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Sample records for glovebox ha-21i muffle

  1. Plan for the Startup of HA-21I Furnace Operations at the Plutonium Finishing Plant (PFP)

    WILLIS, H.T.

    2000-01-01

    Achievement of Thermal Stabilization mission elements require the installation and startup of three additional muffle furnaces for the thermal stabilization of plutonium and plutonium bearing materials at the Plutonium Finishing Plant (PFP). The release to operate these additional furnaces will require an Activity Based Startup Review. The conduct of the Activity Based Startup Review (ABSR) was approved by Fluor Daniel Hanford on October 15, 1999. This plan has been developed with the objective of identifying those activities needed to guide the controlled startup of five furnaces from authorization to unrestricted operations by adding the HA-211 furnaces in an orderly and safe manner after the approval to Startup has been given. The Startup Plan provides a phased approach that bridges the activities between the completion of the Activity Based Startup Review authorizing the use of the three additional furnaces and the unrestricted operation of the five thermal stabilization muffle furnaces. The four phases are: (1) the initiation of five furnace operations using three empty (simulated full) boat charges from HA-211 and two full charges from HC-21C; (2) three furnace operations (one full charge from HA-211 and two full charges from HC-21C); (3) four furnace operations (two full charges from HA-211 and two full charges from HC-21C); and (4) integrated five furnace operations and unrestricted operations. Phase 1 of the Plan will be considered as the cold runs. This Plan also provides management oversight and administrative controls that are to be implemented until unrestricted operations are authorized. It also provides a formal review process for ensuring that all preparations needed for full five furnace operations are completed and formally reviewed prior to proceeding to the increased activity levels associated with five furnace operations. Specific objectives include: (1) To ensure that activities are conducted in a safe manner. (2) To provide supplemental

  2. CSER 98-003: criticality safety evaluation report for PFP glovebox HC-21A with button can opening

    ERICKSON, D.G.

    1999-01-01

    Glovebox HC-21A is an enclosure where cans containing plutonium metal buttons or other plutonium bearing materials are prepared for thermal stabilization in the muffle furnaces. The Inert Atmosphere Confinement (IAC), a new feature added to Glovebox HC-21 A, allows the opening of containers suspected of containing hydrided plutonium metal. The argon atmosphere in the IAC prevents an adverse reaction between oxygen and the hydride. The hydride is then stabilized in a controlled manner to prevent glovebox over pressurization. After removal from the containers, the plutonium metal buttons or plutonium bearing materials will be placed into muffle furnace boats and then be sent to one of the muffle furnace gloveboxes for stabilization. The materials allowed to be brought into Glovebox HC-21A are limited to those with a hydrogen to fissile atom ratio (H/X) ≤ 20. Glovebox HC-21A is classified as a DRY glovebox, meaning it has no internal liquid lines, and no free liquids or solutions are allowed to be introduced. The double contingency principle states that designs shall incorporate sufficient factors of safety to require at least two unlikely, independent, and concurrent changes in process conditions before a criticality accident is possible. This criticality safety evaluation report (CSER) shows that the operations to be performed in this glovebox are safe from a criticality standpoint. No single identified event that causes criticality controls to be lost exceeded the criticality safety limit of k eff = 0.95 (including uncertainties). Therefore, this CSER meets the requirements for a criticality analysis contained in the Hanford Site Nuclear Criticality Safety Manual, HNF-PRO-334, and meets the double contingency principle

  3. CSER 98-003: Criticality safety evaluation report for PFP glovebox HC-21A with button can opening

    ERICKSON, D.G.

    1999-01-01

    Glovebox HC-21A is an enclosure where cans containing plutonium metal buttons or other plutonium bearing materials are prepared for thermal stabilization in the muffle furnaces. The Inert Atmosphere Confinement (IAC), a new feature added to Glovebox HC-21A, allows the opening of containers suspected of containing hydrided plutonium metal. The argon atmosphere in the IAC prevents an adverse reaction between oxygen and the hydride. The hydride is then stabilized in a controlled manner to prevent glovebox over pressurization. After removal from the containers, the plutonium metal buttons or plutonium bearing materials will be placed into muffle furnace boats and then be sent to one of the muffle furnace gloveboxes for stabilization. The materials allowed to be brought into GloveboxHC-21 A are limited to those with a hydrogen to fissile atom ratio (H/X) ≤ 20. Glovebox HC-21A is classified as a DRY glovebox, meaning it has no internal liquid lines, and no free liquids or solutions are allowed to be introduced. The double contingency principle states that designs shall incorporate sufficient factors of safety to require at least two unlikely, independent, and concurrent changes in process conditions before a criticality accident is possible. This criticality safety evaluation report (CSER) shows that the operations to be performed in this glovebox are safe from a criticality standpoint. No single identified event that causes criticality controls to be lost exceeded the criticality safety limit of k eff = 0.95. Therefore, this CSER meets the requirements for a criticality analysis contained in the Hanford Site Nuclear Criticality Safety Manual, HNF-PRO-334, and meets the double contingency principle

  4. Glovebox decontamination technology comparison

    Quintana, D.M.; Rodriguez, J.B.; Cournoyer, M.E.

    1999-01-01

    Reconfiguration of the CMR Building and TA-55 Plutonium Facility for mission requirements will require the disposal or recycle of 200--300 gloveboxes or open front hoods. These gloveboxes and open front hoods must be decontaminated to meet discharge limits for Low Level Waste. Gloveboxes and open front hoods at CMR have been painted. One of the deliverables on this project is to identify the best method for stripping the paint from large numbers of gloveboxes. Four methods being considered are the following: conventional paint stripping, dry ice pellets, strippable coatings, and high pressure water technology. The advantages of each technology will be discussed. Last, cost comparisons between the technologies will be presented

  5. Glovebox and Experiment Safety

    Maas, Gerard

    2005-12-01

    Human spaceflight hardware and operations must comply with NSTS 1700.7. This paper discusses how a glovebox can help.A short layout is given on the process according NSTS/ISS 13830, explaining the responsibility of the payload organization, the approval authority of the PSRP and the defined review phases (0 till III).Amongst others, the following requirement has to be met:"200.1 Design to Tolerate Failures. Failure tolerance is the basic safety requirement that shall be used to control most payload hazards. The payload must tolerate a minimum number of credible failures and/or operator errors determined by the hazard level. This criterion applies when the loss of a function or the inadvertent occurrence of a function results in a hazardous event.200.1a Critical Hazards. Critical hazards shall be controlled such that no single failure or operator error can result in damage to STS/ISS equipment, a nondisabling personnel injury, or the use of unscheduled safing procedures that affect operations of the Orbiter/ISS or another payload.200.1b Catastrophic Hazards. Catastrophic hazards shall be controlled such that no combination of two failures or operator errors can result in the potential for a disabling or fatal personnel injury or loss of the Orbiter/ISS, ground facilities or STS/ISS equipment."For experiments in material science, biological science and life science that require real time operator manipulation, the above requirement may be hard or impossible to meet. Especially if the experiment contains substances that are considered hazardous when released into the habitable environment. In this case operation of the experiment in a glovebox can help to comply.A glovebox provides containment of the experiment and at the same time allows manipulation and visibility to the experiment.The containment inside the glovebox provides failure tolerance because the glovebox uses a negative pressure inside the working volume (WV). The level of failure tolerance is dependent of

  6. TRU waste characterization chamber gloveboxes

    Duncan, D. S.

    1998-01-01

    Argonne National Laboratory-West (ANL-W) is participating in the Department of Energy's (DOE) National Transuranic Waste Program in support of the Waste Isolation Pilot Plant (WIPP). The Laboratory's support currently consists of intrusive characterization of a selected population of drums containing transuranic waste. This characterization is performed in a complex of alpha containment gloveboxes termed the Waste Characterization Gloveboxes. Made up of the Waste Characterization Chamber, Sample Preparation Glovebox, and the Equipment Repair Glovebox, they were designed as a small production characterization facility for support of the Idaho National Engineering and Environmental Laboratory (INEEL). This paper presents salient features of these gloveboxes

  7. Students build glovebox at Space Science Center

    2001-01-01

    Students in the Young Astronaut Program at the Coca-Cola Space Science Center in Columbus, GA, constructed gloveboxes using the new NASA Student Glovebox Education Guide. The young astronauts used cardboard copier paper boxes as the heart of the glovebox. The paper boxes transformed into gloveboxes when the students pasted poster-pictures of an actual NASA microgravity science glovebox inside and outside of the paper boxes. The young astronauts then added holes for gloves and removable transparent top covers, which completed the construction of the gloveboxes. This image is from a digital still camera; higher resolution is not available.

  8. Redefining design criteria for Pu-238 gloveboxes

    Acosta, S.V.

    1998-01-01

    Enclosures for confinement of special nuclear materials (SNM) have evolved into the design of gloveboxes. During the early stages of glovebox technology, established practices and process operation requirements defined design criteria. Proven boxes that performed and met or exceeded process requirements in one group or area, often could not be duplicated in other areas or processes, and till achieve the same success. Changes in materials, fabrication and installation methods often only met immediate design criteria. Standardization of design criteria took a big step during creation of ''Special-Nuclear Materials R and D Laboratory Project, Glovebox standards''. The standards defined design criteria for every type of process equipment in its most general form. Los Alamos National Laboratory (LANL) then and now has had great success with Pu-238 processing. However with ever changing Environment Safety and Health (ES and H) requirements and Ta-55 Facility Configuration Management, current design criteria are forced to explore alternative methods of glovebox design fabrication and installation. Pu-238 fuel processing operations in the Power Source Technologies Group have pushed the limitations of current design criteria. More than half of Pu-238 gloveboxes are being retrofitted or replaced to perform the specific fuel process operations. Pu-238 glovebox design criteria are headed toward process designed single use glovebox and supporting line gloveboxes. Gloveboxes that will house equipment and processes will support TA-55 Pu-238 fuel processing needs into the next century and extend glovebox expected design life

  9. Design criteria for plutonium gloveboxes

    Anon.

    1981-01-01

    The standard defines criteria for the design of glovebox systems to be used for the handling of plutonium in any form or isotopic composition or when mixed with other elements or compounds. The glovebox system is a series of physical barriers provided with glove ports and gloves, through which process and maintenance operations may be performed, together with an operating ventilation system. The system minimizes the potential for release of radioactive material to the environment, protects operators from contamination, and mitigates the consequences of abnormal condiations. The standard covers confinement, construction, materials, windows, glove ports, gloves, equipment insertion and removal, lighting, ventilation, fire protection, criticality prevention, services and utilities, radiation shielding, waste systems, monitoring and alarm systems, safeguards, quality assurance, and decommissioning

  10. Hands-on glovebox decommissioning

    Smith, D.

    1997-01-01

    Over recent years, the United Kingdom Atomic Energy Authority (UKAEA) has undertaken the decommissioning of a large number of Plutonium glove boxes at Winfrith Technology Centre. UKAEA has managed this work on behalf of the DTI, who funded most of the work. Most of the planning and practical work was contracted to AEA Technology (AEAT), which, until 1996, was the commercial arm of UKAEA, but is now a private company. More than 70 gloveboxes, together with internal plant and equipment such as ball mills, presses and furnaces, have been successfully size reduced into drums for storage, leaving the area, in which they were situated, in a clean condition. (UK)

  11. Electrochemical decontamination system for actinide processing gloveboxes

    Wedman, D.E.; Lugo, J.L.; Ford, D.K.; Nelson, T.O.; Trujillo, V.L.; Martinez, H.E.

    1998-03-01

    An electrolytic decontamination technology has been developed and successfully demonstrated at Los Alamos National Laboratory (LANL) for the decontamination of actinide processing gloveboxes. The technique decontaminates the interior surfaces of stainless steel gloveboxes utilizing a process similar to electropolishing. The decontamination device is compact and transportable allowing it to be placed entirely within the glovebox line. In this way, decontamination does not require the operator to wear any additional personal protective equipment and there is no need for additional air handling or containment systems. Decontamination prior to glovebox decommissioning reduces the potential for worker exposure and environmental releases during the decommissioning, transport, and size reduction procedures which follow. The goal of this effort is to reduce contamination levels of alpha emitting nuclides for a resultant reduction in waste level category from High Level Transuranic (TRU) to low Specific Activity (LSA, less than or equal 100 nCi/g). This reduction in category results in a 95% reduction in disposal and disposition costs for the decontaminated gloveboxes. The resulting contamination levels following decontamination by this method are generally five orders of magnitude below the LSA specification. Additionally, the sodium sulfate based electrolyte utilized in the process is fully recyclable which results in the minimum of secondary waste. The process bas been implemented on seven gloveboxes within LANL's Plutonium Facility at Technical Area 55. Of these gloveboxes, two have been discarded as low level waste items and the remaining five have been reused

  12. Glovebox

    Herrmann, F.

    1980-01-01

    On handling nitric solutions in the glove box nitrous gases are formed that are sucked off via a heated activated charcoal filter and a catalyst cartridge containing e.g. the FG 590 H catalist (Degussa). By the activated charcoal the nitrous gases are reduced to N 2 and CO gas; the catalyst will oxidize CO to CO 2 . The CO 2 obtained is discharged through an exhaust air filter in the glove box. (DG) [de

  13. Automated, High Temperature Furnace for Glovebox Operation

    Neikirk, K.

    2001-01-01

    The U.S. Department of Energy will immobilize excess plutonium in the proposed Plutonium Immobilization Plant (PIP) at the Savannah River Site (SRS) as part of a two track approach for the disposition of weapons usable plutonium. As such, the Department of Energy is funding a development and testing effort for the PIP. This effort is being performed jointly by Lawrence Livermore National Laboratory (LLNL), Westinghouse Savannah River Company (WSRC), Pacific Northwest National Laboratory (PNNL), and Argonne National Laboratory (ANL). The Plutonium Immobilization process involves the disposition of excess plutonium by incorporation into ceramic pucks. As part of the immobilization process, furnaces are needed for sintering the ceramic pucks. The furnace being developed for puck sintering is an automated, bottom loaded furnace with insulting package and resistance heating elements located within a nuclear glovebox. Other furnaces considered for the application include retort furnaces and pusher furnaces. This paper, in part, will discuss the furnace technologies considered and furnace technology selected to support reliable puck sintering in a glovebox environment. Due to the radiation levels and contamination associated with the plutonium material, the sintering process will be fully automated and contained within nuclear material gloveboxes. As such, the furnace currently under development incorporates water and air cooling to minimize heat load to the glovebox. This paper will describe the furnace equipment and systems needed to employ a fully automated puck sintering process within nuclear gloveboxes as part of the Plutonium Immobilization Plant

  14. 2014 AFCI Glovebox Event Executive Summary

    Campbell, Joseph Lenard

    2016-01-01

    One of the primary INL missions is to support development of advanced fuels with the goal of creating reactor fuels that produce less waste and are easier to store. The Advanced Fuel Cycle Initiative (AFCI) Glovebox in the Fuel Manufacturing Facility (FMF) is used for several fuel fabrication steps that involve transuranic elements, including americium. The AFCI glove box contains equipment used for fuel fabrication, including an arc melter - a small, laboratory-scale version of an electric arc furnace used to make new metal alloys for research - and an americium distillation apparatus. This overview summarizes key findings related to the investigation into the releases of airborne radioactivity that occurred in the AFCI glovebox room in late August and early September 2014. The full report (AFCI Glovebox Radiological Release - Evaluation, Corrective Actions and Testing, INL/INL-15-36996) provides details of the identified issues, corrective actions taken as well as lessons learned

  15. Scrap of gloveboxes No. 801-W and No. 802-W

    Ohuchi, S; Kurosawa, M; Okane, S; Usui, T

    2002-01-01

    Both gloveboxes No. 801-W for measuring samples of uranium or plutonium and No. 802-W for analyzing the quantity of uranium or plutonium are established at twenty five years ago in the analyzing room No. 108 of Plutonium Fuel Research Facility. It was planned to scrap the gloveboxes and to establish new gloveboxes. This report describes the technical view of the scrapping works.

  16. Robotic system for glovebox size reduction

    KWOK, KWAN S.; MCDONALD, MICHAEL J.

    2000-01-01

    The Intelligent Systems and Robotics Center (ISRC) at Sandia National Laboratories (SNL) is developing technologies for glovebox size reduction in the DOE nuclear complex. A study was performed for Kaiser-Hill (KH) at the Rocky Flats Environmental Technology Site (RFETS) on the available technologies for size reducing the glovebox lines that require size reduction in place. Currently, the baseline approach to these glovebox lines is manual operations using conventional mechanical cutting methods. The study has been completed and resulted in a concept of the robotic system for in-situ size reduction. The concept makes use of commercially available robots that are used in the automotive industry. The commercially available industrial robots provide high reliability and availability that are required for environmental remediation in the DOE complex. Additionally, the costs of commercial robots are about one-fourth that of the custom made robots for environmental remediation. The reason for the lower costs and the higher reliability is that there are thousands of commercial robots made annually, whereas there are only a few custom robots made for environmental remediation every year. This paper will describe the engineering analysis approach used in the design of the robotic system for glovebox size reduction

  17. Ventilation of gloveboxes and containment shells

    Guetron, R.

    1984-01-01

    In this paper are defined fundamental principles for the ventilation of containment enclosures and gloveboxes, and examined criteria required to maintain containment in normal or accidental conditions. Dimensioning of ventilation network and associated equipment (adjustement and filtering devices). Some examples are given [fr

  18. Automated, High Temperature Furnace for Glovebox Operation

    Neikirk, K.

    2001-01-01

    The Plutonium Immobilization Project (PIP), to be located at the Savannah River Site SRS, is a combined development and testing effort by Lawrence Livermore National Laboratory (LLNL), Westinghouse Savannah River Company (WSRC), Pacific Northwest National Laboratory (PNNL), Argonne National Laboratory (ANL), and the Australian National Science and Technology Organization (ANSTO). The Plutonium Immobilization process involves the disposition of excess plutonium by incorporation into ceramic pucks. As part of the immobilization process, furnaces are needed for sintering the ceramic pucks. The furnace being developed for puck sintering is an automated, bottom loaded furnace with insulating package and resistance heating elements located within a nuclear glovebox. Other furnaces types considered for the application include retort furnaces and pusher furnaces. This paper, in part, will discuss the furnace technologies considered and furnace technology selected to support reliable puck sintering in a glovebox environment

  19. Design considerations for heated wells in gloveboxes

    Frigo, A. A.; Preuss, D. E.

    1999-01-01

    Heated wells in gloveboxes have been used for many years by the Argonne National Laboratory Chemical Technology Division for nuclear-technology, waste-management, chemical-technology, and analytical-chemistry research. These wells allow experiments to be isolated from the main working volume of the glovebox. In addition, wells, when sealed, allow experiments to be conducted under pressurized or vacuum conditions. Until recently, typical maximum operational temperatures were about 500 C. However, more recent research is requiring operational temperatures approaching 900 C. These new requirements pose interesting design challenges that must be resolved. Some problem areas include temperature effects on material properties, maintaining a seal, cooling selected areas, and minimizing stresses. This paper discusses issues related to these design challenges and the ways in which these issues have been resolved

  20. Institutional glovebox safety committee (IGSC) annual report FY2010

    Cournoyer, Michael E [Los Alamos National Laboratory; Roybal, Richard F [Los Alamos National Laboratory; Lee, Roy J [Los Alamos National Laboratory

    2011-01-04

    The Institutional Glovebox Safety Committee (IGSC) was chartered to minimize and/or prevent glovebox operational events. Highlights of the IGSC's third year are discussed. The focus of this working committee is to address glovebox operational and safety issues and to share Lessons Learned, best practices, training improvements, and glovebox glove breach and failure data. Highlights of the IGSC's third year are discussed. The results presented in this annual report are pivotal to the ultimate focus of the glovebox safety program, which is to minimize work-related injuries and illnesses. This effort contributes to the LANL Continuous Improvement Program by providing information that can be used to improve glovebox operational safety.

  1. Unique features in the ARIES glovebox line

    Martinez, H.E.; Brown, W.G.; Flamm, B.; James, C.A.; Laskie, R.; Nelson, T.O.; Wedman, D.E.

    1998-01-01

    A series of unique features have been incorporated into the Advanced Recovery and Integrated Extraction System (ARIES) at the Los Alamos National Laboratory, TA-55 Plutonium Facility. The features enhance the material handling in the process of the dismantlement of nuclear weapon primaries in the glovebox line. Incorporated into these features are the various plutonium process module's different ventilation zone requirements that the material handling systems must meet. These features include a conveyor system that consists of a remotely controlled cart that transverses the length of the conveyor glovebox, can be operated from a remote location and can deliver process components to the entrance of any selected module glovebox. Within the modules there exists linear motion material handling systems with lifting hoist, which are controlled via an Allen Bradley control panel or local control panels. To remove the packaged products from the hot process line, the package is processed through an air lock/electrolytic decontamination process that removes the radioactive contamination from the outside of the package container and allows the package to be removed from the process line

  2. An Integrated Science Glovebox for the Gateway Habitat

    Calaway, M. J.; Evans, C. A.; Garrison, D. H.; Bell, M. S.

    2018-01-01

    Next generation habitats for deep space exploration of cislunar space, the Moon, and ultimately Mars will benefit from on-board glovebox capability. Such a glovebox facility will maintain sample integrity for a variety of scientific endeavors whether for life science, materials science, or astromaterials. Glovebox lessons learned from decades of astromaterials curation, ISS on-board sample handling, and robust analog missions provide key design and operational factors for inclusion in on-going habitat development.

  3. WRAP low level waste (LLW) glovebox operational test report

    Kersten, J.K.

    1998-01-01

    The Low Level Waste (LLW) Process Gloveboxes are designed to: receive a 55 gallon drum in an 85 gallon overpack in the Entry glovebox (GBIOI); and open and sort the waste from the 55 gallon drum, place the waste back into drum and relid in the Sorting glovebox (GB 102). In addition, waste which requires further examination is transferred to the LLW RWM Glovebox via the Drath and Schraeder Bagiess Transfer Port (DO-07-201) or sent to the Sample Transfer Port (STC); crush the drum in the Supercompactor glovebox (GB 104); place the resulting puck (along with other pucks) into another 85 gallon overpack in the Exit glovebox (GB 105). The status of the waste items is tracked by the Data Management System (DMS) via the Plant Control System (PCS) barcode interface. As an item is moved from the entry glovebox to the exit glovebox, the Operator will track an items location using a barcode reader and enter any required data on the DMS console. The Operational Test Procedure (OTP) will perform evolution's (described below) using the Plant Operating Procedures (POP) in order to verify that they are sufficient and accurate for controlled glovebox operation

  4. WRAP low level waste (LLW) glovebox operational test report

    Kersten, J.K.

    1998-02-19

    The Low Level Waste (LLW) Process Gloveboxes are designed to: receive a 55 gallon drum in an 85 gallon overpack in the Entry glovebox (GBIOI); and open and sort the waste from the 55 gallon drum, place the waste back into drum and relid in the Sorting glovebox (GB 102). In addition, waste which requires further examination is transferred to the LLW RWM Glovebox via the Drath and Schraeder Bagiess Transfer Port (DO-07-201) or sent to the Sample Transfer Port (STC); crush the drum in the Supercompactor glovebox (GB 104); place the resulting puck (along with other pucks) into another 85 gallon overpack in the Exit glovebox (GB 105). The status of the waste items is tracked by the Data Management System (DMS) via the Plant Control System (PCS) barcode interface. As an item is moved from the entry glovebox to the exit glovebox, the Operator will track an items location using a barcode reader and enter any required data on the DMS console. The Operational Test Procedure (OTP) will perform evolution`s (described below) using the Plant Operating Procedures (POP) in order to verify that they are sufficient and accurate for controlled glovebox operation.

  5. Guidelines for gloveboxes. Section 5.14: Electrical

    Tollner, R.L.

    1995-07-01

    This is the electric portion of the design guidelines for gloveboxes developed by the American Glovebox Society. The topics include applicable codes/industry standards, penetrations/feedthroughs, wireways, junction boxes, receptacles, derating factors, conductors, conductor insulation and grounding. References for the guidelines are provided

  6. Compatibility of selected elastomers with plutonium glovebox environment

    Burns, R.

    1994-06-01

    This illustrative test was undertaken as a result of on-going failure of elastomer components in plutonium gloveboxes. These failures represent one of the major sources of required maintenance to keep gloveboxes operational. In particular, it was observed that the introduction of high specific activity Pu-238 into a glovebox, otherwise contaminated with Pu-239, resulted in an inordinate failure of elastomer components. Desiring to keep replacement of elastomer components to a minimum, a decision to explore a few possible alternative elastomer candidates was undertaken and reported upon herewith. Sample specimens of Neoprene, Urethane, Viton, and Hypalon elastomeric formulations were obtained from the Bacter Rubber Company. Strips of the elastomer specimens were placed in a plutonium glovebox and outside of a glovebox, and were observed for a period of three years. Of the four types of elastomers, only Hypalon remained completely viable

  7. Inert atmosphere system for plutonium processing gloveboxes

    Bogard, C.F.; Calkins, K.W.; Rogers, R.F.

    1975-01-01

    Recent efforts to reduce fire hazards in plutonium processing operations are described. In such operations, the major environmental controls are developed through various kinds of glovebox systems. In evaluating the air-atmosphere glovebox systems, formerly in use at Rocky Flats and many other plants, a decision was made to convert to a recirculating ''inert'' atmosphere. The inert atmosphere consists of nitrogen, supplied from an on-site generating plant, diluting oxygen content to one to 5 percent by volume. Problems encountered during the change over included: determination of all factors influencing air leakage into the system, and reducing leakage to the practical minimum; meeting all fire and safety standards on the filter plenum and exhaust systems; provision for converting portions of the system to an air atmosphere to conduct maintenance work; inclusion of oxygen analyzers throughout the system to check gas quality and monitor for leaks; and the use of automatic controls to protect against a variety of potential malfunctions. The current objectives to reduce fire hazards have been met and additional safeguards were added. The systems are operating satisfactorily. (U.S.)

  8. The chemical transformation of calcium in Shenhua coal during combustion in a muffle furnace

    Tian, Sida [North China Electric Power Univ., Beijing (China). School of Energy, Power and Mechanical Engineering; Ministry of Education, Beijing (China). Key Lab. of Condition Monitoring and Control for Power Plant Equipment; Zhuo, Yuqun; Chen, Changhe [Tsinghua Univ., Beijing (China). Dept. of Thermal Engineering; Ministry of Education, Beijing (China). Key Lab. for Thermal Science and Power Engineering; Shu, Xinqian [China Univ. of Mining and Technology, Beijing (China). School of Chemical and Environmental Engineering

    2013-07-01

    The chemical reaction characteristics of calcium in three samples of Shenhua coal, i.e. raw sample, hydrochloric acid washed sample and hydrochloric acid washed light fraction, during combustion in a muffle furnace have been investigated in this paper. Ca is bound by calcite and organic matter in Shenhua coal. X ray diffraction (XRD) phase analysis has been conducted to these samples' combustion products obtained by heating at different temperatures. It has been found that the organically-bound calcium could easily react with clays and transform into gehlenite and anorthite partially if combusted under 815 C, whilst the excluded minerals promoted the conversion of gehlenite to anorthite. Calcite in Shenhua coal decomposed into calcium oxide and partially transformed into calcium sulfate under 815 C, and formed gehlenite and anorthite under 1,050 C. Calcite and other HCl-dissolved minerals in Shenhua coal were responsible mainly for the characteristic that the clay minerals in Shenhua coal hardly became mullite during combustion.

  9. Glovebox pressure relief and check valve

    Blaedel, K.L.

    1986-01-01

    This device is a combined pressure relief valve and check valve providing overpressure protection and preventing back flow into an inert atmosphere enclosure. The pressure relief is embodied by a submerged vent line in a mercury reservior, the releif pressure being a function of the submerged depth. The pressure relief can be vented into an exhaust system and the relieving pressure is only slightly influenced by the varying pressure in the exhaust system. The check valve is embodied by a ball which floats on the mercury column and contacts a seat whenever vacuum exists within the glovebox enclosure. Alternatively, the check valve is embodied by a vertical column of mercury, the maximum back pressure being a function of the height of the column of mercury

  10. Glovebox pressure relief and check valve

    Blaedel, K.L.

    1986-03-17

    This device is a combined pressure relief valve and check valve providing overpressure protection and preventing back flow into an inert atmosphere enclosure. The pressure relief is embodied by a submerged vent line in a mercury reservior, the releif pressure being a function of the submerged depth. The pressure relief can be vented into an exhaust system and the relieving pressure is only slightly influenced by the varying pressure in the exhaust system. The check valve is embodied by a ball which floats on the mercury column and contacts a seat whenever vacuum exists within the glovebox enclosure. Alternatively, the check valve is embodied by a vertical column of mercury, the maximum back pressure being a function of the height of the column of mercury.

  11. Low impact plutonium glovebox D ampersand D

    Rose, R.W.

    1995-01-01

    A dilemma often encountered in decontamination and decommissioning operations is the lack of choice as to the location where the work is to be performed. Facility siting, laboratory location, and adjacent support areas were often determined based on criteria, which while appropriate at the time, are not always the most conducive to a D ampersand D project. One must learn to adapt and cope with as found conditions. High priority research activities, which cannot be interrupted, may be occurring in adjacent non-radiological facilities in the immediate vicinity where highly contaminated materials must be handled in the course of a D ampersand D operation. The execution of a project within such an environment involves a high level of coordination, cooperation, professionalism and flexibility among the project, the work force and the surrounding occupants. Simply moving occupants from the potentially affected area is not always an option and much consideration must be given in the selection of the D ampersand D methodology to be employed and the processes to be implemented. Determining project boundaries and the ensuring that adjacent occupants are included in the planning/scheduling of specific operations which impact their work area are important in the development of the safety envelope. Such was the case in the recent D ampersand D of 61 gloveboxes contaminated with plutonium and other transuranic nuclides at the Argonne National Laboratory-East site. The gloveboxes, which were used in Department of Energy research and development program activities over the past 30 years, were decontaminated to below transuranic waste criteria, size reduced, packaged and removed from Building 212 by Argonne National Laboratory personnel in conjunction with Nuclear Fuel Services, Inc. with essentially no impact to adjacent occupants

  12. Low impact plutonium glovebox D&D

    Rose, R.W.

    1995-12-31

    A dilemma often encountered in decontamination and decommissioning operations is the lack of choice as to the location where the work is to be performed. Facility siting, laboratory location, and adjacent support areas were often determined based on criteria, which while appropriate at the time, are not always the most conducive to a D&D project. One must learn to adapt and cope with as found conditions. High priority research activities, which cannot be interrupted, may be occurring in adjacent non-radiological facilities in the immediate vicinity where highly contaminated materials must be handled in the course of a D&D operation. The execution of a project within such an environment involves a high level of coordination, cooperation, professionalism and flexibility among the project, the work force and the surrounding occupants. Simply moving occupants from the potentially affected area is not always an option and much consideration must be given in the selection of the D&D methodology to be employed and the processes to be implemented. Determining project boundaries and the ensuring that adjacent occupants are included in the planning/scheduling of specific operations which impact their work area are important in the development of the safety envelope. Such was the case in the recent D&D of 61 gloveboxes contaminated with plutonium and other transuranic nuclides at the Argonne National Laboratory-East site. The gloveboxes, which were used in Department of Energy research and development program activities over the past 30 years, were decontaminated to below transuranic waste criteria, size reduced, packaged and removed from Building 212 by Argonne National Laboratory personnel in conjunction with Nuclear Fuel Services, Inc. with essentially no impact to adjacent occupants.

  13. W-026, transuranic waste (TRU) glovebox acceptance test report

    Leist, K.J.

    1998-01-01

    On July 18, 1997, the Transuranic (TRU) glovebox was tested using glovebox acceptance test procedure 13021A-86. The primary focus of the glovebox acceptance test was to examine control system interlocks, display menus, alarms, and operator messages. Limited mechanical testing involving the drum ports, hoists, drum lifter, compacted drum lifter, drum tipper, transfer car, conveyors, sorting table, lidder/delidder device and the TRU empty drum compactor were also conducted. As of February 25, 1998, 10 of the 102 test exceptions that affect the TRU glovebox remain open. These items will be tracked and closed via the WRAP Master Test Exception Database. As part of Test Exception resolution/closure the responsible individual closing the Test Exception performs a retest of the affected item(s) to ensure the identified deficiency is corrected, and, or to test items not previously available to support testing. Test exceptions are provided as appendices to this report

  14. Seismic analysis of plutonium glovebox by MSC/NASTRAN

    Hirata, Masaru; Ishikawa, Kazuya; Korosawa, Makoto; Fukushima, Susumu; Hoshina, Hirofumi.

    1993-01-01

    Seismic analysis of the structural strength of gloveboxes is important for plutonium confinement evaluation. However, the analytical methods must be developed for evaluating the mutual displacement between the window frame and acrylic resin window panel with regard to plutonium confinement during an earthquake. Therefore, seismic analysis for a standard glovebox in Plutonium Fuel Research Facility at Oarai Research Establishment of JAERI has been conducted by FEM (Finite Element Method) computer code MSC/NASTRAN (MacNeal-Schwendler Corporation NASA Structural Analysis). Modelling of glovebox window frame has been investigated from the results of natural frequency analysis and static analysis. After the acquisition of a suitable model, displacement around the window frame and glovebox structural strength have been evaluated in detail by use of floor response spectrum analysis and time-history (transient response) analysis. (author)

  15. Macro and Micro Remote Viewing of Objects in Sealed Gloveboxes

    Heckendorn, F.M.

    2004-01-01

    The Savannah River Site uses sophisticated glovebox facilities to process and analyze material that is radiologically contaminated or that must be protected from contamination by atmospheric gases. The analysis can be visual, non destructive measurement, or destructive measurement, and allows for the gathering of information that would otherwise not be obtainable. Macro and Micro systems that cover a range of 2X to 400X magnifications with a robust system compatible with the harsh glovebox environment were installed. Remote video inspection systems were developed and deployed in Savannah River Site glovebox facilities that provide high quality or mega-pixel quality remote views, for remote inspections. The specialized video systems that are the subject of this report exhibited specialized field application of remote video/viewing techniques by expanding remote viewing to high and very high quality viewing in gloveboxes. This technological enhancement will allow the gathering of precision information that is otherwise not available

  16. WRAP low level waste (LLW) glovebox acceptance test report

    Leist, K.J.

    1998-01-01

    In June 28, 1997, the Low Level Waste (LLW) glovebox was tested using glovebox acceptance test procedure 13031A-85. The primary focus of the glovebox acceptance test was to examine control system interlocks, display menus, alarms, and operator messages. Limited mechanical testing involving the drum ports, hoists, drum lifter, compacted drum lifter, drum tipper, transfer car, conveyors, lidder/delidder device and the supercompactor were also conducted. As of November 24, 1997, 2 of the 131 test exceptions that affect the LLW glovebox remain open. These items will be tracked and closed via the WRAP Master Test Exception Database. As part of Test Exception resolution/closure the responsible individual closing the Test Exception performs a retest of the affected item(s) to ensure the identified deficiency is corrected, and, or to test items not previously available to support testing. Test Exceptions are provided as appendices to this report

  17. WRAP low level waste (LLW) glovebox acceptance test report

    Leist, K.J.

    1998-02-17

    In June 28, 1997, the Low Level Waste (LLW) glovebox was tested using glovebox acceptance test procedure 13031A-85. The primary focus of the glovebox acceptance test was to examine control system interlocks, display menus, alarms, and operator messages. Limited mechanical testing involving the drum ports, hoists, drum lifter, compacted drum lifter, drum tipper, transfer car, conveyors, lidder/delidder device and the supercompactor were also conducted. As of November 24, 1997, 2 of the 131 test exceptions that affect the LLW glovebox remain open. These items will be tracked and closed via the WRAP Master Test Exception Database. As part of Test Exception resolution/closure the responsible individual closing the Test Exception performs a retest of the affected item(s) to ensure the identified deficiency is corrected, and, or to test items not previously available to support testing. Test Exceptions are provided as appendices to this report.

  18. Issues for reuse of gloveboxes at LANL TA-55

    Cadwallader, L.C.; Pinson, P.A.; Miller, C.F.

    1998-08-01

    This report is a summary of issues that face plutonium glovebox designers and users at the Los Alamos National Laboratory (LANL) Technical Area 55 (TA-55). Characterizing the issues is a step in the task of enhancing the next generation glovebox design to minimize waste streams while providing the other design functions. This report gives an initial assessment of eight important design and operation issues that can benefit from waste minimization.

  19. MINIMIZING GLOVEBOX GLOVE BREACHES, PART IV: CONTROL CHARTS

    Cournoyer, Michael E.; Lee, Michelle B.; Schreiber, Stephen B.

    2007-01-01

    At the Los Alamos National Laboratory (LANL) Plutonium Facility, plutonium. isotopes and other actinides are handled in a glovebox environment. The spread of radiological contamination, and excursions of contaminants into the worker's breathing zone, are minimized and/or prevented through the use of glovebox technology. Evaluating the glovebox configuration, the glovebo gloves are the most vulnerable part of this engineering control. Recognizing this vulnerability, the Glovebox Glove Integrity Program (GGIP) was developed to minimize and/or prevent unplanned openings in the glovebox environment, i.e., glove failures and breaches. In addition, LANL implement the 'Lean Six Sigma (LSS)' program that incorporates the practices of Lean Manufacturing and Six Sigma technologies and tools to effectively improve administrative and engineering controls and work processes. One tool used in LSS is the use of control charts, which is an effective way to characterize data collected from unplanned openings in the glovebox environment. The benefit management receives from using this tool is two-fold. First, control charts signal the absence or presence of systematic variations that result in process instability, in relation to glovebox glove breaches and failures. Second, these graphical representations of process variation detennine whether an improved process is under control. Further, control charts are used to identify statistically significant variations (trends) that can be used in decision making to improve processes. This paper discusses performance indicators assessed by the use control charts, provides examples of control charts, and shows how managers use the results to make decisions. This effort contributes to LANL Continuous Improvement Program by improving the efficiency, cost effectiveness, and formality of glovebox operations.

  20. Ergonomic glovebox workspace layout tool and associated method of use

    Roddy, Shannon Howard

    2018-02-20

    The present invention provides an elongate tool that aides in the placement of objects and machinery within a glovebox, such that the objects and machinery can be safely handled by a user. The tool includes a plurality of visual markings (in English units, metric units, other units, grooves, ridges, varying widths, etc.) that indicate distance from the user within the glovebox, optionally broken into placement preference zones that are color coded, grayscale coded, or the like.

  1. Issues for reuse of gloveboxes at LANL TA-55

    Cadwallader, L.C.; Pinson, P.A.; Miller, C.F.

    1998-08-01

    This report is a summary of issues that face plutonium glovebox designers and users at the Los Alamos National Laboratory (LANL) Technical Area 55 (TA-55). Characterizing the issues is a step in the task of enhancing the next generation glovebox design to minimize waste streams while providing the other design functions. This report gives an initial assessment of eight important design and operation issues that can benefit from waste minimization

  2. Mathematical experimental modeling for muffle furnace drying process of municipal sewage sludge in Beijing and Osaka

    Li, Xinyi; Takaoka, Masaki; Zhu, Fenfen; Oshita, Kazuyuki; Mizuno, Tadao; Morisawa, Shinsuke

    2010-01-01

    Over the past two decades, China has experienced rapid urbanization, which also leads to a lot of environmental problems including those of sewage sludge. As the amount of sewage sludge increases, conventional methods of treatment, such as compost and landfill, are facing the problems of limitations in demands or land. Considering that the demand of constructive materials in China keeps increasing, reusing municipal sewage sludge (MSS) in cement manufactory plant as fuels and raw materials is another practicable way to deal with it. The aim of this study is to describe the process of the heating of sewage sludge under different atmospheres of nitrogen and oxygen, and to find out some relation between the moisture of MSS and the heating time under different surrounding temperature by means of a mathematical model. In this study, we compared 4 kinds of MSS sampled in Beijing and Osaka. First of all, we defined the differences in those fundamental physical properties, such as concentration of various elements, calorific values and so on. Then the macroscopical thermal properties of the sludges were observed by means of thermogravimetric (TG) analysis. Both pyrolysis and combustion of 4 samples of MSS were studied by TG dynamic runs carried out at 10K/m. Visual observation of the heating profiles shows three stages in the heating process, which have been characterized. At last, we focused on batch processing drying tests using muffle furnace under temperature of 200, 250 and 300 degrees Celsius. The volatile matters loss besides moisture during heating process was evaluated and the experimental drying curves were matched with a mathematical model. (author)

  3. Computer modeling for optimal placement of gloveboxes

    Hench, K.W.; Olivas, J.D. [Los Alamos National Lab., NM (United States); Finch, P.R. [New Mexico State Univ., Las Cruces, NM (United States)

    1997-08-01

    Reduction of the nuclear weapons stockpile and the general downsizing of the nuclear weapons complex has presented challenges for Los Alamos. One is to design an optimized fabrication facility to manufacture nuclear weapon primary components (pits) in an environment of intense regulation and shrinking budgets. Historically, the location of gloveboxes in a processing area has been determined without benefit of industrial engineering studies to ascertain the optimal arrangement. The opportunity exists for substantial cost savings and increased process efficiency through careful study and optimization of the proposed layout by constructing a computer model of the fabrication process. This paper presents an integrative two- stage approach to modeling the casting operation for pit fabrication. The first stage uses a mathematical technique for the formulation of the facility layout problem; the solution procedure uses an evolutionary heuristic technique. The best solutions to the layout problem are used as input to the second stage - a computer simulation model that assesses the impact of competing layouts on operational performance. The focus of the simulation model is to determine the layout that minimizes personnel radiation exposures and nuclear material movement, and maximizes the utilization of capacity for finished units.

  4. Computer modeling for optimal placement of gloveboxes

    Hench, K.W.; Olivas, J.D.; Finch, P.R.

    1997-08-01

    Reduction of the nuclear weapons stockpile and the general downsizing of the nuclear weapons complex has presented challenges for Los Alamos. One is to design an optimized fabrication facility to manufacture nuclear weapon primary components (pits) in an environment of intense regulation and shrinking budgets. Historically, the location of gloveboxes in a processing area has been determined without benefit of industrial engineering studies to ascertain the optimal arrangement. The opportunity exists for substantial cost savings and increased process efficiency through careful study and optimization of the proposed layout by constructing a computer model of the fabrication process. This paper presents an integrative two- stage approach to modeling the casting operation for pit fabrication. The first stage uses a mathematical technique for the formulation of the facility layout problem; the solution procedure uses an evolutionary heuristic technique. The best solutions to the layout problem are used as input to the second stage - a computer simulation model that assesses the impact of competing layouts on operational performance. The focus of the simulation model is to determine the layout that minimizes personnel radiation exposures and nuclear material movement, and maximizes the utilization of capacity for finished units

  5. Determining the Radiation Damage Effect on Glovebox Glove Material

    Cournoyer, M.E.; Balkey, J.J.; Andrade, R.M.

    2005-01-01

    The Nuclear Material Technology (NMT) Division has the largest inventory of glove box gloves at Los Alamos National Laboratory. The minimization of unplanned breaches in the glovebox, e.g., glove failures, is a primary concern in the daily operations in NMT Division facilities, including the Plutonium Facility (PF-4) at TA-55 and Chemical and Metallurgy Research (CMR) Facility. Glovebox gloves in these facilities are exposed to elevated temperatures and exceptionally aggressive radiation environments (particulate 239 Pu and 238 Pu). Predictive models are needed to estimate glovebox glove service lifetimes, i.e. change-out intervals. Towards this aim aging studies have been initiated that correlate changes in mechanical (physical) properties with degradation chemistry. This present work derives glovebox glove change intervals based on previously reported mechanical data of thermally aged hypalon glove samples. Specifications for 30 mil tri-layered hypalon/lead glovebox gloves (TLH) and 15 mil hypalon gloves (HYP) have already been established. The relevant mechanical properties are shown on Table 1. Tensile strength is defined as the maximum load applied in breaking a tensile test piece divided by the original cross-sectional area of the test piece (Also termed maximum stress and ultimate tensile stress). Ultimate elongation is the elongation at time of rupture (Also termed maximum strain). The specification for the tensile test and ultimate elongation are the minimum acceptable values. In addition, the ultimate elongation must not vary 20% from the original value. In order to establish a service lifetimes for glovebox gloves in a thermal environment, the mechanical properties of glovebox glove materials were studied.

  6. Determining the Radiation Damage Effect on Glovebox Glove Material.

    Cournoyer, M. E. (Michael E.); Balkey, J. J. (James J.); Andrade, R.M. (Rose M.)

    2005-01-01

    The Nuclear Material Technology (NMT) Division has the largest inventory of glove box gloves at Los Alamos National Laboratory. The minimization of unplanned breaches in the glovebox, e.g., glove failures, is a primary concern in the daily operations in NMT Division facilities, including the Plutonium Facility (PF-4) at TA-55 and Chemical and Metallurgy Research (CMR) Facility. Glovebox gloves in these facilities are exposed to elevated temperatures and exceptionally aggressive radiation environments (particulate {sup 239}Pu and {sup 238}Pu). Predictive models are needed to estimate glovebox glove service lifetimes, i.e. change-out intervals. Towards this aim aging studies have been initiated that correlate changes in mechanical (physical) properties with degradation chemistry. This present work derives glovebox glove change intervals based on previously reported mechanical data of thermally aged hypalon glove samples. Specifications for 30 mil tri-layered hypalon/lead glovebox gloves (TLH) and 15 mil hypalon gloves (HYP) have already been established. The relevant mechanical properties are shown on Table 1. Tensile strength is defined as the maximum load applied in breaking a tensile test piece divided by the original cross-sectional area of the test piece (Also termed maximum stress and ultimate tensile stress). Ultimate elongation is the elongation at time of rupture (Also termed maximum strain). The specification for the tensile test and ultimate elongation are the minimum acceptable values. In addition, the ultimate elongation must not vary 20% from the original value. In order to establish a service lifetimes for glovebox gloves in a thermal environment, the mechanical properties of glovebox glove materials were studied.

  7. Develop and Manufacture an Ergonomically Sound Glovebox Glove Report

    Lawton, Cindy M. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2017-10-18

    Ergonomic injury and radiation exposure are two safety concerns for the Plutonium Facility at Los Alamos National Laboratory (LANL). This facility employs the largest number of gloveboxes (GB) at LANL with approximately 6000 gloves installed. The current GB glove design dates back to the 1960’s and is not based on true hand anatomy, revealing several issues: short fingers, inappropriate length from the wrist to finger webbing, nonexistent joint angles and incorrect thumb placement. These design flaws are directly related to elbow (lateral epicondylitis) and thumb (DeQuervain’s tenosynovitis) injuries. The current design also contributes to increased wear on the glove, causing unplanned glove openings (failures) which places workers at risk of exposure. An improved glovebox glove design has three significant benefits: 1) it will reduce the risk of injury, 2) it will improve comfort and productivity, and 3) it will reduce the risk of a glovebox failures. The combination of these three benefits has estimated savings of several million dollars. The new glove design incorporated the varied physical attributes of workers ranging from the 5th percentile female to the 95th percentile male. Anthropometric hand dimensions along with current GB worker dimensions were used to develop the most comprehensive design specifications for the new glove. Collaboration with orthopedic hand surgeons also provided major contributtions to the design. The new glovebox glove was developed and manufactured incorporating over forty dimensions producing the most comprehensive ergonomically sound design. The new design received a LANL patent (patent attorney docket No: LANS 36USD1 “Protective Glove”, one of 20 highest patents awarded by the Richard P. Feynman Center for Innovation. The glove dimensions were inputed into a solid works model which was used to produce molds. The molds were then shipped to a glove manufacturer for production of the new glovebox gloves. The new

  8. Decrease the Number of Glovebox Glove Breaches and Failures

    Hurtle, Jackie C. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2013-12-24

    Los Alamos National Laboratory (LANL) is committed to the protection of the workers, public, and environment while performing work and uses gloveboxes as engineered controls to protect workers from exposure to hazardous materials while performing plutonium operations. Glovebox gloves are a weak link in the engineered controls and are a major cause of radiation contamination events which can result in potential worker exposure and localized contamination making operational areas off-limits and putting programmatic work on hold. Each day of lost opportunity at Technical Area (TA) 55, Plutonium Facility (PF) 4 is estimated at $1.36 million. Between July 2011 and June 2013, TA-55-PF-4 had 65 glovebox glove breaches and failures with an average of 2.7 per month. The glovebox work follows the five step safety process promoted at LANL with a decision diamond interjected for whether or not a glove breach or failure event occurred in the course of performing glovebox work. In the event that no glove breach or failure is detected, there is an additional decision for whether or not contamination is detected. In the event that contamination is detected, the possibility for a glove breach or failure event is revisited.

  9. Follow-On Vapor Containment Tests of the Rapid Response System Glovebox

    Arca, Victor

    1997-01-01

    ...) glovebox in April 1996. The tests were conducted by generating a cloud of the simulant methyl salicylate inside the glovebox and measuring the concentration of any simulant that permeated to the operator workspace...

  10. Comparison of deliverable and exhaustible pressurized air flow rates in laboratory gloveboxes

    Compton, J.A.

    1994-01-01

    Calculations were performed to estimate the maximum credible flow rates of pressurized air into Plutonium Process Support Laboratories gloveboxes. Classical equations for compressible fluids were used to estimate the flow rates. The calculated maxima were compared to another's estimates of glovebox exhaust flow rates and corresponding glovebox internal pressures. No credible pressurized air flow rate will pressurize a glovebox beyond normal operating limits. Unrestricted use of the pressurized air supply is recommended

  11. Rotator Cuff Strength Ratio and Injury in Glovebox Workers

    Weaver, Amelia M. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2014-01-30

    Rotator cuff integrity is critical to shoulder health. Due to the high workload imposed upon the shoulder while working in an industrial glovebox, this study investigated the strength ratio of the rotator cuff muscles in glovebox workers and compared this ratio to the healthy norm. Descriptive statistics were collected using a short questionnaire. Handheld dynamometry was used to quantify the ratio of forces produced in the motions of shoulder internal and external rotation. Results showed this population to have shoulder strength ratios that were significantly different from the healthy norm. The deviation from the normal ratio demonstrates the need for solutions designed to reduce the workload on the rotator cuff musculature of glovebox workers in order to improve health and safety. Assessment of strength ratios can be used to screen for risk of symptom development.

  12. Seismic analysis of safety class 1 incinerator glovebox in building 232-Z 200 W Area

    Ocoma, E.C.

    1994-09-01

    This report documents the seismic evaluation for the existing safety class 1 incinerator glovebox in 232Z Building. The glovebox is no longer in use and most of the internal mechanical equipment have been removed. However, the insulation firebricks are still in the glovebox for proper disposal

  13. Organic Contamination Baseline Study on NASA JSC Astromaterial Curation Gloveboxes

    Calaway, Michael J.; Allton, J. H.; Allen, C. C.; Burkett, P. J.

    2013-01-01

    Future planned sample return missions to carbon-rich asteroids and Mars in the next two decades will require strict handling and curation protocols as well as new procedures for reducing organic contamination. After the Apollo program, astromaterial collections have mainly been concerned with inorganic contamination [1-4]. However, future isolation containment systems for astromaterials, possibly nitrogen enriched gloveboxes, must be able to reduce organic and inorganic cross-contamination. In 2012, a baseline study was orchestrated to establish the current state of organic cleanliness in gloveboxes used by NASA JSC astromaterials curation labs that could be used as a benchmark for future mission designs.

  14. Applications of LabVIEW programming in a glovebox environment

    Evans, M.E.; Peralta, G.; Gray, D.

    1995-01-01

    When dealing with neutron radiation one of the keys to reducing worker exposure is to have as much distance and shielding between the radiation and the radiation worker as possible. Using a PC to control a process from a remote location allows the distance between the radiation worker and the radiation source to be increase. Increasing the distance at which radiation worker can control a process allows more shielding to be placed around the glovebox. There are many commercial packages that allow controlling remote processes with a PC. This paper shows how flexible the LabVIEW Graphical Programming Language can be in implementing the remote control of glovebox process

  15. Determination of an Ergonomically Sound Glovebox Glove Port Center Line

    Christman, Marissa St John [Los Alamos National Laboratory

    2016-11-30

    Determine an ergonomic glovebox glove port center line location which will be used for standardization in new designs, thus allowing for predictable human work performance, reduced worker exposure to radiation and musculoskeletal injury risks, and improved worker comfort, efficiency, health, and safety.

  16. DISPOSITION PATHS FOR ROCKY FLATS GLOVEBOXES: EVALUATING OPTIONS

    Lobdell, D.; Geimer, R.; Larsen, P.; Loveland, K.

    2003-01-01

    The Kaiser-Hill Company, LLC has the responsibility for closure activities at the Rocky Flats Environmental Technology Site (RFETS). One of the challenges faced for closure is the disposition of radiologically contaminated gloveboxes. Evaluation of the disposition options for gloveboxes included a detailed analysis of available treatment capabilities, disposal facilities, and lifecycle costs. The Kaiser-Hill Company, LLC followed several processes in determining how the gloveboxes would be managed for disposition. Currently, multiple disposition paths have been chosen to accommodate the needs of the varying styles and conditions of the gloveboxes, meet the needs of the decommissioning team, and to best manage lifecycle costs. Several challenges associated with developing a disposition path that addresses both the radiological and RCRA concerns as well as offering the most cost-effective solution were encountered. These challenges included meeting the radiological waste acceptance criteria of available disposal facilities, making a RCRA determination, evaluating treatment options and costs, addressing void requirements associated with disposal, and identifying packaging and transportation options. The varying disposal facility requirements affected disposition choices. Facility conditions that impacted decisions included radiological and chemical waste acceptance criteria, physical requirements, and measurement for payment options. The facility requirements also impacted onsite activities including management strategies, decontamination activities, and life-cycle cost

  17. Constant depression fan system a novel glovebox ventilation system

    Milliner, W.V.

    1995-01-01

    In a conventional glovebox ventilation system the depression within the glovebox under normal operation is controlled by instrumentation. In the event of a breach the pressure within the box rises to atmospheric pressure, this pressure rise is detected by instrumentation which in turn operates a quick opening damper in a high depression extract to achieve a 1 metre/sec (200 fpm) inflow through the breach, which can take up to 2 seconds to establish. This system, although widely used, suffers from two distinct drawbacks: It takes a finite time to achieve the containment velocity of 1 metre/sec. It relies upon instrumentation to achieve its objectives. A new glovebox ventilation system has been developed by AWE to overcome these drawbacks. This is the Constant Depression Fan System (CDFS) which is based on an extract fan with a flat characteristic. This achieves all the requirements for the ventilation of gloveboxes and has the advantages that: It has only one moving part - the extract fan. It requires NO INSTRUMENTATION to achieve its objectives. It achieves the containment velocity of 1 metre/sec in the shortest possible time - approximately 0.2 seconds - and tests have shown that containment is maintained under breach conditions. Thus the CDFS is SAFER, SIMPLER and MORE RELIABLE

  18. Chloride-catalyzed corrosion of plutonium in glovebox atmospheres

    Burgess, M.; Haschke, J.M.; Allen, T.H.; Morales, L.A.; Jarboe, D.M.; Puglisi, C.V.

    1998-04-01

    Characterization of glovebox atmospheres and the black reaction product formed on plutonium surfaces shows that the abnormally rapid corrosion of components in the fabrication line is consistent with a complex salt-catalyzed reaction involving gaseous hydrogen chloride (HCl) and water. Analytical data verify that chlorocarbon and HCl vapors are presented in stagnant glovebox atmospheres. Hydrogen chloride concentrations approach 7 ppm at some locations in the glovebox line. The black corrosion product is identified as plutonium monoxide monohydride (PuOH), a product formed by hydrolysis of plutonium in liquid water and salt solutions at room temperature. Plutonium trichloride (PuCl 3 ) produced by reaction of HCl at the metal surface is deliquescent and apparently forms a highly concentrated salt solution by absorbing moisture from the glovebox atmosphere. Rapid corrosion is attributed to the ensuing salt-catalyzed reaction between plutonium and water. Experimental results are discussed, possible involvement of hydrogen fluoride (HF) is examined, and methods of corrective action are presented in this report

  19. Glovebox characterization and barrier integrity testing using fluorescent powder

    Wahlquist, D.R.

    1996-01-01

    This paper presents a method for characterizing the spread of contamination and testing the barrier integrity of a new glovebox during material transfer operations and glove change-outs using fluorescent powder. Argonne National Laboratory-West has performed this test on several new gloveboxes prior to putting them into service. The test is performed after the glovebox has been leak tested and all systems have been verified to be operational. The purpose of the test is to show that bag-in/bag-out operations and glove change-outs can be accomplished without spreading the actual contaminated material to non-contaminated areas. The characterization test also provides information as to where contamination might be expected to build-up during actual operations. The fluorescent powder is used because it is easily detectable using an ultra-violet light and disperses in a similar fashion to radioactive material. The characterization and barrier integrity test of a glovebox using fluorescent powder provides a visual method of determining areas of potential contamination accumulation and helps evaluate the ability to perform clean transfer operations and glove change-outs

  20. Determination of an Ergonomically Sound Glovebox Glove Port Center Line

    Christman, Marissa St; Land, Whitney Morgan

    2016-01-01

    Determine an ergonomic glovebox glove port center line location which will be used for standardization in new designs, thus allowing for predictable human work performance, reduced worker exposure to radiation and musculoskeletal injury risks, and improved worker comfort, efficiency, health, and safety.

  1. Constant depression fan system a novel glovebox ventilation system

    Milliner, W.V. [AME plc., Aldermaston (United Kingdom)

    1995-02-01

    In a conventional glovebox ventilation system the depression within the glovebox under normal operation is controlled by instrumentation. In the event of a breach the pressure within the box rises to atmospheric pressure, this pressure rise is detected by instrumentation which in turn operates a quick opening damper in a high depression extract to achieve a 1 metre/sec (200 fpm) inflow through the breach, which can take up to 2 seconds to establish. This system, although widely used, suffers from two distinct drawbacks: It takes a finite time to achieve the containment velocity of 1 metre/sec. It relies upon instrumentation to achieve its objectives. A new glovebox ventilation system has been developed by AWE to overcome these drawbacks. This is the Constant Depression Fan System (CDFS) which is based on an extract fan with a flat characteristic. This achieves all the requirements for the ventilation of gloveboxes and has the advantages that: It has only one moving part - the extract fan. It requires NO INSTRUMENTATION to achieve its objectives. It achieves the containment velocity of 1 metre/sec in the shortest possible time - approximately 0.2 seconds - and tests have shown that containment is maintained under breach conditions. Thus the CDFS is SAFER, SIMPLER and MORE RELIABLE.

  2. Tritium stripping in a nitrogen glovebox using SAES St 198

    Klein, J.E.; Wermer, J.R.

    1994-01-01

    SAES metal getter material St 198 was chosen for glovebox stripper tests to evaluate its effectiveness of removing tritium from a nitrogen atmosphere. The St 198 material is unique from a number of other metal hydride-based getter materials in that it is relatively inert to nitrogen and can thus be used in nitrogen glovebox atmospheres. Six tritium stripper experiments which mock-up the use of a SAES St 198 stripper bed for a full-scale (10,500 liter) nitrogen glovebox have been completed. Experiments consisted of a release of small quantity of protium/deuterium spiked with tritium which were scaled to simulate tritium releases of 0.1 g., 1.0 g., and 10 g. into the glovebox. The tritium spike allows detection using tritium ion chambers. The St 198 stripper system produced a reduction in tritium activity of approximately two orders of magnitude in 24 hours (6--8 atmosphere turn-overs) of stripper operation

  3. Dexterity test data contribute to proper glovebox over-glove use

    Cournoyer, Michael E.; Lawton, Cindy M.; Castro, Armanda M.; Costigan, Stephen A.; Apel, D.M.; Neal, G.E.; Castro, J.M.; Michelotti, R.A.

    2010-01-01

    Programmatic operations at the Los Alamos National Laboratory Plutonium Facility (TA-55) involve working with various amounts of plutonium and other highly toxic, alpha-emitting materials. The spread of radiological contamination on surfaces, airborne contamination, and excursions of contaminants into the operator's breathing zone are prevented through the use of a variety of gloveboxes (the glovebox, coupled with an adequate negative pressure gradient, provides primary confinement). The glovebox gloves are the weakest part of this engineering control. The Glovebox Glove Integrity Program, which controls glovebox gloves from procurement to disposal at TA-55, manages this vulnerability. A key element of this program is to consider measures that lower the overall risk of glovebox operations. Proper selection of over-gloves is one of these measures. Line management owning glovebox processes have the responsibility to approve the appropriate personal protective equipment/glovebox glove/over-glove combination. As low as reasonably achievable (ALARA) considerations to prevent unplanned glovebox glove openings must be balanced with glove durability and worker dexterity, both of which affect the final overall risk to the worker. In this study, the causes of unplanned glovebox glove openings, the benefits of over-glove features, the effect of over-gloves on task performance using standard dexterity tests, the pollution prevention benefits, and the recommended over-gloves for a task are presented.

  4. Examining the efficiency of muffle furnance-induced alkaline hydrolysis in determining the titanium content of environmental samples containing engineered titanium dioxide particles

    A novel muffle furnace (MF)-based potassium hydroxide (KOH) fusion digestion technique was developed and its comparative digestion and dissolution efficacy for different titanium dioxide nanoparticles (TiO2-NPs)/environmental matrices was evaluated. Digestion of different enviro...

  5. Microgravity Science Glovebox Aboard the International Space Station

    2003-01-01

    In the Destiny laboratory aboard the International Space Station (ISS), European Space Agency (ESA) astronaut Pedro Duque of Spain is seen working at the Microgravity Science Glovebox (MSG). He is working with the PROMISS experiment, which will investigate the growth processes of proteins during weightless conditions. The PROMISS is one of the Cervantes program of tests (consisting of 20 commercial experiments). The MSG is managed by NASA's Marshall Space Flight Center (MSFC).

  6. Peak pressures from hydrogen deflagrations in the PFP thermal stabilization glovebox

    Van Keuren, J.C.

    1998-01-01

    This document describes the calculations of the peak pressures due to hydrogen deflagrations in the glovebox used for thermal stabilization (glovebox HC-21A) in PFP. Two calculations were performed. The first considered the burning of hydrogen released from a 7 inch Pu can in the Inert Atmosphere Confinement (IAC) section of the glovebox. The peak pressure increase was 12400 Pa (1.8 psi). The second calculation considered burning of the hydrogen from 25 g of plutonium hydride in the airlock leading to the main portion of the glovebox. Since the glovebox door exposes most of the airlock when open, the deflagration was assumed to pressurize the entire glovebox. The peak pressure increase was 3860 Pa (0.56 psi)

  7. Standard guide for design criteria for plutonium gloveboxes

    American Society for Testing and Materials. Philadelphia

    2009-01-01

    1.1 This guide defines criteria for the design of glovebox systems to be used for the handling of plutonium in any chemical or physical form or isotopic composition or when mixed with other elements or compounds. Not included in the criteria are systems auxiliary to the glovebox systems such as utilities, ventilation, alarm, and waste disposal. Also not addressed are hot cells or open-face hoods. The scope of this guide excludes specific license requirements relating to provisions for criticality prevention, hazards control, safeguards, packaging, and material handling. Observance of this guide does not relieve the user of the obligation to conform to all federal, state, and local regulations for design and construction of glovebox systems. 1.2 The values stated in SI units are to be regarded as the standard. The values given in parentheses are for information only. 1.3 This standard does not purport to address all of the safety problems, if any, associated with its use. It is the responsibility of the user...

  8. Glovebox enclosed dc plasma source for the determination of metals in plutonium

    Morris, W.F.

    1986-01-01

    The direct current plasma source of a Beckman Spectraspan IIIB emission spectrometer was enclosed in a glovebox at Lawrence Livermore National Laboratory in December 1982. Since that time, the system has been used for the routine determination of alloy and impurity metals in plutonium. This paper presents the systematic steps involved in developing the glovebox and gives information regarding performance of the plasma in the glovebox and the effectiveness of containment of plutonium. 8 refs., 9 figs., 3 tabs

  9. Glovebox glove change program at Technical Area 55, Los Alamos National Laboratory

    Olivas, J.D.; Burkett, B.O.; Weier, D.R.

    1992-01-01

    A formal glovebox glove change program is planned for the the gloveboxes in technical area 55 at the Los Alamos National laboratory. The program will increase worker safety by reducing the chance of having worn out gloves in service. The Los Alamos program is based on a similar successful program at the Rocky Flats Plant in Golden, Colorado. Glove change frequencies at Rocky Flats were determined statistically, and are based on environmental factors the glovebox gloves are subjected to

  10. The Virtual Glovebox (VGX): An Immersive Simulation System for Training Astronauts to Perform Glovebox Experiments in Space

    Smith, Jeffrey D.; Dalton, Bonnie (Technical Monitor)

    2002-01-01

    The era of the International Space Station (ISS) has finally arrived, providing researchers on Earth a unique opportunity to study long-term effects of weightlessness and the space environment on structures, materials and living systems. Many of the physical, biological and material science experiments planned for ISS will require significant input and expertise from astronauts who must conduct the research, follow complicated assay procedures and collect data and samples in space. Containment is essential for Much of this work, both to protect astronauts from potentially harmful biological, chemical or material elements in the experiments as well as to protect the experiments from contamination by air-born particles In the Space Station environment. When astronauts must open the hardware containing such experiments, glovebox facilities provide the necessary barrier between astronaut and experiment. On Earth, astronauts are laced with the demanding task of preparing for the many glovebox experiments they will perform in space. Only a short time can be devoted to training for each experimental task and gl ovebox research only accounts for a small portion of overall training and mission objectives on any particular ISS mission. The quality of the research also must remain very high, requiring very detailed experience and knowledge of instrumentation, anatomy and specific scientific objectives for those who will conduct the research. This unique set of needs faced by NASA has stemmed the development of a new computer simulation tool, the Virtual Glovebox (VGB), which is designed to provide astronaut crews and support personnel with a means to quickly and accurately prepare and train for glovebox experiments in space.

  11. Survey of Technologies to Support Reuse of Gloveboxes at LANL TA-55

    Cadwallader, L.C.; Pinson, P.A.

    1998-01-01

    This report is a summary of ideas and technologies available to support reuse of plutonium gloveboxes at the Los Alamos National Laboratory (LANL) Technical Area 55 (TA-55). This work is the second of two deliverables in the task to enhance glovebox design for longevity and reusability at TA-55. The report presents several design change suggestions to be evaluated for their feasibility by LANL glovebox designers. The report also describes some techniques to be evaluated by LANL for their usefulness in reducing glovebox waste

  12. HB-Line Dissolution of Glovebox Floor Sweepings

    Gray, J.H.

    1998-02-01

    Two candidate flowsheets for dissolving glovebox floor sweepings in the HB-Line Phase I geometrically favorable dissolver have been developed.Dissolving conditions tested and modified during the laboratory program were based on the current processing scheme for dissolving high-fired Pu-238 oxide in HB-Line. Subsequent adjustments made to the HB-Line flowsheet reflected differences in the dissolution behavior between high-fired Pu-238 oxide and the MgO sand/PuF 4 /PuO 2 mixture in glovebox floor sweepings. Although both candidate flowsheets involved two separate dissolving steps and resulted incomplete dissolution of all solids, the one selected for use in HB-Line will require fewer processing operations and resembles the initial flowsheet proposed for dissolving sand, slag, and crucible material in F-Canyon dissolvers. Complete dissolution of glovebox floor sweepings was accomplished in the laboratory by initially dissolving between 55 and 65 degree in a 14 molar nitric acid solution. Under these conditions, partial dissolution of PuF 4 and complete dissolution of PuO 2 and MgO sand were achieved in less than one hour. The presence of free fluoride in solution,uncomplexed by aluminum, was necessary for complete dissolution of the PuO 2 .The remaining PuF 4 dissolved following addition of aluminum nitrate nonahydrate (ANN) to complex the fluoride and heating between 75 and 85 degree C for an additional hour. Precipitation of magnesium and/or aluminum nitrates could occur before, during, and after transfer of product solutions. Both dilution and/or product solution temperature controls may be necessary to prevent precipitation of these salts. Corrosion of the dissolver should not be an issue during these dissolving operations. Corrosion is minimized when dissolving at 55-65 degree C for one to three hours at a maximum uncomplexed free fluoride concentration of 0.07 molar and by dissolving at 75-85 degree C at a one to one aluminum to fluoride mole ratio for another

  13. Design/build/mockup of the Waste Isolation Pilot Plant gas generation experiment glovebox

    Rosenberg, K.E.; Benjamin, W.W.; Knight, C.J.; Michelbacher, J.A.

    1996-01-01

    A glovebox was designed, fabricated, and mocked-up for the WIPP Gas Generation Experiments (GGE) being conducted at ANL-W. GGE will determine the gas generation rates from materials in contact handled transuranic waste at likely long term repository temperature and pressure conditions. Since the customer's schedule did not permit time for performing R ampersand D of the support systems, designing the glovebox, and fabricating the glovebox in a serial fashion, a parallel approach was undertaken. As R ampersand D of the sampling system and other support systems was initiated, a specification was written concurrently for contracting a manufacturer to design and build the glovebox and support equipment. The contractor understood that the R ampersand D being performed at ANL-W would add additional functional requirements to the glovebox design. Initially, the contractor had sufficient information to design the glovebox shell. Once the shell design was approved, ANL-W built a full scale mockup of the shell out of plywood and metal framing; support systems were mocked up and resultant information was forwarded to the glovebox contractor to incorporate into the design. This approach resulted in a glovebox being delivered to ANL-W on schedule and within budget

  14. Process and device for extinguishing fires inside gloveboxes

    Lopez, P

    1975-01-09

    The present invention relates to a process of extinguishing all types of fire inside gloveboxes. Said process prevents the inner part of the box to communicate with the room atmosphere: the glove that is the nearest to the hearth of fire is perforated with an edged tip mounted on the outlet of the extinguisher and the product contained inside said extinguisher is released until the fire extinction is achieved. A device for operating said process consists in an edged tubular tip, the end of which is bevelled and in means of dispersion and of connection to an extinguisher at the other end.

  15. Operational considerations for the Space Station Life Science Glovebox

    Rasmussen, Daryl N.; Bosley, John J.; Vogelsong, Kristofer; Schnepp, Tery A.; Phillips, Robert W.

    1988-01-01

    The U.S. Laboratory (USL) module on Space Station will house a biological research facility for multidisciplinary research using living plant and animal specimens. Environmentally closed chambers isolate the specimen habitats, but specimens must be removed from these chambers during research procedures as well as while the chambers are being cleaned. An enclosed, sealed Life Science Glovebox (LSG) is the only locale in the USL where specimens can be accessed by crew members. This paper discusses the key science, engineering and operational considerations and constraints involving the LSG, such as bioisolation, accessibility, and functional versatility.

  16. Virtual Glovebox (VGX) Aids Astronauts in Pre-Flight Training

    2003-01-01

    NASA's Virtual Glovebox (VGX) was developed to allow astronauts on Earth to train for complex biology research tasks in space. The astronauts may reach into the virtual environment, naturally manipulating specimens, tools, equipment, and accessories in a simulated microgravity environment as they would do in space. Such virtual reality technology also provides engineers and space operations staff with rapid prototyping, planning, and human performance modeling capabilities. Other Earth based applications being explored for this technology include biomedical procedural training and training for disarming bio-terrorism weapons.

  17. Light transmission and air used for inspection of glovebox gloves

    Castro, Julio M.; Steckle, Warren P. Jr.; Macdonald, John M.

    2002-01-01

    Various materials used for manufacturing the glovebox gloves are translucent material such as hypalon, rubbers, and neoprene. This means that visible light can be transmitted through the inside of the material. Performing this test can help to increase visualization of the integrity of the glove. Certain flaws such as pockmarks, foreign material, pinholes, and scratches could be detected with increased accuracy. An analysis was conducted of the glovebox gloves obscure polymer material using a inspection light table. The fixture is equipped with a central light supply and small air pump to inflate the glove and test for leak and stability. A glove is affixed to the fixture for 360-degree inspection. Certain inspection processes can be performed: (1) Inspection for pockmarks and thin areas within the gloves; (2) Observation of foreign material within the polymer matrix; and (3) Measurements could be taken for gloves thickness using light measurements. This process could help reduce eyestrain when examining gloves and making a judgment call on the size of material thickness in some critical areas. Critical areas are fingertips and crotch of fingers.

  18. Dexterity tests data contribute to reduction in leaded glovebox gloves use

    Cournoyer, Michael E [Los Alamos National Laboratory; Lawton, Cindy M [Los Alamos National Laboratory; Castro, Amanda M [Los Alamos National Laboratory

    2008-01-01

    Programmatic operations at the Los Alamos National Laboratory Plutonium Facility (TA-55) involve working with various amounts of plutonium and other highly toxic, alphaemitting materials. The spread of radiological contamination on surfaces and airborne contamination and excursions of contaminants into the operator's breathing zone are prevented through the use of a variety of gloveboxes. Through an integrated approach, controls have been developed and implemented through an efficient Glovebox Glove Integrity Program (GGJP). A key element of this program is to consider measures that lower the overall risk of glovebox operations. Line management owning glovebox processes through this program make decisions on which type of glovebox gloves (the weakest component of this safety significant system) would perform in these aggressive environments. As Low As Reasonably Achievable (ALARA) considerations must be balanced with glove durability and worker dexterity, both of which affect the final overall risk of the operation. In the past, lead-loaded (leaded) glovebox gloves made from Hypalon(reg.) had been the workhorse of programmatic operations at TA-55. Replacing leaded gloves with unleaded gloves for certain operations would lower the overall risk as well as reduced the amount of mixed TRU waste. This effort contributes to Los Alamos National Laboratory Continuous Improvement Program by improving the efficiency, cost effectiveness, and formality of glovebox operations. In the following report, the pros and cons of wearing leaded glovebox gloves, the effect of leaded gloves versus unleaded gloves on task performance using standard dexterity tests, the justification for switching from leaded to unleaded gloves, and pollution prevention benefits of this dramatic change in the glovebox system are presented.

  19. Requalification of the 235-F Metallograph Facility gloveboxes for use in the 773-A plutonium immobilization demonstration

    Hinds, S.S.; Hidlay, J.

    1997-01-01

    A concern has been identified regarding the viability of redesigning and requalifying existing glovebox lines for use as glovebox lines integral to future mission activities in the 773-A laboratory building at the Savannah River Site (SRS). The Bechtel Savannah River Inc. (BSRI) design engineering team has been requested to perform an evaluation which would investigate the reuse of these existing gloveboxes versus the procurement of completely new glovebox systems. The existing glovebox lines were manufactured for the Plutonium (Pu) Metallograph Facility, Project 3253, located in building 235-F at SRS. These gloveboxes were designed as independent, fully functional Pu 'metal' and Pu 'oxide' processing glovebox systems for this facility. These gloveboxes, although fully installed, have never processed radioactive material. The proposed use for these gloveboxes are: (1) to utilize the Pu 'metal' glovebox system for the primary containment associated with the Pre-Processing/Re-Processing Laboratory for obtaining radioactive glass compound viscometer analysis and (2) to utilize the Pu 'oxide' glovebox system for primary containment associated with the Pu 'Can in Can' Demonstration for proof of principle testing specific to long term Pu immobilization and storage technology. This report presents objective evidence that supports the engineering judgment indicating the existing gloveboxes can be requalified for the proposed uses indicated above. SRS has the ability to duplicate the test parameters, with site forces, that will meet or exceed the identical acceptance criteria established to qualify the existing gloveboxes. The qualification effort will be a documented procedure using the leak test criteria characteristic of the original glovebox purchase. Two equivalent tests will be performed, one for post modification leak test acceptance and one for post installation leak test acceptance. (Abstract Truncated)

  20. Object-oriented process dose modeling for glovebox operations

    Boerigter, S.T.; Fasel, J.H.; Kornreich, D.E.

    1999-01-01

    The Plutonium Facility at Los Alamos National Laboratory supports several defense and nondefense-related missions for the country by performing fabrication, surveillance, and research and development for materials and components that contain plutonium. Most operations occur in rooms with one or more arrays of gloveboxes connected to each other via trolley gloveboxes. Minimizing the effective dose equivalent (EDE) is a growing concern as a result of steadily declining allowable dose limits being imposed and a growing general awareness of safety in the workplace. In general, the authors discriminate three components of a worker's total EDE: the primary EDE, the secondary EDE, and background EDE. A particular background source of interest is the nuclear materials vault. The distinction between sources inside and outside of a particular room is arbitrary with the underlying assumption that building walls and floors provide significant shielding to justify including sources in other rooms in the background category. Los Alamos has developed the Process Modeling System (ProMoS) primarily for performing process analyses of nuclear operations. ProMoS is an object-oriented, discrete-event simulation package that has been used to analyze operations at Los Alamos and proposed facilities such as the new fabrication facilities for the Complex-21 effort. In the past, crude estimates of the process dose (the EDE received when a particular process occurred), room dose (the EDE received when a particular process occurred in a given room), and facility dose (the EDE received when a particular process occurred in the facility) were used to obtain an integrated EDE for a given process. Modifications to the ProMoS package were made to utilize secondary dose information to use dose modeling to enhance the process modeling efforts

  1. Device Assembly Facility (DAF) Glovebox Radioactive Waste Characterization

    Dominick, J L

    2001-01-01

    The Device Assembly Facility (DAF) at the Nevada Test Site (NTS) provides programmatic support to the Joint Actinide Shock Physics Experimental Research (JASPER) Facility in the form of target assembly. The target assembly activities are performed in a glovebox at DAF and include Special Nuclear Material (SNM). Currently, only activities with transuranic SNM are anticipated. Preliminary discussions with facility personnel indicate that primarily two distributions of SNM will be used: Weapons Grade Plutonium (WG-Pu), and Pu-238 enhanced WG-Pu. Nominal radionuclide distributions for the two material types are included in attachment 1. Wastes generated inside glove boxes is expected to be Transuranic (TRU) Waste which will eventually be disposed of at the Waste Isolation Pilot Plant (WIPP). Wastes generated in the Radioactive Material Area (RMA), outside of the glove box is presumed to be low level waste (LLW) which is destined for disposal at the NTS. The process knowledge quantification methods identified herein may be applied to waste generated anywhere within or around the DAF and possibly JASPER as long as the fundamental waste stream boundaries are adhered to as outlined below. The method is suitable for quantification of waste which can be directly surveyed with the Blue Alpha meter or swiped. An additional quantification methodology which requires the use of a high resolution gamma spectroscopy unit is also included and relies on the predetermined radionuclide distribution and utilizes scaling to measured nuclides for quantification

  2. Design improvements for gloveboxes used [in] {sup 238}PuO{sub 2} process operations

    George, T.G. [Los Alamos National Lab., NM (United States). Nuclear Materials Technology Div.

    1997-09-01

    {sup 238}PuO{sub 2} process operations are housed in a complex of 76 gloveboxes and introductory hoods connected by means of an overhead trolley housed in a tunnel. Because a significant number of the gloveboxes used for {sup 238}PuO{sub 2} processing were installed before the original startup of the facility in 1978, they have been in service for nearly 20 years. During a recent heat source production campaign, numerous contamination releases in the {sup 238}PuO{sub 2} processing area were traced to degraded elastomer gaskets used for glovebox connections, and attachment of feed-throughs, service panels, and windows. Evaluation of the degraded gaskets revealed that a combination of radiolytic degradation related to the high specific activity of {sup 238}Pu, and extended service at high altitude in a low (to extremely low) humidity environment had resulted in accelerated gasket aging. However, it was also apparent that gasket design was the most important factor in actual contamination release. All of the contamination releases that were traced to degraded gaskets occurred in variations of a design that used a spline to expand an elastomeric gasket into the space between a connecting flange, window, or service panel, and a glovebox opening. No contamination releases were traced to the gasket design that employed bolted clamps to compress the gasket between a connecting flange, window, or panel, and the exterior surface of a glovebox opening. As a result of these findings, the Actinide Ceramics group at LANL (NMT-9) has initiated a routine replacement and upgrade program to replace aging gloveboxes. All of the new gloveboxes will utilize the preferred gasket design, which is expected to reduce the number and frequency of contamination releases.

  3. Design improvements for gloveboxes used [in] 238PuO2 process operations

    George, T.G.

    1997-01-01

    238 PuO 2 process operations are housed in a complex of 76 gloveboxes and introductory hoods connected by means of an overhead trolley housed in a tunnel. Because a significant number of the gloveboxes used for 238 PuO 2 processing were installed before the original startup of the facility in 1978, they have been in service for nearly 20 years. During a recent heat source production campaign, numerous contamination releases in the 238 PuO 2 processing area were traced to degraded elastomer gaskets used for glovebox connections, and attachment of feed-throughs, service panels, and windows. Evaluation of the degraded gaskets revealed that a combination of radiolytic degradation related to the high specific activity of 238 Pu, and extended service at high altitude in a low (to extremely low) humidity environment had resulted in accelerated gasket aging. However, it was also apparent that gasket design was the most important factor in actual contamination release. All of the contamination releases that were traced to degraded gaskets occurred in variations of a design that used a spline to expand an elastomeric gasket into the space between a connecting flange, window, or service panel, and a glovebox opening. No contamination releases were traced to the gasket design that employed bolted clamps to compress the gasket between a connecting flange, window, or panel, and the exterior surface of a glovebox opening. As a result of these findings, the Actinide Ceramics group at LANL (NMT-9) has initiated a routine replacement and upgrade program to replace aging gloveboxes. All of the new gloveboxes will utilize the preferred gasket design, which is expected to reduce the number and frequency of contamination releases

  4. Dexterity Test Data Contribute To Reduction in Leaded Glovebox Glove Use

    Cournoyer, M.E.; Lawton, C.M.; Castro, A.M.; Costigan, S.A.; Schreiber, S.

    2009-01-01

    Programmatic operations at the Los Alamos National Laboratory Plutonium Facility (TA-55) involve working with various amounts of plutonium and other highly toxic, alpha-emitting materials. The spread of radiological contamination on surfaces, airborne contamination, and excursions of contaminants into the operator's breathing zone are prevented through the use of a variety of gloveboxes. Using an integrated approach, controls have been developed and implemented through an efficient Glovebox Glove Integrity Program. A key element of this program is to consider measures that lower the overall risk of glovebox operations. Line management who own glovebox processes through this program make decisions on which type of glovebox gloves (hereafter referred to as gloves), the weakest component of this safety-significant system, would perform best in these aggressive environments. As Low as Reasonably Achievable considerations must be balanced with glove durability and worker dexterity, both of which affect the final overall risk of the operation. In the past, lead-loaded (leaded) gloves made from Hypalon R were the primary glove for programmatic operations at TA-55. Replacing leaded gloves with unleaded gloves for certain operations would lower the overall risk as well as reduce the amount of mixed transuranic waste. This effort contributes to the Los Alamos National Laboratory Continuous Improvement Program by improving the efficiency, cost-effectiveness, and formality of glovebox operations. In this report, the pros and cons of wearing leaded gloves, the effect of leaded gloves versus unleaded gloves on task performance using standard dexterity tests, the justification for switching from leaded to unleaded gloves, and the pollution prevention benefits of this dramatic change in the glovebox system are presented. (authors)

  5. WRAP low level waste restricted waste management (LLW RWM) glovebox acceptance test report

    Leist, K.J.

    1997-01-01

    On April 22, 1997, the Low Level Waste Restricted Waste Management (LLW RWM) glovebox was tested using acceptance test procedure 13027A-87. Mr. Robert L. Warmenhoven served as test director, Mr. Kendrick Leist acted as test operator and test witness, and Michael Lane provided miscellaneous software support. The primary focus of the glovebox acceptance test was to examine glovebox control system interlocks, operator Interface Unit (OIU) menus, alarms, and messages. Basic drum port and lift table control sequences were demonstrated. OIU menus, messages, and alarm sequences were examined, with few exceptions noted. Barcode testing was bypassed, due to the lack of installed equipment as well as the switch from basic reliance on fixed bar code readers to the enhanced use of portable bar code readers. Bar code testing was completed during performance of the LLW RWM OTP. Mechanical and control deficiencies were documented as Test Exceptions during performance of this Acceptance Test. These items are attached as Appendix A to this report

  6. Building 773-A, Lab F003 Glovebox Project Radiological Design Summary Report

    Gaul, W.C.

    2003-01-01

    Engineering Standards present the radiological design criteria and requirements, which must be satisfied for all SRS facility designs. The radiological design criteria and requirements specified in the standard are based on the Code of Federal Regulations, DOE Orders, Site manuals, other applicable standards, and various DOE guides and handbooks. This report contains top-level requirements for the various areas of radiological protection for workers. For the purposes of demonstrating compliance with these requirements, the designer must examine the requirement for the design and either incorporate or provide a technical justification as to why the requirement is not incorporated. This document reports a radiological design review for the STREAK lab glovebox upgrades of inlet ventilation, additional mechanical and electrical services, new glovebox instrumentation and alarms. This report demonstrates that the gloveboxes meet the radiological design requirements of Engineering Standards

  7. A technique for the assessment of the masses of residual plutonium in gloveboxes using thermoluminescent dosimeters

    Day, B.; Godward, D.F.

    1979-01-01

    A means of measuring the mass of residual plutonium in gloveboxes in the size range 1 to 10 m 3 has been developed using multiple thermoluminescent detectors. By optimising the location and the number of detectors, and by using suitable filtration, the mean response from them has been made insensitive to the distribution and the composition of the plutonium. It is possible to detect 10 g of plutonium in the largest glovebox considered. The measurement and mass estimation processes have been reduced to simple operations which can be carried out by skilled industrial staff. The routine application of the technique has been arranged to minimise disturbance to be production work going on in the gloveboxes by making unattended measurements during silent hours

  8. Alternative approach for fire suppression of class A, B and C fires in gloveboxes

    Rosenberger, Mark S [Los Alamos National Laboratory; Tsiagkouris, James A [Los Alamos National Laboratory

    2011-02-10

    Department of Energy (DOE) Orders and National Fire Protection Association (NFPA) Codes and Standards require fire suppression in gloveboxes. Several potential solutions have been and are currently being considered at Los Alamos National Laboratory (LANL). The objective is to provide reliable, minimally invasive, and seismically robust fire suppression capable of extinguishing Class A, B, and C fires; achieve compliance with DOE and NFPA requirements; and provide value-added improvements to fire safety in gloveboxes. This report provides a brief summary of current approaches and also documents the successful fire tests conducted to prove that one approach, specifically Fire Foe{trademark} tubes, is capable of achieving the requirement to provide reliable fire protection in gloveboxes in a cost-effective manner.

  9. Inductively coupled plasma-atomic emission spectroscopy glovebox assembly system at the West Valley Demonstration Project

    Marlow, J.H.; McCarthy, K.M.; Tamul, N.R.

    1999-01-01

    The inductively coupled plasma/atomic emission spectroscopy [ICP/AES (ICP)] system for elemental analyses in support of vitrification processing was first installed in 1986. The initial instrument was a Jobin Yvon (JY) Model JY-70 ICP that consisted of sequential and simultaneous spectrometers for analysis of nonradioactive samples as radioactive surrogates. The JY-70 ICP continued supporting nonradioactive testing during the Functional and Checkout Testing of Systems (FACTS) using the full-scale melter with ''cold'' (nonradioactive) testing campaigns. As a result, the need for another system was identified to allow for the analysis of radioactive samples. The Mass Spec (Spectrometry) Lab was established for the installation of the modified ICP system for handling radioactive samples. The conceptual setup of another ICP was predicated on the use of a hood to allow ease of accessibility of the torch, nebulizer, and spray chamber, and the minimization of air flow paths. However, reconsideration of the radioactive sample dose rate and contamination levels led to the configuration of the glovebox system with a common transfer interface box for the ICP and the inductively coupled plasma-mass spectrometer (ICP-MS) glovebox assemblies. As a result, a simultaneous Model JY-50P ICP with glovebox was installed in 1990 as a first generation ICP glovebox system. This was one of the first ICP glovebox assemblies connected with an ICP-MS glovebox system. Since the economics of processing high-level radioactive waste (HLW) required the availability of an instrument to operate 24 hours a day throughout the year without any downtime, a second generation ICP glovebox assembly was designed, manufactured, and installed in 1995 using a Model JY-46P ICP. These two ICP glovebox systems continue to support vitrification of the HLW into canisters for storage. The ICP systems have been instrumental in monitoring vitrification batch processing. To date, remote sample preparation and

  10. Report of working group for technical standard of cutting and melting works in Glovebox dismantling

    Asazuma, Shinichiroh; Takeda, Shinsoh; Tajima, Shoichi

    2004-11-01

    In order to prevent spread of contamination, glovebox dismantling activity is usually performed in a confined enclosure with personal radioactive protective equipment. Since large potion of these materials is made of vinyl acetate, there exist potential risks of fire, damage and injury to the environment and workers during the dismantling (cutting or melting) operation. It is therefore important to establish standard for proper use of equipment and hazard controls in such a specific environment. Working Group composed of Tokai Works and Oarai Works has examined and developed the operational standard for cutting work in glovebox dismantlement. The result is reflected to the Tokai Works Safety Operational Standard. (author)

  11. Preliminary evaluation of the electrapette for possible use in the glovebox for pipetting plutonium solutions

    Hansbury, E.; Ortiz, B.; Roybal, C.

    1990-12-01

    At the Los Alamos Laboratory Plutonium Facility, Solution Assay Instruments (SAIs) are used to provide real-time information on the plutonium (Pu) content of the process stream at various stages in the process. Much of the solution analysis must be carried and as a glovebox to protect the operator from radiation. In order to overcome some of the difficulties usually encountered when working in a glovebox, an electronic solution-volume measuring device called an Electrapette was ordered from Matrix Technologies Corporation. It is said to be highly accurate, simple to use, and can handle the 25 ml of solution required for SAI analyses. It is microprocessor-controlled and comes in two components connected by a detachable cable so that the electronic part can be installed outside the box, while the nosepiece is inside. The two pieces are connected through a plug-in on the glovebox wall. The Electrapette was tested in three sets of experiments: a cold'' lab set, a set run is a hood in a production building, and a third set run in a glovebox using a process solution whose density had been predetermined. The accuracy of the determination could not be determined because the samples had been mixed with other feed before being sent for analysis by the Electrapette. 2 refs., 5 tabs.

  12. Modular glovebox connector and associated good practices for control of radioactive and chemically toxic materials

    Hoover, M.D.; Mewhinney, C.J.; Newton, G.J.

    1999-01-01

    Design and associated good practices are described for a modular glovebox connector to improve control of radioactive and chemically toxic materials. The connector consists of an anodized aluminum circular port with a mating spacer, gaskets, and retaining rings for joining two parallel ends of commercially available or custom-manufactured glovebox enclosures. Use of the connector allows multiple gloveboxes to be quickly assembled or reconfigured in functional units. Connector dimensions can be scaled to meet operational requirements for access between gloveboxes. Options for construction materials are discussed, along with recommendations for installation of the connector in new or retrofitted systems. Associated good practices include application of surface coatings and caulking, use of disposable glovebags, and proper selection and protection of gasket and glove materials. Use of the connector at an inhalation toxicology research facility has reduced the time and expense required to reconfigure equipment for changing operational requirements, the dispersion of contamination during reconfigurations, and the need for decommissioning and disposal of contaminated enclosures

  13. W-026, transuranic waste restricted waste management (TRU RWM) glovebox operational test report

    Leist, K.J.

    1998-02-18

    The TRU Waste/Restricted Waste Management (LLW/PWNP) Glovebox 401 is designed to accept and process waste from the Transuranic Process Glovebox 302. Waste is transferred to the glovebox via the Drath and Schraeder Bagless Transfer Port (DO-07401) on a transfer stand. The stand is removed with a hoist and the operator inspects the waste (with the aid of the Sampling and Treatment Director) to determine a course of action for each item. The waste is separated into compliant and non compliant. One Trip Port DO-07402A is designated as ``Compliant``and One Trip Port DO-07402B is designated as ``Non Compliant``. As the processing (inspection, bar coding, sampling and treatment) of the transferred items takes place, residue is placed in the appropriate One Trip port. The status of the waste items is tracked by the Data Management System (DMS) via the Plant Control System (PCS) barcode interface. As an item is moved for sampling or storage or it`s state altered by treatment, the Operator will track an items location using a portable barcode reader and entry any required data on the DMS console. The Operational Test Procedure (OTP) will perform evolutions (described here) using the Plant Operating Procedures (POP) in order to verify that they are sufficient and accurate for controlled glovebox operation.

  14. Procedure for hazards analysis of plutonium gloveboxes used in analytical chemistry operations

    Delvin, W.L.

    1977-06-01

    A procedure is presented to identify and assess hazards associated with gloveboxes used for analytical chemistry operations involving plutonium. This procedure is based upon analytic tree methodology and it has been adapted from the US Energy Research and Development Administration's safety program, the Management Oversight and Risk Tree

  15. W-026, transuranic waste restricted waste management (TRU RWM) glovebox operational test report

    Leist, K.J.

    1998-01-01

    The TRU Waste/Restricted Waste Management (LLW/PWNP) Glovebox 401 is designed to accept and process waste from the Transuranic Process Glovebox 302. Waste is transferred to the glovebox via the Drath and Schraeder Bagless Transfer Port (DO-07401) on a transfer stand. The stand is removed with a hoist and the operator inspects the waste (with the aid of the Sampling and Treatment Director) to determine a course of action for each item. The waste is separated into compliant and non compliant. One Trip Port DO-07402A is designated as ''Compliant''and One Trip Port DO-07402B is designated as ''Non Compliant''. As the processing (inspection, bar coding, sampling and treatment) of the transferred items takes place, residue is placed in the appropriate One Trip port. The status of the waste items is tracked by the Data Management System (DMS) via the Plant Control System (PCS) barcode interface. As an item is moved for sampling or storage or it's state altered by treatment, the Operator will track an items location using a portable barcode reader and entry any required data on the DMS console. The Operational Test Procedure (OTP) will perform evolutions (described here) using the Plant Operating Procedures (POP) in order to verify that they are sufficient and accurate for controlled glovebox operation

  16. Adaptation of a glow discharge mass spectrometer in a glove-box for the analysis of nuclear materials

    Betti, M.; Rasmussen, G.; Hiernaut, T.; Koch, L.

    1994-01-01

    A VG9000 glow discharge mass spectrometer has been modified for the direct analysis of solid nuclear samples within a glove-box environment. Because containment is needed for the analysis of this kind of material, the glove-box encloses all parts of the instrument that come into contact with the sample, namely the ion source chamber, sample interlock and associated pumping system. External modifications eliminate outside contamination by the fitting of absolute filters on all source supplies. Internally the design of the ion source has been altered to minimize the number of operations performed inside the glove-box thereby simplifying operation and routine maintenance. These modifications retain the ion extraction and focusing properties of the instrument. The data presented show that there is no compromise in the analytical performance of the instrument when placed in the glove-box. Data representative of nuclear materials is also shown. (Author)

  17. NASA Virtual Glovebox: An Immersive Virtual Desktop Environment for Training Astronauts in Life Science Experiments

    Twombly, I. Alexander; Smith, Jeffrey; Bruyns, Cynthia; Montgomery, Kevin; Boyle, Richard

    2003-01-01

    The International Space Station will soon provide an unparalleled research facility for studying the near- and longer-term effects of microgravity on living systems. Using the Space Station Glovebox Facility - a compact, fully contained reach-in environment - astronauts will conduct technically challenging life sciences experiments. Virtual environment technologies are being developed at NASA Ames Research Center to help realize the scientific potential of this unique resource by facilitating the experimental hardware and protocol designs and by assisting the astronauts in training. The Virtual GloveboX (VGX) integrates high-fidelity graphics, force-feedback devices and real- time computer simulation engines to achieve an immersive training environment. Here, we describe the prototype VGX system, the distributed processing architecture used in the simulation environment, and modifications to the visualization pipeline required to accommodate the display configuration.

  18. Dismantling techniques for plutonium-contaminated gloveboxes: experience from first year of decommissioning

    Baumann, R.; Faber, P.

    2003-01-01

    At the mixed-oxide (MOX) processing facility formerly operated by ALKEM GmbH in Hanau, Germany - which was taken over to Siemens in 1988 and renamed Siemens' Hanau Fuel Fabrication Plant, MOX facility - around 8500 kg of plutonium were processed to make MOX fuel rods and fuel assemblies since production started in 1965. After shutdown of the facility by the authorities in mid-1991 for political reasons, the remaining nuclear fuel materials were processed during the subsequent ''cleanout'' phase starting in 1997 into rods and assemblies suitable for long-term storage. The last step in cleanout consisted of ''flushing'' the production equipment with depleted uranium and thoroughly cleaning the gloveboxes. During cleanout around 700 kg of plutonium were processed in the form of mixed oxides. The cleanout phase including the subsequent cleaning and flushing operations ended on schedule in September 2001 without any significant problems. Starting in mid-1999, the various glovebox dismantling techniques were tested using uncontaminated components while cleanout was still in progress and then, once these trials had been successfully completed, further qualified through use on actual components. The pilot-phase trials required four separate licenses under Section 7, Subsection (3) of the German Atomic Energy Act. Thanks to detailed advance planning and experience from the pilot trials the individual dismantling steps could be described in sufficient detail for the highly complex German licensing procedure. The first partial license for decommissioning the MOX facility under Sec. 7, Subsec. (3) of the Atomic Energy Act was issued on May 28, 2001. It mainly covers dismantling of the interior equipment inside the gloveboxes a well as the gloveboxes themselves. Actual decommissioning work inside the former production areas of the MOX facility started on a large scale in early September 2001. (orig.)

  19. HOLDUP MEASUREMENTS FOR VISUAL EXAMINATION GLOVEBOXES AT THE SAVANNAH RIVER SITE

    Sigg, R

    2006-05-03

    Visual Examination (VE) gloveboxes are used at the Savannah River Site (SRS) to remediate transuranic waste (TRU) drums. Noncompliant items are removed before the drums undergo further characterization in preparation for shipment to the Waste Isolation Pilot Plant (WIPP). Maintaining the flow of drums through the remediation process is critical to the program's seven-days-per-week operation. Conservative assumptions are used to ensure that glovebox contamination from this continual operation is below acceptable limits. Holdup measurements are performed in order to confirm that these assumptions are conservative. High Cs-137 backgrounds in the VE glovebox areas preclude the use of a sodium iodide spectrometer, so a high-purity germanium (HPGe) detector, having superior resolution, is used. Plutonium-239 is usually the nuclide of interest; however, Pu-241, Np-237 (including its daughter Pa-233) and Pu-238 (if detected) are typically assayed. Cs-137 and Co-60 may also be detected but are not reported since they do not contribute to the Pu-239 Fissile Gram Equivalent or Pu-239 Equivalent Curies. HEPA filters, drums and waste boxes are also assayed by the same methodology. If--for example--the HEPA is contained in a stainless steel housing, attenuation corrections must be applied for both the filter and the housing. Dimensions, detector locations, materials and densities are provided as inputs to Ortec's ISOTOPIC software to estimate attenuation and geometry corrections for the measurement positions. This paper discusses the methodology, results and limitations of these measurements for different VE glovebox configurations.

  20. A new glove-box system for a high-pressure tritium pump

    Wilson, S.W.; Borree, R.J.; Chambers, D.I.; Chang, Y.; Merrill, J.T.; Souers, P.C.; Wiggins, R.K.

    1988-01-01

    A new glove-box system that was designed around a high-pressure tritium pump is described. The system incorporates new containment ideas such as ''burpler'' passive pressure controls, valves that can be turned from outside the box, inflatable door seals, ferro-fluidic motor-shaft seals, and rapid box-to-hood conversion during cryostaging. Currently under construction, the system will contain nine separate sections with automatic pressure-balancing and venting systems. 3 refs., 5 figs

  1. Improving Efficiency with 3-D Imaging: Technology Essential in Removing Plutonium Processing Equipment from Plutonium Finishing Plant Gloveboxes

    Crow, Stephen H.; Kyle, Richard N.; Minette, Michael J.

    2008-01-01

    The Plutonium Finishing Plant at Hanford, Washington began operations in 1949 to process plutonium and plutonium products. Its primary mission was to produce plutonium metal, fabricate weapons parts, and stabilize reactive materials. These operations, and subsequent activities, were performed in remote production lines, consisting primarily of hundreds of gloveboxes. Over the years these gloveboxes and processes have been continuously modified. The plant is currently inactive and Fluor Hanford has been tasked to clean out contaminated equipment and gloveboxes from the facility so it can be demolished in the near future. Approximately 100 gloveboxes at PFP have been cleaned out in the past four years and about 90 gloveboxes remain to be cleaned out. Because specific commitment dates for this work have been established with the State of Washington and other entities, it is important to adopt work practices that increase the safety and speed of this effort. The most recent work practice to be adopted by Fluor Hanford D and D workers is the use of 3-D models to improve the efficiency of cleaning out radioactive gloveboxes at the plant. The use of 3-D models has significantly improved the work planning process by providing workers with a clear image of glovebox construction and composition, which is then used to determine cleanout methods and work sequences. The 3-D visual products enhance safety by enabling workers to more easily identify hazards and implement controls. In addition, the ability to identify and target the removal of radiological materials early in the D and D process provides substantial dose reduction for the workers

  2. CSER 00-003: Criticality Safety Evaluation report for PFP Magnesium Hydroxide Precipitation Process for Plutonium Stabilization Glovebox 3

    LAN, J.S.

    2000-01-01

    This Criticality Safety Evaluation Report analyzes the stabilization of plutonium/uranium solutions in Glovebox 3 using the magnesium hydroxide precipitation process at PFP. The process covered are the receipt of diluted plutonium solutions into three precipitation tanks, the precipitation of plutonium from the solution, the filtering of the plutonium precipitate from the solution, the scraping of the precipitate from the filter into boats, and the initial drying of the precipitated slurry on a hot plate. A batch (up to 2.5 kg) is brought into the glovebox as plutonium nitrate, processed, and is then removed in boats for further processing. This CSER establishes limits for the magnesium hydroxide precipitation process in Glovebox 3 to maintain criticality safety while handling fissionable material

  3. Glovebox design requirements for molten salt oxidation processing of transuranic waste

    Ramsey, K.B.; Acosta, S.V. [Los Alamos National Lab., NM (United States); Wernly, K.D. [Molten Salt Oxidation Corp., Bensalem, PA (United States)

    1998-12-31

    This paper presents an overview of potential technologies for stabilization of {sup 238}Pu-contaminated combustible waste. Molten salt oxidation (MSO) provides a method for removing greater than 99.999% of the organic matrix from combustible waste. Implementation of MSO processing at the Los Alamos National Laboratory (LANL) Plutonium Facility will eliminate the combustible matrix from {sup 238}Pu-contaminated waste and consequently reduce the cost of TRU waste disposal operations at LANL. The glovebox design requirements for unit operations including size reduction and MSO processing will be presented.

  4. Glovebox design requirements for molten salt oxidation processing of transuranic waste

    Ramsey, K.B.; Acosta, S.V.; Wernly, K.D.

    1998-01-01

    This paper presents an overview of potential technologies for stabilization of 238 Pu-contaminated combustible waste. Molten salt oxidation (MSO) provides a method for removing greater than 99.999% of the organic matrix from combustible waste. Implementation of MSO processing at the Los Alamos National Laboratory (LANL) Plutonium Facility will eliminate the combustible matrix from 238 Pu-contaminated waste and consequently reduce the cost of TRU waste disposal operations at LANL. The glovebox design requirements for unit operations including size reduction and MSO processing will be presented

  5. In-Situ Leak Testing And Replacement Of Glovebox Isolator, Or Containment Unit Gloves

    Castro, Julio M.; Macdonald, John M.; Steckle, Jr., Warren P.

    2004-11-02

    A test plug for in-situ testing a glove installed in a glovebox is provided that uses a top plate and a base plate, and a diametrically expandable sealing mechanism fitting between the two plates. The sealing mechanism engages the base plate to diametrically expand when the variable distance between the top plate and the bottom plate is reduced. An inlet valve included on the top plate is used to introducing a pressurized gas to the interior of the glove, and a pressure gauge located on the top plate is used to monitor the interior glove pressure.

  6. Strategy for decommissioning of the glove-boxes in the Belgonucleaire Dessel MOX fuel fabrication plant

    Vandergheynst, Alain; Cuchet, Jean-Marie

    2007-01-01

    Available in abstract form only. Full text of publication follows: BELGONUCLEAIRE has been operating the Dessel plant from the mid-80's at industrial scale. In this period, over 35 metric tons of plutonium (HM) was processed into almost 100 reloads of MOX fuel for commercial West-European Light Water Reactors. In late 2005, the decision was made to stop the production because of the shortage of MOX fuel market remaining accessible to BELGONUCLEAIRE after the successive capacity increases of the MELOX plant (France) and the commissioning of the SMP plant (UK). As a significant part of the decommissioning project of this Dessel plant, about 170 medium-sized glove-boxes are planned for dismantling. In this paper, after having reviewed the different specifications of ±-contaminated waste in Belgium, the authors introduce the different options considered for cleaning, size reduction and packaging of the glove-boxes, and the main decision criteria (process, α-containment, mechanization and radiation protection, safety aspects, generation of secondary waste, etc) are analyzed. The selected strategy consists in using cold cutting techniques and manual operation in shielded disposable glove-tents, and packaging α-waste in 200-liter drums for off-site conditioning and intermediate disposal. (authors)

  7. Microgravity Science Glovebox (MSG) Space Science's Past, Present, and Future on the International Space Station (ISS)

    Spivey, Reggie A.; Spearing, Scott F.; Jordan, Lee P.; McDaniel S. Greg

    2012-01-01

    The Microgravity Science Glovebox (MSG) is a double rack facility designed for microgravity investigation handling aboard the International Space Station (ISS). The unique design of the facility allows it to accommodate science and technology investigations in a "workbench" type environment. MSG facility provides an enclosed working area for investigation manipulation and observation in the ISS. Provides two levels of containment via physical barrier, negative pressure, and air filtration. The MSG team and facilities provide quick access to space for exploratory and National Lab type investigations to gain an understanding of the role of gravity in the physics associated research areas. The MSG is a very versatile and capable research facility on the ISS. The Microgravity Science Glovebox (MSG) on the International Space Station (ISS) has been used for a large body or research in material science, heat transfer, crystal growth, life sciences, smoke detection, combustion, plant growth, human health, and technology demonstration. MSG is an ideal platform for gravity-dependent phenomena related research. Moreover, the MSG provides engineers and scientists a platform for research in an environment similar to the one that spacecraft and crew members will actually experience during space travel and exploration. The MSG facility is ideally suited to provide quick, relatively inexpensive access to space for National Lab type investigations.

  8. Design and fabrication of a glovebox for the Plasma Hearth Process radioactive bench-scale system

    Wahlquist, D.R.

    1996-01-01

    This paper presents some of the design considerations and fabrication techniques for building a glovebox for the Plasma Hearth Process (PHP) radioactive bench-scale system. The PHP radioactive bench-scale system uses a plasma torch to process a variety of radioactive materials into a final vitrified waste form. The processed waste will contain plutonium and trace amounts of other radioactive materials. The glovebox used in this system is located directly below the plasma chamber and is called the Hearth Handling Enclosure (HHE). The HHE is designed to maintain a confinement boundary between the processed waste and the operator. Operations that take place inside the HHE include raising and lowering the hearth using a hydraulic lift table, transporting the hearth within the HHE using an overhead monorail and hoist system, sampling and disassembly of the processed waste and hearth, weighing the hearth, rebuilding a hearth, and sampling HEPA filters. The PHP radioactive bench-scale system is located at the TREAT facility at Argonne National Laboratory-West in Idaho Falls, Idaho

  9. Equipping a glovebox for waste form testing and characterization of plutonium bearing materials

    Noy, M.; Johnson, S.G.; Moschetti, T.L.

    1997-01-01

    The recent decision by the Department of Energy to pursue a hybrid option for the disposition of weapons plutonium has created the need for additional facilities that can examine and characterize waste forms that contain Pu. This hybrid option consists of the placement of plutonium into stable waste forms and also into mixed oxide fuel for commercial reactors. Glass and glass-ceramic waste forms have a long history of being effective hosts for containing radionuclides, including plutonium. The types of tests necessary to characterize the performance of candidate waste forms include: static leaching experiments on both monolithic and crushed waste forms, microscopic examination, and density determination. Frequently, the respective candidate waste forms must first be produced using elevated temperatures and/or high pressures. The desired operations in the glovebox include, but are not limited to the following: (1) production of vitrified/sintered samples, (2) sampling of glass from crucibles or other vessels, (3) preparing samples for microscopic inspection and monolithic and crushed static leach tests, and (4) performing and analyzing leach tests in situ. This paper will describe the essential equipment and modifications that are necessary to successfully accomplish the goal of outfitting a glovebox for these functions

  10. CSER 00-008 use of PFP Glovebox HC-18BS for Storage and Transport of Fissionable Material

    ERICKSON, D.G.

    2000-01-01

    This CSER addresses the feasibility of increasing the allowed number of open containers and permitting the transfer and storage of fissionable material in Glovebox HC-18BS without regard to form or density (metal, oxide having an H/X (le) 20, material having unrestricted moderation and plutonium hydroxide having a plutonium density of 0.2 g/cm 3 )

  11. A human factors approach towards the design of a new glovebox glove for Los Alamos National Laboratory

    Oka, Jude M. [Los Alamos National Laboratory

    2012-08-06

    Present day glovebox gloves at Los Alamos National Laboratory (LANL) are underdeveloped and ergonomically inaccurate. This problem results in numerous sprain and strain injuries every year for employees who perform glovebox work. In addition to injuries, using the current glovebox glove design also contributes to breaches and contamination. The current glove used today at LANL has several problems: (1) The length of the fingers is incorrect, (2) the web spacing between the fingers is nonexistent, (3) the angles between each digit on the finger are incorrect, (4) the thumb is placed inaccurately, and (5) the length of the hand is incorrect. These problems present a need to correct the current glove design to decrease the risk of injuries, breaches, and contamination. Anthropometrics were researched to help find the best range of hand measurements to fix the current glove design. Anthropometrics is the measure of the human physical variation. Anthropometrics for this study were gathered from the American National Survey (ANSUR) data that was conducted by the U.S Army in 1988. The current glovebox glove uses anthropometrics from the 95th to 105th percentile range which is too large so the new gloves are going to implement data from a smaller range of percentile groups. The 105th percentile range represents measurements that exceed the human population but are needed to fit certain circumstance such as wearing several under gloves within the glovebox gloves. Anthropometrics used in this study include: 105th percentile measurements for joint circumference which was unchanged because the room for under gloves plus ease of hand insertion and extraction is needed, 80th percentile measurements for crotch length to allow workers to reach the web spacing in the glove, 20th percentile measurements for finger length to allow workers to reach the end of the glove, standard 10.5cm hand breadth to allow more room to accommodate under gloves, 45 degrees abduction angle for the

  12. Glovebox glove deterioration in the Hanford Engineering Development Laboratory fuel fabrication facility

    Greenhalgh, W.O.; Smith, R.C.; Powell, D.L.

    1979-07-01

    Neoprene glovebox gloves have been found susceptible to periodic rapid deterioration under normal operating conditions in fuel fabrication facilities. Examinations of glove failure histories and measurements of the atmospheres in inert atmosphere dry-boxes indicated ozone at low concentrations of 100 to 500 ppB was probably the most important factor in rapid glove deterioration. Testing of a varity of new glove materials indicated that Hypalon and ethylene-propylene-diamine monomer (EDPM) gloves have greater than 30 times the longevity of neoprene in low-level ozone concentration atmospheres. comparative tests over a 30-month period have also confirmed that the two glove candidates have a significantly longer operative life. 14 figures

  13. Prediction of dose and field mapping around a shielded plutonium fuel fabrication glovebox

    Strode, J.N.; Soldat, K.L.; Brackenbush, L.W.

    1984-01-01

    Westinghouse Hanford Company, as the Department of Energy's (DOE) prime contractor for the operation of the Hanford Engineering Development Laboratory (HEDL), is responsible for the development of the Secure Automated Fabrication (SAF) Line which is to be installed in the recently constructed Fuels and Materials Examination Facility (FMEF). The SAF Line will fabricate mixed-oxide (MOX) fuel pins for the Fast Flux Test Facility (FFTF) at an annual throughput rate of six (6) metric tons (MT) of MOX. The SAF Line will also demonstrate the automated manufacture of fuel pins on a production-scale. This paper describes some of the techniques used to reduce personnel exposure on the SAF Line, as well as the prediction and field mapping of doses from a shielded fuel fabrication glovebox. Tables are also presented from which exposure rate estimates can be made for plutonium recovered from fuels having different isotopic compositions as a result of varied burnup

  14. Calculation note - Consequences of a fire in the sorting and repackaging glovebox in room 636 of bldg 2736-ZB - Plutonium Finishing Plant

    JOHNSON, L.E.

    1999-01-01

    This Calculation Note provides a conservative estimate of the grams of plutonium released from Building 2736-ZB of the Plutonium Finishing Plant as a result of a fire within Glovebox 636, without consideration of mitigation

  15. Implementation of a spark plasma sintering facility in a hermetic glovebox for compaction of toxic, radiotoxic, and air sensitive materials

    Tyrpekl, V., E-mail: vaclav.tyrpekl@ec.europa.eu, E-mail: vaclav.tyrpekl@gmail.com; Berkmann, C.; Holzhäuser, M.; Köpp, F.; Cologna, M.; Somers, J. [European Commission, Joint Research Centre (JRC), Institute for Transuranium Elements (ITU), Postfach 2340, 76125 Karlsruhe (Germany); Wangle, T. [European Commission, Joint Research Centre (JRC), Institute for Transuranium Elements (ITU), Postfach 2340, 76125 Karlsruhe (Germany); Faculty of Nuclear Sciences and Physical Engineering, Czech Technical University in Prague, Břehová 7, Praha 1, 115 19 (Czech Republic)

    2015-02-15

    Spark plasma sintering (SPS) is a rapidly developing method for densification of powders into compacts. It belongs to the so-called “field assisted sintering techniques” that enable rapid sintering at much lower temperatures than the classical approaches of pressureless sintering of green pellets or hot isostatic pressing. In this paper, we report the successful integration of a SPS device into a hermetic glovebox for the handling of highly radioactive material containing radioisotopes of U, Th, Pu, Np, and Am. The glovebox implantation has been facilitated by the replacement of the hydraulic system to apply pressure with a compact electromechanical unit. The facility has been successfully tested using UO{sub 2} powder. Pellets with 97% of the theoretical density were obtained at 1000 °C for 5 min, significantly lower than the ∼1600 °C for 5-10 h used in conventional pellet sintering.

  16. The Virtual GloveboX (VGX: a Semi-immersive Virtual Environment for Training Astronauts in Life Sciences Experiments

    I. Alexander Twombly

    2004-06-01

    Full Text Available The International Space Station will soon provide an unparalleled research facility for studying the near- and longer-term effects of microgravity on living systems. Using the Space Station Glovebox Facility - a compact, fully contained reach-in environment - astronauts will conduct technically challenging life sciences experiments. Virtual environment technologies are being developed at NASA Ames Research Center to help realize the scientific potential of this unique resource by facilitating the experimental hardware and protocol designs and by assisting the astronauts in training. The "Virtual GloveboX" (VGX integrates high-fidelity graphics, force-feedback devices and real-time computer simulation engines to achieve an immersive training environment. Here, we describe the prototype VGX system, the distributed processing architecture used in the simulation environment, and modifications to the visualization pipeline required to accommodate the display configuration.

  17. Dismantling of a furnace and gloveboxes of a U3O8 with 20% enrichment production line

    Yorio, Daniel; Cinat, Enrique; Cincotta, Daniel; Fernandez, Carlos A.; Bruno, Hernan R.; Camacho, Esteban F.; Boero, Norma

    1999-01-01

    In the Uranium Powder Manufacturing Plant at CAC, U 3 O 8 with 20% enrichment is manufactured for fuel plates to be used in test reactors. This plant is in full operation since 1986, producing uranium oxide for Peru, Algeria, Iran, Egypt and the RA-3-CAE reactors. Some of the equipment of the Plant have finished their life time and one of the furnaces of the processing line had to be replaced. This work implied the dismantling not only of the furnace, but also of the gloveboxes connected to the furnace and the dismantling of the extraction lines and air injection of the gloveboxes. The work had to be performed with the necessary care in order to minimize risks and effects on personnel, installations and environment involved. (author)

  18. Glovebox-contained forty-millimeter gun system for the study of one-dimensional shock waves in toxic materials

    Honodel, C.A.

    1975-01-01

    A new gun system is being constructed at the Lawrence Livermore Laboratory for studies of the behavior of toxic materials under shock-loaded conditions. Due to the extreme toxicity of some materials, such as plutonium, the entire gun system must be enclosed in gloveboxes. Some of the experimental requirements that affected the design of the system, various diagnostic techniques that will be employed with the system, and some details of the final design that is presently under assembly are presented

  19. Automation of Command and Data Entry in a Glovebox Work Volume: An Evaluation of Data Entry Devices

    Steele, Marianne K.; Nakamura, Gail; Havens, Cindy; LeMay, Moira

    1996-01-01

    The present study was designed to examine the human-computer interface for data entry while performing experimental procedures within a glovebox work volume in order to make a recommendation to the Space Station Biological Research Project for a data entry system to be used within the Life Sciences Glovebox. Test subjects entered data using either a manual keypad, similar to a standard computer numerical keypad located within the glovebox work volume, or a voice input system using a speech recognition program with a microphone headset. Numerical input and commands were programmed in an identical manner between the two systems. With both electronic systems, a small trackball was available within the work volume for cursor control. Data, such as sample vial identification numbers, sample tissue weights, and health check parameters of the specimen, were entered directly into procedures that were electronically displayed on a video monitor within the glovebox. A pen and paper system with a 'flip-chart' format for procedure display, similar to that currently in use on the Space Shuttle, was used as a baseline data entry condition. Procedures were performed by a single operator; eight test subjects were used in the study. The electronic systems were tested under both a 'nominal' or 'anomalous' condition. The anomalous condition was introduced into the experimental procedure to increase the probability of finding limitations or problems with human interactions with the electronic systems. Each subject performed five test runs during a test day: two procedures each with voice and keypad, one with and one without anomalies, and one pen and paper procedure. The data collected were both quantitative (times, errors) and qualitative (subjective ratings of the subjects).

  20. An open-walled ionization chamber appropriate to tritium monitoring for glovebox

    Chen Zhilin; Chang Ruiming; Mu Long; Song Guoyang; Wang Heyi; Wu Guanyin; Wei Xiye

    2010-01-01

    An open-walled ionization chamber is developed to monitor the tritium concentration in gloveboxes in tritium processing systems. Two open walls are used to replace the sealed wall in common ionization chambers, through which the tritium gas can diffuse into the chamber without the aid of pumps and pipelines. Some basic properties of the chamber are examined to evaluate its performance. Results turn out that an open-walled chamber of 1 l in volume shows a considerably flat plateau over 700 V for a range of tritium concentration. The chamber also gives a good linear response to gamma fields over 4 decades under a pressure condition of 1 atm. The pressure dependence characteristics show that the ionization current is only sensitive at low pressures. The pressure influence becomes weaker as the pressure increases mainly due to the decrease in the mean free path of β particles produced by tritium decay. The minimum detection limit of the chamber is 3.7x10 5 Bq/m 3 .

  1. Evaluation of Life Sciences Glovebox (LSG) and Multi-Purpose Crew Restraint Concepts

    Whitmore, Mihriban

    2005-01-01

    Within the scope of the Multi-purpose Crew Restraints for Long Duration Spaceflights project, funded by Code U, it was proposed to conduct a series of evaluations on the ground and on the KC-135 to investigate the human factors issues concerning confined/unique workstations, such as the design of crew restraints. The usability of multiple crew restraints was evaluated for use with the Life Sciences Glovebox (LSG) and for performing general purpose tasks. The purpose of the KC-135 microgravity evaluation was to: (1) to investigate the usability and effectiveness of the concepts developed, (2) to gather recommendations for further development of the concepts, and (3) to verify the validity of the existing requirements. Some designs had already been tested during a March KC-135 evaluation, and testing revealed the need for modifications/enhancements. This flight was designed to test the new iterations, as well as some new concepts. This flight also involved higher fidelity tasks in the LSG, and the addition of load cells on the gloveports.

  2. Material handling systems for use in glovebox lines: A survey of Department of Energy facility experience

    Teese, G.D.; Randall, W.J.

    1992-01-01

    The Nuclear Weapons Complex Reconfiguration Study has recommended that a new manufacturing facility be constructed to replace the Rocky Flats Plant. In the new facility, use of an automated material handling system for movement of components would reduce both the cost and radiation exposure associated with production and maintenance operations. Contamination control would be improved between process steps through the use of airlocks and portals. Part damage associated with improper transport would be reduced, and accountability would be increased. In-process workpieces could be stored in a secure vault, awaiting a request for parts at a production station. However, all of these desirable features rely on the proper implementation of an automated material handling system. The Department of Energy Weapons Production Complex has experience with a variety of methods for transporting discrete parts in glovebox lines. The authors visited several sites to evaluate the existing technologies for their suitability for the application of plutonium manufacturing. Technologies reviewed were Linear motors, belt conveyors, roller conveyors, accumulating roller conveyors, pneumatic transport, and cart systems. The sites visited were The Idaho National Engineering laboratory, the Hanford Site, and the Rocky Flats Plant. Linear motors appear to be the most promising technology observed for the movement of discrete parts, and further investigation is recommended

  3. Implementation of dynamic cross-talk correction (DCTC) for MOX holdup assay measurements among multiple gloveboxes

    Nakamichi, Hideo; Nakamura, Hironobu; Mukai, Yasunobu; Kurita, Tsutomu; Beddingfield, David H.

    2012-01-01

    Plutonium holdup in gloveboxes (GBs) are measured by (passive neutron based NDA (HBAS) for the material control and accountancy (MC and A) at Plutonium Conversion Development Facility (PCDF). In the case that the GBs are installed close to one another, the cross-talk which means neutron double counting among GBs should be corrected properly. Though we used to use predetermined constants as the cross-talk correction, a new correction methodology for neutron cross-talk among the GBs with inventory changes is required for the improvement of MC and A. In order to address the issue of variable cross-talk contributions to holdup assay values, we applied a dynamic cross-talk correction (DCTC) method, based on the distributed source-term analysis approach, to obtain the actual doubles derived from the cross-talk between multiple GBs. As a result of introduction of DCTC for HBAS measurement, we could reduce source biases from the assay result by estimating the reliable doubles-counting derived from the cross-talk. Therefore, we could improve HBAS measurement uncertainty to a half of conventional system, and we are going to confirm the result. Since the DCTC methodology can be used to determine the cross-correlation among multiple inventories in small areas, it is expected that this methodology can be extended to the knowledge of safeguards by design. (author)

  4. Author Contribution to the Pu Handbook II: Chapter 37 LLNL Integrated Sample Preparation Glovebox (TEM) Section

    Wall, Mark A.

    2016-01-01

    The development of our Integrated Actinide Sample Preparation Laboratory (IASPL) commenced in 1998 driven by the need to perform transmission electron microscopy studies on naturally aged plutonium and its alloys looking for the microstructural effects of the radiological decay process (1). Remodeling and construction of a laboratory within the Chemistry and Materials Science Directorate facilities at LLNL was required to turn a standard radiological laboratory into a Radiological Materials Area (RMA) and Radiological Buffer Area (RBA) containing type I, II and III workplaces. Two inert atmosphere dry-train glove boxes with antechambers and entry/exit fumehoods (Figure 1), having a baseline atmosphere of 1 ppm oxygen and 1 ppm water vapor, a utility fumehood and a portable, and a third double-walled enclosure have been installed and commissioned. These capabilities, along with highly trained technical staff, facilitate the safe operation of sample preparation processes and instrumentation, and sample handling while minimizing oxidation or corrosion of the plutonium. In addition, we are currently developing the capability to safely transfer small metallographically prepared samples to a mini-SEM for microstructural imaging and chemical analysis. The gloveboxes continue to be the most crucial element of the laboratory allowing nearly oxide-free sample preparation for a wide variety of LLNL-based characterization experiments, which includes transmission electron microscopy, electron energy loss spectroscopy, optical microscopy, electrical resistivity, ion implantation, X-ray diffraction and absorption, magnetometry, metrological surface measurements, high-pressure diamond anvil cell equation-of-state, phonon dispersion measurements, X-ray absorption and emission spectroscopy, and differential scanning calorimetry. The sample preparation and materials processing capabilities in the IASPL have also facilitated experimentation at world-class facilities such as the

  5. Microgravity Science Glovebox (MSG), Space Science's Past, Present and Future Aboard the International Space Station (ISS)

    Spivey, Reggie; Spearing, Scott; Jordan, Lee

    2012-01-01

    The Microgravity Science Glovebox (MSG) is a double rack facility aboard the International Space Station (ISS), which accommodates science and technology investigations in a "workbench' type environment. The MSG has been operating on the ISS since July 2002 and is currently located in the US Laboratory Module. In fact, the MSG has been used for over 10,000 hours of scientific payload operations and plans to continue for the life of ISS. The facility has an enclosed working volume that is held at a negative pressure with respect to the crew living area. This allows the facility to provide two levels of containment for small parts, particulates, fluids, and gases. This containment approach protects the crew from possible hazardous operations that take place inside the MSG work volume and allows researchers a controlled pristine environment for their needs. Research investigations operating inside the MSG are provided a large 255 liter enclosed work space, 1000 watts of dc power via a versatile supply interface (120, 28, + 12, and 5 Vdc), 1000 watts of cooling capability, video and data recording and real time downlink, ground commanding capabilities, access to ISS Vacuum Exhaust and Vacuum Resource Systems, and gaseous nitrogen supply. These capabilities make the MSG one of the most utilized facilities on ISS. MSG investigations have involved research in cryogenic fluid management, fluid physics, spacecraft fire safety, materials science, combustion, and plant growth technologies. Modifications to the MSG facility are currently under way to expand the capabilities and provide for investigations involving Life Science and Biological research. In addition, the MSG video system is being replaced with a state-of-the-art, digital video system with high definition/high speed capabilities, and with near real-time downlink capabilities. This paper will provide an overview of the MSG facility, a synopsis of the research that has already been accomplished in the MSG, and an

  6. Overview of the Life Science Glovebox (LSG) Facility and the Research Performed in the LSG

    Cole, J. Michael; Young, Yancy

    2016-01-01

    The Life Science Glovebox (LSG) is a rack facility currently under development with a projected availability for International Space Station (ISS) utilization in the FY2018 timeframe. Development of the LSG is being managed by the Marshal Space Flight Center (MSFC) with support from Ames Research Center (ARC) and Johnson Space Center (JSC). The MSFC will continue management of LSG operations, payload integration, and sustaining following delivery to the ISS. The LSG will accommodate life science and technology investigations in a "workbench" type environment. The facility has a.Ii enclosed working volume that is held at a negative pressure with respect to the crew living area. This allows the facility to provide two levels of containment for handling Biohazard Level II and lower biological materials. This containment approach protects the crew from possible hazardous operations that take place inside the LSG work volume. Research investigations operating inside the LSG are provided approximately 15 cubic feet of enclosed work space, 350 watts of28Vdc and l IOVac power (combined), video and data recording, and real time downlink. These capabilities will make the LSG a highly utilized facility on ISS. The LSG will be used for biological studies including rodent research and cell biology. The LSG facility is operated by the Payloads Operations Integration Center at MSFC. Payloads may also operate remotely from different telescience centers located in the United States and different countries. The Investigative Payload Integration Manager (IPIM) is the focal to assist organizations that have payloads operating in the LSG facility. NASA provides an LSG qualification unit for payload developers to verify that their hardware is operating properly before actual operation on the ISS. This poster will provide an overview of the LSG facility and a synopsis of the research that will be accomplished in the LSG. The authors would like to acknowledge Ames Research Center, Johnson

  7. Unraveling aminophosphine redox mechanisms for glovebox-free InP quantum dot syntheses.

    Laufersky, Geoffry; Bradley, Siobhan; Frécaut, Elian; Lein, Matthias; Nann, Thomas

    2018-05-10

    The synthesis of colloidal indium phosphide quantum dots (InP QDs) has always been plagued by difficulties arising from limited P3- sources. Being effectively restricted to the highly pyrophoric tris(trimethylsilyl) phosphine (TMS3P) creates complications for the average chemist and presents a significant risk for industrially scaled reactions. The adaptation of tris(dialkylamino) phosphines for these syntheses has garnered attention, as these new phosphines are much safer and can generate nanoparticles with competitive photoluminescence properties to those from (TMS)3P routes. Until now, the reaction mechanics of this precursor were elusive due to many experimental optimizations, such as the inclusion of a high concentration of zinc salts, being atypical of previous InP syntheses. Herein, we utilize density functional theory calculations to outline a logical reaction mechanism. The aminophosphine precursor is found to require activation by a zinc halide before undergoing a disproportionation reaction to self-reduce this P(iii) material to a P(-iii) source. We use this understanding to adapt this precursor for a two-pot nanoparticle synthesis in a noncoordinating solvent outside of glovebox conditions. This allowed us to generate spherical InP/ZnS nanoparticles possessing fluorescence quantum yields >55% and lifetimes as fast as 48 ns, with tunable emission according to varying zinc halide acidity. The development of high quality and efficient InP QDs with this safer aminophosphine in simple Schlenk environments will enable a broader range of researchers to synthesize these nontoxic materials for a variety of high-value applications.

  8. Author Contribution to the Pu Handbook II: Chapter 37 LLNL Integrated Sample Preparation Glovebox (TEM) Section

    Wall, Mark A. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

    2016-10-25

    The development of our Integrated Actinide Sample Preparation Laboratory (IASPL) commenced in 1998 driven by the need to perform transmission electron microscopy studies on naturally aged plutonium and its alloys looking for the microstructural effects of the radiological decay process (1). Remodeling and construction of a laboratory within the Chemistry and Materials Science Directorate facilities at LLNL was required to turn a standard radiological laboratory into a Radiological Materials Area (RMA) and Radiological Buffer Area (RBA) containing type I, II and III workplaces. Two inert atmosphere dry-train glove boxes with antechambers and entry/exit fumehoods (Figure 1), having a baseline atmosphere of 1 ppm oxygen and 1 ppm water vapor, a utility fumehood and a portable, and a third double-walled enclosure have been installed and commissioned. These capabilities, along with highly trained technical staff, facilitate the safe operation of sample preparation processes and instrumentation, and sample handling while minimizing oxidation or corrosion of the plutonium. In addition, we are currently developing the capability to safely transfer small metallographically prepared samples to a mini-SEM for microstructural imaging and chemical analysis. The gloveboxes continue to be the most crucial element of the laboratory allowing nearly oxide-free sample preparation for a wide variety of LLNL-based characterization experiments, which includes transmission electron microscopy, electron energy loss spectroscopy, optical microscopy, electrical resistivity, ion implantation, X-ray diffraction and absorption, magnetometry, metrological surface measurements, high-pressure diamond anvil cell equation-of-state, phonon dispersion measurements, X-ray absorption and emission spectroscopy, and differential scanning calorimetry. The sample preparation and materials processing capabilities in the IASPL have also facilitated experimentation at world-class facilities such as the

  9. Overview of the Microgravity Science Glovebox (MSG) Facility and the Research Performed in the MSG

    Jordan, Lee

    2016-01-01

    The Microgravity Science Glovebox (MSG) is a rack facility aboard the International Space Station (ISS) designed for investigation handling. The MSG was built by the European Space Agency (ESA) which also provides sustaining engineering support for the facility. The MSG has been operating on the ISS since July 2002 and is currently located in the US Laboratory Module. The unique design of the facility allows it to accommodate science and technology investigations in a "workbench" type environment. The facility has an enclosed working volume that is held at a negative pressure with respect to the crew living area. This allows the facility to provide two levels of containment for small parts, particulates, fluids, and gases. This containment approach protects the crew from possible hazardous operations that take place inside the MSG work volume. Research investigations operating inside the MSG are provided a large 255 liter enclosed work space, 1000 watts of direct current power via a versatile supply interface (120, 28, plus or minus 12, and 5 volts direct current), 1000 watts of cooling capability, video and data recording and real time downlink, ground commanding capabilities, access to ISS Vacuum Exhaust and Vacuum Resource Systems, and gaseous nitrogen supply. These capabilities make the MSG one of the most utilized facilities on ISS. The MSG has been used for over 27,000 hours of scientific payload operations. MSG investigations involve research in cryogenic fluid management, fluid physics, spacecraft fire safety, materials science, combustion, plant growth, biological studies and life support technology. The MSG facility is operated by the Payloads Operations Integration Center at Marshall Space Flight Center. Payloads may also operate remotely from different telescience centers located in the United States and Europe. The Investigative Payload Integration Manager (IPIM) is the focal to assist organizations that have payloads operating in the MSG facility

  10. Muffling Hammer Blows In A Workshop

    Thiele, Alfred W.; Gilbert, Jeffrey L.; Gutow, David A.

    1994-01-01

    Sound-deadening bags placed on hammered workpieces. Useful in many workshop situations. Fabricated easily and inexpensively. Bags filled with particles of sand, metal shot, plastic, or glass, then sewn or molded shut. Tailored to fit special configurations of some workpieces. Devices used to deaden print rollers and to reduce vibrations in main-injector inlet manifold of rocket engine.

  11. CSER 99-002: CSER for unrestricted moderation of sludge material with two-boat operations in gloveboxes HC-21A and HC-21C

    LAN, J.S.

    1999-01-01

    This Criticality Safety Evaluation Report was prepared by Fluor Daniel Northwest under contract to BWHC. This document establishes the criticality safety parameters for unrestricted moderation of Sludge material with two-boat operations in gloveboxes HC-21A and HC-21C

  12. Decontamination and decommissioning of 61 plutonium gloveboxes in D-Wing, Building 212 Argonne National Laboratory-East: Final project report

    Cheever, C.L.; Rose, R.W.

    1996-09-01

    Argonne National Laboratory-East (ANL-E) is a government-owned, contractor operated, multipurpose research facility located 25 miles southwest of downtown Chicago on 689 hectares (1,700 acres) in DuPage County, Illinois, as shown in Figure 1.1. Building 212 is located in the central area of ANL-E, as shown in Figure 1.2. The purpose of this project was to eliminate the risk of radioactive material release from the contaminated glovebox systems and to make the laboratories available for unrestricted use. The following work objectives were established: (1) Identify and remove radioactive materials for return to ANL-E Special Materials control. (2) Remove and package the radioactively contaminated materials and equipment from the gloveboxes. (3) Decontaminate the gloveboxes to nontransuranic (non-TRU) levels. (4) Size-reduce and package the gloveboxes and support systems. (5) Document and dispose of the radioactive and mixed waste. (6) Decontaminate, survey, and release the nine laboratories and corridor areas for unrestricted use

  13. Effects of glovebox gloves on grip and key pinch strength and contact forces for simulated manual operations with three commonly used hand tools.

    Sung, Peng-Cheng

    2014-01-01

    This study examined the effects of glovebox gloves for 11 females on maximum grip and key pinch strength and on contact forces generated from simulated tasks of a roller, a pair of tweezers and a crescent wrench. The independent variables were gloves fabricated of butyl, CSM/hypalon and neoprene materials; two glove thicknesses; and layers of gloves worn including single, double and triple gloving. CSM/hypalon and butyl gloves produced greater grip strength than the neoprene gloves. CSM/hypalon gloves also lowered contact forces for roller and wrench tasks. Single gloving and thin gloves improved hand strength performances. However, triple layers lowered contact forces for all tasks. Based on the evaluating results, selection and design recommendations of gloves for three hand tools were provided to minimise the effects on hand strength and optimise protection of the palmar hand in glovebox environments. To improve safety and health in the glovebox environments where gloves usage is a necessity, this study provides recommendations for selection and design of glovebox gloves for three hand tools including a roller, a pair of tweezers and a crescent wrench based on the results discovered in the experiments.

  14. In situ remediation of plutonium from glovebox exhaust ducts at the Department of Energy's Rocky Flats Plant

    Dugdale, J.S.; Humiston, T.J.; Omer, G.E.

    1993-01-01

    Plutonium and other miscellaneous hold-up materials have been accumulating in the glovebox exhaust ducts at the Rocky Flats Plant over the 40 years of weapons production at the site. The Duct Remediation Project was undertaken to assess the safety impacts of this material, and to remove it from the ductwork. The project necessitated the development of specialized tools, equipment and methods to remediate the material from continuously operating ventilation systems. Special engineered access locations were also required to provide access to the ductwork, and to ensure that safety and system operability were not degraded as a result of the remediation efforts. Operations personnel underwent significant training and development, and became an important asset to the success of the project. In total, the project succeeded in removing over 40 kilograms of plutonium-bearing material from one of the major weapons production buildings at the plant

  15. CSER 01-008 Canning of Thermally Stabilized Plutonium Oxide Powder in PFP Glovebox HC-21A

    ERICKSON, D.G.

    2001-01-01

    This document presents the analysis performed to support the canning operation in HC-21A. Most of the actual analysis was performed for the operation in HC-18M and HA-20MB, and is documented in HNF-2707 Rev I a (Erickson 2001a). This document will reference Erickson (2001a) as necessary to support the operation in HC-21A. The plutonium stabilization program at the Plutonium Finishing Plant (PFP) uses heat to convert plutonium-bearing materials into dry powder that is chemically stable for long term storage. The stabilized plutonium is transferred into one of several gloveboxes for the canning process, Gloveboxes HC-18M in Room 228'2, HA-20MB in Room 235B, and HC-21A in Room 230B are to be used for this process. This document presents the analysis performed to support the canning operation in HC-21A. Most of the actual analysis was performed for the operation in HC-I8M and HA-20MB, and is documented in HNF-2707 Rev l a (Erickson 2001a). This document will reference Erickson (2001a) as necessary to support the operation in HC-21A. Evaluation of this operation included normal, base cases, and contingencies. The base cases took the normal operations for each type of feed material and added the likely off-normal events. Each contingency is evaluated assuming the unlikely event happens to the conservative base case. Each contingency was shown to meet the double contingency requirement. That is, at least two unlikely, independent, and concurrent changes in process conditions are required before a criticality is possible

  16. Use of simulation to examine operational scenarios in a lathe glovebox for the processing of nuclear materials

    McQueen, M.; Ashok, P.; Cox, D.J.; Pittman, P.C.; Turner, C.J.; Hollen, R.M.

    2001-01-01

    In the process of dispositioning nuclear materials into storage, the use of a robot eliminates the safety risks to humans and increases productivity. The current process of processing typically uses humans to handle the hazardous material using gloves through glove-ports. This process is not only dangerous, but also costly, because humans can only be subjected to limited exposure to nuclear materials due to the actual Occupational Radiation Exposure (ORE) and thus have a fixed amount of dedicated workload per unit time. Use of robotics reduces ORE to humans and increases productivity. The Robotics Research Group at the University of Texas at Austin has created a simulation model of a conceptual application that uses a robot inside the glovebox to handle hazardous materials for lathe machining process operations in cooperation with Los Alamos National Laboratories (LANL). The actions of the robot include preparing the parts for entry into the box, weighing the parts, positioning the parts into the headstock chuck of the lathe, handling the subsequent processed parts, changing and replacing the lathe tools and chuck assemblies are necessary to process the material. The full three-dimensional geometric model of the simulation demonstrates the normal expected operation from beginning to end and verifies the path plans for the robot. The emphasis of this paper is to report additional findings from the simulation model, which is currently being expanded to include failure mode analysis, error recovery, and other what-if scenarios involved in unexpected, or unplanned, operation of the robot and lathe process inside of the glovebox.

  17. Preliminary hazards analysis of thermal scrap stabilization system. Revision 1

    Lewis, W.S.

    1994-01-01

    This preliminary analysis examined the HA-21I glovebox and its supporting systems for potential process hazards. Upon further analysis, the thermal stabilization system has been installed in gloveboxes HC-21A and HC-21C. The use of HC-21C and HC-21A simplified the initial safety analysis. In addition, these gloveboxes were cleaner and required less modification for operation than glovebox HA-21I. While this document refers to glovebox HA-21I for the hazards analysis performed, glovebox HC-21C is sufficiently similar that the following analysis is also valid for HC-21C. This hazards analysis document is being re-released as revision 1 to include the updated flowsheet document (Appendix C) and the updated design basis (Appendix D). The revised Process Flow Schematic has also been included (Appendix E). This Current revision incorporates the recommendations provided from the original hazards analysis as well. The System Design Description (SDD) has also been appended (Appendix H) to document the bases for Safety Classification of thermal stabilization equipment

  18. Dismantling techniques for plutonium-contaminated gloveboxes: experience from first year of decommissioning; Zerlegungstechniken fuer Pu-kontaminierte Handschuhkaesten: Erfahrungsbericht nach einem Jahr Rueckbau

    Baumann, R.; Faber, P. [Siemens Power Generation, Decommissioning Projects, Hanau (Germany)

    2003-07-01

    At the mixed-oxide (MOX) processing facility formerly operated by ALKEM GmbH in Hanau, Germany - which was taken over to Siemens in 1988 and renamed Siemens' Hanau Fuel Fabrication Plant, MOX facility - around 8500 kg of plutonium were processed to make MOX fuel rods and fuel assemblies since production started in 1965. After shutdown of the facility by the authorities in mid-1991 for political reasons, the remaining nuclear fuel materials were processed during the subsequent ''cleanout'' phase starting in 1997 into rods and assemblies suitable for long-term storage. The last step in cleanout consisted of ''flushing'' the production equipment with depleted uranium and thoroughly cleaning the gloveboxes. During cleanout around 700 kg of plutonium were processed in the form of mixed oxides. The cleanout phase including the subsequent cleaning and flushing operations ended on schedule in September 2001 without any significant problems. Starting in mid-1999, the various glovebox dismantling techniques were tested using uncontaminated components while cleanout was still in progress and then, once these trials had been successfully completed, further qualified through use on actual components. The pilot-phase trials required four separate licenses under Section 7, Subsection (3) of the German Atomic Energy Act. Thanks to detailed advance planning and experience from the pilot trials the individual dismantling steps could be described in sufficient detail for the highly complex German licensing procedure. The first partial license for decommissioning the MOX facility under Sec. 7, Subsec. (3) of the Atomic Energy Act was issued on May 28, 2001. It mainly covers dismantling of the interior equipment inside the gloveboxes a well as the gloveboxes themselves. Actual decommissioning work inside the former production areas of the MOX facility started on a large scale in early September 2001. (orig.)

  19. CSER 90-006, addendum 1: Criticality safety control for source term reduction project in the scrubber glovebox of Building 232-Z. Revision 1

    Hess, A.L.

    1995-01-01

    This Criticality Safety Evaluation Report addendum extends the coverage of the original CSER (90-006) about dismantling the ductwork in 232-Z to include cleanout of the Scrubber Glovebox, with an estimated residual Pu holdup of less than 200 grams. For conservatism and containment considerations, the provisions about waste packaging and water exclusion from the original work are retained, even though it is not credible for the Scrubber Pu content to be made critical with water added (NDA gives about 1/3 a minimum critical mass)

  20. An Overview of the Microgravity Science Glovebox (MSG) Facility and the Research Performed in the MSG on the International Space Station (ISS)

    Jordan, Lee P.

    2013-01-01

    The Microgravity Science Glovebox (MSG) is a rack facility aboard the International Space Station (ISS) designed for investigation handling. The MSG was built by the European Space Agency (ESA) which also provides sustaining engineering support for the facility. The MSG has been operating on the ISS since July 2002 and is currently located in the US Laboratory Module. The unique design of the facility allows it to accommodate science and technology investigations in a "workbench" type environment. The facility has an enclosed working volume that is held at a negative pressure with respect to the crew living area. This allows the facility to provide two levels of containment for small parts, particulates, fluids, and gases. This containment approach protects the crew from possible hazardous operations that take place inside the MSG work volume. Research investigations operating inside the MSG are provided a large 255 liter enclosed work space, 1000 watts of dc power via a versatile supply interface (120, 28, +/- 12, and 5 Vdc), 1000 watts of cooling capability, video and data recording and real time downlink, ground commanding capabilities, access to ISS Vacuum Exhaust and Vacuum Resource Systems, and gaseous nitrogen supply. These capabilities make the MSG one of the most utilized facilities on ISS. The MSG has been used for over 14500 hours of scientific payload operations. MSG investigations involve research in cryogenic fluid management, fluid physics, spacecraft fire safety, materials science, combustion, plant growth, and life support technology. The MSG facility is operated by the Payloads Operations Integration Center at Marshall Space flight Center. Payloads may also operate remotely from different telescience centers located in the United States and Europe. The investigative Payload Integration Manager (iPIM) is the focal to assist organizations that have payloads operating in the MSG facility. NASA provides an MSG engineering unit for payload developers

  1. Laser dismantling of a glovebox

    Johnson, R.; Fender, M.

    1985-01-01

    A 5 kW laser has been used to cut up a 2.6 x 1 x 1 m glove box made of 5 mm mild steel with 12.5 mm perspex windows and 3 mm neoprene gaskets. The laser cut all components including the sandwich of perspex, neoprene and steel with ease. The production of fibrous filaments of perspex during the cutting process has been almost avoided by modifying the cutting variables. The combustion of material beyond that being cut has also been prevented by adopting the correct level of laser power. The problems encountered with loss of glove box rigidity with progressive dismantling are discussed, together with the relevance these problems have to possible cutting methods other than lasers. (author)

  2. Dismantling of a furnace and gloveboxes of a U{sub 3}O{sub 8} with 20% enrichment production line; Desmantelamiento de un horno y cajas de guantes de una linea de produccion de U{sub 3}O{sub 8} enriquecido al 20%

    Yorio, Daniel; Cinat, Enrique; Cincotta, Daniel; Fernandez, Carlos A; Bruno, Hernan R; Camacho, Esteban F; Boero, Norma [Comision Nacional de Energia Atomica, General San Martin (Argentina). Dept. de Combustibles Nucleares

    1999-07-01

    In the Uranium Powder Manufacturing Plant at CAC, U{sub 3}O{sub 8} with 20% enrichment is manufactured for fuel plates to be used in test reactors. This plant is in full operation since 1986, producing uranium oxide for Peru, Algeria, Iran, Egypt and the RA-3-CAE reactors. Some of the equipment of the Plant have finished their life time and one of the furnaces of the processing line had to be replaced. This work implied the dismantling not only of the furnace, but also of the gloveboxes connected to the furnace and the dismantling of the extraction lines and air injection of the gloveboxes. The work had to be performed with the necessary care in order to minimize risks and effects on personnel, installations and environment involved. (author)

  3. Muffled voices. Making way for impact statements in criminal justice system in India

    Dipa Dube

    2018-03-01

    Full Text Available Victim Impact Statement (VIS is a crucial aspect in the process of dispensation of justice. It reinforces the participatory model of criminal justice system, wherein both the accused and the victim are significant and interwined in justice delivery mechanism. VIS has received little support from pro-accused activists who assert that the acceptance of such statements would make way for emotional blackmail and consequent enhancement of quantum of sentence. The claim has, however, been assailed by victimologists the world over, who have hailed the same as a positive assertion of the rights of the victim in the sentencing process. Simply speaking, a victim impact statement is a written or verbal statement made as part of the judicial legal process, which allows a victim of crime the opportunity to speak during the sentencing of the accused. It offers an opportunity to the victim or his/her family members to elaborate the trauma and hardships faced as a result of the crime committed. The present status of the victim or family, including the inconveniences faced, also become clear to the judge and allows him to make a decision. While VIS has been considered as significant and included as part of the criminal justice process in several nations across the world, India has remained rather unmoved and untouched. Several victimological approaches have been included in recent years in the criminal procedure of the land, yet impact statements seem to have eluded the legislators. This is particularly of significance in light of Indian judgments where the courts have reiterated that punishment must respond to the “society’s cry for justice”.

  4. Experimental studies on radiation heat transfer enhancement on a standard muffle furnace

    Minea Alina Adriana

    2013-01-01

    Full Text Available One of the sources of increased industrial energy consumption is the heating equipment, e.g., furnaces. Their domain of use is very wide and due to its abundance of applications it is key equipment in modern civilization. The present experimental investigations are related to reducing energy consumptions and started from the geometry of a classic manufactured furnace. During this experimental study, different cases have been carefully chosen in order to compare and measure the effects of applying different enhancement methods of the radiation heat transfer processes. The main objective work was to evaluate the behavior of a heated enclosure, when different radiant panels were introduced. The experimental investigation showed that their efficiency was influenced by their position inside the heating area. In conclusion, changing the inner geometry by introducing radiant panels inside the heated chamber leads to important time savings in the heating process.

  5. Predicting Worker Exposure from a Glovebox Leak

    Jordan, H.; Gordon, D. J.; Whicker, J. J.; Wannigman, D. L.

    2001-01-01

    It is difficult to predict immediate worker radiological consequences from a hypothetical accident. This is recognized in DOE safety analysis guidance and the reason such guidance does not call for quantitative determinations of such consequences. However, it would be useful to at least have a means of systematically and formally quantifying worker dose to be able to identify the relative risks of various processes and to provide an order-of-magnitude impression of absolute consequences. In this report, we present such a means in the form of a simple calculation model that is easily applied and generates reasonable, qualitative dose predictions. The model contains a scaling parameter whose value was deduced from extensive laboratory ventilation flow rate measurements performed at Los Alamos National Laboratory (LANL) over the last several years and from recent indoor radioactive contamination dispersion measurements, also at LANL. Application of the model is illustrated with the aid of two example calculations

  6. Sludge Stabilization Campaign blend plan

    De Vries, M.L.

    1994-01-01

    This sludge stabilization blend plan documents the material to be processed and the order of processing for the FY95 Sludge Stabilization Campaign. The primary mission of this process is to reduce the inventory of unstable plutonium bearing sludge. The source of the sludge is residual and glovebox floor sweepings from the production of material at the Plutonium Finishing Plant (PFP). The reactive sludge is currently being stored in various gloveboxes at PFP. There are two types of the plutonium bearing material that will be thermally stabilized in the muffle furnace: Plutonium Reclamation Facility (PRF) sludge and Remote Mechanical C (RMC) Line material

  7. Engineering study on conveyor system for HC-21C project

    De Vries, M.L.

    1995-01-01

    The sludge stabilization process thermally stabilizes reactive plutonium bearing materials in a muffle furnace. This process is used to prepare the material for long term storage in the vaults. The process is conducted in Room 230A and 230B. The furnaces are located in glovebox HC-21C. Glovebox HC-21A is used for preparation of the charge and packaging of the high fired oxide. The feed for the process is located throughout the PRF and RMC-line gloveboxes, with over half of the feedstock currently being located in HA-23S. For readiness assessment, the sludge stabilization process at PFP was reviewed by the ALARA team to see how the process could be improved. One suggestion was made that the conveyor system be used to transfer items from HA-23S to the process glovebox (HA-21A) instead of sealing items in and out of the gloveboxes. The following discussion describes and compares past and current methods. In addition, actions are addressed that would need to be completed before the conveyor method could be used. The transportation of the feedstock to the process and all the different influencing factors will be examined to determine the best method. This assessment is being performed considering only the current campaign for HC-21C. However, there is a possibility that in the future, additional furnaces will be installed and further campaigns done

  8. Study of plutonium fire extinction in glove-boxes

    Boisson, H.; Chappellier, A.; Debiar, A.; Savornin, J.

    1965-01-01

    The report concerns attempts to extinguish fire in uranium - chosen as a basis for comparison - and in plutonium, these being contained in glove boxes. The extinguishing powders TEC and MG 10 were tried and compared. The operator used in plastic bags. The metal was dealt with respectively in the form of billets, compact chips and finally thin shavings. In each case fire control was without difficulty. One must allow a certain time for cooling. The powder MG 10 showed very good results. Moreover, the trials proved that densely packed shavings are a very real security factor. The interior lay-out of the glove boxes ought, in order to facilitate further manipulations, be such as to render extinction as easy as possible should the need arise. (authors) [fr

  9. Glovebox atmosphere detritiation process using gas separation membranes

    Le Digabel, M.; Truan, P.A.; Ducret, D.; Laquerbe, C.; Perriat, P.; Niepce, J.C.; Pelletier, T.

    2003-01-01

    The use of gas separation membranes in atmospheric detritiation systems has been studied. The main advantage of this new process is to reduce the number and/or the size of the equipment in comparison to conventional tritium removal systems. Owing to the constraints linked to tritium handling, the separation performances of several commercial hollow fiber organic membranes have been analyzed, under various operating conditions, with hydrogen/nitrogen or deuterium/nitrogen mixtures. The experiments are performed with small quantities of hydrogen or deuterium (5000 ppm). The experimental results allow to evaluate the separation efficiency of these membranes and to determine the appropriate operating conditions to apply to a membrane detritiation process

  10. Sludge stabilization at the Plutonium Finishing Plant, Hanford Site, Richland, Washington

    1994-10-01

    This Environmental Assessment evaluates the proposed action to operate two laboratory-size muffle furnaces in glovebox HC-21C, located in the Plutonium Finishing Plant (PFP), Hanford Site, Richland, Washington. The muffle furnaces would be used to stabilize chemically reactive sludges that contain approximately 25 kilograms (55 pounds) of plutonium by heating to approximately 500 to 1000 degrees C (900 to 1800 degrees F). The resulting stable powder, mostly plutonium oxide with impurities, would be stored in the PFP vaults. The presence of chemically reactive plutonium-bearing sludges in the process gloveboxes poses a risk to workers from radiation exposure and limits the availability of storage space for future plant cleanup. Therefore, there is a need to stabilize the material into a form suitable for long-term storage. This proposed action would be an interim action, which would take place prior to completion of an Environmental Impact Statement for the PFP which would evaluate stabilization of all plutonium-bearing materials and cleanout of the facility. However, only 10 percent of the total quantity of plutonium in reactive materials is in the sludges, so this action will not limit the choice of reasonable alternatives or prejudice the Record of Decision of the Plutonium Finishing Plant Environmental Impact Statement

  11. Addendum 1 to CSERs 94-007 and 94-008: Use of 2.2 liter boats in muffle furnace operations at PFP

    Hess, A.L.

    1996-01-01

    This criticality safety review justifies raising the container size limit in CPS-Z-165-80621 and CPS-165-80622 to 2.3 liters, thereby allowing the use of 2.2-liter furnace boats in the Pu stabilization activities covered by these specifications

  12. Catalyst study for the decontamination of glove-box atmospheres containing tritium at MPC levels

    Chobot, J.; Montel, J.; Sannier, J.

    1988-01-01

    The BEATRICE loop was designed for studying the conversion of tritium at very low activity levels using catalytic oxidation followed by water trapping. The purpose is to study kinetic parameters required for the design of the NET tritium cleanup system with the two main objectives to operate without isotopic swamping and to determine the ability of efficient conversion at room temperature. From experiments carried out between 20 and 250 0 C it is concluded that two palladium/alumina and platinum/alumina catalysts are very efficient in removing tritium from contaminated gas mixtures down to a few MPC levels without isotopic swamping and even at room temperature. However at room temperature, in relation to tritium species trapped on the catalyst surface a progressive deactivation with time occurs. This phenomenon may be a concern for process efficiency and tritium inventory and regeneration conditions have to be determined in order to demonstrate industrial feasibility of operating at room temperature

  13. Developing glovebox robotics to meet the national robot safety standard and nuclear safety criteria

    McMahon, T.T.; Sievers, R.H.

    1991-09-01

    Development of a glove box based robotic system by the Lawrence Livermore National Laboratory (LLNL) is reported. Safety issues addressed include planning to meet the special constraints of operations within a hazardous material glove box and with hostile environments, compliance with the current and draft national robotic system safety standards, and eventual satisfaction of nuclear material handling requirements. Special attention has been required for the revision to the robot and control system models which antedate adoption of the present national safety standard. A robotic test bed, using non-radioactive surrogates is being activated at the Lawrence Livermore National Laboratory to develop the material handling system and the process interfaces for future special nuclear material processing applications. Part of this effort is to define, test, and revise adequate safety controls to ensure success when the system is eventually deployed at a DOE site. The current system is primarily for demonstration and testing, but will evolve into the baseline configuration from which the production system is to be derived. This results in special hazards associated with research activities which may not be present on a production line. Nuclear safety is of paramount importance and has been successfully addressed for 50 years in the DOE weapons production complex. It carries its particular requirements for robot systems and manual operations, as summarized below: Criticality must be avoided (materials cannot consolidate or accumulate to approach a critical mass). Radioactive materials must be confined. The public and workers must be protected from accountable radiation exposure. Nuclear material must be readily retrievable. Nuclear safety must be conclusively demonstrated through hazards analysis. 7 refs

  14. Object-oriented process dose modeling for glove-box operations

    Boerigter, S.T.; Fasel, J.H.; Kornreich, D.E.

    1999-01-01

    The Plutonium Facility at Los Alamos National Laboratory (LANL) supports several defense- and non-defense-related missions for the country by performing fabrication, surveillance, and research and development for materials and components that contain plutonium. Most operations occur in rooms with one or more arrays of glove boxes connected to each other via trolley glove boxes. Each room may contain glove boxes dedicated to several different operations or functions. Minimizing the effective dose equivalent (EDE) is a growing concern as a result of steadily allowable dose limits being imposed and a growing general awareness of safety in the workplace. In general, the authors discriminate three components of a worker's total EDE: the primary EDE, the secondary EDE, and background EDE. The immediate sources to which a worker is exposed provide the primary EDE. The secondary EDE results from operations and sources in the same vicinity or room as the worker. The background EDE results from all other sources of radiation, such as natural sources and sources outside of the room. A particular background source of interest is the nuclear materials vault. The distinction between sources inside and outside of a particular room is arbitrary with the underlying assumption that building walls and floors provide significant shielding to justify including sources in other rooms in the background category. An associated paper details the tool that they use to determine the primary and secondary EDEs for all processes of interest in a room containing glove boxes

  15. Applications of a glove-box ICP-MS for the analysis of nuclear materials

    Garcia Alonso, J.I.; Babelot, J.F.; Glatz, J.P.; Cromboom, O.; Koch, L.

    1993-01-01

    The relatively new analytical technique, Inductively Coupled Plasma Mass Spectrometry (ICP-MS), has been used for the analysis of nuclear materials stemming from different parts of the nuclear fuel cycle. The original instrument has been modified in order to work with radioactive materials in a glove box. The plasma torch and vacuum interface are situated inside the glove box while the mass spectrometer and associated electronics are outside. Samples analysed include fresh nuclear fuels (natural impurities), spent fuels (fission products and actinides), reprocessing solutions (minor actinides) and leachates of spent fuel and high level waste glasses (natural elements, fission products and actinides). (orig.)

  16. Glovebox with purification and pressure control of the neutral gas atmosphere in closed circuit

    Cadrot, J.

    1990-01-01

    In the gas main are placed 2 series of specific gas purifiers in parallel. Pressure is controlled with a buffer tank two three way solenoid value upstream and down stream a compressor and a supercharger. A checking board allows continuous monitoring of circuit tightness [fr

  17. Corrosion studies and recommendation of alloys for an incinerator of glove-boxes wastes

    Devisme, F.; Garnier, M.H.

    1992-01-01

    In the framework of the development of an incineration process for high chlorinated wastes, commercial alloys have been investigated by means of parametric laboratory tests in HCl containing gas mixtures and also in field tests. Recommendations may be formulated for the three main components i.e. pyrolyser, calciner and cooler. In very low oxygen-potential atmospheres, the alloys Hastelloy C276 and Inconel 625 present the best behaviours. For the calciner, alloy Inconel 601 is more satisfactory than AISI 310 steel. As for the cooler, only the alloy Haynes 214 appears acceptable at 1100 deg C. Because of the very low stress level affecting the components, thermomechanical properties do not modify these recommendations based on corrosion behaviour

  18. Catalyst study for the decontamination of glove-boxe atmospheres containing tritium at MPC levels

    Chabot, J.; Montel, J.; Sannier, J.

    1988-01-01

    The BEATRICE loop was designed for studying the conversion of tritium at very low activity levels using catalytic oxidation followed by water trapping. The purpose is to study kinetic parameters required for the design of the NET tritium clean-up system with the two main objectives to operate without isotopic swamping and to determine the ability of efficient conversion at room temperature. From experiments carried out between 20 and 250 0 C it is concluded that two palladium/alumina and platinum/alumina catalysts are very efficient in removing tritium from contaminated gas mixtures down to a few MPC levels without isotopic swamping and even at room temperature. However at room temperature, in relation to tritium species trapped on the catalyst surface a progressive deactivation with time occurs. This phenomenon may be a concern for process efficiency and tritium inventory and best regeneration conditions have to be determined in order to demonstrate industrial feasibility of operating at room temperature

  19. REMOTE MATERIAL HANDLING IN THE YUCCA MOUNTAIN WASTE PACKAGE CLOSURE CELL AND SUPPORT AREA GLOVEBOX

    K.M. Croft; S.M. Allen; M.W. Borland

    2005-01-01

    The Yucca Mountain Waste Package Closure System (WPCS) cells provide for shielding of highly radioactive materials contained in unsealed waste packages. The purpose of the cells is to provide safe environments for package handling and sealing operations. Once sealed, the packages are placed in the Yucca Mountain Repository. Closure of a typical waste package involves a number of remote operations. Those involved typically include the placement of matched lids onto the waste package. The lids are then individually sealed to the waste package by welding. Currently, the waste package includes three lids. One lid is placed before movement of the waste package to the closure cell; the final two are placed inside the closure cell, where they are welded to the waste package. These and other important operations require considerable remote material handling within the cell environment. This paper discusses the remote material handling equipment, designs, functions, operations, and maintenance, relative to waste package closure

  20. Honeywell modular automation system computer software documentation

    Cunningham, L.T.

    1997-01-01

    This document provides a Computer Software Documentation for a new Honeywell Modular Automation System (MAS) being installed in the Plutonium Finishing Plant (PFP). This system will be used to control new thermal stabilization furnaces in HA-21I

  1. A permanently magnetized high gradient magnetic filter for glove-box cleaning and increasing HEPA filter life

    Watson, J.H.P.; Boorman, C.H.

    1991-01-01

    The purpose of this paper is to describe the structure and testing of a permanently magnetized magnetic filter on simulants for radioactive material. The experimental work was carried out at British Nuclear Fuels plc, Sellafield, England and in CEN/SCK, Mol, Belgium using Cr powder which is a good magnetic simulant for PuO 2 . The basis of the use of such a filter in the nuclear industry relies on the fact that much of the radioactive material is paramagnetic. In the last twenty years a separation technique has been developed which allows weakly paramagnetic particles of colloidal size to be separated from fluid which passes through the separator. This method is called high gradient magnetic separation (HGMS) and is accomplished by magnetizing a fine ferromagnetic wire matrix by an externally applied magnetic field. This paper describes a new approach to this problem, by using a magnetically hysteretic material to construct the ferromagnetic matrix, it has been possible to provide a magnetic field in the region of the matrix and also have a residual magnetization within the matrix. This provides extremely compact magnetic separation systems. There are some subtle differences between this separation system and conventional HGMS which makes the radial feed system, with all its advantages, almost mandatory for hysteretic HGMS

  2. Operating manual for the electrostatic glove-box prefilter installed inside the filter glove box No. 046 at Rocky Flats, Building 776

    Bergman, W.; Kaifer, R.C.; Hebard, H.D.; Taylor, R.D.; Lum, B.Y.; Boling, R.M.; Buttedahl, O.I.; Woodard, R.W.; Terada, K.

    1979-01-01

    Objective of the evaluation is to evaluate the effectiveness of the electrostatic prefilter in prolonging the life of HEPA (high-efficiency particulate-air) filters. The theory of the electrostatic filter is reviewed, and Glove Box Number 046 is described in detail, followed by a description of the electrostatic prefilter used in the present application. Engineering drawings of the electrostatic prefilter are included. The procedure for evaluating the electrostatic prefilter includes the steps for conducting five different tests: evaluating (1) the HEPA filter alone, (2 and 3) the HEPA filter with a standard prefilter treated both as disposable and reusable, and (4 and 5) the HEPA filter with the electrostatic prefilter, again treated as disposable and reusable. Procedures for flowmeter calibrations and measurements of particle-size distributions are also included. Long-term maintenence of the system during the evaluation program is outlined, and estimates of component durability are given. An electrical engineering safety note describes the high-voltage operational hazard of the electrostatic prefilter and the testing of safety devices

  3. Study of plutonium fire extinction in glove-boxes; Etude sur l'extinction des feux de plutonium en boites a gants

    Boisson, H; Chappellier, A; Debiar, A; Savornin, J [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1965-07-01

    The report concerns attempts to extinguish fire in uranium - chosen as a basis for comparison - and in plutonium, these being contained in glove boxes. The extinguishing powders TEC and MG 10 were tried and compared. The operator used in plastic bags. The metal was dealt with respectively in the form of billets, compact chips and finally thin shavings. In each case fire control was without difficulty. One must allow a certain time for cooling. The powder MG 10 showed very good results. Moreover, the trials proved that densely packed shavings are a very real security factor. The interior lay-out of the glove boxes ought, in order to facilitate further manipulations, be such as to render extinction as easy as possible should the need arise. (authors) [French] II s'agit d'un compte rendu d'essais d'extinction sur feux d'uranium - pris comme base de comparaison - et de plutonium, en boites a gants. Sont utilisees et comparees les poudres extinctrices TEC et MG 10. Elles sont employees par l'operateur en sachets de plastique. Le metal est pris successivement sous forme de billettes, de copeaux compactes, enfin de tournures fines. L'intervention est aisee dans tous les cas; il faut laisser un certain temps de refroidissement. La poudre MG 10 a donne de tres bons resultats, Les essais ont montre, de plus, que le compactage des copeaux est un facteur reel de securite. L'agencement interieur des boites a gants pour les manipulations a venir, devrait tenir compte de cette facilite d'extinction afin de la rendre la plus aisee possible en cas de besoin. (auteurs)

  4. Resuspension of uranium-plutonium oxide particles from burning Plexiglas

    Pickering, S.

    1987-01-01

    Nuclear fuel materials such as Uranium-Plutonium oxide must be handled remotely in gloveboxes because of their radiotoxicity. These gloveboxes are frequently constructed largely of combustible Plexiglas sheet. To estimate the potential airborne spread of radioactive contamination in the event of a glovebox fire, the resuspension of particles from burning Plexiglas was investigated. (author)

  5. An improved ashing procedure for biologic sample

    Zongmei, Wu [Zhejiang Province Enviromental Radiation Monitoring Centre (China)

    1992-07-01

    The classical ashing procedure in muffle was modified for biologic samples. In the modified procedure the door of muffle was open in the duration of ashing process, the ashing was accelerated and the ashing product quality was comparable to that the classical procedure. The modified procedure is suitable for ashing biologic samples in large batches.

  6. An improved ashing procedure for biologic sample

    Wu Zongmei

    1992-01-01

    The classical ashing procedure in muffle was modified for biologic samples. In the modified procedure the door of muffle was open in the duration of ashing process, the ashing was accelerated and the ashing product quality was comparable to that the classical procedure. The modified procedure is suitable for ashing biologic samples in large batches

  7. Tungsten-rhenium composite tube fabricated by CVD for application in 18000C high thermal efficiency fuel processing furnace

    Svedberg, R.C.; Bowen, W.W.; Buckman, R.W. Jr.

    1980-04-01

    Chemical Vapor Deposit (CVD) rhenium was selected as the muffle material for an 1800 0 C high thermal efficiency fuel processing furnace. The muffle is exposed to high vacuum on the heater/insulation/instrumentation side and to a flowing argon-8 V/0 hydrogen gas mixture at one atmosphere pressure on the load volume side. During operation, the muffle cycles from room temperature to 1800 0 C and back to room temperature once every 24 hours. Operational life is dependent on resistance to thermal fatigue during the high temperature exposure. For a prototypical furnace, the muffle is approximately 13 cm I.D. and 40 cm in length. A small (about one-half size) rhenium closed end tube overcoated with tungsten was used to evaluate the concept. The fabrication and testing of the composite tungsten-rhenium tube and prototypic rhenium muffle is described

  8. FULL LENGTH RESEARCH ARTICLE Jauro et al. (2008) SWJ:79 ...

    Dr. Ahmed

    environmental, economic, technological and human health impacts. (Renton 1982 ... 5g of the sample was weighed into a platinum crucible and ignited in a muffle furnace .... also enhances the risk of lung cancer (Lenntech 2008). Magnesium.

  9. Synthesis, characterization and comparison of Li{sub 1,05}M{sub 0,02}Mn{sub 1,98}O{sub 4} (M = Al{sup 3+} or + Ga{sup 3+}) obtained by calcination in muffle and microwave; Sintese, caracterizacao e comparacao dos Li{sub 1,05}Mn{sub 1,98}M{sub 0,02}O{sub 4} (M= Al{sup 3+} ou GA{sup 3+}) obtidos por calcinacao em mufla e microondas

    Santana, L.K.; Canobre, S.C.; Amaral, F.A., E-mail: fabioamaral@yahoo.com.br [Universidade Federal de Uberlandia (UFU), MG (Brazil). Instituto de Quimica. Laboratorio de Armazenamento de Energia e Tratamento de Efluentes

    2014-07-01

    Due to the economic and environmental importance of using LiMn{sub 2}O{sub 4} as cathode batteries, the goal of this work was to synthesize LiMn{sub 2}O{sub 4} doped and undoped, comparing methods of calcination kiln and microwave. The precursors were obtained by Pechini method. The resulting samples were structurally characterized by XRD, morphology by SEM and area by B.E.T. XRD results were compared to card JCPDS 35-0782 regarding the pure LiMn{sub 2}O{sub 4}. The DRX results indicate that the calcination furnace was more efficient for obtaining doped oxides. However, the use of microwave was effective for rapid attainment of non-doped spinel close to those found for the pure spinel structural features. The surface area values confirm the existence of clusters and particles with nanometric features. Oxides synthesized in both procedures showed small, organized and highly crystalline particles, demonstrating the efficiency of the methodology and Pechini methods of calcination compared. (author)

  10. Ultracold Field Gradient Magnetometry and Transport to Study Correlated Topological Phases

    2016-10-01

    MIT) 77 Massachusetts Ave. NE18-901 Cambridge , MA 02139 -4307 ABSTRACT Number of Papers published in peer-reviewed journals: Number of Papers published...group of the PI and the subfield of new correlated topological phases. List of Illustrations Figure 1 – View of MBE and Glovebox System Figure... Illustrations   Figure 1 – View of MBE and Glovebox System  Figure 2 – View of Glovebox, MBE, and Dilution Refrigerator System    Statement of Problems Studied  To

  11. Plutonium production in a remote cell

    Maddux, E.P.; Purcell, J.A.

    1987-01-01

    Production of 239 Pu metal has traditionally been carried out in glovebox enclosures for protection of operating personnel and the environment. With the advent of more stringent federal regulations for protecting personnel, the environment, and security of special nuclear materials, it is proposed that plutonium be processed in a totally remote environment using automated work stations and robotic materials transfer and equipment maintenance. At the Savannah River Plant, the existing plutonium production facility is a batch-type glovebox operation built in the 1950s. A viable alternative to restoration of the existing glovebox operation is to provide a facility that uses remote cell operation

  12. Duct Remediation Program: Engineered access research and construction

    Beckman, T.D.; Davis, M.M.; Karas, T.M.

    1992-01-01

    The Rocky Flats Plant, Duct Remediation mission concentrated on removing Plutonium Oxide from the process ductwork in the primary Plutonium processing facility. When possible, remediation took place from existing process gloveboxes. Fifteen locations were identified, however, that required accessing duct runs where no process gloveboxes existed. The building's second floor utility areas had many locations where long, inaccessible duct runs were prevalent. Consequently, an extensive program for design, procurement and construction was initiated to contain and isolate ducts for penetration when existing glovebox sites were not present

  13. W-026, acceptance test report manipulator system

    Watson, T.L.

    1997-01-01

    The purpose of the WRAP Manipulator System Acceptance Test Plan (ATP) is to verify that the 4 glovebox sets of WRAP manipulator components, including rail/carriage, slave arm, master controller and auxiliary equipment, meets the requirements of the functional segments of 14590 specification. The demonstration of performance elements of the ATP are performed as a part of the Assembly specifications. Manipulator integration is integrated in the performance testing of the gloveboxes. Each requirement of the Assembly specification will be carried out in conjunction with glovebox performance tests

  14. The radiological evaluation of a prototype posting-in hatch under conditions of high alpha activity

    Smith, D.I.; Hollick, R.C.

    1987-07-01

    A prototype posting-in hatch, mounted vertically in the top panel of a highly active glovebox has been radiologically evaluated in the Fuels Laboratory, AEEW. This simple, air-lock type system of 100 mm diameter has pneumatically operated and interlocked lids and a low velocity, inward purge, supplied by the glovebox depression. The hatch proved extremely reliable and very easy to operate. More than 1200 simulated posting movements were carried out and a > 8 order of magnitude reduction in aerosol concentration was recorded from the active glovebox to the monitoring environment. (author)

  15. Plutonium active operation of the Winfrith modular containment system

    Sanders, M.J.; Pengelly, M.G.A.; McSherry, K.

    1985-01-01

    Three gloveboxes contaminated with plutonium have been dismantled inside the Winfrith Modular Containment System. This system is a portable, demountable pressurised suit area with its own filters and shower entry tunnel. Details of the operation are given. (U.K.)

  16. 77 FR 11112 - Proposed Approval of the Central Characterization Project's Remote-Handled Transuranic Waste...

    2012-02-24

    ... debris waste from the FB-Line at SRS. This waste was generated by glovebox operations, decontamination... summary category group solids (S3000) or soils and gravel (S4000) is characterized for WIPP disposal; and...

  17. Crystal Growth of New Radiation Detector Materials in Microgravity, Phase I

    National Aeronautics and Space Administration — RMD proposes to conduct a series of crystal growth experiments on the International Space Station in the SUBSA furnace inside the MSG glovebox to grow crystals of...

  18. Glove boxes. Dimensions and requirements. Draft

    1985-07-01

    The standard is to be applied to work done in glove-boxes, whereby either the personnel need to be protected from the damaging effects of the materials being handled, or the materials from the effects of the environment. It is to be applied to glove-boxes in which substances are handled which emit ionising radiation (radioactive substances). This norm is not restricted to glove-boxes in which processes are carried out on a technique scale. In accordance with this norm, only those pressures and temperatures are allowed to be present in the glove-boxes, that do not offer significantly from the work areas. Alongside the stipulations of this standard regard is also always to be taken of the regulations in the radiation protection ordinance. (orig./HP) [de

  19. Development history of crimp shear tools. Item D11 Decommissioning Group

    Farmer, A.K.

    1988-02-01

    This report gives information on the continuing development of a range of crimp/shear tools aimed at separating items of radioactive plant, eg, gloveboxes, from a variety of service pipelines which could also be internally contaminated. (author)

  20. Plutonium metal burning facility

    Hausburg, D.E.; Leebl, R.G.

    1977-01-01

    A glove-box facility was designed to convert plutonium skull metal or unburned oxide to an oxide acceptable for plutonium recovery and purification. A discussion of the operation, safety aspects, and electrical schematics are included

  1. CSER 99-001: PFP LAB Dentirating calciner

    MILLER, E.M.; DOBBIN, K.D.

    1999-01-01

    A criticality safety evaluation report was prepared for the Plutonium Finishing Plant (PFP) laboratory denigrating calciner, located in Glovebox 188-1, that converts Pu(NO 3 ) 4 solutions to the high fired stable oxide PuO 2 . Fissile mass limits and volume limits are set for the glovebox for testing operations and training operators using only nitric acid feed to a plutonium oxide bed in the calciner

  2. Safe handling of kilogram amounts of fuel-grade plutonium and of gram amounts of plutonium-238, americium-241 and curium-244

    Louwrier, K.P.; Richter, K.

    1976-01-01

    During the past 10 years about 600 glove-boxes have been installed at the Institute for Transuranium Elements at Karlsruhe. About 80% of these glove-boxes have been designed and equipped for handling 100-g to 1-kg amounts of 239 Pu containing 8-12% 240 Pu (low-exposure plutonium). A small proportion of the glove-boxes is equipped with additional shielding in the form of lead sheet or lead glass for work with recycled plutonium. In these glove-boxes gram-amounts of 241 Am have also been handled for preparation of Al-Am targets using tongs and additional shielding inside the glove-boxes themselves. Water- and lead-shielded glove-boxes equipped with telemanipulators have been installed for routine work with gram-amounts of 241 Am, 243 Am and 244 Cm. A prediction of the expected radiation dose for the personnel is difficult and only valid for a preparation procedure with well-defined preparation steps, owing to the fact that gamma dose-rates depend strongly upon proximity and source seize. Gamma radiation dose measurements during non-routine work for 241 Am target preparation showed that handling of gram amounts leads to a rather high irradiation dose for the personnel, despite lead or steel glove-box shielding and shielding within the glove-boxes. A direct glove-hand to americium contact must be avoided. For all glove-handling of materials with gamma radiation an irradiation control of the forearms of the personnel by, for example, thermoluminescence dosimeters is necessary. Routine handling of americium and curium should be executed with master-slave equipment behind neutron and gamma shielding. (author)

  3. Investigating the potential of Aucoumea klaineana Pierre sapwood ...

    vainqueuer

    2016-11-16

    Nov 16, 2016 ... process (Harris et al., 1945). Advantages and disadvantages of lignocellulose pretreatment process for ethanol cellulose production with sulfuric acid have been extensively ... ceramic ashing crucible, and introduced in a muffle furnace ... At the termination of the pyrolysis, the ceramic ashing crucible.

  4. Preparation and characterization of activated carbons from albizia ...

    Activated carbon was prepared from the pods of Albizia saman for the purpose of converting the waste to wealth. The pods were thoroughly washed with water to remove any dirt, air- dried and cut into sizes of 2-4 cm. The prepared pods were then carbonised in a muffle furnace at temperatures of 4000C, 5000C, 6000C ...

  5. The behavior of heavy metals in the process of desulfurization of Brazilian coal combustion gases by the addition of limestone

    Sebag M.G.

    2001-01-01

    Full Text Available The concentrations of heavy metals in two kinds of Brazilian coals at 100° C (acid digestion and at 850° C were studied (ashes the obtained in muffle furnace with and without addition of limestone. Data were analyzed by flame atomic absorption, using the air acetylene flame. For Pb, Zn, Ni, Mn and Cu the metal concentration obtained the acid digestion were higher than metal concentration were obtained in tests in the muffle furnace. This behavior observed in the muffle furnace occurs because these metals are fixed in stable sulfated compounds in the ashes, which are difficult to dissociate at flame temperature, and also due to the volatile character of the metals, mainly Pb and Zn. There was a constant concentration in the ashes in of Cr the acid digestion and muffle furnace tests. Results from tests using an XRD apparatus indicated, he formation of sulfated compounds in the ashes for both. coals. The analysis using microprobe electronic showed retention of metals like Ni, Mn, Cu, Fe, Ti and Ca. For both coals, the low mobility of most of the metals studied occured due to the alkaline pH of sulfated ashes. These metals in the ash from coal combustion in fluidized bed reactor were also studied and showed similar results, enabling a scale-up to pilot scale.

  6. THE SHAPING OF SOME LIFTING AND TRANSPORTATION SYSTEMS, USING AUTODESK INVENTOR

    URSE Cătălin

    2011-11-01

    Full Text Available The paper presents, through the use of Autodesk Inventor software package, several mechanisms from the structure of lifting and transportation machines, in this case lifting system with winch operated by screw,lifting system type with muffle with hook, respectively bridge crane type.

  7. Auditory and Respiratory Health Disorders Among Workers in an ...

    For early detection of respiratory and auditory disorders, spirometry and audiometry should be included in the periodic medical examination. Accurate health records of workers, so, those at risk can be monitored, and/or pre-placed. Using personal protective equipments especially masks and ear muffles as well as prohibit ...

  8. The determination, by x-ray-fluorescence spectrometry, of gold, silver, and base metals on activated carbon

    Wall, G.; Jacobs, J.J.; Dixon, K.

    1980-01-01

    The method proposed involves ashing of the sample at a low temperature in a muffle furnace, mixing of the ash with alumina and boric acid in a Siebtechnik mill, and briquetting of the mixture. The elements are measured in the briquette by the use of x-ray fluorescence spectrometry. The detailed laboratory method is given in an appendix [af

  9. Sintering furnace for remote fuel fabrication

    Bowen, W.W.

    1978-10-01

    Component testing and evaluation of a chemical vapor deposition Re/W muffle has been initiated. Hydrogen permeation testing and thermal cycling behavior will be evaluated. Fabrication of prototype 10-12 Kg furnace is scheduled for completion late in 1979, at which time testing of the system will be initiated

  10. Effectiveness of Nigerian Bamboo Activated with Different Activating ...

    The effectiveness of Nigerian Bamboo activated with different activating agents on the adsorption of BTX was investigated. A series of activated carbons was prepared from Nigerian bamboo, carbonized at 400oC – 500oC and impregnated with different concentrations of four acids at 800oC in a muffle furnace for 2 hours.

  11. Polymorph-dependent titanium dioxide nanoparticle dissolution in acidic and alkali digestions

    Multiple polymorphs (anatase, brookite and rutile) of titanium dioxide nanoparticles (TiO2-NPs) with variable structures were quantified in environmental matrices via microwave-based hydrofluoric (HF) and nitric (HNO3) mixed acid digestion and muffle furnace (MF)-based potassium ...

  12. Thermogravimetric and kinetic study of methylolmelamine ...

    Some salient properties of cotton cellulose which requires it to be treated with additives to improve its versatility were examined taken into consideration, the molecular structure. Thermogravimetric analysis of the cotton fabric and the treated cotton fabric were carried out in an improvised muffled furnace. The result was in ...

  13. Insights into the effect of structure-directing agents on structural ...

    properties of mesoporous carbon for polymer electrolyte fuel cells. A ARUNCHANDER ..... lowed by sintering in a muffle furnace at 350◦C for 30 min. For the catalyst ..... Su F B, Zeng J H, Bao X Y, Yu Y S, Lee J Y and Zhao X S. 2005 Chem.

  14. Loss on Ignition Furnace Acceptance and Operability Test Procedure

    JOHNSTON, D.C.

    2000-01-01

    The purpose of this Acceptance Test Procedure and Operability Test Procedure (ATP/OTP)is to verify the operability of newly installed Loss on Ignition (LOI) equipment, including a model 1608FL CMTM Furnace, a dessicator, and balance. The operability of the furnace will be verified. The arrangement of the equipment placed in Glovebox 157-3/4 to perform LOI testing on samples supplied from the Thermal Stabilization line will be verified. In addition to verifying proper operation of the furnace, this ATP/OTP will also verify the air flow through the filters, verify a damper setting to establish and maintain the required differential pressure between the glovebox and the room pressure, and test the integrity of the newly installed HEPA filter. In order to provide objective evidence of proper performance of the furnace, the furnace must heat 15 crucibles, mounted on a crucible rack, to 1000 C, according to a program entered into the furnace controller located outside the glovebox. The glovebox differential pressure will be set to provide the 0.5 to 2.0 inches of water (gauge) negative pressure inside the glovebox with an expected airflow of 100 to 125 cubic feet per minute (cfm) through the inlet filter. The glovebox inlet G1 filter will be flow tested to ensure the integrity of the filter connections and the efficiency of the filter medium. The newly installed windows and glovebox extension, as well as all disturbed joints, will be sonically tested via ultra probe to verify no leaks are present. The procedure for DOS testing of the filter is found in Appendix A

  15. Loss on Ignition Furnace Acceptance and Operability Test Procedure

    JOHNSON, D.C.

    2000-06-01

    The purpose of this Acceptance Test Procedure and Operability Test Procedure (ATP/OTP)is to verify the operability of newly installed LOI equipment, including a model 1608FL CM{trademark} Furnace, a dessicator, and balance. The operability of the furnace will be verified. The arrangement of the equipment placed in Glovebox 157-3/4 to perform Loss on Ignition (LOI) testing on samples supplied from the Thermal Stabilization line will be verified. In addition to verifying proper operation of the furnace, this ATP/OTP will also verify the air flow through the filters, verify a damper setting to establish and maintain the required differential pressure between the glovebox and the room pressure, and test the integrity of the newly installed HEPA filter. In order to provide objective evidence of proper performance of the furnace, the furnace must heat 15 crucibles, mounted on a crucible rack, to 1000 C, according to a program entered into the furnace controller located outside the glovebox. The glovebox differential pressure will be set to provide the 0.5 to 2.0 inches of water (gauge) negative pressure inside the glovebox with an airflow of 100 to 125 cubic feet per minute (cfm) through the inlet filter. The glovebox inlet Glfilter will he flow tested to ensure the integrity of the filter connections and the efficiency of the filter medium. The newly installed windows and glovebox extension, as well as all disturbed joints, will be sonically tested via ultra probe to verify no leaks are present. The procedure for DOS testing of the filter is found in Appendix A.

  16. Robotic requirements for plutonium handling automation

    Heywood, A.C.; Armantrout, G.A.

    1990-01-01

    While over 200,000 robots are in manufacturing service worldwide, only two are in use for the handling of plutonium in a glovebox. The difficulties of applying robotics to the glovebox environment include limited access for service and maintenance, radiation damage to electronics and insulators, and abrasion damage to bearings and sliding surfaces. The limited volume of the glovebox environment, and the need to handle heavy workloads, and the need to maximize work volume dictates the use of an overhead gantry system. This paper discusses how the application of such a system will require a robot with extensive safety features, a high degree of flexibility to perform a variety of tasks, and high reliability coupled with an easily serviced design. Substantial challenges exist in control system design, sensor and operator integration, and programming to achieve these goals

  17. Scattering profiles of sparks and combustibility of filter against hot sparks

    Asazuma, Shinichiro; Okada, Takashi; Kashiro, Kashio

    2004-01-01

    The glove-box dismantling facility in the Plutonium Fuel Production Facility is developed to dismantle after-service glove-boxes with remote-controlled devices such as an arm-type manipulator. An abrasive wheel cutter, which is used to size reduce the gloveboxes, generates sparks during operation. This dispersing spark was a problem from the fire prevention point of view. A suitable spark control measures for this operation were required. We developed panels to minimize spark dispersion, shields to prevent the income of sparks to the pre-filter, and incombustible pre-filters. The equipment was tested and effectiveness was confirmed. This report provides the results of these tests. (author)

  18. Plan for the Initiation of HA-211 Furnace Operations at the Plutonium Finishing Plan (PFP)

    WILLIS, H.T.

    2000-01-01

    This plan provides a phased approach authorizing the use of three additional muffle furnaces for thermal stabilization. Achievement of Thermal Stabilization mission elements require the installation and startup of three additional muffle furnaces for the thermal stabilization of plutonium and plutonium bearing materials at the Plutonium Finishing Plant (PFP). The release to operate these additional furnaces will require an Activity Based Startup Review. The conduct of the Activity Based Startup Review (ABSR) was approved by Fluor Daniel Hanford on October 15, 1999. This plan has been developed with the objective of identifying those activities needed to guide the controlled startup of five furnaces from authorization to unrestricted operations by adding the HA-211 furnaces in an orderly and safe manner after the approval to Startup has been given

  19. The Rocky Flats Decontamination and Decommissioning (D and D) Challenge

    Parker, A.M.; Mathis, B.W.; Stevens, J.L.

    1999-01-01

    At the Rocky Flats Environmental Technology Site (RFETS), the D and D task is enormous. Tons of plutonium has been processed over the years in approximately 1,000 gloveboxes, This represents nearly half of the gloveboxes in the DOE complex. In addition, more than a thousand tanks of various designs, with miles of associated piping, supported the processes. A wide variety of operations were performed at RFETS, including aqueous processing, pyrophoric processing, hydriding and dehydriding, metal casting, and machining of plutonium. Various materials have been handled at the facility, including plutonium, uranium, americium, tantalum, beryllium, chloride salts, and various acids and solvents. Significant amounts of plutonium residues remain in inaccessible equipment in the facilities, which create criticality safety issues. Some of the plutonium has been at RFETS for many years, and there is significant in-growth of americium, a decay product that emits gamma radiation, which potentially increases exposure to the workers. The size reduction portion of the D and D will be difficult and costly. The gloveboxes and tanks are constructed of stainless steel, frequently with lead shielding or double walls that hold water for neutron shielding. Window mountings, glove port rings, site gages, bolted flanges, and various penetrations reinforce the walls. Tanks may be filled with berated glass rings for criticality control, or double walled to hold the process fluid in the space between walls. The gloveboxes and tanks are generally tall enough to require workers to stand on scaffolding or platforms to perform D and D. Gloveboxes and tanks were individually constructed over a span of many years with evolving design specifications; therefore, most gloveboxes are unique and few tank designs are duplicated in more than pairs. This paper describes the cultural transition and technical approaches taken for D and D at RFETS to achieve 2006 closure. Specific emphasis is placed on

  20. Strontium-90 and cesium-137 in total diet; from June 1980 to Dec. 1980

    1980-01-01

    A full one day ordinary diet including three meals, water, tea and other in-between snacks for five persons was collected as a sample of ''total diet''. The sample in a large stainless steel pan was carbonized carefully by direct application of gas flame, and was transferred to a porcelain dish and then ashed at 500 0 C in an electric muffle furnace. The results obtained from June 1980 to December 1980 were shown in a table. (J.P.N.)

  1. Strontium-90 and cesium-137 in total diet; from Nov. 1978 to Dec. 1979

    1980-01-01

    A full one day ordinary diet including three meals, water, tea and other in-between snacks for five persons was collected as a sample of ''total diet''. The sample in a large stainless steel pan was carbonized carefully by direct application of gas flame, and was transferred to a porcelain dish and then ashed at 500 0 C in an electric muffle furnace. The results obtained from November 1978 to December 1979 were shown in a table. (J.P.N.)

  2. Strontium-90 and cesium-137 in total diet; from Aug. 1979 to Jul. 1980

    1980-01-01

    A full one day ordinary diet including three meals, water, tea and other in-between snacks for five persons was collected as a sample of ''total diet''. The sample in a large stainless steel pan was carbonized carefully by direct application of gas flame, and was transferred to a porcelain dish and then ashed at 500 0 C in an electric muffle furnace. The results obtained from August 1979 to July 1980 were shown in a table. (J.P.N.)

  3. Effect of Microstructure on the Wear Behavior of Heat Treated SS-304 Stainless Steel

    S. Kumar

    2016-01-01

    Sliding wear characteristics of some heat treated SS-304 stainless steel against EN-8 steel in dry condition have been studied in the present experimental work. Samples of SS-304 stainless steel have been heated in a muffle furnace in desired temperature and allowed to dwell for two hours. The heated specimen are then cooled in different media namely inside the furnace, open air, cutting grade oil (grade 44) and water at room temperature to obtain different grades of heat treatment. Microstr...

  4. Procedures for Handling and Chemical Analysis of Sediment and Water Samples,

    1981-05-01

    spc i fica 1y (ei.;3 ,ed fotr m’erury analys i may be s r1)A 1 tit the -Ltumic ’ibl;orption spetIopho tometer. The flow cell -lh)iu 1w ’ p:3proxi...approximately 14 by 10 by 2-1/2 in. Oven, drying Muffle furnace Desiccator Crucibles, porcelain, squat form, Size 2 Omni or Sorvall mixer with chamber of

  5. Laboratory robotics systems at the Savannah River Laboratory

    Dyches, G.M.; Burkett, S.D.

    1983-01-01

    Many analytical chemistry methods normally used at the Savannah River site require repetitive procedures and handling of radioactive and other hazardous solutions. Robotics is being investigated as a method of reducing personnel fatigue and radiation exposure and also increasing product quality. Several applications of various commercially available robot systems are discussed involving cold (nonradioactive) and hot (radioactive) sample preparations and glovebox waste removal. Problems encountered in robot programming, parts fixturing, design of special robot hands and other support equipment, glovebox operation, and operator-system interaction are discussed. A typical robot system cost analysis for one application is given

  6. Los Alamos DP West Plutonium Facility decontamination project, 1978-1981

    Garde, R.; Cox, E.J.; Valentine, A.M.

    1982-09-01

    The DP West Plutonium Facility operated by the Los Alamos National Laboratory, Los Alamos, New Mexico was decontaminated between April 1978 and April 1981. The facility was constructed in 1944 to 1945 to produce plutonium metal and fabricate parts for nuclear weapons. It was continually used as a plutonium processing and research facility until mid-1978. Decontamination operations included dismantling and removing gloveboxes and conveyor tunnels; removing process systems, utilities, and exhaust ducts; and decontaminating all remaining surfaces. This report describes glovebox and conveyor tunnel separations, decontamination techniques, health and safety considerations, waste management procedures, and costs of the operation

  7. Savannah River Site Bagless Transfer - What Have We Learned?

    Wong, J.W.

    2001-01-01

    Conventional glovebox techniques for handling radioactive material include the use of plastic sleeving for ''bagging out'' material in order to remove it from the glovebox. This method has been used for many years, and has proven very effective when implemented by trained operators. One drawback to this method is that it is not suitable for removal of material for long-term storage, due to radiolytic decomposition of the plastic. In order to comply with long term storage criteria, engineers at the Savannah River Site developed an alternative process for removal of radioactive material known as ''bagless transfer''

  8. Analysis of Zinc 65 Contamination after Vacuum Thermal Process

    Korinko, Paul S.; Tosten, Michael H.

    2013-01-01

    Radioactive contamination with a gamma energy emission consistent with 65 Zn was detected in a glovebox following a vacuum thermal process. The contaminated components were removed from the glovebox and subjected to examination. Selected analytical techniques were used to determine the nature of the precursor material, i.e., oxide or metallic, the relative transferability of the deposit and its nature. The deposit was determined to be borne from natural zinc and was further determined to be deposited as a metallic material from vapor

  9. Organic Contamination Baseline Study: In NASA JSC Astromaterials Curation Laboratories. Summary Report

    Calaway, Michael J.

    2013-01-01

    In preparation for OSIRIS-REx and other future sample return missions concerned with analyzing organics, we conducted an Organic Contamination Baseline Study for JSC Curation Labsoratories in FY12. For FY12 testing, organic baseline study focused only on molecular organic contamination in JSC curation gloveboxes: presumably future collections (i.e. Lunar, Mars, asteroid missions) would use isolation containment systems over only cleanrooms for primary sample storage. This decision was made due to limit historical data on curation gloveboxes, limited IR&D funds and Genesis routinely monitors organics in their ISO class 4 cleanrooms.

  10. Simplification of an MCNP model designed for dose rate estimation

    Laptev, Alexander; Perry, Robert

    2017-09-01

    A study was made to investigate the methods of building a simplified MCNP model for radiological dose estimation. The research was done using an example of a complicated glovebox with extra shielding. The paper presents several different calculations for neutron and photon dose evaluations where glovebox elements were consecutively excluded from the MCNP model. The analysis indicated that to obtain a fast and reasonable estimation of dose, the model should be realistic in details that are close to the tally. Other details may be omitted.

  11. Simplification of an MCNP model designed for dose rate estimation

    Laptev Alexander

    2017-01-01

    Full Text Available A study was made to investigate the methods of building a simplified MCNP model for radiological dose estimation. The research was done using an example of a complicated glovebox with extra shielding. The paper presents several different calculations for neutron and photon dose evaluations where glovebox elements were consecutively excluded from the MCNP model. The analysis indicated that to obtain a fast and reasonable estimation of dose, the model should be realistic in details that are close to the tally. Other details may be omitted.

  12. 19 mm ballistic range: a potpourri of techniques and recipes

    Carpluk, G.T.

    1975-01-01

    The expansion of ballistic gun range facilities at LLL has introduced state-of-the-art diagnostic techniques to glovebox-enclosed ballistic guns systems. These enclosed ballistic ranges are designed for the study of one-dimensional shock phenomena in extremely toxic material such as plutonium. The extension of state-of-the-art phtographic and interferometric diagnostic systems to glovebox-enclosed gun systems introduces new design boundaries and performance criteria on optical and mechanical components. A technique for experimentally evaluating design proposals is illustrated, and several specific examples (such as, target alignment, collateral shrapnel damage, and soft recovery) are discussed

  13. Los Alamos DP West Plutonium Facility decontamination project

    Garde, R.; Cox, E.J.; Valentine, A.M.

    1982-01-01

    The DP West Plutonium Facility operated by the Los Alamos National Laboratory, Los Alamos, New Mexico, was decontaminated between April 1978 and April 1981. The facility was constructed in 1944 to 1945 to produce plutonium metal and fabricate parts for nuclear weapons. It was continually used as a plutonium processing and research facility until mid-1978. Decontamination operations included dismantling and removing gloveboxes and conveyor tunnels; removing process systems, utilities, and exhaust ducts; and decontaminating all remaining surfaces. This report describes glovebox and conveyor tunnel separations, decontamination techniques, health and safety considerations, waste management procedures, and costs of the operation

  14. A MODULAR ACTUATOR ARCHITECTURE FOR ROBOTIC APPLICATIONS

    None

    2001-07-01

    The United States Department of Energy (DOE) Complexes perform numerous hazardous material handling operations within the confines of a glovebox. The DOE is continuing to seek more efficient and safer means of handling these materials inside gloveboxes rather than the conventional, labor-intensive method through lead lined gloves. The use of glovebox automation technology will also be critical to the DOE in its efforts to comply with its mandated ALARA principles in handling the hazardous materials associated with the cleanup process. Operations associated with materials processing in a glovebox are similar to many industrial tasks, but the unique glovebox environment and Plutonium material properties create a unique set of challenges for conventional automation machinery. Such properties include: Low to moderate levels of ionizing radiation, high abrasiveness, corrosiveness, pyrophoric tendencies, rapid dispersal and permeation of environment, diffuses quickly, and possible incompatible material interaction. The glovebox presents the following challenges: existing gloveboxes may not be readily altered or even modified at all, complex mechanical operations for maintenance and repair are difficult or impossible through gloves, failed equipment may not be removed easily or at all. If a broken piece of equipment cannot be bagged-out through a glove port (approximately 216 mm (8 1/2 inch) diameter) it must remain in place. Broken equipment obstructs further operations. If it renders the entire glovebox unusable, a significant volume of waste is generated and an expensive system must be disposed of and replaced. A moderate sized glovebox alone costs between $250,000 and $500,000 and an equipment malfunction, which penetrates the glovebox and exposes the room to Plutonium or other toxic materials, is catastrophic. In addition to the human exposure issues, cleanup can easily run into the millions of dollars. A solution to the issues described above is ARM Automation Inc

  15. A MODULAR ACTUATOR ARCHITECTURE FOR ROBOTIC APPLICATIONS

    None

    2001-01-01

    The United States Department of Energy (DOE) Complexes perform numerous hazardous material handling operations within the confines of a glovebox. The DOE is continuing to seek more efficient and safer means of handling these materials inside gloveboxes rather than the conventional, labor-intensive method through lead lined gloves. The use of glovebox automation technology will also be critical to the DOE in its efforts to comply with its mandated ALARA principles in handling the hazardous materials associated with the cleanup process. Operations associated with materials processing in a glovebox are similar to many industrial tasks, but the unique glovebox environment and Plutonium material properties create a unique set of challenges for conventional automation machinery. Such properties include: Low to moderate levels of ionizing radiation, high abrasiveness, corrosiveness, pyrophoric tendencies, rapid dispersal and permeation of environment, diffuses quickly, and possible incompatible material interaction. The glovebox presents the following challenges: existing gloveboxes may not be readily altered or even modified at all, complex mechanical operations for maintenance and repair are difficult or impossible through gloves, failed equipment may not be removed easily or at all. If a broken piece of equipment cannot be bagged-out through a glove port (approximately 216 mm (8 1/2 inch) diameter) it must remain in place. Broken equipment obstructs further operations. If it renders the entire glovebox unusable, a significant volume of waste is generated and an expensive system must be disposed of and replaced. A moderate sized glovebox alone costs between $250,000 and $500,000 and an equipment malfunction, which penetrates the glovebox and exposes the room to Plutonium or other toxic materials, is catastrophic. In addition to the human exposure issues, cleanup can easily run into the millions of dollars. A solution to the issues described above is ARM Automation Inc

  16. A Novel and Cost Effective Approach to the Decommissioning and Decontamination of Legacy Glove Boxes - Minimizing TRU Waste and Maximizing LLW Waste - 13634

    Pancake, Daniel; Rock, Cynthia M.; Creed, Richard [Argonne National Laboratory, 9700 South Cass Avenue, Lemont, IL 60439 (United States); Donohoue, Tom; Martin, E. Ray; Mason, John A. [ANTECH Corporation 9050 Marshall Court, Westminster, CO, 80031 (United States); Norton, Christopher J.; Crosby, Daniel [Environmental Alternatives, Inc., 149 Emerald Street, Suite R, Keene, NH 03431 (United States); Nachtman, Thomas J. [InstaCote, Inc., 160 C. Lavoy Road, Erie, MI, 48133 (United States)

    2013-07-01

    This paper describes the process of decommissioning two gloveboxes at the Argonne National Laboratory (ANL) that were employed for work with plutonium and other radioactive materials. The decommissioning process involved an initial phase of clearing tools and materials from the glove boxes and disconnecting them from the laboratory infrastructure. The removed materials, assessed as Transuranic (TRU) waste, were packaged into 55 gallon (200 litre) drums and prepared for ultimate disposal at the Waste Isolation Pilot Plant (WIPP) at Carlsbad New Mexico. The boxes were then sampled to determine the radioactive contents by means of smears that were counted with alpha and beta detectors to determine the residual surface contamination, especially in terms of alpha particle emitters that are an indicator of TRU activity. Paint chip samples were also collected and sent for laboratory analysis in order to ascertain the radioactive contamination contributing to the TRU activity as a fixed contamination. The investigations predicted that it may be feasible to reduce the residual surface contamination and render the glovebox structure low level waste (LLW) for disposal. In order to reduce the TRU activity a comprehensive decontamination process was initiated using chemical compounds that are particularly effective for lifting and dissolving radionuclides that adhere to the inner surfaces of the gloveboxes. The result of the decontamination process was a reduction in the TRU surface activity on the inner surfaces of the gloveboxes by four orders of magnitude in terms of disintegrations per unit area (DPA). The next phase of the process involved a comprehensive assay of the gloveboxes using a combination of passive neutron and gamma ray scintillation detectors and a shielded and collimated high purity Germanium (HPGe) gamma ray detector. The HPGe detector was used to obtain gamma ray spectra for a variety of measurement positions within the glovebox. The spectra were used to

  17. A Novel and Cost Effective Approach to the Decommissioning and Decontamination of Legacy Glove Boxes - Minimizing TRU Waste and Maximizing LLW Waste - 13634

    Pancake, Daniel; Rock, Cynthia M.; Creed, Richard; Donohoue, Tom; Martin, E. Ray; Mason, John A.; Norton, Christopher J.; Crosby, Daniel; Nachtman, Thomas J.

    2013-01-01

    This paper describes the process of decommissioning two gloveboxes at the Argonne National Laboratory (ANL) that were employed for work with plutonium and other radioactive materials. The decommissioning process involved an initial phase of clearing tools and materials from the glove boxes and disconnecting them from the laboratory infrastructure. The removed materials, assessed as Transuranic (TRU) waste, were packaged into 55 gallon (200 litre) drums and prepared for ultimate disposal at the Waste Isolation Pilot Plant (WIPP) at Carlsbad New Mexico. The boxes were then sampled to determine the radioactive contents by means of smears that were counted with alpha and beta detectors to determine the residual surface contamination, especially in terms of alpha particle emitters that are an indicator of TRU activity. Paint chip samples were also collected and sent for laboratory analysis in order to ascertain the radioactive contamination contributing to the TRU activity as a fixed contamination. The investigations predicted that it may be feasible to reduce the residual surface contamination and render the glovebox structure low level waste (LLW) for disposal. In order to reduce the TRU activity a comprehensive decontamination process was initiated using chemical compounds that are particularly effective for lifting and dissolving radionuclides that adhere to the inner surfaces of the gloveboxes. The result of the decontamination process was a reduction in the TRU surface activity on the inner surfaces of the gloveboxes by four orders of magnitude in terms of disintegrations per unit area (DPA). The next phase of the process involved a comprehensive assay of the gloveboxes using a combination of passive neutron and gamma ray scintillation detectors and a shielded and collimated high purity Germanium (HPGe) gamma ray detector. The HPGe detector was used to obtain gamma ray spectra for a variety of measurement positions within the glovebox. The spectra were used to

  18. W-026 integrated engineering cold run operational test report for balance of plant (BOP)

    Kersten, J.K.

    1998-01-01

    This Cold Run test is designed to demonstrate the functionality of systems necessary to move waste drums throughout the plant using approved procedures, and the compatibility of these systems to function as an integrated process. This test excludes all internal functions of the gloveboxes. In the interest of efficiency and support of the facility schedule, the initial revision of the test (rev 0) was limited to the following: Receipt and storage of eight overpacked drums, four LLW and four TRU; Receipt, routing, and staging of eleven empty drums to the process area where they will be used later in this test; Receipt, processing, and shipping of two verification drums (Route 9); Receipt, processing, and shipping of two verification drums (Route 1). The above listed operations were tested using the rev 0 test document, through Section 5.4.25. The document was later revised to include movement of all staged drums to and from the LLW and TRU process and RWM gloveboxes. This testing was performed using Sections 5.5 though 5.11 of the rev 1 test document. The primary focus of this test is to prove the functionality of automatic operations for all mechanical and control processes listed. When necessary, the test demonstrates manual mode operations as well. Though the gloveboxes are listed, only waste and empty drum movement to, from, and between the gloveboxes was tested

  19. A sealed enclosure of the glove box type

    Moreels, Pierre.

    1974-01-01

    The invention relates to a sealed enclosure of the glove-box type. According to the invention, the box-frame comprises: angle-bars having a right-angled cross-section, sealing joints, tightening bars and fastening means [fr

  20. Evaluation of Need and Location for a Thermogravimetric Analyzer in the Plutonium Finishing Plant (PFP) Materials Stabilization

    WILLIS, H.T.

    2000-01-01

    This plan provides an analysis for locating a TGA to support PFP Thermal Stabilization processes. The scope of this document is to evaluate the need for, and location for, installation of a TGA system as a supplement to the SFE equipment for moisture measurement in pure oxides. A location assessment for the SFE equipment was previously performed (HNF 1999). Based on that assessment, co-location of the TGA system with the SFE system is the preferred option. This would enable thermally stabilized material to be analyzed for residual moisture by either the TGA system or SFE system or both This evaluation considers glovebox locations in the PFP 234-52 Building Analytical Laboratory or operating areas for the installation of the TGA system and it's supporting equipment. This evaluation considers using existing gloveboxes along with an alternative of adding a new glovebox to existing process lines. The location evaluation criteria focuses mainly on glovebox size, with qualitative consideration of relative cost and schedule impacts associated with system implementation, radiological control, and interaction with other laboratory operations and processes. In addition, the possible co-location of a TGA furnace system with the SFE system was considered

  1. Improved HEPA Filter Technology for Flexible and Rigid Containment Barriers

    Pinson, Paul Arthur

    1998-01-01

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

  2. Remote measurements of actinide species in aqueous solutions using an optical fiber photoacoustic spectrometer

    Russo, R.E.; Robouch, P.B.; Silva, R.J.

    1990-01-01

    A photoacoustic spectrometer, equipped with an 85 meter optical fiber, was used to perform absorption measurements of lanthanide and actinide samples, located in a glovebox. The spectrometer was tested using aqueous solutions of praseodymium and americium ions; the sensitivity for remote measurements was found to be similar to that achieved in the laboratory without the fiber. 14 refs., 3 figs

  3. Atlas of atomic spectral lines of plutonium emitted by an inductively coupled plasma

    Edelson, M.C.; DeKalb, E.L.; Winge, R.K.; Fassel, V.A.

    1986-09-01

    Optical emission spectra from high-purity Pu-242 were generated with a glovebox-enclosed inductively coupled plasma (ICP) source. Spectra covering the 2280 to 7008 Angstrom wavelength range are presented along with general commentary on ICP-Pu spectroscopy.

  4. Sludge stabilization operability test report

    Lewis, W.S.

    1994-01-01

    Document provides the results of the Operability Test Procedure performed to test the operability of the HC-21C thermal stabilization process for sludge. The OTP assured all equipment functioned properly and established the baseline temperature profile for glovebox HC-21C

  5. WRAP Module 1 data management system (DMS) software design description (SDD)

    Weidert, J.R.

    1996-01-01

    Revision 2 of the Waste Receiving and Processing (WRAP) Module 1 Data Management System (DMS) Preliminary Software Design Description (PSDD) provides a high-level design description of the system. The WRAP 1 DMS is required to collect, store, and report data related to certification, tracking, packaging, repackaging, processing, and shipment of waste processed or stored at the WRAP 1 facility. The WRAP 1 DMS SDD is used as the primary medium for communication software design information. This release provides design descriptions for the following process modules produced under Phase 1 of the development effort: Receiving Drum or Box Containers Process Routing and Picklists; Waste Inventory by Location and/or Container Relationships; LLW Process Glovebox Facility Radiologic Material Inventory Check (partial); Shipping (partial production); Drum or Box NDE Operations; and Drum or Box NDA Operations Data Review (partial production). In addition, design descriptions are included for the following process modules scheduled for development under Phases 2 and 3: Activity Comment; LLW RWM Glovebox Sample Management; TRU Process Glovebox; TRU RWM Glovebox; and TRUPACT Processing. Detailed design descriptions for Reports and Facility Metrics have also been provided for in Revision 2 of this document

  6. Acceptance Test Report for the Modular Automation System (MAS) Manufactured by Honeywell Inc

    ANDERSON, D.L.

    2000-01-01

    This document details the performance of the acceptance test of the Honeywell MAS Control System for equipment to be installed in gloveboxes HA-20MB and HA-211 at a later date. Equipment that was anticipated included 6 stabilization furnaces, only three and their associated equipment were installed

  7. Process and device for leak rate measurement of an enclosure

    Giroux, J.

    1989-01-01

    The volume of a cavity, such as a cylinder and a piston, connected to the enclosure (glovebox or reactor containment shell) is varied to find back the previous pressure difference with the outside (positive or negative). Thermometers and a barometer are provided for eventual corrections [fr

  8. Design and installation of high-temperature ultrasonic measuring system and grinder for nuclear fuel containing trans-uranium elements

    Serizawa, Hiroyuki; Kikuchi, Hironobu; Iwai, Takashi; Arai, Yasuo; Kurosawa, Makoto; Mimura, Hideaki; Abe, Jiro

    2005-07-01

    A high-temperature ultrasonic measuring system had been designed and installed in a glovebox (711-DGB) to study a mechanical property of nuclear fuel containing trans-uranium (TRU) elements. A figuration apparatus for the cylinder-type sample preparation had also been modified and installed in an established glovebox (142-D). The system consists of an ultrasonic probe, a heating furnace, cooling water-circulating system, a cooling air compressor, vacuum system, gas supplying system and control system. An A/D converter board and an pulsar/receiver board for the measurement of wave velocity were installed in a personal computer. The apparatus was modified to install into the glovebox. Some safety functions were supplied to the control system. The shape and size of the sample was revised to minimize the amount of TRU elements for the use of the measurement. The maximum sample temperature is 1500degC. The performance of the installed apparatuses and the glovebox were confirmed through a series of tests. (author)

  9. Fusion Canada issue 4

    1988-05-01

    A short bulletin from the National Fusion Program. Included in this issue is a technical update on Tokamak de Varennes, a report on the Beatrix II Breeding Materials Test Program, the Tritium glovebox system for UPM, Saudi Arabia, a broad update of the Canadian Fusion Fuels Technology Project is also included. 1 fig

  10. Fusion Canada issue 4

    NONE

    1988-05-01

    A short bulletin from the National Fusion Program. Included in this issue is a technical update on Tokamak de Varennes, a report on the Beatrix II Breeding Materials Test Program, the Tritium glovebox system for UPM, Saudi Arabia, a broad update of the Canadian Fusion Fuels Technology Project is also included. 1 fig.

  11. Solid Freeform Fabrication Proceedings (9th) Held in Austin, Texas on August 10-12 1998

    1998-08-01

    through a CaFl viewport in the LENS glovebox using a 12 bit digital camera equipped with a telephoto lens and 650nm broad band filter. A total of 2048 ...SLS of investment casting shells - rapidly to metal parts 5 References König, W. (1990) Fertigungsverfahren Band 4, Massivumformung, VDI -Verlag

  12. Preparation of uranium-plutonium mixed nitride pellets with high purity

    Arai, Yasuo; Shiozawa, Ken-ichi; Ohmichi, Toshihiko

    1992-01-01

    Uranium-plutonium mixed nitride pellets have been prepared in the gloveboxes with high purity Ar gas atmosphere. Carbothermic reduction of the oxides in N 2 -H 2 mixed gas stream was adopted for synthesizing mixed nitride. Sintering was carried out in various conditions and the effect on the pellet characteristics was investigated. (author)

  13. Point kinetics modeling

    Kimpland, R.H.

    1996-01-01

    A normalized form of the point kinetics equations, a prompt jump approximation, and the Nordheim-Fuchs model are used to model nuclear systems. Reactivity feedback mechanisms considered include volumetric expansion, thermal neutron temperature effect, Doppler effect and void formation. A sample problem of an excursion occurring in a plutonium solution accidentally formed in a glovebox is presented

  14. Transuranic (TRU) waste volume reduction operations at a plutonium facility

    Cournoyer, Michael E.; Nixon, Archie E.; Fife, Keith W.; Sandoval, Arnold M.; Garcia, Vincent E.; Dodge, Robert L.

    2011-01-01

    Programmatic operations at the Los Alamos National Laboratory Plutonium Facility (TA-55) involve working with various amounts of plutonium and other highly toxic, alpha-emitting materials. The spread of radiological contamination on surfaces, airborne contamination, and excursions of contaminants into the operator's breathing zone are prevented through use of a variety of gloveboxes (the glovebox, coupled with an adequate negative pressure gradient, provides primary confinement). Size-reduction operations on glovebox equipment are a common activity when a process has been discontinued and the room is being modified to support a new customer. The Actinide Processing Group at TA-55 uses one-meter or longer glass columns to process plutonium. Disposal of used columns is a challenge, since they must be size-reduced to get them out of the glovebox. The task is a high-risk operation because the glass shards that are generated can puncture the bag-out bags, leather protectors, glovebox gloves, and the worker's skin when completing the task. One of the Lessons Learned from these operations is that Laboratory management should critically evaluate each hazard and provide more effective measures to prevent personnel injury. A bag made of puncture-resistant material was one of these enhanced controls. We have investigated the effectiveness of these bags and have found that they safely and effectively permit glass objects to be reduced to small pieces with a plastic or rubber mallet; the waste can then be easily poured into a container for removal from the glovebox as non-compactable transuranic (TRU) waste. This size-reduction operation reduces solid TRU waste volume generation by almost 2½ times. Replacing one-time-use bag-out bags with multiple-use glass crushing bags also contributes to reducing generated waste. In addition, significant costs from contamination, cleanup, and preparation of incident documentation are avoided. This effort contributes to the Los Alamos

  15. Transuranic (Tru) waste volume reduction operations at a plutonium facility

    Cournoyer, Michael E [Los Alamos National Laboratory; Nixon, Archie E [Los Alamos National Laboratory; Dodge, Robert L [Los Alamos National Laboratory; Fife, Keith W [Los Alamos National Laboratory; Sandoval, Arnold M [Los Alamos National Laboratory; Garcia, Vincent E [Los Alamos National Laboratory

    2010-01-01

    Programmatic operations at the Los Alamos National Laboratory Plutonium Facility (TA 55) involve working with various amounts of plutonium and other highly toxic, alpha-emitting materials. The spread of radiological contamination on surfaces, airborne contamination, and excursions of contaminants into the operator's breathing zone are prevented through use of a variety of gloveboxes (the glovebox, coupled with an adequate negative pressure gradient, provides primary confinement). Size-reduction operations on glovebox equipment are a common activity when a process has been discontinued and the room is being modified to support a new customer. The Actin ide Processing Group at TA-55 uses one-meter-long glass columns to process plutonium. Disposal of used columns is a challenge, since they must be size-reduced to get them out of the glovebox. The task is a high-risk operation because the glass shards that are generated can puncture the bag-out bags, leather protectors, glovebox gloves, and the worker's skin when completing the task. One of the Lessons Learned from these operations is that Laboratory management should critically evaluate each hazard and provide more effective measures to prevent personnel injury. A bag made of puncture-resistant material was one of these enhanced controls. We have investigated the effectiveness of these bags and have found that they safely and effectively permit glass objects to be reduced to small pieces with a plastic or rubber mallet; the waste can then be easily poured into a container for removal from the glove box as non-compactable transuranic (TRU) waste. This size-reduction operation reduces solid TRU waste generation by almost 2% times. Replacing one-time-use bag-out bags with multiple-use glass crushing bags also contributes to reducing generated waste. In addition, significant costs from contamination, cleanup, and preparation of incident documentation are avoided. This effort contributes to the Los Alamos

  16. The Creative Application of Science, Technology and Work Force Innovations to the Decontamination and Decommissioning of the Plutonium Finishing Plant at the Hanford Nuclear Reservation

    Charboneau, S.; Klos, B.; Heineman, R.; Skeels, B.; Hopkins, A.

    2006-01-01

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

  17. Transuranic (Tru) waste volume reduction operations at a plutonium facility

    Cournoyer, Michael E.; Nixon, Archie E.; Dodge, Robert L.; Fife, Keith W.; Sandoval, Arnold M.; Garcia, Vincent E.

    2010-01-01

    Programmatic operations at the Los Alamos National Laboratory Plutonium Facility (TA 55) involve working with various amounts of plutonium and other highly toxic, alpha-emitting materials. The spread of radiological contamination on surfaces, airborne contamination, and excursions of contaminants into the operator's breathing zone are prevented through use of a variety of gloveboxes (the glovebox, coupled with an adequate negative pressure gradient, provides primary confinement). Size-reduction operations on glovebox equipment are a common activity when a process has been discontinued and the room is being modified to support a new customer. The Actin ide Processing Group at TA-55 uses one-meter-long glass columns to process plutonium. Disposal of used columns is a challenge, since they must be size-reduced to get them out of the glovebox. The task is a high-risk operation because the glass shards that are generated can puncture the bag-out bags, leather protectors, glovebox gloves, and the worker's skin when completing the task. One of the Lessons Learned from these operations is that Laboratory management should critically evaluate each hazard and provide more effective measures to prevent personnel injury. A bag made of puncture-resistant material was one of these enhanced controls. We have investigated the effectiveness of these bags and have found that they safely and effectively permit glass objects to be reduced to small pieces with a plastic or rubber mallet; the waste can then be easily poured into a container for removal from the glove box as non-compactable transuranic (TRU) waste. This size-reduction operation reduces solid TRU waste generation by almost 2% times. Replacing one-time-use bag-out bags with multiple-use glass crushing bags also contributes to reducing generated waste. In addition, significant costs from contamination, cleanup, and preparation of incident documentation are avoided. This effort contributes to the Los Alamos National

  18. A rapid method for the determination on fluoride in geological samples

    Josephson, M.; Cook, E.B.T.; Dixon, K.

    1977-01-01

    An account is given of a rapid procedure for the determination by use of the specific-ion electrode of fluoride in geological samples. The sample is fused with sodium hydroxide in a nickel crucible in a muffle furnace. The melt is leached with water, a buffer solution of ammonium citrate is added, and the fluoride activity is measured with a specific-ion electrode. All operations are carried out in the crucible, making possible approximately 100 determinations a day. The precision of the method is approximately 10 per cent at a fluoride concentration of 500 p.p.m., which is acceptable for geological-survey work [af

  19. Strut fracture and disc embolization of a Björk-Shiley mitral valve prosthesis: localization of embolized disc by computerized axial tomography.

    Larrieu, A J; Puglia, E; Allen, P

    1982-08-01

    The case of a patient who survived strut fracture and embolization of a Björk-Shiley mitral prosthetic disc is presented. Prompt surgical treatment was directly responsible for survival. In addition, computerized axial tomography of the abdomen aided in localizing and retrieving the embolized disc, which was lodged at the origin of the superior mesenteric artery. A review of similar case reports from the literature supports our conclusions that the development of acute heart failure and absent or muffled prosthetic heart sounds in a patient with a Björk-Shiley prosthetic heart valve inserted prior to 1978 should raise the possibility of valve dysfunction and lead to early reoperation.

  20. Spectrographic determination of niobium in uranium - niobium alloys

    Charbel, M.Y.; Lordello, A.R.

    1984-01-01

    A method for the spectrographic determination of niobium in uranium-niobium alloys in the concentration range 1-10% has been developed. The metallic sample is converted to oxide by calcination in a muffle furnace at 800 0 C for two hours. The standards are prepared synthetically by dry-mixing. One part of the sample or standard is added to nineteen parts of graphite powder and the mixture is excited in a DC arc. Hafnium has been used as internal standard. The precision of the method is + - 4.8%. (Author) [pt

  1. Effect of sterilization on mineralization of straw and black carbon

    Bobul'ská, Lenka; Bruun, Sander; Fazekašová, Danica

    2013-01-01

    The study was aimed at investigating the role of microorganisms in the degradation of BC (black carbon). CO evolution was measured under sterilized and non-sterilized soil using BC and straw amendments. Black carbon and straw were produced from homogenously C labelled roots of barley (Hordeum vulgare) with a specific activity 2.9 MBq g C. Production of BC was implemented at 300 °C for 24 h in a muffle oven, incubated in soil and C in the evolved CO was measured after 0.5, 1, 2, 4, 8, 16, 26 a...

  2. Phase identification of SiO/sub/2 in rice husk ash

    Ikram, N.; Hussain, K.; Shah, M.A.

    1987-01-01

    Semiconductor grade silicon is generally used in the manufacture of highly efficient solar cells. In this paper, we describe rice husk ash (RHA) as a viable raw material for obtaining silica. Rice husk contains about 15 percent silica. Rice husk ash is prepared by first burning rice husk in air at a temperature of 300 degree centigrade and then firing it in alumina crucibles in a muffle furnace upto 1200 degree centigrade. Rice husk ash is then ground into fine powder and its X-ray diffraction pattern is obtained in order to studies its structure at various temperatures of preparation. (author/A.B)

  3. Investigation about the thermal features of the ovens used for thermoluminescence; Indagine sulle specifiche dei forni usati per i trattamenti termici dei rilevatori a termoluminescenza

    Scarpa, G; Caporali, C; Moscati, M [ENEA - Area Energia, Ambiente e Salute, Centro Ricerche Energia, Casaccia, Rome (Italy)

    1991-02-15

    The present paper reports the results of an investigation carried out by the PAS-FIBI-DOSIBIO laboratory (ENEA, Casaccia, Roma) about the thermal features of the ovens used for annealing treatments of TL dosemeters. A total number of 45 commercial ovens and muffle furnaces were studied. belonging to 24 Italian Health Physics laboratories. The investigation has shown that the majority of the ovens do not possess a degree of accuracy, stability, uniformity and reproducibility suitable for their use in the field of thermoluminescence dosimetry. Practical suggestions are also given in order to reduce the effects of some of the negative characteristics found in most ovens. (author)

  4. Synthesis and characterization of Al2O3 obtained from the polymeric precursor method using glycerin as a poly alcohol

    Elicker, C.; Gaier, M.; Almeida, S.R.; Vieiraaa, B.M.; Ratmann, C.W.R.; Pereira, C.M.P. de; Cava, S.S.; Egea, J.J.

    2014-01-01

    In this study, calcium aluminate was synthesized using glycerin to replace ethylene glycol in the polymeric precursor method. The resulting resin was pre-calcined in a muffle at 300 °C for 2 h and the resulting material was calcined at 900 °C for 2 h. The powders were analyzed by XRD, SEM and EDX, TEM, Micro-Raman and IR. The results demonstrated the possibility of using glycerin as an alternative to ethylene glycol in the polymeric precursor method. (author)

  5. Determination of total alpha and beta activities on vegetable samples by LSC

    Nogueira, Regina Apolinaria; Santos, Eliane Eugenia dos; Bakker, Alexandre Pereira; Vavassori, Giullia

    2011-01-01

    Gross alpha and beta analyses are screening techniques used for environmental radioactivity monitoring. The present study proposes to determine the gross alpha and beta activities in vegetable samples by using LSC - liquid scintillation spectrometry. The procedure was applied to vegetable foods. After ashing vegetable samples in a muffle furnace, 100 mg of ash were added to gel mixture of scintillation cocktails, Water - Instagel - Ultima Gold AB (6:10:4) ml, in polyethylene vial. Am-241 standard solution and a KCl (K-40) solution were used to determine the counting configuration, alpha/beta efficiencies and spillover

  6. Structural and morphological characteristics of composite: polyamide 6/ferrite nickel; Caracteristicas morfologicas e estruturais do composito: poliamida 6/ferrita de niquel

    Fernandes, P.C.; Santos, P.T.A.; Silva, T.R.G.; Araujo, E.M.; Costa, A.C.F.M., E-mail: patricia.fernandes24@hotmail.co [Universidade Federal de Campina Grande (UFCG), PB (Brazil). Unidade Academica de Engenharia de Materiais

    2010-07-01

    This study aims to evaluate the structural and morphological characteristics of a composite polyamide 6 with 50% loading of nickel ferrite. The ferrite was obtained by combustion synthesis and calcined in muffle furnace at 700 deg C. The polymer matrix was previously dried in vacuum oven at 80 deg C / 48 h to eliminate moisture. The composites were characterized by XRD and SEM. XRD results show the incorporation of cargo in the matrix, and that increasing temperature led to a considerable increase in crystallinity. The particle size of the load in the matrix was changed by increasing temperature. (author)

  7. Breakfast in a hotel dining room

    Mary Kennan Herbert

    2009-01-01

    Full Text Available My father and I were the only ones there on a winter Saturday.Yet a full staff of penguins was on duty, webbed shoes muffled on thick but aging carpet, their lined faces and beaks a bit mottled.They brought us the morning newspaper, toast, coffee, orange juice, grapefruit (a beauty nestled on ice in a pewter tureen, an old-fashioned presentation,with a hint of decay.The hotel was closed shortly thereafter, for a decade, then remodeled,reopened with new crystal, dinnerware with postmodern chi...

  8. Investigation about the thermal features of the ovens used for thermoluminescence

    Scarpa, G.; Caporali, C.; Moscati, M.

    1991-02-01

    The present paper reports the results of an investigation carried out by the PAS-FIBI-DOSIBIO laboratory (ENEA, Casaccia, Roma) about the thermal features of the ovens used for annealing treatments of TL dosemeters. A total number of 45 commercial ovens and muffle furnaces were studied. belonging to 24 Italian Health Physics laboratories. The investigation has shown that the majority of the ovens do not possess a degree of accuracy, stability, uniformity and reproducibility suitable for their use in the field of thermoluminescence dosimetry. Practical suggestions are also given in order to reduce the effects of some of the negative characteristics found in most ovens. (author)

  9. Synthesis and characterization of Al{sub 2}O{sub 3} obtained from the polymeric precursor method using glycerin as a poly alcohol; Sintese e caracterizacao de Al{sub 2}O{sub 3} obtida por meio do metodo dos precursores polimericos utilizando glicerina como polialcool

    Elicker, C.; Gaier, M.; Almeida, S.R.; Vieiraaa, B.M.; Ratmann, C.W.R.; Pereira, C.M.P. de; Cava, S.S. [Universidade Federal de Pelotas (UFPel), Pelotas, RS (Brazil); Egea, J.J. [Consejo Superior de Investigaciones Cientificas, Madrid (Spain)

    2014-07-01

    In this study, calcium aluminate was synthesized using glycerin to replace ethylene glycol in the polymeric precursor method. The resulting resin was pre-calcined in a muffle at 300 °C for 2 h and the resulting material was calcined at 900 °C for 2 h. The powders were analyzed by XRD, SEM and EDX, TEM, Micro-Raman and IR. The results demonstrated the possibility of using glycerin as an alternative to ethylene glycol in the polymeric precursor method. (author)

  10. A facility to remotely assemble radioisotope thermoelectric generators

    Engstrom, J.W.; Goldmann, L.H.; Truitt, R.W.

    1992-07-01

    Radioisotope Thermoelectric Generators (RTGs) are electrical power sources that use heat from decaying radioisotopes to directly generate electrical power. The RTG assembly process is performed in an inert atmosphere inside a large glovebox, which is surrounded by radiation shielding to reduce exposure to neutron and gamma radiation from the radioisotope heat source. In the past, allowable dose rate limits have allowed direct, manual assembly methods; however, current dose rate limits require a thicker radiation shielding that makes direct, manual assembly infeasible. To minimize RTG assembly process modifications, telerobotic systems are being investigated to perform remote assembly tasks. Telerobotic systems duplicate human arm motion and incorporate force feedback sensitivity to handle objects and tools in a human-like manner. A telerobotic system with two arms and a three-dimensional (3-D) vision system can be used to perform remote RTG assembly tasks inside gloveboxes and cells using unmodified, normal hand tools

  11. Posting system

    Hackney, S.

    1983-01-01

    A system for posting hazardous materials into and out of an enclosure, such as a glovebox, through a port in a wall of the enclosure. The port is normally closed by a door which cooperates with a removable end closure, on a container or the like when the latter is presented to and secured at the port. The container is secured in position at the port by means of a rotatable coupling ring. A single interlock ensures that the door cannot be opened in the absence of a container at the port and also that the container cannot be removed from the port when the door is open. In place of the container, a glove secured to a rigid sleeve may be used to enable the operator to perform a work function within the glovebox. (author)

  12. Operation of the lithium pellet injector

    Khlopenkov, K.V.; Sudo, S.; Sergeev, V.Yu.

    1996-05-01

    A lithium pellet injection requires an accurate handling with lithium and special technique of loading the pellets. Thus, the technology for this has been developed based on the following conditions: 1) Because of chemical activity of lithium it is necessary to operate in a glove-box with the noble gas atmosphere (He, Ar, etc.). 2) A special procedure of replacing the glove-box atmosphere allows to achieve high purity of the noble gas. 3) When making the pellets it is better to keep the clean lithium in the liquid hexane so as to maintain lithium purity. 4) The pressure of the accelerating gas for Li pellets should be not less than 30 atm. (author)

  13. INERT Atmosphere confinement operability test procedure

    RISENMAY, H.R.

    1999-01-01

    This Operability Test Procedure (OTP) provides instructions for testing operability of the Inert Atmosphere Confinement (IAC). The Inert Atmosphere Confinement was designed and built for opening cans of metal items that might have hydrided surfaces. Unreviewed Safety Question (USQ) PFP-97-005 addresses the discovery of suspected plutonium hydride forming on plutonium metal currently stored in the Plutonium Finishing Plant vaults. Plutonium hydride reacts quickly with air, liberating energy. The Inert Atmosphere Confinement was designed to prevent this sudden liberation of energy by opening the material in an inert argon atmosphere instead of the normal glovebox atmosphere. The IAC is located in glovebox HC-21A, room 230B of the 234-5Z Building at the Plutonium Finishing Plant (PFP) in the 200-West Area of the Hanford Site

  14. Design integration of favorable geometry, structural support and containment

    Purcell, J.A.; McGehee, G.A.

    1991-07-01

    In designs for fissile processes at Savannah River site, different approaches have been used to provide engineered margins of safety for criticality with containment and seismic resistance as additional requirements. These requirements are frequently at odds in engineered systems. This paper proposes a plan to take advantage of vessels with favorable geometry to provide seismic resistance and to support a glovebox for containment. Thin slab tanks, small diameter pencil tanks, annular tanks, and other novel designs have been used for criticality safety. The requirement for DBE seismic resistance and rigid control of dimensions leads the designer to consider annular tanks for meeting these requirements. The high strength of annular tanks may logically be used to support secondary containment. Hands-on access to all instruments, piping etc. within containment can be provided through gloveports, thus a specialized glovebox. This paper examines the advantages of using an annular tank design to provide favorable geometry, structural support and containment

  15. Guide to good practice: bagless transfer systems for use on radioactive facilities

    Lillyman, E.

    1988-09-01

    The development of the bagless posting system has improved the degree of safety possible during posting operations. It has provided the means of significantly reducing the large amounts of contaminated plastic waste created during bag posting and has provided the means of minimising personal exposure both in glovebox plutonium handling and in heavily shielded facilities. This report is intended to provide a guide to the types of bagless posting systems that are available both for glovebox and shielded facilities use. Included are references to developments which have utilised the bagless posting principle for sealing and utility change operations. Details of particular system types can be obtained from the identified design office or commercial organisation. (author)

  16. Tritiated ammonia formation

    Heung, L.K.

    1995-01-01

    When nitrogen was selected as the glovebox atmosphere for the Replacement Tritium Facility (RTF) at the Savannah River Site (SRS), a concern was raised as to the possibility of tritiated ammonia formation in the gloveboxes. Experimental data were produced to study the tritiated ammonia formation rate in a tritium and nitrogen mixture. A rate equation that closely simulates the experimental data was developed. This rate equation can be used to calculate the formation of tritiated ammonia from different concentrations of tritium and nitrogen. The reaction of T 2 and N 2 to form NT 3 is a slow process, particularly when the tritium concentration is low. The reaction requires weeks or months to reach radiochemical equilibrium dependent on the concentrations of the reactants. 4 refs., 6 figs., 1 tab

  17. Contained x-ray diffraction goniometer for examination of radioactive materials

    Smith, P.K.; Osgood, B.C.; Blaser, D.E.; Howell, R.E.; Stuhler, H.; Stauver, J.

    1987-11-01

    Radioactive materials are being characterized for chemical form and certain physical properties with an x-ray diffraction goniometer customized for containment in a shielded alpha glovebox. A Siemens D500 goniometer was customized by Siemens to locate the associated electronics and x-ray generator outside the glovebox to minimize corrosion and facilitate maintenance. A graphite monochromator is used with a shielded scintillation detector to separate diffracted x-radiation from nuclear radiation. The diffraction system is computer automated for data acquisition and reduction. The facility is designed to handle primarily alpha- and beta-emitting samples with moderate neutron and gamma radiation. Samples containing plutonium, enriched uranium, and other transuranic elements are analyzed in support of site nuclear operations and development programs on nuclear waste, chemical separations, reactor fuels, and product forms

  18. Re-evaluation of Moisture Controls During ARIES Oxide Processing, Packaging and Characterization

    Karmiol, Benjamin [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Wayne, David Matthew [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2017-12-18

    DOE-STD-3013 [1] requires limiting the relative humidity (RH) in the glovebox during processing of the oxide product for specific types of plutonium oxides. This requirement is mandated in order to limit corrosion of the stainless steel containers by deliquescence of chloride salts if present in the PuO2. DOE-STD-3013 also specifies the need to limit and monitor internal pressure buildup in the 3013 containers due to the potential for the generation of free H2 and O2 gas from the radiolysis of surfaceadsorbed water. DOE-STD-3013 requires that the oxide sample taken for moisture content verification be representative of the stabilized material in the 3013 container. This is accomplished by either limiting the time between sampling and packaging, or by control of the glovebox relative humidity (%RH). This requirement ensures that the sample is not only representative, but also conservative from the standpoint of moisture content.

  19. A new waste minimization method for the determination of total nonhalogenated volatile organic compounds in TRU wastes

    Sandoval, W.; Quintana, B.D.; Ortega, L.

    1997-01-01

    As part of the technical support CST-12 provides for a wide variety of defense and nondefense programs within Los Alamos National Laboratory (LANL) and the Department of Energy (DOE) complex, new waste minimization technique is under development for radiological volatile organic analysis (Hot VOA). Currently all HOT VOA must be run in a glovebox. Several types of sample contain TRU radiological waste in the form of particulates. By prefiltering the samples through a 1.2 micron syringe and counting the radioactivity, it has been found that many of the samples can be analyzed outside a glovebox. In the present investigation, the types of Hot VOA samples that can take advantage of this new technique, the volume and types of waste reduced and the experimental parameters will be discussed. Overall, the radioactive waste generated is minimized

  20. System specification/system design document comment review: Plutonium Stabilization and Packaging System. Notes of conference

    1996-01-01

    A meeting was held between DOE personnel and the BNFL team to review the proposed resolutions to DOE comments on the initial issue of the system specification and system design document for the Plutonium Stabilization and Packaging System. The objectives of this project are to design, fabricate, install, and start up a glovebox system for the safe repackaging of plutonium oxide and metal, with a requirement of a 50-year storage period. The areas discussed at the meeting were: nitrogen in can; moisture instrumentation; glovebox atmosphere; can marking bar coding; weld quality; NFPA-101 references; inner can swabbing; ultimate storage environment; throughput; convenience can screw-top design; furnacetrays; authorization basis; compactor safety; schedule for DOE review actions; fire protection; criticality safety; applicable standards; approach to MC and A; homogeneous oxide; resistance welder power; and tray overfill. Revised resolutions were drafted and are presented

  1. Some recent changes in tritium handling and control at Mound Laboratory

    Rhinehammer, T.B.

    1976-01-01

    Significant reductions in tritium effluents and personnel exposures at Mound Laboratory have been made during the past 5 yr. Yearly effluents are less than 3 percent of former levels and personnel exposures have been reduced by a factor of 300. Several recent changes which have contributed to these reductions include lowered tritium levels in gloveboxes, and the efficiency and capacity of Mound's new effluent removal system. Personnel exposures have been reduced dramatically by changing to precious metal catalytic converters or oxidizers for use with the glovebox gas purification system. Unlike some former systems using hot copper or proprietary reactants for oxygen removal, a catalyst provides very effective removal of both oxygen and tritium. Both oxygen and tritium can be monitored and, if necessary, increments of hydrogen in argon can be added until the oxygen level is brought down to the desired value

  2. An overview of plutonium-238 decontamination and decommissioning (D and D) projects at Mound

    Bond, W.H.; Davis, W.P.; Draper, D.G.; Geichman, J.R.; Harris, J.C.; Jaeger, R.R.; Sohn, R.L.

    1987-01-01

    Mound is currently decontaminating for restricted reuse and/or decommissioning for conditional release four major plutonium-238 contaminated facilities that contained 1700 linear feet of gloveboxes and associated equipment and services. Several thousand linear feet of external underground piping, associated tanks, and contaminated soil are being removed. Two of the facilities contain ongoing operations and will be reused for both radioactive and nonradioactive programs. Two others will be completely demolished and the land area will become available for future DOE building sites. An overview of the successful techniques and equipment used in the decontamination and decommissioning of individual pieces of equipment, gloveboxes, services, laboratories, sections of buildings, entire buildings, and external underground piping, tanks, and soil in a highly populated residential area is described and pictorially presented

  3. Decontamination of a plutonium laboratory after a contamination accident

    Francioni, W.M.; Haenni, F.

    1985-02-01

    On the 24th May 1983, a minor explosion occured in a glovebox at the hotlaboratories of the Swiss Federal Institute for Reactor Re-search (EIR). The incident occured during the evaporation of waste slurries associated with the Institute's mixed carbide fuel programme. It resulted in a breaching of the glovebox seals and in heavy contamination of the laboratory housing the box. In this report the problems of decontaminating the laboratory concerned are presented, especially those problems associated with re-contamination during the cleanup process. The experience gained from the decontamination exercise are discussed and details of the costs and resulting quantities of radwaste are also presented. The most important information concerning the incident are also related. (author)

  4. Improved Casting Furnace Conceptual Design

    Fielding, Randall Sidney [Idaho National Lab. (INL), Idaho Falls, ID (United States); Tolman, David Donald [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2017-02-01

    In an attempt to ensure more consistent casting results and remove some schedule variance associated with casting, an improved casting furnace concept has been developed. The improved furnace uses the existing arc melter hardware and glovebox utilities. The furnace concept was designed around physical and operational requirements such as; a charge sized of less than 30 grams, high heating rates and minimal additional footprint. The conceptual model is shown in the report as well as a summary of how the requirements were met.

  5. Los Alamos transuranic waste size reduction facility

    Briesmeister, A.; Harper, J.; Reich, B.; Warren, J.L.

    1982-01-01

    To facilitate disposal of transuranic (TRU) waste, Los Alamos National Laboratory designed and constructed the Size Reduction Facility (SRF) during the period 1977 to 1981. This report summarizes the engineering development, installation, and early test operations of the SRF. The facility incorporates a large stainless steel enclosure fitted with remote handling and cutting equipment to obtain an estimated 4:1 volume reduction of gloveboxes and other bulky metallic wastes

  6. JCSC_128_6_875_881_SI.doc

    A solution of primary or secondary amine (0.99 mmol) in toluene (1.0 mL) was added drop wise into the reaction mixure of carbodiimide (0.99 mmol) and DippBIAOZnCl2 (1) (0.276 mmol) to a 25 mL dry Schlenk flask inside the glovebox. The dark red reaction mixture was stirred for 12 h at 90˚C temperature. Solvent was ...

  7. Plutonium Finishing Plant (PFP) Generalized Geometry Holdup Calculations and Total Measurement Uncertainty

    Keele, B.D.

    2005-01-01

    A collimated portable gamma-ray detector will be used to quantify the plutonium content of items that can be approximated as a point, line, or area geometry with respect to the detector. These items can include ducts, piping, glove boxes, isolated equipment inside of gloveboxes, and HEPA filters. The Generalized Geometry Holdup (GGH) model is used for the reduction of counting data. This document specifies the calculations to reduce counting data into contained plutonium and the associated total measurement uncertainty.

  8. An X-ray diffractometer specimen holder for use with reactive and toxic materials

    Huyton, A.; Munden, A.B.

    1979-04-01

    An X-ray diffractometer specimen holder has been designed for analysis of reactive sodium compounds which will satisfactorily seal the sample from the atmosphere. The holder can be readily filled in a glove-box and is easily transported for mounting on a vertical Philips PW 1051 X-ray diffractometer. It is considered that this holder could also be applied to a wide range of other reactive and toxic materials, e.g. plutonium or its compounds. (author)

  9. A simple air-cooled reflux condenser for laboratory use

    Boult, K.A.

    1979-10-01

    This Memorandum describes the design of a simple compact air-cooled reflux condenser suitable for gloveboxes, cells or other locations where the provision of cooling water presents a problem. In a typical application the condenser functioned satisfactorily when used to condense water from a flask heated by a 100 watt mantle. There was no measurable loss of water from the boiling flask in 100 hours. (author)

  10. Device for cementing radioactive of toxic waste into barrels

    Hempelmann, W.; Waldenmeier, G.; Mathis, P.; Mathis, B.; Mathis, F.

    1987-01-01

    The plant consists of conventional means, such as through mixers and dosing and transport spirals, which are accommodated in a glovebox. The inactive additives cement and sand and the active materials evaporation concentrates and sludges are mixed by them, and are then filled into a waste barrel which is empty or already filled with solid waste. Liquid radioactive wastes are used to concrete over the solid waste. (DG) [de

  11. Development of a separatif microsystem for radionuclides analysis in nitric acid media

    Losno , Marion

    2017-01-01

    Radionuclides analysis is a key point for nuclear waste management and nuclear material control. Several steps of sample modification have to be carried out before measurements in order to avoid any interferences and improve measurement precision. However those different steps are long, irradiant and difficult to achieve in gloveboxes. Moreover they produce liquid and solid waste. The goal of the study is to offer a new alternative to the use of solid phase extraction column for radionuclides...

  12. Tritium monitoring equipments for animal experiment facilities

    Sato, Hiroo

    1980-01-01

    Animal experiment facilities using tritium are described with reference to laws and regulations concerning radiological safety. Usual breeding facilities and surrounding conditions at non-radioactive animal experiments are summarized on feasible and effective designs of tritium monitors. Characteristics and desirable arrangements of various kinds of tritium monitors such as ionization chambers, proportional counters and liquid scintillation detectors are discussed from the standpoint of monitoring for room, glove-box, stack, liquid waste and personnel. (J.P.N.)

  13. Solution In-Line Alpha Counter (SILAC) Instruction Manual-Version 4.00

    Alferink, Steven M.; Farnham, Joel E.; Fowler, Malcolm M.; Wong, Amy S.

    2002-01-01

    The Solution In-Line Alpha Counter (SILAC) provides near real-time alpha activity measurements of aqueous solutions in gloveboxes located in the Plutonium Facility (TA-55) at Los Alamos National Laboratory (LANL). The SILAC detector and its interface software were first developed by Joel Farnham at LANL [1]. This instruction manual describes the features of the SILAC interface software and contains the schematic and fabrication instructions for the detector

  14. Los Alamos transuranic waste size reduction facility

    Briesmeister, A.; Harper, J.; Reich, B.; Warren, J.L.

    1982-01-01

    A transuranic (TRU) Waste Size Reduction Facility (SRF) was designed and constructed at the Los Alamos National Laboratory during the period of 1977 to 1981. This paper summarizes the engineering development, installation, and early test operations of the SRF. The facility incorporates a large stainless steel enclosure fitted with remote handling and cutting equipment to obtain an estimated 4:1 volume reduction of gloveboxes and other bulky metallic wastes

  15. Resolution of USQ regarding source term in the 232-Z Waste Incinerator Building

    Westsik, G.A.

    1995-09-01

    The 232-Z Waste Incinerator at the Hanford Plutonium Finishing Plant (PFP) was used to incinerate plutonium-bearing combustible materials generated during normal plant operations. Nondestructive (NDA) measurements performed after the incinerator ceased operations indicated high plutonium loadings in exhaust ductwork near the incinerator glovebox, while the incinerator was found to have only low quantities. Measurements, following a campaign to remove some of the ductwork, resulted in markedly higher assay value for the incinerator glovebox itself. Subsequent assays confirmed the most recent results and pointed to a potential further underestimation of the holdup, in part because of attenuation due to fire brick, which could not be seen easily and which had been reported to not be present. NaI detector based measurements were used to map the deposits. Extended count times, using high resolution Ge detectors helped estimate the isotopic composition of the plutonium and quantify the deposits. Experiments were performed using a Ge detector to obtain adequate corrections for the high attenuation of the incinerator glovebox. Several neutron detectors and detector configurations were employed to understand and quantify the neutron flux. Due to the disparity that was anticipated to occur between the gamma ray and neutron assay results, radiation modeling was used to try to reconcile the divergent results. This was a third aspect of the team's effort, utilizing computer modeling to resolve discrepancies between measurement methods

  16. Off gas processing device for degreasing furnace for uranium/plutonium mixed oxide fuel

    Ueda, Masaya; Akasaka, Takayuki; Noura, Takeshi.

    1996-01-01

    A low melting ingredient capturing-cooling trap connected to a degreasing sintering furnace by way of sealed pipelines, a burning/decomposing device for decomposing high melting ingredient gases discharged from the cooling trap by burning them and a gas sucking means for forming the flow of off gases are contained in a glovebox, the inside pressure of which is kept negative. Since the degreasing sintering furnace for uranium/plutonium mixed oxide fuels is disposed outside of the glovebox, operation can be performed safely without greatly increasing the scale of the device, and the back flow of gases is prevented easily by keeping the pressure in the inside of the glovebox negative. Further, a heater is disposed at the midway of the sealed pipelines from the degreasing sintering furnace to the cooling trap, the temperature is kept high to prevent deposition of low melting ingredients to prevent clogging of the sealed pipelines. Further, a portion of the pipelines is made extensible in the axial direction to eliminate thermal stresses caused by temperature change thereby enabling to extend the life of the sealed pipelines. (N.H.)

  17. HB-Line Dissolver Dilution Flows and Dissolution Capability with Dissolver Charge Chute Cover Off

    Hallman, D.F.

    2003-01-01

    A flow test was performed in Scrap Recovery of HB-Line to document the flow available for hydrogen dilution in the dissolvers when the charge chute covers are removed. Air flow through the dissolver charge chutes, with the covers off, was measured. A conservative estimate of experimental uncertainty was subtracted from the results. After subtraction, the test showed that there is 20 cubic feet per minute (cfm) air flow through the dissolvers during dissolution with a glovebox exhaust fan operating, even with the scrubber not operating. This test also showed there is 6.6 cfm air flow through the dissolvers, after subtraction of experimental uncertainty if the scrubber and the glovebox exhaust fans are not operating. Three H-Canyon exhaust fans provide sufficient motive force to give this 6.6 cfm flow. Material charged to the dissolver will be limited to chemical hydrogen generation rates that will be greater than or equal to 25 percent of the Lower Flammability Limit (LFL) during normal operations. The H-Canyon fans will maintain hydrogen below LFL if electrical power is lost. No modifications are needed in HB-Line Scrap Recovery to ensure hydrogen is maintained less that LFL if the scrubber and glovebox exhaust fans are not operating

  18. Resolution of the 15N balance enigma?

    Clough, T.J.; Sherlock, R.R.; Cameron, K.C.; Stevens, R.J.; Laughlin, R.J.; Mueller, C.

    2001-01-01

    The enigma of soil nitrogen balance sheets has been discussed for over 40 years. Many reasons have been considered for the incomplete recovery of 15 N applied to soils, including sampling uncertainty, gaseous N losses from plants, and entrapment of soil gases. The entrapment of soil gases has been well documented for rice paddy and marshy soils but little or no work appears to have been done to determine entrapment in drained pasture soils. In this study 15 N-labelled nitrate was applied to a soil core in a gas-tight glovebox. Water was applied, inducing drainage, which was immediately collected. Dinitrogen and N -2 were determined in the flux through the soil surface, and in the gases released into the glovebox as a result of irrigation or physical destruction of the core. Other components of the N balance were also measured, including soil inorganic-N and organic-N. Quantitative recovery of the applied 15 N was achieved when the experiment was terminated 484 h after the 15 N-labelled material was applied. Nearly 23% of the 15 N was recovered in the glovebox atmosphere as N 2 and N 2 O due to diffusion from the base of the soil core, convective flow after irrigation, and destructive soil sampling. This 15 N would normally be unaccounted for using the sampling methodology typically employed in 15 N recovery experiments. Copyright (2001) CSIRO Publishing

  19. Pu abundances, concentrations, and isotopics by x- and gamma-ray spectrometry assay techniques

    Camp, D.C.; Gunnink, R.; Ruhter, W.D.; Prindle, A.L.; Gomes, R.J.

    1986-01-01

    Two x- and gamma-ray systems were recently installed at-line in gloveboxes and will measure Pu solution concentrations from 5 to 105 g/L. These NDA technique, developed and refined over the past decade, are now used domestically and internationally for nuclear material process monitoring and accountability needs. In off- and at-line installations, they can measure solution concentrations to 0.2%. The K-XRFA systems use a transmission source to correct for solution density. The gamma-ray systems use peaks from 59- to 208-keV to determine solution concentrations and relative isotopics. A Pu check source monitors system stability. These two NDA techniques can be combined to form a new, NDA measurement methodology. With the instrument located outside of a glovebox, both relative Pu isotopics and absolute Pu abundances of a sample located inside a glovebox can be measured. The new technique works with either single or dual source excitation; the former for a detector 6 to 20 cm away with no geometric corrections needed; the latter requires geometric corrections or source movement if the sample cannot be measured at the calibration distance. 4 refs., 7 figs., 2 tabs

  20. SEM facility for examination of reactive and radioactive materials

    Downs, G.L.; Tucker, P.A.

    1977-01-01

    A scanning electron microscope (SEM) facility for the examination of tritium-containing materials is operational at Mound Laboratory. The SEM is installed with the sample chamber incorporated as an integral part of an inert gas glovebox facility to enable easy handling of radioactive and pyrophoric materials. A standard SEM (ETEC Model B-1) was modified to meet dimensional, operational, and safety-related requirements. a glovebox was designed and fabricated which permitted access with the gloves to all parts of the SEM sample chamber to facilitate director and accessory replacement and repairs. A separate console combining the electron optical column and specimen chamber was interfaced to the glovebox by a custom-made, neoprene bellows so that the vibrations normally associated with the blowers and pumps were damped. Photomicrographs of tritiated pyrophoric materials show the usefulness of this facility. Some of the difficulties involved in the investigation of these materials are also discussed. The SEM is also equipped with an energy dispersive x-ray detector (ORTEC) and a Secondary Ion Mass Spectrometer (3M) attachments. This latter attachment allows analysis of secondary ions with masses ranging from 1-300 amu. (Auth.)

  1. The Laboratory for Laser Energetics’ Hydrogen Isotope Separation System

    Shmayda, W.T., E-mail: wshm@lle.rochester.edu; Wittman, M.D.; Earley, R.F.; Reid, J.L.; Redden, N.P.

    2016-11-01

    The University of Rochester’s Laboratory for Laser Energetics has commissioned a hydrogen Isotope Separation System (ISS). The ISS uses two columns—palladium on kieselguhr and molecular sieve—that act in a complementary manner to separate the hydrogen species by mass. The 4-sL per day throughput system is compact and has no moving parts. The columns and the attendant gas storage and handling subsystems are housed in a 0.8 -m{sup 3} glovebox. The glovebox uses a helium cover gas that is continuously processed to extract oxygen and water vapor that permeates through the glovebox gloves and any tritium that is released while attaching or detaching vessels to add feedstock to or drawing product from the system. The isotopic separation process is automated and does not require manual intervention. A total of 315 TBq of tritium was extracted from 23.6 sL of hydrogen with tritium purities reaching 99.5%. Deuterium was the sole residual component in the processed gas. Raffinate contained 0.2 TBq of activity was captured for reprocessing. The total emission from the system to the environment was 0.4 GBq over three weeks.

  2. Use of the CoFe{sub 2}O{sub 4} ferrospinel as catalyst in the WGSR process; Utilizacao do ferroespinelio CoFe{sub 2}O{sub 4} como catalisador no processo de WGSR

    Lima, M.S.; Dantas, J.; Costa, A.C.F.M., E-mail: joeldadantas@yahoo.com.br [Universidade Federal de Campina Grande (LabSMaC/UFCG), PB (Brazil). Departamento de Engenharia de Materiais. Laboratorio de Sintese de Materiais Ceramicos; Sazaki, J.M. [Universidade Federal do Ceara (UFC), Fortaleza, CE (Brazil). Departamento de Fisica; Andrade, H.M.C. [Universidade Federal da Bahia (UFBA), Salvador, BA (Brazil). Departamento de Quimica Geral e Inorganica. Lab. de Catalise e Materiais

    2014-07-01

    This work investigates the use of ferrospinel CoFe{sub 2}O{sub 4} as a catalyst in water gas shift reactions (WGSR). The ferrospinel was synthesized by combustion reaction using the following heating conditions: ceramic base, resistive muffle oven, and microwave oven. The samples were characterized by XRD, FTIR, textural analysis and SEM. The catalytic tests were carried out on a bench scale using mixed CO/N{sub 2} (5% CO mol.mol) to the reaction flow 30mL.min{sup -1}, molar ratio H{sub 2}O/CO of 0.3. The results showed that for all heating conditions there was the monophasic formation of CoFe{sub 2}O{sub 4}, with crystallite size ranging from 38 to 40 nm. Samples showed mesoporous characteristics with type II isotherm and hysteresis loop H3. The sample synthesized in the muffle furnace showed the highest conversion rate of 56.0% and the sample synthesized in the ceramic base showed higher selectivity with 90.19% for the WGRS process. (author)

  3. Radioactivity survey data in Japan. Pt. 2. Dietary materials

    NONE

    1996-03-01

    This issue is the special number on the radioactive survey data of dietary materials collected in 1996. The samples sent from 46 prefectures in Japan were analyzed for strontium-90 and cesium-137 by Japan Chemical Analysis Center. The collection of dietary materials were conducted as follows. A full one-day ordinary diet including three meals, water, tea and snack between meals was collected semiyearly from 5 persons as a total diet sample and ashed at 450degC in an electric muffle furnace. Polished rice was yearly collected in producing districts and consumer`s areas followed by ashing in a porcelain dish. Raw milk is producing districts and commercial one were collected semiyearly. Spinach and Japanese radish were chosen as the representatives for left vegetables and for non-starch roots, respectively. Yearly collected fish, shellfish and seaweed were ashed in an electric muffle furnace after carbonization. All samples were analyzed for strontium-90 and cesium-137 after radiochemical separation by the precipitation method with sodium carbonate. Counting of radioactivity was conducted by low background {beta}-counter and based on those results, the concentrations of the nuclides were estimated. The detail data are presented in this report. (M.N.)

  4. Trace analysis of lead and cadmium in seafoods by differential pulse anodic stripping voltametry

    Sumera, F.C.; Verceluz, F.P.; Kapauan, P.A.

    1979-01-01

    A method for the simultaneous determination of cadmium and lead in seafoods is described. The sample is dry ashed in a muffle furnace elevating the temperature gradually up to 500 0 C. The ashed sample is treated with concentrated nitric acid, dried on a heating plate and returned to the muffle furnace for further heating. The treated ash is then dissolved in 1 N HCL acetate buffer and citric acid are added and the pH adjusted to 3.6-4. The resulting solution is analyzed for lead and cadmium by differential pulse anodic stripping voltametry (DPASV) using a wax-impregnated graphite thin film electrode. The average recoveries of 0.4 of cadmium and lead added to 5 fish samples were 97% and 99% respectively. The standard deviations, on a homogenized shark sample for lead and cadmium analysis were 6.7 ppb and 12.3 ppb, respectively, and the relative standard deviations were 21.0% and 15.5% respectively. Studies on instrumental parameters involved in the DPASV step of analysis and methods of measuring peak current signals were also made. (author)

  5. Radioactivity survey data in Japan. Pt. 2. Dietary materials

    1996-03-01

    This issue is the special number on the radioactive survey data of dietary materials collected in 1996. The samples sent from 46 prefectures in Japan were analyzed for strontium-90 and cesium-137 by Japan Chemical Analysis Center. The collection of dietary materials were conducted as follows. A full one-day ordinary diet including three meals, water, tea and snack between meals was collected semiyearly from 5 persons as a total diet sample and ashed at 450degC in an electric muffle furnace. Polished rice was yearly collected in producing districts and consumer's areas followed by ashing in a porcelain dish. Raw milk is producing districts and commercial one were collected semiyearly. Spinach and Japanese radish were chosen as the representatives for left vegetables and for non-starch roots, respectively. Yearly collected fish, shellfish and seaweed were ashed in an electric muffle furnace after carbonization. All samples were analyzed for strontium-90 and cesium-137 after radiochemical separation by the precipitation method with sodium carbonate. Counting of radioactivity was conducted by low background β-counter and based on those results, the concentrations of the nuclides were estimated. The detail data are presented in this report. (M.N.)

  6. Immobilization of uranium and plutonium into boro-basalt, pyroxene and andradite mineral-like compositions

    Matyunin, Y.I.; Smelova, T.V.

    2000-01-01

    The immobilization of plutonium-containing wastes with the manufacturing of stable solid compositions is one of the problems that should be solved in the disposal of radioactive wastes. The works on the choice, preparation with the use of the cold crucible induction melter (CCIM) technology, and investigation of materials that are most suitable for immobilizing plutonium-containing wastes of different origin have been carried out at the All-Russian Scientific Research Institute of Inorganic Materials (VNIINM) and the Institute of the Geology of Ore Deposits, Petrography, Mineralogy, and Geochemistry (IGEM), Russian Academy of Sciences in the framework of the agreements with Lawrence Livermore National Laboratory (LLNL, USA) on the material and technical support. This paper presents the data on the synthesis of cerium-, uranium-, and plutonium-containing materials based on boro-basalt, pyroxene, and andradite compositions in the muffle furnace and by using the CCIM method. The compositions containing up to 15 - 18 wt % cerium oxide, 8 - 11 wt % uranium oxide, and 4.6 - 5.7 wt % plutonium oxide were obtained in laboratory facilities installed in glove boxes. Comparison studies of the materials synthesized in the muffle furnace and CCIM demonstrate the advantages of using the CCIM method. The distribution of components in the materials synthesized are investigated, and their certain physicochemical properties are determined. (authors)

  7. The Role of Diffusion Media in Nitriding Process on Surface Layers Characteristics of AISI 4140 with and without Hard Chrome Coatings

    K.A. Widi

    2016-09-01

    Full Text Available The surface layer characteristics of the AISI 4140 tool steel treated by nitriding gas before and after hard chrome plating utilizing pure nitrogen diffusion media (fluidized bed reactor and the without gas (muffle reactor has been studied experimentally. The result shows that nitriding substrate with hard chrome layers has nitrogen atoms concentration almost twice greater than that without hard chrome layers. After being given a hard chrome plating, nitriding on AISI 4140 steel generally has a nitrogen concentration of up to 4 times more than the substrate without hard chrome coating. Almost the entire specimen showed the highest concentration of N atoms in the area below the surface (hardening depth of 200 to 450 µm. N atoms diffusion depth profile has a correlation with hardening depth profile, especially on the specimens layered with hard chromium. The substrate without hard chrome plating tends to have higher surface hardness than the sub-surface. The results show that the effectiveness and efficiency of the gas nitriding diffusion process can be produced without the use of gas in the muffle reactor but the specimens must be hard chromium coated first. This phenomenon can be explained by the role of the passive layer formation that works as a barrier to keeps the spreading of N atoms concentrated in sub-surface areas.

  8. Evaluation of fire severity via analysis of photosynthetic pigments: Oak, eucalyptus and cork oak leaves in a Mediterranean forest.

    Soler, M; Úbeda, X

    2018-01-15

    Few studies to date have examined the effect of the high temperatures attained during wildfire events on the pigments present in forest foliage. Here, we seek to analyse the main photosynthetic pigments in the leaves of the oak, cork oak and eucalyptus following a wildfire. We also subject leaves of these last two species to a range of contact temperatures (100-500 °C) in the laboratory using a muffle furnace. The samples were left in the muffle for two hours at 100, 150, 200, 250, 300, 350, 400 and 500 °C, in line with other soil study models (Úbeda et al., 2009; Düdaite et al., 2013). At temperatures above 250 °C, chromatography fails to detect any pigments. A minimal increase in temperature degrades chlorophyll, the process being more rapid in eucalyptus than in cork oak, while it increases pheophytin concentrations. Copyright © 2017 Elsevier Ltd. All rights reserved.

  9. Plutonium Finishing Plan (PFP) Treatment and Storage Unit Interim Status Closure Plan

    PRIGNANO, A.L.

    2000-01-01

    This document describes the planned activities and performance standards for closing the Plutonium Finishing Plant (PFP) Treatment and Storage Unit. The PFP Treatment and Storage Unit is located within the 234-52 Building in the 200 West Area of the Hanford Facility. Although this document is prepared based upon Title 40 Code of Federal Regulations (CFR), Part 265, Subpart G requirements, closure of the unit will comply with Washington Administrative Code (WAC) 173-303-610 regulations pursuant to Section 5.3 of the Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement) Action Plan (Ecology et al. 1996). Because the PFP Treatment and Storage Unit manages transuranic mixed (TRUM) waste, there are many controls placed on management of the waste. Based on the many controls placed on management of TRUM waste, releases of TRUM waste are not anticipated to occur in the PFP Treatment and Storage Unit. Because the intention is to clean close the PFP Treatment and Storage Unit, postclosure activities are not applicable to this closure plan. To clean close the unit, it will be demonstrated that dangerous waste has not been left onsite at levels above the closure performance standard for removal and decontamination. If it is determined that clean closure is not possible or is environmentally impractical, the closure plan will be modified to address required postclosure activities. The PFP Treatment and Storage Unit will be operated to immobilize and/or repackage plutonium-bearing waste in a glovebox process. The waste to be processed is in a solid physical state (chunks and coarse powder) and will be sealed into and out of the glovebox in closed containers. The containers of immobilized waste will be stored in the glovebox and in additional permitted storage locations at PFP. The waste will be managed to minimize the potential for spills outside the glovebox, and to preclude spills from reaching soil. Containment surfaces will be maintained to ensure

  10. Reducing Organic Contamination in NASA JSC Astromaterial Curation Facility

    Calaway, M. J.; Allen, C. C.; Allton, J. H.

    2013-01-01

    Future robotic and human spaceflight missions to the Moon, Mars, asteroids and comets will require handling and storing astromaterial samples with minimal inorganic and organic contamination to preserve the scientific integrity of each sample. Much was learned from the rigorous attempts to minimize and monitor organic contamination during Apollo, but it was not adequate for current analytical requirements; thus [1]. OSIRIS-REx, Hayabusa-2, and future Mars sample return will require better protocols for reducing organic contamination. Future isolation con-tainment systems for astromaterials, possibly nitrogen enriched gloveboxes, must be able to reduce organic and inorganic cross-contamination. In 2012, a baseline study established the current state of organic cleanliness in gloveboxes used by NASA JSC astromaterials curation labs that could be used as a benchmark for future mission designs [2, 3]. After standard ultra-pure water (UPW) cleaning, the majority of organic contaminates found were hydrocarbons, plasticizers, silicones, and solvents. Hydro-carbons loads (> C7) ranged from 1.9 to 11.8 ng/cm2 for TD-GC-MS wafer exposure analyses and 5.0 to 19.5 ng/L for TD-GC-MS adsorbent tube exposure. Plasticizers included peracetic acid sterilization were used in the atmospheric de-contamination (R) cabinets. Later, Lunar curation gloveboxes were degreased with a pressurized Freon 113 wash. Today, UPW has replaced Freon as the standard cleaning procedure, but does not have the degreasing solvency power of Freon. Future Cleaning Studies: Cleaning experiments are cur-rently being orchestrated to study how to degrease and reduce organics in a JSC curation glovebox lower than the established baseline. Several new chemicals in the industry have replaced traditional degreasing solvents such as Freon and others that are now federally restricted. However, these new suites of chemicals remain untested for lowering organics in curation gloveboxes. 3M's HFE-7100DL and Du

  11. GeoLab: A Geological Workstation for Future Missions

    Evans, Cynthia; Calaway, Michael; Bell, Mary Sue; Li, Zheng; Tong, Shuo; Zhong, Ye; Dahiwala, Ravi

    2014-01-01

    The GeoLab glovebox was, until November 2012, fully integrated into NASA's Deep Space Habitat (DSH) Analog Testbed. The conceptual design for GeoLab came from several sources, including current research instruments (Microgravity Science Glovebox) used on the International Space Station, existing Astromaterials Curation Laboratory hardware and clean room procedures, and mission scenarios developed for earlier programs. GeoLab allowed NASA scientists to test science operations related to contained sample examination during simulated exploration missions. The team demonstrated science operations that enhance theThe GeoLab glovebox was, until November 2012, fully integrated into NASA's Deep Space Habitat (DSH) Analog Testbed. The conceptual design for GeoLab came from several sources, including current research instruments (Microgravity Science Glovebox) used on the International Space Station, existing Astromaterials Curation Laboratory hardware and clean room procedures, and mission scenarios developed for earlier programs. GeoLab allowed NASA scientists to test science operations related to contained sample examination during simulated exploration missions. The team demonstrated science operations that enhance the early scientific returns from future missions and ensure that the best samples are selected for Earth return. The facility was also designed to foster the development of instrument technology. Since 2009, when GeoLab design and construction began, the GeoLab team [a group of scientists from the Astromaterials Acquisition and Curation Office within the Astromaterials Research and Exploration Science (ARES) Directorate at JSC] has progressively developed and reconfigured the GeoLab hardware and software interfaces and developed test objectives, which were to 1) determine requirements and strategies for sample handling and prioritization for geological operations on other planetary surfaces, 2) assess the scientific contribution of selective in-situ sample

  12. A metallurgical study of Nāga Bhasma

    Dev Nath Singh Gautam

    2017-01-01

    Full Text Available Background: The metal Nāga (Lead is being used by Indians since ancient times. Its external and internal uses have been described in Caraka, Suśruta and other Ayurvedic Saṃhitā. According to most of the Rasa texts, Nāga Bhasma and its formulations are used in many diseases such as Prameha, Jvara, Gulma, Śukrameha etc. Objectives: In the present study, Nāga Bhasma was prepared by the traditional Puṭa method (TPM and by the electric muffle furnace Puṭa method (EMFPM and standardized using Metallographic studies. Doing so helps in the study of the microstructure of Nāga Bhasma and also helps in the identification of the metal particles along with the nature of compound formed during the Māraṇa (Bhasmīkaraṇa process. Setting and Design: Different samples from initial raw material to final product of Nāga Bhasma were collected during the pharmaceutical process (1st, 30th and 60th Puṭa from both methods i.e. TPM and EMFPM. Samples from both methods were studied using metallographic examination. Materials and Methods: The processing of the Nāga Bhasma (ṣaṣṭipuṭa was done according to Ānanda Kanda[9] Samples from the raw material i.e. Aśodhita Nāga (raw Lead and that processed after 1st, 30th and 60th Puṭa from both methods i.e. traditional Puṭa method (using heat from burning of cow dung cakes and electric muffle furnace Puṭa method were taken. They were mounted on self hardening acrylic base. After careful polishing to obtain scratch free surface of product, they were used for metallurgical study. Conclusion: This study shows that traditional Puṭa method may be better than electric muffle furnace Puṭa method because of more homogeneous distribution of Lead sulphide in the Nāga Bhasma which is prepared by traditional method.

  13. Strontium-90 and cesium-137 in sea fish (from Nov. 1984 to Jun. 1985)

    1985-01-01

    Sr-90 and Cs-137 in sea fish were determined using radiochemical analysis. Seven species of fish (Branchiostegus sp., Katsuwonus pelamis, Limanda herzensteini, Sillago sihama, Scomber japonicus, Caesio chrysozonus cuvier, and Sebastes Inermis) were collected during the fishing season from nine sampling locations. Only the edible part was used in cases of larger sized fish, and the whole part was used in cases of smaller ones. Each sample was weighed and placed in a stainless steel pan or a porcelain dish. After carbonization, the sample was ashed in an electric muffle furnace. The maximum value of Sr-90 was 0.9 +- 0.26 pCi/kg in Limanda herzensteini collected from Hiroshima in March 1985; and that of Cs-137 was 12 +- 0.5 pCi/kg in Katsuwonus pelamis collected from Kochi in May 1985. (Namekawa, K.)

  14. GdCuMg with ZrNiAl-type structure. An 82.2 K ferromagnet

    Stein, Sebastian; Heletta, Lukas; Poettgen, Rainer [Muenster Univ. (Germany). Inst. fuer Anorganische und Analytische Chemie

    2017-08-01

    GdCuMg has been synthesized by induction-melting of the elements in a sealed niobium ampoule followed by annealing in a muffle furnace. The sample was studied by powder and single crystal X-ray diffraction: ZrNiAl type, P anti 62m (a=749.2(4), c=403.3(1) pm), wR2=0.0242, 315 F{sup 2} values and 15 variables. Temperature dependent magnetic susceptibility measurements have revealed an experimental magnetic moment of 8.54(1) μ{sub B} per Gd atom. GdCuMg orders ferromagnetically below T{sub C}=82.2(5) K and based on the magnetization isotherms it can be classified as a soft ferromagnet.

  15. STUDY ON REDUCING AND MELTING BEHAVIOR OF MILL SCALE/PETROLEUM COKE BLEND

    Bruno Deves Flores

    2015-07-01

    Full Text Available Self-reducing tests were carried out under isothermal and non-isothermal condition in a muffle furnace, aiming to assess the reduction and melting of a self-reducing blend of mill scale and petroleum coke (85-15% in weight. The products obtained were analyzed by mass loss and wet analysis. Further investigations for the products from the non-isothermal condition were done by X-ray diffraction, nude eye inspection and carbon analyzer. It was observed that mass loss fraction and metallization degree are directly related and both increase with time and temperature. In the non-isothermal maximum mass loss was achieved in 8 minutes, reaching metallization degrees above 90%. It was observed that the reduction of iron oxide occurs mainly in solid state and the smelting of the samples is directly related to the iron carburization process. Thus, the use of self-reducing mixtures shows a possible way to recycle mill scale.

  16. γ-ray activity in bituminous, subbituminous and lignite coals

    Barber, D.E.; Giorgio, H.R.

    1977-01-01

    Specimens of three different types of coal from four different geographical locations (Montana, North Dakota, Illinois and Pennsylvania) were examined by γ-ray spectrometry. Some samples were ashed in a muffle furnace. Other samples included pulverized coal, slag and fly ash from an electric power generating station. Activity from the 232 Th and 238 U series was present in all samples. Activity varied widely depending upon the source of the coal. The results indicate a need for additional examination of activity in coal to: (1) establish more precisely the relative environmental impact of coal-fired power stations compared with nuclear ones, (2) indicate the degree of sophistication required in environmental surveillance programs involving areas where both nuclear and coal-fired power stations are operational, and (3) determine the occupational exposure risks in mining operations. (author)

  17. Influence of the external heating type in the morphological and structural characteristics of alumina powder prepared by combustion reaction

    Cordeiro, V.V.; Freitas, N.L.; Viana, K.M.S.; Dias, G.; Costa, A.C.F.M.; Lira, H.L.

    2009-01-01

    The aim of this work is to evaluate the influence of the external heating in the morphological and structural characteristics of the alumina powder prepared by combustion reaction. It was evaluated different types of external heating: muffle oven, microwave oven and ceramic plate with electrical spiral resistance. The powders were prepared according to the propellants and explosives theory, using urea in the stoichiometric proportion (Φe = 1). During the synthesis parameters such as flame combustion time and temperature were measured. The structural and morphological characteristics of the powders were evaluate by XRD, particle size distribution, SEM and nitrogen adsorption (BET). The results showed the production of a-alumina as unique phase and formed by agglomerates with irregular plate shape of thin particles for all studied conditions. The powders prepared by electrical oven presented small particle size, with narrow agglomerates size distribution. (author)

  18. Effects of La0.2Ce0.6Eu0.2F3 nanocrystals capped with polyethylene glycol on human pancreatic cancer cells in vitro

    Withers, Nathan J.; Glazener, Natasha N.; Rivera, Antonio C.; Akins, Brian A.; Armijo, Leisha M.; Plumley, John B.; Cook, Nathaniel C.; Sugar, Jacqueline M.; Chan, Rana; Brandt, Yekaterina I.; Smolyakov, Gennady A.; Heintz, Philip H.; Osiński, Marek

    2013-02-01

    Lanthanide fluoride colloidal nanocrystals offer a way to improve the diagnosis and treatment of cancer through the enhanced absorption of ionizing radiation, in addition to providing visible luminescence. In order to explore this possibility, tests with a kilovoltage therapy unit manufactured by the Universal X-Ray Company were performed to estimate the energy sensitivity of this technique. La0.2Ce0.6Eu0.2F3 nanocrystals capped with polyethylene glycol of molecular weight 6000 were synthesized, suspended in deionized water, and made tolerant to biological ionic pressures by incubation with fetal bovine serum. These nanocrystals were characterized by dynamic light scattering, muffle furnace ashing, and photoluminescence spectroscopy. Clonogenic assays were performed on the cells to assay the cytotoxicity and radiotoxicity of the nanocrystals on the human pancreatic cancer cell line PANC-1, purchased from ATCC.

  19. Copaifera cf. langsdorfii Desf. AND Dipteryx odorata (Aubl. Wild. CHARCOAL ANATOMY

    Francielli Rodrigues Ribeiro Batista

    2012-11-01

    Full Text Available Species discrimination by charcoal analysis is possible, because the wood anatomical structure remains almost intact after carbonization process. Studies in this area are rare and directed to paleoecology and paleoetnobotany. Thus, this study aimed to characterize anatomically the carbonized wood of Copaifera cf. langsdorfii Desf. and Dipteryx odorata (Aubl. Wild., proceeding from north region of Mato Grosso state, in order to provide information to manage its illegal commerce. From each species were carbonized ten samples with dimensions of 2 x 2 x 5 cm in muffle furnace, in stage program and highest temperature of 450°C for 30 minutes, for seven hours. Final temperature applied does not change anatomical structure from both species, allowing its differentiation. The crystals formatremained without alterations, being visible little split.

  20. 90Sr and 137Cs in total diet

    1978-01-01

    Under the commission of Science and Technology Agency, Japan Chemical Analysis Center has analyzed total diet samples collected from 30 prefectures, and determined the content of strontium-90 and cesium-137 in these samples. Each prefectural public health laboratory and institute have collected 2 times a year all the daily regular diet consumed for five persons, namely three meals and other eating between meals. These samples were collected at Japan Chemical Analysis Center after carbonation without smoke rising. At Japan Chemical Analysis Center, these samples were ashed in an electric muffle furnace. And the ash to which both some carriers and hydrochloric acid were added, was destroyed under heating. The nuclides were dissolved into hydrochloric acid and filtrated, after it was added with nitric acid and heated to dryness. The filtrate was radiochemically analyzed for strontium-90 and cesium-137. (author)

  1. Strontium-90 and cesium-137 in total diet

    1977-01-01

    Under the commission of Science and Technology Agency, Japan Chemical Analysis Center has analysed total diet samples collected from 30 prefectures (2 times per year), and determined to content of strontium-90 and cesium-137 in these samples. Each Prefectural public health laboratories and institutes have collected all the daily regular diet consumed for five persons, namely three meals and other eating between meals, for radiochemical analysis in polyethylene containers. These samples were collected to Japan Chemical Analysis Center after carbonization without smoke rising in the large stainless dish. At Japan Chemical Analysis Center, these samples were asked in an electric muffle furnance. And the ask to which both some carriers and hydrochloric acid were added, was destroyed under heating. The nuclides were dissolved into hydrochloric acid and filtrated, after it was added with nitric acid and heated to dryness. The filtrates was analysed for strontium-90 and cesium-137 using the method recommended by Science and Technology Agency. (author)

  2. Strontium-90 and cesium-137 in sea fish from Nov. 1983 to Jun. 1984

    1984-01-01

    Sr-90 and Cs-137 in sea fish were determined using radiochemical analysis. Seven species of fish (Branchiostegus sp., Katsuwonus pelamis, Limanda herzensteini, Sillago sihama, Pneumatophorus japonicus, Caesio chrysozonus cuvier, and Sebastes Inermis) were collected during the fishing season from 8 sampling locations. Only the edible part was used in case of larger sized fish, and the whole part was used in case of smaller ones. Each sample was weighed and placed in a stainless steel pan or a porcelain dish. After carbonized, the sample was ashed in an electric muffle furnace. The maximum values of Sr-90 was 1.0+-0.25 pCi/kg in Sebastes Inermis collected from Yamaguchi in April 1984; the maximum value of Cs-137 was 14.0+-0.60 pCi/kg in Katsuwonus pelamis collected from Kochi in May 1984. (Namekawa, K.)

  3. Comparison of removed dentin thickness with hand and rotary instruments

    Shahriari, Shahriar; Abedi, Hasan; Hashemi, Mahdi; Jalalzadeh, Seyed Mohsen

    2009-01-01

    INTRODUCTION: The aim of this study was to evaluate the amount of dentine removed after canal preparation using stainless steel (SS) hand instruments or rotary ProFile instruments. MATERIALS AND METHODS: Thirty-six extracted human teeth with root canal curvatures less than 30º were embedded in clear polyester resin. The roots were cut horizontally at apical 2, 4 and 7 mm. Dentin thickness was measured at each section and the sections were accurately reassembled using a muffle. Root canals were randomly prepared by SS hand instruments or rotary ProFile instruments. Root sections were again separated, and the remaining dentin thickness was measured. Mann-Whitney U and t tests were performed for analytic comparison of the results. RESULTS: The thickness of removed dentin was significantly different between the two used methods (Pinstrumentation group (Protary instrumentation prepares root canals with a greater conservation of tooth structure. PMID:23940489

  4. Microwave sintering of ZnO nanopowders and characterization for gas sensing

    Bai Zikui; Xie Changsheng; Zhang Shunping; Xu Weilin; Xu Jie

    2011-01-01

    Thick film gas sensors based on ZnO nanopowders were fabricated by using microwave sintering. The surface and cross section morphologies were characterized by field-emission scanning electron microscopy (FE-SEM). The stability of the microstructure was studied by impedance spectroscopy. The results showed that the shape of the nanoparticles was not changed through microwave sintering, and the thick films had the more dense microstructures than that by muffle oven sintering. The resistance-temperature characteristic and the responses to toluene, methanol and formaldehyde revealed that the microwave sintering technique could effectively control the growth of ZnO nanoparticles, realize the uniform sintering of thick film, gain the stable microstructure and improve the response of sensor. In addition, the formative mechanism of the thick film microstructure was proposed according to microwave sintering mechanism.

  5. Organic carbon determination in histosols and soil horizons with high organic matter content from Brazil Determinação do carbono orgânico em organossolos e solos com horizontes com elevado conteúdo de matéria orgânica

    Marcos Gervasio Pereira

    2006-04-01

    Full Text Available Soil taxonomy systems distinguish mineral soils from organic soils based on the amount of soil organic carbon. Procedures adopted in soil surveys for organic carbon measurement are therefore of major importance to classify the soils, and to correlate their properties with data from other studies. To evaluate different methods for measuring organic carbon and organic matter content in Histosols and soils with histic horizons, from different regions of Brazil, 53 soil samples were comparatively analyzed by the methods of Walkley & Black (modified, Embrapa, Yeomans & Bremner, modified Yeomans & Bremner, muffle furnace, and CHN. The modified Walkley & Black (C-W & B md and the combustion of organic matter in the muffle furnace (OM-Muffle were the most suitable for the samples with high organic carbon content. Based on regression analysis data, the OM-muffle may be estimated from C-W & B md by applying a factor that ranges from 2.00 to 2.19 with 95% of probability. The factor 2.10, the average value, is suggested to convert results obtained by these methods.Sistemas taxonômicos distinguem horizontes e/ou camadas minerais das orgânicas baseando-se na quantidade de carbono orgânico. Assim, o procedimento adotado em pesquisas para a quantificação do conteúdo de carbono orgânico é de grande importância para a classificação das terras e correlacionar as suas propriedades com dados de outros estudos. Com o objetivo de avaliar os diferentes métodos para medir o conteúdo de carbono orgânico e de matéria orgânica em Organossolo e solos com elevados teores de matéria orgânica, de diferentes regiões do Brasil, cinqüenta e três amostras de terra foram comparativamente analisadas pelos métodos de Walkley & Black (modificado, Embrapa, Yeomans & Bremner, Yeomans & Bremner modificado, forno mufla, e CHN. O método Walkley & Black modificado (C-W & B md e a combustão de matéria orgânica no forno mufla (MO-Mufla revelaram-se mais satisfat

  6. Strontium-90 and cesium-137 in total diet from Oct. 1983 to Jul. 1984

    1984-01-01

    Sr-90 and Cs-137 in total diet were determined using radiochemical analysis. A full one day ordinary diet including three meales, water, tea, and other in-between snacks for five persons was collected as a sample of ''total diet'' from 29 sampling locations. The sample in a large stainless steel pan was carbonized carefully by direct application of gas flame, and was transfered to a porcelain dish and then ashed at 500 0 C in an electric muffle furnace. The maximum values of Sr-90 and Cs-137 were 5.8+-0.47 pCi.p -1 .d -1 and 19.0+-0.60 pCi.p -1 .d -1 in total diet collected from Akita in July 1984. (Namekawa, K.)

  7. Strontium-90 and cesium-137 in total diet (from Jun. 1983 to Dec. 1983)

    1983-01-01

    Sr-90 and Cs-137 in total diet were determined using radiochemical analysis. A full one day ordinary diet including three meals, water, tea and other in-between snacks for five persons was collected as a sample of ''total diet'' from 27 sampling locations. The sample in a large stainless steel pan was carbonized carefully by direct application of gas flame, and was transfered to a porcelain dish and then ashed at 500 0 C in an electric muffle furnace. The maximum values of Sr-90 and Cs-137 in total diet were 5.4 +- 0.43 pCi.p -1 .d -1 from Kochi in November 1983 and 5.5 +- 0.32 pCi.p -1 .d -1 from Akita in November 1983, respectively. (Namekawa, K.)

  8. Strontium-90 and cesium-137 in total diet (from Jun. 1984 to Dec. 1984)

    1984-01-01

    Sr-90 and Cs-137 in total diet were determined using radiochemical analysis. A full one ordinary diet including three meals, water, tea and other in-between snacks for five persons was collected as a sample of ''total diet'' from 20 sampling locations. The sample in a large stainless steel pan was carbonized carefully by direct application of gas flame, and was transferred to a porcelain dish and then ashed at 500 deg C in an electric muffle furnace. The maximum values of Sr-90 and Cs-137 in total diet were 5.3 +- 0.47 pCi · p -1 · d -1 and 5.4 +- 0.38 pCi · p -1 · d -1 , respectively, from Hokkaido in December 1984. (Namekawa, K.)

  9. Strontium-90 and cesium-137 in total diet (from Oct. 1984 to Jul. 1985)

    1985-01-01

    Sr-90 and Cs-137 in total diet were determined using radiochemical analysis. A full one day ordinary diet including three meals, water, tea and other in-between snacks for five persons was collected as a sample of ''total diet'' from 27 sampling locations. The sample in a large stainless steel pan was carbonized carefully by direct application of gas flame, and was transferred to a porcelain dish and then ashed at 500 deg C in an electric muffle furnace. The maximum values of Sr-90 and Cs-137 in total diet were 4.5 +- 0.43 pCi/p·d from Niigata in June 1985 and 4.9 +- 0.40 pCi/p·d from Fukushima in January 1985, respectively. (Namekawa, K.)

  10. Effect of fire on phosphorus forms in Sphagnum moss and peat soils of ombrotrophic bogs.

    Wang, Guoping; Yu, Xiaofei; Bao, Kunshan; Xing, Wei; Gao, Chuanyu; Lin, Qianxin; Lu, Xianguo

    2015-01-01

    The effect of burning Sphagnum moss and peat on phosphorus forms was studied with controlled combustion in the laboratory. Two fire treatments, a light fire (250 °C) and a severe fire (600 °C), were performed in a muffle furnace with 1-h residence time to simulate the effects of different forest fire conditions. The results showed that fire burning Sphagnum moss and peat soils resulted in losses of organic phosphorus (Po), while inorganic phosphorus (Pi) concentrations increased. Burning significantly changed detailed phosphorus composition and availability, with severe fires destroying over 90% of organic phosphorus and increasing the availability of inorganic P by more than twofold. Our study suggest that, while decomposition processes in ombrotrophic bogs occur very slowly, rapid changes in the form and availability of phosphorus in vegetation and litter may occur as the result of forest fires on peat soils. Copyright © 2014 Elsevier Ltd. All rights reserved.

  11. Determination of fluorine injuries on an alley of linden trees in the immediate proximity of a brick kiln near Ismaning by leaf analysis and aerial infrared photography

    Baum, I F

    1974-01-01

    Upon discovery of severe leaf injuries in an alley of linden trees near Ismaning (Munich, West Germany), leaf samples were taken from the lower branches of the trees at three different time periods. The samples were dried, ground, and ashed according to the method by Buck (ashing of 5 g dry substance in a nickel vessel at a temperature of 450 to 500 C in a muffle furnace). The fluorine in the ash was determined by the method of Buck and Stratman. A relationship was determined between the fluorine concentration of the leaves and the location of the tree with regard to a brick kiln close to the alley. The severity of necrosis not only corresponded to the determined fluorine concentration but also the gray tone of the infrared photographs. The results led to the initiation of measures for reduction of the fluorine emissions by this brick kiln. 17 references.

  12. Effect of sterilization on mineralization of straw and black carbon

    Bobul'ská, Lenka; Bruun, Sander; Fazekašová, Danica

    2013-01-01

    vulgare) with a specific activity 2.9 MBq g C. Production of BC was implemented at 300 °C for 24 h in a muffle oven, incubated in soil and C in the evolved CO was measured after 0.5, 1, 2, 4, 8, 16, 26 and 40 days. BC showed much lower and slow evolution of CO than the plant material which refers to high...... the plant material proceeded with a lag phase while CO evolution from the charcoals showed no lag phase. This indicates that microorganisms are not involved in the initial flush of carbon emitted from the BC. We suggest that an alternative source may be carbonates on the surfaces of the BC, but another...

  13. Characterization and study of the behavior of wire Ti-Ni with shape memory effect enables manufacture of actuators; Estudo da caracterizacao e do comportamento de fios de Ti-Ni com efeito memoria de forma viabilizando fabricacao de atuadores

    Pina, E.A.C.; Araujo Filho, O.O. de; Urtiga Filho, S.L.; Gonzalez, C.H., E-mail: kikipina@hotmail.co [Universidade Federal de Pernambuco (DEM/CTG/UFPE), Recife, PE (Brazil). Centro de Tecnologia e Geociencias. Dept. de Engenharia Mecanica

    2010-07-01

    This work aims to characterize the wire commercial Ti-Ni of 1.27 mm in diameter with shape memory effect for the development of helical springs with the function of sensor / actuator. After heat treatment, the transformation temperatures, the presence of precipitates, the degree of damping, maximum stress of rupture, modulus of elasticity, the presence of phase R, the behavior of the alloy under tension, will be analyzed and compared in each situation. For characterization we used several methods including: heat treatment, Differential Scanning Calorimetry (DSC), tensile, dynamic mechanical analysis (DMA), X-ray diffraction, thermomechanical cycling. The wires were cut into pieces and heat-treated at 400 deg C with variation of time in muffle furnaces and quenching in water at 25 deg C. (author)

  14. Determinations of total residue, total oxide and density of high-level liquid waste (HLLW) by gravimetric method

    Li Yun; Gao Yueying; Yang Ming; Jin Liyun

    1992-01-01

    Gravimetric method for determination of total residue, total oxide and density of HLLW is developed. An aliquot of the original HLLW solution is piped on to the small quartz disc and put into the mini muffle furnace carefully. It is first heated to below 100 degree C (for 1.5 hours to remove the free water, and then heated to 180 degree C for 2 hours to remove the crystal water in a furnace. The total residue is weighed at room temperature. The precision is better than 3% for the determination of total residue and total oxide. An aliquot of the original HLLW solution is piped into the weighing bottle and weighed. The precision is better than 1%

  15. Case report: study of a beagle with a malignant ectopic thyroid tumor

    Brewster, R.D.; Miller, C.W.; Stephens, L.C.; Jaenke, R.S.

    1981-01-01

    A Segment III beagle was noted clinically to have cervical edema and muffled heart sounds. Radiographically, masses were found at the base of the heart and throughout the lung field. An electrocardiogram revealed right bundle branch blockage. An echocardiogram demonstrated thickening of the left ventricle and conduction disturbances in the heart which could not be visualized by conventional diagnostic techniques. At necropsy, a neoplasm was found at the base of the heart that had extended into the pulmonary artery, right atria-auricle, interatrial septum, dorsal interventricular septum, and between the pericardium and epicardium over the surface of the right and left ventricles. The location of the tumor masses accounted for the clinical signs and the abnormalities in the electrocardiogram and echocardiogram. Light and electron microscopic examination of the neoplasm at the base of the heart and metastatic neoplasms in the lungs, kidney, and pancreas established a diagnosis of malignant ectopic thyroid tumor

  16. Combustion synthesis by reaction and characterization of nano ferrites: study of fuel aniline, citric and its mixture; Sintese por reacao de combustao e caracterizacao de nanoferritas Ni-Zn: estudo dos combustiveis anilina, acido citrico e sua mistura

    Silva, M.C. da; Coutinho, J.P.; Costa, A.C.F.M., E-mail: normanda@ufcg.edu.br [Universidade Federal de Campina Grande (UFCG), PB (Brazil). Unidade Academica de Engenharia de Materiais; Kiminami, R.H.G.A. [Universidade Federal de Sao Carlos (UFSCar), SP (Brazil). Departamento de Engenharia de Materiais; Freitas, N.L. de [Universidade Federal de Campina Grande (UFCG), PB (Brazil). Unidade Academica de Tecnologia do Desenvolvimento

    2012-07-01

    The present study aims to evaluate the influence of aniline and citric acid used alone and combined in a ratio of 50% each in the characterization of NiZn ferrite synthesized by combustion reaction method in a muffle furnace. Measurements were made of temperature and reaction time. The nano-powders were characterized by XRD, EDX, textural analysis and SEM. The highest temperature was achieved by the reaction using the mixture of fuel and increased reaction time using citric acid. The nano ferrites using different fuels, and the mixture changed phases, the crystallite size and decreased surface area of the samples with aniline, citric acid and a mixture of both, respectively. The powder morphology ranged from presenting the formation of irregular blocks for the use of citric agglomerated in the form of skeins with aniline and a mixture to agglomerate larger particles. (author)

  17. Combustion synthesis by reaction and characterization of nano ferrites: study of fuel aniline, citric and its mixture

    Silva, M.C. da; Coutinho, J.P.; Costa, A.C.F.M.; Kiminami, R.H.G.A.; Freitas, N.L. de

    2012-01-01

    The present study aims to evaluate the influence of aniline and citric acid used alone and combined in a ratio of 50% each in the characterization of NiZn ferrite synthesized by combustion reaction method in a muffle furnace. Measurements were made of temperature and reaction time. The nano-powders were characterized by XRD, EDX, textural analysis and SEM. The highest temperature was achieved by the reaction using the mixture of fuel and increased reaction time using citric acid. The nano ferrites using different fuels, and the mixture changed phases, the crystallite size and decreased surface area of the samples with aniline, citric acid and a mixture of both, respectively. The powder morphology ranged from presenting the formation of irregular blocks for the use of citric agglomerated in the form of skeins with aniline and a mixture to agglomerate larger particles. (author)

  18. Congenital peritoneopericardial diaphragmatic hernia in a terrier dog

    Reza Kheirandish

    2014-06-01

    Full Text Available A one-month-old male terrier dog was referred in shock status with a history of anorexia, tachypnea, abdominal distention and progressive weight loss. Auscultation of right side of the lungs found enhanced respiratory noises. The thorough auscultation of the opposite side of the chest revealed the presence of typical intestinal sounds. Cardiac auscultation revealed muffled heart sounds and a diminished palpable precordial cardiac impulse was evident. The radiograph showed the presence of gas within the bowel in abrupt contrast to the adjacent structures of soft tissue opacity. Conservative treatment was failed and the animal died. At necropsy, cranial displacement of abdominal viscera into the pericardial sac was seen. A definitive diagnosis of peritoneopericardial diaphragmatic hernia was made. Although congenital pericardial diseases are rare in dogs, awareness of the clinical manifestation of these kinds of defects combined with early use of available imaging modalities can yield a preoperative diagnosis.

  19. Thermal and Physical Properties of Plutonium Dioxide Produced from the Oxidation of Metal: a Data Summary

    Wayne, David M. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2014-01-13

    The ARIES Program at the Los Alamos National Laboratory removes plutonium metal from decommissioned nuclear weapons, and converts it to plutonium dioxide in a specially-designed Direct Metal Oxidation furnace. The plutonium dioxide is analyzed for specific surface area, particle size distribution, and moisture content. The purpose of these analyses is to certify that the plutonium dioxide powder meets or exceeds the specifications of the end-user, and the specifications for the packaging and transport of nuclear materials. Analytical results from plutonium dioxide from ARIES development activities, from ARIES production activities, from muffle furnace oxidation of metal, and from metal that was oxidized over a lengthy time interval in air at room temperature, are presented. The processes studied produce plutonium dioxide powder with distinct differences in measured properties, indicating the significant influence of oxidation conditions on physical properties.

  20. Uvula Bee Sting: A Case Report

    Jarungjit Kraiwattanapong

    2016-05-01

    Full Text Available There have been several reports of Hymenoptera sting around the world, but only a few have been reported being stung at the oropharynx which is considered uncommon and can cause life threatening condition. The authors reported a case of a 41-year-old healthy man who had a bee sting at his uvula 4 hours before coming to the hospital. He felt a lump in his throat and had some degrees of difficult swallowing and breathing and had muffled voice. The uvula was swollen and there was a pinpoint penetrating lesion at the anterior surface of the uvula. No stinger was identified. Vital signs were stable with no stridor nor wheezing. Intraoperative examination to identify stinger was conducted and tissue at the stinging area was excised to confirm complete removal of the possible embedded foreign body.

  1. Radioecological investigations on tree rings of spruce

    Haas, G.; Mueller, A.

    1995-01-01

    Tree ring analysis contributes essentially to the explanation of physiological and element-specific transport phenomena in trees. After the accident in Chernobyl the behaviour of Cs-134 and Cs-137 in trees is most informative for the prediction of the future development of the distribution of these elements. In this study the uptake and the long term behaviour of Cs-134, Cs-137, Pb-210, Ra-226, Ra-228, K-40, Th-228, Th-230, Th-232, U-234 and U-238 in tree rings of spruce are examined by α- and γ-spectrometry. All samples are dried at 105C and ashed at 450C in a muffle furnace. The distributions found in the tree rings vary for different radionuclides. A soil profile from the spruce stand provides additional information

  2. Adsorption of arsenate from aqueous solution by rice husk-based adsorbent

    Khan, Taimur; Chaudhuri, Malay

    2013-01-01

    Rice husk-based adsorbent (RHBA) was prepared by burning rice husk in a muffle furnace at 400°C for 4 h and adsorption of arsenate by the RHBA from aqueous solution was examined. Batch adsorption test showed that extent of arsenate adsorption depended on contact time and pH. Equilibrium adsorption was attained in 60 min, with maximum adsorption occurring at pH 7. Equilibrium adsorption data were well described by the Freundlich isotherm model. Freundlich constants K f and 1/n were 3.62 and 2, respectively. The RHBA is effective in the adsorption of arsenate from water and is a potentially suitable filter medium for removing arsenate from groundwater at wells or in households.

  3. Strontium-90 and cesium-137 in freshwater fish

    1983-01-01

    Sr-90 and Cs-137 in freshwater fish were determined using radiochemical analysis. Three species of fish (Carassius auratus, Cyprinus carpio, and Hypomesus transpacificus nipponensis) were collected during the fishing season from seven sampling locations. Only edible part was used in case of larger sized fish, and the whole part was used in case of smaller ones. Each sample was weighed and placed in a stainless steel pan or a porcelain dish. After carbonized, the sample was ashed in an electric muffle furnace. The maximum values of Sr-90 and Cs-137 were 49.0 +- 1.30 pCi/kg and 8.5 +- 0.64 pCi/kg in Carassius auratus collected from Kyoto and Fukui, respectively, in December 1983. (Namekawa, K.)

  4. Strontium-90 and cesium-137 in freshwater fish (from Jul. 1984 to Dec. 1984)

    1984-01-01

    Sr-90 and Cs-137 in freshwater fish were determined using radiochemical analysis. Three species of fish (Cyprinus carpio, Carassius auratus, and Hypomesus transpacificus nipponensis) were collected during the fishing season from eight sampling locations. Only the edible part was used in case of larger sized fish, and the whole part was used in case of smaller ones. Each sample was weighed and placed in a stainless steel pan or a porcelain dish. After carbonized, the sample was ashed in an electric muffle furnace. The maximum value of Sr-90 was 96 +- 1.7 pCi/kg in Cyprinus carpio collected from Akita in July 1984; and that of Cs-137 was 11 +- 0.7 pCi/kg in Carassius auratus from Fukui in December 1984. (Namekawa, K.)

  5. Characterization and study of the behavior of wire Ti-Ni with shape memory effect enables manufacture of actuators

    Pina, E.A.C.; Araujo Filho, O.O. de; Urtiga Filho, S.L.; Gonzalez, C.H.

    2010-01-01

    This work aims to characterize the wire commercial Ti-Ni of 1.27 mm in diameter with shape memory effect for the development of helical springs with the function of sensor / actuator. After heat treatment, the transformation temperatures, the presence of precipitates, the degree of damping, maximum stress of rupture, modulus of elasticity, the presence of phase R, the behavior of the alloy under tension, will be analyzed and compared in each situation. For characterization we used several methods including: heat treatment, Differential Scanning Calorimetry (DSC), tensile, dynamic mechanical analysis (DMA), X-ray diffraction, thermomechanical cycling. The wires were cut into pieces and heat-treated at 400 deg C with variation of time in muffle furnaces and quenching in water at 25 deg C. (author)

  6. Use of urethane foam in preparing for decontamination and decommissioning of radioactive facilities

    1981-01-01

    Portable urethane foam generating equipment has been in use for 15 to 20 years for a large number of applications, such as roof systems, tank insulation, and building insulation. Still another industrial application is its use in the decontamination and decommissioning of radioactive facilities at Mound Facility. The major problems encountered with urethane foams were with the packaging and stabilization procedures. The operation for spraying the foam on interior surfaces and equipment involved getting the gun inside without opening up the interior to the outside environment. A Gusmer FF proportioner and Model D spray gun was used for this operation. The gun was modified so that the trigger could be remotely located to facilitate its entry through a glovebox gloveport opening. The Model D gun has an air cap to blow foam off the tip of the gun. This cap was used to hold a plastic bag in place around the gun. The plastic bag is then put on a glove port and fastened securely. Urethane spray is applied on all exposed surfaces. This assures that all residual material is fixed for shipment. This simplifies cleaning operations as there is no need to remove the last trace of plutonium and results in a considerable shortening of the time required to prepare the gloveboxes. With the interior foamed, the gloveboxes are moved to the loading and packaging areas. Urethane foams are used to fill in the voids in our final shipping container. Radioactive waste materials are segregated according to the level of radioactive material present. One category is low level or low specific activity (LSA) and the other high level or Transuranic (TRU). Foam is used in TRU packages as packaging material to stabilize the loads and to help cushion against shock in transit on truck or railcar

  7. Decommissioning the Belgonucleaire Dessel MOX plant: presentation of the project and situation end august 2013

    Cuchet, J.M. [TRACTEBEL ENGINEERING, Avenue Ariane, 7, B1200 Brussels (Belgium); Libon, H.; Verheyen, C. [BELGONUCLEAIRE S.A. / N.V. Europalaan, 20, B2480 Dessel (Belgium); Bily, J. [STUDSVIK GmbH, Karlsruher Strasse, 20, D75179 Pforzheim,(Germany); Boden, S. [SCK-CEN, Boeretang, 200, B2400 Mol (Belgium); Joffroy, F. [TECNUBEL N.V., Zandbergen, 1, B2480 Dessel (Belgium); Walthery, R. [BELGOPROCESS, Gravenstraat, 73, B2480 Dessel (Belgium)

    2013-07-01

    Belgonucleaire has been operating the Dessel MOX plant at an industrial scale between 1986 and 2006. During this period, 40 metric tons of plutonium (HM) have been processed into 90 reloads of MOX fuel for commercial light water reactors. The decision to stop the production in 2006 and to decommission the MOX plant was the result of the shrinkage of the MOX fuel market due to political and commercial factors. As a significant part of the decommissioning project of the Dessel MOX plant, about 170 medium-sized glove-boxes and about 1.200 metric tons of structure and equipment outside the glove-boxes are planned for dismantling. The license for the dismantling of the MOX plant was granted by Royal Decree in 2008 and the dismantling started in March 2009. The dismantling works are carried out by an integrated organization under leadership and responsibility of Belgonucleaire; this organization includes 3 main contractors, namely Tecnubel N.V., the THV ('Tijdelijke HandelsVereniging') Belgoprocess / SCK-CEN and Studsvik GmbH and Tractebel Engineering as project manager. In this paper, after having described the main characteristics of the project, the authors review the different organizational and technical options considered for the decommissioning of the glove-boxes; thereafter the main decision criteria (qualification of personnel and of processes, confinement, cutting techniques and radiation protection, safety aspects, alpha-bearing waste management) are analyzed as well. Finally the progress, the feedback and the lessons learned at the end of August 2013 are presented, giving the principal's and contractors point of view. (authors)

  8. Develop and Manufacture an airlock sliding tray

    Lawton, Cindy M. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2014-02-26

    The goal of this project is to continue to develop an airlock sliding tray and then partner with an industrial manufacturing company for production. The sliding tray will be easily installed into and removed from most glovebox airlocks in a few minutes. Technical Approach: A prototype of a sliding tray has been developed and tested in the LANL cold lab and 35 trays are presently being built for the plutonium facility (PF-4). The current, recently approved design works for a 14-inch diameter round airlock and has a tray length of approximately 20 inches. The grant will take the already tested and approved round technology and design for the square airlock. These two designs will be suitable for the majority of the existing airlocks in the multitude of DOE facilities. Partnering with an external manufacturer will allow for production of the airlock trays at a much lower cost and increase the availability of the product for all DOE sites. Project duration is estimated to be 12-13 months. Benefits: The purpose of the airlock sliding trays is fourfold: 1) Mitigate risk of rotator cuff injuries, 2) Improve ALARA, 3) Reduce risk of glovebox glove breaches and glove punctures, and 4) Improve worker comfort. I have had the opportunity to visit many other DOE facilities including Savannah, Y-12, ORNL, Sandia, and Livermore for assistance with ergonomic problems and/or injuries. All of these sites would benefit from the airlock sliding tray and I can assume all other DOE facilities with gloveboxes built prior to 1985 could also use the sliding trays.

  9. Evaluation of the risk of a stripping perforation with gates-glidden drills: serial versus crown-down sequences

    Tauby Coutinho-Filho

    2008-03-01

    Full Text Available The aim of this study was to evaluate the remaining dentine/cementum thickness using Gates-Glidden burs in serial and crown-down sequences and to observe which of the two sequences is the safest for preparing mesial roots of molars. Thirty-six left and right human mandibular first molars were selected. Standard access cavities were made and initially explored with Flexofiles sizes 10 and 15 until the tip was visible at the apex. The teeth were embedded in a muffle specially developed for this study using a PVC tube with two parallel metal rods in its lid. Each tooth-block was sectioned 3 mm apically to the furcation using a low-speed saw with a diamond disc. The tooth-block was examined under a microscope and an initial image was captured by a digital video system with 8 X and 12 X magnifications. Finally, the tooth-blocks were reassembled in the muffle so that the canals could be instrumented. After instrumentation the area of each mesial canal as well as the smallest distance to the root furcation were measured again. The mesio-buccal canals (crown-down order and the mesio-lingual canals (serial sequence presented an average area of 0.46 ± 0.16 mm² and 0.88 ± 0.27 mm² (P < 0.01, respectively. The mean values of the smallest distance to the furcation for the mesio-buccal and mesio-lingual canals were 0.66 ± 0.19 mm and 0.39 ± 0.13 mm (P < 0.01, respectively. The remaining dentine/cementum thickness using Gates-Glidden burs was greater in the crown-down sequence than in the serial sequence.

  10. Plasma nitriding and simultaneous tempering of VF 800AT tool steel; Nitretacao por plasma com revenimento simultaneo do aco ferramenta VF 800AT

    Prass, Andre Ricardo; Fontana, Luis Cesar; Recco, Abel Andre Candido, E-mail: prass.andrericardo@gmail.com, E-mail: luis.fontana@udesc.br, E-mail: abel.recco@udesc.br [Universidade do Estado de Santa Catarina (UDESC), Joinville, SC (Brazil)

    2017-04-15

    Plasma nitriding of tool steels improves the surface hardness due to formation of diffusion zone and/or compound layer. The process parameters such as temperature, gas composition and dwell time, allow to control the layer thickness, the microstructure, the crystalline phases and the type of layer (for example white layer or diffusion zone). This paper discusses an alternative procedure for the heat treatment of tempering and surface treatment, both in plasma or combining conventional heat treatment with subsequent plasma nitriding. Carrying out both treatments in plasma could enable reduction in manufacturing costs, lower energy consumption and less time for tools manufacturing. Samples of VF800AT steel were treated and characterized (at surface and core of samples) through the following technique: X-ray diffraction, optical microscopy, scanning electron microscopy, micro-hardness profile and Rockwell C measurement. Temperature measurements during the plasma treatment, show that arise thermal gradient between the surface and the core of the samples. In this work, it was observed that the surface was up to 7% hotter than the core of sample, during the plasma treatment with temperature of magnitude about 5 x 10{sup 2} °C. This thermal gradient seems inherent to the plasma process, so that it can produce different microstructure, hardness and crystalline phases between core and edge of samples. However, when two tempering operations are prior carried out in a muffle furnace and the third tempering treatment is subsequently carried out simultaneously with the plasma nitriding, it is observed that the microstructure, the crystalline phases, hardness and micro hardness (in both, edge and core) are similar to treatments done in conventional mode cycle (in muffle furnace) with subsequent plasma nitriding. (author)

  11. The quantitation of buffering action II. Applications of the formal & general approach

    Schmitt, Bernhard M

    2005-01-01

    Background The paradigm of "buffering" originated in acid-base physiology, but was subsequently extended to other fields and is now used for a wide and diverse set of phenomena. In the preceding article, we have presented a formal and general approach to the quantitation of buffering action. Here, we use that buffering concept for a systematic treatment of selected classical and other buffering phenomena. Results H+ buffering by weak acids and "self-buffering" in pure water represent "conservative buffered systems" whose analysis reveals buffering properties that contrast in important aspects from classical textbook descriptions. The buffering of organ perfusion in the face of variable perfusion pressure (also termed "autoregulation") can be treated in terms of "non-conservative buffered systems", the general form of the concept. For the analysis of cytoplasmic Ca++ concentration transients (also termed "muffling"), we develop a related unit that is able to faithfully reflect the time-dependent quantitative aspect of buffering during the pre-steady state period. Steady-state buffering is shown to represent the limiting case of time-dependent muffling, namely for infinitely long time intervals and infinitely small perturbations. Finally, our buffering concept provides a stringent definition of "buffering" on the level of systems and control theory, resulting in four absolute ratio scales for control performance that are suited to measure disturbance rejection and setpoint tracking, and both their static and dynamic aspects. Conclusion Our concept of buffering provides a powerful mathematical tool for the quantitation of buffering action in all its appearances. PMID:15771784

  12. Study and determination of the ratio atoms between hydrogen and manganese in the manganese sulphate bath: procedure and calculation

    Castro, Leonardo C. de; Pereira, Walsan W.; Fonseca, Evaldo S.; Leite, Sandro P.

    2007-01-01

    The Brazilian Neutron Laboratory (LN) is part of the National Laboratory of Ionising Radiation of Metrology (LNMRI/IRD). It operates a system for absolute standardization for the measurement of the neutrons sources fluence. The Manganese Sulphate Bath (MSB) is part of this measurement system and was donated by the Bureau International de Poids et Measures (BIPM) in 1996. Since then at LN has become a fulfilled inquiry and measurements of fluence rate of a neutrons source Q. LN has carried through activities for the maintenance and dissemination of the reference values for this primary standard. Currently LN advances in two work lines: One of them is the study of the bath sensibility of the detection system (e), and the other is the study of f parameter, that measures the fraction of captured neutrons by 55 Mn. In the present work, we dedicate special attention to the measurement of the neutron fraction that depends on the amount of ratio atoms between hydrogen and manganese. A revision of the procedures and the experience involved with the measurement system gave chance to evaluate points for a metrology refinement leading to lower uncertainties and greater reliability degree values. To obtain the cited refinement, the following stages had been fulfilled: Firstly, the development of a tool for confection of standardized crucibles. Secondly, the characterization of the muffle used in the work through the survey of heating slopes. And finally, the study of the volatility with the temperature of manganese sulphate (MnSO4 + H2O) through a thermo-gravimetric analysis in the own muffle conditions used in the work. It was observed that the steady temperature of operation in the quantification of the Manganese in the solution meets above of 350 deg C and this caused a significant improvement over the measurement proceeding. This work demonstrates that the improvements in the proceeding for the determination of the NH/NMn ratio leads to the one of the goals longed for this

  13. Muscle Deoxygenation Causes Muscle Fatigue

    Murthy, G.; Hargens, A. R.; Lehman, S.; Rempel, D.

    1999-01-01

    Muscle fatigue is a common musculoskeletal disorder in the work place, and may be a harbinger for more disabling cumulative trauma disorders. Although the cause of fatigue is multifactorial, reduced blood flow and muscle oxygenation may be the primary factor in causing muscle fatigue during low intensity muscle exertion. Muscle fatigue is defined as a reduction in muscle force production, and also occurs among astronauts who are subjected to postural constraints while performing lengthy, repetitive tasks. The objectives of this research are to: 1) develop an objective tool to study the role of decreased muscle oxygenation on muscle force production, and 2) to evaluate muscle fatigue during prolonged glovebox work.

  14. Apparatus for posting materials into and out of enclosures

    Sperinck, W.A.; Ashcroft, K.C.

    1986-01-01

    The patent concerns an apparatus for posting toxic or radioactive materials into and out of a high integrity enclosure, such as a glovebox, through a port in a wall of the enclosure. The apparatus comprises a container for the materials, with a lid which is engageable with a door for the port, and the container is supported in a cradle. The door cannot be opened in the absence of a container in the cradle, and the container cannot be removed when the door and lid unit is away from the port. (UK)

  15. A view from the nuclear fuel reprocessing industry

    Smith, R.; Hartley, G.

    1982-01-01

    Radiological protection in UK nuclear industry is discussed, with special reference to British Nuclear Fuels Ltd. The following aspects are covered: historical introduction, relevant legislation and general principles; radioactive decay processes (fission, fission products, radio-isotopes, ionising radiations, neutrons); risk assessment (historical, biological radiation effects; ICRP recommendations, dose limits); cost effectiveness of protection; plant design principles; examples of containment (shielding, ventilation and contamination control required for various types of radioactive materials, e.g. fission products, plutonium, depleted uranium; fuel rod storage ponds and decanning caves; fission products at dissolution stage; glovebox handling of Pu operations; critical assembly of fissile materials; surface contamination control; monitoring radiation levels). (U.K.)

  16. MOX Fabrication Isolation Considerations

    Eric L. Shaber; Bradley J Schrader

    2005-08-01

    This document provides a technical position on the preferred level of isolation to fabricate demonstration quantities of mixed oxide transmutation fuels. The Advanced Fuel Cycle Initiative should design and construct automated glovebox fabrication lines for this purpose. This level of isolation adequately protects the health and safety of workers and the general public for all mixed oxide (and other transmutation fuel) manufacturing efforts while retaining flexibility, allowing parallel development and setup, and minimizing capital expense. The basis regulations, issues, and advantages/disadvantages of five potential forms of isolation are summarized here as justification for selection of the preferred technical position.

  17. Spectrochemical determination of tantalum in plutonium metal using direct current plasma emission spectrometry

    Fadeff, S.K.; Morris, W.F.

    1983-01-01

    Tantalum is determined by direct current plasma spectrometry after separation of plutonium from solution as PuF 3 . After centrifugation of the PuF 3 precipitate, a low level of plutonium remains in solution in sufficient quantity to cause spectral interferences. It is necessary to determine the plutonium by dc plasma spectrometry and apply a correction to determine low tantalum concentrations with good accuracy and precision. Tantalum can be determined down to 0.4 ppM in solution with a relative standard deviation of 10 percent. Better precision can be achieved at higher concentrations. The procedure is simple and convenient for glovebox work. 5 references, 1 figure, 1 table

  18. Protection, transfer, and maintenance of the MA23 bilateral servomanipulator

    Vertut, J.; Marchal, P.; Germond, J.C.; Francois, D.; Brossard, J.P.

    1978-01-01

    After a successful plasma torch cutting test, use of the MA23 in a large cell for maintenance in the new reprocessing plant is anticipated. A protective self-ventilated caisson with a boot is used. The arm is transferred into a decontamination-shielded box, then into a repair glove box. The caisson is repaired in a similar parallel line that has two connecting repair boxes. The recent two-operator glove-box recabling test showed the feasibility of this concept. Total labor was twice that of factory cabling labor. Arm improvement and tooling are being designed. A full, double-maintenance line mockup will be tested in mid-1979

  19. The centrifuge facility - A life sciences research laboratory for Space Station Freedom

    Fuller, Charles A.; Johnson, Catherine C.; Hargens, Alan R.

    1991-01-01

    The paper describes the centrifugal facility that is presently being developed by NASA for studies aboard the Space Station Freedom on the role of gravity, or its absence, at varying intensities for varying periods of time and with multiple model systems. Special attention is given to the design of the centrifuge system, the habitats designed to hold plants and animals, the glovebox system designed for experimental manipulations of the specimens, and the service unit. Studies planned for the facility will include experiments in the following disciplines: cell and developmental biology, plant biology, regulatory physiology, musculoskeletal physiology, behavior and performance, neurosciences, cardiopulmonary physiology, and environmental health and radiation.

  20. Overview of tritium systems for the Compact Ignition Tokamak

    Bartlit, J.R.; Gruetzmacher, K.M.; Fleming, R.B.

    1987-01-01

    The Compact Ignition Tokamak (CIT) is being designed at several laboratories to produce and study fully ignited plasma discharges. The tritium systems which will be needed for CIT include fueling systems and radiation monitoring and safety systems. Design of the tritium systems is the responsibility of the Tritium Systems Test Assembly (TSTA) at Los Alamos National Laboratory. Major new tritium systems for CIT include a pellet injector, an air detritiation system and a glovebox atmosphere detritiation system. The pellet injector is being developed at Oak Ridge National Laboratory. 7 refs., 2 figs

  1. System design description PFP thermal stabilization

    RISENMAY, H.R.

    1998-01-01

    The purpose of this document is to provide a system design description and design basis for the Plutonium Finishing P1ant (PFP) Thermal Stabilization project. The sources of material for this project are residues scraped from glovebox floors and materials already stored in vault storage that need further stabilizing to meet the 3013 storage requirements. Stabilizing this material will promote long term storage and reduced worker exposure. This document addresses: function design, equipment, and safety requirements for thermal stabilization of plutonium residues and oxides

  2. STS-95 Day 02 Highlights

    1998-01-01

    On this second day of the STS-95 mission, the flight crew, Cmdr. Curtis L. Brown, Pilot Steven W. Lindsey, Mission Specialists Scott E. Parazynski, Stephen K. Robinson, and Pedro Duque, and Payload Specialists Chiaki Mukai and John H. Glenn, are seen preparing a glovebox device in the middeck area of Discovery, an enclosed research facility that will support numerous science investigations throughout the mission. Payload Specialist John Glenn, activates the Microgravity Encapsulation Process experiment (MEPS). This experiment will study the formation of capsules containing two kinds of anti-tumor drugs that could be delivered directly to solid tumors with applications for future chemotherapy treatments and the pharmaceutical industry.

  3. Setting-up of a direct reading emission spectrometer and its adaptation for plutonium handling

    Page, A.G.; Godbole, S.V.; Kulkarni, M.J.; Porwal, N.K.; Thulasidas, S.K.; Sastry, M.D.; Srinivasan, P.S.

    1986-01-01

    A Jarrell-Ash 750 AtomComp 1100 series direct reading emission spectrometer was set up and its performance features were checked with regard to analysis of uranium-based samples using d.c. arc/inductively coupled argon plasma excitation techniques. The instrument has been subsequently modified to enable handling of plutonium-based samples. The modifications include building up of a specially designed glove-box around the excitation sources and consequent changes in the electro-mechanical controls associated with them. The modified system was extensively used for the trace metal assay of FBTR fuel sample. (author)

  4. A preview of a microgravity laser light scattering instrument

    Meyer, W. V.; Ansari, R. R.

    1991-01-01

    The development of a versatile, miniature, modular light scattering instrument to be used in microgravity is described. The instrument will measure microscopic particles in the size range of thirty angstroms to above three microns. This modular instrument permits several configurations, each optimized for a particular experiment. In particular, a multiangle instrument will probably be mounted in a rack in the Space Shuttle and on the Space Station. It is possible that a Space Shuttle glove-box and a lap-top computer containing a correlator card can be used to perform a number of experiments and to demonstrate the technology needed for more elaborate investigations.

  5. Field study of alpha characterization of a D ampersand D site using long-range alpha detectors

    Rawool-Sullivan, M.W.; Allander, K.S.; Bounds, J.A.; Koster, J.E.; MacArthur, D.W.; Sprouse, L.L.; Stout, D.; Vaccarella, J.A.; Vu, T.Q.

    1994-01-01

    A successful and cost-effective D ampersand D effort relies upon an accurate, real-time, in situ, and non-destructive method of characterization of contamination both before and after the decontamination process. Detector systems based on long-range alpha detection (LRAD) technology meet these criteria. Currently, LANL is in the process of investigating, designing, or building various surface monitors, various pipe monitors, and glove-box monitors. This paper describes the field studies conducted using detectors based on LRAD technology

  6. International Space Station Crew Restraint Design

    Whitmore, M.; Norris, L.; Holden, K.

    2005-01-01

    With permanent human presence onboard the International Space Station (ISS), crews will be living and working in microgravity, dealing with the challenges of a weightless environment. In addition, the confined nature of the spacecraft environment results in ergonomic challenges such as limited visibility and access to the activity areas, as well as prolonged periods of unnatural postures. Without optimum restraints, crewmembers may be handicapped for performing some of the on-orbit tasks. Currently, many of the tasks on ISS are performed with the crew restrained merely by hooking their arms or toes around handrails to steady themselves. This is adequate for some tasks, but not all. There have been some reports of discomfort/calluses on the top of the toes. In addition, this type of restraint is simply insufficient for tasks that require a large degree of stability. Glovebox design is a good example of a confined workstation concept requiring stability for successful use. They are widely used in industry, university, and government laboratories, as well as in the space environment, and are known to cause postural limitations and visual restrictions. Although there are numerous guidelines pertaining to ventilation, seals, and glove attachment, most of the data have been gathered in a 1-g environment, or are from studies that were conducted prior to the early 1980 s. Little is known about how best to restrain a crewmember using a glovebox in microgravity. In 2004, The Usability Testing and Analysis Facility (UTAF) at the NASA Johnson Space Center completed development/evaluation of several design concepts for crew restraints to meet the various needs outlined above. Restraints were designed for general purpose use, for teleoperation (Robonaut) and for use with the Life Sciences Glovebox. All design efforts followed a human factors engineering design lifecycle, beginning with identification of requirements followed by an iterative prototype/test cycle. Anthropometric

  7. Synthesis of Fluoroalkoxy Substituted Arylboronic Esters by Iridium-Catalyzed Aromatic C–H Borylation

    Batool, Farhat

    2015-08-17

    The preparation of fluoroalkoxy arylboronic esters by iridium-catalyzed aromatic C–H borylation is described. The fluoroalkoxy groups employed include trifluoromethoxy, difluoromethoxy, 1,1,2,2-tetrafluoroethoxy, and 2,2-difluoro-1,3-benzodioxole. The borylation reactions were carried out neat without the use of a glovebox or Schlenk line. The regioselectivities available through the iridium-catalyzed C–H borylation are complementary to those obtained by the electrophilic aromatic substitution reactions of fluoroalkoxy arenes. Fluoroalkoxy arylboronic esters can serve as versatile building blocks.

  8. Development of a lab-scale contaminated organic effluents treatment process using evaporation and supercritical water oxidation

    Turc, H.A.; Joussot-Dubien, C

    2004-07-01

    The organic liquid waste produced in the ATALANTE facility have to be treated in order to reduce the fire and contamination risks. Therefore, the Mini-DELOS process has been developed, which combines a low pressure evaporator in a shielded enclosure and a continuous supercritical water oxidation (SCWO) reactor in a glovebox. Evaporation makes it possible to evacuate the main organic stream as decontaminated distillates to an industrial incinerator. The remaining residue, concentrating the radioactivity can be converted through SCWO into a contaminated aqueous effluent, fully compatible with the existing outlets of the facility. The preliminary results of the first year of active operation of the Mini- DELOS process are here presented. (authors)

  9. DYMAC digital electronic balance

    Stephens, M.M.

    1980-06-01

    The Dynamic Materials Accountability (DYMAC) System at LASL integrates nondestructive assay (NDA) instruments with interactive data-processing equipment to provide near-real-time accountability of the nuclear material in the LASL Plutonium Processing Facility. The most widely used NDA instrument in the system is the DYMAC digital electronic balance. The DYMAC balance is a commercial instrument that has been modified at LASL for weighing material in gloveboxes and for transmitting the weight data directly to a central computer. This manual describes the balance components, details the LASL modifications, reviews a DYMAC measurement control program that monitors balance performance, and provides instructions for balance operation and maintenance

  10. Analysis of tritium mission FMEF/FAA fuel handling accidents

    Van Keuren, J.C.

    1997-11-18

    The Fuels Material Examination Facility/Fuel Assembly Area is proposed to be used for fabrication of mixed oxide fuel to support the Fast Flux Test Facility (FFTF) tritium/medical isotope mission. The plutonium isotope mix for the new mission is different than that analyzed in the FMEF safety analysis report. A reanalysis was performed of three representative accidents for the revised plutonium mix to determine the impact on the safety analysis. Current versions computer codes and meterology data files were used for the analysis. The revised accidents were a criticality, an explosion in a glovebox, and a tornado. The analysis concluded that risk guidelines were met with the revised plutonium mix.

  11. Methods to estimate equipment and materials that are candidates for removal during the decontamination of fuel processing facilities

    Duncan, D.R.; Valero, O.J.; Hyre, R.A.; Pottmeyer, J.A.; Millar, J.S.; Reddick, J.A.

    1995-02-01

    The methodology presented in this report provides a model for estimating the volume and types of waste expected from the removal of equipment and other materials during Decontamination and Decommissioning (D and D) of canyon-type fuel reprocessing facilities. This methodology offers a rough estimation technique based on a comparative analysis for a similar, previously studied, reprocessing facility. This approach is especially useful as a planning tool to save time and money while preparing for final D and D. The basic methodology described here can be extended for use at other types of facilities, such as glovebox or reactor facilities

  12. Decommissioning of a tritium-contaminated laboratory

    Harper, J.R.; Garde, R.

    1982-01-01

    A tritium laboratory facility at the Los Alamos National Laboratory, Los Alamos, New Mexico, was decommissioned in 1979. The project involved dismantling the laboratory equipment and disposing of the equipment and debris at an on-site waste disposal/storage area. The laboratory, constructed in 1953, was in service for tritium research and fabrication of lithium tritide components until 1974. The major features of the laboratory included 25 meters of gloveboxes and hoods, associated vacuum lines, utility lines, exhaust ducts, electrodryers, blowers, and laboratory benches. This report presents details on the decommissioning, health physics, waste management, environmental surveillance, and costs for the operation

  13. Electrically Driven Thermal Management: Flight Validation, Experiment Development, Future Technologies

    Didion, Jeffrey R.

    2018-01-01

    Electrically Driven Thermal Management is an active research and technology development initiative incorporating ISS technology flight demonstrations (STP-H5), development of Microgravity Science Glovebox (MSG) flight experiment, and laboratory-based investigations of electrically based thermal management techniques. The program targets integrated thermal management for future generations of RF electronics and power electronic devices. This presentation reviews four program elements: i.) results from the Electrohydrodynamic (EHD) Long Term Flight Demonstration launched in February 2017 ii.) development of the Electrically Driven Liquid Film Boiling Experiment iii.) two University based research efforts iv.) development of Oscillating Heat Pipe evaluation at Goddard Space Flight Center.

  14. High-temperature spectroscopy for nuclear waste applications

    Grant, P.M.; Robouch, P.; Torres, R.A.; Silva, R.J.

    1991-10-01

    Instrumentation has been developed to perform uv-vis-nir absorbance measurements remotely and at elevated temperatures and pressures. Fiber-optic spectroscopy permits the interrogation of radioactive species within a glovebox enclosure at temperatures ranging from ambient to >100 degree C. Spectral shifts as a function of metal- ligand coordination are used to compute thermodynamic free energies of reaction by matrix regression analysis. Pr 3+ serves as a convenient analog for trivalent actinides without attendant radioactivity hazards, and recent results obtained from 20 degree--95 degree C with the Pr-acetate complexation system are presented. Preliminary experimentation on Am(3) hydrolysis is also described. 16 refs., 1 tab

  15. Tritium confinement in a new tritium processing facility at the Savannah River Site

    Heung, L.K.; Owen, J.H.; Hsu, R.H.; Hashinger, R.F.; Ward, D.E.; Bandola, P.E.

    1991-01-01

    A new tritium processing facility, named the Replacement Tritium Facility (RTF), has been completed and is being prepared for startup at the Savannah River Site (SRS). The RTF has the capability to recover, purify and separate hydrogen isotopes from recycled gas containers. A multilayered confinement system is designed to reduce tritium losses to the environment. This confinement system is expected to confine and recover any tritium that might escape the process equipment, and to maintain the tritium concentration in the nitrogen glovebox atmosphere to less than 10 -2 μCi/cc tritium

  16. CSER 00-001 Criticality Safety Evaluation Report for Cementation Operations at the PFP

    DOBBIN, K.D.

    2000-04-18

    Glovebox HA-20MB is located in Room 235B of the 234-5Z Building at the Plutonium Finishing Plant. This enclosure contains mixers, mixer bowls, a crusher unit, an isolated inoperable conveyor unit, plutonium residue feed cans, cemented cans, and a feedwater container. Plutonium residue, not conducive to other forms of stabilization, is prepared for storage and ultimate disposal by cementation. The feed residue material cans can have plutonium contents of only a few grams or up to 200 grams. This evaluation accommodates this wide range of container fissile concentrations.

  17. The Institute of Radiochemistry, University of Liege, (Sart-Tilman), Belgium

    Duyckaerts, G.

    1977-01-01

    The Institute of Radiochemistry, erected in the new Sart-Tilman campus of the University of Liege has been especially planned and equipped for research on actinide chemistry. The two-floor building is well adapted for work in glove-boxes and well ventilated hoods with highly radioactive α-emitters. For the last ten years, research has been carried out in the following directions: synthesis and structural analysis of actinide compounds, thermodynamic evaluations on actinide compounds by microcalorimetry, electrochemistry of actinides in fused salts, redox properties of actinides in fused salts by absorption spectrophotometry, solution chemistry of actinides by solvent extraction, ion exchange and electrochemistry. (T.G.)

  18. Measuring Pu in a glove box using portable NaI and germanium detectors

    Hankins, D.E.

    1984-01-01

    A NaI crystal or germanium detector inside a portable lead shield can determine the amount of plutonium in a glove box. The number of counts required are defined and the locations outside the box where the detector needs to be positioned are given. The calculated accuracy for measuring the Pu when these locations are used is within +/-30% for most glove boxes. Other factors that may affect this accuracy, such as γ-ray absorption by glove-box materials, self-absorption by Pu, absorption by equipment in the glove box, and the limits of the counting equipment are also discussed

  19. Synthesis of Fluoroalkoxy Substituted Arylboronic Esters by Iridium-Catalyzed Aromatic C–H Borylation

    Batool, Farhat; Parveen, Shehla; Emwas, Abdul-Hamid M.; Sioud, Salim; Gao, Xin; Munawar, Munawar A.; Chotana, Ghayoor A.

    2015-01-01

    The preparation of fluoroalkoxy arylboronic esters by iridium-catalyzed aromatic C–H borylation is described. The fluoroalkoxy groups employed include trifluoromethoxy, difluoromethoxy, 1,1,2,2-tetrafluoroethoxy, and 2,2-difluoro-1,3-benzodioxole. The borylation reactions were carried out neat without the use of a glovebox or Schlenk line. The regioselectivities available through the iridium-catalyzed C–H borylation are complementary to those obtained by the electrophilic aromatic substitution reactions of fluoroalkoxy arenes. Fluoroalkoxy arylboronic esters can serve as versatile building blocks.

  20. Acclimatization of bananas ‘Prata-Anã’: methods and times for degreening after cold storage. = Climatização de bananas ‘Prata-Anã’: métodos e tempos para o desverdecimento após o armazenamento refrigerado.

    Marcos André de Souza Prill

    2011-08-01

    Full Text Available The control and standardization of the ripening of bananas brings economic advantages for the agricultural marketing. Thus, the aim of this study was to evaluate the application of methods (Muffling and Ethrel® and times of degreening aimed on the standardization and uniformity of bananas ‘Prata-Anã’ produced in Boa Vista/RR. After harvested, the fruits were selected in the form of bouquets, sanitized and stored under refrigeration for four periods of time, 0, 10, 20 and 30 days at 12 ± 1°C and 93 ± 2% RH. The treatments were: T1–muffling + 0 days of cold storage (CS, T2–Ethrel® + 0 days of cold storage,T3–muffling + 10 days of cold storage; T4–Ethrel® + 10 days of cold storage; T5–muffling + 20 days of cold storage; T6–Ethrel ® + 20 days of cold storage; T7–muffling + 20 days of cold storage; T8–Ethrel ® + 30 days of cold storage. After each period of cold storage, the fruits were subjected to degreening and analyzed with 1, 2, 3 and 4 days thereafter. The following analyses were performed: lesions in the skin, ethylene production, pH, titratable acidity (TA total and reduced sugars. There were no significant effects to determine what is the best method of muffling, however, it was found that the longer the period of cold storage, the lower was the period of maintaining the bananas ‘Prata-Anã’ quality after the degreening. It is thereforerecommended that the degreenning be carried out safely for up 20 days (12 ± 1oC e 93 ± 2% de R.U. It is expected, in this situation, the maintenance of the sensory quality attributes in bananas for at least three days, average marketing. =O controle e padronização do amadurecimento em bananas trazem vantagens econômicas para o setor agrícola de comercialização. Assim, objetivou-se com o presente trabalho avaliar a aplicação de métodos (Abafamento e Ethrel® e tempos de desverdecimento visando à padronização e uniformização de bananas ‘Prata-Anã’ produzidas

  1. Observation of an Aligned Gas - Solid "Eutectic" during Controlled Directional Solidification Aboard the International Space Station - Comparison with Ground-based Studies

    Grugel, R. N.; Anilkumar, A.

    2005-01-01

    Direct observation of the controlled melting and solidification of succinonitrile was conducted in the glovebox facility of the International Space Station (ISS). The experimental samples were prepared on ground by filling glass tubes, 1 cm ID and approximately 30 cm in length, with pure succinonitrile (SCN) in an atmosphere of nitrogen at 450 millibar pressure for eventual processing in the Pore Formation and Mobility Investigation (PFMI) apparatus in the glovebox facility (GBX) on board the ISS. Real time visualization during controlled directional melt back of the sample showed nitrogen bubbles emerging from the interface and moving through the liquid up the imposed temperature gradient. Over a period of time these bubbles disappear by dissolving into the melt. Translation is stopped after melting back of about 9 cm of the sample, with an equilibrium solid-liquid interface established. During controlled re-solidification, aligned tubes of gas were seen growing perpendicular to the planar solid/liquid interface, inferring that the nitrogen previously dissolved into the liquid SCN was now coming out at the solid/liquid interface and forming the little studied liquid = solid + gas eutectic-type reaction. The observed structure is evaluated in terms of spacing dimensions, interface undercooling, and mechanisms for spacing adjustments. Finally, the significance of processing in a microgravity environment is ascertained in view of ground-based results.

  2. Transfer arrangement for sealable enclosure

    Broxup, K.H.

    1991-01-01

    An arrangement for transferring items to or from e.g. a glovebox, in a closed moveable container. The glovebox port has a door having a non-rotatable outer portion and a rotatable inner portion. The container has a lid having a non-rotatable outer portion and a rotatable inner portion, the outer portion having a thin lip. The port has a thin lip which can be aligned with the lip of the lid. The outer portion of the door retains a peripheral sealing ring and the rim of the container retains a similar ring which can sandwich and bridge the two lips. The container is attached to the port by a rotatable locking ring. Via an externally rotatable and slidable shaft, lined at its inner end to the inner portion of the door, the latter is rotatable to disengage the door from the port, couple this inner portion to that of the lid, disengage the lid from the container, and move the coupled door and lid back and laterally away from the port, and vice versa. (author)

  3. Mixed low-level waste minimization at Los Alamos

    Starke, T.P.

    1998-01-01

    During the first six months of University of California 98 Fiscal Year (July--December) Los Alamos National Laboratory has achieved a 57% reduction in mixed low-level waste generation. This has been accomplished through a systems approach that identified and minimized the largest MLLW streams. These included surface-contaminated lead, lead-lined gloveboxes, printed circuit boards, and activated fluorescent lamps. Specific waste minimization projects have been initiated to address these streams. In addition, several chemical processing equipment upgrades are being implemented. Use of contaminated lead is planned for several high energy proton beam stop applications and stainless steel encapsulated lead is being evaluated for other radiological control area applications. INEEL is assisting Los Alamos with a complete systems analysis of analytical chemistry derived mixed wastes at the CMR building and with a minimum life-cycle cost standard glovebox design. Funding for waste minimization upgrades has come from several sources: generator programs, waste management, the generator set-aside program, and Defense Programs funding to INEEL

  4. Decontamination and size reduction of plutonium contaminated process exhaust ductwork and glove boxes

    LaFrate, P.; Elliott, J.; Valasquez, M.

    1996-01-01

    The Los Alamos National Laboratory (LANL) Decommissioning Program has decontaminated and demolished two filter plenum buildings at Technical Area 21 (TA-21). During the project a former hot cell was retrofitted to perform decontamination and size reduction of highly Pu contaminated process exhaust (1,100 ft) and gloveboxes. Pu-238/239 concentrations were as high a 1 Ci per linear foot and averaged approximately 1 mCi/ft. The Project decontamination objective was to reduce the plutonium contamination on surfaces below transuranic levels. If possible, metal surfaces were decontaminated further to meet Science and Ecology Group (SEG) waste classification guidelines to enable the metal to be recycled at their facility in oak Ridge, Tennessee. Project surface contamination acceptance criteria for low-level radioactive waste (LLRW), transuranic waste, and SEG waste acceptance criteria will be presented. Ninety percent of all radioactive waste for the project was characterized as LLRW. Twenty percent of this material was shipped to SEG. Process exhaust and glove boxes were brought to the project decontamination area, an old hot cell in Building 4 North. This paper focuses on process exhaust and glovebox decontamination methodology, size reduction techniques, waste characterization, airborne contamination monitoring, engineering controls, worker protection, lessons learned, and waste minimization. Decontamination objectives are discussed in detail

  5. Stabilization of Rocky Flats combustible residues contaminated with plutonium metal and organic solvents

    Bowen, S.M.; Cisneros, M.R.; Jacobson, L.L.; Schroeder, N.C.; Ames, R.L.

    1998-01-01

    This report describes tests on a proposed flowsheet designed to stabilize combustible residues that were generated at the Rocky Flats Environmental Technology Site (RFETS) during the machining of plutonium metal. Combustible residues are essentially laboratory trash contaminated with halogenated organic solvents and plutonium metal. The proposed flowsheet, designed by RFETS, follows a glovebox procedure that includes (1) the sorting and shredding of materials, (2) a low temperature thermal desorption of solvents from the combustible materials, (3) an oxidation of plutonium metal with steam, and (4) packaging of the stabilized residues. The role of Los Alamos National Laboratory (LANL) in this study was to determine parameters for the low temperature thermal desorption and steam oxidation steps. Thermal desorption of carbon tetrachloride (CCl 4 ) was examined using a heated air stream on a Rocky Flats combustible residue surrogate contaminated with CCl 4 . Three types of plutonium metal were oxidized with steam in a LANL glovebox to determine the effectiveness of this procedure for residue stabilization. The results from these LANL experiments are used to recommend parameters for the proposed RFETS stabilization flowsheet

  6. Key points for the design of Mox facilities

    Ducroux, R.; Gaiffe, L.; Dumond, S.; Cret, L.

    1998-01-01

    The design of a MOX fuel fabrication facility involves specific technical difficulties: - Process aspects: for example, its is necessary to meet the stringent requirements on the end products, while handling large quantities of powders and pellets; - Safety aspects: for example, containment of radioactive materials requires to use gloveboxes, to design process equipment so as to limit dispersion to the gloveboxes and to use systems for dust collection. - Technological aspects: for example, it is necessary to take into account maintenance early in the design, in order to lower the operation costs and lower the dose to the personnel. - Quality control and information systems: for example, it is necessary to be able to trace all the different products (powder lots, pellets, rods, assemblies). The design methods and organization set-up by COGEMA enables to master these technical difficulties during the different design steps and to obtain a MOX fabrication facility at the best performance versus cost compromise. These design methods rely mainly on: - taking into account all the different above mentioned constraints from the very beginning of the design process (by using the know-how resulting from experience feed-back, and also specific design tools developed by COGEMA and SGN); - launching a technical development and testing program at the beginning of the project and incorporating its results in the course of the design. (author)

  7. ZEPHYR tritium system

    Swansiger, W.; Andelfinger, C.; Buchelt, E.; Fink, J.; Sandmann, W.; Stimmelmayr, A.; Wegmann, H.G.; Weichselgartner, H.

    1982-04-01

    The ignition experiment ZEPHYR will need tritium as an essential component of the fuel. The ZEPHYR Tritium Systems are designed as to recycle the fuel directly at the experiment. An amount of tritium, which is significantly below the total throughput, for example 10 5 Ci will be stored in uranium getters and introduced into the torus by a specially designed injection system. The torus vacuum system operates with tritium-tight turbomolecular pumps and multi-stage roots pumps in order to extract and store the spent fuel in intermediate storage tanks at atmospheric pressure. A second high vacuum system, similar in design, serves as to evacuate the huge containments of the neutral injection system. The spent fuel will be purified and subsequently processed by an isotope separation system in which the species D 2 , DT and T 2 will be recovered for further use. This isotope separation will be achieved by a preparative gaschromatographic process. All components of the tritium systems will be installed within gloveboxes which are located in a special tritium handling room. The atmospheres of the gloveboxes and of the tritium rooms are controlled by a tritium monitor system. In the case of a tritium release - during normal operation as well as during an accident - these atmospheres become processed by efficient tritium absorption systems. All ZEPHYR tritium handling systems are designed as to minimize the quantity of tritium released to the environment, so that the stringent German laws on radiological protection are satisfied. (orig.)

  8. Exobiological implications of dust aggregation in planetary atmospheres: An experiment for the gas-grain simulation facility

    Huntington, J. L.; Schwartz, D. E.; Marshall, J. R.

    1991-01-01

    The Gas-Grain Simulation Facility (GGSF) will provide a microgravity environment where undesirable environmental effects are reduced, and thus, experiments involving interactions between small particles and grains can be more suitably performed. Slated for flight aboard the Shuttle in 1992, the ESA glovebox will serve as a scientific and technological testbed for GGSF exobiology experiments as well as generating some basic scientific data. Initial glovebox experiments will test a method of generating a stable, mono-dispersed cloud of fine particles using a vibrating sprinkler system. In the absence of gravity and atmospheric turbulence, it will be possible to determine the influence of interparticle forces in controlling the rate and mode of aggregation. The experimental chamber can be purged of suspended matter to enable multiple repetitions of the experiments. Of particular interest will be the number of particles per unit volume of the chamber, because it is suspected that aggregation will occur extremely rapidly if the number exceeds a critical value. All aggregation events will be recorded on high-resolution video film. Changes in the experimental procedure as a result of surprise events will be accompanied by real-time interaction with the mission specialist during the Shuttle flight.

  9. Minimum Analytical Chemistry Requirements for Pit Manufacturing at Los Alamos National Laboratory; TOPICAL

    Moy, Ming M.; Leasure, Craig S.

    1998-01-01

    Analytical chemistry is one of several capabilities necessary for executing the Stockpile Stewardship and Management Program at Los Alamos National Laboratory (LANL). Analytical chemistry capabilities reside in the Chemistry Metallurgy Research (CMR) Facility and Plutonium Facility (TA-55). These analytical capabilities support plutonium recovery operations, plutonium metallurgy, and waste management. Analytical chemistry capabilities at both nuclear facilities are currently being configured to support pit manufacturing. This document summarizes the minimum analytical chemistry capabilities required to sustain pit manufacturing at LANL. By the year 2004, approximately$16 million will be required to procure analytical instrumentation to support pit manufacturing. In addition,$8.5 million will be required to procure glovebox enclosures. An estimated 50% increase in costs has been included for installation of analytical instruments and glovebox enclosures. However, no general and administrative (G and A) taxes have been included. If an additional 42.5/0 G and A tax were to be incurred, approximately$35 million would be required over the next five years to prepare analytical chemistry to support a 50-pit-per-year manufacturing capability by the year 2004

  10. Task analysis: a detailed example of stepping up from JSA

    Banks, W.W.; Paramore, B.A.; Buys, J.R.

    1984-10-01

    This paper discusses a pilot task analysis of operations in a proposed facility for the cutting and packaging of radioactively contaminated gloveboxes, for long-term storage or burial. The objective was to demonstrate how task analysis may be used as a tool for planning and risk management. Two specific products were generated - preliminary operating procedures and training requirements. The task data base, procedures list and training requirements developed were intended as first order categorizations. The analysis was limited to tasks that will be performed within the boundaries of the operational facility and the associated load-out area. The analysis documents tasks to be performed by D and D (Decontamination and Decommissioning) Workers. However, the analysis included all tasks identified as an integral part of glovebox processing within the facility. Thus tasks involving Radiation Protection Technicians (RPTs) are included. Based on hazard assessments, it is planned that at least two RPTs will be assigned full-time to the facility, so they may be considered part of its crew. Similarly, supervisory/administrative tasks are included where they were determined to be directly part of process sequences, such as obtaining appropriate certification. 11 tables

  11. A university hot laboratory for teaching and research

    Heinonen, O.; Miettinen, J.K.

    1976-01-01

    In small countries which have limited material and capital resources there is more need for studying and teaching reactor chemistry in universities than there is in countries with special nuclear research and training centres. A new 150-m 2 laboratory of reactor chemistry was added to the premises of the Department of Radiochemistry, University of Helsinki, in October 1975. It contains a hot area with low-pressure air-conditioning, a sanitary room, a low-activity area, and an office area. The main instrument is a mass-spectrometer MI-1309 equipped with an ion counter which is particularly useful for plutonium analysis. The laboratory can handle samples up-to 10Ci gamma-acitivity - which equals one pellet of a fuel rod - in a sealed lead cell which has an interchangeable box for alpha-active work. Pretreated samples are submitted to chemical separations in glove-boxes. Samples for alpha and mass spectroscopy are also prepared in glove-boxes. Also the laboratory is provided with fume hoods suitable for building lead shields. Radiation protection and special features typical to the university environment are discussed. Methods for verfication of contamination and protection against internal and external contamination are applied. These include air monitoring, analysis of excreta, and whole-body counting. (author)

  12. Decontamination and decommissioning of the Argonne National Laboratory Building 350 Plutonium Fabrication Facility. Final report

    Kline, W.H.; Moe, H.J.; Lahey, T.J.

    1985-02-01

    In 1973, Argonne National Laboratory began consolidating and upgrading its plutonium-handling operations with the result that the research fuel-fabrication facility located in Building 350 was shut down and declared surplus. Sixteen of the twenty-three gloveboxes which comprised the system were disassembled and relocated for reuse or placed into controlled storage during 1974 but, due to funding constraints, full-scale decommissioning did not start until 1978. Since that time the fourteen remaining contaminated gloveboxes, including all internal and external equipment as well as the associated ventilation systems, have been assayed for radioactive content, dismantled, size reduced to fit acceptable packaging and sent to a US Department of Energy (DOE) transuranic retrievable-storage site or to a DOE low-level nuclear waste burial ground. The project which was completed in 1983, required 5 years to accomplish, 32 man years of effort, produced some 540 m 3 (19,000 ft 3 ) of radioactive waste of which 60% was TRU, and cost 2.4 million dollars

  13. A user's evaluation of radial flow HEPA filters

    Purcell, J.A.

    1992-07-01

    High efficiency particulate air (HEPA) filters of rectangular cross section have been used to remove particulates and the associated radioactivity from air ventilation streams since the advent of nuclear materials processing. Use of round axial flow HEPA filters is also longstanding. The advantages of radial flow filters in a circular configuration have been well demonstrated in UKAEA during the last 5--7 years. An evaluation of radial flow filters for fissile process gloveboxes reveals several substantial benefits in addition to the advantages claimed in UKAEA Facilities. The radial flow filter may be provided in a favorable geometry resulting in improved criticality safety. The filter configuration lends to in-place testing at the glovebox to exhaust duct interface. This will achieve compliance with DOE Order 6430.1A, Section 99.0.2. Preliminary testing at SRS for radial flow filters manufactured by Flanders Filters, Inc. revealed compliance in all the usual specifications for filtration efficiency, pressure differential and materials of construction. An evaluation, further detailed in this report, indicates that the radial flow HEPA filter should be considered for inclusion in new ventilation system designs

  14. Demonstration and evaluation of the CORPEX trademark Nuclear Decontamination Process, Technical task plan No. SR152005. Final Report

    May, C.G.

    1997-01-01

    In June, 1995, the Decontamination and Decommissioning Focus Area funded a demonstration of the CORPEX Nuclear Decontamination Process in an Old Metallography Laboratory glovebox at the Savannah River Site. The objective of the demonstration was to prove the effectiveness of a new and innovative technology that would reduce the risks associated with future cleanups of plutonium-238 contaminated equipment in the DOE complex. After facility and vendor preparations in support of the demonstration, Westinghouse Savannah River Company (WSRC) was informed by the vendor that the chemistry proposed for use in the decontamination process was not effective on sintered plutonium, which was the form of plutonium in the selected glovebox. After further technical evaluation, the demonstration was canceled. This report describes the work performed in support of the demonstration and the present status of the project. The CORPEX chemical process is a nondestructive cleaning method that removes only the contaminant and the matrix that fixed the contaminant to the surface. It does not damage the substrate. The cleaning agent is destroyed by the addition of proprietary oxidizers, leaving water, carbon dioxide and nitrogen gases, and a sludge as waste

  15. Basis Document for Sludge Stabilization

    Risenmay, H R

    2001-01-01

    DOE-RL recently issued Safety Evaluation Report (SER) amendments to the PFP Final Safety Analysis Report, HNF-SD-CP-SAR-021 Rev. 2. The Justification for Continued Operations for 2736-ZB and plutonium oxides in BTCs Safety Basis change (letter DOE-RL ABD-074) was approved by one of the SERs. Also approved by SER was the revised accident analysis for Magnesium Hydroxide Precipitation Process (MHPP) gloveboxes HC-230C-3 and HC-230C-5 containing increased glovebox inventories and corresponding increases in seismic release consequence. Numerous implementing documents require revision and issuance to implement the SER approvals. The SER plutonium oxides into BTCs specifically limited the SER scope to ''pure or clean oxides, i.e., 85 wt% or grater Pu, in this feed change'' (SER Section 3.0 Base Information paragraph 4 [page 11]). Comprehensive USQ Evaluation PFP-2001-12 addressed the packaging of Pu alloy metals into BTCs, and the packaging of Pu alloy oxides (powders) into food pack cans and determined that the ac...

  16. Dependence of Acetate-Based Antisolvents for High Humidity Fabrication of CH3NH3PbI3 Perovskite Devices in Ambient Atmosphere.

    Yang, Fu; Kapil, Gaurav; Zhang, Putao; Hu, Zhaosheng; Kamarudin, Muhammad Akmal; Ma, Tingli; Hayase, Shuzi

    2018-05-16

    High-efficiency perovskite solar cells (PSCs) need to be fabricated in the nitrogen-filled glovebox by the atmosphere-controlled crystallization process. However, the use of the glovebox process is of great concern for mass level production of PSCs. In this work, notable efficient CH 3 NH 3 PbI 3 solar cells can be obtained in high humidity ambient atmosphere (60-70% relative humidity) by using acetate as the antisolvent, in which dependence of methyl, ethyl, propyl, and butyl acetate on the crystal growth mechanism is discussed. It is explored that acetate screens the sensitive perovskite intermediate phases from water molecules during perovskite film formation and annealing. It is revealed that relatively high vapor pressure and high water solubility of methyl acetate (MA) leads to the formation of highly dense and pinhole free perovskite films guiding to the best power conversion efficiency (PCE) of 16.3% with a reduced hysteresis. The devices prepared using MA showed remarkable shelf life stability of more than 80% for 360 h in ambient air condition, when compared to the devices fabricated using other antisolvents with low vapor pressure and low water solubility. Moreover, the PCE was still kept at 15.6% even though 2 vol % deionized water was added in the MA for preparing the perovskite layer.

  17. A Technology Demonstration Experiment for Laser Cooled Atomic Clocks in Space

    Klipstein, W. M.; Kohel, J.; Seidel, D. J.; Thompson, R. J.; Maleki, L.; Gibble, K.

    2000-01-01

    We have been developing a laser-cooling apparatus for flight on the International Space Station (ISS), with the intention of demonstrating linewidths on the cesium clock transition narrower than can be realized on the ground. GLACE (the Glovebox Laser- cooled Atomic Clock Experiment) is scheduled for launch on Utilization Flight 3 (UF3) in 2002, and will be mounted in one of the ISS Glovebox platforms for an anticipated 2-3 week run. Separate flight definition projects funded at NIST and Yale by the Micro- gravity Research Division of NASA as a part of its Laser Cooling and Atomic Physics (LCAP) program will follow GLACE. Core technologies for these and other LCAP missions are being developed at JPL, with the current emphasis on developing components such as the laser and optics subsystem, and non-magnetic vacuum-compatible mechanical shutters. Significant technical challenges in developing a space qualifiable laser cooling apparatus include reducing the volume, mass, and power requirements, while increasing the ruggedness and reliability in order to both withstand typical launch conditions and achieve several months of unattended operation. This work was performed at the Jet Propulsion Laboratory under a contract with the National Aeronautics and Space Administration.

  18. Mixed low-level waste minimization at Los Alamos

    Starke, T.P.

    1998-12-01

    During the first six months of University of California 98 Fiscal Year (July--December) Los Alamos National Laboratory has achieved a 57% reduction in mixed low-level waste generation. This has been accomplished through a systems approach that identified and minimized the largest MLLW streams. These included surface-contaminated lead, lead-lined gloveboxes, printed circuit boards, and activated fluorescent lamps. Specific waste minimization projects have been initiated to address these streams. In addition, several chemical processing equipment upgrades are being implemented. Use of contaminated lead is planned for several high energy proton beam stop applications and stainless steel encapsulated lead is being evaluated for other radiological control area applications. INEEL is assisting Los Alamos with a complete systems analysis of analytical chemistry derived mixed wastes at the CMR building and with a minimum life-cycle cost standard glovebox design. Funding for waste minimization upgrades has come from several sources: generator programs, waste management, the generator set-aside program, and Defense Programs funding to INEEL.

  19. Decommissioning of the Plutonium Purification and Residues Recovery Plant

    Hunt, J. G.

    2006-01-01

    British Nuclear Group is continuing to build on BNFL's successful record of decommissioning redundant nuclear facilities. Challenging radiological conditions and complex technical problems have been overcome to reduce the hazard associated with the UK's nuclear legacy. The former Plutonium Purification and Residues Recovery Plant at Sellafield operated from 1954 through to 1987. This is the only plant to have experienced an uncontrolled criticality incident in the UK, in August 1970 during operations. The plant comprised of two mirror image cells approximately 6.5 m x 13.5 m x 16 m, constructed of bare brick. The cell structure provided secondary containment, the process vessels and pipes within the cell providing primary containment. The plant utilized a solvent extraction process to purify the plutonium stream. Surrounding the two process cells to the north, east and south is an annulus area that housed the operational control panels, feed and sample glove-boxes, and ancillary equipment. The building was ventilated by an unfiltered extract on the process cells and a filtered extract from the vessels and glove-boxes. During the long operational lifetime of the plant, the primary containment deteriorated to such an extent that the process cells eventually became the main containment, with levels of radioactive contamination in excess of 14,256 pCi alpha. This led to significant aerial effluent discharges towards the end of the plant's operational life and onerous working conditions during decommissioning. Implementation of a phased decommissioning strategy from 1991 has led to: - A reduction of approximately 60% in the Sellafield site's aerial alpha discharges following installation of a new ventilation system, - Removal of 12 plutonium contaminated glove-boxes and sample cabinets from the building, - Disposal of the approximately 500 m 2 of asbestos building cladding, - Removal of over 90% of the active pipes and vessels from the highly contaminated process cells

  20. Separation of {sup 90}Sr from radioactive waste matrices-Microwave versus fusion decomposition

    Jaeggi, M. [Paul Scherrer Institut, Department Logistics for Radiation Safety and Security, Radioanalytics, 5232 Villigen (Switzerland)], E-mail: maya.jaeggi@psi.ch; Eikenberg, J. [Paul Scherrer Institut, Department Logistics for Radiation Safety and Security, Radioanalytics, 5232 Villigen (Switzerland)

    2009-05-15

    Radioactive waste (slurry) from a detention pond deriving from two research reactors and several inactive and active drain outlets at the Paul Scherrer Institute are the basis for the current {sup 90}Sr investigation. For decomposition, a microwave method was applied, where 1 g of dry-ashed slurry was partially dissolved (HNO{sub 3} (65%)/H{sub 2}O{sub 2} (30%); v:v=8:2). In this slurry we obtained an {sup 90}Sr activity of 5.3{+-}0.2 Bq/g in solution. In a second run, we applied a borate-fusion (Li metaborate/Li tetraborate (80:20 w/w%) dissolving 1 g of dry-ashed 'Si-free' slurry at 1100 deg. C in a muffle furnace. We achieved an {sup 90}Sr activity of (7.8{+-}0.3) Bq/g, yet observing BaSO{sub 4} precipitation during the chromatographical separation of Sr. An alkali fusion using Na{sub 2}CO{sub 3} was done using the Bunsen burner and the muffle furnace for 20 min at 1000 deg. C, in combination. During formation of the hot glass, the surplus of Na{sub 2}CO{sub 3}, produced Na{sub 2}SO{sub 4} and BaCO{sub 3} in solid form. The hot glass was dissolved in deionised water, removing thus the SO{sub 4}{sup 2-} ions. Dissolving the residue directly in HNO{sub 3}, solves Ba as Ba(NO{sub 3}){sub 2} and thus we achieved over 80% of the {sup 133}Ba activity in the solution, as measured by {gamma}-spectrometry. {sup 85}Sr tracer of 88.0%{+-}3.3% was recovered, yielding on average in (7.4{+-}0.3) Bq/g of {sup 90}Sr activity. The increase of 2.1-2.5 Bq/g of {sup 90}Sr activity achieved with the alkali fusion, and the Li metaborate/Li tetraborate 80:20 w/w% fusion, respectively, clearly shows that some Sr must have been present as SrSO{sub 4} in the slurry.

  1. Comparison of dry, wet and microwave digestion methods for the determination of Pb in commercially available poultry feed samples in Pakistan

    Iqbal, S.; Hussain, A.; Hussain, I.; Sher, M.

    2012-01-01

    Summary: The poultry feed ingredients, contaminated by Lead (Pb) from different sources, may pose serious threats towards health of bird as well as consumers. Toxicity of Pb requires accurate quantification from poultry samples, which in turn is dependent on efficiency of digestion procedure. Therefore, aim of this study was to compare three main digestion methods; microwave-assisted wet digestion, wet-acid digestion on hot plate and dry ashing mineralization in muffle furnace for the maximum recovery of Pb from 28 poultry feed samples of 7 commercial brands from Pakistan. Novelty in wet-acid digestion on hot plate lies in applying 6 different compositions of nitric acid with oxidants and other mineral acids i.e. hydrogen peroxide (H/sub 2/O/sub 2/ ), perchloric (HClO/sub 4/), hydrochloric (HCl), and hydrofluoric (HF) acids. The concentration of Pb in samples was found to be in the range of 43-58.5, 26-35.5, 17- 30, 11-18.5, 22-30.5, 27-37 .5, 36-48 and 2- 6.5 mg/kg by 1 MW (microwave-assisted wet digestion), 2 AW (wet digestion with HNO/sub 3/ and H/sub 2/O/sub 2/ mixture), 2 BW (wet digestion with mixture of HNO/sub 3/ and HClO/sub 4/), 2 CW (wet digestion with aqua regia), 2 DW (wet digestion with reverse aqua regia), 2 EW (wet digestion with mixture of HNO/sub 3/ and H/sub 2/SO/sub 4/), 2 FW (wet digestion with mixture of HNO/sub 3/ and HF) and 3 DD (Dry digestion in Muffle furnace), respectively. The results were subjected to statistical analysis i.e. ANOVA, which showed significant differences among all the digestion methods and cluster analysis, which confirmed the similarity between 2 FW (wet digestion with mixture of nitric acid and hydrofluoric acid) and microwave-assisted digestion method. (author)

  2. Integrated monitoring and surveillance system demonstration project: Phase I accomplishments

    Aumeier, S.E.; Walters, B.G.; Crawford, D.C.

    1997-01-01

    The authors present the results of the Integrated Monitoring and Surveillance System (IMSS) demonstration project Phase I efforts. The rationale behind IMSS development is reviewed and progress in each of the 5 basic tasks is detailed. Significant results include decisions to use Echelon LonWorks networking protocol and Microsoft Access for the data system needs, a preliminary design for the plutonium canning system glovebox, identification of facilities and materials available for the demonstration, determination of possibly affected facility documentation, and a preliminary list of available sensor technologies. Recently imposed changes in the overall project schedule and scope are also discussed and budgetary requirements for competition of Phase II presented. The results show that the IMSS demonstration project team has met and in many cases exceeded the commitments made for Phase I deliverables

  3. The Safety and Tritium Applied Research (STAR) Facility: Status-2004

    Anderl, R.A.; Longhurst, G.R.; Pawelko, R.J.; Sharpe, J.P.; Schuetz, S.T.; Petti, D.A.

    2005-01-01

    The Safety and Tritium Applied Research (STAR) Facility, a US DOE National User Facility at the Idaho National Engineering and Environmental Laboratory (INEEL), comprises capabilities and infrastructure to support both tritium and non-tritium research activities important to the development of safe and environmentally friendly fusion energy. Research thrusts include (1) interactions of tritium and deuterium with plasma-facing-component (PFC) materials, (2) fusion safety issues [PFC material chemical reactivity and dust/debris generation, activation product mobilization, tritium behavior in fusion systems], and (3) molten salts and fusion liquids for tritium breeder and coolant applications. This paper updates the status of STAR and the capabilities for ongoing research activities, with an emphasis on the development, testing and integration of the infrastructure to support tritium research activities. Key elements of this infrastructure include a tritium storage and assay system, a tritium cleanup system to process glovebox and experiment tritiated effluent gases, and facility tritium monitoring systems

  4. Bus bar electrical feedthrough for electrorefiner system

    Williamson, Mark; Wiedmeyer, Stanley G; Willit, James L; Barnes, Laurel A; Blaskovitz, Robert J

    2013-12-03

    A bus bar electrical feedthrough for an electrorefiner system may include a retaining plate, electrical isolator, and/or contact block. The retaining plate may include a central opening. The electrical isolator may include a top portion, a base portion, and a slot extending through the top and base portions. The top portion of the electrical isolator may be configured to extend through the central opening of the retaining plate. The contact block may include an upper section, a lower section, and a ridge separating the upper and lower sections. The upper section of the contact block may be configured to extend through the slot of the electrical isolator and the central opening of the retaining plate. Accordingly, relatively high electrical currents may be transferred into a glovebox or hot-cell facility at a relatively low cost and higher amperage capacity without sacrificing atmosphere integrity.

  5. Tips for the fabrication of temporary tritium experiments

    Binning, K.E.; Jenkins, E.M.

    1988-01-01

    The Tritium System Test Assembly (TSTA) is a facility built for the demonstration of tritium handling systems necessary for tritium-burning fusion reactors. The facility has been in operation handling tritium for four years. The current inventory of tritium is approximately one hundred grams, with DOE approval for a maximum inventory of two hundred grams. Not all experiments performed at TSTA require the operation of the main process loop. During the last four years, many small scale experiments have been performed to test the compatibility and operation of tritium processing components in small self-contained experimental packages. These packages are fabricated inside secondary containment gloveboxes and can be operated for hours or months with little monitoring. Construction of these packages need to be tritium compatible, inexpensive, easy to build, and versatile. This paper discusses some of the problems and remedies encountered during the building of temporary experiments

  6. Method of extruding and packaging a thin sample of reactive material including forming the extrusion die

    Lewandowski, E.F.; Peterson, L.L.

    1985-01-01

    This invention teaches a method of cutting a narrow slot in an extrusion die with an electrical discharge machine by first drilling spaced holes at the ends of where the slot will be, whereby the oil can flow through the holes and slot to flush the material eroded away as the slot is being cut. The invention further teaches a method of extruding a very thin ribbon of solid highly reactive material such as lithium or sodium through the die in an inert atmosphere of nitrogen, argon or the like as in a glovebox. The invention further teaches a method of stamping out sample discs from the ribbon and of packaging each disc by sandwiching it between two aluminum sheets and cold welding the sheets together along an annular seam beyond the outer periphery of the disc. This provides a sample of high purity reactive material that can have a long shelf life

  7. Safe handling and monitoring of tritium in research on nuclear fusion

    Yoshida, Yoshikazu; Naruse, Yuji

    1978-01-01

    An actual condition of technique of safety handling and monitoring of tritium in the laboratory which treated a great quantity of tritium in relation to nuclear fusion, was described. With respect to the technique of safety handling of tritium, an actual condition of the technique in the U.S.A. which had wide experience in treating a great quantity of 3 H was mainly introduced, and it was helpful to a safety measure and a reduction of tritium effluence. Glovebox, hood, and other component machinery and tools for treating 3 H were also introduced briefly. As a monitoring technique, monitoring of indoor air and air exhaust by ionization chamber-type monitor for continuous monitoring of a great quantity of gaseous tritium was mentioned. Next, monitoring of a room, the surfaces of equipments, and draining, internal exposure of the individual, and monitoring of the environment were introduced. (Kanao, N.)

  8. Hydrothermal processing of radioactive combustible waste

    Worl, L.A.; Buelow, S.J.; Harradine, D.; Le, L.; Padilla, D.D.; Roberts, J.H.

    1998-01-01

    Hydrothermal processing has been demonstrated for the treatment of radioactive combustible materials for the US Department of Energy. A hydrothermal processing system was designed, built and tested for operation in a plutonium glovebox. Presented here are results from the study of the hydrothermal oxidation of plutonium and americium contaminated organic wastes. Experiments show the destruction of the organic component to CO 2 and H 2 O, with 30 wt.% H 2 O 2 as an oxidant, at 540 C and 46.2 MPa. The majority of the actinide component forms insoluble products that are easily separated by filtration. A titanium liner in the reactor and heat exchanger provide corrosion resistance for the oxidation of chlorinated organics. The treatment of solid material is accomplished by particle size reduction and the addition of a viscosity enhancing agent to generate a homogeneous pumpable mixture

  9. Getting the most D and D ''know how'' before starting to plan your decommissioning project

    Boing, L. E.

    1999-01-01

    Over the last 20 years, the Decommissioning Program of the ANL-East Site has successfully decommissioned numerous facilities including: three research reactors (a 100 MW BWR, a smaller 250 kW biological irradiation reactor and a 10 kW research reactor), a critical assembly, a suite of 61 plutonium gloveboxes in 9 laboratories, a fuels fabrication facility and several non-reactor (waste management and operations) facilities. In addition, extensive decontamination work was performed on 5 hot cells formerly used in a joint ANL/US Navy R and D program. Currently the D and D of the CP-5 research reactor is underway as is planning for several other future D and D projects. The CP-5 facility was also used as a test bed for the evaluation of select evolving D and D technologies to ascertain their value for use in future D and D projects

  10. Study of the potential use of carburized niobium in plutonium processing

    Johnson, M.J.

    1998-01-01

    Carburized refractory metals, especially tantalum, have been shown to possess properties useful for application as hardware in the plutonium-processing environment. These applications are driven in part by a desire to minimize the production of radioactively contaminated waste. The current use of ceramics as containment materials for Pu processing are not ideal due to the short service life of the hardware, placing an additional burden on the contaminated waste stream. Carburized niobium has been examined for use as an improved hardware material. The Nb-C system is analogous to the previously studied Ta-C system. The low density of niobium relative to tantalum will improve the ergonomics of the glovebox environment. The choice of the Nb-C system will be supported by a thermodynamic and kinetic analysis. Preliminary results of the processing investigation also will be presented

  11. Tritium proof-of-principle injector experiment

    Fisher, P.W.; Milora, S.L.; Combs, S.K.; Carlson, R.V.; Coffin, D.O.

    1988-01-01

    The Tritium Proof-of-Principle (TPOP) pellet injector was designed and built by Oak Ridge National Laboratory (ORNL) to evaluate the production and acceleration of tritium pellets for fueling future fision reactors. The injector uses the pipe-gun concept to form pellets directly in a short liquid-helium-cooled section of the barrel. Pellets are accelerated by using high-pressure hydrogen supplied from a fast solenoid valve. A versatile, tritium-compatible gas-handling system provides all of the functions needed to operate the gun, including feed gas pressure control and flow control, plus helium separation and preparation of mixtures. These systems are contained in a glovebox for secondary containment of tritium Systems Test Assembly (TSTA) at Los Alamos National Laboratory (LANL). 18 refs., 3 figs

  12. Phase Equilibria in the Bi-In-Sn-Zn System. Thermal Analysis vs. Calculations

    Dębski A.

    2017-12-01

    Full Text Available With the use of the differential thermal analysis (DTA, studies of the phase transitions were conducted for 90 of alloys from the quaternary Bi-In-Sn-Zn system and for the constant ratio of Bi:In and Bi:Sn. The studies were conducted for the alloys prepared from the purity metals (Bi, In, Sn, Zn = 99.999 mas. % by way of melting in a graphite crucible in a glove-box filled with Ar, in which the impurities level was less than 0.1 ppm. After melting and thorough mixing, the liquid alloys were poured out into a graphite test mold. The phase transition temperature data obtained from the DTA investigations were next confronted with those determined from the calculations based on the binary and ternary optimized thermodynamic parameters available in the literature. It was found that the experimental and the calculated phase transition temperatures were in good agreement.

  13. New Technologies Being Developed for the Thermophoretic Sampling of Smoke Particulates in Microgravity

    Sheredy, William A.

    2003-01-01

    The Characterization of Smoke Particulate for Spacecraft Fire Detection, or Smoke, microgravity experiment is planned to be performed in the Microgravity Science Glovebox Facility on the International Space Station (ISS). This investigation, which is being developed by the NASA Glenn Research Center, ZIN Technologies, and the National Institute of Standards and Technologies (NIST), is based on the results and experience gained from the successful Comparative Soot Diagnostics experiment, which was flown as part of the USMP-3 (United States Microgravity Payload 3) mission on space shuttle flight STS-75. The Smoke experiment is designed to determine the particle size distributions of the smokes generated from a variety of overheated spacecraft materials and from microgravity fires. The objective is to provide the data that spacecraft designers need to properly design and implement fire detection in spacecraft. This investigation will also evaluate the performance of the smoke detectors currently in use aboard the space shuttle and ISS for the test materials in a microgravity environment.

  14. Catalytic detritiation of water

    Rogers, M.L.; Lamberger, P.H.; Ellis, R.E.; Mills, T.K.

    1977-01-01

    A pilot-scale system has been used at Mound Laboratory to investigate the catalytic detritiation of water. A hydrophobic, precious metal catalyst is used to promote the exchange of tritium between liquid water and gaseous hydrogen at 60 0 C. Two columns are used, each 7.5 m long by 2.5 cm ID and packed with catalyst. Water flow is 5-10 cm 3 /min and countercurrent hydrogen flow is 9,000-12,000 cm 3 /min. The equipment, except for the columns, is housed in an inert atmosphere glovebox and is computer controlled. The hydrogen is obtained by electrolysis of a portion of the water stream. Enriched gaseous tritium is withdrawn for further enrichment. A description of the system is included along with an outline of its operation. Recent experimental data are discussed

  15. Plutonium determination by spectrophotometry of plutonium (VI): control of the nuclear fuel reprocessing plant

    Grison, J [Compagnie Generale des Matieres Nucleaires (COGEMA), Centre de la Hague, 50 - Cherbourg (France)

    1980-10-01

    The plutonium (VI) spectrophotometric determination, after AgO oxidation in 3 M nitric acid medium, is used for the running-control of the nuclear fuel reprocessing plant at La Hague. Analytical device used in glove-box or shielded-cell is briefly described. This method is fast, sensitive, unfailing and gives simple effluents. It is applied by day and night shifts, during Light Water Reactor fuel reprocessing campaign, for 0.5 mg/l up to 20 g/l plutonium solutions. Reference solution measurements have a 0.8 to 1.4 % relative standard deviation; duplicate plutonium determinations give a 0.3% relative standard deviation for sample analysis. There is a discrepancy (- 0.3% to - 0.9%) between the spectrophotometric method results and the isotopic dilution analysis.

  16. Plutonium determination by spectrophotometry of plutonium (VI): control of the nuclear fuel reprocessing plant

    Grison, J.

    1980-01-01

    The plutonium (VI) spectrophotometric determination, after AgO oxidation in 3 M nitric acid medium, is used for the running-control of the nuclear fuel reprocessing plant at La Hague. Analytical device used in glove-box or shielded-cell is briefly described. This method is fast, sensitive, unfailing and gives simple effluents. It is applied by day and night shifts, during Light Water Reactor fuel reprocessing campaign, for 0.5 mg/l up to 20 g/l plutonium solutions. Reference solution measurements have a 0.8 to 1.4 % relative standard deviation; duplicate plutonium determinations give a 0.3% relative standard deviation for sample analysis. There is a discrepancy (- 0.3% to - 0.9%) between the spectrophotometric method results and the isotopic dilution analysis [fr

  17. Refurbishment of an Analytical Laboratory Hot Cell Facility

    Rosenberg, K.; Henslee, S.P.; Michelbacher, J.A.; Coleman, R.M.

    1997-01-01

    An Analytical Laboratory Hot Cell (ALHC) Facility at Argonne National Laboratory-West (ANL-W) was in service for nearly thirty years. In order to comply with DOE regulations governing such facilities and meet ANL-W programmatic requirements, a major refurbishment effort was undertaken. All penetrations within the facility were sealed; the ventilation system was redesigned, upgraded and replaced; the manipulators were replaced; the hot cell windows were removed, refurbished, and reinstalled; all hot cell utilities were replaced; a lead-shielded glovebox housing an Inductively Coupled Plasma - Atomic Emission Spectrometer (ICP-AES) System was interfaced with the hot cells, and a new CO2 fire suppression system and other ALHC support equipment were installed

  18. Experience gained with the Synroc demonstration plant at ANSTO and its relevance to plutonium immobilization

    Jostsons, A.; Ridal, A.; Mercer, D.J.; Vance, E.R.L. [Australian Nuclear Science and Technology Organisation, Menai (Australia)

    1996-05-01

    The Synroc Demonstration Plant (SDP) was designed and constructed at Lucas Heights to demonstrate the feasibility of Synroc production on a commercial scale (10 kg/hr) with simulated Purex liquid HLW. Since commissioning of the SDP in 1987, over 6000 kg of Synroc has been fabricated with a range of feeds and waste loadings. The SDP utilises uniaxial hot-pressing to consolidate Synroc. Pressureless sintering and hot-isostatic pressing have also been studied at smaller scales. The results of this extensive process development have been incorporated in a conceptual design for a radioactive plant to condition HLW from a reprocessing plant with a capacity to treat 800 tpa of spent LWR fuel. Synroic containing TRU, including Pu, and fission products has been fabricated and characterised in a glove-box facility and hot cells, respectively. The extensive experience in processing of Synroc over the past 15 years is summarised and its relevance to immobilization of surplus plutonium is discussed.

  19. Chemical aspects of fission product transport in the primary circuit of a light water reactor

    Bowsher, B.R.; Dickinson, S.; Nichols, A.L.; Ogden, J.S.; Potter, P.E.

    1985-01-01

    The transport and fission products in the primary circuit of a light water reactor are of fundamental importance in assessing the consequences of severe accidents. Recent experimental studies have concentrated upon the behaviour of simulant fission product species such as caesium iodide, caesium hydroxide and tellurium, in terms of their vapour deposition characteristics onto metals representative of primary circuit materials. An induction furnace has been used to generate high-density/structural materials aerosols for subsequent analysis, and similar equipment has been incorporated into a glove-box to study lightly-irradiated UO/sub 2/ clad in Zircaloy. Analytical techniques are being developed to assist in the identification of fission product chemical species released from the fuel at temperatures from 1000 to 2500 0 C. Matrix isolation-infrared spectroscopy has been used to identify species in the vapour phase, and specific data using this technique are reported

  20. Chemical aspects of fission product transport in the primary circuit of a light water reactor

    Bowsher, B.R.; Dickinson, S.; Nichols, A.L.; Ogden, J.S.; Potter, P.E.

    1985-01-01

    The transport and deposition of fission products in the primary circuit of a light water reactor are of fundamental importance in assessing the consequences of severe accidents. Recent experimental studies have concentrated upon the behavior of simulant fission product species such as cesium iodide, cesium hydroxide and tellurium, in terms of their vapor deposition characteristics onto metals representative of primary circuit materials. An induction furnace has been used to generate high density/structural materials aerosols for subsequent analysis, and similar equipment has been incorporated into a glove-box to study lightly-irradiated UO 2 clad in Zircaloy. Analytical techniques are being developed to assist in the identification of fission product chemical species released from the fuel at temperatures from 1000 to 2500 0 C. Matrix isolation-infrared spectroscopy has been used to identify species in the vapor phase, and specific data using this technique are reported

  1. Separation of Gram-amounts of Lanthanides by Cation Exchange, using an aqueous Solution of α-Hydroxyisobutyric Acid as an Eluant. RCN Report

    Das, H.A.; Hoede, D.; Stigt, Ch.A. van; Zonderhuis, J.

    1970-09-01

    This report describes a procedure developed for the mutual separation of gram quantities of the lanthanides present in solutions of thermal fission products. A second aim was the purification of ''crude'' 147 Pm-sources. The method is based on column chromatography on Dowex - 50 W (50 - 100 mesh) with an aqueous solution of a-hydroxyisobutyric acid (AHIB) as an eluant. Due to the radioactivity of the samples, the process has to be performed in a shielded glove-box. Consequently, a considerably economy was exercised with respect to the volume of the apparatus. The process was successfully tested with labeled artificial mixtures of 20 grammes of the rare earths involved. The method has been applied to the purification of batches of ''crude'' 147 Pm. (author)

  2. ''FIXBOX'' - a new technique for the reliable conditioning of plutonium waste solutions

    Bruchertseifer, H.; Sommer, E.; Steinemann, M.; Bart, G.

    1994-01-01

    ''FIXBOX'' - A new technique and facility for the conditioning of plutonium waste solutions has been developed and brought into operation in the Hot-laboratory at PSI, for the solidification of the waste from the research programmes. The facility is situated in glove-boxes for handling alpha activity and gamma-shielded for conditioning of fission product-containing waste. This report gives a brief description of the FIXBOX facility, the procedure and the first results of the cementation of plutonium waste solutions. As a result of this solidification, the actinide waste is homogeneous and strongly bound in the cement. The presence of gluconic acid and other complexing agents in the waste solution will not disturb this process. (author) figs., tabs., refs

  3. Integrated Monitoring and Surveillance System demonstration project. Phase 2 accomplishments

    Aumeier, S.E.; Walters, B.G.; Singleterry, R.C.

    1997-01-01

    The paper presents the results of the Integrated Monitoring and Surveillance System (IMSS) demonstration project Phase 2 efforts. the rationale behind IMSS development is reviewed and progress in each of the 5 basic tasks is detailed. Significant results include further development of the data acquisition system and procurement of necessary hardware/software, options and associated costs for plutonium canning systems and gloveboxes, initiation of facility modifications, determination of possibly affected facility documentation, results from sensor system trade study, and preliminary storage configuration designs. Resources invested during Phase 1 and Phase 2 are summarized and budgetary requirements for completion of Phase 3 presented. The results show that the IMSS demonstration project team has met and in many cases exceeded the commitments made for Phase 2 deliverables

  4. Remote engineering progress report, January-December 1982

    Brown, C.M.

    1984-01-01

    Discussed briefly are the objectives, prior work (if any), present achievements, and future work in the following areas: an automated storage, transfer, and retrieval system for laboratory specimens; automation of molten salt button breakout operations; emission spectrometer automation, direct oxide reduction process support; hydride operations support; part serialization processes; contact handled waste container welding; automated sample cutting; filter probe positioner; Unimate robot replacement to handle uranium ingots in a hot pressing operation; development and testing of a device to automate compacting on site return nuclear weapons parts for pyrochemical operations; remote transfer system for gloveboxes (made from a modified radio-controlled toy tank); plutonium oxide/skull burn and reburn process; advanced size reduction facility; automation of the plutonium oxide pelletizing process for chemical analytical laboratory operations; automated assembly demonstration for a Mechanical Safe and Arm Detonator (MSAD); and a stacker-retriever remote vacuum cleaning system

  5. SAFETY STUDIES TO MEASURE EXOTHERMIC REACTIONS OF SPENT PLUTONIUM DECONTAMINATION CHEMICALS USING WET AND DRY DECONTAMINATION METHODS

    HOPKINS, A.M.; JACKSON, G.W.; MINETTE, M.; EWALT, J.; COOPER, T.; SCOTT, P.; JONES, S.; SCHEELEY, R.

    2005-01-01

    The Plutonium Finishing Plant (PFP) at the Hanford site in Eastern Washington is currently being decommissioned by Fluor Hanford. Chemicals being considered for dccontamination of gloveboxes in PFP include cerium (IV) nitrate in a nitric acid solution, and proprietary commercial solutions that include acids and sequestering agents. Aggressive chemicals are commonly used to remove transuranic contaminants from process equipment to allow disposal of the equipment as low level waste. Fluor's decontamination procedure involves application of chemical solutions as a spray on the contaminated surfaces, followed by a wipe-down with rags. Alternatively, a process of applying oxidizing Ce IV ions contained in a gel matrix and vacuuming a dry gel material is being evaluated. These processes effectively transfer the transuranic materials to rags or a gel matrix which is then packaged as TRU waste and disposed

  6. Developments in the treatment of solid alpha-bearing wastes at the PNC plutonium fuel facilities

    Ohtsuka, K.; Miyo, H.; Ohuchi, J.; Shiga, K.; Muto, T.

    1978-01-01

    Some results of experiments done in PNC are presented on volume reduction technics for alpha-bearing wastes. A pilot wood milling machine automatically mills the plywood frames of nipple connected HEPA filters, which result in fine sized wooden chips, two nipples and the filter components. The filter components are melted in an induction furnace to be homogeneous solids. These methods and incineration of wooden chips reduce the stored volume of HEPA filters to 1/50 -- 1/100. PVC and neoprene rubber are decomposed in concentrated sulfuric acid, followed by oxidation with nitric acid. The acid digestion process generates chlorine-rich gas, from which only chlorine is selectively absorbed in water. An alpha-bearing vessel and a glovebox are cut at their installed places without spread of plutonium contamination outside the greenhouses. (auth.)

  7. Tritium system for compact high field devices

    Roccella, M.; Bonizzoni, G.; Chiesa, P.; Ghezzi, F.; Nassi, M.; Pavesi, U.; Amedeo, P.; Boschetti, G.; Giffanti, F.; Moriggio, A.

    1988-01-01

    Some theoretical results and the current status of the work on a prototype plant for the Tritium cycle of compact high-field tokamaks (such as, Ignitor, CIT, etc.), using the SAES Getter St 707 getter material, are described in this report. The schematics and present status of the main subplants of the cycle are reported together with some experimental results demostrating the possibility of utilizing the St 707 material to purify the inert atmosphere of the glove-boxes and the secondary containment of the double-containment metal canalization which is to eventually house the various parts of the plant. Finally, as an example, the FTU machine, under construction at ENEA Frascati, has been taken as a reference, and theoretical evaluations are given for the inventory, permeation and release of the Tritium from the first wall and the thermal shieldes of such a tokamak

  8. CONTAMINATED PROCESS EQUIPMENT REMOVAL FOR THE DECOMMISSIONG AND DECONTAMINATION OF THE 232-Z CONTAMINATED WASTE RECOVERY PROCESS FACILITY AT THE PLUTONIUM FINISHING PLANT

    HOPKINS, A.M.; MINETTE, M.J.; KLOS, D.B.

    2007-01-01

    This paper describes the unique challenges encountered and subsequent resolutions to accomplish the deactivation and decontamination of a plutonium ash contaminated building. The 232-Z Contaminated Waste Recovery Process Facility at the Plutonium Finishing Plant was used to recover plutonium from process wastes such as rags, gloves, containers and other items by incinerating the items and dissolving the resulting ash. The incineration process resulted in a light-weight plutonium ash residue that was highly mobile in air. This light-weight ash coated the incinerator's process equipment, which included gloveboxes, blowers, filters, furnaces, ducts, and filter boxes. Significant airborne contamination (over 1 million derived air concentration hours [DAC]) was found in the scrubber cell of the facility. Over 1300 grams of plutonium held up in the process equipment and attached to the walls had to be removed, packaged and disposed. This ash had to be removed before demolition of the building could take place

  9. Transoral tracheal intubation of rodents using a fiberoptic laryngoscope.

    Costa, D L; Lehmann, J R; Harold, W M; Drew, R T

    1986-06-01

    A fiberoptic laryngoscope which allows direct visualization of the deep pharynx and epiglottis has been developed for transoral tracheal intubation of small laboratory mammals. The device has been employed in the intubation and instillation of a variety of substances into the lungs of rats, and with minor modification, has had similar application in mice, hamsters, and guinea pigs. The simplicity and ease of handling of the laryngoscope permits one person to intubate large numbers of enflurane anesthetized animals either on an open counter top or in a glove-box, as may be required for administration of carcinogenic materials. Instillation of 7Be-labeled carbon particles into the lungs of mice, hamsters, rats, and guinea pigs resulted in reasonably consistent interlobal distribution of particles for each test animal species with minimal tracheal deposition. However, actual lung tissue doses of carbon exhibited some species dependence.

  10. Development of a versatile laser light scattering instrument

    Meyer, William V.; Ansari, Rafat R.

    1990-10-01

    A versatile laser light scattering (LLS) instrument is developed for use in microgravity to measure microscopic particles of 30 A to above 3 microns. Since it is an optical technique, LLS does not affect the sample being studied. A LLS instrument built from modules allows several configurations, each optimized for a particular experiment. The multiangle LLS instrument can be mounted in the rack in the Space Shuttle and on Space Station Freedom. It is possible that a Space Shuttle glove-box and a lap-top computer containing a correlator card can be used to perform a number of experiments and to demonstrate the technology needed for more elaborate investigations. This offers simple means of flying a great number of experiments without the additional requirements of full-scale flight hardware experiments.

  11. Handling of a glove box accident. Surgical treatment of a wound contaminated by a mixture of plutonium-239 and americium

    Lalu, P.

    1977-01-01

    An employee of the Valduc Centre (France) suffered an injury to his right thumb when working in a glove-box on a pipeline which had contained a solution of 239 Pu and Am. The lesion was slight but attempts at decontamination were fruitless. The contamination was deep-seated (activity of not less than 18nCi). DTPA was injected intravenously, and it was decided to excise the lesion surgically. Thanks to the quality of its physical facilities and the professional quality of its radiation medicine and surgery team, the Valduc Centre was able to carry out the operation successfully. The result was excellent, and the contamination was eliminated to the satisfaction of both the patient and the physician. (author)

  12. Ash Stabilization Campaign Blend Plan

    Winstead, M.L.

    1995-01-01

    This Stabilization Blend Plan documents the material to be processed and the processing order for the FY95 Ash Stabilization Campaign. The primary mission of this process is to reduce the inventory of unstable plutonium bearing ash. The source of the ash is from Rocky Flats and the 232-Z incinerator at the Plutonium Finishing Plant (PFP). The ash is currently being stored in Room 235B and Vault 174 in building 234-5Z. The sludge is to be thermally stabilized in a glovebox in room 230A of the 234-5Z building and material handling for the process will be done in room 230B of the same building. The campaign is scheduled for approximately 12--16 weeks. A total of roughly 4 kg of Pu will be processed

  13. Tests of prototype salt stripper system for IFR fuel cycle

    Carls, E.L.; Blaskovitz, R.J.; Johnson, T.R.; Ogata, T.

    1993-01-01

    One of the waste treatment steps for the on-site reprocessing of spent fuel from the Integral Fast Reactor fuel cycles is stripping of the electrolyte salt used in the electrorefining process. This involves the chemical reduction of the actinides and rare earth chlorides forming metals which then dissolve in a cadmium pool. To develop the equipment for this step, a prototype salt stripper system has been installed in an engineering scale argon-filled glovebox. Pumping trails were successful in transferring 90 kg of LiCl-KCl salt containing uranium and rare earth metal chlorides at 500 degree C from an electrorefiner to the stripper vessel at a pumping rate of about 5 L/min. The freeze seal solder connectors which were used to join sections of the pump and transfer line performed well. Stripping tests have commenced employing an inverted cup charging device to introduce a Cd-15 wt % Li alloy reductant to the stripper vessel

  14. Advanced dust monitoring system applied to new TRU handling facility of JAERI

    Yabuta, H.; Shigeta, Y.; Sawahata, K.; Hasegawa, K.

    1993-01-01

    In JAERI, a large, scale multipurpose facility is under construction, which consists of a TRU waste management testing installation, a solution fuel treatment installation and critical assemblies with uranium and/or plutonium solution fuel. The facility is also equipped with a lot of gloveboxes for handling and treatment of solution fuel and hot cells for research on reprocessing process. As there may be a relatively high potential of air contamination, it is important to monitor air contamination effectively and efficiently. An advanced dust monitoring system was introduced for convenience of handling and automatical measurement of filter papers, by developing a filter-holder with an IC memory and a radioactivity measuring device with an automatic filter-holder changing mechanism as a part of a centralized monitoring system with a computer

  15. Development of a new monitor for tritium in air model TAM-II

    Wu Bin; Yang Hailan; Wen Xuelian; Zhao Yi; Yang Huaiyuan

    2001-01-01

    The author introduces development of a real-time continuous tritium monitor model TAM-II. The detector of the instrument is comprised of four geometric-symmetry open wall ionization chamber with the effective volume of 2 L, which enables to minimize the remember effect of the ionization chamber due to contamination by the monitored tritium. It is γ background compensation rate is better than 97% in almost all direction. The detector is equipped with a FET static electrometer working in micro-current integration mode. The measurement process of the tritium monitor can be controlled automatically by a micro-processor sheet, such as automatic range changing, data displaying and storing, and data processing. The measuring range is 6 - 10 6 Bq/L. It is especially application for monitoring tritium in off-gas effluence from glove-box or stack of tritium facility and laboratory

  16. Design and evaluation of a microcomputer-controlled remote pipetter system

    Goeringer, D.E.; Klatt, L.N.

    1981-01-01

    A remote pipetter has been designed and evaluated. The system is suitable for use in either a hot-cell or a glove-box environment and, therefore, is applicable in any situation where operating personnel must be separated from hazardous materials. The principle of operation for the pipetter is the displacement of liquid via a calibrated, screw-driven plunger. Variably sized aliquots of 1 to 1000 μL can be delivered. A steppng motor is used to move the plunger, and its position is verified with a linear variable differential transformer. The unit is controlled by a microcomputer. Besides the required operation sequences and error checking, a self-calibration check has been designed into the software. Measured accuracies and precisions of aliquot delivery are 0.4 and 0.2%, respectively

  17. Virtual reality and telepresence control of robots used in hazardous environments

    Bronisz, L.E.; Pittman, P.C.

    1996-01-01

    The purpose of this project was to explore the application of teleoperation and telepresence control to robots in hazardous environments at Los Alamos. The primary use of this technology would be in a glove-box type operation potentially allowing operators to work on hazardous materials while being completely removed from the danger of exposure in situations that are difficult to completely automate due to the highly unstructured environments or off-normal conditions. This project focused on determining the most appropriate tools and methods that could be applied in the near future resulting in a reasonably inexpensive working teleoperation or telepresence control system for industrial robots used in the handling of hazardous materials. Several topics had to be addressed to perform this task including input devices, control systems, robot manipulators, and simulation techniques or packages. Much of the work is still in the developmental stage and hardware will follow -- providing a usable tool for glove box robot control

  18. The dry heat exchanger calorimeter system

    Renz, D.P.; Wetzel, J.R.; James, S.J.; Kasperski, P.W.; Duff, M.F.

    1991-01-01

    A radiometric isothermal heat flow calorimeter and preconditioner system that uses air instead of water as the heat exchange medium has been developed at Mound. The dry heat exchanger calorimeter is 42 inches high by 18 inches in diameter and the preconditioner is a 22 inch cube, making it extremely compact compared to existing units. The new system is ideally suited for transportable, stand-alone, or glovebox applications. Preliminary tests of the system have produced sample measurements with standard deviations less than 0.25% and sample errors less than 0.50%. These tests have shown that the dry heat exchanger system will yield acceptance data with an accuracy comparable to those of Mound water bath systems now in use. 4 figs., 1 tab

  19. Robot hand tackles jobs in hazardous areas

    Simms, Mark; Crowder, Richard.

    1989-01-01

    A robot hand and arm designed to mimic the operation of its human counterpart, developed at the University of Southampton for use in a standard industrial glovebox, is described. It was specifically designed for use in a radioactive environment moving high dosage components around. As dosage limits go down, there is a legal requirement to remove people from that environment. The nine-axis arm is for use in a glove designed for a human hand. Drive for the motors used to power the hand is from three-phase MOSFET inventor cards, the switching pattern controlled by the Hall effect communication sensors integral to each motor. The computer software for the arm allows the hand to be positioned using a joystick on a control box, with three levels of command for grip, pinch and touch. (author)

  20. Inactive trials on a shredder for PCM waste

    Chester, I.B.

    1985-07-01

    Future processing of plutonium contaminated waste will include shredding of all soft items - mainly plastics and paper tissues - from glovebox operations. This paper describes tests on a Metal Box Pulvermatic HS800, prior to its installation in an active area. Measurements were made of the throughput rate of material, temperature rise, hold-up, and the properties of the shredded product. Dust production is of some importance because of the possibility of dust explosions, but it is shown that the concentrations obtained below the cutters are less than those at which a deflagration can be propagated by a factor of at least 100. References to use of a particular manufacturer's product do not necessarily imply a preference for that product. (author)

  1. Optimization of air-sparged plutonium oxalate/hydroxide precipitators

    VanderHeyden, W.B.; Yarbro, S.L.; Fife, K.W.

    1997-04-01

    The high cost of waste management and experimental work makes numerical modeling an inexpensive and attractive tool for optimizing and understanding complex chemical processes. Multiphase open-quotes bubbleclose quotes columns are used extensively at the Los Alamos Plutonium Facility for a variety of different applications. No moving parts and efficient mixing characteristics allow them to be used in glovebox operations. Initially, a bubble column for oxalate precipitations is being modeled to identify the effect of various design parameters such as, draft tube location, air sparge rate and vessel geometry. Two-dimensional planar and axisymmetric models have been completed and successfully compared to literature data. Also, a preliminary three-dimensional model has been completed. These results are discussed in this report along with future work

  2. Hearing of Mrs Marie-Pierre Comets and Mr Marc Sanson, commissioners of the Nuclear Safety Authority (ASN), as well as Mrs Marie-Claude Dupuis, general manager of the National Agency for the management of radioactive wastes (ANDRA), on the nuclear events in Cadarache

    2009-01-01

    Representatives of the French Nuclear Safety Authority (ASN, Autorite de Surete Nucleaire) and of the French National Agency for the Management of Radioactive Wastes (ANDRA, Agence nationale pour la gestion des dechets radioactifs) answer questions about an incident which occurred in a workshop, where MOx fuel was produced and which is now being dismantled. It appeared that the amount of plutonium present in the gloveboxes has been largely under-assessed: 8 kg were expected, 22 kg of plutonium have already been recovered, and finally 39 kg might be recovered by the end the dismantling operations. Other issues are addressed like the ANDRA's projects of radioactive material geological storage, their technical and institutional aspects, and then again about the late declaration of the Cadarache incident

  3. Tips for the fabrication of temporary tritium experiments

    Binning, K.E.; Jenkins, E.M.

    1988-01-01

    The Tritium System Test Assembly (TSTA) is a facility built for the demonstration of tritium handling systems necessary for tritium-burning fusion reactors. The facility has been in operation handling tritium for four years. The current inventory of tritium is approximately one hundred grams with DOE approval exists for a maximum inventory of two hundred grams. Not all experiments performed at TSTA require the operation of the main process loop. During the last four years, many small scale experiments have been performed to test the compatibility and operation of tritium processing components in small self-contained experimental packages. These packages are fabricated inside secondary containment gloveboxes and can be operated for hours or months with little monitoring. Construction of these packages need to be tritium compatible, inexpensive, easy to build, and versatile. This paper discusses some of the problems and remedies encountered during the building of temporary experiments

  4. Digital processing method for monitoring the radioactivity of stack releases

    Vialettes, H.; Leblanc, P.; Perotin, J.P.; Lazou, J.P.

    1978-01-01

    The digital processing method proposed is adapted for data supplied by a fixed-filter detector normally used for analogue processing (integrator system). On the basis of the raw data (pulses) from the detector, the technique makes it possible to determine the rate of activity released whereas analogue processing gives only the released activity. Furthermore, the method can be used to develop alarm systems on the basis of a possible exposure rate at the point of fall-out, and by including in the program a coefficient which allows for atmospheric diffusion conditions at any given time one can improve the accuracy of the results. In order to test the digital processing method and demonstrate its advantages over analogue processing, various atmospheric contamination situations were simulated in a glove-box and analysed simultaneously, using both systems, from the pulses transmitted by the same sampling and fixed-filter detection unit. The experimental results confirm the advantages foreseen in the theoretical research. (author)

  5. Laser light scattering instrument advanced technology development

    Wallace, J. F.

    1993-01-01

    The objective of this advanced technology development (ATD) project has been to provide sturdy, miniaturized laser light scattering (LLS) instrumentation for use in microgravity experiments. To do this, we assessed user requirements, explored the capabilities of existing and prospective laser light scattering hardware, and both coordinated and participated in the hardware and software advances needed for a flight hardware instrument. We have successfully breadboarded and evaluated an engineering version of a single-angle glove-box instrument which uses solid state detectors and lasers, along with fiber optics, for beam delivery and detection. Additionally, we have provided the specifications and written verification procedures necessary for procuring a miniature multi-angle LLS instrument which will be used by the flight hardware project which resulted from this work and from this project's interaction with the laser light scattering community.

  6. Posting system

    Jones, E.L.

    1983-01-01

    A posting system for the movement of equipment, such as a manipulator, into and out of an enclosure e.g. a cell or glovebox, for toxic or radioactive materials has the manipulator arranged within a collapsible bellows-like container with an end of the container cooperating with a port entry to the enclosure. The collapsible container isolates the manipulator from the environment outside the enclosure and allows the manipulator to enter and leave the contaminated enclosure without breach of the containment. A particular construction of cell for use with radioactive material is described, having a thick wall of shielding material such as concrete provided with a door normally closed by a Pb shutter and having a cylindrical gamma shield block located over the shutter on the exterior of the wall. (author)

  7. CRITICALITY CURVES FOR PLUTONIUM HYDRAULIC FLUID MIXTURES

    WITTEKIND WD

    2007-01-01

    This Calculation Note performs and documents MCNP criticality calculations for plutonium (100% 239 Pu) hydraulic fluid mixtures. Spherical geometry was used for these generalized criticality safety calculations and three geometries of neutron reflection are: (sm b ullet)bare, (sm b ullet)1 inch of hydraulic fluid, or (sm b ullet)12 inches of hydraulic fluid. This document shows the critical volume and critical mass for various concentrations of plutonium in hydraulic fluid. Between 1 and 2 gallons of hydraulic fluid were discovered in the bottom of HA-23S. This HA-23S hydraulic fluid was reported by engineering to be Fyrquel 220. The hydraulic fluid in GLovebox HA-23S is Fyrquel 220 which contains phosphorus. Critical spherical geometry in air is calculated with 0 in., 1 in., or 12 inches hydraulic fluid reflection

  8. High pressure apparatus for hydrogen isotopes to pressures of 345 MPa (50,000 psi) and temperatures of 12000C

    Lakner, J.F.

    1977-01-01

    A functional new high pressure, high temperature apparatus for hydrogen isotopes uses an internally heated pressure vessel within a larger pressure vessel. The pressure capability is 345 MPa (50 K psi) at 1200 0 C. The gas pressure inside the internal vessel is balanced with gas pressure in the external vessel. The internal vessel is attached to a closure and is also the sample container. Our design allows thin-walled internal vessel construction and keeps the sample from ''seeing'' the furnace or other extraneous environment. The sample container together with the closure can easily be removed and loaded under argon using standard glove-box procedures. The small volume of the inner vessel permits small volumes of gas to be used, thus increasing the sensitivity during pressure-volume-temperature (PVT) work

  9. Mound's decommissioning experience, tooling, and techniques

    Combs, A.B.; Davis, W.P.; Elswick, T.C.; Garner, J.M.; Geichman, J.R.

    1982-01-01

    Monsanto Research Corporation (MRC), which operates Mound for the Department of Energy (DOE), has been decommissioning radioactively contaminated facilities since 1949. We are currently decommissioning three plutonium-238 contaminated facilities (approximately 50,000 ft 2 ) that contained 1100 linear ft of gloveboxes; 900 linear ft of conveyor housing; 2650 linear ft of dual underground liquid waste lines; and associated contaminated piping, services, equipment, structures, and soil. As of June 1982, over 29,000 Ci of plutonium-238 have been removed in waste and scrap residues. As a result of the current and previous decommissioning projects, valuable experience has been gained in tooling and techniques. Special techniques have been developed in planning, exposure control, contamination control, equipment removal, structural decontamination, and waste packaging

  10. Device for contaminating laboratory animals by inhalation of radioactive aerosols

    Lutz, M.; Rouvroy, H.

    1966-01-01

    The contamination enclosure is made up of a sphere to which are attached an aerosol generator, containers adapted to the animals to be used, and the atmospheric sampling system. The sphere is placed in a protective glove-box, the latter being itself protected by an introduction chamber fitted with locking access lids. A detailed description is given of the working principle. As an example, some results are given concerning the contamination of rats by a plutonium oxide aerosol: characteristics of the powder (mean diameter 0.50 μ - standard deviation: 1.4), examination and evolution of the atmospheric activity as a function of time, evaluation of the retention by the lungs by means of histological and autoradiographic examinations. (authors) [fr

  11. Hot cell design in the vitrification plant China

    Jiang Yubo; Wang Guangkai; Zhang Wei; Liang Runan; Dou Yuan

    2015-01-01

    In the area of reprocessing and radioactive waste management, gloveboxes and cells are a kind of non-standard equipments providing an isolated room to operate radioactive material inside, while the operator outside with essential biological shield and protection. The hot cell is a typical one, which could handle high radioactive material with various operating means and tight enclosure. The dissertation is based on Vitrification Plant China, a cooperation project between China and Germany. For the sino-western difference in design philosophy, it was presented how to draft an acceptable design proposal of applicable huge hot cells by analysing the design requirements, such as radioprotection, observation, illumination, remote handling, transportation, maintenance and decontamination. The construction feasibility of hot cells was also approved. Thanks to 3D software Autodesk Inventor, digital hot cell was built to integrate all the interfaces inside, which validated the design by checking the mechanical interference. (author)

  12. EVALUATION OF STATE-OF-THE-ART MANIPULATORS AND REQUIREMENTS FOR DOE ROBOTICS APPLICATIONS

    BLACK, DEREK; GRUPINSKI, STEPHEN

    1998-10-08

    This report provides an overview of applications within the DOE complex which could benefit from the use of modular robotics technology during remediation operations. Each application area contains one or more specific tasks which are presently conducted by humans under hazardous conditions or which are deemed highly impractical, or are altogether impossible without automation. Five major areas were investigated for specific needs with respect to automation. Information was collected on Mixed Waste Operations, Contaminant Automated Analysis, Tanks, Decontamination and Dismantlement and Automated Plutonium Processing. During this investigation, information was gathered from available literature, telephone interviews with informed personnel and on-site visits. This data serves to provide design requirements and guidelines for the design of a family of modular actuators, which will be used to construct manipulators suited to each task. In addition, a survey of existing modular manipulator designs is presented. This survey addresses modular manipulators developed inside government labs and in universities for such applications as space exploration or controls research. It also addresses efforts at commercially viable industrial manipulators which have been built. This survey of robotic systems provides the reader with a glimpse into what technology currently exists in the way of modular manipulator automation and, to a degree, where this technology may be applicable or, more often, where these systems are unsuited to EM applications. From the information gathered during this study, it is possible to sufficiently define the requirements of one manipulator system which can be used to conduct automated transfer operations within Plutonium gloveboxes. This manipulator will be constructed from ARM Automation actuator modules and will provide this application with a viable option for automation within these gloveboxes. The design issues surrounding this manipulator and its

  13. MODULAR MANIPULATOR FOR ROBOTICS APPLICATIONS

    Joseph W. Geisinger, Ph.D.

    2001-07-31

    ARM Automation, Inc. is developing a framework of modular actuators that can address the DOE's wide range of robotics needs. The objective of this effort is to demonstrate the effectiveness of this technology by constructing a manipulator from these actuators within a glovebox for Automated Plutonium Processing (APP). At the end of the project, the system of actuators was used to construct several different manipulator configurations, which accommodate common glovebox tasks such as repackaging. The modular nature and quickconnects of this system simplify installation into ''hot'' boxes and any potential modifications or repair therein. This work focused on the development of self-contained robotic actuator modules including the embedded electronic controls for the purpose of building a manipulator system. Both of the actuators developed under this project contain the control electronics, sensors, motor, gear train, wiring, system communications and mechanical interfaces of a complete robotics servo device. Test actuators and accompanying DISC{trademark}s underwent validation testing at The University of Texas at Austin and ARM Automation, Inc. following final design and fabrication. The system also included custom links, an umbilical cord, an open architecture PC-based system controller, and operational software that permitted integration into a completely functional robotic manipulator system. The open architecture on which this system is based avoids proprietary interfaces and communication protocols which only serve to limit the capabilities and flexibility of automation equipment. The system was integrated and tested in the contractor's facility for intended performance and operations. The manipulator was tested using the full-scale equipment and process mock-ups. The project produced a practical and operational system including a quantitative evaluation of its performance and cost.

  14. Plutonium assay of large waste burial containers at the Pacific Northwest Laboratory

    Haggard, D.L.; Newman, D.F.

    1987-01-01

    As one phase of an upgrade program at one of the Battelle Pacific Northwest Laboratory facilities, two plutonium glovebox hoods were replaced. They were dismantled, packaged in plastic for contamination control, and loaded into waste burial boxes. All of the plutonium-contaminated waste material from the two glovebox hoods was placed into six stainless steel boxes with identification letters A through F. Boxes A through E have 104.8- x 196.2- x 119.4-cm i.d.'s. Box F has an i.d. of 154.9 x 266.7 x 192.4 cm. The loaded boxes were assayed for plutonium content using both neutron and gamma-ray techniques. The difference between the results were greater than anticipated. Because of the importance of accurate plutonium assay measurements, additional measurements of box contents were made using a variety of techniques and assumptions including downloading of boxes and measurement of individual packages. These measurements have shown that a far-field, gamma-ray assay of a loaded waste box usually provides adequate measurement of low-density plutonium content, such as that found in packages of plastic, cellulose, and clothing. Comparing the far-field assays of the loaded waste boxes to the quantities determined by the assays of the downloaded packages resulted in good agreement between the two methods for boxes with low attenuation. Based on these results, it was concluded that it was valid to use the far-field assay results for the boxes that were not downloaded

  15. Hot Chemistry Laboratory decommissioning activities at IPEN/CNEN-SP, Brazil

    Camilo, Ruth L.; Lainetti, Paulo E.O.

    2009-01-01

    IPEN's fuel cycle activities were accomplished in laboratory and pilot plant scale and most facilities were built in the 70-80 years. Nevertheless, radical changes of the Brazilian nuclear policy in the beginning of 90's determined the interruption of several fuel cycle activities and facilities shutdown. Since then, IPEN has faced the problem of the pilot plants decommissioning considering that there was no experience/expertise in this field at all. In spite of this, some laboratory and pilot plant decommissioning activities have been performed in IPEN in the last years, even without previous experience and training support. One of the first decommissioning activities accomplished in IPEN involved the Hot Chemistry Laboratory. This facility was built in the beginning of the 80's with the proposal of supporting research and development in the nuclear chemistry area. It was decided to settle a new laboratory in the place where the Hot Chemistry Laboratory was installed, being necessary its total releasing from the radioactive contamination point of view. The previous work in the laboratory involved the manipulation of samples of irradiated nuclear fuel, besides plutonium-239 and uranium-233 standard solutions. There were 5 glove-boxes in the facility but only 3 were used with radioactive material. The glove-boxes contained several devices and materials, besides the radioactive compounds, such as: electric and electronic equipment, metallic and plastic pieces, chemical reagents, liquid and solid radioactive wastes, etc. The laboratory's decommissioning process was divided in 12 steps. This paper describes the procedures, problems faced and results related to the Hot Chemistry Laboratory decommissioning operations and its reintegration as a new laboratory of the Chemical and Environmental Technology Center (CQMA) - IPEN-CNEN/SP. (author)

  16. Time-Dependent Neutron and Photon Dose-Field Analysis

    Wooten, Hasani Omar [Georgia Inst. of Technology, Atlanta, GA (United States)

    2005-08-01

    A unique tool is developed that allows the user to model physical representations of complicated glovebox facilities in two dimensions and determine neutral-particle flux and ambient dose-equivalent fields throughout that geometry. The Pandemonium code, originally designed to determine flux and dose-rates only, is improved to include realistic glovebox geometries, time-dependent source and detector positions, time-dependent shielding thickness calculations, time-integrated doses, a representative criticality accident scenario based on time-dependent reactor kinetics, and more rigorous photon treatment. A primary benefit of this work has been an extensive analysis and improvement of the photon model that is not limited to the application described in this thesis. The photon model has been extended in energy range to 10 MeV to include photons from fission and new photon buildup factors have been included that account for the effects of photon buildup at slant-path thicknesses as a function of angle, where the mean free path thickness has been preserved. The overall system of codes is user-friendly and it is directly applicable to facilities such as the plutonium facility at Los Alamos National Laboratory, where high-intensity neutron and photon emitters are regularly used. The codes may be used to determine a priori doses for given work scenarios in an effort to supply dose information to process models which will in turn assist decision makers on ensuring as low as reasonably achievable (ALARA) compliance. In addition, coupling the computational results of these tools with the process model visualization tools will help to increase worker safety and radiological safety awareness.

  17. A method for characterizing photon radiation fields

    Whicker, J.J.; Hsu, H.H.; Hsieh, F.H.; Borak, T.B.

    1999-01-01

    Uncertainty in dosimetric and exposure rate measurements can increase in areas where multi-directional and low-energy photons (< 100 keV) exist because of variations in energy and angular measurement response. Also, accurate measurement of external exposures in spatially non-uniform fields may require multiple dosimetry. Therefore, knowledge of the photon fields in the workplace is required for full understanding of the accuracy of dosimeters and instruments, and for determining the need for multiple dosimeters. This project was designed to develop methods to characterize photon radiation fields in the workplace, and to test the methods in a plutonium facility. The photon field at selected work locations was characterized using TLDs and a collimated NaI(Tl) detector from which spatial variations in photon energy distributions were calculated from measured spectra. Laboratory results showed the accuracy and utility of the method. Field measurement results combined with observed work patterns suggested the following: (1) workers are exposed from all directions, but not isotropically, (2) photon energy distributions were directionally dependent, (3) stuffing nearby gloves into the glovebox reduced exposure rates significantly, (4) dosimeter placement on the front of the chest provided for a reasonable estimate of the average dose equivalent to workers' torsos, (5) justifiable conclusions regarding the need for multiple dosimetry can be made using this quantitative method, and (6) measurements of the exposure rates with ionization chambers pointed with open beta windows toward the glovebox provided the highest measured rates, although absolute accuracy of the field measurements still needs to be assessed

  18. Effect of hole-transporting materials on the photovoltaic performance and stability of all-ambient-processed perovskite solar cells

    Nanaji Islavath; S Saroja; K Srinivas Reddy; P C Harikesh; G Veerappan; Shrikant V Joshi; Easwaramoorthi Ramasamy

    2017-01-01

    High-efficiency perovskite solar cells (PSCs) reported hitherto have been mostly prepared in a moisture and oxygen-free glove-box atmosphere,which hampers upscaling and real-time performance assessment of this exciting photovoltaic technology.In this work,we have systematically studied the feasibility of allambient-processing of PSCs and evaluated their photovoltaic performance.It has been shown that phasepure crystalline tetragonal MAPbI3 perovskite films are instantly formed in ambient air at room temperature by a two-step spin coating process,undermining the need for dry atmosphere and post-annealing.All-ambient-processed PSCs with a configuration of FTO/TiO2/MAPbI3/Spiro-OMeTAD/Au achieve opencircuit voltage (990 mV) and short-circuit current density (20.31 mA/cm2) comparable to those of best reported glove-box processed devices.Nevertheless,device power conversion efficiency is still constrained at 5% by the unusually low fill-factor of 0.25.Dark current-voltage characteristics reveal poor conductivity of hole-transporting layer caused by lack of oxidized spiro-OMeTAD species,resulting in high seriesresistance and decreased fill-factor,The study also establishes that the above limitations can be readily overcome by employing an inorganic p-type semiconductor,copper thiocyanate,as ambient-processable hole-transporting layer to yield a fill-factor of 0.54 and a power conversion efficiency of 7.19%.The present findings can have important implications in industrially viable fabrication of large-area PSCs.

  19. VALIDATION OF HANFORD PERSONNEL AND EXTREMITY DOSIMETERS IN PLUTONIUM ENVIRONMENTS

    Scherpelz, Robert I.; Fix, John J.; Rathbone, Bruce A.

    2000-02-10

    A study was performed in the Plutonium Finishing Plant to assess the performance of Hanford personnel neutron dosimetry. The study was assessed whole body dosimetry and extremity dosimetry performance. For both parts of the study, the TEPC was used as the principle instrument for characterizing workplace neutron fields. In the whole body study, 12.7-cm-diameter TEPCs were used in ten different locations in the facility. TLD and TED personnel dosimeters were exposed on a water-filled phantom to enable a comparison of TEPC and dosimeter response. In the extremity study, 1.27-cm-diameter TEPCs were exposed inside the fingers of a gloveboxe glove. Extremity dosimeters were wrapped around the TEPCs. The glove was then exposed to six different cans of plutonium, simulating the exposure that a worker's fingers would receive in a glovebox. The comparison of TEPC-measured neutron dose equivalent to TLD-measured gamma dose equivalent provided neutron-to-gamma ratios that can be used to estimate the neutron dose equivalent received by a worker's finger based on the gamma readings of an extremity dosimeter. The study also utilized a Snoopy and detectors based on bubble technology for assessing neutron exposures, providing a comparison of the effectiveness of these instruments for workplace monitoring. The study concludes that the TLD component of the HCND performs adequately overall, with a positive bias of 30%, but exhibits excessive variability in individual results due to instabilities in the algorithm. The TED response was less variable but only 20% of the TEPC reference dose on average because of the low neutron energies involved. The neutron response of the HSD was more variable than the TLD component of the HCND and biased high by a factor of 8 overall due to its calibration to unmoderated 252Cf. The study recommends further work to correct instabilities in the HCND algorithm and to explore the potential shown by the bubble-based dosimeters.

  20. Ergonomic Evaluations of Microgravity Workstations

    Whitmore, Mihriban; Berman, Andrea H.; Byerly, Diane

    1996-01-01

    Various gloveboxes (GBXs) have been used aboard the Shuttle and ISS. Though the overall technical specifications are similar, each GBX's crew interface is unique. JSC conducted a series of ergonomic evaluations of the various glovebox designs to identify human factors requirements for new designs to provide operator commonality across different designs. We conducted 2 0g evaluations aboard the Shuttle to evaluate the material sciences GBX and the General Purpose Workstation (GPWS), and a KC-135 evaluation to compare combinations of arm hole interfaces and foot restraints (flexible arm holes were better than rigid ports for repetitive fine manipulation tasks). Posture analysis revealed that the smallest and tallest subjects assumed similar postures at all four configurations, suggesting that problematic postures are not necessarily a function of the operator s height but a function of the task characteristics. There was concern that the subjects were using the restrictive nature of the GBX s cuffs as an upper-body restraint to achieve such high forces, which might lead to neck/shoulder discomfort. EMG data revealed more consistent muscle performance at the GBX; the variability in the EMG profiles observed at the GPWS was attributed to the subjects attempts to provide more stabilization for themselves in the loose, flexible gauntlets. Tests revealed that the GBX should be designed for a 95 percentile American male to accommodate a neutral working posture. In addition, the foot restraint with knee support appeared beneficial for GBX operations. Crew comments were to provide 2 foot restraint mechanical modes, loose and lock-down, to accommodate a wide range of tasks without egressing the restraint system. Thus far, we have developed preliminary design guidelines for GBXs and foot.

  1. Application of cryogenic grinding to achieve homogenization of transuranic wastes

    Atkins, W.H.; Hill, D.D.; Lucero, M.E.; Jaramillo, L.; Martinez, H.E.

    1996-08-01

    This paper describes work done at Los Alamos National Laboratory (LANL) in collaboration with the Department of Energy Rocky Flats Field Office (DOE/RFFO) and with the National Institute of Standards and Technology (NIST), Boulder, Colorado. Researchers on this project have developed a method for cryogenic grinding of mixed wastes to homogenize and, thereby, to acquire a representative sample of the materials. There are approximately 220,000 waste drums owned by the Rocky Flats Environmental Technology Site (RFETS)-50,000 at RFETS and 170,000 at the Idaho National Engineering Laboratory. The cost of sampling the heterogeneous distribution of waste in each drum is prohibitive. In an attempt to produce a homogeneous mixture of waste that would reduce greatly the cost of sampling, researchers at NIST and RFETS are developing a cryogenic grinder. The Los Alamos work herein described addresses the implementation issues of the task. The first issue was to ascertain whether samples of the open-quotes small particleclose quotes mixtures of materials present in the waste drums at RFETS were representative of actual drum contents. Second, it was necessary to determine at what temperature the grinding operation must be performed in order to minimize or to eliminate the release of volatile organic compounds present in the waste. Last, it was essential to evaluate any effect the liquid cryogen might have on the structural integrity and ventilation capacity of the glovebox system. Results of this study showed that representative samples could be and had been obtained, that some release of organics occurred below freezing because of sublimation, and that operation of the cryogenic grinding equipment inside the glovebox was feasible

  2. Treatment of tritiated exhaust gases at the Tritium Laboratory Karlsruhe

    Hutter, E.; Besserer, U. [Kernforschungszentrum Karlsruhe GmbH (Germany); Jacqmin, G. [NUKEM GmbH, Industreistr, Alzenau (Germany)

    1995-02-01

    The Tritium Laboratory Karlsruhe (TLK) accomplished commissioning; tritium involving activities will start this year. The laboratory is destined mainly to investigating processing of fusion reactor fuel and to developing analytic devices for determination of tritium and tritiated species in view of control and accountancy requirements. The area for experimental work in the laboratory is about 800 m{sup 2}. The tritium infrastructure including systems for tritium storage, transfer within the laboratory and processing by cleanup and isotope separation methods has been installed on an additional 400 m{sup 2} area. All tritium processing systems (=primary systems), either of the tritium infrastructure or of the experiments, are enclosed in secondary containments which consist of gloveboxes, each of them connected to the central depressurization system, a part integrated in the central detritiation system. The atmosphere of each glovebox is cleaned in a closed cycle by local detritiation units controlled by two tritium monitors. Additionally, the TLK is equipped with a central detritiation system in which all gases discharged from the primary systems and the secondary systems are processed. All detritiation units consist of a catalyst for oxidizing gaseous tritium or tritiated hydrocarbons to water, a heat exchanger for cooling the catalyst reactor exhaust gas to room temperature, and a molecular sieve bed for adsorbing the water. Experiments with tracer amounts of tritium have shown that decontamination factors >3000 can be achieved with the TLK detritiation units. The central detritiation system was carefully tested and adjusted under normal and abnormal operation conditions. Test results and the behavior of the tritium barrier preventing tritiated exhaust gases from escaping into the atmosphere will be reported.

  3. MODULAR MANIPULATOR FOR ROBOTICS APPLICATIONS

    Geisinger, Joseph W. Ph.D.

    2001-01-01

    ARM Automation, Inc. is developing a FR-amework of modular actuators that can address the DOE's wide range of robotics needs. The objective of this effort is to demonstrate the effectiveness of this technology by constructing a manipulator FR-om these actuators within a glovebox for Automated Plutonium Processing (APP). At the end of the project, the system of actuators was used to construct several different manipulator configurations, which accommodate common glovebox tasks such as repackaging. The modular nature and quickconnects of this system simplify installation into ''hot'' boxes and any potential modifications or repair therein. This work focused on the development of self-contained robotic actuator modules including the embedded electronic controls for the purpose of building a manipulator system. Both of the actuators developed under this project contain the control electronics, sensors, motor, gear train, wiring, system communications and mechanical interfaces of a complete robotics servo device. Test actuators and accompanying DISC(trademark)s underwent validation testing at The University of Texas at Austin and ARM Automation, Inc. following final design and fabrication. The system also included custom links, an umbilical cord, an open architecture PC-based system controller, and operational software that permitted integration into a completely functional robotic manipulator system. The open architecture on which this system is based avoids proprietary interfaces and communication protocols which only serve to limit the capabilities and flexibility of automation equipment. The system was integrated and tested in the contractor's facility for intended performance and operations. The manipulator was tested using the full-scale equipment and process mock-ups. The project produced a practical and operational system including a quantitative evaluation of its performance and cost

  4. Onsite vibrational characterization of DCMIX2/3 experiments

    Ollé, Judit; Dubert, Diana; Gavaldà, Josefina; Laverón-Simavilla, Ana; Ruiz, Xavier; Shevtsova, Valentina

    2017-11-01

    The SODI-DCMIX thermodiffusion series experiments are part of the fluid research program carried out by the European Space Agency on board of the International Space Station (ISS). In particular, DCIMIX2/3 were conducted in the past inside the Microgravity Science Glovebox in the US Laboratory. Due to the physical nature of the processes implied, these kind of runs were very long and particularly delicate because the low vibratory limit requirements must be maintained for hours. This restrictive condition not always is achieved, therefore, an accurate surveillance of the acceleration levels along the different experiments is necessary, to ensure a correct interpretation of the experimental results. This work analyzes onsite vibrational environment of DCMIX2/3 covering the periods in which the experiments were going on. To do so, acceleration signals only coming from the es03 sensor, nearest to the experimental equipment and located in the Glovebox, were downloaded from the PIMS NASA website. To be as precise as possible the signals have always been treated minute by minute. To detect the transient disturbances along the experiments, several warnings were considered. First, 1 min RMS values, for the three acceleration components were evaluated, in time and in frequency domain. Additional information was obtained by plotting the power spectral densities of the signals, PSD, and their spectrogram with the aim of characterizing long periods of acceleration data. Due to great influence of low frequencies in this type of experiments, the Frequency Factor Index, FFI, was evaluated each minute. Complementary, the spectral entropy evolution was proposed as a fast new indicator of external perturbations. It has been found a good correlation between the spectrogram, temporal RMS and spectral entropy. Finally, a graphic representation of the points associated to the 1-min RMS values in one-third-octave frequency intervals which exceed the ISS limit curve requirements, was

  5. Bi-Modal Model for Neutron Emissions from PuO2 and MOX Holdup

    Menlove, Howard; Lafleur, Adrienne

    2015-01-01

    The measurement of uranium and plutonium holdup in plants during process activity and for decommissioning is important for nuclear safeguards and material control. The amount of plutonium and uranium holdup in glove-boxes, pipes, ducts, and other containers has been measured for several decades using both neutron and gamma-ray techniques. For the larger containers such as hot cells and glove-boxes that contain processing equipment, the gamma-ray techniques are limited by self-shielding in the sample as well as gamma absorption in the equipment and associated shielding. The neutron emission is more penetrating and has been used extensively to measure the holdup for the large facilities such as the MOX processing and fabrication facilities in Japan and Europe. In some case the totals neutron emission rates are used to determine the holdup mass and in other cases the coincidence rates are used such as at the PFPF MOX fabrication plant in Japan. The neutron emission from plutonium and MOX has 3 primary source terms: 1) Spontaneous fission (SF) from the plutonium isotopes, 2) The (α,n) reactions from the plutonium alpha particle emission reacting with the oxygen and other impurities, and 3) Neutron multiplication (M) in the plutonium and uranium as a result of neutrons created by the first two sources. The spontaneous fission yield per gram is independent of thickness, whereas, the above sources 2) and 3) are very dependent on the thickness of the deposit. As the effective thickness of the deposit becomes thin relative to the alpha particle range, the (α,n) reactions and neutrons from multiplication (M) approach zero. In any glove-box, there will always be two primary modes of holdup accumulation, namely direct powder contact and non-contact by air dispersal. These regimes correspond to surfaces in the glove-box that have come into direct contact with the process MOX powder versus surface areas that have not had direct contact with the powder. The air dispersal of Pu

  6. Bi-Modal Model for Neutron Emissions from PuO{sub 2} and MOX Holdup

    Menlove, Howard; Lafleur, Adrienne [Los Alamos National Laboratory, Safeguard Science and Technology Group, NEN-1, MS E540, Los Alamos, NM, 87545 (United States)

    2015-07-01

    The measurement of uranium and plutonium holdup in plants during process activity and for decommissioning is important for nuclear safeguards and material control. The amount of plutonium and uranium holdup in glove-boxes, pipes, ducts, and other containers has been measured for several decades using both neutron and gamma-ray techniques. For the larger containers such as hot cells and glove-boxes that contain processing equipment, the gamma-ray techniques are limited by self-shielding in the sample as well as gamma absorption in the equipment and associated shielding. The neutron emission is more penetrating and has been used extensively to measure the holdup for the large facilities such as the MOX processing and fabrication facilities in Japan and Europe. In some case the totals neutron emission rates are used to determine the holdup mass and in other cases the coincidence rates are used such as at the PFPF MOX fabrication plant in Japan. The neutron emission from plutonium and MOX has 3 primary source terms: 1) Spontaneous fission (SF) from the plutonium isotopes, 2) The (α,n) reactions from the plutonium alpha particle emission reacting with the oxygen and other impurities, and 3) Neutron multiplication (M) in the plutonium and uranium as a result of neutrons created by the first two sources. The spontaneous fission yield per gram is independent of thickness, whereas, the above sources 2) and 3) are very dependent on the thickness of the deposit. As the effective thickness of the deposit becomes thin relative to the alpha particle range, the (α,n) reactions and neutrons from multiplication (M) approach zero. In any glove-box, there will always be two primary modes of holdup accumulation, namely direct powder contact and non-contact by air dispersal. These regimes correspond to surfaces in the glove-box that have come into direct contact with the process MOX powder versus surface areas that have not had direct contact with the powder. The air dispersal of Pu

  7. Synthesis of porous graphene powder through improved Hummers' method

    Gupta, Siddhant; Bonageri, Shrilakshmi; Achar, Siddarth Krishnaraja; Menon, Atul; Basavaraja R., J.

    2018-05-01

    Graphene due to its high specific surface area is considered to be a potential adsorbent for air and water purification systems. In this study, graphene was synthesized using the recently developed Improved Hummers' method to achieve a high oxidation rate and thermal treatment of the synthesized graphene was done to increase its pore size and make it more capable for applications in purification systems. Graphite flakes were oxidized to obtain graphene oxide which was then reduced to obtain graphene. The synthesized graphene was then thermally treated at 200 °C for two hours in a muffle furnace to improve its surface properties. The characterization results of graphene oxide and graphene show the presence of many impurities which is inferred to be the result of contaminated water used in the experimentation. The analysis of the characterization results also shows that the thermally treated graphene has more spacing and voids when compared to graphene which makes it a better suit for adsorption of gases such as carbon dioxide.

  8. Low-Temperature Sol-Gel Synthesis of Nitrogen-Doped Anatase/Brookite Biphasic Nanoparticles with High Surface Area and Visible-Light Performance

    Liang Jiang

    2017-12-01

    Full Text Available Nitrogen doping in combination with the brookite phase or a mixture of TiO2 polymorphs nanomaterials can enhance photocatalytic activity under visible light. Generally, nitrogen-dopedanatase/brookite mixed phases TiO2 nanoparticles obtained by hydrothermal or solvothermal method need to be at high temperature and with long time heating treatment. Furthermore, the surface areas of them are low (<125 m2/g. There is hardly a report on the simple and direct preparation of N-doped anatase/brookite mixed phase TiO2 nanostructures using sol-gel method at low heating temperature. In this paper, the nitrogen-doped anatase/brookite biphasic nanoparticles with large surface area (240 m2/g were successfully prepared using sol-gel method at low temperature (165 °C, and with short heating time (4 h under autogenous pressure. The obtained sample without subsequent annealing at elevated temperatures showed enhanced photocatalytic efficiency for the degradation of methyl orange (MO with 4.2-, 9.6-, and 7.5-fold visible light activities compared to P25 and the amorphous samples heated in muffle furnace with air or in tube furnace with a flow of nitrogen at 165 °C, respectively. This result was attributed to the synergistic effects of nitrogen doping, mixed crystalline phases, and high surface area.

  9. Perceiving the vertical distances of surfaces by means of a hand-held probe.

    Chan, T C; Turvey, M T

    1991-05-01

    Nine experiments were conducted on the haptic capacity of people to perceive the distances of horizontal surfaces solely on the basis of mechanical stimulation resulting from contacting the surfaces with a vertically held rod. Participants touched target surfaces with rods inside a wooden cabinet and reported the perceived surface location with an indicator outside the cabinet. The target surface, rod, and the participant's hand were occluded, and the sound produced in exploration was muffled. Properties of the probe (length, mass, moment of inertia, center of mass, and shape) were manipulated, along with surface distance and the method and angle of probing. Results suggest that for the most common method of probing, namely, tapping, perceived vertical distance is specific to a particular relation among the rotational inertia of the probe, the distance of the point of contact with the surface from the probe's center of percussion, and the inclination at contact of the probe to the surface. They also suggest that the probe length and the distance probed are independently perceivable. The results were discussed in terms of information specificity versus percept-percept coupling and parallels between selective attention in haptic and visual perception.

  10. A Study on the Pyrolysis of Peanut Shells at Different Isothermal Conditions and Determination of the Kinetic Parameters

    Şeyda Taşar

    2015-12-01

    Full Text Available The pyrolysis process, which is applied for the aim of producing energy and raw materials which are implemented for the chemical industry from biomass sources, is a thermal conversion process. Determination of the pyrolysis kinetic parameters are important In order to suitable equipment and process design. In this target, in the study the pyrolysis of peanut shells was conducted in a muffle furnace at static atmosphere with temperatures ranging from 300-700 °C. The effects of various parameters on the rate of thermal decomposition rate and the solid yield were determined. The parameters of interest were temperature 300-700 °C, particle size 4-50 mesh, pelletizing, and pelletizing pressure 1.103-5.103 kgf/cm2. Regression coefficients for the total decomposition step were obtained using the thermographs were obtained as a result of the pyrolysis of the peanut shells, and 20 different theoretical model equations that represented the degradation by the Coast-Redfern method. According to regression coefficients of the theoretical model equations, we determined the kinetic model that best represented the degradation. Using this model to represent the degradation, the activation energy (Ea and Arhenius frequency factor ln(A for the total reaction were calculated to be 38.245 kJ/mol and 8.124, respectively.

  11. Measurement of relative permittivity of LTCC ceramic at different temperatures

    Qiulin Tan

    2014-02-01

    Full Text Available Devices based on LTCC (low-temperature co-fired ceramic technology are more widely applied in high temperature environments, and the temperature-dependent properties of the LTCC material play an important role in measurements of the characteristics of these devices at high temperature. In this paper, the temperature-dependence of the relative permittivity of DuPont 951 LTCC ceramic is studied from room temperature to 500 °C. An expression for relative permittivity is obtained, which relates the relative permittivity to the resonant frequency, inductance, parasitic capacitance and electrode capacitance of the LTCC sample. Of these properties, the electrode capacitance is the most strongly temperature-dependent. The LTCC sample resonant frequency, inductance and parasitic capacitance were measured (from room temperature to 500 °C with a high temperature measurement system comprising a muffle furnace and network analyzer. We found that the resonant frequency reduced and the inductance and parasitic capacitance increased slightly as the temperature increases. The relative permittivity can be calculated from experimental frequency, inductance and parasitic capacitance measurements. Calculating results show that the relative permittivity of DuPont 951 LTCC ceramic ceramic increases to 8.21 from room temperature to 500 °C.

  12. Postobstructive pulmonary edema after biopsy of a nasopharyngeal mass.

    Mehta, Keyur Kamlesh; Ahmad, Sabina Qureshi; Shah, Vikas; Lee, Haesoon

    2015-01-01

    We describe a case of 17 year-old male with a nasopharyngeal rhabdomyosarcoma who developed postobstructive pulmonary edema (POPE) after removing the endotracheal tube following biopsy. He developed muffled voice, rhinorrhea, dysphagia, odynophagia, and difficulty breathing through nose and weight loss of 20 pounds in the preceding 2 months. A nasopharyngoscopy revealed a fleshy nasopharyngeal mass compressing the soft and hard palate. Head and neck MRI revealed a large mass in the nasopharynx extending into the bilateral choana and oropharynx. Biopsy of the mass was taken under general anesthesia with endotracheal intubation. Immediately after extubation he developed oxygen desaturation, which did not improve with bag mask ventilation with 100% of oxygen, but improved after a dose of succinylcholine. He was re-intubated and pink, frothy fluid was suctioned from the endotracheal tube. Chest radiograph (CXR) was suggestive of an acute pulmonary edema. He improved with mechanical ventilation and intravenous furosemide. His pulmonary edema resolved over the next 24 h. POPE is a rare but serious complication associated with upper airway obstruction. The pathophysiology of POPE involves hemodynamic changes occurring in the lung and the heart during forceful inspiration against a closed airway due to an acute or chronic airway obstruction. This case illustrates the importance of considering the development of POPE with general anesthesia, laryngospasm and removal of endotracheal tube to make prompt diagnosis and to initiate appropriate management.

  13. Evaluation of the vitreous matrices to include high-level radioactive wastes

    Varani, J.L.; Petraitis, E.J.; Pasquali, R.C.

    1987-01-01

    The Argentine Nuclear Programme considers a fuel cycle with Pu recycle. This will generate high-level liquid wastes, that should be safely eliminated. With this purpose, primary glasses utilizing three prototipe compositions were prepared. Simulated wastes oxides in the rate of about 10% were added to the vitreous matrices. The mixture was melted in ceramic melting pots in a muffle furnace at 1 100 deg C during 8 hours. Resistance leaching tests were made following an adaptation of the DIN 12 111 standard. Quantitative analysis of the leaching solutions were made to evaluate the solubility of the different elements. Glasses were observed with optical microscopy scanning before and after leaching. In the first, glasses, bubbles and crystalline-phase appear; in the second ones, puncture and embrittlement were detected. By means of differential thermoanalysis, endo and exothermal peaks were identified in glasses supporting gradual heating. X ray diffraction analysis were made in samples with and without wastes. The degree of crystallization of samples was evaluated by photographic and diffractometric techniques. Leaching studies showed the existance of a direct relation between leaching and glass alkaline content. (M.E.L.) [es

  14. The Micromorphological Research of the Internal Structure of Chairside CAD/CAM Materials by the Method of Scanning Impulse Acoustic Microscopy (SIAM).

    Goryainova, Kristina E; Morokov, Egor S; Retinskaja, Marina V; Rusanov, Fedor S; Apresyan, Samvel V; Lebedenko, Igor Yu

    2018-01-01

    The aim of the present work was to compare the elastic properties and internal structure of 4 different CAD/CAM chairside materials, by the method of Scanning Impulse Acoustic Microscopy (SIAM). Four chairside CAD/CAM materials with different structures from hybrid ceramic (VITA Enamic, VITA Zahnfabrik), feldspatic ceramic (VITABlocs Mark II, VITA Zahnfabrik), leucite glass-ceramic (IPS Empress CAD, Ivoclar Vivadent) and PMMA (Telio CAD, Ivoclar Vivadent) were examined by Scanning Impulse Acoustic Microscope (SIAM). The results of micromorphological research of CAD/CAM chairside materials using SIAM method showed differences between the internal structures of these materials. The internal structure of feldspatic and glass-ceramic samples revealed the presence of pores with different sizes, from 10 to 100 microns; the structure of polymer materials rendered some isolated defects, while in the structure of hybrid material, defects were not found. Based on the results obtained from the present study, in cases of chairside production of dental crowns, it would be advisable to give preference to the blocks of hybrid ceramics. Such ceramics devoid of quite large porosity, glazing for CAD/CAM crowns made from leucite glass-ceramic and feldspatic ceramic may be an option. For these purposes, commercially available special muffle furnace for clinical and laboratory individualization and glazing of ceramic prostheses were provided. Further studies are needed to confirm the evidence emerging from the present research.

  15. Oxidation behavior of NiCoCrAlY coatings deposited by double-Glow plasma alloying

    Cui, Shiyu; Miao, Qiang; Liang, Wenping; Li, Baiqiang

    2018-01-01

    The NiCoCrAlY coatings were deposited on the Inconel 718 alloy substrates by a novel method called double-glow plasma alloying (DG). The phases and microstructure of the coatings were investigated by X-ray diffraction analysis while their chemical composition was analyzed using scanning electron microscopy. The morphology of the NiCoCrAlY coatings was typical of coatings formed by DG, with their structure consisting of uniform submicron-sized grains. Further, the coatings showed high adhesion strength (critical load >46 N). In addition, the oxidation characteristics of the coatings and the substrate were examined at three different temperatures (850, 950, and 1050 °C) using a muffle furnace. The coatings showed a lower oxidation rate, which was approximately one-tenth of that of the substrate. Even after oxidation for 100 h, the Al2O3 phase was the primary phase in the surface coating (850 °C), with the thickness of the oxide film increasing to 0.65 μm at 950 °C. When the temperature was increased beyond 1050 °C, the elemental Al and Ni were consumed in the formation of the oxide scale, which underwent spallation at several locations. The oxidation products of Cr, which were produced in large amounts and had a prism-like structure, controlled the subsequent oxidation behavior at the surface.

  16. Influence of pentavalent dopant addition to polarization and bioactivity of hydroxyapatite

    Dhal, Jharana; Bose, Susmita; Bandyopadhyay, Amit

    2013-01-01

    Influence of pentavalent tantalum doping in bulk hydroxyapatite (HAp) ceramics has been investigated for polarizability and bioactivity. Phase analysis from X-ray diffraction measurement indicates that increasing dopant concentration decreased the amount of HAp phase and increased β-TCP and/or α-TCP phases during sintering at 1250 °C in a muffle furnace. Results from thermally stimulated depolarization current (TSDC) measurements showed that doping hindered charge storage ability in HAp ceramics, and doped samples stored fewer charge compared to pure HAp. However, doping enhanced wettability of HAp samples, which was improved further due to polarization. In vitro human osteoblast cell–material interaction study revealed an increase in bioactivity due to dopant addition and polarization compared to pure HAp. This increase in bioactivity was attributed to the increase in wettability due to surface charge and dopant addition. - Highlights: • Tantalum doping makes HAp unstable during sintering at 1250 °C and forms TCP. • Tantalum doping reduces charge storage ability of HAp ceramics. • Even with lower charge storage ability tantalum doping improves wettability. • Tantalum doping enhances bioactivity of calcium phosphate based sintered compacts

  17. Solution combustion synthesis of the nanocrystalline NCM oxide for lithium-ion battery uses

    Habibi, Amirhosein; Jalaly, Maisam; Rahmanifard, Roohollah; Ghorbanzadeh, Milad

    2018-02-01

    In this study, the NCM cathode with a chemical composition of {{{LiNi}}}1/3}{{{Co}}}1/3}{{{Mn}}}1/3}{{{O}}}2 were synthesized through a solution combustion method. In this method, metal nitrates and urea were used as precursors and fuel, respectively. The powder obtained from combustion were transferred into a alumina crucible and insert to the muffle furnace and calcined at 750 °C for 15 h. The crystallite size of the sample was calculated with sherer equation to be about 41 nm. The prepared cathode were characterized using x-ray diffraction (XRD), scanning electron microscopy (SEM), thermogravimetry analysis (TGA), differential scanning calorimetry (DSC) and battery charge-discharge test. The initial charge and discharge capacities of {{{LiNi}}}1/3}{{{Co}}}1/3}{{{Mn}}}1/3}{{{O}}}2 electrode containing 94% active material at a rate of 0.05 C in voltage window of 2.5-4.3 V at room temperature was obtained 168.03 and 150.01 mAh g-1, respectively.

  18. Growth of CdS thin films on indium coated glass substrates via chemical bath deposition and subsequent air annealing

    Ghosh, Biswajit; Kumar, Kamlesh; Singh, Balwant Kr; Banerjee, Pushan; Das, Subrata, E-mail: neillohit@yahoo.co.in

    2014-11-30

    Graphical abstract: - Highlights: • CdS film grown on indium coated glass substrates via CBD and subsequent annealing. • Disappearance of the indium (1 1 2) peak confirms interdiffusion at 300 °C. • SIMS indicates the subsequent interdiffusion at progressively higher temperature. • Composite In–CdS layer showed lower photosensitivity compared to pure CdS. - Abstract: In the present work attempts were made to synthesize indium doped CdS films by fabricating In/CdS bilayers using CBD-CdS on vacuum evaporated In thin films and subsequent air annealing. 135 nm CdS films were grown onto 20 nm and 35 nm indium coated glass substrate employing chemical bath deposition technique. The In/CdS bilayers thus formed were subjected to heat treatment at the temperatures between 200 and 400 °C for 4 min in the muffle furnace to facilitate indium to diffuse into the CdS films. XRD pattern ascertained no noticeable shift in lattice constant implying grain boundary metal segregation, while secondary ion mass spectrometry indicated the diffusion profile of indium into CdS matrices. Mass spectrometry results showed that substantial diffusion of indium had been taken place within CdS at 400 °C. Dark and photocurrent with different illumination time were measured to ascertain the photosensitivity of pure and composite CdS films.

  19. Strontium-90 and cesium-137 in total diet

    1979-01-01

    Under the commission of Science and Technology Agency, prefectural public health laboratories and institutes and Japan Chemical Analysis Center have collected total diet samples, and determined the contents of 90 Sr and 137 Cs in these samples. Thirty-two prefectural public health laboratories and institutes have collected 2 times a year all the daily regular diet consumed for five persons, namely three meals and other eating between them. These samples were collected at Japan Chemical Analysis Center after carbonization without smoke rising. At Japan Chemical Analysis Center, these samples were ashed in an electric muffle furnace. And the ash to which both some carriers were added were destroyed with hydrochloric acid and nitric acid. The nuclides were dissolved into hydrochloric acid and filtrated, after it was added with nitric acid. The nuclides were dissolved into hydrochloric acid and filtrated, after it was added with nitric acid. The samples solution including radionuclides was extracted with hydrochloric acid and water, and 90 Y which reached radioactive equivallence to 90 Sr, and 137 Cs were chemically separated from it. And the radioactivity was measured with low back ground beta-ray spectrometer. (author)

  20. Sol-gel synthesis of lithium metatitanate as tritium breeding material under different sintering conditions

    Lu, Wei; Wang, Jing; Pu, Wenjing; Li, Kaiping; Ma, Shubing; Wang, Weihua

    2018-04-01

    Lithium metatitanate (Li2TiO3) is a promising tritium breeding material candidate for solid blanket of D-T fusion reactors, due to its high mechanical strength, chemical stability, and tritium release rate. In this paper, Li2TiO3 powder with homogeneous crystal structure is synthesized by sol-gel method. The chemical reactions in gel thermal cracking and sintering process are studied by thermo gravimetric/differential scanning calorimetry (TG-DSC). The relationship between the sintering condition and the particle/grain size is characterized by X-ray diffraction (XRD) and scanning electron microscopy (SEM). Results show that below 673 K the gel precursor is completely decomposed and Li2TiO3 phase initially forms. The LiTiO2 by-product formed under the reductive atmosphere in muffle furnace, could be oxidized continually to Li2TiO3 at higher sintering temperature (≥1273 K) for longer sintering time (≥10 h). Both grain and particle sizes rely on a linear growth with the increase of sintering time at 1273 K. Over 1473 K, significant agglomerations exist among particles. The optimal sintering condition is selected as 1273 K for 10 h, for the purer Li2TiO3 phase (>99%), smaller grain and particle size.

  1. Noise and vibration levels in artificial polar bear dens as related to selected petroleum exploration and developmental activities

    Blix, A.S.; Lentfer, J.W.

    1992-01-01

    Petroleum exploration and development are occurring in various locations in the Arctic, where there are important denning sites for polar bears. Petroleum activities usually coincide with winter denning activities by bears, who may abandon dens if subject to prolonged annoyance. A study was carried out to measure noise and vibration levels in artificial polar bear dens at Prudhoe's Bar, Alaska, resulting from seismic testing, drilling and transport. A microphone and an accelerometer were frozen to the floor of the dens, with leads passed through a consolidated snow filled entrance to a truck, tent or helicopter. Tests were carried out on land, sea ice, and next to a drilling tower on an artificial island, which was also used to measure noise levels resulting from a helicopter taking off. It was concluded that the dry and wind-beaten arctic snow muffles both sound and vibration extremely well, and it is unlikely that polar bears in their dens will be disturbed by the type of petroleum-related activities measured, provided they do not take place within 100 m of the dens. 8 refs., 7 figs., 1 tab

  2. Focal intramural pericardial effusion and cardiac tamponade associated with necrotic adipose tissue in a dog.

    Krentz, Terence A; Schutrumpf, Robert J; Zitz, Julie C

    2017-07-15

    CASE DESCRIPTION A 1-year-old castrated male German Shepherd Dog was examined because of an acute onset of lethargy, tachypnea, and inappetence. CLINICAL FINDINGS On initial physical examination, the dog was tachypneic with muffled heart sounds on thoracic auscultation and a palpable abdominal fluid wave. Transthoracic echocardiography revealed focal intramural pericardial effusion and cardiac tamponade. TREATMENT AND OUTCOME The patient underwent emergency therapeutic pericardiocentesis, followed by right lateral intercostal thoracotomy and subtotal pericardiectomy. A 3 × 5-cm mass located between the parietal and visceral layers of the pericardium was resected. The histologic diagnosis was necrotic adipose tissue with granulomatous inflammation and fibroplasia. The patient also underwent exploratory laparotomy and umbilical herniorrhaphy during the same anesthetic episode and recovered from surgery without apparent complications. There were no further clinical signs of cardiac disease. CLINICAL RELEVANCE The patient described in the present report underwent successful subtotal pericardiectomy for treatment of a benign focal lesion causing recurrent pericardial effusion and cardiac tamponade. Prompt diagnosis and intervention may have contributed to the positive outcome in this case.

  3. Macro and trace elements in edible mushrooms, Shiitake, Shimeji and Cardoncello from Petrópolis, Rio de Janeiro, Brazil

    Jaylei Monteiro Gonçalves

    2014-05-01

    Full Text Available The concentrations of twenty-five elements (Al, As, Ba, Bi, Ca, Cd, Cr, Cu, Fe, Ga, K, Li, Mg, Mn, Mo, Na, Ni, Pb, Rb , Sb, Se, Sn, Sr, V and Zn were determined in three edible mushrooms, Shiitake (Lentinula edodes, Black Shimeji (Pleurotus ostreatusi and Cardoncello (Pleurotus eryngyii from Petrópolis, Rio de Janeiro, Brazil. Samples were collected along the year 2010 and their preparations were made after drying, milling, an acid pre-digestion and a decomposition procedure in a muffle furnace. The analytical techniques employed for the elements determination were Mass Spectrometry with Inductively Coupled Plasma and Flame Atomic Absorption Spectrometry. Two certified reference materials, Apple Leaves and Mussel Tissue, were used for the evaluation of the analytical procedure and recovery values around 98% were obtained. The results showed that the analyzed mushrooms have high levels of Cu, Fe, K, Mg, Mn and Zn containing more than 30% the recommended daily intake for these nutrients according to Brazilian legislation. These mushrooms presented a very low ratio Na/K. Regarding the levels of some contaminants, the mushrooms had concentrations of Cd, Pb and As below the recommended maximum limits allowed by Brazilian legislation.

  4. Obtainment the reverse phase spinel [Zn2+0,5Fe3+0,5](Ni2+0,5Fe3+ 1,5)O4 by the method combustion reaction: the form of assessment heating

    Silva, M.C.; Costa, A.C.F.; Coutinho, J.P.; Silva, A.T.C.; Freitas, N.L.

    2011-01-01

    This paper aims to synthesize the inverse spinel phase of by combustion reaction method and to evaluate how [Zn 2+ 0,5Fe 3+ 0,5](Ni 2+ 0,5Fe 3+ 1,5)O 4 the heat source influences the structural and morphological this phase. The forms of heating were muffle oven and ceramic plate with built-in resistance and aniline as reducing agent. Comparisons were made between temperature, reaction time and physical changes undergone by the material during the combustion carried out in two warm-up. The material was characterized by XRD, SEM, and textural analysis. Based on the results showed that the spinel phase was successfully obtained, were found traces of the phases ZnO and Fe2O3. The Most crystallite size and higher reaction temperature were presented by the material produced in the plate. As for surface area and pore volume, the highest values were achieved by the material synthesized in the oven. The agglomerates were presented in the form of skeins made of pre-sintered particles. (author)

  5. Investigation of thermodynamic parameters in the pyrolysis conversion of biomass and manure to biochars using thermogravimetric analysis.

    Xu, Yiliang; Chen, Baoliang

    2013-10-01

    The thermodynamic parameters of the conversion of two companion pair materials, i.e., rice straw vs dairy manure, and rice bran vs chicken manure, to biochars were characterized by thermogravimetric analysis. The overall changes of activation energy (Ea) were well described by the Flynn-Wall method. The Ea values increased steeply from about 120 to 180 kJ/mol at the mass conversion (α) at 0.2-0.4, followed by a relatively steady change at 0.40.65. The higher contents of minerals in manures resulted in the larger Ea. The individual conversion of hemicellulose, cellulose and lignin in the feedstocks was identified and their thermodynamic parameters (ΔH°, ΔG° and ΔS°) were calculated. The yields of biochars calculated from TG curve were compared with the determined yields of biochars using muffle pyrolysis. Along with Fourier transform infrared spectra data, the distinct decompositions of biomasses and manures were evaluated. Copyright © 2013 Elsevier Ltd. All rights reserved.

  6. Fabrication and tribological response of aluminium 6061 hybrid composite reinforced with bamboo char and boron carbide micro-fillers

    Chethan, K. N.; Pai, Anand; Keni, Laxmikant G.; Singhal, Ashish; Sinha, Shubham

    2018-02-01

    Metal matrix composites (MMCs) have a wide scope of industrial applications and triumph over conventional materials due to their light weight, higher specific strength, good wear resistance and lower coefficient of thermal expansion. The present study aims at establishing the feasibility of using Bamboo charcoal particulate and boron carbide as reinforcements in Al-6061 alloy matrix and to investigate their effect on the wear of composites taking into consideration the interfacial adhesion of the reinforcements in the alloy. Al-6061 alloy was chosen as a base metallic alloy matrix. Sun-dried bamboo canes were used for charcoal preparation with the aid of a muffle furnace. The carbon content in the charcoal samples was determined by EDS (energy dispersive spectroscopy). In present study, stir casting technique was used to prepare the samples with 1%, 2%, and 3% weight of bamboo charcoal and boron carbide with Al-6061. The fabricated composites were homogenised at 570°C for 6 hours and cooled at room temperature. Wear studies were carried out on the specimens with different speed and loads. It was found that wear rate and coefficient of friction decreased with increase in the reinforcement content.

  7. Arrhythmogenic right ventricular cardiomyopathy in a dog : case report

    A.J. Möhr

    2000-07-01

    Full Text Available An 8-month-old Labrador retriever bitch was evaluated for sudden-onset, progressive abdominal distension. Physical examination revealed an exaggerated inspiratory effort, severe ascites, bilateral jugular vein distension, and hypokinetic femoral arterial pulses. Thoracic auscultation detected tachycardia with muffled heart sounds, without audible cardiac murmurs. Thoracic radiographs identified severe right ventricular enlargement and pleural effusion. The electrocardiogram was consistent with incomplete right bundle branch block or right ventricular enlargement. Echocardiography demonstrated severe right ventricular and atrial dilation, secondary tricuspid regurgitation, and thinning and hypocontractility of the right ventricular myocardium. Left heart chamber sizes were slightly decreased, with normal left ventricular contractility. Adiagnosis of arrhythmogenic right ventricular cardiomyopathy was reached, based on the characteristic clinical, electrocardiographic, radiographic and echocardiographic findings, and the exclusion of other causes of isolated right ventricular failure. Treatment effected good control of clinical signs, until acutely decompensated congestive right heart failure led to euthanasia after 4 months. Arrhythmogenic right ventricular cardiomyopathy is a well-described clinical entity in humans, and has previously been documented in 3 male dogs. The condition is characterised by progressive fibro-adipose replacement of right ventricular myocardium, while the left ventricle usually remains unaffected. It should be considered a differential diagnosis in any young dog presented with isolated right heart failure, syncope, or unexplained ventricular tachyarrhythmias. This article reports the 1st case of arrhythmogenic right ventricular cardiomyopathy in a female dog, and highlights its echocardiographic features.

  8. Combustion behavior of briquettes from oil palm's empty fruit bunch

    Pratoto, A. [Andalas Univ., Padang (Indonesia). Dept. of Mechanical Engineering

    2006-07-01

    Empty fruit bunch (EFB) briquettes from palm plantations are now being considered as a renewable energy source in Indonesia. This paper provided details of a study that investigated the combustion behaviour of an EFB briquette. Thermogravimetry was used to study the briquettes under dynamic conditions at 50 degrees C in a muffle furnace. Thermal decomposition rates and phases were identified, and the effect of the briquette's size on the decomposition rate was evaluated by comparing the combustion behaviour of the briquette to that of loose EFB materials. Rates of devolatilization and char oxidation were also examined. Results of the derivative thermogravimetry (DTG) analysis showed that larger briquettes did not exhibit a sharp peak on the DTG curve. Results suggested that heat transfer was predominant over the kinetic reaction during combustion. The ignition temperature of the briquettes was comparable to typical lignocellulose biomass. Peak combustion temperatures for loose EFB were only slightly lower than other types of biomass. Maximum combustion rates decreased with the size of the fuel. It was concluded that small briquettes are suitable for applications where high rates of heat are required. 16 refs., 1 tab., 6 figs.

  9. About of the Electrostatic fields excitation theory by a RF wave in a plasma; Acerca de la teoria de excitacion de campos electrostaticos por una onda de rf en un plasma

    Gutierrez T, C.R

    1991-01-15

    In an unidimensional model is shown in the cases of a semi limited plasma and a layer of plasma the excitement mechanism of electrostatic fields for a radiofrequency wave (RF) polarized lineally. This phenomenon depends strongly on the combined action of the Miller force and that of impulsion. It is shown that the action of these forces is carried out in different characteristic times when the front of wave crosses through the plasma. The cases of a semi limited plasma and of a layer of plasma without and with current are analyzed. It is shown that near the frontiers of the plasma where the field is sufficiently big arise oscillations of the width of the field that are slowly muffled in the space in an exponential way. In the cases of a plasma layer its are shown that the processes that arise near the frontier x = L are similar to the processes that arise near the frontier x = 0. The existence of current in the plasma layer leads to the blockade of the excited perturbations in the frontier x = L. (Author)

  10. Utilization of open pit burned household waste ash--a feasibility study in Dhaka.

    Haque, Md Obaidul; Sharif, Ahmed

    2014-05-01

    Informal incineration or open pit burning of waste materials is a common practice in the peripheral area of Dhaka, one of the fastest growing mega-cities in the world. This study deals with the effect of open pit burned (i.e. open burned) household waste bottom ash on fired clay bricks. Between 0 to 50% (by weight) of open pit burned household waste bottom ash was mixed with clay to make bricks. The molded specimens were air-dried at room temperature for 24 h and then oven dried at 100 °C for another 24 h to remove the water. The raw bricks were fired in a muffle furnace to a designated temperature (800, 900 and 1000 °C, respectively). The firing behaviour (mechanical strength, water absorption and shrinkage) was determined. The microstructures, phase compositions and leachates were evaluated for bricks manufactured at different firing temperatures. These results demonstrate that open pit burned ash can be recycled in clay bricks. This study also presents physical observations of the incinerated ash particles and determination of the chemical compositions of the raw materials by wet analysis. Open pit burned ash can be introduced easily into bricks up to 20% wt. The concentrations of hazardous components in the leachates were below the standard threshold for inert waste category landfill and their environmental risk during their use-life step can be considered negligible.

  11. Advances in the graphitization protocol at the Radiocarbon Laboratory of the Universidade Federal Fluminense (LAC-UFF) in Brazil

    Macario, Kita D., E-mail: kitamacario@gmail.com [Departamento de Física, Instituto deFísica, Universidade Federal Fluminense, Campus da Praia Vermelha, Av. Gal. Milton Tavares de Souza s/n°, Niterói, RJ, 24210-346 (Brazil); Oliveira, Fabiana M. [Departamento de Física, Instituto deFísica, Universidade Federal Fluminense, Campus da Praia Vermelha, Av. Gal. Milton Tavares de Souza s/n°, Niterói, RJ, 24210-346 (Brazil); Carvalho, Carla [Departamento de Geoquímica, Instituto de Química, Universidade Federal Fluminense, Campus do Valonguinho, Outeiro São João Batista, s/n°, Niterói, RJ, 24020-150 (Brazil); Santos, Guaciara M.; Xu, Xiaomei [Department of Earth System Science, B321 Croul Hall, University of California Irvine, Irvine, CA, 92697-3100 (United States); Chanca, Ingrid S.; Alves, Eduardo Q.; Jou, Renata M.; Oliveira, Maria Isabela; Pereira, Bruna B.; Moreira, Vinicius; Muniz, Marcelo C.; Linares, Roberto; Gomes, Paulo Roberto Silveira; Meigikos dos Anjos, Roberto [Departamento de Física, Instituto deFísica, Universidade Federal Fluminense, Campus da Praia Vermelha, Av. Gal. Milton Tavares de Souza s/n°, Niterói, RJ, 24210-346 (Brazil); and others

    2015-10-15

    In this paper, we summarize the sample preparation methods currently used at the Radiocarbon Laboratory of the Universidade Federal Fluminense (LAC-UFF) in Brazil. We also report on a series of results with regards to the graphitization protocol. Tests with different temperatures and baking times were performed, and carbon stable isotope ratios of graphite were measured by an EA–IRMS (elemental analyzer coupled with an isotopic ratio mass spectrometer) to infer the completeness of the graphitization reaction. We monitored the muffle furnace temperature using an independent thermocouple and found a −60 °C offset, which may have caused the lower graphitization yields (detected from the large isotopic fractionation on several reference materials targets). At a temperature of 520 °C, the isotopic fractionation in the graphitization reaction was systematically lower (−5‰ in average) and the overall scattering was reduced. As long as isotopic fractionation corrections are made using the online stable isotopes ratios provided by the AMS system, the accuracy of the {sup 14}C results should be maintained.

  12. Experimental charcoalification of plant reproductive organs: Taphonomic implications for taxonomic information loss

    Lupia, R. (Univ. of Chicago, IL (United States))

    1992-01-01

    Charcoalification can preserve reproductive organs of plants in exceptional detail, but it has not been clear to what extent these taxonomically important structures suffer non-allometric size reduction during this process. To address this problem, seven angiosperm and two gymnosperm species were buried in sand and experimentally charcoalified in a muffle furnace at 325--350 degrees Celsius for two hours, and percent size reduction measured. Carpels, stamens, and petals never shrank by the same amount for a given angiosperm species. To determine the effect of different periods of heating on organs, one angiosperm species was treated for 0.5, 1, 2, 4, and 6 hours. Organs continued to shrink over this entire period without reaching a plateau. This is important in designing future experiments, and in terms of interpreting fossils, since heat treatment varies across a single site in natural fires. Observations made during this study suggest that some carpels and petals never become charcoalified, that stamens are particularly susceptible to fragmentation after charcoalification, that some organs show predictable damage which is correlated with time, and that the saturation of a structure with water can significantly retard charcoalification for heat exposure of less than one hour. These factors may severely affect the entry of the charred remains into the fossil record. Despite the suggestion that female structures can be expected to shrink the least, it is impossible to prescribe quantitative correction factors to permit accurate reconstructions without constraining additional variables such as temperature and duration of heating.

  13. Synthesis, characterization and structural refinement of polycrystalline uranium substituted zirconolite

    Shrivastava, O.P.; Narendra Kumar; Sharma, I.B.

    2005-01-01

    Ceramic precursors of Zirconolite (CaZrTi 2 O 7 ) family have a remarkable property of substitution Zr 4+ cationic sites. This makes them potential material for nuclear waste management in 'synroc' technology. In order to simulate the mechanism of partial substitution of zirconium by tetravalent actinides, a solid phase of composition CaZr 0.95 U 0.5 Ti 2 O 7 has been synthesized through ceramic route by taking calculated quantities of oxides of Ca, Ti and nitrates of uranium and zirconium respectively. Solid state synthesis has been carried out by repeated pelletizing and sintering the finely powdered oxide mixture in a muffle furnace at 1050 degC. The polycrystalline solid phase has been characterized by its typical powder diffraction pattern. Step analysis data has been used for ab initio calculation of structural parameters. The uranium substituted zirconolite crystallizes in monoclinic symmetry with space group C2/c (15). The following unit cell parameters have been calculated: a =12.4883(15), b =7.2448(5), c 11.3973(10) and β = 100.615(9)0. The structure was refined to satisfactory completion. The Rp and Rwp are found to be 7.48% and 9.74% respectively. (author)

  14. Project Management Plan for Material Stabilization

    SPEER, D.R.

    1999-01-01

    This plan presents the overall objectives, description, justification and planning for the plutonium Finishing Plant (PFP) Materials Stabilization project. The intent of this plan is to describe how this project will be managed and integrated with other facility stabilization and deactivation activities. This plan supplements the overall integrated plan presented in the Plutonium Finishing Plant Integrated Project Management Plan (IPMP), HNF-3617/Rev. 0. This is the top-level definitive project management document that specifies the technical (work scope), schedule, and cost baselines to manager the execution of this project. It describes the organizational approach and roles/responsibilities to be implemented to execute the project. This plan is under configuration management and any deviations must be authorized by appropriate change control action. Materials stabilization is designated the responsibility to open and stabilize containers of plutonium metal, oxides, alloys, compounds, and sources. Each of these items is at least 30 weight percent plutonium/uranium. The output of this project will be containers of materials in a safe and stable form suitable for storage pending final packaging and/or transportation offsite. The corrosion products along with oxides and compounds will be stabilized via muffle furnaces to reduce the materials to high fired oxides

  15. Equiatomic indides REIrIn (RE=La, Pr, Nd, Er-Yb). Crystal and electronic structure

    Zaremba, Nazar [Ivan Franko National Univ. of Lviv (Ukraine). Dept. of Inorganic Chemistry; Technische Univ. Muenchen, Garching (Germany). Fakultaet fuer Chemie; Muts, Ihor; Zaremba, Vasyl [Ivan Franko National Univ. of Lviv (Ukraine). Dept. of Inorganic Chemistry; Hlukhyy, Viktor [Technische Univ. Muenchen, Garching (Germany). Fakultaet fuer Chemie; Stein, Sebastian; Rodewald, Ute C.; Poettgen, Rainer [Muenster Univ. (Germany). Inst. fuer Anorganische und Analytische Chemie; Pavlyuk, Volodymyr [Ivan Franko National Univ. of Lviv (Ukraine). Dept. of Inorganic Chemistry; Czestochowa Jan Dlugosz Univ., Czestochowa (Poland). Inst. of Chemistry, Environmental Protection and Biotechnology

    2017-10-01

    The equiatomic rare earth iridium indides REIrIn (RE=La, Pr, Nd, Er-Yb) were synthesized by reaction of the elements in induction or muffle furnaces and were characterized through X-ray powder patterns. The structures of LaIr{sub 0.86}In{sub 1.14}, PrIr{sub 0.89}In{sub 1.11}, NdIr{sub 0.94}In{sub 1.06}, ErIrIn (all ZrNiAl type, P anti 62m), and YbIrIn (TiNiSi type, Pnma) were refined from single crystal X-ray diffractometer data. Refinements of the occupancy parameters revealed small degrees of solid solutions with indium substitution on the iridium sites. Chemical bonding analyses and electronic structure calculations indicate the dominance of metallic bonding in addition to partial ionic interactions between the cations and polyanions, as well as covalent contributions between the indium and iridium atoms.

  16. Preparation of octahedral CuO micro/nanocrystals and electrochemical performance as anode for lithium-ion battery

    Feng, Lili; Xuan, Zhewen; Bai, Yang; Zhao, Hongbo; Li, Li; Chen, Yashun; Yang, Xianqin; Su, Changwei; Guo, Junming; Chen, Xiaokai

    2014-01-01

    Highlights: • Octahedral cupric oxides with hollow structure were prepared. • No hard template was used in the preparation of hollow cupric oxides. • The cupric oxides show good reversible capacity. - Abstract: Herein we report that three octahedral CuO samples with hollow or solid structure are successfully prepared by firstly preparation of Cu 2 O products using a chemical reduction method, then by calcination in a muffle furnace at 300 °C for 3 h in air atmosphere. The obtained CuO samples serve as a good model system for the study as anodes for lithium ion batteries. All the three CuO samples have high discharge specific capacity and good cycling stability from the 2nd cycling to the 50th cycling. Octahedral CuO hollow crystals with 400 nm in size have the highest reversible capacity and the smallest resistance. So their electrochemical performances are partly related to their morphologies. The results suggest that the as-prepared CuO samples, especially the 400 nm hollow octahedral CuO crystals could be a promising material for the anode of lithium-ion battery

  17. Preliminary study on immobilization of buffing dust by solidification method in ceramic brick

    Yuliansyah, Ahmad Tawfiequrrahman; Prasetya, Agus; Putra, Arif Eka; Satriawan, Humam Budi

    2017-11-01

    Leather-based industries generate a substantial amount of hazardous solid and liquid wastes in their process. One of the solid wastes is buffing dust, which is fine particulates containing fat, tanning, dyes and chromium. From 1 ton of leather processed, approximately 2-6 kg of buffing dust is generated. Chromium in the buffing dust is carcinogenic, so a proper handling is highly required. Solidification is a method commonly used to immobilize toxic material. Hence, the material is trapped in a matrix made of binding agents to minimize its mobility. However, a very small amount of the materials is sometimes released to the environment during storage. This study investigates leaching process of chromium from immobilized buffing dust in ceramic brick. Buffing dust, which contains chromium, is solidified by mixing it with clay at certain compositions and fired in a muffle furnace to produce a ceramic brick. Performance of the solidification process is evaluated by measuring the leaching of chromium in the leaching test. The results show that the solidification has significantly reduced the potential release of chromium to the environment. Higher of the firing temperature, less chromium is leached from ceramic brick. The chromium concentration of leachate water from 800°C brick is 0.376 ppm, while those from 850 and 900°C brick are 0.212 and 0.179 ppm respectively.

  18. Activated carbon from biomass

    Manocha, S.; Manocha, L. M.; Joshi, Parth; Patel, Bhavesh; Dangi, Gaurav; Verma, Narendra

    2013-06-01

    Activated carbon are unique and versatile adsorbents having extended surface area, micro porous structure, universal adsorption effect, high adsorption capacity and high degree of surface reactivity. Activated carbons are synthesized from variety of materials. Most commonly used on a commercial scale are cellulosic based precursors such as peat, coal, lignite wood and coconut shell. Variation occurs in precursors in terms of structure and carbon content. Coir having very low bulk density and porous structure is found to be one of the valuable raw materials for the production of highly porous activated carbon and other important factor is its high carbon content. Exploration of good low cost and non conventional adsorbent may contribute to the sustainability of the environment and offer promising benefits for the commercial purpose in future. Carbonization of biomass was carried out in a horizontal muffle furnace. Both carbonization and activation were performed in inert nitrogen atmosphere in one step to enhance the surface area and to develop interconnecting porosity. The types of biomass as well as the activation conditions determine the properties and the yield of activated carbon. Activated carbon produced from biomass is cost effective as it is easily available as a waste biomass. Activated carbon produced by combination of chemical and physical activation has higher surface area of 2442 m2/gm compared to that produced by physical activation (1365 m2/gm).

  19. Impact of heat treatment on HSS cutting tool (ASTM A600) and its behaviour during machining of mild steel (ASTM A36)

    Afolalu, S. A.; Abioye, O. P.; Salawu, E. Y.; Okokpujie, I. P.; Abioye, A. A.; Omotosho, O. A.; Ajayi., O. O.

    2018-04-01

    Carburization is one the best heat treatment that responded well to hardening with Palm Kernel Shell giving the best hardness value. This work studied the influence of carburization on HSStool(ASTM A600) and its behaviour during machining of mild steel (ASTM A36). Composition of the samples (12 pieces of 180 × 12 × 12 mm) HSS tools were checked using UV-VIS spectrometer and the tools were carburized with PKS at holding temperatures and time of 800, 850, 900, 950 °C and 60,90 120 minutes using muffle furnance. The micro structural analysis, surface and core hardnessof the treated samples gave better results than the untreated samples when checked withsoft driven and optical microscope. It wasalso observed that increase in the feed rate and depth for length of cut of 50 mm significantly reduces the wear progression and thereby gave best machining time at maximum carburizing temperature and time(950 °C / 120 minutes) when it was used to cut mild steelon the lathe machine.

  20. Morphology-controlled synthesis and electrochemical performance of NiCo{sub 2}O{sub 4} as anode material in lithium-ion battery application

    Xu, Shan; Lu, Lin; Zhang, Qing; Zheng, Hao; Liu, Lian; Yin, Shengyu; Wang, Shiquan, E-mail: wsqhao@126.com; Li, Guohua; Feng, Chuanqi [Hubei University, Hubei Collaborative Innovation Center for Advanced Organic Chemical Materials, Ministry-of-Education Key Laboratory for Synthesis and Applications of Organic Functional Molecules (China)

    2015-09-15

    Mixed-valence oxide precursors were synthesized by a solvothermal method using NiSO{sub 4}, CoSO{sub 4}, and NH{sub 4}HCO{sub 3} as raw materials. The precursors were heat-treated in a muffle furnace at 500 °C to obtain the products (NiCo{sub 2}O{sub 4}). The samples were characterized by X-ray diffractometer, thermogravimetric, energy-dispersive spectroscopy, scanning electron microscopy, and transmission electron microscopy. The results show that dumbbells, microspheres, and particle-like NiCo{sub 2}O{sub 4} were successfully synthesized by changing the volume of solvent and solvothermal temperature. The NiCo{sub 2}O{sub 4} microspheres (prepared at 180 °C with 30 ml solvent) as anode material for lithium-ion battery, exhibit a reversible discharge capacity of 1160 mAh g{sup −1} and good cycling stability (729 mAh g{sup −1} after 50 cycles) at a constant current of 100 mA g{sup −1} in the voltage range of 0.01–3.0 V due to its high crystallinity and uniform porous morphology. Hence, the synthetic method could be extended to other high-capacity ternary metal oxide materials for lithium-ion battery application.

  1. Effects of four step sintering on Y2O3: SiO2 nanocomposite

    Ahlawat, Rachna

    2015-01-01

    Need for high performance materials for advanced applications have led to the development of new concepts in materials design processing and their fabrication. The development of nanocrystalline materials with improved and novel properties is an important turning point in materials research. In present work, we report synthesis and structural characterization of Y 2 O 3 : SiO 2 nanocomposite. Sol-gel technique is being used to prepare-Y 2 O 3 SiO 2 nanocomposite due to its effectiveness in preparing samples with good mixing of starting materials and at relatively low reaction temperature. We have used Y(NO 3 ) 3 .4H 2 O and TEOS as precursors and followed usual approach of sol-gel technique, the final product of Y 2 O 3 : SiO 2 nanocomposite is obtained in the form of powder. The powder samples were sintered at different temperature for different time durations in programmable muffle furnace. The samples were characterized by complementary techniques as X-Ray Diffraction (XRD), Fourier Transforms Infrared Spectroscopy (FTIR) and Transmission Electron Microscopy (TEM). (author)

  2. Produção de carvão ativado a partir de casca de arroz

    Amanda da Silva Reis

    2016-12-01

    Full Text Available The rice husk, one of the most abundant agricultural wastes in our country, is a fibrous material with a high silica content (SiO2. The use of rice husk as raw material for activated carbon production is a new project and its use is due to the adequacy of its basic characteristics (non-grafitizável, high fixed carbon content for this purpose. This study aimed to make charcoal activated from the rice husk. After rice husk being properly treated was charred to 600th C for 40 minutes in a muffle furnace. The activating agent used in the chemical activation of the material was Phosphoric Acid (H3PO4 concentrate (85%. The tests were: pH of zero charge, chromatographic methods (pesticides adsorption, AC test as adsorbent pesticides, FTIR analysis, scanning electron microscopy SEM. For determining the pHpcz, the point of intersection of the curve is at 6.4, that is, shows that the activated carbon from rice husk is slightly acidic. The chromatographic method (adsorption using HPLC showed that the activated carbon rice hull was more efficient removal of methyl parathion pesticidal solution (83.78%, which in the removal of 2,4 pesticide D (21.61% .

  3. The Micromorphological Research of the Internal Structure of Chairside CAD/CAM Materials by the Method of Scanning Impulse Acoustic Microscopy (SIAM)

    Goryainova, Kristina E.; Morokov, Egor S.; Retinskaja, Marina V.; Rusanov, Fedor S.; Apresyan, Samvel V.; Lebedenko, Igor Yu.

    2018-01-01

    Aim: The aim of the present work was to compare the elastic properties and internal structure of 4 different CAD/CAM chairside materials, by the method of Scanning Impulse Acoustic Microscopy (SIAM). Methods: Four chairside CAD/CAM materials with different structures from hybrid ceramic (VITA Enamic, VITA Zahnfabrik), feldspatic ceramic (VITABlocs Mark II, VITA Zahnfabrik), leucite glass-ceramic (IPS Empress CAD, Ivoclar Vivadent) and PMMA (Telio CAD, Ivoclar Vivadent) were examined by Scanning Impulse Acoustic Microscope (SIAM). Results: The results of micromorphological research of CAD/CAM chairside materials using SIAM method showed differences between the internal structures of these materials. The internal structure of feldspatic and glass-ceramic samples revealed the presence of pores with different sizes, from 10 to 100 microns; the structure of polymer materials rendered some isolated defects, while in the structure of hybrid material, defects were not found. Conclusion: Based on the results obtained from the present study, in cases of chairside production of dental crowns, it would be advisable to give preference to the blocks of hybrid ceramics. Such ceramics devoid of quite large porosity, glazing for CAD/CAM crowns made from leucite glass-ceramic and feldspatic ceramic may be an option. For these purposes, commercially available special muffle furnace for clinical and laboratory individualization and glazing of ceramic prostheses were provided. Further studies are needed to confirm the evidence emerging from the present research. PMID:29492178

  4. Effect of Microstructure on the Wear Behavior of Heat Treated SS-304 Stainless Steel

    S. Kumar

    2016-12-01

    Full Text Available Sliding wear characteristics of some heat treated SS-304 stainless steel against EN-8 steel in dry condition have been studied in the present experimental work. Samples of SS-304 stainless steel have been heated in a muffle furnace in desired temperature and allowed to dwell for two hours. The heated specimen are then cooled in different media namely inside the furnace, open air, cutting grade oil (grade 44 and water at room temperature to obtain different grades of heat treatment. Microstructures and corresponding micro hardness of the samples have been measured along with Feritscopic studies. Wear characteristics have been studied in a multi tribo-tester (Ducom in dry sliding condition against EN-8 steel roller. Speed, load on job and duration of test run have been considered as the experimental parameters. The wear of the samples have been obtained directly from ‘Winducom 2006’ software. Mass loss of the samples before and after operation has also been considered as the measure of wear in the present study. All the samples have been slid against EN-8 steel roller with fixed experimental parameters. The data have been plotted, compared and analyzed. Effect of microstructures as well as micro hardness on the wear behavior has been studied and concluded accordingly.

  5. Microstructures and mechanical properties of 3D 4-directional, C{sub f}/ZrC–SiC composites using ZrC precursor and polycarbosilane

    Li, Qinggang, E-mail: liqinggang66@gmail.com [School of Material Science and Engineering, University of Jinan, Jinan 250022 (China); Shandong Provincial Key Laboratory of Preparation and Measurement of Building Materials, Jinan 250022 (China); Dong, Shaoming [Structural Ceramics and Composites Engineering Research Center, Shanghai Institute of Ceramics, Chinese Academy of Sciences, Shanghai 200050 (China); Wang, Zhi; Shi, Guopu; Ma, Yan [School of Material Science and Engineering, University of Jinan, Jinan 250022 (China); Zhou, Haijun; Wang, Zhen; He, Ping [Structural Ceramics and Composites Engineering Research Center, Shanghai Institute of Ceramics, Chinese Academy of Sciences, Shanghai 200050 (China)

    2013-11-01

    Highlights: • Three-dimensional 4-directional C{sub f}/ZrC–SiC composites fabricated by polymer infiltration and pyrolysis. • The microstructure and mechanical properties of the composites were studied. • High-temperature oxidation resistance and anti-ablation properties were evaluated. • Results show the composites have good mechanical and excellent ablative properties. -- Abstract: Three-dimensional 4-directional C{sub f}/ZrC–SiC composites were successfully fabricated by polymer infiltration and pyrolysis combined with ZrC precursor impregnation. The microstructure and mechanical properties of the composites were studied. The composite with PyC/SiC interphase had a bulk density of 2.14 g/cm{sup 3}, an open porosity of 10%, and a bending stress of 474 MPa, and exhibited a non-brittle failure behavior due to propagation and deflection of cracks, and fracture and pullout of fibers. Their high-temperature oxidation resistance and anti-ablation properties were evaluated using a muffle furnace and plasma wind tunnel test. Results show that the composites have good mechanical and excellent ablative properties.

  6. 14C Accelerator mass spectrometry in Brazil

    Macario, K.D.; Gomes, P.R.S.; Anjos, Roberto M.; Linares, R.; Queiroz, E.A.; Oliveira, F.M.; Cardozo, L.; Carvalho, C.R.A.

    2011-01-01

    Radiocarbon Accelerator Mass Spectrometry is an ultra-sensitive technique that enables the direct measurement of carbon isotopes in samples as small as a few milligrams. The possibility of dating or tracing rare or even compound specific carbon samples has application in many fields of science such as Archaeology, Geosciences and Biomedicine. Several kinds of material such as wood, charcoal, carbonate and bone can be chemically treated and converted to graphite to be measured in the accelerator system. The Physics Institute of Universidade Federal Fluminense (UFF), in Brazil will soon be able to perform the complete 14 C-AMS measurement of samples. At the Nuclear Chronology Laboratory (LACRON) samples are prepared and converted to carbon dioxide. A stainless steel vacuum system was constructed for carbon dioxide purification and graphitization is performed in sealed tubes in a muffle oven. Graphite samples will be analyzed in a 250 kV Single Stage Accelerator produced by National Electrostatic Corporation which will be installed in the beginning of 2012. With the sample preparation laboratory at LACRON and the SSAMS system, the Physics Institute of UFF will be the first 14 C-AMS facility in Latin America. (author)

  7. Studies on the performance of TiO{sub 2} thin films as protective layer to chlorophyll in Ocimum tenuiflorum L from UV radiation

    Malliga, P. [Department of Physics, V.V.Vanniaperumal College for Women, Virudhunagar – 626001 (India); Selvi, B. Karunai [Department of Botany, V.V.Vanniaperumal College for Women, Virudhunagar – 626001 (India); Pandiarajan, J.; Prithivikumaran, N. [Nanoscience Lab, Department of Physics, VHNSN College, Virudhunagar – 626001 (India); Neyvasagam, K., E-mail: srineyvas@yahoo.co.in [Department of Physics, The Madura College, Madurai - 625011 (India)

    2015-06-24

    Thin films of TiO{sub 2} were prepared on glass substrates using sol-gel dip coating technique. The films with 10 coatings were prepared and annealed at temperatures 350°C, 450°C and 550°C for 1 hour in muffle furnace. The annealed films were characterized by X – Ray diffraction (XRD), UV – Visible, AFM, Field Effect Scanning Electron Microscopy (FESEM) and EDAX studies. Chlorophyll has many health benefits due to its structural similarity to human blood and its good chelating ability. It has antimutagenic and anticarcinogenic properties. UV light impairs photosynthesis and reduces size, productivity, and quality in many of the crop plant species. Increased exposure of UV light reduces chlorophyll contents a, b and total content in plants. Titanium Dioxide (TiO{sub 2}) is a wide band gap semiconductor and efficient light harvester. TiO{sub 2} has strong UltraViolet (UV) light absorbing capability. Here, we have studied the performance of TiO{sub 2} thin films as a protective layer to the chlorophyll contents present in medicinal plant, tulsi (Ocimum tenuiflorum L) from UV radiation. The study reveals that crystallite size increases, transmittance decreases and chlorophyll contents increases with increase in annealing temperature. This study showed that TiO{sub 2} thin films are good absorber of UV light and protect the chlorophyll contents a, b and total content in medicinal plants.

  8. Photodegradation of Methylene Blue by TiO2-Fe3O4-Bentonite Magnetic Nanocomposite

    Wei Chen

    2015-01-01

    Full Text Available Fe3O4-bentonite nanoparticles have been prepared by a coprecipitation technique under a nitrogen atmosphere. An aqueous suspension of bentonite was first modified with FeCl2 and FeCl3. TiO2 was then loaded onto the surface of the Fe3O4-bentonite by a sol-gel method. After sufficient drying, the colloidal solution was placed in a muffle furnace at 773 K to obtain the TiO2-Fe3O4-bentonite composite. The material has been characterized by scanning electron microscopy (SEM, X-ray diffraction (XRD analysis, and vibrating sample magnetometry (VSM. Morphological observation showed that Fe3O4 and TiO2 nanoparticles had been adsorbed on the surface of bentonite nanoneedles. The material was then applied for the photodegradation of the azo dye methylene blue (MB. It was found that the removal efficiency of MB exceeded 90% under UV illumination, and that only a 20% mass loss was incurred after six cycles. The composite material thus showed good photocatalytic performance and recycling properties.

  9. Synthesis of carbon nanosheet from barley and its use as non-enzymatic glucose biosensor

    Soma Das

    2014-12-01

    Full Text Available In this work, carbon nanosheet (CNS based electrode was designed for electrochemical biosensing of glucose. CNS has been obtained by the pyrolysis of barley at 600–750 °C in a muffle furnace; it was then purified and functionalized. The CNS has been characterized by scanning electron microscopy (SEM, X-ray diffraction (XRD and Raman spectroscopic techniques. The electrochemical activity of CNS-based electrode was investigated by linear sweep voltammetry (LSV and square wave voltammetry (SWV, for the oxidation of glucose in 0.001 M H2SO4 (pH 6.0. The linear range of the sensor was found to be 10−4–10−6 M (1–100 µM within the response time of 4 s. Interestingly, its sensitivity reached as high as ~26.002±0.01 μA/μM cm2. Electrochemical experiments revealed that the proposed electrode offered an excellent electrochemical activity towards the oxidation of glucose and could be applied for the construction of non-enzymatic glucose biosensors. Keywords: Carbon nanosheet, β-d glucose, Linear sweep voltammetry, Square wave voltammetry, Pharmaceutical analysis

  10. Investigation of U3O8 immobilization in the GP-91 borosilicate glass by induction melter with a cold crucible (CCIM)

    Matyunin, Y.I.; Demin, A.V.; Smelova, T.V.; Yudintsev, S.V.; Lapina, M.I.

    1997-01-01

    One of the most promising and intensively developed methods for the solidification of high-level wastes is their vitrification with the use of a cold crucible induction melter (CCIM), which offers a number of advantages over ceramic melter. This work is concerned with comparison studies on the behavior of uranium in vitreous borosilicate materials synthesized by the traditional technique (melting in muffle furnaces) and CCIM method. The incorporation of uranium oxide U 3 O 8 into the GP-91 borosilicate glass with the use of CCIM technology is investigated. The limiting solubility of uranium in the GP-91 borosilicate glass is evaluated. The phase composition of precipitated dispersed particles based on uranium is determined. Some physicochemical properties of synthesized materials are explored. Investigations into the behavior of uranium in borosilicate glass prepared in the CCIM show a feasibility to synthesize the X-ray amorphous homogeneous borosilicate glasses incorporating as much as 25 - 28 wt% uranium, which is 4 - 5 times larger than that in glasses obtained by the traditional method. (author)

  11. Study of effect of temperature on burning of textile sludge for use as alternative material on civil building; Estudo do efeito da temperatura na queima de lodo textil para uso como material alternativo na construcao civil

    Guedes, B.F.R.; Morais, C.R.S.; Altidis, M.E.D.; Lira, B.S.; Morais, S.R.A., E-mail: crislene@dema.ufcg.edu.br [Universidade Federal de Campina Grande (UFCG), PB (Brazil)

    2011-07-01

    The waste generated by textile industries has been the target of numerous challenges due to their release to the environment without proper treatment. These problems have led many researchers to seek solutions that enable the use of waste as building materials. This study aimed to heat-treat the textile sludge, and evaluate their chemical, mineralogical and structural properties. The textile sludge was calcined in a muffle furnace, a heating rate of 10°C/min and 2 hours stabilization by the following temperatures 400°C, 450°C, 500°C, 550°C and 600°C. It was observed a reduction between 88 and 90% weight, indicating the presence of a large amount of formation water and organic matter. The sludge after calcinations was characterized by techniques such as X-ray diffraction, infrared and chemical analysis. The x-ray spectra showed predominant peaks of silica, which were confirmed by chemical analysis (86% silica). (author)

  12. Nutritional value of breast and thigh muscle of chukar partridge (Alectoris chukar under intensive fattening conditions

    Radovan Jůzl

    2012-01-01

    Full Text Available The aim of our study was to evaluate the nutritional value of the breast and thigh muscle of chukar partridge (Alectoris chukar under intensive fattening conditions. Commercial feeding mixtures for broilers were used. Live weight of 60 partridges (birds were not sexed was controlled during 90 days of fattening. After the fattening was finished, 30 birds were selected to monitor the carcass yield. Breast and thigh muscle were used for chemical analysis of crude protein (Kjeldahl method, total lipids (fat analyser ANKOMXT10, ash (Muffle furnace - 550° C and gross energy (calorimetry. Average values ​​of live weight were increasing in the course of fattening; at the end of fattening the live weight reached 0.452 kg. The carcass yield, breast muscle yield and thigh yield were evaluated (73.72%, 18.09%, 20.80%, respectively. Chemical analysis showed a highly significant difference (P ≤ 0.01 between the breast and thigh muscle for crude protein, fat, ash and gross energy. The ash content demonstrated a significant difference (P ≤ 0.05 between the breast and thigh muscle. This study brings new data on the nutritional value of the meat of chukar partridge that can be used for reccomendation of a suitable feeding mixture.

  13. The equiatomic intermetallics REPtCd (RE = La, Ce, Pr, Nd, Eu) and magnetic properties of CeAuCd

    Johnscher, Michael; Niehaus, Oliver; Poettgen, Rainer [Muenster Univ. (Germany). Inst. fuer Anorganische und Analytische Chemie; Tappe, Frank [Hochschule Hamm-Lippstadt, Hamm (Germany)

    2015-06-01

    The cadmium intermetallics REPtCd (RE = La, Ce, Pr, Nd, Eu) and CeAuCd were synthesized by induction-melting of the elements in sealed niobium ampoules followed by annealing in muffle furnaces. The samples were characterized by powder X-ray diffraction. The structures of CePtCd (ZrNiAl type, P anti 62m, a = 763.8(6), c = 409.1(4) pm, wR2 = 0.0195, 298 F{sup 2} values, 14 variables) and EuPtCd (TiNiSi type, Pnma, a = 741.3(2), b = 436.4(1), c = 858.0(4) pm, wR2 = 0.0385, 440 F{sup 2} values, 20 variables) were refined from single-crystal data. The REPtCd structures exhibit three-dimensional networks of corner- and edge-sharing Cd rate at Pt{sub 2/6}Pt{sub 2/3} and Cd rate at Pt{sub 4/4} tetrahedra, which leave cages for the rare earth atoms. Temperature-dependent magnetic susceptibility data of CeAuCd reveal a paramagnetic to antiferromagnetic phase transition at T{sub N} = 3.7(5) K.

  14. The equiatomic intermetallics REPtCd (RE = La, Ce, Pr, Nd, Eu) and magnetic properties of CeAuCd

    Johnscher, Michael; Niehaus, Oliver; Poettgen, Rainer

    2015-01-01

    The cadmium intermetallics REPtCd (RE = La, Ce, Pr, Nd, Eu) and CeAuCd were synthesized by induction-melting of the elements in sealed niobium ampoules followed by annealing in muffle furnaces. The samples were characterized by powder X-ray diffraction. The structures of CePtCd (ZrNiAl type, P anti 62m, a = 763.8(6), c = 409.1(4) pm, wR2 = 0.0195, 298 F 2 values, 14 variables) and EuPtCd (TiNiSi type, Pnma, a = 741.3(2), b = 436.4(1), c = 858.0(4) pm, wR2 = 0.0385, 440 F 2 values, 20 variables) were refined from single-crystal data. The REPtCd structures exhibit three-dimensional networks of corner- and edge-sharing Cd rate at Pt 2/6 Pt 2/3 and Cd rate at Pt 4/4 tetrahedra, which leave cages for the rare earth atoms. Temperature-dependent magnetic susceptibility data of CeAuCd reveal a paramagnetic to antiferromagnetic phase transition at T N = 3.7(5) K.

  15. About of the Electrostatic fields excitation theory by a RF wave in a plasma

    Gutierrez T, C.R.

    1991-01-01

    In an unidimensional model is shown in the cases of a semi limited plasma and a layer of plasma the excitement mechanism of electrostatic fields for a radiofrequency wave (RF) polarized lineally. This phenomenon depends strongly on the combined action of the Miller force and that of impulsion. It is shown that the action of these forces is carried out in different characteristic times when the front of wave crosses through the plasma. The cases of a semi limited plasma and of a layer of plasma without and with current are analyzed. It is shown that near the frontiers of the plasma where the field is sufficiently big arise oscillations of the width of the field that are slowly muffled in the space in an exponential way. In the cases of a plasma layer its are shown that the processes that arise near the frontier x = L are similar to the processes that arise near the frontier x = 0. The existence of current in the plasma layer leads to the blockade of the excited perturbations in the frontier x = L. (Author)

  16. Embedded Data Acquisition Tools for Rotorcraft Diagnostic Sensors

    Wagoner, Robert

    2014-01-01

    Rotorcraft drive trains must withstand enormous pressure while operating continuously in extreme temperature and vibration environments. Captive components, such as planetary and spiral bevel gears, see enormous strain but are not accessible to fixed instrumentation, such as a piezoelectric transducer. Thus, it is difficult to directly monitor components that are most susceptible to damage. This innovation is a self-contained data processing unit within a specialized fixture that installs directly inside the rotating pinion gear in the gearbox. From this location, it detects and transmits high-resolution prognostic data to a fixed transceiver. The sensor is based on microelectromechanical systems (MEMS) technology and uses innovative circuit designs to capture high-bandwidth data and transmit it wirelessly from inside an operational helicopter transmission. With Ridgetop's advanced MEMS-based sensor, researchers have, for the first time, been able to extract high-resolution acoustic signatures wirelessly from sensors within the transmission that would otherwise be muffled by background gear noises. Ridgetop's innovative instrument will help researchers perform dynamic analysis of gear interaction and develop improved designs for gear components. In addition, data from this instrument can be used to validate new algorithms that detect and predict faults based on external acoustic signatures, for prognostic purposes. The result of this work will be an improvement in safety, performance, and cost for future generations of rotating components.

  17. Determination of uranium in coated fuel particle compact by potassium fluoride fusion-gravimetric method

    Ito, Mitsuo; Iso, Shuichi; Hoshino, Akira; Suzuki, Shuichi.

    1992-03-01

    Potassium fluoride-gravimetric method has been developed for the determination of uranium in TRISO type-coated fuel particle compact. Graphite matrix in the fuel compact is burned off by heating it in a platinum crucible at 850degC. The coated fuel particles thus obtained are decomposed by fusion with potassium fluoride at 900degC. The melt was dissolved with sulfuric acid. Uranium is precipitated as ammonium diuranate, by passing ammonia gas through the solution. The resulting precipitate is heated in a muffle furnace at 850degC, to convert uranium into triuranium octoxide. Uranium in the triuranium octoxide was determined gravimetrically. Ten grams of caoted fuel particles were completely decomposed by fusion with 50 g of potassium fluoride at 900degC for 3 hrs. Analytical result for uranium in the fuel compact by the proposed method was 21.04 ± 0.05 g (n = 3), and was in good agreement with that obtained by non-destructive γ-ray measurement method : 21.01 ± 0.07 g (n = 3). (author)

  18. Sequential automated fusion/extraction chromatography methodology for the dissolution of uranium in environmental samples for mass spectrometric determination

    Milliard, Alex; Durand-Jezequel, Myriam [Laboratoire de Radioecologie, Departement de chimie, Universite Laval, 1045 Avenue de la Medecine, Quebec, QC, G1V 0A6 (Canada); Lariviere, Dominic, E-mail: dominic.lariviere@chm.ulaval.ca [Laboratoire de Radioecologie, Departement de chimie, Universite Laval, 1045 Avenue de la Medecine, Quebec, QC, G1V 0A6 (Canada)

    2011-01-17

    An improved methodology has been developed, based on dissolution by automated fusion followed by extraction chromatography for the detection and quantification of uranium in environmental matrices by mass spectrometry. A rapid fusion protocol (<8 min) was investigated for the complete dissolution of various samples. It could be preceded, if required, by an effective ashing procedure using the M4 fluxer and a newly designed platinum lid. Complete dissolution of the sample was observed and measured using standard reference materials (SRMs) and experimental data show no evidence of cross-contamination of crucibles when LiBO{sub 2}/LiBr melts were used. The use of a M4 fusion unit also improved repeatability in sample preparation over muffle furnace fusion. Instrumental issues originating from the presence of high salt concentrations in the digestate after lithium metaborate fusion was also mitigated using an extraction chromatography (EXC) protocol aimed at removing lithium and interfering matrix constituants prior to the elution of uranium. The sequential methodology, which can be performed simultaneously on three samples, requires less than 20 min per sample for fusion and separation. It was successfully coupled to inductively coupled plasma mass spectrometry (ICP-MS) achieving detection limits below 100 pg kg{sup -1} for 5-300 mg of sample.

  19. Electrochemical reduction of oxygen on lead-silver alloys in an alkaline medium

    Seliverstov, S.D.; Arkhangel'skaya, Z.P.; Lyzlov, N.Y.

    1986-01-01

    The use of lead-silver alloys as materials for the gas-absorbing electrode in sealed silver-cadmium alkaline storage batteries is desirable primarily from the stanpoint of saving the costly silver. The authors studied reduction of oxygen with the aim of optimizing the composition of the Pb-Ag alloy and of the porous structure of the electrodes. The alloys were made in a muffle furnace in corundum crucibles under a layer of VI-2 flux. Curves are shown which represent the dependence of the ionization current of molecular oxygen on smooth partially immersed electrodes made from alloys differing in composition on the length of the part of the electrode withdrawn from the solution. It is shown that decrease of the corrosion resistance of the alloy in the porous electrode causes partial loss of its mechanical strength. Worsening of the electric contact between the particles of active material is also possible. An alloy of the composition (mass %) 60 Pb-40 Ag is the most suitable from the practical standpoint

  20. Flame Spread and Damaged Properties of RCD Cases by Tracking

    Choi, Chung-Seog; Kim, Hyang-Kon; Shong, Kil-Mok; Kim, Dong-Woo

    In this paper, the flame spread and damaged properties of residual current protective devices (RCDs) by tracking were analyzed. Pictures of tracking process were taken by High Speed Imaging System (HSIS), and fire progression was observed by timeframe. During the tracking process of RCD, it seemed to explode just once in appearance, but in the results of HSIS analysis, a small fire broke out and disappeared repeatedly 35 times and a flash of light repeated 15 times. Finally, an explosion with a flash of light occurred and lots of particles were scattered. Electric muffle furnace was used for heat treatment of RCD cases. The surface characteristics of specimens due to heat treatment and tracking deterioration were taken by Scanning Electron Microscope (SEM). Chemical and thermal properties of these deteriorated specimens were analyzed by Fourier Transform Infrared Spectrometer (FT-IR) and Differential Thermal Analyzer (DTA). The carbonization characteristics showed different chemical properties due to energy sources, and the results could be applicable to judge the accident causes.