accidents, (2) describe proper techniques on how to successfully handle, store, and dispose of pyrophoric liquids and solids, and (3) illustrate best practices for working with this class of reactants in a laboratory environment.

Simmons, F.; Kuntamukkula, M.; Alnajjar, M.; Quigley, D.; Freshwater, D.; Bigger, S.

2010-02-02T23:59:59.000Z

216

Coal- and Ash-Handling Systems Reliability Conference and Workshop Proceedings  

Science Conference Proceedings (OSTI)

This report presents papers, discussion summaries, and conclusions from an EPRI workshop on reliability problems with coal- and ash-handling systems in power plants. Held in October 1980 in St. Louis, the workshop covered yard and in-plant coal handling, frozen coal, fugitive dust, fly ash handling, bottom ash handling, and ash disposal.

1981-08-01T23:59:59.000Z

217

MRP2 and the handling of mercuric ions in rats exposed acutely to inorganic and organic species of mercury  

Science Conference Proceedings (OSTI)

Mercuric ions accumulate preferentially in renal tubular epithelial cells and bond with intracellular thiols. Certain metal-complexing agents have been shown to promote extraction of mercuric ions via the multidrug resistance-associated protein 2 (MRP2). Following exposure to a non-toxic dose of inorganic mercury (Hg{sup 2+}), in the absence of complexing agents, tubular cells are capable of exporting a small fraction of intracellular Hg{sup 2+} through one or more undetermined mechanisms. We hypothesize that MRP2 plays a role in this export. To test this hypothesis, Wistar (control) and TR{sup -} rats were injected intravenously with a non-nephrotoxic dose of HgCl{sub 2} (0.5 {mu}mol/kg) or CH{sub 3}HgCl (5 mg/kg), containing [{sup 203}Hg], in the presence or absence of cysteine (Cys; 1.25 {mu}mol/kg or 12.5 mg/kg, respectively). Animals were sacrificed 24 h after exposure to mercury and the content of [{sup 203}Hg] in blood, kidneys, liver, urine and feces was determined. In addition, uptake of Cys-S-conjugates of Hg{sup 2+} and methylmercury (CH{sub 3}Hg{sup +}) was measured in inside-out membrane vesicles prepared from either control Sf9 cells or Sf9 cells transfected with human MRP2. The amount of mercury in the total renal mass and liver was significantly greater in TR{sup -} rats than in controls. In contrast, the amount of mercury in urine and feces was significantly lower in TR{sup -} rats than in controls. Data from membrane vesicles indicate that Cys-S-conjugates of Hg{sup 2+} and CH{sub 3}Hg{sup +} are transportable substrates of MRP2. Collectively, these data indicate that MRP2 plays a role in the physiological handling and elimination of mercuric ions from the kidney.

Bridges, Christy C., E-mail: Bridges_cc@mercer.edu; Joshee, Lucy; Zalups, Rudolfs K.

2011-02-15T23:59:59.000Z

218

Recommended strategy for the disposal of remote-handled transuranic waste  

SciTech Connect

The current baseline plan for RH TRU (remote-handled transuranic) waste disposal is to package the waste in special canisters for emplacement in the walls of the waste disposal rooms at the Waste Isolation Pilot Plant (WIPP). The RH waste must be emplaced before the disposal rooms are filled by contact-handled waste. Issues which must be resolved for this plan to be successful include: (1) construction of RH waste preparation and packaging facilities at large-quantity sites; (2) finding methods to get small-quantity site RH waste packaged and certified for disposal; (3) developing transportation systems and characterization facilities for RH TRU waste; (4) meeting lag storage needs; and (5) gaining public acceptance for the RH TRU waste program. Failure to resolve these issues in time to permit disposal according to the WIPP baseline plan will force either modification to the plan, or disposal or long-term storage of RH TRU waste at non-WIPP sites. The recommended strategy is to recognize, and take the needed actions to resolve, the open issues preventing disposal of RH TRU waste at WIPP on schedule. It is also recommended that the baseline plan be upgraded by adopting enhancements such as revised canister emplacement strategies and a more flexible waste transport system.

Bild, R.W. [Sandia National Lab., Albuquerque, NM (United States). Program Integration Dept.

1994-07-01T23:59:59.000Z

219

Some thoughts on using argumentation to handle trust  

Science Conference Proceedings (OSTI)

This paper describes some of our recent work on using argumentation to handle information about trust. We first discuss the importance of trust in computer science in general and in multi-agent systems in particular.We then describe the setting of our ...

Simon Parsons; Yuqing Tang; Kai Cai; Elizabeth Sklar; Peter McBurney

2011-07-01T23:59:59.000Z

220

A business process modeling notation extension for risk handling  

Science Conference Proceedings (OSTI)

During the years of prosperity, numerous organizations neglected numerous aspects of risk management. As systematic approach to handling identified risks is crucial to achieving success by the organization, modern business modeling standards and techniques ... Keywords: BPMN extension, business process modeling notation, risk management

Bartosz Marcinkowski; Michal Kuciapski

2012-09-01T23:59:59.000Z

Note: This page contains sample records for the topic "handling test prepared" 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

Certification Plan, low-level waste Hazardous Waste Handling Facility  

SciTech Connect

The purpose of this plan is to describe the organization and methodology for the certification of low-level radioactive waste (LLW) handled in the Hazardous Waste Handling Facility (HWHF) at Lawrence Berkeley Laboratory (LBL). This plan also incorporates the applicable elements of waste reduction, which include both up-front minimization and end-product treatment to reduce the volume and toxicity of the waste; segregation of the waste as it applies to certification; an executive summary of the Waste Management Quality Assurance Implementing Management Plan (QAIMP) for the HWHF and a list of the current and planned implementing procedures used in waste certification. This plan provides guidance from the HWHF to waste generators, waste handlers, and the Waste Certification Specialist to enable them to conduct their activities and carry out their responsibilities in a manner that complies with the requirements of WHC-WAC. Waste generators have the primary responsibility for the proper characterization of LLW. The Waste Certification Specialist verifies and certifies that LBL LLW is characterized, handled, and shipped in accordance with the requirements of WHC-WAC. Certification is the governing process in which LBL personnel conduct their waste generating and waste handling activities in such a manner that the Waste Certification Specialist can verify that the requirements of WHC-WAC are met.

Albert, R.

1992-06-30T23:59:59.000Z

222

Guidelines for Handling Confidential Information by Remote Access  

E-Print Network (OSTI)

Guidelines for Handling Confidential Information by Remote Access You have signed an OHSU of your access to OHSU electronic information and/or other sanctions. Remember, using remote access of the OHSU facilities. When you are utilizing remote access, you must provide the same level of security used

Chapman, Michael S.

223

METHOD OF PREPARING COATED REFRACTORY WARE  

DOE Patents (OSTI)

A method is presented for preparing a dense, refractory coating on a vessel adapted to the handling of molten metals such as uranium and plutonium. According to the invention, the inner surface of a heat stable container formed of a refractory metal of either niobium, molybdenum, tantalum, or tungsten is coated with molten thorium within 10 minutes so as to present alloying with the refractory metal and then exposed to a reactive atmosphere of nitrogen at a temperature of about 1750 deg for 30 minutes to form a refractory thorium nitride coating.

Perlman, M.L.; Lipkin, D.; Weissman, S.I.

1959-07-21T23:59:59.000Z

224

Safety Evaluation Report of the Waste Isolation Pilot Plant Contact Handled (CH) Waste Documented Safety Analysis  

Science Conference Proceedings (OSTI)

This Safety Evaluation Report (SER) documents the Department of Energy’s (DOE's) review of Revision 9 of the Waste Isolation Pilot Plant Contact Handled (CH) Waste Documented Safety Analysis, DOE/WIPP-95-2065 (WIPP CH DSA), and provides the DOE Approval Authority with the basis for approving the document. It concludes that the safety basis documented in the WIPP CH DSA is comprehensive, correct, and commensurate with hazards associated with CH waste disposal operations. The WIPP CH DSA and associated technical safety requirements (TSRs) were developed in accordance with 10 CFR 830, Nuclear Safety Management, and DOE-STD-3009-94, Preparation Guide for U. S. Department of Energy Nonreactor Nuclear Safety Analysis Reports.

Washington TRU Solutions LLC

2005-09-01T23:59:59.000Z

225

Process Knowledge Summary Report for Materials and Fuels Complex Contact-Handled Transuranic Debris Waste  

SciTech Connect

This Process Knowledge Summary Report summarizes the information collected to satisfy the transportation and waste acceptance requirements for the transfer of transuranic (TRU) waste between the Materials and Fuels Complex (MFC) and the Advanced Mixed Waste Treatment Project (AMWTP). The information collected includes documentation that addresses the requirements for AMWTP and the applicable portion of their Resource Conservation and Recovery Act permits for receipt and treatment of TRU debris waste in AMWTP. This report has been prepared for contact-handled TRU debris waste generated by the Idaho National Laboratory at MFC. The TRU debris waste will be shipped to AMWTP for purposes of supercompaction. This Process Knowledge Summary Report includes information regarding, but not limited to, the generation process, the physical form, radiological characteristics, and chemical contaminants of the TRU debris waste, prohibited items, and packaging configuration. This report, along with the referenced supporting documents, will create a defensible and auditable record for waste originating from MFC.

R. P. Grant; P. J. Crane; S. Butler; M. A. Henry

2010-02-01T23:59:59.000Z

226

The Department of Energy`s Rocky Flats Plant: A guide to record series useful for health related research. Volume 4: Production and materials handling  

Science Conference Proceedings (OSTI)

This is the fourth in a series of seven volumes which constitute a guide to records of the Rocky Flats Plant useful for conducting health-related research. The primary purpose of Volume 4 is to describe record series pertaining to production and materials handling activities at the Department of Energy`s (DOE) Rocky Flats Plant, now named the Rocky Flats Environmental Technology Site, near Denver, Colorado. History Associates Incorporated (HAI) prepared this guide as part of its work as the support services contractor for DOE`s Epidemiologic Records Inventory Project. This introduction briefly describes the Epidemiologic Records Inventory Project and HAI`s role in the project, provides a history of production and materials handling practices at Rocky Flats, and identifies organizations contributing to production and materials handling policies and activities. Other topics include the scope and arrangement of the guide and the organization to contact for access to these records.

NONE

1995-08-01T23:59:59.000Z

227

Guidebook for preparing players' handbooks  

SciTech Connect

This Addendum to the Guidebook for Preparing Players' Handbooks contains several documents that can be inserted into handbooks for future test exercises. Descriptions of these documents are provided in Section 4 of the Guidebook. While the documents are general enough to be included in handbooks with little or no editing, it is recommended the handbook preparers review the documents to determine whether the language is appropriate for a specific future exercise. Some of the documents refer to specific sections or tab numbers which may be inappropriate if future handbooks are organized differently from past handbooks.

Not Available

1989-09-01T23:59:59.000Z

228

DOE Seeks Independent Evaluation of Remote-Handled Waste Program  

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

Seeks Independent Evaluation Seeks Independent Evaluation Of Remote-Handled Waste Program CARLSBAD, N.M., July 24, 2001 - An independent panel of scientific and engineering experts will convene July 30 in Carlsbad to evaluate U.S. Department of Energy (DOE) plans for managing remote-handled (RH) transuranic (TRU) waste at the Waste Isolation Pilot Plant (WIPP). DOE's Carlsbad Field Office has asked the American Society of Mechanical Engineers and the Institute for Regulatory Science to review its proposed RH-TRU waste program. The program must be approved by the New Mexico Environment Department and the U.S. Environmental Protection Agency before DOE will be permitted to accept and dispose of RH-TRU waste at WIPP. "Safety and compliance are our primary considerations in developing the plans for

229

Development and implementation of automated radioactive materials handling systems  

SciTech Connect

Material handling of radioactive and hazardous materials has forced the need to pursue remotely operated and robotic systems in light of operational safety concerns. Manual maneuvering, repackaging, overpacking and inspecting of containers which store radioactive and hazardous materials is the present mode of operation at the Department of Energy (DOE) Fernald Environmental Management Project (FEMP) in Fernald Ohio. The manual methods are unacceptable in the eyes of concerned site workers and influential community oversight committees. As an example to respond to the FEMP material handling needs, design efforts have been initiated to provide a remotely operated system to repackage thousands of degradated drums containing radioactive Thorium: Later, the repackaged Thorium will be shipped offsite to a predesignated repository again requiring remote operation.

Jacoboski, D.L.

1992-12-01T23:59:59.000Z

230

Best Practices for Biomass Handling in Wood Yard Operations  

Science Conference Proceedings (OSTI)

Utilities are beginning to add wood and other biomass fuels to fire their generating units to enable them to produce carbon-neutral electricity and participate in state or national renewable energy programs. However, because the material handling aspects of biomass differ from those of coal, firing at a significant scale requires new equipment to receive, store, and deliver the biomass to the flame front. This equipment is analogous in function to existing machinery but is quite different in detail, desi...

2011-08-29T23:59:59.000Z

231

Safety aspects of large-scale handling of hydrogen  

DOE Green Energy (OSTI)

Since the decade of the 1950s, there has been a large increase in the quantity of hydrogen, especially liquid hydrogen, that has been produced, transported, and used. The technology of hydrogen, as it relates to safety, has also developed at the same time. The possible sources of hazards that can arise in the large-scale handling of hydrogen are recognized, and for the most part, sufficiently understood. These hazard sources are briefly discussed. 26 refs., 4 figs.

Edeskuty, F.J.; Stewart, W.F.

1988-01-01T23:59:59.000Z

232

Optimizing Ash Handling - SmartAshTM System Evaluation  

Science Conference Proceedings (OSTI)

High ash levels in electrostatic precipitator (ESP) hoppers are notorious for increasing particulate matter (PM) emissions and plume opacity. Conventional means of monitoring hopper ash levels and fly ash handling system performance have been time-consuming and problematic. Neundorfer, Inc., has developed a fly ash conveying system-monitoring package (SmartAshSystem) that provides improved monitoring of fly ash removal process parameters and provides graphical depictions of ash system performance. Additi...

2007-11-21T23:59:59.000Z

233

CLASSIFICATION OF THE MGR WASTE HANDLING BUILDING ELECTRICAL SYSTEM  

SciTech Connect

The purpose of this analysis is to document the Quality Assurance (QA) classification of the Monitored Geologic Repository (MGR) waste handling building electrical system structures, systems and components (SSCs) performed by the MGR Safety Assurance Department. This analysis also provides the basis for revision of YMP/90-55Q, Q-List (YMP 1998). The Q-List identifies those MGR SSCs subject to the requirements of DOE/RW-0333P, ''Quality Assurance Requirements and Description'' (QARD) (DOE 1998).

S.E. Salzman

1999-08-31T23:59:59.000Z

234

Baseline descriptions for LWR spent fuel storage, handling, and transportation  

SciTech Connect

Baseline descriptions for the storage, handling, and transportation of reactor spent fuel are provided. The storage modes described include light water reactor (LWR) pools, away-from-reactor basins, dry surface storage, reprocessing-facility interim storage pools, and deep geologic storage. Land and water transportation are also discussed. This work was sponsored by the Department of Energy/Office of Safeguards and Security as part of the Sandia Laboratories Fixed Facility Physical Protection Program. 45 figs, 4 tables.

Moyer, J.W.; Sonnier, C.S.

1978-04-01T23:59:59.000Z

235

EURISOL-DS Multi-Megawatt Target: Remote Handling Equipment  

E-Print Network (OSTI)

The design proposed within Task #2 of the EURISOL Design Study for the remote handling of the mercury converter target and its associated loop is presented with particular emphasis on achieving rapid turn-around during routine maintenance.The converter target needs to be completely exchanged every four months due to the high irradiation damage sustained. Other components are less susceptible to damage but may need periodic maintenance; in particular the on-line isotopic separation unit in the mercury loop.

Cyril Kharoua, Olivier Choisnet, Yacine Kadi, Karel Samec (CERN)

236

West Valley facility spent fuel handling, storage, and shipping experience  

Science Conference Proceedings (OSTI)

The result of a study on handling and shipping experience with spent fuel are described in this report. The study was performed by Pacific Northwest Laboratory (PNL) and was jointly sponsored by the US Department of Energy (DOE) and the Electric Power Research Institute (EPRI). The purpose of the study was to document the experience with handling and shipping of relatively old light-water reactor (LWR) fuel that has been in pool storage at the West Valley facility, which is at the Western New York Nuclear Service Center at West Valley, New York and operated by DOE. A subject of particular interest in the study was the behavior of corrosion product deposits (i.e., crud) deposits on spent LWR fuel after long-term pool storage; some evidence of crud loosening has been observed with fuel that was stored for extended periods at the West Valley facility and at other sites. Conclusions associated with the experience to date with old spent fuel that has been stored at the West Valley facility are presented. The conclusions are drawn from these subject areas: a general overview of the West Valley experience, handling of spent fuel, storing of spent fuel, rod consolidation, shipping of spent fuel, crud loosening, and visual inspection. A list of recommendations is provided. 61 refs., 4 figs., 5 tabs.

Bailey, W.J.

1990-11-01T23:59:59.000Z

237

Oxygen Handling and Cooling Options in High Temperature Electrolysis Plants  

DOE Green Energy (OSTI)

Idaho National Laboratory is working on a project to generate hydrogen by high temperature electrolysis (HTE). In such an HTE system, safety precautions need to be taken to handle high temperature oxygen at ~830°C. This report is aimed at addressing oxygen handling in a HTE plant.. Though oxygen itself is not flammable, most engineering material, including many gases and liquids, will burn in the presence of oxygen under some favorable physicochemical conditions. At present, an absolute set of rules does not exist that can cover all aspects of oxygen system design, material selection, and operating practices to avoid subtle hazards related to oxygen. Because most materials, including metals, will burn in an oxygen-enriched environment, hazards are always present when using oxygen. Most materials will ignite in an oxygen-enriched environment at a temperature lower than that in air, and once ignited, combustion rates are greater in the oxygen-enriched environment. Even many metals, if ignited, burn violently in an oxygen-enriched environment. However, these hazards do not preclude the operations and systems involving oxygen. Oxygen can be safely handled and used if all the materials in a system are not flammable in the end-use environment or if ignition sources are identified and controlled. In fact, the incidence of oxygen system fires is reported to be low with a probability of about one in a million. This report is a practical guideline and tutorial for the safe operation and handling of gaseous oxygen in high temperature electrolysis system. The intent is to provide safe, practical guidance that permits the accomplishment of experimental operations at INL, while being restrictive enough to prevent personnel endangerment and to provide reasonable facility protection. Adequate guidelines are provided to govern various aspects of oxygen handling associated with high temperature electrolysis system to generate hydrogen. The intent here is to present acceptable oxygen standards and practices for minimum safety requirements. A summary of operational hazards, along with oxygen safety and emergency procedures, are provided.

Manohar S. Sohal; J. Stephen Herring

2008-07-01T23:59:59.000Z

238

DOE-HDBK-1129-2007: Tritium Handling and Safe Storage; Replaced...  

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

HDBK-1129-2007: Tritium Handling and Safe Storage; Replaced by DOE-HDBK-1129-2008 DOE-HDBK-1129-2007: Tritium Handling and Safe Storage; Replaced by DOE-HDBK-1129-2008 Tritium...

239

Medical Examiner/Coroner on the Handling of a Body/Human Remains...  

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

Medical ExaminerCoroner on the Handling of a BodyHuman Remains that are Potentially Radiologically Contaminated Medical ExaminerCoroner on the Handling of a BodyHuman Remains...

240

Operational simulation model of the raw material handling in an integrated steel making plant  

Science Conference Proceedings (OSTI)

This article is focused on the design and implementation of an operational simulation model (OSM) of the handling of raw material in an integrated steel making plant, considering operations of receiving, unloading, stocking, handling and supplying the ...

Robson Jacinto Coelho; Paula Fernandes Lana; Adriano César Silva; Takeo Fugiwara Santos; ArcelorMittal Tubarão; Marcelo Moretti Fioroni; Luiz Augusto G. Franzese; Daniel de Oliveira Mota; Paragon Tecnologia; Luiz Bueno da Silva

2009-12-01T23:59:59.000Z

Note: This page contains sample records for the topic "handling test prepared" 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

Disposal of Remote-Handled Transuranic Waste at the WasteIsolation...  

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

gear and is referred to as "contact-handled" TRU. However, TRU wastes with a surface radiation dose rate greater than 200 millirem per hour must be handled using remote...

242

V-177: VMware vCenter Chargeback Manager File Upload Handling...  

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

7: VMware vCenter Chargeback Manager File Upload Handling Vulnerability V-177: VMware vCenter Chargeback Manager File Upload Handling Vulnerability June 13, 2013 - 6:00am Addthis...

243

U-271: Google Android Dialer TEL URL Handling Flaw Lets Remote...  

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

1: Google Android Dialer TEL URL Handling Flaw Lets Remote Users Deny Service U-271: Google Android Dialer TEL URL Handling Flaw Lets Remote Users Deny Service October 1, 2012 -...

244

Practical Guide to Vegetable Oil ProcessingChapter 8 Finished Product Storage and Handling  

Science Conference Proceedings (OSTI)

Practical Guide to Vegetable Oil Processing Chapter 8 Finished Product Storage and Handling Processing eChapters Processing Press Downloadable pdf of Chapter 8 Finished Product Storage and Handling from the book ...

245

Practical Handbook of Soybean Processing and UtilizationHarvest, Storage, Handling and Trading of Soybeans  

Science Conference Proceedings (OSTI)

Practical Handbook of Soybean Processing and Utilization Harvest, Storage, Handling and Trading of Soybeans Processing eChapters Processing AOCS Press Downloadable pdf of Chapter 4 Harvest, Storage, Handling and T

246

METHOD OF PREPARING SINTERED ZIRCONIUM METAL FROM ITS HYDRIDES  

DOE Patents (OSTI)

The invention relates to the preparation of metal shapes from zirconium hydride by powder metallurgical techniques. The zirconium hydride powder which is to be used for this purpose can be prepared by rendering massive pieces of crystal bar zirconium friable by heat treatment in purified hydrogen. This any then be ground into powder and powder can be handled in the air without danger of it igniting. It may then be compacted in the normal manner by being piaced in a die. The compact is sintered under vacuum conditions preferably at a temperature ranging from 1200 to 1300 deg C and for periods of one to three hours.

Angier, R.P.

1958-02-11T23:59:59.000Z

247

Modelling and simulation of high capacity waterside container handling systems at deep-sea terminals  

Science Conference Proceedings (OSTI)

Current handling systems at deep-sea container terminals run into their physical limits and new methods of handling containers are needed to deal with the ever-growing container shipping volumes. We present a domain specific simulation model of high ... Keywords: adjustable simulation model, container handling system, container workflow, productivity improvement, quay crane concepts

F. Geldof; B. C. van Haarlem; W. Lock; E. E. Roubtsova

2008-04-01T23:59:59.000Z

248

A non-contact end-effector for the handling of garments  

Science Conference Proceedings (OSTI)

In order to handle a material with either a delicate surface or an air permeable structure, a novel nozzle was designed and developed. This nozzle utilises the phenomena of the radial air outflow. It is envisaged that this new nozzle will handle materials ... Keywords: End-effector, Fabric, Garment, Gripper, Handling

Babur Ozcelik; Fehmi Erzincanli

2002-07-01T23:59:59.000Z

249

Environments for Remote Teaching in Embedded Systems Courses Christian Trodhandl Thomas Handl Markus Proske Bettina Weiss  

E-Print Network (OSTI)

Environments for Remote Teaching in Embedded Systems Courses Christian Tr¨odhandl Thomas Handl points for discussion at the workshop: How to handle remote access? In a distance lab with a limited/2, 1040 Vienna, Austria {troedhandl,handl,proske,bw}@ecs.tuwien.ac.at 1 Introduction Embedded systems lab

250

Octant 1 boom extension The JET remote handling system has been used  

E-Print Network (OSTI)

Octant 1 boom extension Background The JET remote handling system has been used since 1998 to maintain and modify components inside the torus. The efficiency of in-vessel remote handling activities study Remote handling Top: The Octant 1 boom prior to being extended Bottom: The fully assembled

251

A review of polymer-based water conditioners for reduction of handling-related injury  

Science Conference Proceedings (OSTI)

Fish are coated with an external layer of protective mucus. This layer serves as the primary barrier against infection or injury, reduces friction, and plays a role in ionic and osmotic regulation. However, the mucus layer is easily disturbed when fish are netted, handled, transported, stressed, or subjected to adverse water conditions. Water additives containing polyvinylpyrrolidone (PVP) or proprietary polymers have been used to prevent the deleterious effects of mucus layer disturbances in the commercial tropical fish industry, aquaculture, and for other fisheries management purposes. This paper reviews research on the effectiveness of water conditioners, and examines the contents and uses of a wide variety of commercially available water conditioners. Water conditioners containing polymers may reduce external damage to fish held in containers during scientific experimentation, including surgical implantation of electronic tags. However, there is a need to empirically test the effectiveness of water conditioners at preventing damage to and promoting healing of the mucus layer. A research agenda is provided to advance the science related to the use of water conditions to improve the condition of fish during handling and tagging.

Harnish, Ryan A.; Colotelo, Alison HA; Brown, Richard S.

2011-01-01T23:59:59.000Z

252

Focus on O & M: safeguarding coal-handling assets  

Science Conference Proceedings (OSTI)

Coal fired power plants have millions of dollars invested in conveyor systems and train-unloading equipment. The article gives advice on routine maintenance of coal handling equipment and of the use of monitoring and control systems to prevent fire. It sites an incidence of a fire being triggered by the automated fire protection systems having failed to deliver sufficient water to the upper levels of the conveyor, whilst unloading a coal train at a plant which had switched to Powder River Basin coal which is more prone to spontaneous combustion. 3 photos.

Earney, T.C. [Air Control Science Inc. (United States)

2006-11-15T23:59:59.000Z

253

Supply Fan Control for Constant Air Volume Air Handling Units  

E-Print Network (OSTI)

Since terminal boxes do not have a modulation damper in constant volume (CV) air handling unit (AHU) systems, zone reheat coils have to be modulated to maintain the space temperature with constant supply airflow. This conventional control sequence causes a significant amount of reheat and constant fan power under partial load conditions. Variable Frequency Drives (VFDs) can be installed on these constant air volume systems. The fan speed can be modulated based on the maximum zone load. This paper present the procedure to control the supply fan speed and analyzes the thermal performance and major fan energy and thermal energy savings without expensive VAV retrofit through the actual system operation.

Cho, Y.; Wang, G.; Liu, M.

2007-01-01T23:59:59.000Z

254

Internal Audit Preparation Worksheet  

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

2 Internal Audit Preparation Job Aid 11_0304 Page 1 of 5 2 Internal Audit Preparation Job Aid 11_0304 Page 1 of 5 EOTA - Business Form Document Title: Internal Audit Preparation Job Aid Document Number: F-012 Rev. 11_0304 Document Owner: Elizabeth Sousa Backup Owner: Melissa Otero Approver(s): Melissa Otero Parent Document: P-007, Internal Audit Process Notify of Changes: Internal Auditors Referenced Document(s): F-011 Internal Audit Report F-012 Internal Audit Preparation Job Aid 11_0304 Page 2 of 5 Revision History: Rev. Description of Change A Initial Release 11_0304 Change title from Worksheet to Job Aid and changed revision from alpha to numeric for consistency. F-012 Internal Audit Preparation Job Aid 11_0304 Page 3 of 5 Internal Audit Preparation Worksheet F-012 Internal Audit Preparation Job Aid 11_0304 Page 4 of 5

255

International perspectives on coal preparation  

SciTech Connect

The report consists of the vugraphs from the presentations which covered the following topics: Summaries of the US Department of Energy`s coal preparation research programs; Preparation trends in Russia; South African coal preparation developments; Trends in hard coal preparation in Germany; Application of coal preparation technology to oil sands extraction; Developments in coal preparation in China; and Coal preparation in Australia.

1997-12-31T23:59:59.000Z

256

Preparation of biliquid foam compositions  

DOE Green Energy (OSTI)

Technology developed by the late Dr. Felix Sebba of the VPI Chemical Engineering Department by which an oil phase can be broken up into small droplets and encapsulated in a continuous water phase led to research on the possible merits of a fuel prepared by this procedure. The resulting mixture is called a polyaphron. Part 1 of this report describes the testing of polyaphronated gasoline in an automobile engine. Nitrogen oxides (NO{sub x}) emissions, total hydrocarbon (HC) emissions, and exhaust temperature were determined for various load and RPM combinations. Difficulties with viscosity and separation of the water phase have prevented complete testing at road load conditions. Rather than continue with engine testing, some bench tests of polyaphrons were performed to see the effect of various filtering processes on fuel stability as well as measuring viscosity and density. These results are reported in Part 2 of this paper. 6 figs., 4 tabs.

Jaasma, D.R.; Osucha, D.C.; Scheuren, J.

1990-12-12T23:59:59.000Z

257

ETA-HITP07  

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

7 Revision 0 Effective November 1, 2004 Road Course Handling Test Prepared by Electric Transportation Applications Prepared by: Date: ...

258

EIS-0302: Notice of Intent to Prepare an Environmental Impact...  

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

Impact Statement EIS-0302: Notice of Intent to Prepare an Environmental Impact Statement Transfer of the Heat Source Radioisotope Themoelectric Generator Assembly and Test...

259

Process development for remote-handled mixed-waste treatment  

SciTech Connect

The Oak Ridge National Laboratory (ORNL) is developing a treatment process for remote-handled (RH) liquid transuranic mixed waste governed by the concept of minimizing the volume of waste requiring disposal. This task is to be accomplished by decontaminating the bulk components so the process effluent can be disposed with less risk and expense. Practical processes have been demonstrated on the laboratory scale for removing cesium 137 and strontium 90 isotopes from the waste, generating a concentrated waste volume, and rendering the bulk of the waste nearly radiation free for downstream processing. The process is projected to give decontamination factors of 10{sup 4} for cesium and 10{sup 3} for strontium. Because of the extent of decontamination, downstream processing will be contact handled. The transuranic, radioactive fraction of the mixed waste stream will be solidified using a thin-film evaporator and/or microwave solidification system. Resultant solidified waste will be disposed at the Waste Isolation Pilot Plant (WIPP). 8 refs., 2 figs., 3 tabs.

Berry, J.B.; Campbell, D.O.; Lee, D.D.; White, T.L.

1990-01-01T23:59:59.000Z

260

Certification Plan, Radioactive Mixed Waste Hazardous Waste Handling Facility  

SciTech Connect

The purpose of this plan is to describe the organization and methodology for the certification of radioactive mixed waste (RMW) handled in the Hazardous Waste Handling Facility at Lawrence Berkeley Laboratory (LBL). RMW is low-level radioactive waste (LLW) or transuranic (TRU) waste that is co-contaminated with dangerous waste as defined in the Westinghouse Hanford Company (WHC) Solid Waste Acceptance Criteria (WAC) and the Washington State Dangerous Waste Regulations, 173-303-040 (18). This waste is to be transferred to the Hanford Site Central Waste Complex and Burial Grounds in Hanford, Washington. This plan incorporates the applicable elements of waste reduction, which include both up-front minimization and end-product treatment to reduce the volume and toxicity of the waste; segregation of the waste as it applies to certification; an executive summary of the Waste Management Quality Assurance Implementing Management Plan (QAIMP) for the HWHF (Section 4); and a list of the current and planned implementing procedures used in waste certification.

Albert, R.

1992-06-30T23:59:59.000Z

Note: This page contains sample records for the topic "handling test prepared" 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

FUEL HANDLING FACILITY BACKUP CENTRAL COMMUNICATIONS ROOM SPACE REQUIREMENTS CALCULATION  

SciTech Connect

The purpose of the Fuel Handling Facility Backup Central Communications Room Space Requirements Calculation is to determine a preliminary estimate of the space required to house the backup central communications room in the Fuel Handling Facility (FHF). This room provides backup communications capability to the primary communication systems located in the Central Control Center Facility. This calculation will help guide FHF designers in allocating adequate space for communications system equipment in the FHF. This is a preliminary calculation determining preliminary estimates based on the assumptions listed in Section 4. As such, there are currently no limitations on the use of this preliminary calculation. The calculations contained in this document were developed by Design and Engineering and are intended solely for the use of Design and Engineering in its work regarding the FHF Backup Central Communications Room Space Requirements. Yucca Mountain Project personnel from Design and Engineering should be consulted before the use of the calculations for purposes other than those stated herein or use by individuals other than authorized personnel in Design and Engineering.

B. SZALEWSKI

2005-03-22T23:59:59.000Z

262

Remote Handling Concepts for the Long Baseline Neutrino Experiment  

SciTech Connect

The Long Baseline Neutrino Experiment (LBNE) is a DOE funded experiment aimed at furthering the understanding of neutrino physics. The high intensity neutrino beam for LBNE will be produced at Fermi National Accelerator Laboratory (FNAL) by delivering a high power, 120 GeV proton beam to an underground target facility. The design proton beam power on target is 700 kW with an expected future upgrade to 2.3 MW. Both these beam powers will be sufficient to activate critical equipment necessary for producing neutrinos; thus, the activated equipment must be maintained using remote handling tools and operations. Oak Ridge National Laboratory (ORNL) was tasked to develop concepts for the remote maintenance of the LBNE target equipment as well as provide recommendations for facility layouts. A discussion of the proposed LBNE Target Hall layout is presented along with concepts for the facility's remote handling systems and major remote operations. Concepts for replacement and maintenance of beam line components are also discussed.

Graves, Van B [ORNL; Carroll, Adam J [ORNL; Hurh, Patrick G. [FNAL

2011-01-01T23:59:59.000Z

263

Oak Ridge Isotope Production Cyclotron Facility and Target Handling  

SciTech Connect

Abstract The Nuclear Science Advisory Committee issued in August 2009 an Isotopes Subcommittee report that recommended the construction and operation of a variable-energy, high-current, multiparticle accelerator for producing medical radioisotopes. To meet the needs identified in the report, Oak Ridge National Laboratory is developing a technical concept for a commercial 70 MeV dual-port-extraction, multiparticle cyclotron to be located at the Holifield Radioactive Ion Beam Facility. The conceptual design of the isotope production facility as envisioned would provide two types of targets for use with this new cyclotron. One is a high-power target cooled by water circulating on both sides, and the other is a commercial target cooled only on one side. The isotope facility concept includes an isotope target vault for target irradiation and a shielded transfer station for radioactive target handling. The targets are irradiated in the isotope target vault. The irradiated targets are removed from the target vault and packaged in an adjoining shielded transfer station before being sent out for postprocessing. This paper describes the conceptual design of the target-handling capabilities required for dealing with these radioactive targets and for minimizing the contamination potential during operations.

Bradley, Eric Craig [ORNL; Varma, Venugopal Koikal [ORNL; Egle, Brian [ORNL; Binder, Jeffrey L [ORNL; Mirzadeh, Saed [ORNL; Tatum, B Alan [ORNL; Burgess, Thomas W [ORNL; Devore, Joe [Oak Ridge National Laboratory (ORNL); Rennich, Mark [Oak Ridge National Laboratory (ORNL); Saltmarsh, Michael John [ORNL; Caldwell, Benjamin Cale [Oak Ridge National Laboratory (ORNL)

2011-01-01T23:59:59.000Z

264

Monsanto/Mound Laboratory Engineering Development of Tritium-Handling Systems  

SciTech Connect

Mound Laboratory (Mound) has, during the past four years, been actively involved in the development of methods to contain and control tritium during its processing and to recover it from waste streams. Initial bench-scale research was directed mainly toward removal of tritium from gaseous effluent streams and from laboratory liquid wastes. The gaseous effluent investigation has progressed through the developmental stage and has been implemented in routine operations. A test laboratory embodying many of the results of the research phase has been designed and construction has been completed. As the program at Mound has progressed, the scope of the effort has been expanded to include research concerned with handling not only gaseous tritium but also tritiated liquids. A program is presently under way to investigate the detritiation of aqueous wastes encountered in the fuel cycle of the commercial power reactor industry.

Bixel, J. C.; Lamberger, P. H.

1976-07-01T23:59:59.000Z

265

Test Automation Test Automation  

E-Print Network (OSTI)

Test Automation Test Automation Mohammad Mousavi Eindhoven University of Technology, The Netherlands Software Testing 2013 Mousavi: Test Automation #12;Test Automation Outline Test Automation Mousavi: Test Automation #12;Test Automation Why? Challenges of Manual Testing Test-case design: Choosing inputs

Mousavi, Mohammad

266

ENVIRONMENTAL SAMPLING USING LOCATION SPECIFIC AIR MONITORING IN BULK HANDLING FACILITIES  

SciTech Connect

Since the introduction of safeguards strengthening measures approved by the International Atomic Energy Agency (IAEA) Board of Governors (1992-1997), international nuclear safeguards inspectors have been able to utilize environmental sampling (ES) (e.g. deposited particulates, air, water, vegetation, sediments, soil and biota) in their safeguarding approaches at bulk uranium/plutonium handling facilities. Enhancements of environmental sampling techniques used by the IAEA in drawing conclusions concerning the absence of undeclared nuclear materials or activities will soon be able to take advantage of a recent step change improvement in the gathering and analysis of air samples at these facilities. Location specific air monitoring feasibility tests have been performed with excellent results in determining attribute and isotopic composition of chemical elements present in an actual test-bed sample. Isotopic analysis of collected particles from an Aerosol Contaminant Extractor (ACE) collection, was performed with the standard bulk sampling protocol used throughout the IAEA network of analytical laboratories (NWAL). The results yielded bulk isotopic values expected for the operations. Advanced designs of air monitoring instruments such as the ACE may be used in gas centrifuge enrichment plants (GCEP) to detect the production of highly enriched uranium (HEU) or enrichments not declared by a State. Researchers at Savannah River National Laboratory in collaboration with Oak Ridge National Laboratory are developing the next generation of ES equipment for air grab and constant samples that could become an important addition to the international nuclear safeguards inspector's toolkit. Location specific air monitoring to be used to establish a baseline environmental signature of a particular facility employed for comparison of consistencies in declared operations will be described in this paper. Implementation of air monitoring will be contrasted against the use of smear ES when used during unannounced inspections, design information verification, limited frequency unannounced access, and complementary access visits at bulk handling facilities. Analysis of technical features required for tamper indication and resistance will demonstrate the viability of successful application of the system in taking ES within a bulk handling location. Further exploration of putting this technology into practice is planned to include mapping uranium enrichment facilities for the identification of optimal for installation of air monitoring devices.

Sexton, L.; Hanks, D.; Degange, J.; Brant, H.; Hall, G.; Cable-Dunlap, P.; Anderson, B.

2011-06-07T23:59:59.000Z

267

Preparation and Processing Plants AGENCY: Environmental Protection Agency (EPA). ACTION: Final rule.  

E-Print Network (OSTI)

amendments to the new source performance standards for coal preparation and processing plants. These final amendments include revisions to the emission limits for particulate matter and opacity standards for thermal dryers, pneumatic coal cleaning equipment, and coal handling equipment (coal processing and conveying equipment, coal storage systems, and coal transfer and loading systems) located at coal preparation and processing plants. These revised limits apply to affected facilities that commence construction, modification,

Summary Epa Is Promulgating

2009-01-01T23:59:59.000Z

268

A new guide for commissioning air handling systems: Using a model functional test  

E-Print Network (OSTI)

or a transmitter at the RTD. Subject to moderate self-temperature detector (RTD) Nearly linear over a wide rangeresistance compared to a RTD, so lead wire resistance errors

Haasl, Tudi; Sellers, David; Friedman, Hannah; Piette, Mary Ann; Bourassa, Norman; Gillespie, Ken

2002-01-01T23:59:59.000Z

269

Handling Overload Conditions In High Performance Trustworthy Information Retrieval Systems  

E-Print Network (OSTI)

Web search engines retrieve a vast amount of information for a given search query. But the user needs only trustworthy and high-quality information from this vast retrieved data. The response time of the search engine must be a minimum value in order to satisfy the user. An optimum level of response time should be maintained even when the system is overloaded. This paper proposes an optimal Load Shedding algorithm which is used to handle overload conditions in real-time data stream applications and is adapted to the Information Retrieval System of a web search engine. Experiment results show that the proposed algorithm enables a web search engine to provide trustworthy search results to the user within an optimum response time, even during overload conditions.

Ramachandran, Sumalatha; Paulraj, Sujaya; Ramaraj, Vetriselvi

2010-01-01T23:59:59.000Z

270

340 waste handling complex: Deactivation project management plan  

SciTech Connect

This document provides an overview of the strategy for deactivating the 340 Waste Handling Complex within Hanford`s 300 Area. The plan covers the period from the pending September 30, 1998 cessation of voluntary radioactive liquid waste (RLW) transfers to the 340 Complex, until such time that those portions of the 340 Complex that remain active beyond September 30, 1998, specifically, the Retention Process Sewer (RPS), can also be shut down and deactivated. Specific activities are detailed and divided into two phases. Phase 1 ends in 2001 after the core RLW systems have been deactivated. Phase 2 covers the subsequent interim surveillance of deactivated and stand-by components during the period of continued RPS operation, through the final transfer of the entire 340 Complex to the Environmental Restoration Contractor. One of several possible scenarios was postulated and developed as a budget and schedule planning case.

Stordeur, R.T.

1998-06-25T23:59:59.000Z

271

Contact-handled transuranic waste characterization based on existing records  

Science Conference Proceedings (OSTI)

This report contains the results of characterizing the retrievably stored, contact-handled transuranic (CH-TRU) waste based on existing records. This report is the first comprehensive analysis of these records. A history of the methods used in storing the transuranic waste and in determining how the data was accumulated for entry into the Richland-Solid Waste Information Management System (R-SWIMS) is also described. Data from the R-SWIMS have been the primary source of information in characterizing the waste contents. Supporting documents and interviews with knowledgeable people provide the basis for the documenting the history of storage practices. The storage conditions will be investigated further to ensure that a representative statistical sample is obtained for the second phase of this characterization program.

Anderson, B.C.; Anderson, J.D.; Demiter, J.A.; Duncan, D.R.; Fort, L.A.; McCann, D.C.; Stone, S.J.

1991-09-01T23:59:59.000Z

272

Contact-handled transuranic waste characterization based on existing records  

Science Conference Proceedings (OSTI)

This report contains the results of characterizing the retrievably stored, contact-handled transuranic (CH-TRU) waste based on existing records. This report is the first comprehensive analysis of these records. A history of the methods used in storing the transuranic waste and in determining how the data was accumulated for entry into the Richland-Solid Waste Information Management System (R-SWIMS) is also described. Data from the R-SWIMS have been the primary source of information in characterizing the waste contents. Supporting documents and interviews with knowledgeable people provide the basis for documenting the history of storage practices. The storage conditions will be investigated further to ensure that a representative statistical sample is obtained for the second phase of this characterization program 12 refs., 19 figs., 46 tabs.

Anderson, B.C.; Anderson, J.D.; Demiter, J.A.; Duncan, D.R.; McCann, D.C.

1990-02-01T23:59:59.000Z

273

A sensor-based automation system for handling nuclear materials  

Science Conference Proceedings (OSTI)

An automated system is being developed for handling large payloads of radioactive nuclear materials in an analytical laboratory. The automation system performs unpacking and repacking of payloads from shipping and storage containers, and delivery of the payloads to the stations in the laboratory. The system uses machine vision and force/torque sensing to provide sensor-based control of the automation system in order to enhance system safety, flexibility, and robustness, and achieve easy remote operation. The automation system also controls the operation of the laboratory measurement systems and the coordination of them with the robotic system. Particular attention has been given to system design features and analytical methods that provide an enhanced level of operational safety. Independent mechanical gripper interlock and tool release mechanisms were designed to prevent payload mishandling. An extensive Failure Modes and Effects Analysis of the automation system was developed as a safety design analysis tool.

Drotning, W.; Kimberly, H.; Wapman, W.; Darras, D. [and others

1997-03-01T23:59:59.000Z

274

Electrochemically Preparing of Ni-Fe Alloys in Molten Sodium ...  

Science Conference Proceedings (OSTI)

A Pilot-plant Scale Test of Coal-based Rotary Kiln Direct Reduction of Laterite Ore for Fe-Ni Production · A Pilot-plant Scale Test on DRI Preparation from ...

275

Evaluation of a New Remote Handling Design for High Throughput Annular Centrifugal Contactors  

Science Conference Proceedings (OSTI)

Advanced designs of nuclear fuel recycling plants are expected to include more ambitious goals for aqueous based separations including; higher separations efficiency, high-level waste minimization, and a greater focus on continuous processes to minimize cost and footprint. Therefore, Annular Centrifugal Contactors (ACCs) are destined to play a more important role for such future processing schemes. Previous efforts defined and characterized the performance of commercial 5 cm and 12.5 cm single-stage ACCs in a “cold” environment. The next logical step, the design and evaluation of remote capable pilot scale ACCs in a “hot” or radioactive environment was reported earlier. This report includes the development of remote designs for ACCs that can process the large throughput rates needed in future nuclear fuel recycling plants. Novel designs were developed for the remote interconnection of contactor units, clean-in-place and drain connections, and a new solids removal collection chamber. A three stage, 12.5 cm diameter rotor module has been constructed and evaluated for operational function and remote handling in highly radioactive environments. This design is scalable to commercial CINC ACC models from V-05 to V-20 with total throughput rates ranging from 20 to 650 liters per minute. The V-05R three stage prototype was manufactured by the commercial vendor for ACCs in the U.S., CINC mfg. It employs three standard V-05 clean-in-place (CIP) units modified for remote service and replacement via new methods of connection for solution inlets, outlets, drain and CIP. Hydraulic testing and functional checks were successfully conducted and then the prototype was evaluated for remote handling and maintenance suitability. Removal and replacement of the center position V-05R ACC unit in the three stage prototype was demonstrated using an overhead rail mounted PaR manipulator. This evaluation confirmed the efficacy of this innovative design for interconnecting and cleaning individual stages while retaining the benefits of commercially reliable ACC equipment for remote applications in the nuclear industry. Minor modifications and suggestions for improved manual remote servicing by the remote handling specialists were provided but successful removal and replacement was demonstrated in the first prototype.

David H. Meikrantz; Troy G. Garn; Jack D. Law; Lawrence L. Macaluso

2009-09-01T23:59:59.000Z

276

Using Single-Camera 3-D Imaging to Guide Material Handling Robots in a Nuclear Waste Package Closure System  

SciTech Connect

Nuclear reactors for generating energy and conducting research have been in operation for more than 50 years, and spent nuclear fuel and associated high-level waste have accumulated in temporary storage. Preparing this spent fuel and nuclear waste for safe and permanent storage in a geological repository involves developing a robotic packaging system—a system that can accommodate waste packages of various sizes and high levels of nuclear radiation. During repository operation, commercial and government-owned spent nuclear fuel and high-level waste will be loaded into casks and shipped to the repository, where these materials will be transferred from the casks into a waste package, sealed, and placed into an underground facility. The waste packages range from 12 to 20 feet in height and four and a half to seven feet in diameter. Closure operations include sealing the waste package and all its associated functions, such as welding lids onto the container, filling the inner container with an inert gas, performing nondestructive examinations on welds, and conducting stress mitigation. The Idaho National Laboratory is designing and constructing a prototype Waste Package Closure System (WPCS). Control of the automated material handling is an important part of the overall design. Waste package lids, welding equipment, and other tools must be moved in and around the closure cell during the closure process. These objects are typically moved from tool racks to a specific position on the waste package to perform a specific function. Periodically, these objects are moved from a tool rack or the waste package to the adjacent glovebox for repair or maintenance. Locating and attaching to these objects with the remote handling system, a gantry robot, in a loosely fixtured environment is necessary for the operation of the closure cell. Reliably directing the remote handling system to pick and place the closure cell equipment within the cell is the major challenge.

Rodney M. Shurtliff

2005-09-01T23:59:59.000Z

277

Survey of the State-of-the-Art of Coal Handling During Freezing Weather  

Science Conference Proceedings (OSTI)

This report presents a state-of-the-art review of coal-handling procedures and programs used by electric utilities, coal mines, and coal transfer stations during periods of freezing weather. The use of freeze-conditioning agents to reduce coal-handling problems is discussed, as well as the relative efficacy of various nonchemical techniques. Guidelines for handling frozen coal that reflect typical problems and solutions are given.

1981-04-04T23:59:59.000Z

278

End-Effector Development for the PIP Puck Handling Robot  

SciTech Connect

It has been decided that excess, weapons-grade plutonium shall be immobilized to prevent nuclear proliferation. The method of immobilization is to encapsulate the plutonium in a ceramic puck, roughly the size of a hockey puck, using a sintering process. This method has been officially identified as the Plutonium Immobilization Process (PIP). A Can-in-Canister storage method will be used to further immobilize the plutonium. The Can-in-Canister method uses the existing design of a Defense Waste Processing Facility (DWPF) canister to house the plutonium pucks. the process begins with several pucks being stacked in a stainless steel can. Several of the stainless steel cans are stacked in a cage-like magazine. Several of the magazines are then placed in a DWPF canister. The DWPF canister is then filled with molten glass containing high-level, radioactive waste from the DWPF vitrification process. The Can-in-Canister method makes reclamation of plutonium from the pucks technically difficult and highly undesirable. The mechanical requirements of the Can-in-Canister process, in conjunction with the amount of time required to immobilize the vast quantities of weapons-grade plutonium, will expose personnel to unnecessarily high levels of radiation if the processes were completed manually, in glove boxes. Therefore, automated equipment is designed into the process to reduce or eliminate personnel exposure. Robots are used whenever the automated handling operations become complicated. There are two such operations in the initial stages of the Can-in-Canister process, which required a six-axis robot. The first operation is a press unloading process. The second operation is a tray transfer process. To successfully accomplish the operational tasks described in the two operations, the end-effector of the robot must be versatile, lightweight, and rugged. As a result of these demands, an extensive development process was undertaken to design the optimum end-effector for these puck-handling operations. As an overall requirement, it was desired to keep the design of the robot end-effector as simple as possible. There were pros and cons for either type of actuation method (pneumatic or electric). But, pneumatic actuation was chosen for its simplicity and durability in a radioactive environment. It was determined early in the design process that at least two different types of end-effectors would be required for each of the operations. Therefore, a tool changer was incorporated into the end-effector design. The tool changer would also provide for simple end-effector maintenance when used in the PIP process.

Fowley, M.D.

2001-01-03T23:59:59.000Z

279

End-Effector Development for the PIP Puck Handling Robot  

SciTech Connect

It has been decided that excess, weapons-grade plutonium shall be immobilized to prevent nuclear proliferation. The method of immobilization is to encapsulate the plutonium in a ceramic puck, roughly the size of a hockey puck, using a sintering process. This method has been officially identified as the Plutonium Immobilization Process (PIP). A Can-in-Canister storage method will be used to further immobilize the plutonium. The Can-in-Canister method uses the existing design of a Defense Waste Processing Facility (DWPF) canister to house the plutonium pucks. the process begins with several pucks being stacked in a stainless steel can. Several of the stainless steel cans are stacked in a cage-like magazine. Several of the magazines are then placed in a DWPF canister. The DWPF canister is then filled with molten glass containing high-level, radioactive waste from the DWPF vitrification process. The Can-in-Canister method makes reclamation of plutonium from the pucks technically difficult and highly undesirable. The mechanical requirements of the Can-in-Canister process, in conjunction with the amount of time required to immobilize the vast quantities of weapons-grade plutonium, will expose personnel to unnecessarily high levels of radiation if the processes were completed manually, in glove boxes. Therefore, automated equipment is designed into the process to reduce or eliminate personnel exposure. Robots are used whenever the automated handling operations become complicated. There are two such operations in the initial stages of the Can-in-Canister process, which required a six-axis robot. The first operation is a press unloading process. The second operation is a tray transfer process. To successfully accomplish the operational tasks described in the two operations, the end-effector of the robot must be versatile, lightweight, and rugged. As a result of these demands, an extensive development process was undertaken to design the optimum end-effector for these puck-handling operations. As an overall requirement, it was desired to keep the design of the robot end-effector as simple as possible. There were pros and cons for either type of actuation method (pneumatic or electric). But, pneumatic actuation was chosen for its simplicity and durability in a radioactive environment. It was determined early in the design process that at least two different types of end-effectors would be required for each of the operations. Therefore, a tool changer was incorporated into the end-effector design. The tool changer would also provide for simple end-effector maintenance when used in the PIP process.

Fowley, M.D.

2001-01-31T23:59:59.000Z

280

A biomechanical analysis of patient handling techniques and equipment in a remote setting.  

E-Print Network (OSTI)

??Remote area staff performing manual patient handling tasks in the absence of patient lifting hoists available in most health care settings are at an elevated… (more)

Muriti, Andrew John

2005-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "handling test prepared" 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

Proposal for Construction/Demonstration/Implementation of A Material Handling System  

SciTech Connect

Vortec Corporation, the United States Enrichment Corporation (USEC) and DOE/Paducah propose to complete the technology demonstration and the implementation of the Material Handling System developed under Contract Number DE-AC21-92MC29120. The demonstration testing and operational implementation will be done at the Paducah Gaseous Diffusion Plant. The scope of work, schedule and cost for the activities are included in this proposal. A description of the facility to be constructed and tested is provided in Exhibit 1, attached. The USEC proposal for implementation at Paducah is presented in Exhibit 2, and the commitment letters from the site are included in Exhibit 3. Under our agreements with USEC, Bechtel Jacobs Corporation and DOE/Paducah, Vortec will be responsible for the construction of the demonstration facility as documented in the engineering design package submitted under Phase 4 of this contract on August 9, 2001. USEC will have responsibility for the demonstration testing and commercial implementation of the plant. The demonstration testing and initial commercial implementation of the technology will be achieved by means of a USEC work authorization task with the Bechtel Jacobs Corporation. The initial processing activities will include the processing of approximately 4,250 drums of LLW. Subsequent processing of LLW and TSCA/LLW will be done under a separate contract or work authorization task. To meet the schedule for commercial implementation, it is important that the execution of the Phase 4 project option for construction of the demonstration system be executed as soon as possible. The schedule we have presented herein assumes initiation of the construction phase by the end of September 2001. Vortec proposes to complete construction of the demonstration test system for an estimated cost of $3,254,422. This price is based on the design submitted to DOE/NETL under the Phase 4 engineering design deliverable (9 august 2001). The cost is subject to the assumptions and conditions identified in Section 6 of this proposal.

Jim Jnatt

2001-08-24T23:59:59.000Z

282

Fusion Science to Prepare  

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

DIII-D Explorations of Fusion Science to Prepare for ITER and FNSF Dr. Richard Buttery General Atomics Tuesday, Dec 10, 2013 - 11:00AM MBG AUDITORIUM Refreshments at 10:45AM The...

283

PREPARATION OF URANIUM MONOSULFIDE  

DOE Patents (OSTI)

A process is given for preparing uranium monosulfide from uranium tetrafluoride dissolved in molten alkali metal chloride. A hydrogen-hydrogen sulfide gas mixture passed through the solution precipitates uranium monosulfide. (AEC)

Yoshioka, K.

1964-01-28T23:59:59.000Z

284

Safe Frozen Turkey Preparation  

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

to the dog. 4. Save time and dirty dishes, just prepare the meal. A. True why wash so many dishes? B. False wash the cutting board frequently in hot soapy water; same...

285

Paper Preparation Guidelines  

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

735E Validation of the Window Model of the Modelica Buildings Library Thierry Stephane Nouidui, Michael Wetter, and Wangda Zuo July 2012 DISCLAIMER This document was prepared as an...

286

PROCEDURE FOR PREPARING  

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

PROCEDURE FOR PREPARING PROCEDURE FOR PREPARING RECORDS INVENTORY AND DISPOSITION SCHEDULES (RIDS) Revision 1 November 1, 2007 Records Management Division, IM-23 PROCEDURE FOR PREPARING RECORDS INVENTORY AND DISPOSITION SCHEDULES (RIDS) 1. If the records have not yet been inventoried, see "Procedure for Conducting a Records Inventory." An inventory must be completed prior to preparing the RIDS. 2. The Records Inventory and Disposition Schedules (RIDS) should be reviewed and updated at least annually on DOE F 1324.10 and DOE F 1324.9. The RIDS covers all record, administrative and programmatic, as well as non- record material. The RIDS must include: a. Complete and detailed information identifying the organization (s) responsible for the records.

287

Modernizing the handling of ear corn. Final technical report  

DOE Green Energy (OSTI)

The goal of the project was to modernize the handling of ear corn. The corn was picked with a three row JD 300 picker pulled by a tractor. Pulled behind the picker was a side dump wagon with a capacity of 150 bushels of ear corn. When the dump wagon was full, a grain truck was driven along side of the wagon and the dump wagon, controlled by the tractor driver, was emptied into the truck. After two dumps of the wagon, the truck was driven to the storage area. The storage area consisted of ten (ten) 2000 bushel corn cribs set in a semi circle so that the elevator that filled the cribs could be moved from one crib to the next without changing the fill point. At the storage area, the truck full of corn was dumped into the platform feeder. By using a platform feeder to feed the elevator, all ten (10) cribs could be filled without moving it. After the harvest was complete, the corn remains in the cribs until needed for feed or until the corn is sold. During the time that the corn remains in the cribs, the turbine ventilator draws air through the corn and dries it.

Kleptz, C.F.

1980-01-01T23:59:59.000Z

288

Air Handling Unit Supply Air Temperature Optimization During Economizer Cycles  

E-Print Network (OSTI)

Most air handling units (AHUs) in commercial buildings have an air economizer cycle for free cooling under certain outside air conditions. During the economizer cycle, the outside air and return air dampers are modulated to seek mixing air temperature at supply air temperature setpoint. Mechanical cooling is always required when outside air temperature is higher than the supply air temperature setpoint. Generally the supply air temperature setpoint is set at 55°F for space humidity control. Actually the dehumidification is not necessary when outside air dew point is less than 55°F. Meanwhile the space may have less cooling load due to envelope heat loss and/or occupant schedule. These provide an opportunity to use higher supply air temperature to reduce or eliminate mechanical cooling and terminal box reheat. On the other hand the higher supply air temperature will require higher air flow as well as higher fan power. Therefore the supply air temperature has to be optimized to minimize the combined energy for fan, cooling and heating energy. In this paper a simple energy consumption model is established for AHU systems during the economizer and then a optimal supply air temperature control is developed to minimize the total cost of the mechanical cooling and the fan motor power. This paper presents AHU system energy modeling, supply air temperature optimization, and simulated energy savings.

Xu, K.; Liu, M.; Wang, G.; Wang, Z.

2007-01-01T23:59:59.000Z

289

Well tool lock mandrel and handling tools therefor  

SciTech Connect

A lock mandrel and running tool assembly for setting and locking a well tool in a landing nipple along a well bore is described comprising: a lock mandrel having a body provided with at least one side window; a support shoulder on the body for supporting the mandrel in a no-go landing nipple; a radially movable locking dog in the side window; a longitudinally movable expander sleeve in the body movable within the dog for expanding and locking the dog outwardly and releasing the dog for inward movement, the expander sleeve having an internal annular recess for engagement by a handling tool to move the sleeve upwardly and downwardly and an external annular latch boss along an upper end portion thereof; and a latch ring in the body around the expander sleeve above the locking dog for engagement with the latch boss on the sleeve when the sleeve is at an upper locking position to releasably hold the sleeve in the upper position. The running tool includes a head assembly for connection with an operating tool string; an upper retainer dog assembly supported from the head assembly for releasably coupling the running tool with the body of the lock mandrel; a lower locking lug assembly supported from the head assembly for releasably coupling the running tool with the expander sleeve of the lock mandrel to move the expander sleeve between locking and release positions.

Higgins, B.D.

1988-05-24T23:59:59.000Z

290

Removable pellicle for lithographic mask protection and handling  

DOE Patents (OSTI)

A removable pellicle for a lithographic mask that provides active and robust particle protection, and which utilizes a traditional pellicle and two deployments of thermophoretic protection to keep particles off the mask. The removable pellicle is removably attached via a retaining structure to the mask substrate by magnetic attraction with either contacting or non-contacting magnetic capture mechanisms. The pellicle retaining structural is composed of an anchor piece secured to the mask substrate and a frame member containing a pellicle. The anchor piece and the frame member are in removable contact or non-contact by the magnetic capture or latching mechanism. In one embodiment, the frame member is retained in a floating (non-contact) relation to the anchor piece by magnetic levitation. The frame member and the anchor piece are provided with thermophoretic fins which are interdigitated to prevent particles from reaching the patterned area of the mask. Also, the anchor piece and mask are maintained at a higher temperature than the frame member and pellicle which also prevents particles from reaching the patterned mask area by thermophoresis. The pellicle can be positioned over the mask to provide particle protection during mask handling, inspection, and pumpdown, but which can be removed manually or robotically for lithographic use of the mask.

Klebanoff, Leonard E. (Dublin, CA); Rader, Daniel J. (Albuquerque, NM); Hector, Scott D. (Oakland, CA); Nguyen, Khanh B. (Sunnyvale, CA); Stulen, Richard H. (Livermore, CA)

2002-01-01T23:59:59.000Z

291

Lube Oil Predictive Maintenance, Handling, and Quality Assurance Guideline  

Science Conference Proceedings (OSTI)

This guideline has been prepared by EPRI to assist member utilities in the improvement of maintenance processes. It presents the key elements that should be included in conducting comprehensive lubrication program evaluations and in setting up a well-organized lubrication program. EPRI believes that utilities can make organizational and procedural improvements that will yield optimal lubrication programs. This guideline also serves as an excellent reference document because it describes key lubrication t...

2002-12-18T23:59:59.000Z

292

ROCKY MOUNTAIN OILFIELD TESTING CENTER PROJECT TEST RESULTS  

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

PETRO-PLUG PETRO-PLUG BENTONITE PLUGGING JANUARY 27, 1998 Report No. RMOTC/97PT22 ROCKY MOUNTAIN OILFIELD TESTING CENTER PROJECT TEST RESULTS PETRO-PLUG BENTONITE PLUGGING Prepared for: INDUSTRY PUBLICATION Prepared by: Michael R. Tyler RMOTC Project Manager January 27, 1998 Report No. RMOTC/96ET4 CONTENTS Page Technical Description ...................................................................................................... 1 Problem ............................................................................................................................ 1 Solution ............................................................................................................................ 2 Operation..........................................................................................................................

293

Undulator Transportation Test Results  

SciTech Connect

A test was performed to determine whether transporting and handling the undulators makes any changes to their properties. This note documents the test. No significant changes to the test undulator were observed. After the LCLS undulators are tuned and fiducialized in the Magnetic Measurement Facility (MMF), they must be transported to storage buildings and transported to the tunnel. It has been established that the undulators are sensitive to temperature. We wish to know whether the undulators are also sensitive to the vibrations and shocks of transportation. To study this issue, we performed a test in which an undulator was measured in the MMF, transported to the tunnel, brought back to the MMF, and re-measured. This note documents the test and the results.

Wolf, Zachary

2010-11-17T23:59:59.000Z

294

Data-driven modeling and simulation framework for material handling systems in coal mines  

Science Conference Proceedings (OSTI)

In coal mining industry, discrete-event simulation has been widely used to support decisions in material handling system (MHS) to achieve premiums on revenues. However, the conventional simulation modeling approach requires extensive expertise of simulation ... Keywords: Coal mining, Data-driven modeling, Decision making, Material handling system

Chao Meng; Sai Srinivas Nageshwaraniyer; Amir Maghsoudi; Young-Jun Son; Sean Dessureault

2013-03-01T23:59:59.000Z

295

Design and realization of a microfluidic system for dielectrophoretic colloidal handling  

Science Conference Proceedings (OSTI)

Precise spatial localization of colloids is required to fully exploit the potential of colloidal handling in a microfluidic channel. In this work, we present the fabrication and integration of a new type of microfluidic chip that can provide such tools. ... Keywords: Colloidal handling, Dielectrophoresis, Microfluidics, Photopatternable silicones

T. Honegger; K. Berton; T. Pinedo-Rivera; D. Peyrade

2009-04-01T23:59:59.000Z

296

Optimization of Trajectories for the Cask and Plug Remote Handling System in Tokamak  

E-Print Network (OSTI)

May 2011 Optimization of Trajectories for the Cask and Plug Remote Handling System in Tokamak Building and Hot Cell Fusion for Energy Grant: F4E-GRT-276-01 (MS-RH) | April.2011-Oct.2011 o Partners| Project IST (F4E ­ ITER) #12;May 2011 Optimization of Trajectories for the Cask and Plug Remote Handling

Ribeiro,Isabel

297

Conceptual study on Flexible Guidance and Docking system for ITER Remote Handling  

E-Print Network (OSTI)

1 Conceptual study on Flexible Guidance and Docking system for ITER Remote Handling Transport Cask divertors and blanket modules from the Tokamak Building to the Hot Cell Building o Addressed topics for ITER Remote Handling Transport Cask o Publications from IST team: · Isabel Ribeiro, Pedro Lima, Pedro

Ribeiro,Isabel

298

V-007: McAfee Firewall Enterprise ISC BIND Record Handling Lockup  

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

7: McAfee Firewall Enterprise ISC BIND Record Handling Lockup 7: McAfee Firewall Enterprise ISC BIND Record Handling Lockup Vulnerability V-007: McAfee Firewall Enterprise ISC BIND Record Handling Lockup Vulnerability October 22, 2012 - 6:00am Addthis PROBLEM: McAfee Firewall Enterprise ISC BIND Record Handling Lockup Vulnerability PLATFORM: Versions 8.2.x prior to 8.2.1P06, and 8.3.x prior to 8.3.0P02 REFERENCE LINKS: Secunia Advisory SA51050 CVE-2012-5166 McAfee Corporate Knowledge Base IMPACT ASSESSMENT: Medium DISCUSSION: The vulnerability is caused due to an error when handling queries for certain records and can be exploited to cause the named process to lockup. IMPACT: If specific combinations of RDATA are loaded into a nameserver, either via cache or an authoritative zone, a subsequent query for a related record

299

Viability of Existing INL Facilities for Dry Storage Cask Handling R1 |  

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

Viability of Existing INL Facilities for Dry Storage Cask Handling Viability of Existing INL Facilities for Dry Storage Cask Handling R1 Viability of Existing INL Facilities for Dry Storage Cask Handling R1 While dry storage technologies are some of the safest in the world, the U.S. Department of Energy is planning a confirmatory dry storage project for high burnup fuel. This report evaluates existing capabilities at Idaho National Laboratory (INL) to determine if a practical and cost effective method could be developed for handling and opening full-sized dry storage casks. Existing facilities at the Idaho Nuclear Technology and Engineering Center provide the infrastructure to support handling and examining of casks and their contents. Based on a reasonable set of assumptions, it is possible to receive, open, inspect, remove samples, close, and reseal

300

EA-1793: Replacement Capability for Disposal of Remote-handled Low-level  

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

793: Replacement Capability for Disposal of Remote-handled 793: Replacement Capability for Disposal of Remote-handled Low-level Waste Generated at the Department of Energy's Idaho Site EA-1793: Replacement Capability for Disposal of Remote-handled Low-level Waste Generated at the Department of Energy's Idaho Site Summary This EA evaluates the environmental impacts of replacement capability for disposal of remote-handled low-level radioactive waste (LLW) generated at the Idaho National Laboratory (INL) site beginning in October 2017. Public Comment Opportunities Submit Comments to: Mr. Chuck Ljungberg 1955 Fremont Avenue, Mailstop 1216 Idaho Falls, ID 83415 Electronic mail: rhllwea@id.doe.gov Documents Available for Download December 21, 2011 EA-1793: Finding of No Significant Impact Replacement Capability for Disposal of Remote-Handled Low-Level Radioactive

Note: This page contains sample records for the topic "handling test prepared" 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

Effluent treatment options for nuclear thermal propulsion system ground tests  

DOE Green Energy (OSTI)

A variety of approaches for handling effluent from nuclear thermal propulsion system ground tests in an environmentally acceptable manner are discussed. The functional requirements of effluent treatment are defined and concept options are presented within the framework of these requirements. System concepts differ primarily in the choice of fission-product retention and waste handling concepts. The concept options considered range from closed cycle (venting the exhaust to a closed volume or recirculating the hydrogen in a closed loop) to open cycle (real time processing and venting of the effluent). This paper reviews the strengths and weaknesses of different methods to handle effluent from nuclear thermal propulsion system ground tests.

Shipers, L.R.; Brockmann, J.E.

1992-10-16T23:59:59.000Z

302

Rough Ride Test Procedure  

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

NTP005 NTP005 Revision 2 Effective December 1, 2004 Electric Vehicle Rough Road Course Test Prepared by Electric Transportation Applications Prepared by: _______________________________ Date:__________ Ryan Harkins Approved by: _________________________________________________ Date: _______________ Donald B. Karner ©2004 Electric Transportation Applications All Rights Reserved Procedure ETA-NTP005 Revision 2 2 TABLE OF CONTENTS 1.0 Objectives 3 2.0 Purpose 3 3.0 Documentation 3 4.0 Initial Conditions and Prerequisites 4 5.0 Testing Activity Requirements 6 6.0 Glossary 12 7.0 References 14 Appendices Appendix A - Electric Vehicle Rough Road Test Data Sheet 15

303

Preparation of vinyl acetate  

DOE Patents (OSTI)

This invention pertains to the preparation of vinyl acetate by contacting a mixture of hydrogen and ketene with a heterogeneous catalyst containing a transition metal to produce acetaldehyde, which is then reacted with ketene in the presence of an acid catalyst to produce vinyl acetate.

Tustin, Gerald Charles (Kingsport, TN); Zoeller, Joseph Robert (Kingsport, TN); Depew, Leslie Sharon (Kingsport, TN)

1998-01-01T23:59:59.000Z

304

Process for preparing radiopharmaceuticals  

DOE Patents (OSTI)

A process for the preparation of technetium-99m labeled pharmaceuticals is disclosed. The process comprises initially isolating technetium-99m pertechnetate by adsorption upon an adsorbent packing in a chromatographic column. The technetium-99m is then eluted from the packing with a biological compound to form a radiopharmaceutical.

Barak, Morton (Walnut Creek, CA); Winchell, Harry S. (Lafayette, CA)

1977-01-04T23:59:59.000Z

305

Preparation of uranium nitride  

DOE Patents (OSTI)

A process for preparing actinide-nitrides from massive actinide metal which is suitable for sintering into low density fuel shapes by partially hydriding the massive metal and simultaneously dehydriding and nitriding the dehydrided portion. The process is repeated until all of the massive metal is converted to a nitride.

Potter, Ralph A. (Lynchburg, VA); Tennery, Victor J. (Upper Arlington, OH)

1976-01-01T23:59:59.000Z

306

Preparation of vinyl acetate  

DOE Patents (OSTI)

This invention pertains to the preparation of vinyl acetate by contacting a mixture of hydrogen and ketene with a heterogeneous catalyst containing a transition metal to produce acetaldehyde, which is then reacted with ketene in the presence of an acid catalyst to produce vinyl acetate.

Tustin, G.C.; Zoeller, J.R.; Depew, L.S.

1998-03-24T23:59:59.000Z

307

Method for preparing superconductors  

DOE Patents (OSTI)

A superconductor having an equiaxed fine grain beta-tungsten crystalline structure found to have improved high field critical current densities is prepared by sputter-depositing superconductive material onto a substrate cooled to below 200.degree. C. and heat-treating the deposited material.

Dahlgren, Shelley D. (Richland, WA)

1976-01-01T23:59:59.000Z

308

Handling and Use Guide Fourth EditionNotice  

E-Print Network (OSTI)

This report was prepared as an account of work sponsored by an agency of the United States government. Neither the United States government nor any agency thereof, nor any of their employees, makes any warranty, express or implied, or assumes any legal liability or responsibility for the accuracy, completeness, or usefulness of any information, apparatus, product, or process disclosed, or represents that its use would not infringe privately owned rights. Reference herein to any specific commercial product, process, or service by trade name, trademark, manufacturer, or otherwise does not necessarily constitute or imply its endorsement, recommendation, or favoring by the United States government or any agency thereof. The views and opinions of authors expressed herein do not necessarily state or reflect those of the United States government or any agency thereof.

In Paper

2009-01-01T23:59:59.000Z

309

Advanced Aerodynamic Devices to Improve the Performance, Economics, Handling, and Safety of Heavy Vehicles  

Science Conference Proceedings (OSTI)

Research is being conducted at the Georgia Tech Research Institute (GTRI) to develop advanced aerodynamic devices to improve the performance, economics, stability, handling and safety of operation of Heavy Vehicles by using previously-developed and flight-tested pneumatic (blown) aircraft technology. Recent wind-tunnel investigations of a generic Heavy Vehicle model with blowing slots on both the leading and trailing edges of the trailer have been conducted under contract to the DOE Office of Heavy Vehicle Technologies. These experimental results show overall aerodynamic drag reductions on the Pneumatic Heavy Vehicle of 50% using only 1 psig blowing pressure in the plenums, and over 80% drag reductions if additional blowing air were available. Additionally, an increase in drag force for braking was confirmed by blowing different slots. Lift coefficient was increased for rolling resistance reduction by blowing only the top slot, while downforce was produced for traction increase by blowing only the bottom. Also, side force and yawing moment were generated on either side of the vehicle, and directional stability was restored by blowing the appropriate side slot. These experimental results and the predicted full-scale payoffs are presented in this paper, as is a discussion of additional applications to conventional commercial autos, buses, motor homes, and Sport Utility Vehicles.

Robert J. Englar

2001-05-14T23:59:59.000Z

310

Spent nuclear fuel shipping cask handling capabilities of commercial light water reactors  

Science Conference Proceedings (OSTI)

This report describes an evaluation of the cask handling capabilities of those reactors which are operating or under construction. A computerized data base that includes cask handling information was developed with information from the literature and utility-supplied data. The capability of each plant to receive and handle existing spent fuel shipping casks was then evaluated. Modal fractions were then calculated based on the results of these evaluations and the quantities of spent fuel projected to be generated by commercial nuclear power plants through 1998. The results indicated that all plants are capable of receiving and handling truck casks. Up to 118 out of 130 reactors (91%) could potentially handle the larger and heavier rail casks if the maximum capability of each facility is utilized. Design and analysis efforts and physical modifications to some plants would be needed to achieve this high rail percentage. These modifications would be needed to satisfy regulatory requirements, increase lifting capabilities, develop rail access, or improve other deficiencies. The remaining 12 reactors were determined to be capable of handling only the smaller truck casks. The percentage of plants that could receive and handle rail casks in the near-term would be reduced to 64%. The primary reason for a plant to be judged incapable of handling rail casks in the near-term was a lack of rail access. The remaining 36% of the plants would be limited to truck shipments. The modal fraction calculations indicated that up to 93% of the spent fuel accumulated by 1998 could be received at federal storage or disposal facilities via rail (based on each plant's maximum capabilities). If the near-term cask handling capabilities are considered, the rail percentage is reduced to 62%.

Daling, P.M.; Konzek, G.J.; Lezberg, A.J.; Votaw, E.F.; Collingham, M.I.

1985-04-01T23:59:59.000Z

311

ROCKY MOUNTAIN OILFIELD TESTING CENTER PROJECT TEST RESULTS  

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

D-JAX PUMP-OFF CONTROLLER D-JAX PUMP-OFF CONTROLLER APRIL 4,1995 FC9510 / 95PT4 ROCKY MOUNTAIN OILFIELD TESTING CENTER D-JAX PUMP-OFF CONTROLLER PROJECT TEST RESULTES Prepared for: Industry Publication Prepared by: MICHAEL R. TYLER RMOTC Field Engineer April 4, 1995 55103/9510:jb CONTENTS Page Introduction........................................................................................1 NPR-3 Map........................................................................................2 Benefits of D-JAX Pump-Off Controller.....................................................3 Test Results.......................................................................................3 Production Information..........................................................................4

312

Secretary Directs FPO to Prepare Strategic Plan  

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

January 2004 Volume 1, Number 2 January 2004 Volume 1, Number 2 In This Issue * Executive Order Update * $1 Million for Manhattan Project Preservation * 2004 DOE Cultural Resources Forum * ES&H Cultural Resources Update * FPO Site Visits * Oak Ridge Historic Preservation Update * Featured Site: Pantex * Save America's Treasures * Manhattan Project Interactive Website * Goucher College: HP Education Opportunity * Atomic Testing Museum Moves Forward Secretary Directs FPO to Prepare Strategic Plan On December 2, 2003, Secretary of Energy Spencer Abraham directed DOE's Federal Preservation Officer, Chief Historian F. G. Gosling, to prepare a strategic plan for the Department's history and historic preservation/cultural resource management programs. The Secretary (right) gave Gosling 90

313

RMOTC TEST REPORT  

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

MUD DEVIL - DEAERATOR MIXER MUD DEVIL - DEAERATOR MIXER MARCH 30, 1995 RMOTC TEST REPORT Mud Devil - Deaerator Mixer Project Test Results Prepared for: INDUSTRY PUBLICATION Prepared by: MICHAEL R. TYLER RMOTC Field Engineer March 30, 1995 551103/9507:jb ABSTRACT The Rocky Mountain Oilfield Testing Center (RMOTC) conducted a field test on the MUD DEVIL - Deaerator Mixer (MDDM), at the Naval Oil Shale Reserve No. 3 (NOSR-3) located west of Rifle, Colorado. Industrial Screen and Maintenance of Casper, Wyoming, manufactures the MDDM high-shear pin mixing system used to blend products in drilling fluid systems. The test was a comparison between DOE Well 1 -M-1 8 drilled without the MDDM and a sidetrack Well 1-M-18 ST drilled with the MDDM. Test results show that the MDDM, when properly used, reduced the usage of drilling fluid products, decreased water

314

Test Plan for Evaluating Hammer and Fixed Cutter Grinders Using Multiple Varieties and Moistures of Biomass Feedstock  

Science Conference Proceedings (OSTI)

Biomass preprocessing is a critical operation in the preparation of feedstock for the front-end of a cellulosic ethanol biorefinery. Its purpose is to chop, grind, or otherwise format the biomass material into a suitable feedstock for optimum conversion to ethanol and other bioproducts. Without this operation, the natural size, bulk density, and flowability characteristics of harvested biomass would decrease the capacities and efficiencies of feedstock assembly unit operations and biorefinery conversion processes to the degree that programmatic cost targets could not be met. The preprocessing unit operation produces a bulk flowable material that 1) improves handling and conveying efficiencies throughout the feedstock assembly system and biorefinery 2) increases biomass surface areas for improved pretreatment efficiencies, 3) reduces particle sizes for improved feedstock uniformity and density, and 4) fractionates structural components for improved compositional quality. The Idaho National Laboratory (INL) is tasked with defining the overall efficiency/effectiveness of current commercial hammer and fixed cutter grinding systems and other connecting systems such as harvest and collection, storage, transportation, and handling for a wide variety of feedstock types used in bioethanol or syngas production. This test plan details tasks and activities for two separate full-scale grinding tests: Material Characterization Test and Machine Characterization Test. For the Material Characterization Test, a small amount (~5-7 tons each) of several feedstock varieties will be ground. This test will define the fractionation characteristics of the grinder that affect the bulk density, particle size distribution, and quality of the size reduced biomass resulting from different separation screen sizes. A specific screen size will be selected based on the characteristics of the ground material. The Machine Characterization Test will then use this selected screen to grind several 30-ton batches of different feedstock varieties and moistures. This test will focus on identifying the performance parameters of the grinding system specific to the feed, fractionation, and screen separation components and their affect on machine capacity and efficiency.

Not listed

2007-07-01T23:59:59.000Z

315

Internal Audit Preparation Worksheet  

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

5 ILT Course Support Checklist 10_0630 Page 1 of 4 5 ILT Course Support Checklist 10_0630 Page 1 of 4 EOTA - Business Form Document Title: ILT/Exercise Initial Preparation Checklist Document Number: ISDF-015 Rev. 10_0630 Document Owner: Elizabeth Sousa Backup Owner: Melissa Otero Approver(s): Melissa Otero Parent Document: ISDP-002, Training Production Process Notify of Changes: EOTA Employees Referenced Document(s): ITTP-012 Graphic Design Support Process, ISDF-018 Course Roster ISDF-008 ILT Student Feedback Survey ISDF-015 ILT Course Support Checklist 10_0630 Page 2 of 4 Revision History: Rev. Description of Change A Initial Release 10_0630 Modified to accompany TPP ISDF-015 ILT Course Support Checklist 10_0630 Page 3 of 4 ILT/Exercise Initial Preparation Checklist Anticipated

316

Preparing for the Unexpected  

E-Print Network (OSTI)

We can reduce the risk of injury or death from disasters by becoming informed and being prepared for them. This booklet explains how to make a family disaster plan, how to compile a disaster supplies kit, where to find help, and how to get involved in community efforts for disaster preparedness. It also includes special sections on children, food safety, pets, septic systems, and farms and ranches.

Harris, Janie; Norman, Lisa; Lesikar, Bruce J.; Smith, David

2007-03-26T23:59:59.000Z

317

TORIS Data Preparation Guidelines  

SciTech Connect

The objective of this manual is to present guidelines and procedures for the preparation of new data for the Tertiary Oil Recovery Information System (TORIS) data base. TORIS is an analytical system currently maintained by the Department of Energy's (DOE) Bartlesville Project Office. It uses an extensive field- and reservoir-level data base to evaluate the technical and economic recovery potential of specific crude oil reservoirs.

Guinn, H.; Remson, D.

1999-03-11T23:59:59.000Z

318

PREPARATION OF PLUTONIUM HALIDES  

DOE Patents (OSTI)

A process ls presented for the preparation of plutonium trihalides. Plutonium oxide or a compound which may be readily converted to plutonlum oxide, for example, a plutonium hydroxide or plutonlum oxalate is contacted with a suitable halogenating agent. Speciflc agents mentioned are carbon tetrachloride, carbon tetrabromide, sulfur dioxide, and phosphorus pentachloride. The reaction is carried out under superatmospberic pressure at about 300 icient laborato C.

Davidson, N.R.; Katz, J.J.

1958-11-01T23:59:59.000Z

319

PREPARATION OF URANIUM HEXAFLUORIDE  

DOE Patents (OSTI)

A process is described for preparing uranium hexafluoride from carbonate- leach uranium ore concentrate. The briquetted, crushed, and screened concentrate is reacted with hydrogen fluoride in a fluidized bed, and the uranium tetrafluoride formed is mixed with a solid diluent, such as calcium fluoride. This mixture is fluorinated with fluorine and an inert diluent gas, also in a fluidized bed, and the uranium hexafluoride obtained is finally purified by fractional distillation.

Lawroski, S.; Jonke, A.A.; Steunenberg, R.K.

1959-10-01T23:59:59.000Z

320

Internal Audit Preparation Worksheet  

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

ISDF-030 Test Matrix 11_0303 Page 1 of 6 ISDF-030 Test Matrix 11_0303 Page 1 of 6 EOTA - Business Process Document Title: Test Matrix Document Number: ISDP-030 Rev. 11_0303 Document Owner: Elizabeth Sousa Backup Owner: Melissa Otero Approver(s): Melissa Otero Parent Document: ISDP-002, Training Production Process Notify of Changes: ISD, ITT, MGT Referenced Document(s): ISDF-001 Technical Direction, ISDF-045 Analysis Project Plan, ISDF-004 Design Document, ISDF-006 WBT Script Template, ISDF-007 Lesson Plan Template, ITTP-016 WBT Programming, ISDP-002 Training Production Process ISDF-030 Test Matrix 11_0303 Page 2 of 6 Revision History: Rev. Description of Change 10_0630 Initial Release 11_0303 Updated table Test Matrix (Goals, Objectives, Corresponding Knowledge Check and Test Questions, and Content Location)

Note: This page contains sample records for the topic "handling test prepared" 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

WIPP Receives First Remote-Handled Waste Shipment From Sandia Labs |  

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

First Remote-Handled Waste Shipment From Sandia Labs First Remote-Handled Waste Shipment From Sandia Labs WIPP Receives First Remote-Handled Waste Shipment From Sandia Labs December 21, 2011 - 12:00pm Addthis Media Contact Deb Gill www.wipp.energy.gov 575-234-7270 CARLSBAD, N.M. - The U.S. Department of Energy's (DOE) Waste Isolation Pilot Plant (WIPP) has received the first of eight planned defense-related remote-handled transuranic (RH-TRU) waste shipments from Sandia National Laboratories (SNL) in Albuquerque. The shipment arrived December 16 for permanent disposal in WIPP's underground repository. DOE National TRU Program Director J.R. Stroble said the shipment is significant to WIPP. "Our goal is to reduce the nation's nuclear waste footprint and we routinely receive shipments from around the country,"

322

V-217: Microsoft Windows NAT Driver ICMP Packet Handling Denial of Service  

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

7: Microsoft Windows NAT Driver ICMP Packet Handling Denial of 7: Microsoft Windows NAT Driver ICMP Packet Handling Denial of Service Vulnerability V-217: Microsoft Windows NAT Driver ICMP Packet Handling Denial of Service Vulnerability August 14, 2013 - 6:00am Addthis PROBLEM: A vulnerability was reported in the Windows NAT Driver PLATFORM: Windows Server 2012 ABSTRACT: This security update resolves a vulnerability in the Windows NAT Driver in Microsoft Windows REFERENCE LINKS: Secunia Advisory SA54420 Security Tracker ID 1028909 Microsoft Security Bulletin MS13-064 CVE-2013-3182 IMPACT ASSESSMENT: Medium DI SCUSSION: The vulnerability is caused due to an error within the Windows NAT Driver when handling ICMP packets and can be exploited to cause the system to stop responding IMPACT: Denial of Service SOLUTION: Vendor has released a security update

323

State of New Mexico Issues Permit For Remote-Handled Waste at WIPP |  

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

of New Mexico Issues Permit For Remote-Handled Waste at WIPP of New Mexico Issues Permit For Remote-Handled Waste at WIPP State of New Mexico Issues Permit For Remote-Handled Waste at WIPP October 16, 2006 - 1:35pm Addthis Enables DOE to Permanently Move Waste to the WIPP Repository for Safe Disposal CARLSBAD, NM - U.S. Department of Energy (DOE) today announced that the New Mexico Environment Department (NMED) issued a revised hazardous waste facility permit for DOE's Waste Isolation Pilot Plant (WIPP) in Carlsbad, New Mexico. The revised permit enables WIPP to receive and dispose of remote-handled (RH) transuranic (TRU) radioactive waste currently stored at DOE clean-up sites across the country. WIPP expects to receive its first RH-TRU waste shipment in the coming months, as soon as the regulatory approvals are obtained.

324

T-656: Microsoft Office Visio DXF File Handling Arbitrary Code Execution  

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

6: Microsoft Office Visio DXF File Handling Arbitrary Code 6: Microsoft Office Visio DXF File Handling Arbitrary Code Execution Vulnerability T-656: Microsoft Office Visio DXF File Handling Arbitrary Code Execution Vulnerability June 28, 2011 - 3:42pm Addthis PROBLEM: Functional code that demonstrates an exploit of the Microsoft Office Visio DXF file handling arbitrary code execution vulnerability is publicly available. PLATFORM: Microsoft Office Visio 2002 SP2 and prior Microsoft Office Visio 2003 SP3 and prior Microsoft Office Visio 2007 SP2 and prior ABSTRACT: Microsoft Office Visio contains a vulnerability that could allow an unauthenticated, remote attacker to execute arbitrary code on a targeted system. reference LINKS: IntelliShield ID: 20432 Original Release: S516 CVE-2010-1681 IMPACT ASSESSMENT: High Discussion: The vulnerability exists because the affected software does not perform

325

Thread-Specific Data and Signal Handling in Multi-Threaded Applications  

Science Conference Proceedings (OSTI)

This second part of a series on Multi-threading deals with how to use C programs with one of the POSIX packages available for Linux to handle signals and concurrent threads

Martin McCarthy

1997-04-01T23:59:59.000Z

326

Criticality Safety Evaluation Report for the Cold Vacuum Drying (CVD) Facilities Process Water Handling System  

SciTech Connect

This report addresses the criticality concerns associated with process water handling in the Cold Vacuum Drying Facility. The controls and limitations on equipment design and operations to control potential criticality occurrences are identified.

KESSLER, S.F.

2000-08-10T23:59:59.000Z

327

ARRA Material Handling Equipment Composite Data Products: Data through Quarter 2 of 2012  

DOE Green Energy (OSTI)

This presentation from the U.S. Department of Energy's National Renewable Energy Laboratory includes American Recovery and Reinvestment Act (ARRA) fuel cell material handling equipment composite data products for data through the second quarter of 2012.

Kurtz, J.; Sprik, S.; Ramsden, T.; Ainscough, C.; Saur, G.

2012-10-01T23:59:59.000Z

328

Frying Technology and PracticesChapter 5 Procedures for Oil Handling in a Frying Operation  

Science Conference Proceedings (OSTI)

Frying Technology and Practices Chapter 5 Procedures for Oil Handling in a Frying Operation Food Science Health Nutrition Biochemistry eChapters Food Science & Technology Health - Nutrition - Biochemistry Press Downloa

329

U-226: Linux Kernel SFC Driver TCP MSS Option Handling Denial...  

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

August 2, 2012 - 7:00am Addthis PROBLEM: Linux Kernel SFC Driver TCP MSS Option Handling Denial of Service Vulnerability PLATFORM: Linux Kernel 3.2.x ABSTRACT: The Linux...

330

Soap Manufacturing TechnologyChapter 13 Soap Making Raw Materials: Their Sources, Specifications, Markets, and Handling  

Science Conference Proceedings (OSTI)

Soap Manufacturing Technology Chapter 13 Soap Making Raw Materials: Their Sources, Specifications, Markets, and Handling Surfactants and Detergents eChapters Surfactants - Detergents Press Downloadable pdf of\tCha

331

ARRA Material Handling Equipment Composite Data Products: Data Through Quarter 4 of 2012  

DOE Green Energy (OSTI)

This presentation from the U.S. Department of Energy's National Renewable Energy Laboratory includes American Recovery and Reinvestment Act (ARRA) fuel cell material handling equipment composite data products for data through the fourth quarter of 2012.

Kurtz, J.; Sprik, S.; Ainscough, C.; Saur, G.; Post, M.; Peters, M.; Ramsden, T.

2013-05-01T23:59:59.000Z

332

A Novel Dynamic Voltage Restorer with Outage Handling Capability Using Fuzzy Logic Controler  

Science Conference Proceedings (OSTI)

This paper presents a novel dynamic voltage restorer (DVR) capable of handling deep sags including outage on a low voltage distribution system. The DVR recovers sags up to 10% of nominal voltage; otherwise, it will operate as an uninterruptible power ...

M. Ashari; T. Hiyama; M. Pujiantara; H. Suryoatmojo; M. Hery Purnomo

2007-09-01T23:59:59.000Z

333

V-177: VMware vCenter Chargeback Manager File Upload Handling Vulnerability  

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

177: VMware vCenter Chargeback Manager File Upload Handling 177: VMware vCenter Chargeback Manager File Upload Handling Vulnerability V-177: VMware vCenter Chargeback Manager File Upload Handling Vulnerability June 13, 2013 - 6:00am Addthis PROBLEM: vCenter Chargeback Manager Remote Code Execution PLATFORM: VMware vCenter Chargeback Manager 2.x ABSTRACT: The vCenter Chargeback Manager contains a critical vulnerability that allows for remote code execution REFERENCE LINKS: Secunia Advisory SA53798 VMWare Security Advisory VMSA-2013-0008 CVE-2013-3520 IMPACT ASSESSMENT: Medium DISCUSSION: The vCenter Chargeback Manager (CBM) contains a flaw in its handling of file uploads. Exploitation of this issue may allow an unauthenticated attacker to execute code remotely. IMPACT: System Access SOLUTION: Vendor recommends updating to version 2.5.1

334

U-226: Linux Kernel SFC Driver TCP MSS Option Handling Denial of Service  

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

6: Linux Kernel SFC Driver TCP MSS Option Handling Denial of 6: Linux Kernel SFC Driver TCP MSS Option Handling Denial of Service Vulnerability U-226: Linux Kernel SFC Driver TCP MSS Option Handling Denial of Service Vulnerability August 2, 2012 - 7:00am Addthis PROBLEM: Linux Kernel SFC Driver TCP MSS Option Handling Denial of Service Vulnerability PLATFORM: Linux Kernel 3.2.x ABSTRACT: The Linux kernel is prone to a remote denial-of-service vulnerability. reference LINKS: Secunia Advisory SA50081 Bugtraq ID: 54763 Vulnerability Report: Linux Kernel 3.2.x The Linux Kernel Archives Original Advisory CVE-2012-3412 IMPACT ASSESSMENT: Medium Discussion: A vulnerability has been reported in Linux Kernel, which can be exploited by malicious people to cause a DoS (Denial of Service). The vulnerability is caused due to an error in the Solarflare network

335

Dynamical Control in Large-Scale Material Handling Systems through Agent Technology  

Science Conference Proceedings (OSTI)

Delayed arrivals, missing tag codes, flight changes, break-downs, etc. are some of the factors, which make the environment of airport baggage handling systems (BHS) extremely dynamic. Pre-scheduling and optimization is not an option, as identity, destination, ...

Kasper Hallenborg; Yves Demazeau

2006-12-01T23:59:59.000Z

336

Assessing 1D Atmospheric Solar Radiative Transfer Models: Interpretation and Handling of Unresolved Clouds  

Science Conference Proceedings (OSTI)

The primary purpose of this study is to assess the performance of 1D solar radiative transfer codes that are used currently both for research and in weather and climate models. Emphasis is on interpretation and handling of unresolved clouds. ...

H. W. Barker; G. L. Stephens; P. T. Partain; J. W. Bergman; B. Bonnel; K. Campana; E. E. Clothiaux; S. Clough; S. Cusack; J. Delamere; J. Edwards; K. F. Evans; Y. Fouquart; S. Freidenreich; V. Galin; Y. Hou; S. Kato; J. Li; E. Mlawer; J.-J. Morcrette; W. O'Hirok; P. Räisänen; V. Ramaswamy; B. Ritter; E. Rozanov; M. Schlesinger; K. Shibata; P. Sporyshev; Z. Sun; M. Wendisch; N. Wood; F. Yang

2003-08-01T23:59:59.000Z

337

SAFETY CONSIDERATIONS FOR HANDLING PLUTONIUM, URANIUM, THORIUM, THE ALKALI METALS, ZIRCONIUM, TITANIUM, MAGNESIUM, AND CALCIUM  

SciTech Connect

BS>This report compiles from various sources safety considerations for work with the special metals plutonium, uranium, thorium, the alkali group, magnesium, titanium, calcium, and zirconium. General criteria to be observed in handling all of these metals and their alloys are listed, as well as characteristics of individual metals with regard to health hazards, pyrophoricity, explosiveness, and other chemical reactions, in both handling and storage. (auth)

Stout, E.L. comp.

1957-09-01T23:59:59.000Z

338

Paper Preparation Guidelines  

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

5E 5E MAPPING HVAC SYSTEMS FOR SIMULATION IN ENERGYPLUS Author(s), Mangesh Basarkar, James O'Donnell, Philip Haves, Kevin Settlemyre and Tobias Maile Environmental Energy and Technologies Division July 2012 To be presented at the SimBuild 2012 IBPSA Conference DISCLAIMER This document was prepared as an account of work sponsored by the United States Government. While this document is believed to contain correct information, neither the United States Government nor any agency thereof, nor The Regents of the University of California, nor any of their employees, makes any warranty, express or implied, or assumes

339

Integrated Geothermal Well Testing: Test Objectives and Facilities  

DOE Green Energy (OSTI)

A new and highly integrated geothermal well test program was designed for three geothermal operators in the US (MCR, RGI and Mapco Geothermal). This program required the design, construction and operation of new well test facilities. The main objectives of the test program and facilities are to investigate the critical potential and worst problems associated with the well and produced fluids in a period of approximately 30 days. Field and laboratory investigations are required to determine and quantify the problems of fluid production, utilization and reinjection. The facilities are designed to handle a flow rate from a geothermal well of one million pounds per hour at a wellhead temperature of approximately 268 C (515 F). The facilities will handle an entire spectrum of temperature and rate conditions up to these limits. All pertinent conditions for future fluid exploitations can be duplicated with these facilities, thus providing critical information at the very early stages of field development. The new well test facilities have been used to test high temperature, liquid-dominated geothermal wells in the Imperial Valley of California. The test facilities still have some problems which should be solvable. The accomplishments of this new and highly integrated geothermal well test program are described in this paper.

Nicholson, R. W.; Vetter, O. J.

1981-01-01T23:59:59.000Z

340

EV America Skid Test Procedure  

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

3 3 Revision 1 Effective June 2008 Battery Capacity and Depth of Discharge Test Prepared by Electric Transportation Applications Prepared by: _______________________________ Date:__________ Garrett P. Beauregard Approved by: ______________________________________________ Date: _______________ Donald B. Karner Procedure ETA-GTP003 Revision 1 2 Table of Contents 1 Objective ..................................................................................................................... 3 2 Purpose........................................................................................................................ 3 3 Documentation............................................................................................................

Note: This page contains sample records for the topic "handling test prepared" 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

EV America Skid Test Procedure  

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

2 2 Revision 1 Effective June 2008 Traction System Test Prepared by Electric Transportation Applications Prepared by: _______________________________ Date:__________ Garrett P. Beauregard Approved by: ______________________________________________ Date: _______________ Donald B. Karner Procedure ETA-GTP002 Revision 1 2 Table of Contents 1 Objective ..................................................................................................................... 3 2 Purpose........................................................................................................................ 3 3 Documentation............................................................................................................

342

EV America Skid Test Procedure  

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

4 4 Revision 1 Effective June 2008 Electromagnetic Interference and Susceptibility Test Prepared by Electric Transportation Applications Prepared by: _______________________________ Date:__________ Garrett P. Beauregard Approved by: ______________________________________________ Date: _______________ Donald B. Karner Procedure ETA-GTP004 Revision 1 2 Table of Contents 1 Objective ..................................................................................................................... 3 2 Purpose........................................................................................................................ 3 3 Documentation............................................................................................................

343

Recycle Experience of Dismantled Cask Handling Crane by Surface Removal Sampling at Kori Unit No.1  

SciTech Connect

The Kori No.1, which began operation in 1978, replaced its cask handling crane in 2000. To prove the safety of recycling and reuse of crane scrap, a particular calculation method for surface contamination was used. Because surface radioactive contamination of steel is limited to a few-microns-thick layer, we can calculate the total(removable and fixed contamination) activity of the sample conservatively by this surface removal sampling means. If we multiply the ratio of total surface and the area of the selected surface by its activity, total activity of the scrap can be estimated. Conservatively, the sampled portion can be used as a representative sample of the scrap. Both the inner and outer part of the scrap was sampled separately, and gamma spectra were analyzed to check whether activation had occurred. Before sampling, the entire surface of the steel is scan surveyed by several kinds of GM and GP detectors. Contaminated parts were segregated, or decontaminated to the background. Almost one sample per one ton of steel was collected. Gamma spectra of 62 samples were analyzed by 100% efficiency HP Ge detector. Only 60Co was detected, and its highest activity was 0.01 Bq/g,. This level of activity is much lower than the ''clearance levels'' outlined in IAEA TecDoc-855.(4). The total alpha and total beta for 6 samples were measured in the laboratory by low background alpha, using a beta gas proportional counter. Activities were much lower than 0.005 Bq/g. A representative sample was taken from the complete mixture of 62 samples. Gamma activities of nuclides were measured to estimate the dose to the public. This study revealed that activities of nuclides were lower than 'clearance levels' if decontaminated until the lower limit of detection level of the portable field instrument. New surface removal sampling method was tested. This method allows us to easily calculate the specific activity for the solid material.

Kim, K. D.; Baeg, C. Y.; Son, J. K.; Kim, H. S.; Ha, J. A.; Song, M. J.

2002-02-25T23:59:59.000Z

344

Materials Preparation Center | Ames Laboratory  

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

Materials Preparation Center Materials Preparation Center Materials Preparation Center The Materials Preparation Center (MPC) is a U.S. Department of Energy, Office of Science, Office of Basic Energy Sciences, Division of Materials Sciences & Engineering specialized research center located at the Ames Laboratory. MPC operations are primarily funded by the Materials Discovery, Design, & Synthesis team's Synthesis & Processing Science core research activity. MPC is recognized throughout the worldwide research community for its unique capabilities in purification, preparation, and characterization of: Rare earth metals [learn about rare earths] Single crystal growth Metal Powders/Atomization Alkaline-earth metals [learn more, wikipedia] External Link Icon Refractory metal [learn more, wikipedia] External Link Icon

345

Characterization of spent fuel approved testing material: ATM-106  

Science Conference Proceedings (OSTI)

The characterization data obtained to date are described for Approved Testing Material (ATM)-106 spent fuel from Assembly BT03 of pressurized-water reactor Calvert Cliffs No. 1. This report is one in a series being prepared by the Materials Characterization Center at Pacific Northwest Laboratory on spent fuel ATMs. The ATMs are receiving extensive examinations to provide a source of well- characterized spent fuel for testing in the US Department of Energy Office of Civilian Radioactive Waste Management (OCWRM) program. ATM-106 consists of 20 full-length irradiated fuel rods with rod-average burnups of about 3700 GJ/kgM (43 MWd/kgM) and expected fission gas release of /approximately/10%. Characterization data include (1) as-fabricated fuel design, irradiation history, and subsequent storage and handling; (2) isotopic gamma scans; (3) fission gas analyses; (4) ceramography of the fuel and metallography of the cladding; (5) calculated nuclide inventories and radioactivities in the fuel and cladding; and (6) radiochemical analyses of the fuel and cladding. Additional analyses of the fuel rod are being conducted and will be included in planned revisions of this report. 12 refs., 110 figs., 81 tabs.

Guenther, R.J.; Blahnik, D.E.; Campbell, T.K.; Jenquin, U.P.; Mendel, J.E.; Thornhill, C.K.

1988-10-01T23:59:59.000Z

346

Characterization of spent fuel approved testing material---ATM-105  

Science Conference Proceedings (OSTI)

The characterization data obtained to data are described for Approved Testing Material 105 (ATM-105), which is spent fuel from Bundles CZ346 and CZ348 of the Cooper Nuclear Power Plant, a boiling-water reactor. This report is one in a series being prepared by the Materials Characterization Center at Pacific Northwest Laboratory (PNL) on spent fuel ATMs. The ATMs are receiving extensive examinations to provide a source of well-characterized spent fuel for testing in the US Department of Energy Office of Civilian Radioactive Waste Management (OCRWM) Program. ATM-105 consists of 88 full-length irradiated fuel rods with rod-average burnups of about 2400 GJ/kgM (28 MWd/kgM) and expected fission gas release of about 1%. Characterization data include (1) descriptions of as-fabricated fuel design, irradiation history, and subsequent storage and handling; (2) isotopic gamma scans; (3) fission gas analyses; (4) ceramography of the fuel and metallography of the cladding; (5) special fuel studies involving analytical transmission electron microscopy (AEM); (6) calculated nuclide inventories and radioactivities in the fuel and cladding; and (7) radiochemical analyses of the fuel and cladding. Additional analyses of the fuel are being conducted and will be included in planned revisions of this report.

Guenther, R.J.; Blahnik, D.E.; Campbell, T.K.; Jenquin, U.P.; Mendel, J.E.; Thomas, L.E.; Thornhill, C.K.

1991-12-01T23:59:59.000Z

347

Characterization of spent fuel approved testing material--ATM-104  

SciTech Connect

The characterization data obtained to date are described for Approved Testing Material 104 (ATM-104), which is spent fuel from Assembly DO47 of the Calvert Cliffs Nuclear Power Plant (Unit 1), a pressurized-water reactor. This report is one in a series being prepared by the Materials Characterization Center at Pacific Northwest Laboratory (PNL) on spent fuel ATMs. The ATMs are receiving extensive examinations to provide a source of well-characterized spent fuel for testing in the US Department of Energy Office of Civilian Radioactive Waste Management (OCRWM) Program. ATM-104 consists of 128 full-length irradiated fuel rods with rod-average burnups of about 42 MWd/kgM and expected fission gas release of about 1%. A variety of analyses were performed to investigate cladding characteristics, radionuclide inventory, and redistribution of fission products. Characterization data include (1) fabricated fuel design, irradiation history, and subsequent storage and handling history; (2) isotopic gamma scans; (3) fission gas analyses; (4) ceramography of the fuel and metallography of the cladding; (5) special fuel studies involving analytical transmission electron microscopy (AEM) and electron probe microanalyses (EPMA); (6) calculated nuclide inventories and radioactivities in the fuel and cladding; and (7) radiochemical analyses of the fuel and cladding.

Guenther, R.J.; Blahnik, D.E.; Jenquin, U.P.; Mendel, J.E.; Thomas, L.E.; Thornhill, C.K.

1991-12-01T23:59:59.000Z

348

Material handling for the Los Alamos National Laboratory Nuclear Material Storage Facility  

SciTech Connect

This paper will present the design and application of material handling and automation systems currently being developed for the Los Alamos National Laboratory (LANL) Nuclear Material Storage Facility (NMSF) renovation project. The NMSF is a long-term storage facility for nuclear material in various forms. The material is stored within tubes in a rack called a basket. The material handling equipment range from simple lift assist devices to more sophisticated fully automated robots, and are split into three basic systems: a Vault Automation System, an NDA automation System, and a Drum handling System. The Vault Automation system provides a mechanism to handle a basket of material cans and to load/unload storage tubes within the material vault. In addition, another robot is provided to load/unload material cans within the baskets. The NDA Automation System provides a mechanism to move material within the small canister NDA laboratory and to load/unload the NDA instruments. The Drum Handling System consists of a series of off the shelf components used to assist in lifting heavy objects such as pallets of material or drums and barrels.

Pittman, P.; Roybal, J.; Durrer, R.; Gordon, D.

1999-04-01T23:59:59.000Z

349

ROCKY MOUNTAIN OILFIELD TESTING CENTER  

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

ALLIED OIL & TOOL POWERJET SLOTTING TOOL ALLIED OIL & TOOL POWERJET SLOTTING TOOL JANUARY 10, 1996 FC9522 / 95DT3 ROCKY MOUNTAIN OILFIELD TESTING CENTER PROJECT TEST RESULTS ALLIED OIL & TOOL POWERJET SLOTTING TOOL Prepared for: INDUSTRY PUBLICATION Prepared by: RALPH SCHULTE RMOTC Project Engineer January 11, 1996 551103/9522:jb CONTENTS Page Summary .......................................................................................................................2 Introduction.....................................................................................................................2 Description of Operations...................................................................................................3 Figure 1 ..........................................................................................................5

350

ROCKY MOUNTAIN OILFIELD TESTING CENTER PROJECT TEST RESULTS  

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

PETROLEUM MAGNETICS INTERNATIONAL PETROLEUM MAGNETICS INTERNATIONAL NOVEMBER 28, 1996 FC9520 / 95PT8 ROCKY MOUNTAIN OILFIELD TESTING CENTER PROJECT TEST RESULTS PETROLEUM MAGNETIC INTERNATIONAL DOWNHOLE MAGNETS FOR SCALE CONTROL Prepared for: Industry Publication Prepared by: MICHAEL R. TYLER RMOTC Field Engineer November 28, 1995 650100/9520:jb ABSTRACT November 28, 1995 The Rocky Mountain Oilfield Testing Center (RMOTC) conducted a field test on the Petroleum Magnetics International (PMI) downhole magnet, at the Naval Petroleum Reserve No. 3 (NPR- 3) located 35 miles north of Casper in Natrona County, Wyoming. PMI of Odessa, Texas, states that the magnets are designed to reduce scale and paraffin buildup on the rods, tubing

351

Assessment of Geochemical Environment for the Proposed INL Remote-Handled Low-Level Waste Disposal Facility  

Science Conference Proceedings (OSTI)

Conservative sorption parameters have been estimated for the proposed Idaho National Laboratory Remote-Handled Low-Level Waste Disposal Facility. This analysis considers the influence of soils, concrete, and steel components on water chemistry and the influence of water chemistry on the relative partitioning of radionuclides over the life of the facility. A set of estimated conservative distribution coefficients for the primary media encountered by transported radionuclides has been recommended. These media include the vault system, concrete-sand-gravel mix, alluvium, and sedimentary interbeds. This analysis was prepared to support the performance assessment required by U.S. Department of Energy Order 435.1, 'Radioactive Waste Management.' The estimated distribution coefficients are provided to support release and transport calculations of radionuclides from the waste form through the vadose zone. A range of sorption parameters are provided for each key transport media, with recommended values being conservative. The range of uncertainty has been bounded through an assessment of most-likely-minimum and most-likely-maximum distribution coefficient values. The range allows for adequate assessment of mean facility performance while providing the basis for uncertainty analysis.

D. Craig Cooper

2011-11-01T23:59:59.000Z

352

Microsoft Word - Los Alamos National Laboratory ships remote-handled transuranic waste to WIPP  

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

Los Alamos National Laboratory Ships Remote-Handled Los Alamos National Laboratory Ships Remote-Handled Transuranic Waste to WIPP CARLSBAD, N.M., June 3, 2009 - Cleanup of the nation's defense-related transuranic (TRU) waste has reached an important milestone. Today, the first shipment of remote-handled (RH) TRU waste from Los Alamos National Laboratory (LANL) in New Mexico arrived safely at the U.S. Department of Energy's (DOE) Waste Isolation Pilot Plant (WIPP) in the southeast corner of the state. "Shipping this waste to WIPP is important for our national cleanup mission, but this event is especially important for New Mexicans," said DOE Carlsbad Field Office Manager Dave Moody. "It's great to see progress being made right here in our own state." WIPP's mission includes the safe disposal of two types of defense-related

353

29 C.F.R. Part 24: Procedures for the Handling of Retaliation Complaints  

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

Part 24: Procedures for the Handling of Retaliation Part 24: Procedures for the Handling of Retaliation Complaints under Federal Employee Protection Statutes 29 C.F.R. Part 24: Procedures for the Handling of Retaliation Complaints under Federal Employee Protection Statutes Stakeholders: DOE Employees and Employees of DOE Contractors Scope: 29 C.F.R. Part 24 implements procedures under the employee protection provisions for which the Secretary of Labor has been given responsibility pursuant to the following federal statutes: Safe Drinking Water Act, 42 U.S.C. 300j-9(i); Federal Water Pollution Control Act, 33 U.S.C. 1367; Toxic Substances Control Act, 15 U.S.C. 2622; Solid Waste Disposal Act, 42 U.S.C. 6971; Clean Air Act, 42 U.S.C. 7622; Energy Reorganization Act of 1974, 42 U.S.C. 5851; and Comprehensive Environmental Response, Compensation and Liability Act

354

Final remote-handled waste canister leaves Los Alamos National Laboratory  

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

Remote-handled waste canister leaves LANL Remote-handled waste canister leaves LANL Final remote-handled waste canister leaves Los Alamos National Laboratory The Laboratory began shipping the canisters exactly one month ago and averaged four shipments per week. July 2, 2009 Los Alamos National Laboratory sits on top of a once-remote mesa in northern New Mexico with the Jemez mountains as a backdrop to research and innovation covering multi-disciplines from bioscience, sustainable energy sources, to plasma physics and new materials. Los Alamos National Laboratory sits on top of a once-remote mesa in northern New Mexico with the Jemez mountains as a backdrop to research and innovation covering multi-disciplines from bioscience, sustainable energy sources, to plasma physics and new materials. Contact

355

Green Button Giving Millions of Americans Better Handle on Energy Costs |  

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

Giving Millions of Americans Better Handle on Energy Giving Millions of Americans Better Handle on Energy Costs Green Button Giving Millions of Americans Better Handle on Energy Costs March 22, 2012 - 1:14pm Addthis Image courtesy of the National Institute of Standards and Technology. Image courtesy of the National Institute of Standards and Technology. John P. Holdren and Nancy Sutley What does this project do? Green Button provides millions of utility customers with easy access to a downloadable copy of their electricity usage data. This article is cross posted from the White House. More information about Apps for Energy, the Energy Department's software development competition, is here. On that page, you can submit app ideas and sign up for competition news and announcements. This afternoon President Obama is visiting Ohio State University to

356

Remote-Handled Low-Level Waste Disposal Project Alternatives Analysis  

SciTech Connect

This report identifies, evaluates, and compares alternatives for meeting the U.S. Department of Energy’s mission need for management of remote-handled low-level waste generated by the Idaho National Laboratory and its tenants. Each alternative identified in the Mission Need Statement for the Remote-Handled Low-Level Waste Treatment Project is described and evaluated for capability to fulfill the mission need. Alternatives that could meet the mission need are further evaluated and compared using criteria of cost, risk, complexity, stakeholder values, and regulatory compliance. The alternative for disposal of remote-handled low-level waste that has the highest confidence of meeting the mission need and represents best value to the government is to build a new disposal facility at the Idaho National Laboratory Site.

David Duncan

2009-10-01T23:59:59.000Z

357

Remote-Handled Low-Level Waste Disposal Project Alternatives Analysis  

SciTech Connect

This report identifies, evaluates, and compares alternatives for meeting the U.S. Department of Energy’s mission need for management of remote-handled low-level waste generated by the Idaho National Laboratory and its tenants. Each alternative identified in the Mission Need Statement for the Remote-Handled Low-Level Waste Treatment Project is described and evaluated for capability to fulfill the mission need. Alternatives that could meet the mission need are further evaluated and compared using criteria of cost, risk, complexity, stakeholder values, and regulatory compliance. The alternative for disposal of remote-handled low-level waste that has the highest confidence of meeting the mission need and represents best value to the government is to build a new disposal facility at the Idaho National Laboratory Site.

David Duncan

2011-03-01T23:59:59.000Z

358

Remote-Handled Low-Level Waste Disposal Project Alternatives Analysis  

SciTech Connect

This report identifies, evaluates, and compares alternatives for meeting the U.S. Department of Energy’s mission need for management of remote-handled low-level waste generated by the Idaho National Laboratory and its tenants. Each alternative identified in the Mission Need Statement for the Remote-Handled Low-Level Waste Treatment Project is described and evaluated for capability to fulfill the mission need. Alternatives that could meet the mission need are further evaluated and compared using criteria of cost, risk, complexity, stakeholder values, and regulatory compliance. The alternative for disposal of remote-handled low-level waste that has the highest confidence of meeting the mission need and represents best value to the government is to build a new disposal facility at the Idaho National Laboratory Site.

David Duncan

2011-04-01T23:59:59.000Z

359

Remote-Handled Low-Level Waste Disposal Project Alternatives Analysis  

SciTech Connect

This report identifies, evaluates, and compares alternatives for meeting the U.S. Department of Energy’s mission need for management of remote-handled low-level waste generated by the Idaho National Laboratory and its tenants. Each alternative identified in the Mission Need Statement for the Remote-Handled Low-Level Waste Treatment Project is described and evaluated for capability to fulfill the mission need. Alternatives that could meet the mission need are further evaluated and compared using criteria of cost, risk, complexity, stakeholder values, and regulatory compliance. The alternative for disposal of remote-handled low-level waste that has the highest confidence of meeting the mission need and represents best value to the government is to build a new disposal facility at the Idaho National Laboratory Site.

David Duncan

2010-06-01T23:59:59.000Z

360

Robotics for Nuclear Material Handling at LANL:Capabilities and Needs  

SciTech Connect

Nuclear material processing operations present numerous challenges for effective automation. Confined spaces, hazardous materials and processes, particulate contamination, radiation sources, and corrosive chemical operations are but a few of the significant hazards. However, automated systems represent a significant safety advance when deployed in place of manual tasks performed by human workers. The replacement of manual operations with automated systems has been desirable for nearly 40 years, yet only recently are automated systems becoming increasingly common for nuclear materials handling applications. This paper reviews several automation systems which are deployed or about to be deployed at Los Alamos National Laboratory for nuclear material handling operations. Highlighted are the current social and technological challenges faced in deploying automated systems into hazardous material handling environments and the opportunities for future innovations.

Harden, Troy A [Los Alamos National Laboratory; Lloyd, Jane A [Los Alamos National Laboratory; Turner, Cameron J [CO SCHOOL OF MINES/PMT-4

2009-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "handling test prepared" 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

Mixed waste certification plan for the Lawrence Berkeley Laboratory Hazardous Waste Handling Facility. Revision 1  

SciTech Connect

The purpose of this plan is to describe the organization and methodology for the certification of mixed waste handled in the Hazardous Waste Handling Facility (HWHF) at Lawrence Berkeley Laboratory (LBL). This plan is composed to meet the requirements found in the Westinghouse Hanford Company (WHC) Solid Waste Acceptance Criteria (WAC) and follows the suggested outline provided by WHC in the letter of April 26, 1990, to Dr. R.H. Thomas, Occupational Health Division, LBL. Mixed waste is to be transferred to the WHC Hanford Site Central Waste Complex and Burial Grounds in Hanford, Washington.

1995-01-01T23:59:59.000Z

362

Applying Remote Handling Attributes to the ITER Neutral Beam Cell Monorail Crane  

E-Print Network (OSTI)

The maintenance requirements for the equipment in the ITER Neutral Beam Cell requires components to be lifted and transported within the cell by remote means. To meet this requirement, the provision of an overhead crane with remote handling capabilities has been initiated. The layout of the cell has driven the design to consist of a monorail crane that travels on a branched monorail track attached to the cell ceiling. This paper describes the principle design constraints and how the remote handling attributes were applied to the concept design of the monorail crane, concentrating on areas where novel design solutions have been required and on the remote recovery requirements and solutions.

Crofts, O; Raimbach, J; Tesini, A; Choi, C-H; Damiani, C; Van Uffelen, M

2013-01-01T23:59:59.000Z

363

Waste Minimization Plan Prepared by  

E-Print Network (OSTI)

Waste Minimization Plan Prepared by: Environmental Health and Safety Department Revised February 2012 #12;Waste Minimization Plan Table of Contents Policy Statement........................................................... 3 Centralized Waste Management Program

364

Evaluation of a Mobile Hot Cell Technology for Processing Idaho National Laboratory Remote-Handled Wastes  

SciTech Connect

The Idaho National Laboratory (INL) currently does not have the necessary capabilities to process all remote-handled wastes resulting from the Laboratory’s nuclear-related missions. Over the years, various U.S. Department of Energy (DOE)-sponsored programs undertaken at the INL have produced radioactive wastes and other materials that are categorized as remote-handled (contact radiological dose rate > 200 mR/hr). These materials include Spent Nuclear Fuel (SNF), transuranic (TRU) waste, waste requiring geological disposal, low-level waste (LLW), mixed waste (both radioactive and hazardous per the Resource Conservation and Recovery Act [RCRA]), and activated and/or radioactively-contaminated reactor components. The waste consists primarily of uranium, plutonium, other TRU isotopes, and shorter-lived isotopes such as cesium and cobalt with radiological dose rates up to 20,000 R/hr. The hazardous constituents in the waste consist primarily of reactive metals (i.e., sodium and sodium-potassium alloy [NaK]), which are reactive and ignitable per RCRA, making the waste difficult to handle and treat. A smaller portion of the waste is contaminated with other hazardous components (i.e., RCRA toxicity characteristic metals). Several analyses of alternatives to provide the required remote-handling and treatment capability to manage INL’s remote-handled waste have been conducted over the years and have included various options ranging from modification of existing hot cells to construction of new hot cells. Previous analyses have identified a mobile processing unit as an alternative for providing the required remote-handled waste processing capability; however, it was summarily dismissed as being a potentially viable alternative based on limitations of a specific design considered. In 2008 INL solicited expressions of interest from Vendors who could provide existing, demonstrated technology that could be applied to the retrieval, sorting, treatment (as required), and repackaging of INL remote-handled wastes. Based on review of the responses and the potential viability of a mobile hot cell technology, INL subsequently conducted a technology evaluation, including proof-of-process validation, to assess the feasibility of utilizing such a technology for processing INL’s remote-handled wastes to meet established regulatory milestones. The technology evaluation focused on specific application of a mobile hot cell technology to the conditions to be encountered at the INL and addressed details of previous technology deployment, required modifications to accommodate INL’s remote-handled waste, ability to meet DOE safety requirements, requirements for fabrication/construction/decontamination and dismantling, and risks and uncertainties associated with application of the technology to INL’s remote-handled waste. The large capital costs associated with establishing a fixed asset to process INL’s remote-handled waste, the relatively small total volume of waste to be processed when compared to other waste streams through the complex, and competing mission-related needs has made it extremely difficult to secure the necessary support to advance the project. Because of this constraint, alternative contract structures were also explored as part of the technology evaluation wherein the impact of a large capital investment could be lessened.

B.J. Orchard; L.A. Harvego; R.P. Miklos; F. Yapuncich; L. Care

2009-03-01T23:59:59.000Z

365

HEATER TEST PLANNING FOR THE NEAR SURFACE TEST FACILITY AT THE HANFORD RESERVATION  

E-Print Network (OSTI)

Heater Experiment at Hanford. Berkeley, Lawre ;e BerkeleyTest Facility, Hole DC-11, Hanford Reservation. Prepared forof Gable Mountain Basalt Cores, Hanford Nuclear Reservation.

DuBois, A.

2010-01-01T23:59:59.000Z

366

Interface between the SAM data handling system and CDF experiment V. Bartsch 1 , A. Baranovski 2 , D. Benjamin 3 , K. Genser 2 , S. Hsu 3 ,  

E-Print Network (OSTI)

data handling because files which are already present at remote sites are analysed first. This howeverInterface between the SAM data handling system and CDF experiment software V. Bartsch 1 , A at Fermilab has recently changed its data handling system. The old data handling system called DFC (Data File

367

Mechanochemical Preparation of Phosphonium Salts and ...  

Researchers at Iowa State University and Ames Laboratory have developed a unique, solvent-free mechanochemical preparation method to prepare ...

368

Handbook for Handling, Storing, and Dispensing E85, July 2010, Energy Efficiency and Renewable Energy (EERE), Clean Cities (Brochure)  

SciTech Connect

Guidebook contains information about EPAct alternative fuels regulations for fleets, flexible fuel vehicles, E85 properties and specifications, and E85 handling and storage guidelines.

2010-07-01T23:59:59.000Z

369

A plug and play framework for an HVAC air handling unit and temperature sensor auto recognition technique.  

E-Print Network (OSTI)

??A plug and play framework for an HVAC air handling unit control system is proposed in this study. This is the foundation and the first… (more)

Zhou, Xiaohui

2010-01-01T23:59:59.000Z

370

Hydrogen Fuel Cell Performance in the Key Early Markets of Material Handling Equipment and Backup Power (Presentation)  

DOE Green Energy (OSTI)

This presentation summarizes the results of NREL's analysis of hydrogen fuel cell performance in the key early markets of material handling equipment (MHE) and backup power.

Kurtz, J.; Sprik, S.; Ramsden, T.; Saur, G.; Ainscough, C.; Post, M.; Peters, M.

2013-10-01T23:59:59.000Z

371

NREL Develops Test Facility and Test Protocols for Hydrogen Sensor Performance (Fact Sheet), Hydrogen and Fuel Cell Technical Highlights (HFCTH)  

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

8 * November 2010 8 * November 2010 The NREL hydrogen safety sensor test facility (Robert Burgess/NREL) PIX 18240 NREL Develops Test Facility and Test Protocols for Hydrogen Sensor Performance Team: Safety Codes & Standards Group, Hydrogen Technologies & Systems Center Accomplishment: The NREL Hydrogen Sensor Test Facility was recently commissioned for the quantitative assessment of hydrogen safety sensors (first reported in April 2010). Testing of sensors has started and is ongoing. Test Apparatus: The Test Facility was designed to test hydrogen sensors under precisely controlled conditions. The apparatus can simultaneously test multiple sensors and can handle all common electronic interfaces, including voltage, current, resistance,

372

Novel hard compositions and methods of preparation  

DOE Patents (OSTI)

Novel very hard compositions of matter are prepared by using in all embodiments only a minor amount of a particular carbide (or materials which can form the carbide in situ when subjected to heat and pressure); and no strategic cobalt is needed. Under a particular range of conditions, densified compositions of matter of the invention are prepared having hardnesses on the Rockwell A test substantially equal to the hardness of pure tungsten carbide and to two of the hardest commercial cobalt-bonded tungsten carbides. Alternately, other compositions of the invention which have slightly lower hardnesses than those described above in one embodiment also possess the advantage of requiring no tungsten and in another embodiment possess the advantage of having a good fracture toughness value.

Sheinberg, H.

1981-02-03T23:59:59.000Z

373

Brief Linear MPC with optimal prioritized infeasibility handling: application, computational issues and stability  

Science Conference Proceedings (OSTI)

All practical MPC implementations should have a means to recover from infeasibility. We present a recently developed infeasibility handler which computes optimal relaxations of the relaxable constraints subject to a user-defined prioritization, by solving ... Keywords: Infeasibility handling, Linear programming, Linear systems, Model-based control

Jostein Vada; Olav Slupphaug; Tor A. Johansen; Bjarne A. Foss

2001-11-01T23:59:59.000Z

374

Transpired Solar Collector at NREL's Waste Handling Facility Uses Solar Energy to Heat Ventilation Air  

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

Revised fact sheet describes the transpired solar collector that was installed on NREL's Waste handling Facility (WHF) in 1990 to preheat ventilation air. The electrically heated WHF was an ideal candidate for this technology - requiring a ventilation rate of 3,000 cubic feet per meter to maintain safe indoor conditions.

375

Power Generation Loading Optimization using a Multi-Objective Constraint-Handling Method via  

E-Print Network (OSTI)

results of the power generation loading optimization based on a coal-fired power plant demonstratesPower Generation Loading Optimization using a Multi-Objective Constraint-Handling Method via PSO power industry. A major objective for the coal-fired power generation loading optimization

Li, Xiaodong

376

3.1.1.2 Feed Processing and Handling DL2 Final Report  

DOE Green Energy (OSTI)

This milestone report is the deliverable for our Feed Processing and Handling project. It includes results of wet biomass feedstock analysis, slurry pumping information, fungal processing to produce a lignin-rich biorefinery residue and two subcontracted efforts to quantify the amount of wet biomass feedstocks currently available within the corn processing and paper processing industries.

Elliott, Douglas C.; Magnuson, Jon K.; Wend, Christopher F.

2006-09-30T23:59:59.000Z

377

An agent based approach for exception handling in e-procurement management  

Science Conference Proceedings (OSTI)

E-procurement has become an important function of enterprise information systems. The process of e-procurement includes the automatic definition of product requirements, search and selection for suppliers, negotiation and contracting with suppliers. ... Keywords: E-procurement, Exception handling, Intelligent agents, Web service

Sherry X. Sun; Jing Zhao; Huaiqing Wang

2012-01-01T23:59:59.000Z

378

Real-time deferrable load control: handling the uncertainties of renewable generation  

Science Conference Proceedings (OSTI)

Real-time demand response is essential for handling the uncertainties of renewable generation. Traditionally, demand response has been focused on large industrial and commercial loads, however it is expected that a large number of small residential loads ... Keywords: deferrable load control, demand response, model predictive control, smart grid

Lingwen Gan, Adam Wierman, Ufuk Topcu, Niangjun Chen, Steven H. Low

2013-01-01T23:59:59.000Z

379

Current methods to handle wall conduction and room internal heat transfer  

SciTech Connect

This paper reviews methods of handling wall conduction and room internal heat exchange adopted by ASHRAE (1993 Handbook of Fundamentals and later developments), CIBSE (1986 Guide and current proposals), and the CEN/TC89/WG6 proposals to calculate heating and cooling loads and related topics.

Davies, M.G.

1999-07-01T23:59:59.000Z

380

On performance evaluation of handling streaming traffic in IP networks using TFRC protocol  

Science Conference Proceedings (OSTI)

This paper deals with the performance evaluation of handling streaming traffic in IP best effort networks using TFRC protocol. In our studies we check and discuss an influence of video on demand traffic and different network conditions on TFRC congestion ... Keywords: IP network, TCP-friendly, best-effort, video on demand

Kacper Kurowski; Halina Tarasiuk

2008-05-01T23:59:59.000Z

Note: This page contains sample records for the topic "handling test prepared" 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

Guidelines for the Selection, Use, and Handling of High Temperature Insulation  

Science Conference Proceedings (OSTI)

This guide addresses design considerations for selecting replacement materials based on reviewing acceptable operating experience; handling new and used insulating materials safely; and identifying training criteria for personnel that come in contact with insulation. The user can complete an economically sound, energy conserving, and safe insulation maintenance project by applying this guide.

1997-11-13T23:59:59.000Z

382

Handling Triple Hidden Terminal Problems for Multi-Channel MAC in Long-Delay Underwater  

E-Print Network (OSTI)

1 Handling Triple Hidden Terminal Problems for Multi-Channel MAC in Long-Delay Underwater Sensor-channel MAC problem in underwater acoustic sensor networks. To reduce hardware cost, only one acoustic transceiver is often preferred on every node. In a single-transceiver multi- channel long-delay underwater

Cui, Jun-Hong

383

Remote Shopping Robot System for Fresh Foods Method of handling foods  

E-Print Network (OSTI)

Remote Shopping Robot System for Fresh Foods ­ Method of handling foods ­ Tetsuo TOMIZAWA, Akihisa a mobile manipulator as a teleoperated tool for accessing and manipulating remote objects. A human uses the system to select and buy fresh foods of a super market from a remote location via the Internet. We

Ohya, Akihisa

384

Design and control of a heavy material handling manipulator for agricultural robots  

Science Conference Proceedings (OSTI)

In this paper, we propose a manipulation system for agricultural robots that handle heavy materials. The structural systems of a mobile platform and a manipulator are selected and designed after proposing new knowledge about agricultural robots. Also, ... Keywords: Agricultural robots, Evaluation index, Manipulator, Robust control

Satoru Sakai; Michihisa Iida; Koichi Osuka; Mikio Umeda

2008-10-01T23:59:59.000Z

385

Flue Gas Desulfurization Scrubber Maintenance Guide: Wastewater Treatment and Gypsum Handling Area  

Science Conference Proceedings (OSTI)

The Flue Gas Desulfurization Scrubber Maintenance Guide: Wastewater Treatment and Gypsum Handling Area provides fossil plant maintenance personnel with current maintenance information on these systems. This guide will assist plant maintenance personnel in improving the reliability and reducing the maintenance costs for these areas of their scrubber system.

2009-12-23T23:59:59.000Z

386

Improved safety through training for gas-handling operations at the ship-jetty interface  

SciTech Connect

Leith Nautical College has found that integrated training of both ship and dock personnel in LNG-cargo handling is beneficial to both groups of workers. Overlapping coursework alleviate much of the difficulties which emerge in implementing this approach. The use of computers and models to simulate loading and off-loading operation has been a valuable aid in training workers for maximum safety.

Mcquire, G.

1979-01-01T23:59:59.000Z

387

ROCKY MOUNTAIN OILFIELD TESTING CENTER PROJECT TEST RESULTS  

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

AJUST A PUMP BEAM PUMPING UNIT AJUST A PUMP BEAM PUMPING UNIT FEBRUARY 19, 1997 FC9532 / 95EC1 ROCKY MOUNTAIN OILFIELD TESTING CENTER AJUST A PUMP TEST Rosemond Manufacturing, Inc. (RMI) Prepared for: INDUSTRY PUBLICATION Prepared by: MICHAEL J. TAYLOR Project Manager February 19, 1997 650200/551107:9532 ABSTRACT The Rocky Mountain Oilfield Testing Center (RMOTC) conducted a test of a Model-2000 Ajust A Pump system at the Naval Petroleum Reserve No. 3 (NPR-3). Rosemond Manufacturing, Inc. (RMI) manufactures compact beam-pumping units that incorporate energy-efficient gear boxes. The equipment is designed to reduce operating costs and minimize maintenance labor. This report documents the equipment performance and the results of the Ajust A Pump test. The purpose of the test was to demonstrate claims of energy efficiency and reduced labor requirements. The test showed

388

Handbook for Handling, Storing, and Dispensing E85 and Other Ethanol-Gasoline Blends (Book), Clean Cities, Energy Efficiency & Renewable Energy (EERE)  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

DOE/GO-102013-3861 DOE/GO-102013-3861 September 2013 Handbook for Handling, Storing, and Dispensing E85 and Other Ethanol-Gasoline Blends Disclaimer This report was prepared as an account of work sponsored by an agency of the United States government. Neither the United States government nor any agency thereof, nor any of their employees, makes any warranty, express or implied, or assumes any legal liability or responsibility for the accuracy, completeness, or usefulness of any information, apparatus, product, or process disclosed, or represents that its use would not infringe privately owned rights. Reference herein to any specific commercial product, process, or service by trade name, trademark, manufacturer, or otherwise does not necessarily constitute or imply its

389

Target preparations and thickness measurements  

SciTech Connect

A wide variety of isotope target preparative methods have been used, including rolling of metals, vapor deposition, electrodeposition, chemical vapor deposition, and sputtering, to obtain thin and thick films of most elements or compounds of elements in the Periodic Table. Most thin films prepared for use in self-supported form as well as those deposited on substrates require thickness measurement (atom count and distribution) and/or thickness uniformity determination before being used in nuclear research. Preparative methods are described together with thickness and uniformity determination procedures applicable to samples being prepared (in situ) and to completed samples. Only nondestructive methods are considered applicable to target samples prepared by the ORNL Solid State Division, Isotope Research Materials Laboratory. Thickness or areal density measurements of sufficient sophistication to yield errors of less than +-1 percent have been achieved with regularity. A statistical analysis procedure is applied which avoids error caused by balance zero-point drift in direct weight measurement methods. (auth)

Adair, H.L.; Kobisk, E.H.

1975-01-01T23:59:59.000Z

390

Project Plan 7930 Cell G PaR Remote Handling System Replacement  

Science Conference Proceedings (OSTI)

For over 40 years the US Department of Energy (DOE) and its predecessors have made Californium-252 ({sup 252}Cf) available for a wide range of industries including medical, nuclear fuels, mining, military and national security. The Radiochemical Engineering Development Center (REDC) located within the Oak Ridge National Laboratory (ORNL) processes irradiated production targets from the High Flux Isotope Reactor (HFIR). Operations in Building 7930, Cell G provide over 70% of the world's demand for {sup 252}Cf. Building 7930 was constructed and equipped in the mid-1960s. Current operations for {sup 252}Cf processing in Building 7930, Cell G require use of through-the-wall manipulators and the PaR Remote Handling System. Maintenance and repairs for the manipulators is readily accomplished by removal of the manipulator and relocation to a repair shop where hands-on work can be performed in glove boxes. Contamination inside cell G does not currently allow manned entry and no provisions were created for a maintenance area inside the cell. There has been no maintenance of the PaR system or upgrades, leaving operations vulnerable should the system have a catastrophic failure. The Cell G PaR system is currently being operated in a run to failure mode. As the manipulator is now 40+ years old there is significant risk in this method of operation. In 2006 an assessment was completed that resulted in recommendations for replacing the manipulator operator control and power centers which are used to control and power the PaR manipulator in Cell G. In mid-2008 the chain for the bridge drive failed and subsequent examinations indicated several damaged links (see Figure 1). To continue operations the PaR manipulator arm is being used to push and pull the bridge as a workaround. A retrieval tool was fabricated, tested and staged inside Cell G that will allow positioning of the bridge and manipulator arm for removal from the cell should the PaR system completely fail. A fully functioning and reliable Par manipulator arm is necessary for uninterrupted {sup 252}Cf operations; a fully-functioning bridge is needed for the system to function as intended.

Kinney, Kathryn A [ORNL

2009-10-01T23:59:59.000Z

391

ROCKY MOUNTAIN OILFIELD TESTING CENTER PROJECT TEST RESULTS  

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

TANK LEVEL GAUGING SYSTEM TANK LEVEL GAUGING SYSTEM JULY 25, 1996 FC9519 / 95PT7 ROCKY MOUNTAIN OILFIELD TESTING CENTER TANK LEVEL GAUGING SYSTEM DOUBLE M ELECTRIC Prepared for: Industry Publication Prepared by: MICHAEL R. TYLER RMOTC Field Engineer July 25, 1996 551103/9519:jb ABSTRACT The Rocky Mountain Oilfield Testing Center (RMOTC) conducted a test of a Tank Level Gauging System at the Naval Petroleum Reserve No. 3 (NPR-3). Double M. Electric manufactures the equipment that incorporates an optical-encoder sending unit, cellular communications, and software interface. The system effectively displayed its capabilities for remote monitoring and recording of tank levels.

392

Safe Frozen Turkey Preparation  

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

you ready for a SAFE Thanksgiving? you ready for a SAFE Thanksgiving? Thanksgiving ~ time for family, Thanksgiving this year? Test your Thanksgiving safety Safety Quiz, check out the resources and share this page with your friends and family. Most importantly, take just a little extra time to make sure your Thanksgiving holiday is safe for your loved ones. Happy Thanksgiving! 1. How should you thaw a frozen turkey? A. Set it out on the kitchen counter the night before. B. In the microwave on the "thaw" setting C. Run hot water over it in the sink. D. In the refrigerator, according to its 2. How should you store turkey leftovers? A. In the same pan you cooked it in, in the refrigerator B. Put it in gallon freezer bags and freeze C. Cut the turkey into small pieces; refrigerate stuffing and turkey separately in shallow

393

ROCKY MOUNTAIN OILFIELD TESTING CENTER  

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

NOVERFLO (SMART CABLE) NOVERFLO (SMART CABLE) LIQUID LEAK DETECTION SYSTEM FEBRUARY 12, 1996 FC9535/96ET3 RMOTC TEST REPORT NOVERFLO LIQUID LEAK DETECTION SYSTEM (SMART CABLE) Prepared for: INDUSTRY PUBLICATION Prepared by: RALPH SCHULTE RMOTC Project Engineer February 12, 1996 650200/9535:jb CONTENTS Page Summary 1 Introducation 1 NPR-3 Map 2 Description of Operations 3 1 st Test 3 2 nd Test 3 3 rd Test 4 4 th Test 5 Concluding Remarks 5 Acknowledgements 6 Rocky Mountain Oilfield Testing Center Technical Report Noverflo Liquid Leak Detection System (Smart Cable) Summary As part of RMOTC's continuing mission to support and strengthen the domestic oil and gas industry by allowing testing by individual inventors and commercial companies to evaluate their products and technology, RMOTC

394

W-025, acceptance test report  

SciTech Connect

This acceptance test report (ATR) has been prepared to establish the results of the field testing conducted on W-025 to demonstrate that the electrical/instrumentation systems functioned as intended by design. This is part of the RMW Land Disposal Facility.

Roscha, V.

1994-10-04T23:59:59.000Z

395

ENGINEERING EXPERIENCE AT BROOKHAVEN NATIONAL LABORATORY IN HANDLING FUSED CHLORIDE SALTS  

SciTech Connect

Two fused chloride salt eutectics, binary LiCl-KCl and ternary NaCl- KCl- MgCl/sub 2/, were used in fuel processing studies as part of the Liquid Metal Fuel Reactor research and development program. Results of engineering work done at Brookhaven since 1950 are summarized. It was demonstrated that fused chloride salt technology is sufficiently developed so that loops and other experimental equipment can be designed and operated at 500 deg C with a high degree of confidence. The equipment, which was operated for many hours, included a large forced-circulation loop and many thermal-convection loops and tanks. The specifications used for the fabrication, cleaning, and testing of equipment for salt service are described. All welded systems, welded by the usual inert-arc procedures, are preferred, but ring type joint stainless-steel flanged connections were found satisfactory, mainly for connecting melt tanks to experimental equipment and for mounting orifice flowmeters. The surfaces of equipment to be used with fused salts were cleaned satisfactorily prior to assembly by several different methods, but sandblasting was found applicable to all types of equipment. Radiography was used to check all welds in contact with fused salt for flaws and, during operation, to locate and determine the cause of any malfunction. Components tested at the normal operating temperature of 500 deg C included pumps, valves, agitators, sightports, samplers, and filtens. Salt samples were usually taken by the thief method. Both stationary and movable resistance type, liquid-level probes were used and were reliable so long as the salt surface remained quiescent; otherwise, splashing and short-circuiting occurred. Nullmatic, pilot-operated pressure transmitters gave good service in conjunction with both orifice and Venturi flowmeters. A procedure is described for preparing pound quantities of pure eutectics, which, in the case of the ternary eutectic, differs from that used in preparing gram quantities. Both eutectics were pretreated with a Bi- Mg-U solution to remove oxidizing impurities before use in corrosion and processing experiments. The results of physical property measurements on the two eutectics are included. (auth)

Raseman, C.J.; Susskind, H.; Farber, G.; McNulty, W.E.; Salzano, F.J.

1960-06-01T23:59:59.000Z

396

Preparation of thorium-uranium gel spheres  

SciTech Connect

Ceramic oxide spheres with diameters of 15 to 1500 ..mu..m are being evaluated for fabrication of power reactor fuel rods. (Th,U)O/sub 2/ spheres can be prepared by internal or external chemical gelation of nitrate solutions or oxide sols. Two established external gelation techniques were tested but proved to be unsatisfactory for the intended application. Established internal gelation techniques for UO/sub 2/ spheres were applied with minor modifications to make 75% ThO/sub 2/-25% UO/sub 2/ spheres that sinter to diameters of 200 to 1400 ..mu..m (99% T.D.).

Spence, R.D.; Haas, P.A.

1980-01-01T23:59:59.000Z

397

Lead Auditor - Auditor Preparation Checklist  

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

Lead Auditor - Auditor Preparation Checklist Lead Auditor - Auditor Preparation Checklist |Number|Item|Status | ||Staff the Audit || ||Auditor Qualifications|| ||Audit Notification & Audit Plan Issued|| ||Auditor access issues resolved|| ||Audit team facilities|| ||Auditor audit areas / elements assigned|| ||Check lists Prepared Issued || ||Audited Org Docs to team QPP Work plans etc|| ||Past Audits to team || ||PC availability for Auditors|| ||Audit forms to auditors People Interviewed Documents reviewed Entrance Meeting Attendance Exit Meeting Attendance, Issue Development Sheet[1] Form 11 Form 21|| ||Audit protocols, conduct of auditors|| ||Entrance meeting slides|| ||Exit meeting slide outline|| ||Report Shell to Team|| ----------------------- [1] Use of this will be explained in the second article of the series

398

HANDLING AND CO-FIRING OF SHREDDED MUNICIPAL REFUSE AND COAL IN A SPREADER-STOKER BOILER*  

E-Print Network (OSTI)

HANDLING AND CO-FIRING OF SHREDDED MUNICIPAL REFUSE AND COAL IN A SPREADER-STOKER BOILER* D. A for handling up to 120 tons/day of municipal refuse has been developed for co-firing with coal in a spreader-tube metals; and (3) environmental effects of the co-firing, with respect to emissions and ash residues. Co-firing

Columbia University

399

Prepared by WVU Professors:  

E-Print Network (OSTI)

During the past thirty years two major concerns have developed with our current fuels. These concerns are reliable supplies and pollution. Because of these problems there has been a great interest in alternate fuels such as alcohol and natural gas. Since 1997 research has been conducted at West Virginia University on methanol as an alternate fuel for gas turbines. There have been two main areas of study in this research, the problems associated with operating a gas turbine on methanol and exhaust gas emissions. There are two major differences between methanol and aviation kerosene that affect the operation of a gas turbine. The first is methanol’s poor lubricating properties and the second is methanol’s lower heating value. During this research techniques have been developed to measure the lubricating properties of methanol and various additives. Suitable lubricant additives were found to improve methanol’s lubricity to equal that of aviation kerosene, with as little as 1 % additive. The lower heating value of methanol required modifications to the WVU gas turbine’s fuel system and atomizer, to provide higher flow rate of fuel then required with aviation kerosene. The gas turbine was modified and operated on methanol for an extended period, without failure. Exhaust gas emissions were tested

Methanol From; Coal End Use; Mr. Edward; C. Heydorn; John L. Loth; Nigel Clark; Robert Bond; Richard Guiler

2000-01-01T23:59:59.000Z

400

BCM 1 Equipment Inventory | Sample Preparation Laboratories  

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

1 Equipment Inventory 1 Equipment Inventory « Biology Chemistry & Material Science Laboratory 1 Title Equipment Type Description Agilent 8453 UV-Vis Spectrophotometer Analytical Agilent 8453 UV-VIS diode-array spectrophotometer. Wavelength range 190-1100 nm with a 1 nm optical slit width. Disposable plastic cuvettes are available in the lab, and quartz cuvettes and microcuvettes are available on a check-out basis. Beckman GPKR Centrifuge Centrifuge Beckman GPKR refrigerated centrifuge with fixed angle rotor, 8000 rpm max speed, temperature range -10°C to 40°C, fits 50mL tubes. Corning 430 pH Meter pH Meter The Corning 430 pH meter is designed to handle laboratory applications from the most routine to the highly complex. Encased in spill-resistant housings and feature chemical-resistant, sealed keypad. Model 430 (pH range 0.00 to 14.00) is a basic, yet reliable meter providing accurate, efficient digital measurements. Offers simplified, four-button operation, automatic calibration and temperature compensation, % slope readout, self-diagnostics test on powerup and analog recorder output. Unique LCD shows pH, mV

Note: This page contains sample records for the topic "handling test prepared" 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

Test plan/procedure for the SPM-1 shipping container system. Revision 0  

SciTech Connect

The 49 CFR 173.465 Type A packaging tests will verify that SPM-1 will provide adequate protection and pass as a Type A package. Test will determine that the handle of the Pig will not penetrate through the plywood spacer and rupture the shipping container. Test plan/procedure provides planning, pre-test, setup, testing, and post-testing guidelines and procedures for conducting the {open_quotes}Free Drop Test{close_quotes} procedure for the SPM-1 package.

Flanagan, B.D.

1995-07-01T23:59:59.000Z

402

Remote Handling and Plasma Conditions to Enable Fusion Nuclear Science R&D Using a Component Testing Facility  

Science Conference Proceedings (OSTI)

Power Plants, Demo, and Next Steps / Eighteenth Topical Meeting on the Technology of Fusion Energy (Part 2)

Y. K. M. Peng et al.

403

Preparation for Facility Operations RM  

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

The objective of this Standard Review Plan (SRP) on Preparation for Facility Operations is to provide consistency guidance to evaluate the effectiveness of the final project closure of major...

404

Method for preparation of polysilanes  

DOE Patents (OSTI)

High molecular weight polysilanes are prepared using highly non-chain-transferring solvents. Certain alloys of sodium can also be used to advantage with such solvents. The high molecular weights are achievable even in the commercially preferred "normal" addition procedure.

Zeigler, John M. (2208 Lester Dr., NE, Albuquerque, NM 87112)

1991-01-01T23:59:59.000Z

405

Preparation of Internationalized Strings ("stringprep")  

Science Conference Proceedings (OSTI)

This document describes a framework for preparing Unicode text strings in order to increase the likelihood that string input and string comparison work in ways that make sense for typical users throughout the world. The stringprep protocol is useful ...

P. Hoffman; M. Blanchet

2002-12-01T23:59:59.000Z

406

Document Preparation | Department of Energy  

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

Document Preparation Document Preparation Document Preparation Selected documents on the topic of NEPA Document Preparation. October 29, 2013 Directory of Potential Stakeholders for DOE Actions under NEPA DOE Offices are encouraged to be inclusive in providing potentially interested parties with opportunities to review NEPA documents. This Directory of Potential Stakeholders for DOE Actions under NEPA is primarily intended to supplement lists that Departmental Offices compile for individual projects or facilities. It complements the EIS Distribution Guidance. The Office of NEPA Policy and Compliance updates this Directory annually in July and may issue revisions throughout the year as new information becomes available. September 7, 2012 OMB and CEQ Joint Memorandum on Environmental Collaboration and Conflict

407

Electric Transportation Applications All Rights Reserved ETA...  

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

7 Revision 2 Effective March 1, 1997 Road Course Handling Test Prepared by Electric Transportation Applications Prepared by: Date: Jude M....

408

DOE-HDBK-1079-94; Primer on Tritium Safe Handling Practices  

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

METRIC DOE-HDBK-1079-94 December 1994 DOE HANDBOOK PRIMER ON TRITIUM SAFE HANDLING PRACTICES U.S. Department of Energy FSC-6910 Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited This document has been reproduced directly from the best available copy. Available to DOE and DOE contractors from the Office of Scientific and Technical Information. P.O. Box 62, Oak Ridge, TN 37831; (615) 576-8401. Available to the public from the U.S. Department of Commerce, Technology Administration, National Technical Information Service, Springfield, VA 22161. (703)487-4650. Order No. DE95003577 DOE-HDBK-1079-94 TRITIUM SAFE HANDLING PRACTICES

409

Determining Critical Pressure and Duct Leakage in VAV Air-Handling Units  

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

Determining Critical Pressure and Duct Leakage in VAV Air-Handling Units Determining Critical Pressure and Duct Leakage in VAV Air-Handling Units Speaker(s): Clifford Federspiel Date: December 3, 2003 - 12:00pm Location: Bldg. 90 Seminar Host/Point of Contact: Nance Matson Fans for moving air in buildings use a significant amount of energy. It is well known that fan energy use in variable-air-volume (VAV) systems can be reduced by resetting the supply duct pressure. The standard way to reset duct pressure is by controlling the most-open terminal damper to a nearly open position. Most systems can't measure terminal damper positions, so pressures are either not reset at all or use ad hoc resetting strategies that are configured sub-optimally. In this seminar I will describe a new method of determining the critical supply duct pressure for VAV systems.

410

APS Protocols for Handling, Storage, and Disposal of Untreated Foreign Soil  

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

APS Protocols for Handling, Storage, and Disposal of Untreated Foreign Soil APS Protocols for Handling, Storage, and Disposal of Untreated Foreign Soil and Regulated Domestic Soil Arrival of New Samples: Unpack shipping containers. Treat any ice/melted water immediately. Decontaminate any "blue ice" packets with 70% ethyl alcohol. Collect any loose soil from container and heat-treat immediately. Immediately decontaminate shipping containers. Heat-treat wooden, metal, or cardboard shipping containers (using lowest heat). Treat plastic containers and coolers with 70% ethyl alcohol. Storage of Samples: Store dry samples in the locked storage cabinet in Room 431Z021 until they can be delivered to the appropriate beamline for analysis. Label containers with origin and arrival date. Log samples into the APS Soil Inventory book maintained in 431Z021.

411

Performance Analysis of Dual-Fan, Dual-Duct Constant Volume Air-Handling Units  

E-Print Network (OSTI)

Dual-fan, dual-duct air-handling units introduce outside air directly into the cooling duct and use two variable speed devices to independently maintain the static pressure of the hot and the cold air ducts. Analytical models have been developed to compare fan power and thermal energy consumption of dualfan, dual-duct constant volume air-handling units with single-fan, dual-duct constant volume airhandling units. This study shows that the dual-fan, dual-duct system uses less fan power and less thermal energy during winter, and uses more thermal energy during summer. Thermal energy performance can be significantly improved if the thermal energy penalty can be decreased or eliminated.

Joo, I. S.; Liu, M.

2001-01-01T23:59:59.000Z

412

Handling and archiving of magnetic fusion data at DIII-D  

SciTech Connect

Recent modifications to the computer network at DIII-D enhance the collection and distribution of newly acquired and archived experimental data. Linked clients and servers route new data from diagnostic computers to centralized mass storage and distribute data on demand to local and remote workstations and computers. Capacity for data handling exceeds the upper limit of DIII-D Tokamak data production of about 4 GBytes per day. Network users have fast access to new data stored on line. An interactive program handles requests for restoration of data archived off line. Disk management procedures retain selected data on line in preference to other data. Redundancy of all components on the archiving path from the network to magnetic media has prevented loss of data. Older data are rearchived as dictated by limited media life.

VanderLaan, J.F.; Miller, S.; McHarg, B.B. Jr.; Henline, P.A.

1995-10-01T23:59:59.000Z

413

Evaluation of the Total Cost of Ownership of Fuel Cell-Powered Material Handling Equipment  

DOE Green Energy (OSTI)

This report discusses an analysis of the total cost of ownership of fuel cell-powered and traditional battery-powered material handling equipment (MHE, or more typically 'forklifts'). A number of fuel cell MHE deployments have received funding support from the federal government. Using data from these government co-funded deployments, DOE's National Renewable Energy Laboratory (NREL) has been evaluating the performance of fuel cells in material handling applications. NREL has assessed the total cost of ownership of fuel cell MHE and compared it to the cost of ownership of traditional battery-powered MHE. As part of its cost of ownership assessment, NREL looked at a range of costs associated with MHE operation, including the capital costs of battery and fuel cell systems, the cost of supporting infrastructure, maintenance costs, warehouse space costs, and labor costs. Considering all these costs, NREL found that fuel cell MHE can have a lower overall cost of ownership than comparable battery-powered MHE.

Ramsden, T.

2013-04-01T23:59:59.000Z

414

WIPP Receives First Remote-Handled Waste Shipment From Sandia Labs  

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

For immediate release WIPP Receives First Remote-Handled Waste Shipment From Sandia Labs CARLSBAD, N.M., December 21, 2011 - The U.S. Department of Energy's (DOE) Waste Isolation Pilot Plant (WIPP) has received the first of eight planned defense-related remote- handled transuranic (RH-TRU) waste shipments from Sandia National Laboratories (SNL) in Albuquerque. The shipment arrived December 16 for permanent disposal in WIPP's underground repository. DOE National TRU Program Director J.R. Stroble said the shipment is significant to WIPP. "Our goal is to reduce the nation's nuclear waste footprint and we routinely receive shipments from around the country," said Stroble. "This first shipment of RH-TRU waste from

415

Remote Handling Devices for Disposition of Enriched Uranium Reactor Fuel Using Melt-Dilute Process  

SciTech Connect

Remote handling equipment is required to achieve the processing of highly radioactive, post reactor, fuel for the melt-dilute process, which will convert high enrichment uranium fuel elements into lower enrichment forms for subsequent disposal. The melt-dilute process combines highly radioactive enriched uranium fuel elements with deleted uranium and aluminum for inductive melting and inductive stirring steps that produce a stable aluminum/uranium ingot of low enrichment.

Heckendorn, F.M.

2001-01-03T23:59:59.000Z

416

Radioactive and mixed waste management plan for the Lawrence Berkeley Laboratory Hazardous Waste Handling Facility  

SciTech Connect

This Radioactive and Mixed Waste Management Plan for the Hazardous Waste Handling Facility at Lawrence Berkeley Laboratory is written to meet the requirements for an annual report of radioactive and mixed waste management activities outlined in DOE Order 5820.2A. Radioactive and mixed waste management activities during FY 1994 listed here include principal regulatory and environmental issues and the degree to which planned activities were accomplished.

NONE

1995-01-01T23:59:59.000Z

417

Anticipated Radiological Dose to Worker for Plutonium Stabilization and Handling at PFP - Project W-460  

E-Print Network (OSTI)

This report provides estimates of the expected whole body and extremity radiological dose, expressed as dose equivalent (DE), to workers conducting planned plutonium (Pu) stabilization processes at the Hanford Site Plutonium Finishing Plant (PFP). The report is based on a time and motion dose study commissioned for Project W-460, Plutonium Stabilization and Handling, to provide personnel exposure estimates for construction work in the PFP storage vault area plus operation of stabilization and packaging equipment at PFP.

Weiss, E V

2000-01-01T23:59:59.000Z

418

EBR-II argon cooling system restricted fuel handling I and C upgrade  

SciTech Connect

The instrumentation and control of the Argon Cooling System (ACS) restricted fuel handling control system at Experimental Breeder Reactor II (EBR-II) is being upgraded from a system comprised of many discrete components and controllers to a computerized system with a graphical user interface (GUI). This paper describes the aspects of the upgrade including reasons for the upgrade, the old control system, upgrade goals, design decisions, philosophies and rationale, and the new control system hardware and software.

Start, S.E.; Carlson, R.B.; Gehrman, R.L. [Argonne National Lab., Idaho Falls, ID (United States). Engineering Div.

1995-06-01T23:59:59.000Z

419

Remote Handled Transuranic Sludge Retrieval Transfer And Storage System At Hanford  

SciTech Connect

This paper describes the systems developed for processing and interim storage of the sludge managed as remote-handled transuranic (RH-TRU). An experienced, integrated CH2M HILL/AFS team was formed to design and build systems to retrieve, interim store, and treat for disposal the K West Basin sludge, namely the Sludge Treatment Project (STP). A system has been designed and is being constructed for retrieval and interim storage, namely the Engineered Container Retrieval, Transfer and Storage System (ECRTS).

Raymond, Rick E. [CH2M HILL Plateau Remediation Company, Richland, WA (United States); Frederickson, James R. [AREVA, Avignon (France); Criddle, James [AREVA, Avignon (France); Hamilton, Dennis [CH2M HILL Plateau Remediation Company, Richland, WA (United States); Johnson, Mike W. [CH2M HILL Plateau Remediation Company, Richland, WA (United States)

2012-10-18T23:59:59.000Z

420

Hydrogen Gas Generation Model for Fuel Based Remote Handled TRU Waste Stored at INEEL  

DOE Green Energy (OSTI)

The Idaho National Environmental and Engineering Laboratory (INEEL) initiated efforts to calculate the hydrogen gas generation in remote-handled transuranic (RH-TRU) containers in order to evaluate continued storage of unvented RH-TRU containers in vaults and to identify any potential problems during retrieval and aboveground storage. A computer code is developed to calculate the hydrogen concentration in the stored RH-TRU waste drums for known configuration, waste matrix, and radionuclide inventories as a function of time.

Soli T. Khericha; Rajiv N. Bhatt; Kevin Liekhus

2003-02-01T23:59:59.000Z

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


421

Acquisition Strategy for the Idaho National Laboratory Remote-Handled Low-Level Waste Disposition Project  

Science Conference Proceedings (OSTI)

This document describes the design-build acquisition strategy that will be applied to the Remote Handled LLW Disposal Project. The design-build delivery method will be tailored, as appropriate, to integrate the requirements of Department of Energy (DOE) Order 413.3B, 'Program and Project Management for the Acquisition of Capital Assets,' with the DOE budget formulation process and the safety requirements of DOE-STD-1189, 'Integration of Safety into the Design Process.'

David Duncan

2011-05-01T23:59:59.000Z

422

Remote Handling Equipment for a High-Level Waste Waste Package Closure System  

SciTech Connect

High-level waste will be placed in sealed waste packages inside a shielded closure cell. The Idaho National Laboratory (INL) has designed a system for closing the waste packages including all cell interior equipment and support systems. This paper discusses the material handling aspects of the equipment used and operations that will take place as part of the waste package closure operations. Prior to construction, the cell and support system will be assembled in a full-scale mockup at INL.

Kevin M. Croft; Scott M. Allen; Mark W. Borland

2006-04-01T23:59:59.000Z

423

Estimation of tritium and helium inventory in the tritium handling system in Korea  

Science Conference Proceedings (OSTI)

In Korea, the Wolsong Tritium Removal Facility (WTRF) is under construction to reduce the amount of tritium present in the moderator and coolant of the CANDU type Wolsong nuclear power plants. Recently, a study on the tritium handling system for recovery of the tritium collected from the WTRF was started. Some tritium would enter the steel of the container walls and subsequently decay to helium. This helium can deteriorate the mechanical properties of the material of the tritium handling system. To evaluate the tritium and helium inventory in the stainless steel wall of this system, the time-dependent diffusion equation was developed, solved and the results are presented in this paper. These results were compared to previous work that evaluated the tritium inventory in the stainless steel wall of 50-L tritium containers. Tritium and helium concentration profiles and the corresponding inventories were evaluated with respect to the various parameters such as exposure time, temperature, and partial pressure. After 24 years, the helium inventory in the wall of the tritium handling system exceeds the tritium inventory. (authors)

Yook, D.; Lee, S.; Lee, K. [Dept. of Nuclear Eng., KAIST, 373-1, Kusong-dong, Yusong-gu, Daejon 305-701 (Korea, Republic of); Song, K. M.; Shon, S. H. [KEPRI, 103-16 Munji-Dong, Yuseong-Gu, Daejeon, 305-380 (Korea, Republic of)

2008-07-15T23:59:59.000Z

424

Benchmarking the Remote-Handled Waste Facility at the West Valley Demonstration Project  

Science Conference Proceedings (OSTI)

ABSTRACT Facility decontamination activities at the West Valley Demonstration Project (WVDP), the site of a former commercial nuclear spent fuel reprocessing facility near Buffalo, New York, have resulted in the removal of radioactive waste. Due to high dose and/or high contamination levels of this waste, it needs to be handled remotely for processing and repackaging into transport/disposal-ready containers. An initial conceptual design for a Remote-Handled Waste Facility (RHWF), completed in June 1998, was estimated to cost $55 million and take 11 years to process the waste. Benchmarking the RHWF with other facilities around the world, completed in November 1998, identified unique facility design features and innovative waste pro-cessing methods. Incorporation of the benchmarking effort has led to a smaller yet fully functional, $31 million facility. To distinguish it from the June 1998 version, the revised design is called the Rescoped Remote-Handled Waste Facility (RRHWF) in this topical report. The conceptual design for the RRHWF was completed in June 1999. A design-build contract was approved by the Department of Energy in September 1999.

O. P. Mendiratta; D. K. Ploetz

2000-02-29T23:59:59.000Z

425

TECHNOLOGY DEVELOPMENT AND DEPLOYMENT OF SYSTEMS FOR THE RETRIEVAL AND PROCESSING OF REMOTE-HANDLED SLUDGE FROM HANFORD K-WEST FUEL STORAGE BASIN  

SciTech Connect

In 2011, significant progress was made in developing and deploying technologies to remove, transport, and interim store remote-handled sludge from the 105-K West Fuel Storage Basin on the Hanford Site in south-central Washington State. The sludge in the 105-K West Basin is an accumulation of degraded spent nuclear fuel and other debris that collected during long-term underwater storage of the spent fuel. In 2010, an innovative, remotely operated retrieval system was used to successfully retrieve over 99.7% of the radioactive sludge from 10 submerged temporary storage containers in the K West Basin. In 2011, a full-scale prototype facility was completed for use in technology development, design qualification testing, and operator training on systems used to retrieve, transport, and store highly radioactive K Basin sludge. In this facility, three separate systems for characterizing, retrieving, pretreating, and processing remote-handled sludge were developed. Two of these systems were successfully deployed in 2011. One of these systems was used to pretreat knockout pot sludge as part of the 105-K West Basin cleanup. Knockout pot sludge contains pieces of degraded uranium fuel ranging in size from 600 {mu}m to 6350 {mu}m mixed with pieces of inert material, such as aluminum wire and graphite, in the same size range. The 2011 pretreatment campaign successfully removed most of the inert material from the sludge stream and significantly reduced the remaining volume of knockout pot product material. Removing the inert material significantly minimized the waste stream and reduced costs by reducing the number of transportation and storage containers. Removing the inert material also improved worker safety by reducing the number of remote-handled shipments. Also in 2011, technology development and final design were completed on the system to remove knockout pot material from the basin and transport the material to an onsite facility for interim storage. This system is scheduled for deployment in 2012. The prototype facility also was used to develop technology for systems to retrieve remote-handled transuranic sludge smaller than 6350 {mu}m being stored in underwater containers. After retrieving the sludge, the system will be used to load and transport the sludge for interim storage. During 2011, full-scale prototype systems were developed and tested to a Technology Readiness Level 6 as defined by U.S. Department of Energy standards. This system is scheduled for deployment in 2013. Operations also are scheduled for completion in 2014.

RAYMOND RE

2011-12-27T23:59:59.000Z

426

DOE - Office of Legacy Management -- Nevada Test Site - 023  

Office of Legacy Management (LM)

Nevada Test Site - 023 Nevada Test Site - 023 FUSRAP Considered Sites Site: Nevada Test Site (023) Designated Name: Alternate Name: Location: Evaluation Year: Site Operations: Site Disposition: Radioactive Materials Handled: Primary Radioactive Materials Handled: Radiological Survey(s): Site Status: The Nevada Test Site was established by the Atomic Energy Commission in the 1950's to conduct field testing of nuclear explosives in connection with the research and development of nuclear weapons. The environmental management activities for this site are under the purview of the Department of Energy¿s Nevada Operations Office. The National Nuclear Security Administration is the site landlord and will be responsible for Long Term Stewardship. Also see Documents Related to Nevada Test Site

427

Development and testing of a high efficiency advanced coal combustor: Phase 3, industrial boiler retrofit. Quarterly technical progress report number 12, July 1, 1994--September 30, 1994  

SciTech Connect

The objective of this project is to retrofit the previously developed High Efficiency Advanced Coal Combustor (HEACC) to a standard gas/oil designed industrial boiler to assess the technical and economic viability of displacing premium fuels with microfine coal. During this reporting period, data reduction/evaluation and interpretation from the long term four hundred hours Proof-of-Concept System Test under Task 3 were completed. Cumulatively, a total of approximately 563 hours of coal testing was performed with 160 hrs on 100% coal and over 400 hours with co-firing coal and gas. The primary objectives of this testing were to: (1) obtain steady state operation consistently on 100% coal; (2) increase carbon conversion efficiency from 95% to the project goal of 98%; and (3) maintain NOx emissions at or below 0.6 lbs/MBtu. The following specific conclusions are based on results of coal-fired testing at Penn State and the initial economic evaluation of the HEACC system: a coal handling/preparation system can be designed to meet the technical requirements for retrofitting microfine coal combustion to a gas/oil-designed boiler; the boiler thermal performance requirements were met; the NOx emission target of was met; combustion efficiencies of 95% could be met on a daily average basis, somewhat below the target of 98%; the economic playback is very sensitive to fuel differential cost, unit size, and annual operating hours; continuous long term demonstration is needed to quantify ash effects and how to best handle ashes. The following modifications are recommended prior to the 1,000 hour demonstration phase testing: (1) coal feeding improvements--improved raw coal/storage and transport, installation of gravimetric feeder, and redesign/installation of surge bin bottom; (2) burner modification--minor modification to the tip of the existing HEACC burner to prevent change of flame shapes for no apparent reason.

Patel, R.L.; Borio, R. [ABB/Combustion Engineering, Windsor, CT (United States). Power Plant Labs.; Scaroni, A.W.; Miller, B.G. [Pennsylvania State Univ., University Park, PA (United States); McGowan, J.G. [Univ. of Massachusetts, Amherst, MA (United States)

1994-11-18T23:59:59.000Z

428

Plutonium metal preparation and purification at Los Alamos, 1984  

Science Conference Proceedings (OSTI)

Plutonium metal preparation and purification are well established at Los Alamos. Metal is prepared by calcothermic reduction of both PuF/sub 4/ and PuO/sub 2/. Metal is purified by halide slagging, casting, and electrorefining. The product from the production sequence is ultrapure plutonium metal. All of the processes involve high temperature operation and all but casting involve molten salt media. Development efforts are fourfold: (1) recover plutonium values from residues; (2) reduce residue generation through process improvements and changes; (3) recycle of reagents, and (4) optimize and integrate all processes into a close-loop system. Plutonium residues are comprised of oxides, chlorides, colloidal metal suspensions, and impure metal heels. Pyrochemical recovery techniques are under development to address each residue. In addition, we are looking back at each residue generation step and are making process changes to reduce plutonium content in each residue. Reagent salt is the principle media used in pyrochemical processing. The regeneration and recycle of these reagents will both reduce our waste handling and operating expense. The fourth area, process optimization, involves both existing processes and new process developments. A status of efforts in all four of these areas will be summarized.

Christensen, D.C.; Williams, J.D.; McNeese, J.A.; Fife, K.W.

1984-01-01T23:59:59.000Z

429

HYDRAULIC CEMENT PREPARATION FROM LURGI SPENT SHALE  

E-Print Network (OSTI)

P. , "Investigations on hydraulic cement from spent oilCO, April 16-18, 1980 HYDRAULIC CEMENT PREPARATION FROMUniversity of California. HYDRAULIC CEMENT PREPARATION FROM

Mehta, P.K.

2013-01-01T23:59:59.000Z

430

Preparation of Hydroxyapatite by Microwave Heating  

Science Conference Proceedings (OSTI)

HAP powders were successfully prepared in a 2.45 GHz - 900W multimode home model microwave oven. The HAP powder was prepared by microwave heating ...

431

DOE Prepares Programmatic Environmental Impact Statement for...  

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

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432

Explosive simulants for testing explosive detection systems  

DOE Patents (OSTI)

Explosives simulants that include non-explosive components are disclosed that facilitate testing of equipment designed to remotely detect explosives. The simulants are non-explosive, non-hazardous materials that can be safely handled without any significant precautions. The simulants imitate real explosives in terms of mass density, effective atomic number, x-ray transmission properties, and physical form, including moldable plastics and emulsions/gels.

Kury, John W. (Danville, CA); Anderson, Brian L. (Lodi, CA)

1999-09-28T23:59:59.000Z

433

VIBRATION TEST VIBRPT3_S1100C_19APR2K6.doc  

E-Print Network (OSTI)

modifiche; MIL-HDBK-831 23 April 1999 Preparation of Test Reports (guidance only); UNI ­10653 ­ November

Roma "La Sapienza", Università di

434

Prepare The Nation For Change  

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

Prepare The Nation For Change Print E-mail What Is Adaptation and Mitigation? Adaptation An adjustment in natural and/or human systems to a new or changing environment that exploits beneficial opportunities and moderates negative impacts. Mitigation An intervention to reduce the sources or enhance the sinks of greenhouse gases and other climate warming agents. This intervention could include approaches devised to: reduce emissions of greenhouse gases to the atmosphere to enhance their removal from the atmosphere through storage in geological formations, soils, biomass, or the ocean How do we prepare for global change? Global change is affecting many aspects of society, livelihoods, and the environment. Across the United States and around the world, people are making decisions to effectively minimize (mitigate) and prepare for (adapt) global change.

435

ROCKY MOUNTAIN OILFIELD TESTING CENTER  

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

SAM III PROJECT SAM III PROJECT Sandia National laboratories Prepared for: Project File Documentation Prepared by: MICHAEL J. TAYLOR Project Manager March 31, 1998 JO 850200 : FC 970009 ABSTRACT The Rocky Mountain Oilfield Testing Center (RMOTC) conducted a demonstration of the Surface Area Modulation Downhole Telemetry System (SAM 111) at the Department of Energy's Naval Petroleum Reserve No. 3 (NPR-3), in partnership with Sandia National Laboratories (SNL). The project encompassed the testing of a real-time wireless telemetry system in a simulated Measurement-While-Drilling (MWD) environment. A Surface Area Modulation (SAM) technique demonstrated data transmission rates greater than present techniques, in a deployment mode which requires

436

Chesapeake Testing  

Science Conference Proceedings (OSTI)

... Send E-Mail to NVLAP at: NVLAP@nist.gov. Personal Body Armor Testing. ... 7 Ballistic Resistance of Body Armor, Section 7, Ballistic Test Methods. ...

2014-01-03T23:59:59.000Z

437

Structural Testing  

DOE Green Energy (OSTI)

Structural testing at the National Wind Technology Center (NWTC) offers many benefits to wind turbine companies. NWTC includes a new high bay large enough to test any blade expected during the next 5 years. (There are four test bays.) In 1995, NWTC developed a saphisticated data acquisition system, known as the Blade Structural Testing Real-time Acquisition Interface Network (BSTRAIN), to monitor structural testing through 24-hour continuous video surveillance. NWTC recommends ultimate static-strength and fatigue testing, with nondestructive testing in some cases (vibrational testing is covered in a separate information sheet).

NONE

1996-06-01T23:59:59.000Z

438

NMERI 97/6/33010 IDENTIFICATION AND PROOF TESTING ...  

Science Conference Proceedings (OSTI)

... and Proof Testing of New Total Flooding ... organosilicon polymers have been prepared by incorporation of ... incorporated directly into a polymer, these ...

2012-09-01T23:59:59.000Z

439

Preparation  

Science Conference Proceedings (OSTI)

Table 1   Coefficients of thermal expansion for mold materials.../K 10 â??6 /°F Aluminum 22.5 12.5 Steel 12.1 6.7 Sand/polyvinyl alcohol 12.2 6.8 Sand/sodium silicate 11.5 6.4 Ceramic 12.1â??12.6 6.7â??7.0 Glass prepreg 11.7â??13.1 6.5â??7.3 Graphite prepreg 3.6 2.0 Invar 1.4â??5.2 0.8â??2.9 Monolithic graphite 0.2â??1.8 0.1â??1.0...

440

Criticality safety evaluation report for the cold vacuum drying facility's process water handling system  

SciTech Connect

This report addresses the criticality concerns associated with process water handling in the Cold Vacuum Drying Facility. The controls and limitations on equipment design and operations to control potential criticality occurrences are identified.

NELSON, J.V.

1999-05-12T23:59:59.000Z

Note: This page contains sample records for the topic "handling test prepared" 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

Medical Examiner/Coroner on the Handling of a Body/Human Remains that are Potentially Radiologically Contaminated  

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

The purpose of this Model Procedure is to identify precautions and provide guidance to Medical Examiners/Coroners on the handling of a body or human remains that are potentially contaminated with...

442

Practical Handbook of Soybean Processing and Utilization Chapter 9 Handling, Storage, and Transport of Crude and Crude Degummed Soybean Oil  

Science Conference Proceedings (OSTI)

Practical Handbook of Soybean Processing and Utilization Chapter 9 Handling, Storage, and Transport of Crude and Crude Degummed Soybean Oil Processing eChapters Processing AOCS Press Downloadable pdf of Chapter

443

Deep Frying: Chemistry, Nutrition and Practical ApplicationsChapter 2 Storage and Handling of Finished Frying Oils  

Science Conference Proceedings (OSTI)

Deep Frying: Chemistry, Nutrition and Practical Applications Chapter 2 Storage and Handling of Finished Frying Oils Food Science Health Nutrition Biochemistry eChapters Food Science & Technology Health - Nutrition - Biochemistry Pres

444

The U. S. Department of Energy (DOE) has submitted a planned change request to use shielded containers for emplacement of selected remote-handled (RH) transuranic  

E-Print Network (OSTI)

shielded containers for emplacement of selected remote-handled (RH) transuranic (TRU) waste streams, Carlsbad Field Office, Carlsbad, NM. DOE. 2007. First Remote-Handled Transuranic Waste Shipment arrives for transportation and handling and will prevent releases under the most severe accident conditions. The design

445

WM2008 Conference, February 24-28, 2008, Phoenix, AZ Shielded Payload Containers Will Enhance the Safety and Efficiency of the DOE's Remote Handled  

E-Print Network (OSTI)

the Safety and Efficiency of the DOE's Remote Handled Transuranic Waste Disposal Operations - 8199 R. A for Remote Handled (RH) waste. CH waste is emplaced in a variety of payload container configurations. This robust configuration provides an overpack for waste that otherwise would be remotely handled. Up to a 3

446

Power Handling in ITER: Divertor and Blanket Design and R&D M. Merola 1), D. Loesser 2), R. Raffray 1) on behalf of the ITER Organization, ITER  

E-Print Network (OSTI)

that can be handled via the Remote Handling ports and still have an integer number of cassettes per sector operation. Therefore the divertor is allocated a Remote Handling (RH) Maintenance Class 1. Divertor holes in the FW panels for the RH of the SB, and to minimize the space requirement in the Hot Cell. 3

Raffray, A. René

447

Process for preparing fluorine-18  

DOE Patents (OSTI)

An improved process for preparation of fluorine-18 by a neon (deuteron, alpha particle) fluorine-18 nuclear reaction in a non-reactive enclosed reaction zone wherein a ultrapure product is recovered by heating the reaction zone to a high temperature and removing the product with an inert gas.

Winchell, Harry S. (Lafayette, CA); Wells, Dale K. (Martinez, CA); Lamb, James F. (Albany, CA); Beaudry, Samuel B. (Walnut Creek, CA)

1976-09-21T23:59:59.000Z

448

2009 coal preparation buyer's guide  

Science Conference Proceedings (OSTI)

The guide contains brief descriptions and contact details of 926 US companies supplying coal preparation equipment who exhibited at the 26th annual Coal Prep exhibition and conference, 28-30 April - May 2009, in Lexington, KY, USA. An index of categories of equipment available from the manufacturers is included.

NONE

2009-04-15T23:59:59.000Z

449

Preparation of asymmetric porous materials  

SciTech Connect

A method for preparing an asymmetric porous material by depositing a porous material film on a flexible substrate, and applying an anisotropic stress to the porous media on the flexible substrate, where the anisotropic stress results from a stress such as an applied mechanical force, a thermal gradient, and an applied voltage, to form an asymmetric porous material.

Coker, Eric N. (Albuquerque, NM)

2012-08-07T23:59:59.000Z

450

Photochemical preparation of plutonium pentafluoride  

SciTech Connect

The novel compound plutonium pentafluoride may be prepared by the photodissociation of gaseous plutonium hexafluoride. It is a white solid of low vapor pressure, which consists predominantly of a face-centered cubic structure with a.sub.o =4.2709.+-.0.0005 .ANG..

Rabideau, Sherman W. (Los Alamos, NM); Campbell, George M. (Los Alamos, NM)

1987-01-01T23:59:59.000Z

451

PREPARATION OF HALIDES OF PLUTONIUM  

DOE Patents (OSTI)

A dry chemical method is described for preparing plutonium halides, which consists in contacting plutonyl nitrate with dry gaseous HCl or HF at an elevated temperature. The addition to the reaction gas of a small quantity of an oxidizing gas or a reducing gas will cause formation of the tetra- or tri-halide of plutonium as desired.

Garner, C.S.; Johns, I.B.

1958-09-01T23:59:59.000Z

452

Preparation of gas selective membranes  

DOE Patents (OSTI)

Gas separation membranes which possess improved characteristics as exemplified by selectivity and flux may be prepared by coating a porous organic polymer support with a solution or emulsion of a plasticizer and an organic polymer, said coating being effected at subatmospheric pressures in order to increase the penetration depth of the coating material.

Kulprathipanja, S.; Kulkarni, S.S.; Funk, E.W.

1988-06-14T23:59:59.000Z

453

PROCESS OF PREPARING URANIUM CARBIDE  

DOE Patents (OSTI)

A process of preparing uranium monocarbide is de scribed. Uranium metal is dissolved in cadmium, zinc, cadmium-- zinc, or magnesium-- zinc alloy and a small quantity of alkali metal is added. Addition of stoichiometric amounts of carbon at 500 to 820 deg C then precipitates uranium monocarbide. (AEC)

Miller, W.E.; Stethers, H.L.; Johnson, T.R.

1964-03-24T23:59:59.000Z

454

Joint Working Group-39, Manufacturing Technology Subworking Group-F, remote handling and automation  

Science Conference Proceedings (OSTI)

The terms of reference were reviewed and continue to encompass the scope of activities of the SUBWOG. No revisions to the terms of reference were proposed. The list of site contacts who should receive copies of SUBWOG correspondence and meeting minutes was reviewed and updated. Documents exchanged related to the meeting include: Minutes of the sixth SUBOG 39F meeting; transactions of the fifth topical meeting on robotics and remote handling; data on manipulators was forwarded to LLNL from the robotics group at AEA Harwell; and the specifications of the duct remediation robot from the Rocky Flats Plant.

Merrill, R.D.

1995-02-01T23:59:59.000Z

455

Self-Correcting HVAC Controls: Algorithms for Sensors and Dampers in Air-Handling Units  

SciTech Connect

This report documents the self-correction algorithms developed in the Self-Correcting Heating, Ventilating and Air-Conditioning (HVAC) Controls project funded jointly by the Bonneville Power Administration and the Building Technologies Program of the U.S. Department of Energy. The algorithms address faults for temperature sensors, humidity sensors, and dampers in air-handling units and correction of persistent manual overrides of automated control systems. All faults considered create energy waste when left uncorrected as is frequently the case in actual systems.

Fernandez, Nicholas; Brambley, Michael R.; Katipamula, Srinivas

2009-12-31T23:59:59.000Z

456

Preliminary Project Execution Plan for the Remote-Handled Low-Level Waste Disposal Project  

Science Conference Proceedings (OSTI)

This preliminary project execution plan (PEP) defines U.S. Department of Energy (DOE) project objectives, roles and responsibilities of project participants, project organization, and controls to effectively manage acquisition of capital funds for construction of a proposed remote-handled low-level waste (LLW) disposal facility at the Idaho National Laboratory (INL). The plan addresses the policies, requirements, and critical decision (CD) responsibilities identified in DOE Order 413.3B, 'Program and Project Management for the Acquisition of Capital Assets.' This plan is intended to be a 'living document' that will be periodically updated as the project progresses through the CD process to construction and turnover for operation.

David Duncan

2011-05-01T23:59:59.000Z

457

Fuels Preparation Department monthly report, November 1962  

SciTech Connect

This document details activities of the Fuels Preparation Department during the month of November 1962.

1962-12-07T23:59:59.000Z

458

TA Orientation 2007 Activity #3 Lab Preparation  

E-Print Network (OSTI)

TA Orientation 2007 Activity #3 Lab Preparation Activity 3 - Page 1 Preparation for Teaching a Lab, based on the papers of these 6 students. #12;TA Orientation 2007 Activity #3 Lab Preparation Activity 3 - Page 2 #12;TA Orientation 2007 Activity #3 Lab Preparation Activity 3 - Page 3 Warm-up Questions

Minnesota, University of

459

TA Orientation 2006 Activity #3 Lab Preparation  

E-Print Network (OSTI)

TA Orientation 2006 Activity #3 Lab Preparation Activity 3 ­ Page 1 Preparation for Teaching a Lab, based on the papers of these 6 students. #12;TA Orientation 2006 Activity #3 Lab Preparation Activity 3 ­ Page 2 #12;TA Orientation 2006 Activity #3 Lab Preparation Activity 3 ­ Page 3 Warm-up Questions

Minnesota, University of

460

ROCKY MOUNTAIN OILFIELD TESTING CENTER PROJECT TEST RESULTS  

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

MAG-WELL DOWNHOLE MAGNETIC FLUID CONDITIONERS MAG-WELL DOWNHOLE MAGNETIC FLUID CONDITIONERS APRIL 4,1995 FC9511 / 95PT5 ROCKY MOUNTAIN OILFIELD TESTING CENTER MAG-WELL DOWNHOLE MAGNETIC FLUID CONDITIONERS PROJECT TEST RESULTES Prepared for: Industry Publication Prepared by: MICHAEL R. TYLER RMOTC Field Engineer November 28, 1995 650100/9511:jb ABSTRACT November 28, 1995 The Rocky Mountain Oilfield Testing Center (RMOTC) conducted a field test on the Mag-Well Downhole Magnetic Fluid Conditioners (MFCs), at the Naval Petroleum Reserve No. 3 (NPR- 3) located 35 miles north of Casper in Natrona County, Wyoming. Mag-Well, Inc., manufactures the MFCs, that are designed to reduce scale and paraffin buildup on the rods, tubing and downhole pump of producing oil wells. The Mag-Well magnetic tools failed to

Note: This page contains sample records for the topic "handling test prepared" 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

Advanced Burner Test Reactor - Preconceptual Design Report  

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

Burner Test Reactor Preconceptual Design Report ANL-ABR-1 (ANL-AFCI-173) Nuclear Engineering Division Disclaimer This report was prepared as an account of work sponsored by an...

462

Mixed waste solidification testing on polymer and cement-based waste forms in support of Hanford`s WRAP 2A facility  

Science Conference Proceedings (OSTI)

A testing program has been conducted by the Westinghouse Hanford Company to confirm the baseline waste form selection for use in Waste Receiving and Processing (WRAP) Module 2A. WRAP Module 2A will provide treatment required to properly dispose of containerized contact-handled, mixed low-level waste at the US Department of Energy Hanford Site in south-central Washington State. Solidification/stabilization has been chosen as the appropriate treatment for this waste. This work is intended to test cement-based, thermosetting polymer, and thermoplastic polymer solidification media to substantiate the technology approach for WRAP Module 2A. Screening tests were performed using the major chemical constituent of each waste type to measure the gross compatibility with the immobilization media and to determine formulations for more detailed testing. Surrogate materials representing each of the eight waste types were prepared in the laboratory. These surrogates were then solidified with the selected immobilization media and subjected to a battery of standard performance tests. Detailed discussion of the laboratory work and results are contained in this report.

Burbank, D.A. Jr.; Weingardt, K.M.

1993-10-01T23:59:59.000Z

463

EIS-0364: Notice of Intent to Prepare an Environmental Impact Statement |  

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

4: Notice of Intent to Prepare an Environmental Impact 4: Notice of Intent to Prepare an Environmental Impact Statement EIS-0364: Notice of Intent to Prepare an Environmental Impact Statement Decommissioning of the Fast Flux Test Facility at the Hanford Site, Richland, Washington The U.S. Department of Energy (DOE) announces its intent to prepare an Environmental Impact Statement (EIS), pursuant to the National Environmental Policy Act of 1969 (NEPA), on proposed decommissioning of the Fast Flux Test Facility (FFTF) at the Hanford Site, Richland, Washington. Notice of Intent to Prepare an Environmental Impact Statement for the Decommissioning of the Fast Flux Test Facility at the Hanford Site, Richland, Washington (DOE/EIS-0364) (August 2004 - 69 FR 50176) More Documents & Publications EIS-0310: Amended Record of Decision

464

ROCKY MOUNTAIN OILFIELD TESTING CENTER  

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

AUTOMATIC SHUTDOWN VALVE AUTOMATIC SHUTDOWN VALVE CAMBRIA VALVE CORPORATION OCTOBER 17, 1995 FC9536/95ET1 RMOTC TEST REPORT Automatic Shutdown Valve Cambria Valve Corporation Prepared for: INDUSTRY PUBLICATION Prepared by: MICHAEL J. TAYLOR RMOTC Project Manager October 17, 1995 551103/9536:jb TABLE OF CONTENTS Page Introduction 1 Figure 1 2 Test Details 3 Table 1 4 Conclusions 5 Acknowledgments 5 ABSTRACT The Rocky Mountain Oilfield Testing Center (RMOTC) conducted a test of an Automatic Shutdown Valve (ASDV) for hydraulic systems at the Naval Petroleum Reserve No. 3 (NPR- 3). The Cambria Valve Corporation (CVC) manufactures the 3-Port ASDV that is designed to automatically shut down the flow of fluid through a hydraulic system in the event of a ruptured line and safely redirect flow to a bypass system. The CVC ASDV effectively demonstrated its

465

Test Diversity  

E-Print Network (OSTI)

This paper describes a novel method for measuring the degree to which a set of test cases executes a given program in diverse ways with respect to the two fundamental programming concepts: control and data. Test Diversity is a method for measuring the variety of software control flow and data flow, comprising of four new measures: conditional diversity, data diversity, standard deviation of diversity, and test orthogonality. These closely-related measures could be used to evaluate the test effectiveness and the test-effort distribution of a test suite. The Diversity Analyzer is a novel industrial-strength testing tool that can currently perform diversity analysis on software written in C/C++/C#/VB in Windows and.NET environments. The Diversity Analyzer is used to evaluate the fault-detection effectiveness of Test Diversity on various types of industrial projects. Key Words: testing tools, verification, theory, experimentation, conditional diversity, data diversity, standard deviation,

Borislav Nikolik

2006-01-01T23:59:59.000Z

466

End-To-End Request Handling In Distributed Video-On-Demand Systems  

E-Print Network (OSTI)

In this paper we provide an end-to-end analysis of a distributed Video-on-Demand system consisting of a hierarchy of server clusters and networks. We develop an analytical framework for remote service by combining two critical subsystems, the storage and the network subsystems. We use this framework to analyze different request handling policies that maximize throughput. We show that the results of our end-to-end analysis are scalable and may be used to predict system performance when the demand changes and the system size is scaled up. The relative performance order of different request handling policies remains the same, with the policy that uses retrials at more than one resource exhibiting better performance than other policies. Keywords: Network and Resource Management, Distributed VoD. 1 INTRODUCTION The focus of this paper is to conduct an end-to-end analysis that provides insight into efficient operation of a hierarchical Video-on-Demand (VoD) system. Two issues dealt in this...

Padmavathi Mundur; Robert Simon; Arun Sood

1999-01-01T23:59:59.000Z

467

Evaluation of the Total Cost of Ownership of Fuel Cell-Powered Material Handling Equipment  

SciTech Connect

This report discusses an analysis of the total cost of ownership of fuel cell-powered and traditional battery-powered material handling equipment (MHE, or more typically 'forklifts'). A number of fuel cell MHE deployments have received funding support from the federal government. Using data from these government co-funded deployments, DOE's National Renewable Energy Laboratory (NREL) has been evaluating the performance of fuel cells in material handling applications. NREL has assessed the total cost of ownership of fuel cell MHE and compared it to the cost of ownership of traditional battery-powered MHE. As part of its cost of ownership assessment, NREL looked at a range of costs associated with MHE operation, including the capital costs of battery and fuel cell systems, the cost of supporting infrastructure, maintenance costs, warehouse space costs, and labor costs. Considering all these costs, NREL found that fuel cell MHE can have a lower overall cost of ownership than comparable battery-powered MHE.

Ramsden, T.

2013-04-01T23:59:59.000Z

468