WorldWideScience

Sample records for handling and storage

  1. Grain Handling and Storage.

    Science.gov (United States)

    Harris, Troy G.; Minor, John

    This text for a secondary- or postecondary-level course in grain handling and storage contains ten chapters. Chapter titles are (1) Introduction to Grain Handling and Storage, (2) Elevator Safety, (3) Grain Grading and Seed Identification, (4) Moisture Control, (5) Insect and Rodent Control, (6) Grain Inventory Control, (7) Elevator Maintenance,…

  2. DOE handbook: Tritium handling and safe storage

    International Nuclear Information System (INIS)

    1999-03-01

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

  3. DOE handbook: Tritium handling and safe storage

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-03-01

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

  4. Handling of multiassembly sealed baskets between reactor storage and a remote handling facility

    International Nuclear Information System (INIS)

    Massey, J.V.; Kessler, J.H.; McSherry, A.J.

    1989-06-01

    The storage of multiple fuel assemblies in sealed (welded) dry storage baskets is gaining increasing use to augment at-reactor fuel storage capacity. Since this increasing use will place a significant number of such baskets on reactor sites, some initial downstream planning for their future handling scenarios for retrieving multi-assembly sealed baskets (MSBs) from onsite storage and transferring and shipping the fuel (and/or the baskets) to a federally operated remote handling facility (RHF). Numerous options or at-reactor and away-from-reactor handling were investigated. Materials handling flowsheets were developed along with conceptual designs for the equipment and tools required to handle and open the MSBs. The handling options were evaluated and compared to a reference case, fuel handling sequence (i.e., fuel assemblies are taken from the fuel pool, shipped to a receiving and handling facility and placed into interim storage). The main parameters analyzed are throughout, radiation dose burden and cost. In addition to evaluating the handling of MSBs, this work also evaluated handling consolidated fuel canisters (CFCs). In summary, the handling of MSBs and CFCs in the store, ship and bury fuel cycle was found to be feasible and, under some conditions, to offer significant benefits in terms of throughput, cost and safety. 14 refs., 20 figs., 24 tabs

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

    International Nuclear Information System (INIS)

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

    1978-04-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1978-04-01

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

  7. Factors affecting vaccine handling and storage practices among ...

    African Journals Online (AJOL)

    Objective: Assessing the factors associated with vaccine handling and storage practices. Methods: This was a .... Others include insufficient/unavailable backup refrigerators (52%) .... Human Vaccines 2010; 6(3): 270-278. 5. Joao Carlos de ...

  8. Fuel handling and storage systems in nuclear power plants

    International Nuclear Information System (INIS)

    1984-01-01

    The scope of this Guide includes the design of handling and storage facilities for fuel assemblies from the receipt of fuel into the nuclear power plant until the fuel departs from that plant. The unirradiated fuel considered in this Guide is assumed not to exhibit any significant level of radiation so that it can be handled without shielding or cooling. This Guide also gives limited consideration to the handling and storage of certain core components. While the general design and safety principles are discussed in Section 2 of this Guide, more specific design requirements for the handling and storage of fuel are given in detailed sections which follow the general design and safety principles. Further useful information is to be found in the IAEA Technical Reports Series No. 189 ''Storage, Handling and Movement of Fuel and Related Components at Nuclear Power Plants'' and No. 198 ''Guide to the Safe Handling of Radioactive Wastes at Nuclear Power Plants''. However, the scope of the Guide does not include consideration of the following: (1) The various reactor physics questions associated with fuel and absorber loading and unloading into the core; (2) The design aspects of preparation of the reactor for fuel loading (such as the removal of the pressure vessel head for a light water reactor) and restoration after loading; (3) The design of shipping casks; (4) Fuel storage of a long-term nature exceeding the design lifetime of the nuclear power plant; (5) Unirradiated fuel containing plutonium

  9. Handling and storage of conditioned high-level wastes

    International Nuclear Information System (INIS)

    1983-01-01

    This report deals with certain aspects of the management of one of the most important wastes, i.e. the handling and storage of conditioned (immobilized and packaged) high-level waste from the reprocessing of spent nuclear fuel and, although much of the material presented here is based on information concerning high-level waste from reprocessing LWR fuel, the principles, as well as many of the details involved, are applicable to all fuel types. The report provides illustrative background material on the arising and characteristics of high-level wastes and, qualitatively, their requirements for conditioning. The report introduces the principles important in conditioned high-level waste storage and describes the types of equipment and facilities, used or studied, for handling and storage of such waste. Finally, it discusses the safety and economic aspects that are considered in the design and operation of handling and storage facilities

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

    International Nuclear Information System (INIS)

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

    1982-11-01

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

  11. Care and handling of container plants from storage to outplanting

    Science.gov (United States)

    Thomas D. Landis; R. Kasten Dumroese

    2011-01-01

    Nursery plants are in a period of high risk from the time they leave the protected environment of the nursery to when they are outplanted. During handling and shipping, nursery stock may be exposed to many damaging stresses, including extreme temperatures, desiccation, mechanical injuries, and storage molds. This is also the period of greatest financial risk, because...

  12. Handling and storage of conditioned high-level wastes

    International Nuclear Information System (INIS)

    Heafield, W.

    1984-01-01

    This paper deals with certain aspects of the management of one of the most important radioactive wastes arising from the nuclear fuel cycle, i.e. the handling and storage of conditioned high-level wastes. The paper is based on an IAEA report of the same title published during 1983 in the Technical Reports Series. The paper provides illustrative background material on the characteristics of high-level wastes and, qualitatively, their requirements for conditioning. The principles important in the storage of high-level wastes are reviewed in conjunction with the radiological and socio-political considerations involved. Four fundamentally different storage concepts are described with reference to published information and the safety aspects of particular storage concepts are discussed. Finally, overall conclusions are presented which confirm the availability of technology for constructing and operating conditioned high-level waste storage facilities for periods of at least several decades. (author)

  13. Industry trends in chip storage and handling

    Science.gov (United States)

    Tim McDonald; Alastair Twaddle

    2000-01-01

    A survey was conducted of US pulp and paper mills to characterize chip pile management trends. The survey was developed by members of the TAPPI Fiber Raw Material Supply Committee and mailed out in December of 1999. There were a total of 80 respondents to the survey. A typical mill was foudn to maintain one sofhvood and one hardwood chip pile, with maximum inventory of...

  14. Proper Handling and Storage of Human Milk

    Science.gov (United States)

    ... maintain the safety and quality of expressed breast milk for the health of the baby. These are general guidelines for storing human milk at different temperatures. Various factors (milk volume, room ...

  15. Renewal of handling and storage equipment in wholesale company

    Directory of Open Access Journals (Sweden)

    Tânia Brasileiro Azevedo Teixeira

    2015-06-01

    Full Text Available This paper presents a use of methodology for renewing handling and storage equipment in a wholesale company. It is based on equipment maintenance, downtime and possession costs. With the analysis performed,, it was possible to make some suggestions for an optimal economic point for pallets replacement. The methodology is based on mathematical and economic principles in order to provide the organization with an increase in productivity and costs reduction for handling and storage equipment. As a result of the use of methodology, the conclusion that it was possible to consider that this point is obtained when the total annual cost is equal to the average total cost was reached. Therefore, the equilibrium point is achieved when the equipment usage time is six years.

  16. Liquefied natural gas (LNG) : production, storage and handling. 7. ed.

    Energy Technology Data Exchange (ETDEWEB)

    Kalra, S; Jaron, K; Adragna, M; Coyle, S; Foley, C; Hawryn, S; Martin, A; McConnell, J [eds.

    2003-07-01

    This Canadian Standard on the production, storage and handling of liquefied natural gas (LNG) was prepared by the Technical Committee on Liquefied Natural Gas under the jurisdiction of the Steering Committee on Oil and Gas Industry Systems and Materials. It establishes the necessary requirements for the design, installation and safe operation of LNG facilities. The Standard applies to the design, location, construction, operation and maintenance of facilities at any location of the liquefaction of natural gas and for the storage, vaporization, transfer, handling and truck transport of LNG. The training of personnel involved is also included as well as containers for LNG storage, including insulated vacuum systems. It includes non-mandatory guidelines for small LNG facilities but does not apply to the transportation of refrigerants, LNG by rail, marine vessel or pipeline. This latest edition contains changes in working of seismic design requirements and minor editorial changes to several clauses to bring the Standard closer to the US National Fire Protection Association's Committee on Liquefied Natural Gas Standard while maintaining Canadian regulatory requirements. The document is divided into 12 sections including: general requirements; plant site provisions; process equipment; stationary LNG storage containers; vaporization facilities; piping system and components; instrumentation and electrical services; transfer of LNG and refrigerants; fire protection, safety and security; and, operating, maintenance and personnel training. This Standard, like all Canadian Standards, was subject to periodic review and was most recently reaffirmed in 2003. 6 tabs., 6 figs., 3 apps.

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

    International Nuclear Information System (INIS)

    Bailey, W.J.

    1990-11-01

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

  18. Assessing materials handling and storage capacities in port terminals

    Science.gov (United States)

    Dinu, O.; Roşca, E.; Popa, M.; Roşca, M. A.; Rusca, A.

    2017-08-01

    Terminals constitute the factual interface between different modes and, as a result, buffer stocks are unavoidable whenever transport flows with different discontinuities meet. This is the reason why assessing materials handling and storage capacities is an important issue in the course of attempting to increase operative planning of logistic processes in terminals. Proposed paper starts with a brief review of the compatibilities between different sorts of materials and corresponding transport modes and after, a literature overview of the studies related to ports terminals and their specialization is made. As a methodology, discrete event simulation stands as a feasible technique for assessing handling and storage capacities at the terminal, taking into consideration the multi-flows interaction and the non-uniform arrivals of vessels and inland vehicles. In this context, a simulation model, that integrates the activities of an inland water terminal and describes the essential interactions between the subsystems which influence the terminal capacity, is developed. Different scenarios are simulated for diverse sorts of materials, leading to bottlenecks identification, performance indicators such as average storage occupancy rate, average dwell or transit times estimations, and their evolution is analysed in order to improve the transfer operations in the logistic process

  19. The UK Biobank sample handling and storage validation studies.

    Science.gov (United States)

    Peakman, Tim C; Elliott, Paul

    2008-04-01

    and aims UK Biobank is a large prospective study in the United Kingdom to investigate the role of genetic factors, environmental exposures and lifestyle in the causes of major diseases of late and middle age. It involves the collection of blood and urine from 500 000 individuals aged between 40 and 69 years. How the samples are collected, processed and stored will have a major impact on the future scientific usefulness of the UK Biobank resource. A series of validation studies was recommended to test the robustness of the draft sample handling and storage protocol. Samples of blood and urine were collected from 40 healthy volunteers and either processed immediately according to the protocol or maintained at specified temperatures (4 degrees C for all tubes with the exception of vacutainers containing acid citrate dextrose that were maintained at 18 degrees C) for 12, 24 or 36 h prior to processing. A further sample was maintained for 24 h at 4 degrees C, processed and the aliquots frozen at -80 degrees C for 20 days and then thawed under controlled conditions. The stability of the samples was compared for the different times in a wide variety of assays. The samples maintained at 4 degrees C were stable for at least 24 h after collection for a wide range of assays. Small but significant changes were observed in metabonomic studies in samples maintained at 4 degrees C for 36 h. There was no degradation of the samples for a range of biochemical assays after short-term freezing and thawing under controlled conditions. Whole blood maintained at 18 degrees C for 24 h in vacutainers containing acid citrate dextrose is suitable for viral immortalization techniques. The validation studies reported in this supplement provide justification for the sample handling and storage procedures adopted in the UK Biobank project.

  20. Radioactive waste management decommissioning spent fuel storage. V. 3. Waste transport, handling and disposal spent fuel storage

    International Nuclear Information System (INIS)

    1985-01-01

    As part of the book entitled Radioactive waste management decommissioning spent fuel storage, vol. 3 dealts with waste transport, handling and disposal, spent fuel storage. Twelve articles are presented concerning the industrial aspects of nuclear waste management in France [fr

  1. An investigation into the handling and storage of dangerous goods ...

    African Journals Online (AJOL)

    As Ghana develops, the Port of Tema has seen an increase in the handling of good, which are substances either due to their inherent properties or in reaction to the environment are considered dangerous and therefore when not handled properly pose significant injury or harm to people, property and the environment.

  2. Spent fuel receipt and lag storage facility for the spent fuel handling and packaging program

    International Nuclear Information System (INIS)

    Black, J.E.; King, F.D.

    1979-01-01

    Savannah River Laboratory (SRL) is participating in the Spent Fuel Handling and Packaging Program for retrievable, near-surface storage of spent light water reactor (LWR) fuel. One of SRL's responsibilities is to provide a technical description of the wet fuel receipt and lag storage part of the Spent Fuel Handling and Packaging (SFHP) facility. This document is the required technical description

  3. Handling and storage of human body fluids for analysis of extracellular vesicles

    NARCIS (Netherlands)

    Yuana, Yuana; Böing, Anita N.; Grootemaat, Anita E.; van der Pol, Edwin; Hau, Chi M.; Cizmar, Petr; Buhr, Egbert; Sturk, Auguste; Nieuwland, Rienk

    2015-01-01

    Because procedures of handling and storage of body fluids affect numbers and composition of extracellular vesicles (EVs), standardization is important to ensure reliable and comparable measurements of EVs in a clinical environment. We aimed to develop standard protocols for handling and storage of

  4. Disk storage at CERN: Handling LHC data and beyond

    International Nuclear Information System (INIS)

    Espinal, X; Adde, G; Chan, B; Iven, J; Presti, G Lo; Lamanna, M; Mascetti, L; Pace, A; Peters, A; Ponce, S; Sindrilaru, E

    2014-01-01

    The CERN-IT Data Storage and Services (DSS) group stores and provides access to data coming from the LHC and other physics experiments. We implement specialised storage services to provide tools for optimal data management, based on the evolution of data volumes, the available technologies and the observed experiment and users' usage patterns. Our current solutions are CASTOR, for highly-reliable tape-backed storage for heavy-duty Tier-0 workflows, and EOS, for disk-only storage for full-scale analysis activities. CASTOR is evolving towards a simplified disk layer in front of the tape robotics, focusing on recording the primary data from the detectors. EOS is now a well-established storage service used intensively by the four big LHC experiments. Its conceptual design based on multi-replica and in-memory namespace, makes it the perfect system for data intensive workflows. The LHC-Long Shutdown 1 (LSI) presents a window of opportunity to shape up both of our storage services and validate against the ongoing analysis activity in order to successfully face the new LHC data taking period in 2015. In this paper, the current state and foreseen evolutions of CASTOR and EOS will be presented together with a study about the reliability of our systems.

  5. Storage and handling of willow from short rotation coppice

    Energy Technology Data Exchange (ETDEWEB)

    Kofman, P. D.; Spinelli, R.

    1997-07-01

    During the project two main storage and drying trials were organised. The first trial in 1996 consisted of 14 piles of 6 different size material (whole shoots, via 200 mm chunk, 100 mm chunk, 50 mm chip, 28 mm chips, 25 mm chips) and six different methods of covering: Open air storage, storage under plastic cover, storage under top-cover, airtight storage, unventilated storage under roof, and intermittent ventilation (cooling) under roof. The drying trial in 1997 which consisted of four piles was established in Horsens in the same building as the ventilated trials the year before. Only Austoft 50 mm chips were used for this trial. The four piles were established in February and removed in May. Based on all the results of the trials the following conclusions can be drawn: Storage of willow from short rotation coppice is very difficult. Fine chips, such as producted by the two main harvesting machines Claas and Austoft are not suitable for storage over prolonged periods of time (more than 2 months); fine chips loose a large amount of dry matter and a lot of their lower heating value; fine chips also have a heavy infestation of micro-organisms which might cause working environment problems; short rotation coppice is best delivered straight into the heating plants during harvest; if short rotation coppice has to be stored, then this should be done as whole shoots or large chunk; if short rotation coppice has to be stored as chips for a longer period of time (more than two months), then these chips should be sealed airtight as silage. (EG) EFP-94; EFP-95; EFP-96. 10 refs.

  6. Retrospective search on biomass harvesting techniques including materials handling and storage

    Energy Technology Data Exchange (ETDEWEB)

    1985-10-01

    This literature search covers the period 1977 to date. The harvesting, materials handling and storage of the following materials: wood; crops and crop residues; peat; sugar cane; reeds, grasses and fers; algae and jojoba shrubs are covered.

  7. Pre-disposal storage, transport and handling of vitrified high level waste

    International Nuclear Information System (INIS)

    Kempe, T.F.; Martin, A.

    1981-05-01

    The objectives of the study were to review non site-specific engineering features of the storage, transport and handling of vitrified high level radioactive waste prior to its transfer into an underground repository, and to identify those features which require validation or development. Section headings are: introduction (historical and technical background); characteristics and arisings of vitrified high level waste; overpacks (additional containment barrier, corrosion resistant); interim storage of HLW; transport of HLW; handling; conclusions and recommendations. (U.K.)

  8. Conceptual design of the handling and storage system for spent target vessel

    Energy Technology Data Exchange (ETDEWEB)

    Adachi, Junichi; Sasaki, Shinobu; Kaminaga, Masanori; Hino, Ryutaro [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

    2001-03-01

    A conceptual design of a handling and storage system for spent target vessels has been carried out, in order to establish spent target technology for the neutron scattering facility. The spent target vessels must be treated remotely with high reliability and safety, since they are highly activated and contain the poisonous mercury. The system is composed of a target exchange trolley to exchange the target vessel, remote handling equipment such as manipulators, airtight casks for the spent target vessel, storage pits and so on. This report presents the results of conceptual design study on a basic plan, a handling procedure, main devices and their arrangement of a handling and storage system for the spent target vessels. (author)

  9. Facility handling and operational considerations with dry storage casks

    International Nuclear Information System (INIS)

    Moegling, J.; McCreery, P.N.

    1982-09-01

    The Tennessee Valley Authority, in conjunction with US DOE and Pacific Northwest Laboratory, is conducting the first US commercial demonstration of spent fuel storage in casks. The two casks selected for this study are the Castor Ic, on loan from Gesellschaft fur Nuklear Service of Essen, West Germany and the DOE supplied REA 2023, manufactured by Ridihalgh, Eggers, and Associates, of Columbus, Ohio. Preparations began in the spring of 1982. The casks are expected to be loaded with fuel at Brown's Ferry Nuclear Station early in 1984, and the test completed about two years later. NRC is issuing a two-year license for this test under 10 CFR 72

  10. Remote Handled Transuranic Sludge Retrieval Transfer And Storage System At Hanford

    Energy Technology Data Exchange (ETDEWEB)

    Raymond, Rick E. [CH2M HILL Plateau Remediation Company, Richland, WA (United States); Frederickson, James R. [AREVA, Avignon (France); Criddle, James [AREVA, Avignon (France); Hamilton, Dennis [CH2M HILL Plateau Remediation Company, Richland, WA (United States); Johnson, Mike W. [CH2M HILL Plateau Remediation Company, Richland, WA (United States)

    2012-10-18

    This paper describes the systems developed for processing and interim storage of the sludge managed as remote-handled transuranic (RH-TRU). An experienced, integrated CH2M HILL/AFS team was formed to design and build systems to retrieve, interim store, and treat for disposal the K West Basin sludge, namely the Sludge Treatment Project (STP). A system has been designed and is being constructed for retrieval and interim storage, namely the Engineered Container Retrieval, Transfer and Storage System (ECRTS).

  11. Remote Handled Transuranic Sludge Retrieval Transfer And Storage System At Hanford

    International Nuclear Information System (INIS)

    Raymond, Rick E.; Frederickson, James R.; Criddle, James; Hamilton, Dennis; Johnson, Mike W.

    2012-01-01

    This paper describes the systems developed for processing and interim storage of the sludge managed as remote-handled transuranic (RH-TRU). An experienced, integrated CH2M HILL/AFS team was formed to design and build systems to retrieve, interim store, and treat for disposal the K West Basin sludge, namely the Sludge Treatment Project (STP). A system has been designed and is being constructed for retrieval and interim storage, namely the Engineered Container Retrieval, Transfer and Storage System (ECRTS)

  12. Online data handling and storage at the CMS experiment

    Science.gov (United States)

    Andre, J.-M.; Andronidis, A.; Behrens, U.; Branson, J.; Chaze, O.; Cittolin, S.; Darlea, G.-L.; Deldicque, C.; Demiragli, Z.; Dobson, M.; Dupont, A.; Erhan, S.; Gigi, D.; Glege, F.; Gómez-Ceballos, G.; Hegeman, J.; Holzner, A.; Jimenez-Estupiñán, R.; Masetti, L.; Meijers, F.; Meschi, E.; Mommsen, RK; Morovic, S.; Nuñez-Barranco-Fernández, C.; O'Dell, V.; Orsini, L.; Paus, C.; Petrucci, A.; Pieri, M.; Racz, A.; Roberts, P.; Sakulin, H.; Schwick, C.; Stieger, B.; Sumorok, K.; Veverka, J.; Zaza, S.; Zejdl, P.

    2015-12-01

    During the LHC Long Shutdown 1, the CMS Data Acquisition (DAQ) system underwent a partial redesign to replace obsolete network equipment, use more homogeneous switching technologies, and support new detector back-end electronics. The software and hardware infrastructure to provide input, execute the High Level Trigger (HLT) algorithms and deal with output data transport and storage has also been redesigned to be completely file- based. All the metadata needed for bookkeeping are stored in files as well, in the form of small documents using the JSON encoding. The Storage and Transfer System (STS) is responsible for aggregating these files produced by the HLT, storing them temporarily and transferring them to the T0 facility at CERN for subsequent offline processing. The STS merger service aggregates the output files from the HLT from ∼62 sources produced with an aggregate rate of ∼2GB/s. An estimated bandwidth of 7GB/s in concurrent read/write mode is needed. Furthermore, the STS has to be able to store several days of continuous running, so an estimated of 250TB of total usable disk space is required. In this article we present the various technological and implementation choices of the three components of the STS: the distributed file system, the merger service and the transfer system.

  13. Online Data Handling and Storage at the CMS Experiment

    Energy Technology Data Exchange (ETDEWEB)

    Andre, J. M.; et al.

    2015-12-23

    During the LHC Long Shutdown 1, the CMS Data Acquisition (DAQ) system underwent a partial redesign to replace obsolete network equipment, use more homogeneous switching technologies, and support new detector back-end electronics. The software and hardware infrastructure to provide input, execute the High Level Trigger (HLT) algorithms and deal with output data transport and storage has also been redesigned to be completely file- based. All the metadata needed for bookkeeping are stored in files as well, in the form of small documents using the JSON encoding. The Storage and Transfer System (STS) is responsible for aggregating these files produced by the HLT, storing them temporarily and transferring them to the T0 facility at CERN for subsequent offline processing. The STS merger service aggregates the output files from the HLT from ~62 sources produced with an aggregate rate of ~2GB/s. An estimated bandwidth of 7GB/s in concurrent read/write mode is needed. Furthermore, the STS has to be able to store several days of continuous running, so an estimated of 250TB of total usable disk space is required. In this article we present the various technological and implementation choices of the three components of the STS: the distributed file system, the merger service and the transfer system.

  14. Online data handling and storage at the CMS experiment

    International Nuclear Information System (INIS)

    Andre, J-M; Andronidis, A; Chaze, O; Deldicque, C; Dobson, M; Dupont, A; Gigi, D; Glege, F; Hegeman, J; Jimenez-Estupiñán, R; Masetti, L; Meijers, F; Behrens, U; Branson, J; Cittolin, S; Holzner, A; Darlea, G-L; Demiragli, Z; Gómez-Ceballos, G; Erhan, S

    2015-01-01

    During the LHC Long Shutdown 1, the CMS Data Acquisition (DAQ) system underwent a partial redesign to replace obsolete network equipment, use more homogeneous switching technologies, and support new detector back-end electronics. The software and hardware infrastructure to provide input, execute the High Level Trigger (HLT) algorithms and deal with output data transport and storage has also been redesigned to be completely file- based. All the metadata needed for bookkeeping are stored in files as well, in the form of small documents using the JSON encoding. The Storage and Transfer System (STS) is responsible for aggregating these files produced by the HLT, storing them temporarily and transferring them to the T0 facility at CERN for subsequent offline processing. The STS merger service aggregates the output files from the HLT from ∼62 sources produced with an aggregate rate of ∼2GB/s. An estimated bandwidth of 7GB/s in concurrent read/write mode is needed. Furthermore, the STS has to be able to store several days of continuous running, so an estimated of 250TB of total usable disk space is required. In this article we present the various technological and implementation choices of the three components of the STS: the distributed file system, the merger service and the transfer system. (paper)

  15. Online data handling and storage at the CMS experiment

    CERN Document Server

    Andre, Jean-marc Olivier; Behrens, Ulf; Branson, James; Chaze, Olivier; Demiragli, Zeynep; Dobson, Marc; Dupont, Aymeric; Erhan, Samim; Gigi, Dominique; Glege, Frank; Gomez Ceballos, Guillelmo; Hegeman, Jeroen Guido; Holzner, Andre Georg; Jimenez Estupinan, Raul; Masetti, Lorenzo; Meijers, Franciscus; Meschi, Emilio; Mommsen, Remigius; Morovic, Srecko; Nunez Barranco Fernandez, Carlos; O'Dell, Vivian; Orsini, Luciano; Paus, Christoph Maria Ernst; Petrucci, Andrea; Pieri, Marco; Racz, Attila; Roberts, Penelope Amelia; Sakulin, Hannes; Schwick, Christoph; Stieger, Benjamin Bastian; Sumorok, Konstanty; Veverka, Jan; Zaza, Salvatore; Zejdl, Petr

    2015-01-01

    During the LHC Long Shutdown 1, the CMS Data Acquisition (DAQ) system underwent a partial redesign to replace obsolete network equipment, use more homogeneous switching technologies, and support new detector back-end electronics. The software and hardware infrastructure to provide input, execute the High Level Trigger (HLT) algorithms and deal with output data transport and storage has also been redesigned to be completely file- based. All the metadata needed for bookkeeping are stored in files as well, in the form of small 'documents' using the JSON encoding. The Storage and Transfer System (STS) is responsible for aggregating these files produced by the HLT, storing them temporarily and transferring them to the T0 facility at CERN for subsequent offline processing. The STS merger service aggregates the output files from the HLT from ~62 sources produced with an aggregate rate of ~2GB/s. An estimated bandwidth of 7GB/s in concurrent read/write mode is needed. Furthermore, the STS has to be able to store ...

  16. Plutonium dioxide storage: Conditions for preparation and handling

    International Nuclear Information System (INIS)

    Haschke, J.M.; Ricketts, T.E.

    1995-08-01

    Desorption and adsorption of plutonium dioxide are derived from production-scale experiments that demonstrate techniques of preparing weapons-grade material for extended storage. In combination with data from literature, results define conditions for preparing and certifying PuO 2 and provide essential information for developing and implementing a repackaging process compliant with DOE standards for safe storage of plutonium. As demonstrated by loss-on-ignition (LOI) analysis, adsorbates are effectively removed by heating the oxide in air at 950 C for two hours. After oxides are fired at this temperature, specific surface areas are consistently less than 5 m 2 /g. Due to this low surface area, water adsorption by fired oxide is limited to a maximum of 0.2 mass % at 50% relative humidity. Kinetic data for the adsorption process show that water is accommodated on the oxide surface by a sequence of distinct first-order steps comprising five types of adsorbate interaction and accumulating ten molecular layers of H 2 0 at 100% humidity. An equation defining the humidity dependence of the adsorption rate during the first step is applied in estimating time periods that a fired oxide may remain in given configurations without detrimental adsorption. Particle size measurements show that the source terms for environmental dispersal of oxides prepared by hydride-catalyzed reaction of metal and by oxalate calcination are approximately 20 and 0.1 mass %, respectively, and that the values are reduced by firing. Evidence for a chemical reaction between dioxide and water is discussed and practical applications of the results to oxide stabilization and LOI analysis are presented

  17. Handling and final storage of radioactive metal components

    International Nuclear Information System (INIS)

    Loennerberg, B.; Engelbrektson, A.; Neretnieks, I.

    1978-06-01

    After the dismounting of the fuel elements, the next stage is to undertake the final storing of the metal components, which have kept the fuel rods together. The components are transmitted to a pool where they are cut into pieces, compacted and placed in wire baskets. These are transferred in a water channel to a cell, where the metal components are embedded into concrete blocks. Thus the baskets are placed in prefabricated concrete containers, after which the metal parts are embedded into cement grout, injected from the bottom of the containers. The blocks are finally stored in rock tunnels constituting a storage similar to the repositories for vitrified waste and spent fuel, although somewhat simplified, taking advantage of the much lower amount of radioactive material in the case of metal components. Thus a depositioning depth of 300 m in rock is very much on the safe side and it is appropriate in this case to fill the tunnels with concrete, ensuring by its alcalinity a suffi ciently low rate of dissolution of the metal and migration of radioactive substances

  18. 21 CFR 203.32 - Drug sample storage and handling requirements.

    Science.gov (United States)

    2010-04-01

    ... 21 Food and Drugs 4 2010-04-01 2010-04-01 false Drug sample storage and handling requirements. 203.32 Section 203.32 Food and Drugs FOOD AND DRUG ADMINISTRATION, DEPARTMENT OF HEALTH AND HUMAN... contamination, deterioration, and adulteration. (b) Compliance with compendial and labeling requirements...

  19. 18 CFR 1304.405 - Fuel storage tanks and handling facilities.

    Science.gov (United States)

    2010-04-01

    ... used to contain a regulated substance (such as a petroleum product) and has 10 percent or more of its... or remedy pollution or violations of law, including removal of the UST system, with costs charged to... flammable and combustible liquids storage tanks at marine service stations. (d) Fuel handling on private...

  20. Licence template for mobile handling and storage of radioactive substances for the nondestructive testing of materials

    International Nuclear Information System (INIS)

    Lange, A.; Schumann, J.; Huhn, W.

    2016-01-01

    The Technical Committee ''Radiation Protection'' (Fachausschuss ''Strahlenschutz'') and the Laender Committee ''X-ray ordinance'' (Laenderausschuss ''Roentgenverordnung'') have appointed a working group for the formulation of licence templates for the nationwide use of X-ray equipment or handling of radioactive substances. To date, the following licence templates have been adopted: - Mobile operation of X-ray equipment under technical radiography to the coarse structural analysis in material testing; - Mobile operation of a handheld X-ray fluorescence system; - Mobile operation of a flash X-ray system; - Operation of an X-ray system for teleradiology The licence template ''Mobile handling and storage of radioactive substances for the nondestructive testing of materials'' is scheduled for publication. The licence template ''Practices in external facilities and installations'' is currently being revised. The licence template ''Mobile handling and storage of radioactive substances for the nondestructive testing of materials'' is used as an example to demonstrate the legal framework and the results of the working group.

  1. Manual on safe production, transport, handling and storage of uranium hexafluoride

    International Nuclear Information System (INIS)

    1994-11-01

    This document includes a description of the physical, chemical and radiological properties of UF 6 and related products, including information concerning their production, handling, storage and transportation and the management of the wastes which result. All the operations of UF 6 management are considered form a safety point of view. The IAEA organized a series of meetings to consider the hazards of UF 6 transport since considerable quantities of depleted, natural and enriched UF 6 are transported between nuclear fuel sites. Storage of depleted UF 6 is another important issue. Factors affecting long term storage are presented, especially site choice and cylinder corrosion. Other topics such as waste management, quality assurance and emergency preparedness which contribute to the overall safety of UF 6 handling, are included. The intention of this document is to provide analysis of the safety implications of all stages of UF 6 operations and to draw attention to specific features and properties of importance. 38 refs, figs, tabs

  2. Final Generic Environmental Impact Statement. Handling and storage of spent light water power reactor fuel. Volume 2. Appendices

    International Nuclear Information System (INIS)

    1979-08-01

    This volume contains the following appendices: LWR fuel cycle, handling and storage of spent fuel, termination case considerations (use of coal-fired power plants to replace nuclear plants), increasing fuel storage capacity, spent fuel transshipment, spent fuel generation and storage data, characteristics of nuclear fuel, away-from-reactor storage concept, spent fuel storage requirements for higher projected nuclear generating capacity, and physical protection requirements and hypothetical sabotage events in a spent fuel storage facility

  3. 41 CFR 50-204.3 - Material handling and storage.

    Science.gov (United States)

    2010-07-01

    .... Bags, containers, bundles, etc. stored in tiers shall be stacked, blocked, interlocked and limited in... harborage. Vegetation control will be exercised when necessary. (d) Proper drainage shall be provided. (e...

  4. 29 CFR 1917.156 - Fuel handling and storage.

    Science.gov (United States)

    2010-07-01

    ...) Liquid fuel dispensing devices, such as pumps, shall be mounted either on a concrete island or be...) Containers shall be examined before recharging and again before reuse for the following: (A) Dents, scrapes...

  5. Transport, acceptance, storage and handling of the itens of nuclear power plants

    International Nuclear Information System (INIS)

    1989-01-01

    The norm aiming to establish the requirements applied to workers or organizations which participate of the activities of transport, acceptance, storage and handling of important itens for safety of nuclear power plants, is presented. The established requirements treat of protection and control necessary to assure that the quality of important itens for safety be it preserved from the end of fabrication until their incorporation to nuclear power plant. (M.C.K.) [pt

  6. Characteristics of fuel crud and its impact on storage, handling, and shipment of spent fuel

    International Nuclear Information System (INIS)

    Hazelton, R.F.

    1987-09-01

    Corrosion products, called ''crud,'' form on out-of-reactor surfaces of nuclear reactor systems and are transported by reactor coolant to the core, where they deposit on external fuel-rod cladding surfaces and are activated by nuclear reactions. After discharge of spent fuel from a reactor, spallation of radioactive crud from the fuel rods could impact wet or dry storage operations, handling (including rod consolidation), and shipping. It is the purpose of this report to review earlier (1970s) and more recent (1980s) literature relating to crud, its characteristics, and any impact it has had on actual operations. Crud characteristics vary from reactor type to reactor type, reactor to reactor, fuel assembly to fuel assembly in a reactor, circumferentially and axially in an assembly, and from cycle to cycle for a specific facility. To characterize crud of pressurized-water (PWRs) and boiling-water reactors (BWRs), published information was reviewed on appearance, chemical composition, areal density and thickness, structure, adhesive strength, particle size, and radioactivity. Information was also collected on experience with crud during spent fuel wet storage, rod consolidation, transportation, and dry storage. From experience with wet storage, rod consolidation, transportation, and dry storage, it appears crud spallation can be managed effectively, posing no significant radiological problems. 44 refs., 11 figs

  7. Consumer Poultry Handling Behavior in the Grocery Store and In-Home Storage.

    Science.gov (United States)

    Donelan, Amy K; Chambers, Delores H; Chambers, Edgar; Godwin, Sandria L; Cates, Sheryl C

    2016-04-01

    Considerable work on consumers' food safety habits has highlighted issues associated with home food preparation. However, consumer handling of foods, such as poultry, during shopping and storage has not been noted. The objective of this study was to determine consumer behaviors during purchasing and initial storage of raw poultry to determine potential cross-contamination issues. A shop-along observational study was conducted to determine actual shopping, transportation, and storage behavior of consumers who purchase raw poultry products. Neither hand sanitizer nor wipes were observed in 71% of grocery store meat sections of stores visited. Plastic bags could be found in the meat section 85% of the time, but only 25% of shoppers used the bag for their raw poultry purchases. During checkout, the poultry was bagged separately from other products 71% of the time. A majority of shoppers stored raw poultry in the original package without an additional container or overwrap. Overall, there needs to be an increase in food safety education on the handling of poultry during purchasing, transportation, and storage.

  8. Generation, on-site storage; handling and processing of industrial waste of Tehran

    International Nuclear Information System (INIS)

    Abduli, M.A.

    1997-01-01

    This paper describes out the present status of generation, on-site handling, processing and storage of industrial waste in Tehran. In this investigation, 67 large scale factories of different industrial groups were randomly selected. Above cited functional elements of these factories were surveyed. In this investigation a close contact with each factory was required, thus a questionnaire was prepared and distributed among these factories. The relationship between daily weight of the industrial waste (Y) and number of employer of each factory (x) is found to be Y=547.4 + 0.58 x. The relationship between daily volume of industrial waste (V), and daily weight of waste generated in each factory (Y) can be described by V=1.56 + 0.00078 Y. About 68% of the factories have their own interim storage site and the rest of the factories do not possess any on-site storage facility

  9. Immunogenicity of biopharmaceuticals and biosimilars in relation to storage, handling and stability

    International Nuclear Information System (INIS)

    Hincal, F.

    2009-01-01

    Therapeutic proteins or biopharmaceuticals provide effective treatment for many diseases and medical conditions, and vaccines, immunoglobulins and monoclonal antibodies are critical biodefense biopharmaceuticals which constitute an indispensable part of biodefense stockpiles. The manufacturing process for biopharmaceuticals and their generic forms which are called biosimilars is far more complex than for low molecular weight drugs and generics. Any minor change made at any stage may have a critical effect on the clinical efficacy and safety. Potential immunogenicity is the key issue for biopharmaceuticals and biosimilars and may have serious clinical consequences ranging from allergy and anaphylaxis, as well as loss of efficacy of the product. Immunogenicity may be influenced by factors related to manufacturing process, formulation, aggregate formation, contaminants and impurities, and also by the factors related to the storage and handling. Stability is particularly important with larger protein molecules, because their in vivo effects often depend on their three-dimensional structure. Proteins usually aggregate from partially unfolded molecules and aggregates can enhance immunogenicity. Although product formulations are developed to maximize and maintain the fraction of the protein molecules present in the native state, significant amounts of aggregates can form, especially over pharmaceutically relevant time scales and under stress conditions. Exposure to air-liquid and solid-liquid interfaces, light, temperature fluctuations or minor impurities can induce aggregation. Such exposure can occur during processing steps, as well as in the final product container during storage, shipment and handling. Biopharmaceuticals are particularly sensitive to temperature changes and/or shaking. Strict storage and handling conditions and timely and effective stability/shelf-life testing are therefore essential for maintaining product integrity and stability, and hence efficacy

  10. Transport, handling, and interim storage of intermediate-level transuranic waste at the INEL

    International Nuclear Information System (INIS)

    Metzger, J.C.; Snyder, A.M.

    1977-09-01

    The Idaho National Engineering Laboratory stores transuranic (TRU)-contaminated waste emitting significant amounts of beta-gamma radiation. This material is referred to as intermediate-level TRU waste. The Energy Research and Development Administration requires that this waste be stored retrievably during the interim before a Federal repository becomes operational. Waste form and packaging criteria for the eventual storage of this waste at a Federal repository, i.e., the Waste Isolation Pilot Plant (WIPP), have been tentatively established. The packaging and storage techniques now in use at the Idaho National Engineering Laboratory are compatible with these criteria and also meet the requirement that the waste containers remain in a readily-retrievable, contamination-free condition during the interim storage period. The Intermediate Level Transuranic Storage Facility (ILTSF) provides below-grade storage in steel pipe vaults for intermediate-level TRU waste prior to shipment to the WIPP. Designated waste generating facilities, operated for the Energy Research and Development Administration, use a variety of packaging and transportation methods to deliver this waste to the ILTSF. Transfer of the waste containers to the ILTSF storage vaults is accomplished using handling methods compatible with these waste packaging and transport methods

  11. Manual on safe production, transport, handling and storage of uranium hexafluoride

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1994-11-01

    This document includes a description of the physical, chemical and radiological properties of UF{sub 6} and related products, including information concerning their production, handling, storage and transportation and the management of the wastes which result. All the operations of UF{sub 6} management are considered form a safety point of view. The IAEA organized a series of meetings to consider the hazards of UF{sub 6} transport since considerable quantities of depleted, natural and enriched UF{sub 6} are transported between nuclear fuel sites. Storage of depleted UF{sub 6} is another important issue. Factors affecting long term storage are presented, especially site choice and cylinder corrosion. Other topics such as waste management, quality assurance and emergency preparedness which contribute to the overall safety of UF{sub 6} handling, are included. The intention of this document is to provide analysis of the safety implications of all stages of UF{sub 6} operations and to draw attention to specific features and properties of importance. 38 refs, figs, tabs.

  12. Fate of vinclozolin, thiabendazole and dimethomorph during storage, handling and forcing of chicory.

    Science.gov (United States)

    Spanoghe, Pieter; Ryckaert, Bert; Van Gheluwe, Cindy; Van Labeke, Marie-Christine

    2010-02-01

    As part of ongoing research for a sustainable production of Belgian endives, the fate of three fungicides during storage, handling and forcing of witloof chicory roots was investigated. Storage roots are protected against Sclerotinia sp. Fuckel and Phoma exigua var. exigua Desm. by means of vinclozolin and thiabendazole respectively. During hydroponic forcing, the most imminent pathogen is Phytophthora cryptogea Pethybr. & Laff., which is controlled by the use of dimethomorph. Vinclozolin and thiabendazole concentrations on roots remained constant during storage at -1 degrees C. Dermal exposure of the workers in hydroponics was exceeded. Vinclozolin and thiabendazole residues were not detected 2 weeks after hydroponic forcing; dimethomorph was still detected at harvest. At harvest, the vinclozolin concentration in the chicory heads was below the maximum residue limit, but the chicory roots contained residues much above the thiabendazole and dimethomorph maximum residue level. Vinclozolin and thiabendazole residues applied before storage are still present on the roots at the start of the forcing cycle. During the set-up of chicory roots, preventive measures are recommended, as effects of repeated human exposure to low doses of applied fungicides cannot be excluded. Dimethomorph applied at the start of the hydroponic forcing is the only pesticide detected in the drainage water at harvest. The chicory heads were safe for human consumption. However, more attention should be paid to the residues of fungicides in the roots used for cattle feeding.

  13. Storage, handling and internal transport of radioactive materials (fuel elements excepted) in nuclear power plants

    International Nuclear Information System (INIS)

    1983-06-01

    The rule applies to storage and handling as well as to transport within the plant and to the exchange of - solid radioactive wastes, - liquid radioactive wastes, except for those covered by the rule KTA 3603, - radioactive components and parts which are planned to be mounted and dismounted until shutdown of the plant, - radioactive-contaminated tools and appliances, - radioactive preparations. The rule is to be applied within the fenced-in sites of stationary nuclear power plants with LWR or HTR including their transport load halls, as fas as these are situated so as to be approachable from the nuclear power station by local transport systems. (orig./HP) [de

  14. Comparative economics for DUCRETE spent fuel storage cask handling, transportation, and capital requirements

    International Nuclear Information System (INIS)

    Powell, F.P.

    1995-04-01

    This report summarizes economic differences between a DUCRETE spent nuclear fuel storage cask and a conventional concrete storage cask in the areas of handling, transportation, and capital requirements. The DUCRETE cask is under evaluation as a new technology that could substantially reduce the overall costs of spent fuel and depleted U disposal. DUCRETE incorporates depleted U in a Portland cement mixture and functions as the cask's primary radiation barrier. The cask system design includes insertion of the US DOE Multi-Purpose Canister inside the DUCRETE cask. The economic comparison is from the time a cask is loaded in a spent fuel pool until it is placed in the repository and includes the utility and overall US system perspectives

  15. Monitored Retrievable Storage conceptual system study: dry receiving and handling facility

    International Nuclear Information System (INIS)

    1984-01-01

    A preconceptual design and estimate for a MRS receiving and handling (R and H) facility at a hypothetical site in the United States are presented. The facility consists of a receiving and handling building plus associated operating buildings, system, and site development features. The R and H building and the supporting buildings and site development features are referred to as the R and H area. Adjoining the R and H area will be an interim waste storage area currently being considered by others. The desirability of building a full capacity (3000-MTU) MRS facility initially versus adding additional capacity at a later date in a phased construction program was investigated. Several advantages of phased construction include incorporation of new designs, modification of receiving-handling-packaging, and changes in regulatory requirements or the waste management program which may develop following startup and operation of an 1800-MTU MRS facility. The cost of a 3000-MTU MRS facility constructed initially was estimated at $193,200,000. If a phased construction program was implemented, including escalation to the mid-point of Phase 2 construction, a capital expenditure of $215,300,000 is estimated - a cost penalty of $22,100,000 or about 11% for phased construction

  16. Spent fuel handling and storage facility for an LWR fuel reprocessing plant

    International Nuclear Information System (INIS)

    Baker, W.H.; King, F.D.

    1979-01-01

    The facility will have the capability to handle spent fuel assemblies containing 10 MTHM/day, with 30% if the fuel received in legal weight truck (LWT) casks and the remaining fuel received in rail casks. The storage capacity will be about 30% of the annual throughput of the reprocessing plant. This size will provide space for a working inventory of about 50 days plant throughput and empty storage space to receive any fuel that might be in transit of the reprocessing plant should have an outage. Spent LWR fuel assemblies outside the confines of the shipping cask will be handled and stored underwater. To permit drainage, each water pool will be designed so that it can be isolated from the remaining pools. Pool water quality will be controlled by a filter-deionizer system. Radioactivity in the water will be maintained at less than or equal to 2 x 10 -4 Ci/m 3 ; conductivity will be maintained at 1 to 2 μmho/cm. The temperature of the pool water will be maintained at less than or equal to 40 0 C to retard algae growth and reduce evaporation. Decay heat will be transferred to the environment via a heat exchanger-cooling tower system

  17. Equipment for RAW handling, packaging, transport and storage from ZTS VVU KOSICE a.s

    International Nuclear Information System (INIS)

    Vargovcik, L.

    2004-01-01

    Since 1988, the company ZTS VVU KOSICE has devoted a great part of its activities to the development of equipment for RAW handling, packaging, transport and storage, mainly for application in the decommissioning of NPP A1 at Jaslovske Bohunice in Slovakia. This is a HWGCR NPP shut down following a breakdown in 1977. This incident was caused by disruption of the technological channel serving as a barrier between heavy water moderator and fuel assembly. Damage of this barrier enabled heavy water leakage into the primary circuit with partial fuel elements cladding damage and subsequent additional contamination of the primary circuit. During two consecutive years after the incident main effort was focused on activities related to personnel and environment protection, moderator draining, reactor defuelling, dry cleaning of the primary circuit, repair and maintenance of equipment. The next step was the preparation of the concept of NPP A-1 introduction into dry safe state. The order of importance of RAW liquidation was as follows: 1. Spent fuel - spent fuel assemblies from NPP A-1 were, after short cooling, stored temporarily in storage pipe containers filled at the beginning of NPP operation with ''chrompik'' (an aqueous solution of K 2 Cr 2 O 7 with concentration of 3-5%), later with ''dowtherm'' (mixture of bi-phenyl oxide and bi-phenyl). The containers were placed in a storage pond filled with water. 2. Liquid RAW - combustible (dowtherm, oils) and non-combustible (chrompik, Demi water, decontaminating solutions, sludge, sorbents, etc.) 3. Solid RAW - metallic and non-metallic For this purpose, it was necessary to build RAW processing lines, intermediate storage facilities and systems for manipulation and transport of RAW

  18. Remote technology related to the handling, storage and disposal of spent fuel. Proceedings of a technical committee meeting

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-11-01

    Reduced radiation exposure, greater reliability and cost savings are all potential benefits of the application of remote technologies to the handling of spent nuclear fuel. Remote equipment and technologies are used to some extent in all facilities handling fuel and high-level wastes whether they are for interim storage, processing/repacking, reprocessing or disposal. In view of the use and benefits of remote technologies, as well as recent technical and economic developments in the area, the IAEA organized the Technical Committee Meeting (TCM) on Remote Technology Related to the Handling, Storage and/or Disposal of Spent Fuel. Twenty-one papers were presented at the TCM, divided into five general areas: 1. Choice of technologies; 2. Use of remote technologies in fuel handling; 3. Use of remote technologies for fuel inspection and characterization; 4. Remote maintenance of facilities; and 5. Current and future developments. Refs, figs and tabs.

  19. Handling of spent nuclear fuel and final storage of nitrified high level reprocessing waste

    International Nuclear Information System (INIS)

    The following stages of handling and transport of the fuel on its way to final storage are dealt with in the report. 1) The spent nuclear fuel is stored at the power station or in the central fuel storage facility awaiting reprocessing. 2) The fuel is reprocessed, i.e. uranium, plutonium and waste are separated from each other. Reprocessing does not take place in Sweden. The highlevel waste is vitrified and can be sent back to Sweden in the 1990s. 3) Vitrified waste is stored for about 30 years awaiting deposition in the final repository. 4) The waste is encapsulated in highly durable materials to prevent groundwater from coming into contact with the waste glass while the radioactivity of the waste is still high. 5) The canisters are emplaced in a final repository which is built at a depth of 500 m in rock of low permeability. 6) All tunnels and shafts are filled with a mixture of clay and sand of low permeability. A detailed analysis of possible harmful effects resulting from normal acitivties and from conceivable accidents is presented in a special section. (author)

  20. Storage, handling and movement of fuel and related components at nuclear power plants

    International Nuclear Information System (INIS)

    1979-01-01

    The report describes in general terms the various operations involved in the handling of fresh fuel, irradiated fuel, and core components such as control rods, neutron sources, burnable poisons and removable instruments. It outlines the principal safety problems in these operations and provides the broad safety criteria which must be observed in the design, operation and maintenance of equipment and facilities for handling, transferring, and storing nuclear fuel and core components at nuclear power reactor sites

  1. Consumer knowledge, storage, and handling practices regarding Listeria in frankfurters and deli meats: results of a Web-based survey.

    Science.gov (United States)

    Cates, Sheryl C; Morales, Roberta A; Karns, Shawn A; Jaykus, Lee-Ann; Kosa, Katherine M; Teneyck, Toby; Moore, Christina M; Cowen, Peter

    2006-07-01

    Proper storage and handling of refrigerated ready-to-eat foods can help reduce the risk of listeriosis. A national Web-based survey was conducted to measure consumer awareness and knowledge of Listeria and to estimate the prevalence of the U.S. Department of Agriculture-recommended consumer storage and handling practices for frankfurters and deli meats. The demographic characteristics of consumers who are unaware of Listeria and who do not follow the recommended storage guidelines were also assessed. In addition, predictive models were developed to determine which consumers engage in risky storage practices. Less than half of the consumers surveyed were aware of Listeria, and most of those aware were unable to identify associated food vehicles. Awareness was lower among adults 60 years of age and older, an at-risk population for listeriosis, and individuals with relatively less education and lower incomes. Most households safely stored and prepared frankfurters. Most households stored unopened packages of vacuum-packed deli meats in the refrigerator within the U.S. Department of Agriculture-recommended storage guidelines (deli meats and freshly sliced deli meats for longer than the recommended time (< or =5 days). Men, more-educated individuals, and individuals living in metropolitan areas were more likely to engage in risky storage practices. This study identified the need to develop targeted educational initiatives on listeriosis prevention.

  2. Photodegradation of the Mycobacterium ulcerans toxin, mycolactones: considerations for handling and storage.

    Directory of Open Access Journals (Sweden)

    Estelle Marion

    Full Text Available BACKGROUND: Mycolactones are toxins secreted by M. ulcerans, the etiological agent of Buruli ulcer. These toxins, which are the main virulence factors of the bacilli, are responsible for skin lesions. Considering their specificity for M. ulcerans and their presence in skin lesions even at early stages, mycolactones are promising candidates for the development of a diagnostic tool for M. ulcerans infection. Stability of purified mycolactones towards light and heat has not yet been investigated, despite the importance of such parameters in the selection of strategies for a diagnosis tool development. In this context, the effects of UV, light and temperature on mycolactone stability and biological activity were studied. METHODOLOGY/PRINCIPAL FINDINGS: To investigate the effect of these physical parameters, mycolactones were exposed to different wavelengths in several solvents and temperatures. Structural changes and biological activity were monitored. Whilst high temperature had no effect on mycolactones, UV irradiation (UV-A, UV-B and UV-C and sunlight exposure caused a considerable degradation, as revealed by LC-MS and NMR analysis, correlated with a loss of biological activity. Moreover, effect of UVs on mycolactone caused a photodegradation rather than a phototransformation due to the identification of degradation product. CONCLUSION/SIGNIFICANCE: This study demonstrates the high sensitivity of mycolactones to UVs as such it defines instructions for storage and handling.

  3. Generic environmental impact statement on handling and storage of spent light water power reactor fuel. Appendices

    International Nuclear Information System (INIS)

    1978-03-01

    Detailed appendices are included with the following titles: light water reactor fuel cycle, present practice, model 1000MW(e) coal-fired power plant, increasing fuel storage capacity, spent fuel transshipment, spent fuel generation and storage data (1976-2000), characteristics of nuclear fuel, and ''away-from-reactor'' storage concept

  4. The effects of handling and storage on magnesium based implants — First results

    Energy Technology Data Exchange (ETDEWEB)

    Ullmann, Berit, E-mail: berit.ullmann@tiho-hannover.de [University of Veterinary Medicine, Small Animal Clinic, Bünteweg 9, 30559 Hannover (Germany); Angrisani, Nina, E-mail: nina.angrisani@tiho-hannover.de [University of Veterinary Medicine, Small Animal Clinic, Bünteweg 9, 30559 Hannover (Germany); Reifenrath, Janin, E-mail: janin.reifenrath@tiho-hannover.de [University of Veterinary Medicine, Small Animal Clinic, Bünteweg 9, 30559 Hannover (Germany); Seitz, Jan-M., E-mail: seitz@iw.uni-hannover.de [Leibniz University, Institute of Materials Science, An der Universität 2, 30823 Hannover (Germany); Bormann, Dirk, E-mail: dirk.bormann@trimet.de [Leibniz University, Institute of Materials Science, An der Universität 2, 30823 Hannover (Germany); Trimet Aluminium AG, Automotive, Recycling Harzgerode, Aluminiumallee 1, 06493 Harzgerode (Germany); Bach, Friedrich-Wilhelm, E-mail: bach@iw.uni-hannover.de [Leibniz University, Institute of Materials Science, An der Universität 2, 30823 Hannover (Germany); Meyer-Lindenberg, Andrea, E-mail: meyer-lindenberg@chir.vetmed.uni-muenchen.de [University of Veterinary Medicine, Small Animal Clinic, Bünteweg 9, 30559 Hannover (Germany); Clinic for Small Animal Surgery and Reproduction, Centre of Clinical Veterinary Medicine, Faculty of Veterinary Medicine, Ludwig-Maximilians-Universität München, Veterinärstraße 3, 80539 München (Germany)

    2013-07-01

    The present work aimed to investigate the influence of acetone and formalin as well as the duration and type of storage on magnesium based implants by means of microscopic, μ-computed tomographic, scanning electron microscopic, EDX and metallographic investigations. In contrast to storing in acetone, storage in formalin led to an increase in surface to volume ratio, and a decrease of the volume and the density. The various types of storage exerted no differing effects on the implants but with increasing storage duration, a spreading of oxygen rich areas on the surface, increased precipitations and a decrease in grain size could be observed. - Highlights: • Acetone treatment had no detectable effect on magnesium based implants. • Formalin caused distinct changes of the implant's surface, volume and density. • Storage types had no differing effect on the implants. • Storage duration led to distinct changes of the implant's surface and structure.

  5. Conceptual design of the handling and storage system of the spent target vessel for neutron scattering facility 2

    International Nuclear Information System (INIS)

    Adachi, Junichi; Kaminaga, Masanori; Sasaki, Shinobu; Haga, Katsuhiro; Aso, Tomokazu; Kinoshita, Hidetaka; Hino, Ryutaro

    2002-01-01

    In designing the neutron scattering facility, a spent target vessel should be replaced with remote handling devices in order to protect radioactive exposure, since it would be highly activated through the high energy neutron irradiation caused by the spallation reaction between mercury of the target material and the MW-class proton beam. In the storage of the spent target vessel, it is necessary to consider decay heat of the target vessel and mercury contamination caused by vaporization of the residual mercury in the vessel. A conceptual design has been carried out to establish basic concept and to clarify its specification of main equipments on handling and storage systems for the spent target vessel. This report presents the basic concept and a system plot plan based on latest design works of remote handling devices such as a spent target vessel storage cask and a target vessel exchange trolley, which aim at reasonability and simplification. In addition, storage systems for the spent moderator vessel, the spent proton beam window and the spent reflector vessel are also investigated based on the plot plan. (author)

  6. Nitrous oxide emissions from manure handling - effects of storage conditions and climate

    International Nuclear Information System (INIS)

    Sommer, S.G.; Petersen, S.O.

    2002-01-01

    Stored animal manure and manure applied in the field contributes an estimated 20% to the total anthropogenic emissions of nitrous oxide (N 2 0) in Denmark. Manure composition, handling and climatic conditions may all influence the emission level during storage, but there are relatively few experimental data on emissions of N 2 0 from manure management, including animal houses, slurry stores and manure heaps. Among animal housing systems, very high emission rates have been found with pig deep lifter, and N 2 0 emissions are further stimulated by mechanical mixing. Slurry stores are anaerobic, but a recent study showed that N 2 0 can be produced in porous surface covers such as natural surface crusts, straw or leca pebbles, while no N 2 0 was emitted from uncovered slurry. The emission was significantly related to the water balance, i.e., the difference between evaporation and rain, during dry periods; during wet periods no N 2 0 was emitted. For solid manure, previous studies have typically found that less than 1 % of total N is emitted as N 2 0. Nitrous oxide may be produced throughout the manure heap, provided an environment with both aerobic and anaerobic pockets exists. Profiles from an experimental heap indicated that most of the N 2 0 emitted from solid manure was produced near the surface of the heap. Increasing density appears to stimulate N 2 0 emissions up to a point, where the air exchange is significantly impeded. The IPCC methodology calculates N 2 0 emissions from manure on the basis of total N content (that is, on the basis of volume) and climate region only. Possibly, estimates of N 2 0 emissions from slurry stores could be improved by considering surface area, ammonium content and water balance as input variables. Emissions from solid manure heaps should consider surface area and the potential for composting, as reflected in bulk density and moisture content. (au)

  7. Fire protection considerations in the design of plutonium handling and storage facility

    International Nuclear Information System (INIS)

    Blanchard, A.

    2000-01-01

    Unwanted fire in a facility that handles plutonium must be addressed early in the facility design. Such fires have the potential for transporting radioactive contamination throughout the building and widespread downwind dispersal. Features that mitigate such events can be severely challenged during the fire. High temperatures can cause storage containers to burst; a very efficient dispersal mechanism for radioactive contamination. The fire will also establish ventilation patterns that cause the migration of smoke and radioactive contamination throughout the facility. The smoke and soot generated by the fire will enter the exhaust system and travel to the filtration system where it will deposit on the filters. The quantity of smoke generated during a typical multi-room fire is expected to blind most High Efficiency Particulate Airfilter (HEPA) media. The blinding can have two possible outcomes. (1) The air movement though the facility is reduced, compromising the negative pressure containment and allowing contamination to leave the building though doors and other openings; or (2) the filters collapse allowing the contamination to bypass the filtration media and exit the building through the filter plenum. HEPA filter blinding during severe fires can be prevented or mitigated. Increasing the face surface area of HEPA filters will increase the smoke filtration capacity of the system, thus preventing blinding. As an alternative sandfilters can be provided to mitigate the effects of the HEPA filter bypass. Both concepts have distinct advantages. This paper will explore these two design concepts and two others; it will describe the design requirements necessary for each concept to prevent unacceptable contamination spread. The intent is to allow the filter media selection to be based on a comprehensive understanding of the four different design concepts

  8. Handling and storage of high-level radioactive liquid wastes requiring cooling

    International Nuclear Information System (INIS)

    1979-01-01

    The technology of high-level liquid wastes storage and experience in this field gained over the past 25 years are reviewed in this report. It considers the design requirements for storage facilities, describes the systems currently in use, together with essential accessories such as the transfer and off-gas cleaning systems, and examines the safety and environmental factors

  9. 78 FR 78393 - Standard on the Storage and Handling of Anhydrous Ammonia; Extension of the Office of Management...

    Science.gov (United States)

    2013-12-26

    ...OSHA solicits public comments concerning its proposal to extend OMB approval of the information collection requirements specified in the Storage and Handling of Anhydrous Ammonia Standard (29 CFR 1910.111). Paragraphs (b)(3) and (b)(4) of the Standard have paperwork requirements that apply to non-refrigerated containers and systems and refrigerated containers, respectively; employers use these containers and systems to store and transfer anhydrous ammonia in the workplace.

  10. Handling of spent nuclear fuel and final storage of vitrified high level reprocessing waste

    International Nuclear Information System (INIS)

    1978-01-01

    A summary of the planning of transportation and plant design in the Swedish KBS project on management and disposal reprocessed radioactive waste. It describes a transportation system, a central storage facility for used fuel elements, a plant for intermediate storage and encapsulation and a final repository for the vitrified waste. Accounts are given for the reprocessing and vitrification. The safety of the entire system is discussed

  11. Design and safety evaluation of radioactive gas handling and storage in the FFTF

    International Nuclear Information System (INIS)

    Armstrong, G.R.; Hale, J.P.; Halverson, T.G.

    1976-01-01

    During the operation of the Fast Flux Test Facility (FFTF), radioactive gases, primarily xenon and krypton, will be produced which will require processing and storing. Two systems have been installed in the FFTF for handling these gases: (1) one to handle, primarily, the reactor cover gas system, and (2) a second to handle the cells and cover gas systems, other than the reactor, whose atmosphere may become contaminated. The system that processes the reactor cover gas, which is argon, is called the Radioactive Argon Processing System (RAPS). The effluent argon from RAPS will normally be sufficiently decontaminated to allow its reuse as the reactor cover gas. If the radioactive level in the RAPS becomes too high, the exhaust stream will be diverted to the Cell Atmosphere Processing System (CAPS), a system which can function as a backup to RAPS. The design and operation of the RAPS and CAPS systems are described and certain safety aspects of the systems are discussed. It is shown that these systems adequately provide the cleanup services required and that they provide the safety margins necessary to assure adequate safety to the public

  12. Food irradiation in the control of storage and handling losses in the Philippine onions and garlic

    International Nuclear Information System (INIS)

    Lustre, A.O.; Dianco, A.M.; Vito, F.R.; Manalastas, Z.L.

    1996-01-01

    Information will be provided on the nature and magnitude of the control of postharvest losses in onions and garlic from the application of irradiation. Control of losses is measured in storage and during post storage marketing of the commodities. Information will also be presented on market tests and survey of consumer reaction to irradiated onions. The benefits of irradiation will be discussed in relation to the need to reduce postharvest losses in the food supply and to address consumer concerns over the safety of food due to the use of chemicals. (author)

  13. Supply, storage and handling of elemental sulfur derived from sour gas

    International Nuclear Information System (INIS)

    Clark, P.D.; Davis, P.M.; Dowling, N.I.; Calgary Univ., AB

    2003-01-01

    This presentation reviews the supply picture for solid elemental sulfur. It also assesses methods for its storage as well as the disposal of the precursor hydrogen sulfide (H 2 S) by acid gas injection. Both above and below ground block storage is considered environmentally acceptable for sulfur storage as long as measures are taken to minimize the physical and biological breakdown of the sulfur. The preferred option is to store solid elemental sulfur underground, particularly if it is to remain in storage for a prolonged period. Future changes in supply of sulfur will likely be controlled by incremental production of sour gas and utilization of oil sands bitumen. It is expected that future sulfur production from conventional crude oil will remain static or will slowly decrease. The degree to which acid gas injection is applied to large sour gas developments in the Middle East and the Caspian regions will have a significant impact on world sulfur supply. 9 refs., 1 tab., 5 figs

  14. Handling of spent nuclear fuel and final storage of vitrified high level reprocessing waste

    International Nuclear Information System (INIS)

    1978-01-01

    The report gives a general summary of the Swedish KBS-project on management and disposal of vitrified reprocessed waste. Its final aim is to demostrate that the means of processing and managing power reactor waste in an absolutely safe way, as stipulated in the Swedish so called Conditions Act, already exist. Chapters on Storage facility for spent fuel, Intermidiate storage of reprocessed waste, Geology, Final repository, Transportation, Protection, and Siting. (L.E.)

  15. Handling final storage of unreprocessed spent nuclear fuel

    International Nuclear Information System (INIS)

    1978-01-01

    The present second report from KBS describes how the safe final storage of spent unreprocessed nuclear fuel can be implemented. According to the Swedish Stipulation Law, the owner must specify in which form the waste is to be stored, how final storage is to be effected, how the waste is to be transported and all other aspects of fuel handling and storage which must be taken into consideration in judging whether the proposed final storage method can be considered to be absolutely safe and feasible. Thus, the description must go beyond general plans and sketches. The description is therefore relatively detailed, even concerning those parts which are less essential for evaluating the safety of the waste storage method. For those parts of the handling chain which are the same for both alternatives of the Stipulation Law, the reader is referred in some cases to the first report. Both of the alternatives of the Stipulation Law may be used in the future. Handling equipment and facilities for the two storage methods are so designed that a combination in the desired proportions is practically feasible. In this first part of the report are presented: premises and data, a description of the various steps of the handling procedure, a summary of dispersal processes and a safety analysis. (author)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2010-02-02

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

  17. Waste handling and storage in the decontamination pilot projects of JAEA for environments of Fukushima

    Energy Technology Data Exchange (ETDEWEB)

    Nakayama, S.; Kawase, K.; Iijima, K.; Kato, M. [Fukushima Environmental Safety Center, Headquarters of Fukushima Partnership Operations, Japan Atomic Energy Agency, Fukushima (Japan)

    2013-07-01

    After the Fukushima Daiichi nuclear accident, Japan Atomic Energy Agency (JAEA) was chosen by the national government to conduct decontamination pilot projects at selected sites in Fukushima prefecture. Despite tight boundary conditions in terms of timescale and resources, the projects served their primary purpose to develop a knowledge base to support more effective planning and implementation of stepwise regional remediation of the evacuated zone. A range of established, modified and newly developed techniques were tested under realistic field conditions and their performance characteristics were determined. The results of the project can be summarized in terms of site characterization, cleanup and waste management. A range of options were investigated to reduce the volumes of waste produced and to ensure that decontamination water could be cleaned to the extent that it could be discharged to normal drainage. Resultant solid wastes were packaged in standard flexible containers, labelled and stored at the remediation site (temporary storage until central interim storage becomes available). The designs of such temporary storage facilities were tailored to available sites, but all designs included measures to ensure mechanical stability (e.g., filling void spaces between containers with sand, graded cover with soil) and prevent releases to groundwater (impermeable base and cap, gravity flow drainage including radiation monitors and catch tanks). Storage site monitoring was also needed to check that storage structures would not be perturbed by external events that could include typhoons, heavy snowfalls, freeze/thaw cycles and earthquakes. (authors)

  18. European Model Code of safe practice in the storage and handling of petroleum products. Part I. Operations

    Energy Technology Data Exchange (ETDEWEB)

    1973-01-01

    This safe practice code was prepared by a working group consisting of experts from 10 Western European countries. It consists of short guidelines and technical advice on general precautions, injuries and medical services, permits to work, fire prevention and fighting, jetties, pipework, storage tanks, static electricity, electrical equipment, road vehicles, tank cars, handling of bitumen products, liquefied petroleum gases, packed products and training of personnel. The code is supplemented by 10 appendices, including a suggested syllabus for a 2-day course on fire prevention and emergency action for managers of oil installations.

  19. Radiological safety aspects associated with the handling, storage and disposal of self power neutron detectors in TAPS - 3 and 4

    International Nuclear Information System (INIS)

    Parida, B.K.; Mudgal, B.; Ghadigoankar, V.R.; Niraj; Ashok; Pati, C.K.; Patil, P.M.; Pawar, S.K.; Varadhan, R.S.

    2006-01-01

    At Tarapur Atomic Power Station 3 and 4, 540 MWe Pressurised Heavy Water Reactors, core being large in size requires a continuous in core monitoring for local flux disturbances. Nearly 200 Self Powered Neutron Detectors (SPNDs) of the Straight Individually Replaceable (SIR) type are distributed in the reactor core. For purpose of reactor regulation and protection, cobalt SPNDs that have a prompt response for changes in power is used for in-core flux mapping, vanadium SPNDs that provide accurate measure of neutron flux, even though having slow response is used In core SPNDs are placed in Vertical Flux Units (VFU) and Horizontal Flux Units (HFUs). These SPNDs were to be replaced at regular intervals to meet the design intent. Cobalt SPNDs have dose rates of the order of 1000 Gy/h and the Mineral Insulated (MI) cables of Vanadium SPNDs have dose rates of the order of 100 Gy/h. So far 3 Cobalt SPNDs were removed from HFUs and are being stored in lead shielding inside spent fuel storage facility. These high active components were handled with meticulous planning with lowest exposures to the maintainers. Radiological safety aspects of handling and storage of SPNDs are discussed in this report. (author)

  20. PFP Commercial Grade Food Pack Cans for Plutonium Handling and Storage Critical Characteristics

    International Nuclear Information System (INIS)

    BONADIE, E.P.

    1999-01-01

    This document specifies the critical characteristics for Commercial Grade Items (CGI) procured for PFP's Vault Operations system as required by HNF-PRO-268 and HNF-PRO-1819. These are the minimum specifications that the equipment must meet in order to perform its safety function. The changes in these specifications have no detrimental effect on the descriptions and parameters related to handling plutonium solids in the authorization basis. Because no parameters or sequences exceed the limits described in the authorization bases, no accident or abnormal conditions are affected. The specifications prescribed in this critical characteristics document do not represent an unreviewed safety question

  1. Influence of development, postharvest handling, and storage conditions on the carbohydrate components of sweetpotato (Ipomea batatas Lam.) roots.

    Science.gov (United States)

    Nabubuya, Agnes; Namutebi, Agnes; Byaruhanga, Yusuf; Narvhus, Judith; Wicklund, Trude

    2017-11-01

    Changes in total starch and reducing sugar content in five sweetpotato varieties were investigated weekly during root development and following subjection of the roots to different postharvest handling and storage conditions. Freshly harvested (noncured) roots and cured roots (spread under the sun for 4 days at 29-31°C and 63-65% relative humidity [RH]) were separately stored at ambient conditions (23°C-26°C and 70-80% RH) and in a semiunderground pit (19-21°C and 90-95% RH). Changes in pasting properties of flour from sweetpotato roots during storage were analyzed at 14-day intervals. Significant varietal differences ( p  < .05) in total starch, sucrose, glucose, maltose, and fructose concentrations were registered. The total starch and sucrose content of the roots did not change significantly ( p  < .05) during root development (72.4 and 7.4%, respectively), whereas the average concentrations of glucose, maltose, and fructose decreased markedly (0.46-0.18%, 0.55-0.28%, and 0.43-0.21%), respectively. Storage led to decrease in total starch content (73-47.7%) and increase in sucrose and glucose concentrations (8.1-11.2% and 0.22-1.57%, respectively). Storage also resulted in reduction in sweetpotato flour pasting viscosities. Curing resulted in increased sucrose and glucose concentrations (9.1-11.2% and 0.45-0.85%, respectively) and marked reduction ( p  < .05) in total starch content (72.9-47.6%). This resulted in low pasting viscosities compared to flour from storage of uncured roots. These findings show that significant changes occur in the carbohydrate components of sweetpotato roots during storage compared to development and present an opportunity for diverse utilization of flours from sweetpotato roots in the food industry.

  2. The UK Biobank sample handling and storage protocol for the collection, processing and archiving of human blood and urine.

    Science.gov (United States)

    Elliott, Paul; Peakman, Tim C

    2008-04-01

    UK Biobank is a large prospective study in the UK to investigate the role of genetic factors, environmental exposures and lifestyle in the causes of major diseases of late and middle age. Extensive data and biological samples are being collected from 500,000 participants aged between 40 and 69 years. The biological samples that are collected and how they are processed and stored will have a major impact on the future scientific usefulness of the UK Biobank resource. The aim of the UK Biobank sample handling and storage protocol is to specify methods for the collection and storage of participant samples that give maximum scientific return within the available budget. Processing or storage methods that, as far as can be predicted, will preclude current or future assays have been avoided. The protocol was developed through a review of the literature on sample handling and processing, wide consultation within the academic community and peer review. Protocol development addressed which samples should be collected, how and when they should be processed and how the processed samples should be stored to ensure their long-term integrity. The recommended protocol was extensively tested in a series of validation studies. UK Biobank collects about 45 ml blood and 9 ml of urine with minimal local processing from each participant using the vacutainer system. A variety of preservatives, anti-coagulants and clot accelerators is used appropriate to the expected end use of the samples. Collection of other material (hair, nails, saliva and faeces) was also considered but rejected for the full cohort. Blood and urine samples from participants are transported overnight by commercial courier to a central laboratory where they are processed and aliquots of urine, plasma, serum, white cells and red cells stored in ultra-low temperature archives. Aliquots of whole blood are also stored for potential future production of immortalized cell lines. A standard panel of haematology assays is

  3. BWR spent fuel storage cask performance test. Volume 1. Cask handling experience and decay heat, heat transfer, and shielding data

    International Nuclear Information System (INIS)

    McKinnon, M.A.; Doman, J.W.; Tanner, J.E.; Guenther, R.J.; Creer, J.M.; King, C.E.

    1986-02-01

    This report documents a heat transfer and shielding performance test conducted on a Ridihalgh, Eggers and Associates REA 2023 boiling water reactor (BWR) spent fuel storage cask. The testing effort consisted of three parts: pretest preparations, performance testing, and post-test activities. Pretest preparations included conducting cask handling dry runs and characterizing BWR spent fuel assemblies from Nebraska Public Power District's Cooper Nuclear Station. The performance test matrix included 14 runs consisting of two loadings, two cask orientations, and three backfill environments. Post-test activities included calorimetry and axial radiation scans of selected fuel assemblies, in-basin sipping of each assembly, crud collection, video and photographic scans, and decontamination of the cask interior and exterior

  4. Handling and Transport Problems

    Energy Technology Data Exchange (ETDEWEB)

    Pomarola, J. [Head of Technical Section, Atomic Energy Commission, Saclay (France); Savouyaud, J. [Head of Electro-Mechanical Sub-Division, Atomic Energy Commission, Saclay (France)

    1960-07-01

    Arrangements for special or dangerous transport operations by road arising out of the activities of the Atomic Energy Commission are made by the Works and Installations Division which acts in concert with the Monitoring and Protection Division (MPD) whenever radioactive substances or appliances are involved. In view of the risk of irradiation and contamination entailed in handling and transporting radioactive substances, including waste, a specialized transport and storage team has been formed as a complement to the emergency and decontamination teams.

  5. Atlantic salmon skin and fillet color changes effected by perimortem handling stress, rigor mortis, and ice storage.

    Science.gov (United States)

    Erikson, U; Misimi, E

    2008-03-01

    The changes in skin and fillet color of anesthetized and exhausted Atlantic salmon were determined immediately after killing, during rigor mortis, and after ice storage for 7 d. Skin color (CIE L*, a*, b*, and related values) was determined by a Minolta Chroma Meter. Roche SalmoFan Lineal and Roche Color Card values were determined by a computer vision method and a sensory panel. Before color assessment, the stress levels of the 2 fish groups were characterized in terms of white muscle parameters (pH, rigor mortis, and core temperature). The results showed that perimortem handling stress initially significantly affected several color parameters of skin and fillets. Significant transient fillet color changes also occurred in the prerigor phase and during the development of rigor mortis. Our results suggested that fillet color was affected by postmortem glycolysis (pH drop, particularly in anesthetized fillets), then by onset and development of rigor mortis. The color change patterns during storage were different for the 2 groups of fish. The computer vision method was considered suitable for automated (online) quality control and grading of salmonid fillets according to color.

  6. Viability of Existing INL Facilities for Dry Storage Cask Handling

    Energy Technology Data Exchange (ETDEWEB)

    Bohachek, Randy; Wallace, Bruce; Winston, Phil; Marschman, Steve

    2013-04-30

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

  7. Viability of Existing INL Facilities for Dry Storage Cask Handling

    Energy Technology Data Exchange (ETDEWEB)

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

    2013-04-01

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

  8. Final Generic Environmental Impact Statement. Handling and storage of spent light water power reactor fuel. Volume 1. Executive summary and text

    International Nuclear Information System (INIS)

    1979-08-01

    The Generic Environmental Impact Statement on spent fuel storage was prepared by the Nuclear Regulatory Commission staff in response to a directive from the Commissioners published in the Federal Register, September 16, 1975 (40 FR 42801). The Commission directed the staff to analyze alternatives for the handling and storage of spent light water power reactor fuel with particular emphasis on developing long range policy. Accordingly, the scope of this statement examines alternative methods of spent fuel storage as well as the possible restriction or termination of the generation of spent fuel through nuclear power plant shutdown. Volume 1 includes the executive summary and the text

  9. Time and dose assessment of barge shipment and at-reactor handling of a CASTOR V/21 spent fuel storage cask

    Energy Technology Data Exchange (ETDEWEB)

    Hostick, C.J. (Pacific Northwest Lab., Richland, WA (United States)); Lavender, J.C. (Westinghouse Hanford Co., Richland, WA (United States)); Wakeman, B.H. (Virginia Electric and Power Co., Richmond, VA (United States))

    1992-04-01

    This report contains the results of a time/motion analysis and a radiation dose assessment made during the receipt from barge transport and the loading of CAst iron cask for Storage and Transport Of Radioactive material (CASTOR) V/21 storage casks with spent nuclear fuel at the Surry Power Station in Virginia during 1987. The study was a cooperative effort between Pacific Northwest Laboratory (PNL) and Virginia Electric and Power Company (Virginia Power), and was funded by the US Department of Energy (DOE) Transportation Program Office. In this study, cask handling activities were tracked at the Surry Power Station, tracing the transfer of the empty spent fuel storage cask from an ocean-going vessel to a barge for river transport through the activities required to place the loaded storage cask at an at-reactor storage location.

  10. Handling of final storage of unreprocessed spent nuclear fuel

    International Nuclear Information System (INIS)

    1978-01-01

    In this report the various facilities incorporated in the proposed handling chain for spent fuel from the power stations to the final repository are discribed. Thus the geological conditions which are essential for a final repository is discussed as well as the buffer and canister materials and how they contribute towards a long-term isolation of the spent fuel. Furthermore one chapter deals with leaching of the deposited fuel in the event that the canister is penetrated as well as the transport mechanisms which determine the migration of the radioactive substances through the buffer material. The dispersal processes in the geosphere and the biosphere are also described together with the transfer mechanisms to the ecological systems as well as radiation doses. Finally a summary is given of the safety analysis of the proposed method for the handling and final storage of the spent fuel. (E.R.)

  11. Chemical Safety Alert: Safe Storage and Handling of Swimming Pool Chemicals

    Science.gov (United States)

    Hazards of pool water treatment and maintenance chemicals (e.g., chlorine), and the protective measures pool owners should take to prevent fires, toxic vapor releases, and injuries. Triggered by improper wetting, mixing, or self-reactivity over time.

  12. Tree seed handling, processing, testing, and storage at Hayward State Nursery, Wisconsin Department of Natural Resources

    Science.gov (United States)

    Gordon Christians

    2008-01-01

    The Hayward State Nursery, Wisconsin grows more than 40 species from seeds. Up to 6000 bushels of raw unprocessed tree and shrub seeds are collected each year, and all seeds are collected in Wisconsin or adjacent states. All white spruce (Picea glauca) and some white pine seeds (Pinus strobus) are collected from orchards containing...

  13. WET TORREFACTION OF MISCANTHUS – CHARACTERIZATION OF HYDROCHARS IN VIEW OF HANDLING, STORAGE AND COMBUSTION PROPERTIES

    Directory of Open Access Journals (Sweden)

    Mateusz Wnukowski

    2015-06-01

    Full Text Available Properties of miscanthus hydrochars obtained through wet torrefaction were studied. The process was carried out in three different temperatures – 180, 200 and 220 °C and with four different ratios of water to biomass – 3:1, 6:1, 12:1 and 16:1. The obtained solid products were characterized with respect to their fuel properties. The best results were obtained for the temperature of 220 °C and showed a noticeable improvement in fuel properties – especially grindability and lowered ash content. The influence of water to biomass ratio was not so explicit and while high ratio showed an improvement in all mentioned properties, low ratio allowed to achieve the highest energy yield. The results obtained for miscanthus wet torrefaction and the literature data for dry torrefaction were compared.

  14. Handling and storage of high-level liquid wastes from reprocessing of spent fuel

    International Nuclear Information System (INIS)

    Finsterwalder, L.

    1982-01-01

    The high level liquid wastes arise from the reprocessing of irradiated nuclear fuels, which are dissolved in aqueous acid solution, and the plutonium and unburned uranium removed in the chemical separation plant. The remaining solution, containing more than 99% of the dissolved fission products, together with impurities from cladding materials, corrosion products, traces of unseparated plutonium and uranium and most of the transuranic elements, constitutes the high-level waste. At present, these liquid wastes are usually concentrated by evaporation and stored as an aqueous nitric acid solution in high-integrity stainless-steel tanks. There is now world-wide agreement that, for the long term, these liquid wastes should be converted to solid form and much work is in progress to develop techniques for the solidification of these wastes. This paper considers the design requirements for such facilities and the experience gained during nearly 30 years of operation. (orig./RW)

  15. Review of the KBS II plan for handling and final storage of unreprocessed spent nuclear fuel

    International Nuclear Information System (INIS)

    1980-01-01

    The Swedish utilities programme for disposal of spent nuclear fuel elements (KBS II) is summarized. Comments and criticism to the programme are given by experts from several foreign or international institutions. (L.E.)

  16. Characterization of Emissions from Building Products: Selection Criteria, Storage and Handling of Indoor Materials for Experiments

    DEFF Research Database (Denmark)

    Kjær, Ulla Dorte; Nielsen, Peter A.; Marcussen, Lis

    1996-01-01

    In research projects it is usually impossible to study more than a very limited aount of different products. Care and consideration must therefore be taken in the selection. The following criteria were used to select five products for chemical and sensory emission testing: The products should...... be indoor climate relevant, meaning that they should be in direct contact with indoor air when used in buildings, and their emission should contribute significantly to the indoor air concentrations for instance due to a large surface area. They should be representative in terms of being widely used, now...... that the emission mechanisms do not change as a consequence of physical processes or chemical reactions. The five products selected were PVC flooring, waterborne varnish on beechwood parquet, carpet, sealant, and waterborne paint on gypsum board. The products were brought to the laboratory immediately after...

  17. PFP Commercial Grade Food Pack Cans for Plutonium Handling and Storage Critical Characteristics

    International Nuclear Information System (INIS)

    BONADIE, E.P.

    1999-01-01

    This document specifies the critical characteristics for Commercial Grade Items (CGI) procured for PFP's Vault Operations system as required by HNF-PRO-268 and HNF-PRO-1819. These are the minimum specifications that the equipment must meet in order to perform its safety function

  18. 29 CFR 1910.110 - Storage and handling of liquefied petroleum gases.

    Science.gov (United States)

    2010-07-01

    ... fueled industrial trucks used in accordance with paragraph (e)(13) of this section. (e) LP-Gas fueled..., and to commercial gas plants or bulk stations where containers are charged, nor to industrial... mixing, gas manufacturing, or distribution, or to house internal combustion engines, industrial processes...

  19. PFP vault operations containers for Plutonium Handling and Storage Critical Characteristics

    International Nuclear Information System (INIS)

    BONADIE, E.P.

    2000-01-01

    This document specifies the critical characteristics for containers procured for Plutonium Finishing Plant's (PFP's) Vault Operations system as required by HNF-PRO-268 and HNF-PRO-1819. These are the minimum specifications that the equipment must meet in order to perform its safety function

  20. Storage and Materials Handling

    Science.gov (United States)

    1979-09-01

    18 9 Beef, instant , dehydrated ..... Pkg 24 12 6 Beef, noodle , dehydrated ...... Pkg 24 12 6 Beef, vegetable, noodle , dehy- drated... noodle , dehydrated . Can 60 30 15 .............. Pkg 24 12 6 Condensed" ....................... Can 72 36 18 Cream of onion, instant , dehy- drated...6 Onion, instant , dehydrated ... Pkg 24 12 6 Ready to serve ................... Can 48 24 12 Tomato-vegetable w/ noodle , dehydrated

  1. Technology Development And Deployment Of Systems For The Retrieval And Processing Of Remote-Handled Sludge From Hanford K-West Fuel Storage Basin

    International Nuclear Information System (INIS)

    Raymond, R.E.

    2011-01-01

    In 2011, significant progress was made in developing and deploying technologies to remove, transport, and interim store remote-handled sludge from the 105-K West Fuel Storage Basin on the Hanford Site in south-central Washington State. The sludge in the 105-K West Basin is an accumulation of degraded spent nuclear fuel and other debris that collected during long-term underwater storage of the spent fuel. In 2010, an innovative, remotely operated retrieval system was used to successfully retrieve over 99.7% of the radioactive sludge from 10 submerged temporary storage containers in the K West Basin. In 2011, a full-scale prototype facility was completed for use in technology development, design qualification testing, and operator training on systems used to retrieve, transport, and store highly radioactive K Basin sludge. In this facility, three separate systems for characterizing, retrieving, pretreating, and processing remote-handled sludge were developed. Two of these systems were successfully deployed in 2011. One of these systems was used to pretreat knockout pot sludge as part of the 105-K West Basin cleanup. Knockout pot sludge contains pieces of degraded uranium fuel ranging in size from 600 μm to 6350 μm mixed with pieces of inert material, such as aluminum wire and graphite, in the same size range. The 2011 pretreatment campaign successfully removed most of the inert material from the sludge stream and significantly reduced the remaining volume of knockout pot product material. Removing the inert material significantly minimized the waste stream and reduced costs by reducing the number of transportation and storage containers. Removing the inert material also improved worker safety by reducing the number of remote-handled shipments. Also in 2011, technology development and final design were completed on the system to remove knockout pot material from the basin and transport the material to an onsite facility for interim storage. This system is scheduled

  2. Generic environmental impact statement on handling and storage of spent light water power reactor fuel. Executive summary and text

    International Nuclear Information System (INIS)

    1978-03-01

    The study covers the following: (1) The magnitude of the possible shortage of spent fuel storage capacity; (2) The options for dealing with the problem; (3) A cost-benefit analysis of the alternatives; (4) The impacts of possible additional transportation of spent fuel that may be required should one or more of the options be adopted; (5) The need for more definitive regulations and guidance covering the licensing of one or more of the options for dealing with the problem; and (6) The possible need for amendments to 10 CFR 51.20(e). The scope of this study is limited to considerations pertinent to the interim storage of spent fuel

  3. Safe handling, transport and storage of plutonium. Proceedings of a technical committee meeting held in Vienna, 18-21 October 1993

    International Nuclear Information System (INIS)

    1994-10-01

    Plutonium inventories and utilization rates worldwide are growing. It is important for nuclear power programmes everywhere that no incidents or accidents with plutonium occur. It is therefore important that all who deal with plutonium, do so safely. All those who deal with plutonium should have available the best information on safety handling and storage. Several countries have mature plutonium programmes. However, information exchange on plutonium has been limited. This has precluded the development until now of consensus documentation on safe handling and storage of plutonium. The Technical Committee has been established to address these problems and this Technical Document is the first product in this process. The purpose of the meeting was to bring together experts with significant experience in handling, transporting and storing plutonium; to exchange information and experiences dealing with plutonium at their facilities; to describe their practices (guidelines, procedures, regulations, etc.) for safely dealing with plutonium; to assess the need to develop and publish a consensus plutonium safety practices document(s), and to recommend possible future IAEA activities in this technical area. Refs, figs and tabs

  4. Handling of bulk solids theory and practice

    CERN Document Server

    Shamlou, P A

    1990-01-01

    Handling of Bulk Solids provides a comprehensive discussion of the field of solids flow and handling in the process industries. Presentation of the subject follows classical lines of separate discussions for each topic, so each chapter is self-contained and can be read on its own. Topics discussed include bulk solids flow and handling properties; pressure profiles in bulk solids storage vessels; the design of storage silos for reliable discharge of bulk materials; gravity flow of particulate materials from storage vessels; pneumatic transportation of bulk solids; and the hazards of solid-mater

  5. Ergonomics and patient handling.

    Science.gov (United States)

    McCoskey, Kelsey L

    2007-11-01

    This study aimed to describe patient-handling demands in inpatient units during a 24-hour period at a military health care facility. A 1-day total population survey described the diverse nature and impact of patient-handling tasks relative to a variety of nursing care units, patient characteristics, and transfer equipment. Productivity baselines were established based on patient dependency, physical exertion, type of transfer, and time spent performing the transfer. Descriptions of the physiological effect of transfers on staff based on patient, transfer, and staff characteristics were developed. Nursing staff response to surveys demonstrated how patient-handling demands are impacted by the staff's physical exertion and level of patient dependency. The findings of this study describe the types of transfers occurring in these inpatient units and the physical exertion and time requirements for these transfers. This description may guide selection of the most appropriate and cost-effective patient-handling equipment required for specific units and patients.

  6. Development of safety-relevant components for the transport and handling of final storage casks for waste from decommissioning

    International Nuclear Information System (INIS)

    Bruening, D.; Geiser, H.; Kloeckner, F.; Rittscher, D.; Schlesinger, H.J.

    1992-10-01

    The aim of the study was the development, construction and testing of a transportation system that is able to transport cylindrical waste containers as well as containers from the deliverer to the 'KONRAD' final repository. A transport palette has been developed that can carry two cylindrical waste containers with type B requirement or classification II. An Open-All-Container for the transport of palettes and 'KONRAD' containers has been developed. A storage of cylindrical waste containers and containers in the final repository is possible with the newly developed transportation system. Safety specifications of the transportation system have been passed successfully. (orig.). 30 refs., 8 tabs., 74 figs [de

  7. Comparison of methods for conducting marine and estuarine sediment porewater toxicity tests—extraction, storage, and handling techniques

    Science.gov (United States)

    Carr, R.S.; Chapman, D.C.

    1995-01-01

    A series of studies was conducted to compare different porewater extraction techniques and to evaluate the effects of sediment and porewater storage conditions on the toxicity of pore water, using assays with the sea urchin Arbacia punctulata. If care is taken in the selection of materials, several different porewater extraction techniques (pressurized squeezing, centrifugation, vacuum) yield samples with similar toxicity. Where the primary contaminants of concern are highly hydrophobic organic compounds, centrifugation is the method of choice for minimizing the loss of contaminants during the extraction procedure. No difference was found in the toxicity of pore water obtained with the Teflon® and polyvinyl chloride pressurized extraction devices. Different types of filters in the squeeze extraction devices apparently adsorbed soluble contaminants to varying degrees. The amount of fine suspended particulate material remaining in the pore water after the initial extraction varied among the methods. For most of the sediments tested, freezing and thawing did not affect the toxicity of porewater samples obtained by the pressurized squeeze extraction method. Pore water obtained by other methods (centrifugation, vacuum) and frozen without additional removal of suspended particulates by centrifugation may exhibit increased toxicity compared with the unfrozen sample.The toxicity of pore water extracted from refrigerated (4°C) sediments exhibited substantial short-term (days, weeks) changes. Similarly, sediment pore water extracted over time from a simulated amphipod solid-phase toxicity test changed substantially in toxicity. For the sediments tested, the direction and magnitude of change in toxicity of pore water extracted from both refrigerated and solid-phase test sediments was unpredictable.

  8. Grain Grading and Handling.

    Science.gov (United States)

    Rendleman, Matt; Legacy, James

    This publication provides an introduction to grain grading and handling for adult students in vocational and technical education programs. Organized in five chapters, the booklet provides a brief overview of the jobs performed at a grain elevator and of the techniques used to grade grain. The first chapter introduces the grain industry and…

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

    International Nuclear Information System (INIS)

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

    1999-01-01

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

  10. Safety assessment document for spent fuel handling, packaging, and storage demonstrations at the E-MAD facility on the Nevada Test Site

    International Nuclear Information System (INIS)

    1985-04-01

    The objectives for spent fuel handling and packaging demonstration are to develop the capability to satisfactorily encapsulate typical commercial nuclear reactor spent fuel assemblies and to establish the suitability of interim dry surface and near surface storage concepts. To accomplish these objectives, spent fuel assemblies from a pressurized water reactor have been received, encapsulated in steel canisters, and emplaced in on-site storage facilities and subjected to other tests. As an essential element of these demonstrations, a thorough safety assessment of the demonstration activities conducted at the E-MAD facility has been completed. This document describes the site location and characteristics, the existing E-MAD facility, and the facility modifications and equipment additions made specifically for the demonstrations. The document also summarizes the Quality Assurance Program utilized, and specifies the principal design criteria applicable to the facility modifications, equipment additions, and process operations. Evaluations have been made of the radiological impacts of normal operations, abnormal operations, and postulated accidents. Analyses have been performed to determine the affects on nuclear criticality safety of postulated accidents and credible natural phenomena. The consequences of postulated accidents resulting in fission product gas release have also been estimated. This document identifies the engineered safety features, procedures, and site characteristics that (1) prevent the occurrence of potential accidents or (2) assure that the consequences of postulated accidents are either insignificant or adequately mitigated

  11. Method and equipment to prepare aqueous radioactive waste for non-polluting and safe handling, transport, and final storage

    Energy Technology Data Exchange (ETDEWEB)

    Drobmik, S; Hild, W; Kaufmann, F; Koschorke, H

    1977-09-15

    A system is proposed which allows the joint execution of the process steps of denitration, drying and calcination necessary for the treatment of radioactive waste and the subsequent injection of superheated water vapor into the reaction chamber so as to also clean the offgases produced and discharge them from the facility through a filter system without polluting the environment. Several design variants are described which mainly relate to the arrangement of the spray nozzle and its environment. The vitrified radioactive materials are then put into repositories.

  12. 7 CFR 1436.6 - Eligible storage or handling equipment.

    Science.gov (United States)

    2010-01-01

    ...) Electrical equipment, including labor and materials for installation, such as lighting, motors, and wiring... installation, such as lighting, motors, and wiring integral to the proper operation of the sugar storage and... materials for installation, such as lighting, motors, and wiring integral to the proper operation of a cold...

  13. 21 CFR 205.50 - Minimum requirements for the storage and handling of prescription drugs and for the establishment...

    Science.gov (United States)

    2010-04-01

    ... defined in an official compendium, to help ensure that its identity, strength, quality, and purity are not adversely affected. (2) Appropriate manual, electromechanical, or electronic temperature and humidity... examined for identity and to prevent the acceptance of contaminated prescription drugs or prescription...

  14. Coal handling/storage in a sensitive environment

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2005-04-01

    A leading Italian manufacturer Bedeschi has designed and built a coal handling plant for its Outao cement plant in an environmentally sensitive national park in Portugal, Setubal National Park. The receiving station is completely enclosed, to control dusts. The main 80 m{sup 3} hopper can receive several types of truck and an automatic dour seals off the receiving section as soon as the truck has left. Coals tend to be blended according to kiln requirements. A bucket-type reclaimer is used due to the sticky nature of the coal. 2 photos.

  15. Duration on the exposure control, spectra storage and texture goniometer handling in the software complex for the accumulation, control and supervising systems at the NSHR and the SKAT spectrometers (Tofa and Goni tasks)

    International Nuclear Information System (INIS)

    Kirilov, A.S.; Korobchenko, M.L.; Sirotin, A.P.; Heinitz, J.

    1997-01-01

    The VME-based accumulation, control and supervising system has been maintained at the NSHR spectrometer since March 1995. Another copy of system has been in use at the newly created SKAT spectrometer since April 1997. This paper is devoted to a detailed description of the user interface for the Join and the Tofa tasks which are dedicated to controlling the duration of the exposure, the spectra storage and handling the texture goniometer at the spectrometers. (author)

  16. 21 CFR 500.45 - Use of polychlorinated biphenyls (PCB's) in the production, handling, and storage of animal feed.

    Science.gov (United States)

    2010-04-01

    ... a class of toxic industrial chemicals manufactured and sold under a variety of trade names... highly stable, heat resistant, and nonflammable chemicals. Industrial uses of PCB's include, or did... and chemical properties and widespread, uncontrolled industrial applications have caused PCB's to be a...

  17. Harvesting and handling agricultural residues for energy

    Energy Technology Data Exchange (ETDEWEB)

    Jenkins, B.M.; Summer, H.R.

    1986-05-01

    Significant progress in understanding the needs for design of agricultural residue collection and handling systems has been made but additional research is required. Recommendations are made for research to (a) integrate residue collection and handling systems into general agricultural practices through the development of multi-use equipment and total harvest systems; (b) improve methods for routine evaluation of agricultural residue resources, possibly through remote sensing and image processing; (c) analyze biomass properties to obtain detailed data relevant to engineering design and analysis; (d) evaluate long-term environmental, social, and agronomic impacts of residue collection; (e) develop improved equipment with higher capacities to reduce residue collection and handling costs, with emphasis on optimal design of complete systems including collection, transportation, processing, storage, and utilization; and (f) produce standard forms of biomass fuels or products to enhance material handling and expand biomass markets through improved reliability and automatic control of biomass conversion and other utilization systems. 118 references.

  18. Survival or growth of inoculated Escherichia coli O157:H7 and Salmonella on yellow onions (Allium cepa) under conditions simulating food service and consumer handling and storage.

    Science.gov (United States)

    Lieberman, Vanessa M; Zhao, Irene Y; Schaffner, Donald W; Danyluk, Michelle D; Harris, Linda J

    2015-01-01

    Whole and diced yellow onions (Allium cepa) were inoculated with five-strain cocktails of rifampin-resistant Escherichia coli O157:H7 or Salmonella and stored under conditions to simulate food service or consumer handling. The inoculum was grown in broth (for both whole and diced onion experiments) or on agar plates (for whole onion experiments). Marked circles (3.3 cm in diameter) on the outer papery skin of whole onions were spot inoculated (10 μl in 10 drops) at 7 log CFU per circle, and onions were stored at 4°C, 30 to 50 % relative humidity, or at ambient conditions (23°C, 30 to 50 % relative humidity). Diced onions were inoculated at 3 log CFU/g and then stored in open or closed containers at 4°C or ambient conditions. Previously inoculated and ambient-stored diced onions were also mixed 1:9 (wt/wt) with refrigerated uninoculated freshly diced onions and stored in closed containers at ambient conditions. Inoculated pathogens were recovered in 0.1 % peptone and plated onto selective and nonselective media supplemented with 50 μg/ml rifampin. Both E. coli O157:H7 and Salmonella populations declined more rapidly on onion skins when the inoculum was prepared in broth rather than on agar. Agar-prepared E. coli O157:H7 and Salmonella declined by 0.4 and 0.3 log CFU per sample per day, respectively, at ambient conditions; at 4°C the rates of reduction were 0.08 and 0.06 log CFU per sample per day for E. coli O157:H7 and Salmonella, respectively. Populations of E. coli O157:H7 and Salmonella did not change over 6 days of storage at 4°C in diced onions. Lag times of 6 to 9 h were observed with freshly inoculated onion at ambient conditions; no lag was observed when previously inoculated and uninoculated onions were mixed. Growth rates at ambient conditions were 0.2 to 0.3 log CFU/g/h for E. coli O157:H7 and Salmonella in freshly inoculated onion and 0.2 log CFU/g/h in mixed product. Diced onions support pathogen growth and should be kept refrigerated.

  19. Remote handling and accelerators

    International Nuclear Information System (INIS)

    Wilson, M.T.

    1983-01-01

    The high-current levels of contemporary and proposed accelerator facilities induce radiation levels into components, requiring consideration be given to maintenance techniques that reduce personnel exposure. Typical components involved include beamstops, targets, collimators, windows, and instrumentation that intercepts the direct beam. Also included are beam extraction, injection, splitting, and kicking regions, as well as purposeful spill areas where beam tails are trimmed and neutral particles are deposited. Scattered beam and secondary particles activate components all along a beamline such as vacuum pipes, magnets, and shielding. Maintenance techniques vary from hands-on to TV-viewed operation using state-of-the-art servomanipulators. Bottom- or side-entry casks are used with thimble-type target and diagnostic assemblies. Long-handled tools are operated from behind shadow shields. Swinging shield doors, unstacking block, and horizontally rolling shield roofs are all used to provide access. Common to all techniques is the need to make operations simple and to provide a means of seeing and reaching the area

  20. New transport and handling contract

    CERN Multimedia

    SC Department

    2008-01-01

    A new transport and handling contract entered into force on 1.10.2008. As with the previous contract, the user interface is the internal transport/handling request form on EDH: https://edh.cern.ch/Document/TransportRequest/ To ensure that you receive the best possible service, we invite you to complete the various fields as accurately as possible and to include a mobile telephone number on which we can reach you. You can follow the progress of your request (schedule, completion) in the EDH request routing information. We remind you that the following deadlines apply: 48 hours for the transport of heavy goods (up to 8 tonnes) or simple handling operations 5 working days for crane operations, transport of extra-heavy goods, complex handling operations and combined transport and handling operations in the tunnel. For all enquiries, the number to contact remains unchanged: 72202. Heavy Handling Section TS-HE-HH 72672 - 160319

  1. Survey of tritiated oil sources and handling practices

    International Nuclear Information System (INIS)

    Miller, J.M.

    1994-08-01

    Tritium interactions with oil sources (primarily associated with pumps) in tritium-handling facilities can lead to the incorporation of tritium in the oil and the production of tritiated hydrocarbons. This results in a source of radiological hazard and the need for special handling considerations during maintenance, decontamination, decommissioning and waste packaging and storage. The results of a general survey of tritiated-oil sources and their associated characteristics, handling practices, analysis techniques and waste treatment/storage methods are summarized here. Information was obtained from various tritium-handling laboratories, fusion devices, and CANDU plants. 38 refs., 1 fig

  2. System for handling and storing radioactive waste

    Science.gov (United States)

    Anderson, John K.; Lindemann, Paul E.

    1984-01-01

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

  3. Handling, conditioning and storage of spent sealed radioactive sources. Technical manual for the management of low and intermediate level wastes generated at small nuclear research centres and by radioisotope users in medicine, research and industry

    International Nuclear Information System (INIS)

    2000-05-01

    This report is intended to provide reference material, guidance and know-how on handling, conditioning and storage of spent sealed radioactive sources (SRS) to both users of SRS and operators of waste management facilities. The scope of this report covers all types of SRS except those exempted from regulatory control. The report contains in some detail technical procedures for the conditioning of spent SRS, describes the means required to assure the quality of the resulting package and discusses the measures to prepare waste packages with a certain flexibility to accommodate possible future disposal requirements

  4. As-Built Verification Plan Spent Nuclear Fuel Canister Storage Building MCO Handling Machine

    International Nuclear Information System (INIS)

    SWENSON, C.E.

    2000-01-01

    This as-built verification plan outlines the methodology and responsibilities that will be implemented during the as-built field verification activity for the Canister Storage Building (CSB) MCO HANDLING MACHINE (MHM). This as-built verification plan covers THE ELECTRICAL PORTION of the CONSTRUCTION PERFORMED BY POWER CITY UNDER CONTRACT TO MOWAT. The as-built verifications will be performed in accordance Administrative Procedure AP 6-012-00, Spent Nuclear Fuel Project As-Built Verification Plan Development Process, revision I. The results of the verification walkdown will be documented in a verification walkdown completion package, approved by the Design Authority (DA), and maintained in the CSB project files

  5. Engineering Support for Handling Controller Conflicts in Energy Storage Systems Applications

    Directory of Open Access Journals (Sweden)

    Claudia Zanabria

    2017-10-01

    Full Text Available Energy storage systems will play a major role in the decarbonization of future sustainable electric power systems, allowing a high penetration of distributed renewable energy sources and contributing to the distribution network stability and reliability. To accomplish this, a storage system is required to provide multiple services such as self-consumption, grid support, peak-shaving, etc. The simultaneous activation of controllers operation may lead to conflicts, as a consequence the execution of committed services is not guaranteed. This paper presents and discusses a solution to the exposed issue by developing an engineering support approach to semi-automatically detect and handle conflicts for multi-usage storage systems applications. To accomplish that an ontology is developed and exploited by model-driven engineering mechanisms. The proposed approach is evaluated by implementing a use case example, where detection of conflicts is automatically done at an early design stage. Besides this, exploitable source code for conflicts resolution is generated and used during the design and prototype stages of controllers development. Thus, the proposed engineering support enhances the design and development of storage system controllers, especially for multi-usage applications.

  6. Licence template for mobile handling and storage of radioactive substances for the nondestructive testing of materials; Mustergenehmigung zur ortsveraenderlichen Verwendung und Lagerung radioaktiver Stoffe im Rahmen der zerstoerungsfreien Materialpruefung

    Energy Technology Data Exchange (ETDEWEB)

    Lange, A. [Niedersaechsisches Ministerium fuer Umwelt, Energie und Klimaschutz (Germany); Schumann, J. [Landesamt fuer Arbeitsschutz, Gesundheitsschutz und technische Sicherheit, Berlin (Germany); Huhn, W.

    2016-07-01

    The Technical Committee ''Radiation Protection'' (Fachausschuss ''Strahlenschutz'') and the Laender Committee ''X-ray ordinance'' (Laenderausschuss ''Roentgenverordnung'') have appointed a working group for the formulation of licence templates for the nationwide use of X-ray equipment or handling of radioactive substances. To date, the following licence templates have been adopted: - Mobile operation of X-ray equipment under technical radiography to the coarse structural analysis in material testing; - Mobile operation of a handheld X-ray fluorescence system; - Mobile operation of a flash X-ray system; - Operation of an X-ray system for teleradiology The licence template ''Mobile handling and storage of radioactive substances for the nondestructive testing of materials'' is scheduled for publication. The licence template ''Practices in external facilities and installations'' is currently being revised. The licence template ''Mobile handling and storage of radioactive substances for the nondestructive testing of materials'' is used as an example to demonstrate the legal framework and the results of the working group.

  7. Asthma, guides for diagnostic and handling

    International Nuclear Information System (INIS)

    Salgado, Carlos E; Caballero A, Andres S; Garcia G, Elizabeth

    1999-01-01

    The paper defines the asthma, includes topics as diagnostic, handling of the asthma, special situations as asthma and pregnancy, handling of the asthmatic patient's perioperatory and occupational asthma

  8. PREPD O and VE remote handling system

    International Nuclear Information System (INIS)

    Theil, T.N.

    1985-01-01

    The Process Experimental Pilot Plant (PREPP) at the Idaho National Engineering Laboratory is designed for volume reduction and packaging of transuranic (TRU) waste. The PREPP opening and verification enclosure (O and VE) remote handling system, within that facility, is designed to provide examination of the contents of various TRU waste storage containers. This remote handling system will provide the means of performing a hazardous operation that is currently performed manually. The TeleRobot to be used in this system is a concept that will incorporate and develop man in the loop operation (manual mode), standardized automatic sequencing of end effector tools, increased payload and reach over currently available computer-controlled robots, and remote handling of a hazardous waste operation. The system is designed within limited space constraints and an operation that was originally planned, and is currently being manually performed at other plants. The PREPP O and VE remote handling system design incorporates advancing technology to improve the working environment in the nuclear field

  9. Liquid chromatography and ultra-performance liquid chromatography-mass spectrometry fingerprinting of human urine: sample stability under different handling and storage conditions for metabonomics studies.

    Science.gov (United States)

    Gika, Helen G; Theodoridis, Georgios A; Wilson, Ian D

    2008-05-02

    Typically following collection biological samples are kept in a freezer for periods ranging from a few days to several months before analysis. Experience has shown that in LC-MS-based metabonomics research the best analytical practice is to store samples as these are collected, complete the sample set and analyse it in a single run. However, this approach is prudent only if the samples stored in the refrigerator or in the freezer are stable. Another important issue is the stability of the samples following the freeze-thaw process. To investigate these matters urine samples were collected from 6 male volunteers and analysed by LC-MS and ultra-performance liquid chromatography (UPLC)-MS [in both positive and negative electrospray ionization (ESI)] on the day of collection or at intervals of up to 6 months storage at -20 degrees C and -80 degrees C. Other sets of these samples underwent a series of up to nine freeze-thaw cycles. The stability of samples kept at 4 degrees C in an autosampler for up to 6 days was also assessed, with clear differences appearing after 48h. Data was analysed using multivariate statistical analysis (principal component analysis). The results show that sample storage at both -20 and -80 degrees C appeared to ensure sample stability. Similarly up to nine freeze thaw cycles were without any apparent effect on the profile.

  10. Data handling and modelling

    International Nuclear Information System (INIS)

    Minchin, P.E.H.

    1986-01-01

    The author reviews the interpretation of various tracer profiles. A quantitative description of the change of profile shape is given by the transfer function calculated from observed profiles. From the transfer function physically meaningful quantities such as average transit time, dispersion and leakage can be calculated

  11. Safety in handling helium and nitrogen

    International Nuclear Information System (INIS)

    Schmauch, G.; Lansing, L.; Santay, T.; Nahmias, D.

    1991-01-01

    Based upon the authors' industrial experience and practices, they have provided an overview of safety in storage, handling, and transfer of both laboratory and bulk quantities of gaseous and liquid forms of nitrogen and helium. They have addressed the properties and characteristics of both the gaseous and liquid fluids, typical storage and transport containers, transfer techniques, and the associated hazards which include low temperatures, high pressures, and asphyxiation. Methods and procedures to control and eliminate these hazards are described, as well as risk remediation through safety awareness training, personal protective equipment, area ventilation, and atmosphere monitoring. They have included as an example a recent process hazards analysis performed by Air Products on the asphyxiation hazard associated with the use of liquid helium in MRI magnet systems

  12. Simulation of the MRS receiving and handling facility

    International Nuclear Information System (INIS)

    Triplett, M.B.; Imhoff, C.H.; Hostick, C.J.

    1984-02-01

    Monitored retrievable storage (MRS) will be required to handle a large volume of spent fuel or high-level waste (HLW) in case of delays in repository deployment. The quantities of materials to be received and repackaged for storage far exceed the requirements of existing waste mangement facilities. A computer simulation model of the MRS receiving and handling (R and H) fcility has been constructed and used to evaluate design alternatives. Studies have identified processes or activities which may constrain throughput performance. In addition, the model has helped to assess design tradeoffs such as those to be made among improved process times, redundant service lines, and improved component availability. 1 reference, 5 figures

  13. Studies and research concerning BNFP: cask handling equipment standardization

    International Nuclear Information System (INIS)

    McCreery, P.N.

    1980-10-01

    This report covers the activities of one of the sub-tasks within the Spent LWR Fuel Transportation Receiving, Handling, and Storage program. The sub-task is identified as Cask Handling Equipment Standardization. The objective of the sub-task specifies: investigate and identify opportunities for standardization of cask interface equipment. This study will examine the potential benefits of standardized yokes, decontamination barriers and special tools, and, to the extent feasible, standardized methods and software for handling the variety of casks presently available in the US fleet. The result of the investigations is a compilation of reports that are related by their common goal of reducing cask turnaround time

  14. Nuclear hydrogen production and its safe handling

    International Nuclear Information System (INIS)

    Chung, Hongsuk; Paek, Seungwoo; Kim, Kwang-Rag; Ahn, Do-Hee; Lee, Minsoo; Chang, Jong Hwa

    2003-01-01

    An overview of the hydrogen related research presently undertaken at the Korea Atomic Energy Research Institute are presented. These encompass nuclear hydrogen production, hydrogen storage, and the safe handling of hydrogen, High temperature gas-cooled reactors can play a significant role, with respect to large-scale hydrogen production, if used as the provider of high temperature heat in fossil fuel conversion or thermochemical cycles. A variety of potential hydrogen production methods for high temperature gas-cooled reactors were analyzed. They are steam reforming of natural gas, thermochemical cycles, etc. The produced hydrogen should be stored safely. Titanium metal was tested primarily because its hydride has very low dissociation pressures at normal storage temperatures and a high capacity for hydrogen, it is easy to prepare and is non-reactive with air in the expected storage conditions. There could be a number of potential sources of hydrogen evolution risk in a nuclear hydrogen production facility. In order to reduce the deflagration detonation it is necessary to develop hydrogen control methods that are capable of dealing with the hydrogen release rate. A series of experiments were conducted to assess the catalytic recombination characteristics of hydrogen in an air stream using palladium catalysts. (author)

  15. Handling and transport problems (1960)

    International Nuclear Information System (INIS)

    Pomarola, J.; Savouyaud, J.

    1960-01-01

    I. The handling and transport of radioactive wastes involves the danger of irradiation and contamination. It is indispensable: - to lay down a special set of rules governing the removal and transport of wastes within centres or from one centre to another; - to give charge of this transportation to a group containing teams of specialists. The organisation, equipment and output of these teams is being examined. II. Certain materials are particularly dangerous to transport, and for these special vehicles and fixed installations are necessary. This is the case especially for the evacuation of very active liquids. A transport vehicle is described, consisting of a trailer tractor and a recipient holding 500 litres of liquid of which the activity can reach 1000 C/l; the decanting operation, the route to be followed by the vehicle, and the precautions taken are also described. (author) [fr

  16. 3. Production of radionuclides, preparation and handling of labelled compounds

    International Nuclear Information System (INIS)

    Toelgyessy, J.

    1981-01-01

    The preparation of natural radioactive compounds and the manufacture of artificial radionuclides, the labelling of organic compounds, and the methods of radioactive substance separation are described. The principles are shown of handling radioactive materials and a brief description is given of the stability, packaging and storage of radiopharmaceuticals. (J.P.)

  17. Data Handling and Parameter Estimation

    DEFF Research Database (Denmark)

    Sin, Gürkan; Gernaey, Krist

    2016-01-01

    ,engineers, and professionals. However, it is also expected that they will be useful both for graduate teaching as well as a stepping stone for academic researchers who wish to expand their theoretical interest in the subject. For the models selected to interpret the experimental data, this chapter uses available models from...... literature that are mostly based on the ActivatedSludge Model (ASM) framework and their appropriate extensions (Henze et al., 2000).The chapter presents an overview of the most commonly used methods in the estimation of parameters from experimental batch data, namely: (i) data handling and validation, (ii......Modelling is one of the key tools at the disposal of modern wastewater treatment professionals, researchers and engineers. It enables them to study and understand complex phenomena underlying the physical, chemical and biological performance of wastewater treatment plants at different temporal...

  18. Superphenix 1 primary handling system fabrication and testing

    International Nuclear Information System (INIS)

    Branchu, J.; Ebbinghaus, K.; Gigarel, C.

    1985-01-01

    Primary handling covers the operations performed for spent fuel removal, new fuel insertion, and the insodium storage outside the new or spent fuel vessel. This equipment typifies many of the difficulties encountered with the project as a whole: fabrication coordination when several countries are involved and design and construction of very large, relatively complex components. Detailed design studies were mainly influenced by thermal and seismic requirements, as applicable to sodium-immersed structures. Where possible, well-tried mechanical solutions were used, but widely differing techniques were involved, ranging from the high precision fabrication of structures and mechanisms comprising numerous component parts, implying complex machining operations. No particular problems were encountered during the sodium testing of the primary handling equipment. Trends for the 1500-MW (electric) breeder include investigation of the advisability of fuel storage in the core lattice and the possibility of handling system simplification

  19. Current US strategy and technologies for spent fuel handling

    International Nuclear Information System (INIS)

    Bennett, P.C.; Stringer, J.B.

    1999-01-01

    The United States Department of Energy has recently completed a topical safety analysis report outlining the design and operation of a Centralized Interim Storage Facility for spent commercial nuclear fuel. During the course of the design, dose assessments indicated the need for remote operation of many of the cask handling operations. Use of robotic equipment was identified as a desirable handling solution that is capable of automating many of the operations to maintain throughput, and sufficiently flexible to handle five or more different storage cask designs in varying numbers on a given day. This paper discusses the facility and the dose assessment leading to this choice, and reviews factors to be considered when choosing robotics or automation. Further, a new computer simulation tool to quantify dose to humans working in radiological environments, the Radiological Environment Modeling System (REMS), is introduced. REMS has been developed to produce a more accurate estimate of dose to radiation workers in new activities with radiological hazards. (author)

  20. On current US strategy and technologies for spent fuel handling

    International Nuclear Information System (INIS)

    Bennett, P.C.

    1997-01-01

    The US Department of Energy has recently completed a topical safety analysis report outlining the design and operation of a Centralized Interim Storage Facility for spent commercial nuclear fuel. During the course of the design, dose assessments indicated the need for remote operation of many of the cask handling operations. Use of robotic equipment was identified as a desirable handling solution that is capable of automating many of the operations to maintain throughput, and sufficiently flexible to handle five or more different storage cask designs in varying numbers on a given day. This paper discusses the facility and the dose assessment leading to this choice, and reviews factors to be considered when choosing robotics or automation. Further, a new computer simulation tool to quantify dose to humans working in radiological environments, the Radiological Environment Modeling System (REMS), is introduced. REMS has been developed to produce a more accurate estimate of dose to radiation workers in new activities with radiological hazards

  1. Hoisting appliances and fuel handling equipment at nuclear facilities

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1988-12-31

    The guide is followed by the Finnish Centre for Radiation and Nuclear Safety (STUK) in regulating hoisting and handling equipment Class 3 at nuclear facilities. The guide is applied e.g. to the following equipment: reactor building overhead cranes, hoisting appliances at nuclear fuel storages, fuel handling machines, other hoisting appliances, which because of nuclear safety aspects are classified in Safety Class 3, and load-bearing devices connected with the above equipment, such as replaceable hoisting tools and auxiliary lifting devices. The regulating of hoisting and handling equipment comprises the following stages: handling of preliminary and final safety analysis reports, inspection of the construction plan, supervision of fabrication and construction inspection, and supervision of initial start-up and commissioning inspection. 36 refs. Translation. The original text is published under the same guide number. The guide is valid from 5 January 1987 and will be in force until further notice.

  2. Hoisting appliances and fuel handling equipment at nuclear facilities

    International Nuclear Information System (INIS)

    1987-01-01

    The guide is followed by the Finnish Centre for Radiation and Nuclear Safety (STUK) in regulating hoisting and handling equipment Class 3 at nuclear facilities. The guide is applied e.g. to the following equipment: reactor building overhead cranes, hoisting appliances at nuclear fuel storages, fuel handling machines, other hoisting appliances, which because of nuclear safety aspects are classified in Safety Class 3, and load-bearing devices connected with the above equipment, such as replaceable hoisting tools and auxiliary lifting devices. The regulating of hoisting and handling equipment comprises the following stages: handling of preliminary and final safety analysis reports, inspection of the construction plan, supervision of fabrication and construction inspection, and supervision of initial start-up and commissioning inspection

  3. Hot Laboratories and Remote Handling

    International Nuclear Information System (INIS)

    Bart, G.; Blanc, J.Y.; Duwe, R.

    2003-01-01

    The European Working Group on ' Hot Laboratories and Remote Handling' is firmly established as the major contact forum for the nuclear R and D facilities at the European scale. The yearly plenary meetings intend to: - Exchange experience on analytical methods, their implementation in hot cells, the methodologies used and their application in nuclear research; - Share experience on common infrastructure exploitation matters such as remote handling techniques, safety features, QA-certification, waste handling; - Promote normalization and co-operation, e.g., by looking at mutual complementarities; - Prospect present and future demands from the nuclear industry and to draw strategic conclusions regarding further needs. The 41. plenary meeting was held in CEA Saclay from September 22 to 24, 2003 in the premises and with the technical support of the INSTN (National Institute for Nuclear Science and Technology). The Nuclear Energy Division of CEA sponsored it. The Saclay meeting was divided in three topical oral sessions covering: - Post irradiation examination: new analysis methods and methodologies, small specimen technology, programmes and results; - Hot laboratory infrastructure: decommissioning, refurbishment, waste, safety, nuclear transports; - Prospective research on materials for future applications: innovative fuels (Generation IV, HTR, transmutation, ADS), spallation source materials, and candidate materials for fusion reactor. A poster session was opened to transport companies and laboratory suppliers. The meeting addressed in three sessions the following items: Session 1 - Post Irradiation Examinations. Out of 12 papers (including 1 poster) 7 dealt with surface and solid state micro analysis, another one with an equally complex wet chemical instrumental analytical technique, while the other four papers (including the poster) presented new concepts for digital x-ray image analysis; Session 2 - Hot laboratory infrastructure (including waste theme) which was

  4. Some factors to consider in handling and storing spent fuel

    International Nuclear Information System (INIS)

    Bailey, W.J.

    1985-11-01

    This report includes information from various studies performed under the Wet Storage Task of the Behavior of Spent Fuel in Storage Project of the Commercial Spent Fuel Management (CSFM) Program at Pacific Northwest Laboratory. Wet storage experience has been summarized earlier in several other reports. This report summarizes pertinent items noted during FY 1985 concerning recent developments in the handling and storage of spent fuel and associated considerations. The subjects discussed include recent publications, findings, and developments associated with: (1) storage of water reactor spent fuel in water pools, (2) extended-burnup fuel, (3) fuel assembly reconstitution and reinsertion, (4) rod consolidation, (5) variations in the US Nuclear Regulatory Commission's definition of failed fuel, (6) detection of failed fuel rods, and (7) extended integrity of spent fuel. A list of pertinent publications is included

  5. Reviewing reactor engineering and fuel handling

    International Nuclear Information System (INIS)

    1991-12-01

    Experience has shown that the better operating nuclear power plants have well defined and effectively administered policies and procedures for governing reactor engineering and fuel handling (RE and FH) activities. This document provides supplementary guidance to OSART experts for evaluating the RE and FH programmes and activities at a nuclear power plant and assessing their effectiveness and adequacy. It is in no way intended to conflict with existing regulations and rules, but rather to exemplify those characteristics and features that are desirable for an effective, well structured RE and FH programme. This supplementary guidance addresses those aspects of RE and FH activities that are required in order to ensure optimum core operation for a nuclear reactor without compromising the limits imposed by the design, safety considerations of the nuclear fuel. In the context of this document, reactor engineering refers to those activities associated with in-core fuel and reactivity management, whereas fuel handling refers to the movement, storage, control and accountability of unirradiated and irradiated fuel. The document comprises five main sections and several appendices. In Section 2 of this guide, the essential aspects of an effective RE and FH programme are discussed. In Section 3, the various types of documents and reference materials needed for the preparatory work and investigation are listed. In Section 4, specific guidelines for investigation of RE and FH programmes are presented. In Section 5, the essential attributes of an excellent RE and FH programme are listed. The supplementary guidance is concluded with a series of appendices exemplifying the various qualities and attributes of a sound, well defined RE and FH programme

  6. Hot Laboratories and Remote Handling

    International Nuclear Information System (INIS)

    2007-01-01

    The Opening talk of the workshop 'Hot Laboratories and Remote Handling' was given by Marin Ciocanescu with the communication 'Overview of R and D Program in Romanian Institute for Nuclear Research'. The works of the meeting were structured into three sections addressing the following items: Session 1. Hot cell facilities: Infrastructure, Refurbishment, Decommissioning; Session 2. Waste, transport, safety and remote handling issues; Session 3. Post-Irradiation examination techniques. In the frame of Section 1 the communication 'Overview of hot cell facilities in South Africa' by Wouter Klopper, Willie van Greunen et al, was presented. In the framework of the second session there were given the following four communications: 'The irradiated elements cell at PHENIX' by Laurent Breton et al., 'Development of remote equipment for DUPIC fuel fabrication at KAERI', by Jung Won Lee et al., 'Aspects of working with manipulators and small samples in an αβγ-box, by Robert Zubler et al., and 'The GIOCONDA experience of the Joint Research Centre Ispra: analysis of the experimental assemblies finalized to their safe recovery and dismantling', by Roberto Covini. Finally, in the framework of the third section the following five communications were presented: 'PIE of a CANDU fuel element irradiated for a load following test in the INR TRIGA reactor' by Marcel Parvan et al., 'Adaptation of the pole figure measurement to the irradiated items from zirconium alloys' by Yury Goncharenko et al., 'Fuel rod profilometry with a laser scan micrometer' by Daniel Kuster et al., 'Raman spectroscopy, a new facility at LECI laboratory to investigate neutron damage in irradiated materials' by Lionel Gosmain et al., and 'Analysis of complex nuclear materials with the PSI shielded analytical instruments' by Didier Gavillet. In addition, eleven more presentations were given as posters. Their titles were: 'Presentation of CETAMA activities (CEA analytic group)' by Alain Hanssens et al. 'Analysis of

  7. PND fuel handling decontamination: facilities and techniques

    International Nuclear Information System (INIS)

    Pan, R.Y.

    1996-01-01

    The use of various decontamination techniques and equipment has become a critical part of Fuel Handling maintenance work at Ontario Hydro's Pickering Nuclear Division. This paper presents an overview of the set up and techniques used for decontamination in the PND Fuel Handling Maintenance Facility and the effectiveness of each. (author). 1 tab., 9 figs

  8. PND fuel handling decontamination: facilities and techniques

    Energy Technology Data Exchange (ETDEWEB)

    Pan, R Y [Ontario Hydro, Toronto, ON (Canada)

    1997-12-31

    The use of various decontamination techniques and equipment has become a critical part of Fuel Handling maintenance work at Ontario Hydro`s Pickering Nuclear Division. This paper presents an overview of the set up and techniques used for decontamination in the PND Fuel Handling Maintenance Facility and the effectiveness of each. (author). 1 tab., 9 figs.

  9. Better fuel handling system performance through improved elastomers and seals

    Energy Technology Data Exchange (ETDEWEB)

    Wensel, R G; Metcalfe, R [Atomic Energy of Canada Ltd., Chalk River, ON (Canada)

    1997-12-31

    In the area of elastomers, tests have identified specific compounds that perform well in each class of CANDU service. They offer gains in service life, sometimes by factors of ten or more. Moreover, the aging characteristics of these specific compounds are being thoroughly investigated, whereas many elastomers used previously were either non-specific or their aging was unknown. In this paper the benefits of elastomer upgrading, as well as the deficiencies of current station elastomer practices, are discussed in the context of fuel handling equipment. Guidelines for procurement, storage, handling and condition monitoring of elastomer seals are outlined. (author). 3 figs.

  10. Better fuel handling system performance through improved elastomers and seals

    International Nuclear Information System (INIS)

    Wensel, R.G.; Metcalfe, R.

    1996-01-01

    In the area of elastomers, tests have identified specific compounds that perform well in each class of CANDU service. They offer gains in service life, sometimes by factors of ten or more. Moreover, the aging characteristics of these specific compounds are being thoroughly investigated, whereas many elastomers used previously were either non-specific or their aging was unknown. In this paper the benefits of elastomer upgrading, as well as the deficiencies of current station elastomer practices, are discussed in the context of fuel handling equipment. Guidelines for procurement, storage, handling and condition monitoring of elastomer seals are outlined. (author). 3 figs

  11. Survey of postharvest handling, preservation and processing ...

    African Journals Online (AJOL)

    Survey of postharvest handling, preservation and processing practices along the camel milk chain in Isiolo district, Kenya. ... Despite the important contribution of camel milk to food security for pastoralists in Kenya, little is known about the postharvest handling, preservation and processing practices. In this study, existing ...

  12. Process of preparing substantially organic waste liquids containing radioactive or toxic substances for safe, non-pollutive handling, transportation, and permanent storage

    International Nuclear Information System (INIS)

    Baehr, W.; Drobnik, S.; Hild, W.; Kroebel, R.; Meyer, A.; Naumann, G.

    1977-01-01

    In this process, the liquids are mixed with polymerizable mixtures consisting essentially of one or more monomeric monovinyl compounds and one or more polyvinyl compounds and polymerization catalysts, and the resulting mixtures are converted into solid blocks by polymerization at temperatures in the range of from 15 to 150 0 C. 8 claims

  13. DDOS ATTACK DETECTION SIMULATION AND HANDLING MECHANISM

    Directory of Open Access Journals (Sweden)

    Ahmad Sanmorino

    2013-11-01

    Full Text Available In this study we discuss how to handle DDoS attack that coming from the attacker by using detection method and handling mechanism. Detection perform by comparing number of packets and number of flow. Whereas handling mechanism perform by limiting or drop the packets that detected as a DDoS attack. The study begins with simulation on real network, which aims to get the real traffic data. Then, dump traffic data obtained from the simulation used for detection method on our prototype system called DASHM (DDoS Attack Simulation and Handling Mechanism. From the result of experiment that has been conducted, the proposed method successfully detect DDoS attack and handle the incoming packet sent by attacker.

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

    International Nuclear Information System (INIS)

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

    1979-09-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1979-09-01

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

  16. Plutonium stabilization and handling quality assurance program plan

    International Nuclear Information System (INIS)

    Weiss, E.V.

    1998-01-01

    This Quality Assurance Program Plan (QAPP) identifies project quality assurance requirements for all contractors involved in the planning and execution of Hanford Site activities for design, procurement, construction, testing and inspection for Project W-460, Plutonium Stabilization and Handling. The project encompasses procurement and installation of a Stabilization and Packaging System (SPS) to oxidize and package for long term storage remaining plutonium-bearing special nuclear materials currently in inventory at the Plutonium Finishing Plant (PFP), and modification of vault equipment to allow storage of resulting packages of stabilized SNM

  17. Handling and treatment of radioactive aqueous wastes

    International Nuclear Information System (INIS)

    1992-07-01

    This report aims to provide essential guidance to developing Member States without a nuclear power programme regarding selection, design and operation of cost effective treatment processes for radioactive aqueous liquids arising as effluents from small research institutions, hospitals and industries. The restricted quantities and low activity associated with the relevant wastes will generally permit contact-handling and avoid the need for shielding requirements. The selection of liquid waste treatment involves: Characterization of arising with the possibility of segregation; Discharge requirements for decontaminated liquors, both radioactive and non-radioactive; Available technologies and costs; Conditioning of the concentrates resulting from the treatment; Storage and disposal of the conditioned concentrates. The report will serve as a technical manual providing reference material and direct step-by-step know-how to staff in radioisotope user establishments and research centres in the developing Member States without nuclear power generation. Therefore, emphasis is limited to the simpler treatment facilities, which will be included with only the robust, well-established waste management processes carefully chosen as appropriate to developing countries. 20 refs, 12 figs, 7 tabs

  18. Safeguards information handling and treatment

    International Nuclear Information System (INIS)

    Carchon, R.; Liu, J.; Ruan, D.

    2001-01-01

    Many states are currently discussing the new additional protocol (INFCIRC/540). This expanded framework is expected to establish the additional confirmation that there are no undeclared activities and facilities in that state. The information collected by the IAEA mainly comes from three different sources: information either provided by the state, collected by the IAEA, and from open sources. This information can be uncertain, incomplete, imprecise, not fully reliable, contradictory, etc. Hence, there is a need for a mathematical framework that provides a basis for handling and treatment of multidimensional information of varying quality. We use a linguistic assessment based on fuzzy set theory, as a flexible and realistic approach. The concept of a linguistic variable serves the purpose of providing a means of approximated characterization of information that may be imprecise, too complex or ill-defined, for which the traditional quantitative approach does not give an adequate answer. In the application of this linguistic assessment approach, a problem arises on how to aggregate linguistic information. Two different approaches can be followed: (1) approximation approach using the associated membership function; (2) symbolic approach acting by the direct computation on labels, where the use of membership function and the linguistic approximation is unnecessary, which makes computation simple and quick. To manipulate the linguistic information in this context, we work with aggregation operators for combining the linguistic non-weighted and weighted values by direct computation on labels, like the Min-type and Max-type weighted aggregation operators as well as the median aggregation operator. A case study on the application of these aggregation operators to the fusion of safeguards relevant information is given. The IAEA Physical Model of the nuclear fuel cycle can be taken as a systematic and comprehensive indicator system. It identifies and describes indicators of

  19. Handling and carrying head for nuclear fuel assemblies and installation including this head

    International Nuclear Information System (INIS)

    Artaud, R.; Cransac, J.P.; Jogand, P.

    1986-01-01

    The present invention proposes a handling and carrying head ensuring efficiently the cooling of the nuclear fuel asemblies it transports so that any storage in liquid metal in a drum within or adjacent the reactor vessel is suppressed. The invention claims also a nuclear fuel handling installation including the head; it allows a longer time between loading and unloading campaigns and the space surrounding the reactor vessel keeps free without occupying a storage zone within the vessel [fr

  20. Ergonomics: safe patient handling and mobility.

    Science.gov (United States)

    Hallmark, Beth; Mechan, Patricia; Shores, Lynne

    2015-03-01

    This article reviews and investigates the issues surrounding ergonomics, with a specific focus on safe patient handling and mobility. The health care worker of today faces many challenges, one of which is related to the safety of patients. Safe patient handling and mobility is on the forefront of the movement to improve patient safety. This article reviews the risks associated with patient handling and mobility, and informs the reader of current evidence-based practice relevant to this area of care. Copyright © 2015 Elsevier Inc. All rights reserved.

  1. Aerobot Sampling and Handling System, Phase I

    Data.gov (United States)

    National Aeronautics and Space Administration — Honeybee Robotics proposes to: ?Derive and document the functional and technical requirements for Aerobot surface sampling and sample handling across a range of...

  2. Management of transport and handling contracts

    CERN Document Server

    Rühl, I

    2004-01-01

    This paper shall outline the content, application and management strategies for the various contracts related to transport and handling activities. In total, the two sections Logistics and Handling Maintenance are in charge of 27 (!) contracts ranging from small supply contracts to big industrial support contracts. The activities as well as the contracts can generally be divided into four main topics "Vehicle Fleet Management"; "Supply, Installation and Commissioning of Lifting and Hoisting Equipment"; "Equipment Maintenance" and "Industrial Support for Transport and Handling". Each activity and contract requires different approaches and permanent adaptation to the often changing CERN's requirements. In particular, the management and the difficulties experienced with the contracts E072 "Maintenance of lifting and hoisting equipment", F420 "Supply of seven overhead traveling cranes for LHC" and S090/S103 "Industrial support for transport and handling" will be explained in detail.

  3. Data handling systems and methods of wiring

    International Nuclear Information System (INIS)

    Grant, J.

    1981-01-01

    An improved data handling system, for monitoring and control of nuclear reactor operations, is described in which time delays associated with scanning are reduced and noise and fault signals in the system are resolved. (U.K.)

  4. Foster parenting, human imprinting and conventional handling ...

    African Journals Online (AJOL)

    p2492989

    Foster parenting, human imprinting and conventional handling affects survival and early .... bird may subsequently direct its sexual attention to those humans on whom it was imprinted (Bubier et al., ..... The mind through chicks' eyes: memory,.

  5. 77 FR 23117 - Rigging Equipment for Material Handling Construction Standard; Correction and Technical Amendment

    Science.gov (United States)

    2012-04-18

    ... Equipment for Material Handling Construction Standard; Correction and Technical Amendment AGENCY... AND HEALTH REGULATIONS FOR CONSTRUCTION Subpart H--Materials Handling, Storage, Use, and Disposal 0 1... amendment. SUMMARY: OSHA is correcting its sling standard for construction titled ``Rigging Equipment for...

  6. Handling, treatment, conditioning and storage of biological radioactive wastes. Technical manual for the management of low and intermediate level wastes generated at small nuclear research centres and by radioisotope users in medicine, research and industry

    International Nuclear Information System (INIS)

    1994-12-01

    Biological materials that contain radioactive isotopes have many important applications. During the production and use of these materials, waste will inevitably arise which must be managed with particular care due to their potential biological as well as radiological hazards. This report deals with wastes that arise outside the nuclear fuel cycle and is directed primarily to countries without nuclear power programmes. It is intended to provide guidance to Member States in the handling, treatment and conditioning of biological radioactive materials. The objective of radioactive waste management is to handle, pretreat, treat, condition, store, transport and dispose of radioactive waste in a manner that protects human health and the environment without imposing undue burdens on future generations. 31 refs, 15 figs, 3 tabs

  7. Handling, treatment, conditioning and storage of biological radioactive wastes. Technical manual for the management of low and intermediate level wastes generated at small nuclear research centres and by radioisotope users in medicine, research and industry

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1994-12-01

    Biological materials that contain radioactive isotopes have many important applications. During the production and use of these materials, waste will inevitably arise which must be managed with particular care due to their potential biological as well as radiological hazards. This report deals with wastes that arise outside the nuclear fuel cycle and is directed primarily to countries without nuclear power programmes. It is intended to provide guidance to Member States in the handling, treatment and conditioning of biological radioactive materials. The objective of radioactive waste management is to handle, pretreat, treat, condition, store, transport and dispose of radioactive waste in a manner that protects human health and the environment without imposing undue burdens on future generations. 31 refs, 15 figs, 3 tabs.

  8. Religious Serpent Handling and Community Relations.

    Science.gov (United States)

    Williamson, W Paul; Hood, Ralph W

    2015-01-01

    Christian serpent handling sects of Appalachia comprise a community that has long been mischaracterized and marginalized by the larger communities surrounding them. To explore this dynamic, this article traces the emergence of serpent handling in Appalachia and the emergence of anti-serpent-handling state laws, which eventually failed to curb the practice, as local communities gave serpent handling groups support. We present two studies to consider for improving community relations with serpent handling sects. In study 1, we present data relating the incidence of reported serpent-bite deaths with the rise of anti-serpent-handling laws and their eventual abatement, based on increasing acceptance of serpent handlers by the larger community. Study 2 presents interview data on serpent bites and death that provide explanations for these events from the cultural and religious perspective. We conclude that first-hand knowledge about serpent handlers, and other marginalized groups, helps to lessen suspicion and allows them to be seen as not much different, which are tendencies that are important for promoting inter-community harmony.

  9. Specialization and Flexibility in Port Cargo Handling

    Directory of Open Access Journals (Sweden)

    Hakkı KİŞİ

    2016-11-01

    Full Text Available Cargo handling appears to be the fundamental function of ports. In this context, the question of type of equipment and capacity rate need to be tackled with respect to cargo handling principles. The purpose of this study is to discuss the types of equipment to be used in ports, relating the matter to costs and capacity. The question is studied with a basic economic theoretical approach. Various conditions like port location, size, resources, cargo traffic, ships, etc. are given parameters to dictate the type and specification of the cargo handling equipment. Besides, a simple approach in the context of cost capacity relation can be useful in deciding whether to use specialized or flexible equipment. Port equipment is sometimes expected to be flexible to handle various types of cargo as many as possible and sometimes to be specialized to handle one specific type of cargo. The cases that might be suitable for those alternatives are discussed from an economic point of view in this article. Consequently, effectiveness and efficiency criteria play important roles in determining the handling equipment in ports.

  10. Fuel handling machine and auxiliary systems for a fuel handling cell

    International Nuclear Information System (INIS)

    Suikki, M.

    2013-10-01

    This working report is an update for as well as a supplement to an earlier fuel handling machine design (Kukkola and Roennqvist 2006). A focus in the earlier design proposal was primarily on the selection of a mechanical structure and operating principle for the fuel handling machine. This report introduces not only a fuel handling machine design but also auxiliary fuel handling cell equipment and its operation. An objective of the design work was to verify the operating principles of and space allocations for fuel handling cell equipment. The fuel handling machine is a remote controlled apparatus capable of handling intensely radiating fuel assemblies in the fuel handling cell of an encapsulation plant. The fuel handling cell is air tight space radiation-shielded with massive concrete walls. The fuel handling machine is based on a bridge crane capable of traveling in the handling cell along wall tracks. The bridge crane has its carriage provided with a carousel type turntable having mounted thereon both fixed and telescopic masts. The fixed mast has a gripper movable on linear guides for the transfer of fuel assemblies. The telescopic mast has a manipulator arm capable of maneuvering equipment present in the fuel handling cell, as well as conducting necessary maintenance and cleaning operations or rectifying possible fault conditions. The auxiliary fuel handling cell systems consist of several subsystems. The subsystems include a service manipulator, a tool carrier for manipulators, a material hatch, assisting winches, a vacuum cleaner, as well as a hose reel. With the exception of the vacuum cleaner, the devices included in the fuel handling cell's auxiliary system are only used when the actual encapsulation process is not ongoing. The malfunctions of mechanisms or actuators responsible for the motion actions of a fuel handling machine preclude in a worst case scenario the bringing of the fuel handling cell and related systems to a condition appropriate for

  11. Fuel handling machine and auxiliary systems for a fuel handling cell

    Energy Technology Data Exchange (ETDEWEB)

    Suikki, M. [Optimik Oy, Turku (Finland)

    2013-10-15

    This working report is an update for as well as a supplement to an earlier fuel handling machine design (Kukkola and Roennqvist 2006). A focus in the earlier design proposal was primarily on the selection of a mechanical structure and operating principle for the fuel handling machine. This report introduces not only a fuel handling machine design but also auxiliary fuel handling cell equipment and its operation. An objective of the design work was to verify the operating principles of and space allocations for fuel handling cell equipment. The fuel handling machine is a remote controlled apparatus capable of handling intensely radiating fuel assemblies in the fuel handling cell of an encapsulation plant. The fuel handling cell is air tight space radiation-shielded with massive concrete walls. The fuel handling machine is based on a bridge crane capable of traveling in the handling cell along wall tracks. The bridge crane has its carriage provided with a carousel type turntable having mounted thereon both fixed and telescopic masts. The fixed mast has a gripper movable on linear guides for the transfer of fuel assemblies. The telescopic mast has a manipulator arm capable of maneuvering equipment present in the fuel handling cell, as well as conducting necessary maintenance and cleaning operations or rectifying possible fault conditions. The auxiliary fuel handling cell systems consist of several subsystems. The subsystems include a service manipulator, a tool carrier for manipulators, a material hatch, assisting winches, a vacuum cleaner, as well as a hose reel. With the exception of the vacuum cleaner, the devices included in the fuel handling cell's auxiliary system are only used when the actual encapsulation process is not ongoing. The malfunctions of mechanisms or actuators responsible for the motion actions of a fuel handling machine preclude in a worst case scenario the bringing of the fuel handling cell and related systems to a condition appropriate for

  12. 30o inclination in handles of plastic boxes can reduce postural and muscular workload during handling

    Directory of Open Access Journals (Sweden)

    Luciana C. C. B. Silva

    2013-06-01

    Full Text Available BACKGROUND: The handling of materials, which occurs in the industrial sector, is associated with lesions on the lumbar spine and in the upper limbs. Inserting handles in industrial boxes is a way to reduce work-related risks. Although the position and angle of the handles are significant factors in comfort and safety during handling, these factors have rarely been studied objectively. OBJECTIVE: To compare the handling of a commercial box and prototypes with handles and to evaluate the effects on upper limb posture, muscle electrical activity, and perceived acceptability using different grips while handling materials from different heights. METHOD: Thirty-seven healthy volunteers evaluated the handles of prototypes that allowed for changes in position (top and bottom and angle (0°, 15°, and 30°. Wrist, elbow, and shoulder movements were evaluated using electrogoniometry and inclinometry. The muscle electrical activity in the wrist extensors, biceps brachii, and the upper portion of the trapezius was measured using a portable electromyographer. The recorded data on muscle movements and electrical activity were synchronized. Subjective evaluations of acceptability were evaluated using a visual analog scale. RESULTS AND CONCLUSIONS: The prototypes with handles at a 30° angle produced the highest acceptability ratings, more neutral wrist positions, lower levels of electromyographic activity for the upper trapezius, and lower elevation angles for the arms. The different measurement methods were complementary in evaluating the upper limbs during handling.

  13. Automation and remote handling activities in BARC: an overview

    International Nuclear Information System (INIS)

    Badodkar, D.N.

    2016-01-01

    Division of Remote Handling and Robotics, BARC has been working on design and development of various application specific remote handling and automation systems for nuclear front-end and back-end fuel cycle technologies. Division is also engaged in preservice and in-service inspection of coolant channels for Pressurized Heavy Water Reactors in India. Design and development of Reactor Control Mechanisms for Nuclear Research and Power Reactors (PHWRs and Compact LWRs) is another important activity carried out in this division. Robotic systems for Indoor and Outdoor surveillance in and around nuclear installations have also been developed. A line scan camera based system has been developed for measuring individual PHWR fuel pellet lengths as well as stack length. An industrial robot is used for autonomous exchange of pellets to achieve desired stack length. The system can be extended for active fuel pellets also. An automation system has been conceptualized for remote handling and transfer of spent fuel bundles from storage pool directly to the chopper unit of reprocessing plant. In case of Advanced Heavy Water Reactor which uses mixed oxides of (Th-Pu) and (Th-"2"3"3U ) as fuel, automation system for front-end fuel cycle has been designed, which includes Powder processing and pressing; Pellet handling and inspection; Pin handling and inspection; and Cluster assembly and dis-assembly in shielded facilities. System demonstration through fullscale mock-up facility is nearing completion. Above talk is presented on behalf of all the officers and staff of DRHR. The talk is mainly focused on development of an automated fuel fabrication facility for mixed oxides of (Th- Pu)/(Th-"2"3"3U ) fuel pins. An overview of divisional ongoing activities in the field of remote handling and automation are also covered. (author)

  14. Handling, storage, uses and disposal of unsealed radionuclides in hospitals and medical research establishments. A report of Committees 3 and 4 of the International Commission on Radiological Protection. Adopted by the Commission in November 1976. ICRP Publication 25

    Energy Technology Data Exchange (ETDEWEB)

    1977-01-01

    The report is in sections, entitled: hazards associated with radioactive sources and procedures: protection facilities; organization and responsibility; working techniques and protection of workers; protection of the patient; protection of individual members of the public; medical research; control of radioactive contamination; monitoring; radioactive waste; emergency procedures; storage and transport of radioactive materials; leakage from sealed and plated radioactive sources.

  15. Interim and final storage casks

    International Nuclear Information System (INIS)

    Stumpfrock, L.; Kockelmann, H.

    2012-01-01

    The disposal of radioactive waste is a huge social challenge in Germany and all over the world. As is well known the search for a site for a final repository for high-level waste in Germany is not complete. Therefore, interim storage facilities for radioactive waste were built at plant sites in Germany. The waste is stored in these storage facilities in appropriate storage and transport casks until the transport in a final repository can be carried out. Licensing of the storage and transport casks aimed for use in the public space is done according to the traffic laws and for handling in the storage facility according to nuclear law. Taking into account the activity of the waste to be stored, different containers are in use, so that experience is available from the licensing and operation in interim storage facilities. The large volume of radioactive waste to be disposed of after the shut-down of power generation in nuclear power stations makes it necessary for large quantities of licensed storage and transport casks to be provided soon.

  16. Full scale tests on remote handled FFTF fuel assembly waste handling and packaging

    International Nuclear Information System (INIS)

    Allen, C.R.; Cash, R.J.; Dawson, S.A.; Strode, J.N.

    1986-01-01

    Handling and packaging of remote handled, high activity solid waste fuel assembly hardware components from spent FFTF reactor fuel assemblies have been evaluated using full scale components. The demonstration was performed using FFTF fuel assembly components and simulated components which were handled remotely using electromechanical manipulators, shielding walls, master slave manipulators, specially designed grapples, and remote TV viewing. The testing and evaluation included handling, packaging for current and conceptual shipping containers, and the effects of volume reduction on packing efficiency and shielding requirements. Effects of waste segregation into transuranic (TRU) and non-transuranic fractions also are discussed

  17. Biodiesel Handling and Use Guide (Fifth Edition)

    Energy Technology Data Exchange (ETDEWEB)

    Alleman, T.L.; McCormick, R.L.; Christensen, E.D.; Fioroni, G.; Moriarty. K.; Yanowitz, J.

    2016-11-08

    This document is a guide for those who blend, distribute, and use biodiesel and biodiesel blends. It provides basic information on the proper and safe use of biodiesel and biodiesel blends in engines and boilers, and is intended to help fleets, individual users, blenders, distributors, and those involved in related activities understand procedures for handling and using biodiesel fuels.

  18. Interaction orientation and complaint handling?

    NARCIS (Netherlands)

    Ramani, G.V.; Knox, George; Kumar, V.; Shah, D.

    2015-01-01

    Marketing managers have had to reinvent their marketing practices during the last decade to cope with the disruption of traditional marketing channels and the reintegration of customers and marketers in an Internet-driven eco-system. The marketing environment today allows unprecedented and often

  19. Genetics and Forest Seed Handling

    DEFF Research Database (Denmark)

    Schmidt, Lars Holger

    2016-01-01

    High genetic quality seed is obtained from seed sources that match the planting site, have a good outcrossing rate, and are superior in some desirable characters. Non-degraded natural forests and plantations may be used as untested seed sources, which can sometimes be managed to promote outbreeding...... and increase seed production. Planted seed orchards aim at capturing large genetic variation and are planted in a design that facilitates genetic evaluation and promotes outbred seed production. Good seed production relies upon success of the whole range of reproductive events from flower differentiation...

  20. Cask handling method and apparatus

    International Nuclear Information System (INIS)

    Yoli, A.H.; Husain, I.

    1977-01-01

    The method of transferring radioactive material into and out of the cask comprises positioning a tank with an open end in a well. Then a cask having a passage for moving radioactive material into and out of the cask is placed in the tank through the opening in the tank. The tank opening is then sealed to the cask relative to the well without sealing the passage relative to the well to prevent water filled into the well from leaking into the tank. Then the well is filled with water above the seal, and radioactive material is then moved through the water in the well through the passage into the cask. The tank may be filled with demineralized water from a separate source to pressurize the space in the tank on the other side of the seal from the well to prevent water in the well from entering the tank. The water level in the well and in the tank is then lowered, the tank opening to the cask seal is removed, and a cover is attached to the cask passage to maintain the radioactive material and contaminated water in the cask. The apparatus which accomplishes the above method comprises a tank in a well for receiving a cask therein. A seal between the tank and the cask prevents water in the well from flowing into the tank about the cask and permits water in the well to flow through the cask opening into the cask. A first water supply means raises and lowers the water level in the well, and a second water supply means supplies clean demineralized water to the tank under pressure to prevent water in the well from leaking into the tank. The seal is annularly shaped and is attached to the top of the tank. The central portion of the annular seal is aligned with the cask opening and it has means to seal the annular seal to the cask

  1. Beam handling and transport solutions

    Energy Technology Data Exchange (ETDEWEB)

    Maggiore, M. [Laboratori Nazionali di Legnaro, INFN, Via Universita' 2, Legnaro (PD) (Italy); Cirrone, G. A. P.; Schillaci, F.; Scuderi, V. [Istituto Nazionale di Fisica Nucleare, Laboratori Nazionali del Sud, Via Santa Sofia 62, Catania, Italy and Institute of Physics Czech Academy of Science, ELI-Beamlines project, Na Slovance 2, Prague (Czech Republic); Carpinelli, M. [INFN Sezione di Cagliari, c/o Dipartimento di Fisica, Università di Cagliari, Cagliari (Italy); Cuttone, G.; Romano, F. [Istituto Nazionale di Fisica Nucleare, Laboratori Nazionali del Sud, Via Santa Sofia 62, Catania (Italy); Tramontana, A. [Istituto Nazionale di Fisica Nucleare, Laboratori Nazionali del Sud, Via Santa Sofia 62, Catania, Italy and Universita' degli Studi di Catania, Dipartimento di Fisica, Via S. Sofia 64, Catania (Italy)

    2013-07-26

    The main purpose of the present study is to investigate the possibility to characterize the particle beams produced by the laser-target interaction in terms of collection, focusing and energy selection in order to evaluate the feasibility of a laser-driven facility in the field of medical application and, in particular, for hadrontherapy.

  2. Beam handling and transport solutions

    International Nuclear Information System (INIS)

    Maggiore, M.; Cirrone, G. A. P.; Schillaci, F.; Scuderi, V.; Carpinelli, M.; Cuttone, G.; Romano, F.; Tramontana, A.

    2013-01-01

    The main purpose of the present study is to investigate the possibility to characterize the particle beams produced by the laser-target interaction in terms of collection, focusing and energy selection in order to evaluate the feasibility of a laser-driven facility in the field of medical application and, in particular, for hadrontherapy

  3. Thorium-applications and handling

    International Nuclear Information System (INIS)

    Reichelt, A.

    1993-01-01

    The most important aspects concerning the natural occurrence and extraction of thorium are presented the topics covered are: natural isotopes, occurence in minerals, thorium-activity-content of naturally occuring materials, the resulting radiation exposure, extraction of thorium from ores, time-dependent activity after separation. The sources of radiation exposure due to Thorium, caused by human activity, can be divided into two categories, namely, those in which thorium is deliberately added to (consumer) products in order to improve their usefullness, and those in which the thorium is present accidentally and unwanted due to the naturally occuring thorium in the material used in the manufacturing processes. Some examples of such products and substances will be presented and results about their specific thorium activity will be discussed. Experimental data from a currently running research programme, will be presented, and will include results concerning the radiation occupational exposure due to phosphate fertilizers, thorium impregnated gas mantles and the use of thoriated TIG-Electrodes in arc welding. (orig.) [de

  4. Sorting and handling laser targets

    International Nuclear Information System (INIS)

    Kuehnle, J.H.

    1975-05-01

    Techniques have been developed for separating round, hollow microspheres having uniform wall thickness from bulk quantities of glass and metal microballoons. The process is capable of yielding small quantities of thin-walled (1 μm), closely-sized microspheres, in the diameter range of 20 to 250 μm. The air jet sieving and microradiographic techniques employed are described. (U.S.)

  5. Handling and disposing of radioactive waste

    International Nuclear Information System (INIS)

    Trauger, D.B.

    1983-01-01

    Radioactive waste has been separated by definition into six categories. These are: commercial spent fuel; high-level wastes; transuranium waste; low-level wastes; decommissioning and decontamination wastes; and mill tailings and mine wastes. Handling and disposing of these various types of radioactive wastes are discussed briefly

  6. Handling and processing of radioactive waste from nuclear applications

    International Nuclear Information System (INIS)

    2001-01-01

    The main objective of this report is to provide technical information and reference material on different steps and components of radioactive waste management for staff in establishments that use radionuclides and in research centres in Member States. It provides technical information on the safe handling, treatment, conditioning and storage of waste arising from the various activities associated with the production and application of radioisotopes in medical, industrial, educational and research facilities. The technical information cited in this report consists mainly of processes that are commercialised or readily available, and can easily be applied as they are or modified to solve specific waste management requirements. This report covers the sources and characteristics of waste and approaches to waste classification, and describes the particular processing steps from pretreatment until storage of conditioned packages

  7. FACSIM/MRS [Monitored Retrievable Storage]-2: Storage and shipping model documentation and user's guide

    International Nuclear Information System (INIS)

    Huber, H.D.; Chockie, A.D.; Hostick, C.J.; Otis, P.T.; Sovers, R.A.

    1987-06-01

    The Pacific Northwest Laboratory (PNL) has developed a stochastic computer model, FACSIM/MRS, to assist in assessing the operational performance of the Monitored Retrievable Storage (MRS) waste-handling facility. This report provides the documentation and user's guide for FACSIM/MRS-2, which is also referred to as the back-end model. The FACSIM/MRS-2 model simulates the MRS storage and shipping operations, which include handling canistered spent fuel and secondary waste in the shielded canyon cells, in onsite yard storage, and in repository shipping cask loading areas

  8. Canadian capabilities in fusion fuels technology and remote handling

    International Nuclear Information System (INIS)

    1987-10-01

    This report describes Canadian expertise in fusion fuels technology and remote handling. The Canadian Fusion Fuels Technology Project (CFFTP) was established and is funded by the Canadian government, the province of Ontario and Ontario Hydro to focus on the technology necessary to produce and manage the tritium and deuterium fuels to be used in fusion power reactors. Its activities are divided amongst three responsibility areas, namely, the development of blanket, first wall, reactor exhaust and fuel processing systems, the development of safe and reliable operating procedures for fusion facilities, and, finally, the application of these developments to specific projects such as tritium laboratories. CFFTP also hopes to utilize and adapt Canadian developments in an international sense, by, for instance, offering training courses to the international tritium community. Tritium management expertise is widely available in Canada because tritium is a byproduct of the routine operation of CANDU reactors. Expertise in remote handling is another byproduct of research and development of of CANDU facilities. In addition to describing the remote handling technology developed in Canada, this report contains a brief description of the Canadian tritium laboratories, storage beds and extraction plants as well as a discussion of tritium monitors and equipment developed in support of the CANDU reactor and fusion programs. Appendix A lists Canadian manufacturers of tritium equipment and Appendix B describes some of the projects performed by CFFTP for offshore clients

  9. Remote Inspection, Measurement and Handling for LHC

    CERN Document Server

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

    2007-01-01

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

  10. Uranium hexafluoride: Handling procedures and container descriptions

    International Nuclear Information System (INIS)

    1987-09-01

    The US Department of Energy (DOE) guidelines for packaging, measuring, and transferring uranium hexafluoride (UF 6 ) have been undergoing continual review and revision for several years to keep them in phase with developing agreements for the supply of enriched uranium. Initially, K-1323 ''A Brief Guide to UF 6 Handling,'' was issued in 1957. This was superceded by ORO-651, first issued in 1966, and reissued in 1967 to make editorial changes and to provide minor revisions in procedural information. In 1968 and 1972, Revisions 2 and 3, respectively, were issued as part of the continuing effort to present updated information. Revision 4 issued in 1977 included revisions to UF 6 cylinders, valves, and methods to use. Revision 5 adds information dealing with pigtails, overfilled cylinders, definitions and handling precautions, and cylinder heel reduction procedures. Weighing standards previously presented in ORO-671, Vol. 1 (Procedures for Handling and Analysis of UF 6 ) have also been included. This revision, therefore, supercedes ORO-671-1 as well as all prior issues of this report. These guidelines will normally apply in all transactions involving receipt or shipment of UF 6 by DOE, unless stipulated otherwise by contracts or agreements with DOE or by notices published in the Federal Register. Any questions or requests for additional information on the subject matter covered herein should be directed to the United States Department of Energy, P.O. Box E, Oak Ridge, Tennessee 37831, Attention: Director, Uranium Enrichment Operations Division. 33 figs., 12 tabs

  11. Large-component handling equipment and its use

    International Nuclear Information System (INIS)

    Krieg, S.A.; Swannack, D.L.

    1983-01-01

    The Fast Flux Test Facility (FFTF) reactor systems have special requirements for component replacements during maintenance servicing. Replacement operations must address handling of equipment within shielded metal containers while maintaining an inert atmosphere to prevent reaction of sodium with air. Plant identification of a failed component results in selecting and assembling the maintenance cask and equipment transport system for transfer from the storage facility to the Reactor Containment Building (RCB). This includes a proper diameter and length cask, inert atmosphere control consoles, component lift fixture and support structure for interface with the facility area surrounding the component. This equipment is staged in modular groups in the Reactor Service Building for transfer through the equipment airlock to the containment interior. The failed component is generally prepared for replacement by installation of the special lifting fixture attachment. Assembly of the cask support structure is performed over the component position on the containment building operating floor. The cask and shroud from the reactor interface are inerted after all manual service connections and handling attachments are completed. The component is lifted from the reactor and into the cask interior through a floor valve which is then closed to isolate the component reactor port. The cask with sodium wetted component is transferred to a service/repair location, either within containment or outside, to the Maintenance Facility cleaning and repair area. The complete equipment and handling operations for replacement of a large reactor component are described

  12. Heat transport and storage

    International Nuclear Information System (INIS)

    Despois, J.

    1977-01-01

    Recalling the close connections existing between heat transport and storage, some general considerations on the problem of heat distribution and transport are presented 'in order to set out the problem' of storage in concrete form. This problem is considered in its overall plane, then studied under the angle of the different technical choices it involves. The two alternatives currently in consideration are described i.e.: storage in a mined cavity and underground storage as captive sheet [fr

  13. Vestibule and Cask Preparation Mechanical Handling Calculation

    International Nuclear Information System (INIS)

    Ambre, N.

    2004-01-01

    The scope of this document is to develop the size, operational envelopes, and major requirements of the equipment to be used in the vestibule, cask preparation area, and the crane maintenance area of the Fuel Handling Facility. This calculation is intended to support the License Application (LA) submittal of December 2004, in accordance with the directive given by DOE correspondence received on the 27th of January 2004 entitled: ''Authorization for Bechtel SAIC Company L.L.C. to Include a Bare Fuel Handling Facility and Increased Aging Capacity in the License Application, Contract Number DE-AC--28-01R W12101'' (Ref. 167124). This correspondence was appended by further correspondence received on the 19th of February 2004 entitled: ''Technical Direction to Bechtel SAIC Company L.L. C. for Surface Facility Improvements, Contract Number DE-AC--28-01R W12101; TDL No. 04-024'' (Ref. 16875 1). These documents give the authorization for a Fuel Handling Facility to be included in the baseline. The limitations of this preliminary calculation lie within the assumptions of section 5 , as this calculation is part of an evolutionary design process

  14. A Perspective on Remote Handling Operations and Human Machine Interface for Remote Handling in Fusion

    International Nuclear Information System (INIS)

    Haist, B.; Hamilton, D.; Sanders, St.

    2006-01-01

    A large-scale fusion device presents many challenges to the remote handling operations team. This paper is based on unique operational experience at JET and gives a perspective on remote handling task development, logistics and resource management, as well as command, control and human-machine interface systems. Remote operations require an accurate perception of a dynamic environment, ideally providing the operators with the same unrestricted knowledge of the task scene as would be available if they were actually at the remote work location. Traditional camera based systems suffer from a limited number of viewpoints and also degrade quickly when exposed to high radiation. Virtual Reality and Augmented Reality software offer great assistance. The remote handling system required to maintain a tokamak requires a large number of different and complex pieces of equipment coordinating to perform a large array of tasks. The demands on the operator's skill in performing the tasks can escalate to a point where the efficiency and safety of operations are compromised. An operations guidance system designed to facilitate the planning, development, validation and execution of remote handling procedures is essential. Automatic planning of motion trajectories of remote handling equipment and the remote transfer of heavy loads will be routine and need to be reliable. This paper discusses the solutions developed at JET in these areas and also the trends in management and presentation of operational data as well as command, control and HMI technology development offering the potential to greatly assist remote handling in future fusion machines. (author)

  15. Tire, accident, handling, and roadway safety

    International Nuclear Information System (INIS)

    Logan, R.W.

    1994-01-01

    The authors are developing technology for an integrated package for the analysis of vehicle handling and impact into roadside features and into other vehicles. The program involves the development and use of rigid-body algorithms and Lawrence Livermore National Laboratory's DYNA and NIKE finite-element codes. The goal is a tool for use by engineers in industry and at federal and state Departments of Transportation, allowing good quantitative results at the workstation level. At the same time, the work enhances the authors' competency in furthering the development of DYNA and NIKE, and their expertise in spaceframe design for impact and crashworthiness

  16. Automatic refueling platform and CRD remote handling device for BWR plant

    International Nuclear Information System (INIS)

    Kato, Hiroaki; Takagi, Kaoru

    1978-01-01

    In BWR plants, machines for replacing fuel assemblies and control rod drives are usually operated directly by personnel. An automatic refueling platform and a CRD remote handling device aiming at radiation exposure reduction and handling perfectness are described, which are already used in BWR plants. Automation of the former is achieved in transporting fuel assemblies between a reactor pressure vessel and a fuel storage pool, shuffling fuel assemblies in a reactor core and moving fuel assemblies in a fuel storage pool. In the latter, replacement of CRDs is nearly all performed remotely. (Mori, K.)

  17. Computer vision-based evaluation of pre- and postrigor changes in size and shape of Atlantic cod (Gadus morhua) and Atlantic salmon (Salmo salar) fillets during rigor mortis and ice storage: effects of perimortem handling stress.

    Science.gov (United States)

    Misimi, E; Erikson, U; Digre, H; Skavhaug, A; Mathiassen, J R

    2008-03-01

    The present study describes the possibilities for using computer vision-based methods for the detection and monitoring of transient 2D and 3D changes in the geometry of a given product. The rigor contractions of unstressed and stressed fillets of Atlantic salmon (Salmo salar) and Atlantic cod (Gadus morhua) were used as a model system. Gradual changes in fillet shape and size (area, length, width, and roundness) were recorded for 7 and 3 d, respectively. Also, changes in fillet area and height (cross-section profiles) were tracked using a laser beam and a 3D digital camera. Another goal was to compare rigor developments of the 2 species of farmed fish, and whether perimortem stress affected the appearance of the fillets. Some significant changes in fillet size and shape were found (length, width, area, roundness, height) between unstressed and stressed fish during the course of rigor mortis as well as after ice storage (postrigor). However, the observed irreversible stress-related changes were small and would hardly mean anything for postrigor fish processors or consumers. The cod were less stressed (as defined by muscle biochemistry) than the salmon after the 2 species had been subjected to similar stress bouts. Consequently, the difference between the rigor courses of unstressed and stressed fish was more extreme in the case of salmon. However, the maximal whole fish rigor strength was judged to be about the same for both species. Moreover, the reductions in fillet area and length, as well as the increases in width, were basically of similar magnitude for both species. In fact, the increases in fillet roundness and cross-section height were larger for the cod. We conclude that the computer vision method can be used effectively for automated monitoring of changes in 2D and 3D shape and size of fish fillets during rigor mortis and ice storage. In addition, it can be used for grading of fillets according to uniformity in size and shape, as well as measurement of

  18. Radioactivity, shielding, radiation damage, and remote handling

    International Nuclear Information System (INIS)

    Wilson, M.T.

    1975-01-01

    Proton beams of a few hundred million electron volts of energy are capable of inducing hundreds of curies of activity per microampere of beam intensity into the materials they intercept. This adds a new dimension to the parameters that must be considered when designing and operating a high-intensity accelerator facility. Large investments must be made in shielding. The shielding itself may become activated and require special considerations as to its composition, location, and method of handling. Equipment must be designed to withstand large radiation dosages. Items such as vacuum seals, water tubing, and electrical insulation must be fabricated from radiation-resistant materials. Methods of maintaining and replacing equipment are required that limit the radiation dosages to workers.The high-intensity facilities of LAMPF, SIN, and TRIUMF and the high-energy facility of FERMILAB have each evolved a philosophy of radiation handling that matches their particular machine and physical plant layouts. Special tooling, commercial manipulator systems, remote viewing, and other techniques of the hot cell and fission reactor realms are finding application within accelerator facilities. (U.S.)

  19. 21 CFR 58.107 - Test and control article handling.

    Science.gov (United States)

    2010-04-01

    ... 21 Food and Drugs 1 2010-04-01 2010-04-01 false Test and control article handling. 58.107 Section... GOOD LABORATORY PRACTICE FOR NONCLINICAL LABORATORY STUDIES Test and Control Articles § 58.107 Test and control article handling. Procedures shall be established for a system for the handling of the test and...

  20. Getting to grips with remote handling and robotics

    Energy Technology Data Exchange (ETDEWEB)

    Mosey, D [Ontario Hydro, Toronto (Canada)

    1984-12-01

    A report on the Canadian Nuclear Society Conference on robotics and remote handling in the nuclear industry, September 1984. Remote handling in reactor operations, particularly in the Candu reactors is discussed, and the costs and benefits of use of remote handling equipment are considered. Steam generator inspection and repair is an area in which practical application of robotic technology has made a major advance.

  1. 30 CFR 75.817 - Cable handling and support systems.

    Science.gov (United States)

    2010-07-01

    ... High-Voltage Longwalls § 75.817 Cable handling and support systems. Longwall mining equipment must be provided with cable-handling and support systems that are constructed, installed and maintained to minimize... 30 Mineral Resources 1 2010-07-01 2010-07-01 false Cable handling and support systems. 75.817...

  2. Robotic liquid handling and automation in epigenetics.

    Science.gov (United States)

    Gaisford, Wendy

    2012-10-01

    Automated liquid-handling robots and high-throughput screening (HTS) are widely used in the pharmaceutical industry for the screening of large compound libraries, small molecules for activity against disease-relevant target pathways, or proteins. HTS robots capable of low-volume dispensing reduce assay setup times and provide highly accurate and reproducible dispensing, minimizing variation between sample replicates and eliminating the potential for manual error. Low-volume automated nanoliter dispensers ensure accuracy of pipetting within volume ranges that are difficult to achieve manually. In addition, they have the ability to potentially expand the range of screening conditions from often limited amounts of valuable sample, as well as reduce the usage of expensive reagents. The ability to accurately dispense lower volumes provides the potential to achieve a greater amount of information than could be otherwise achieved using manual dispensing technology. With the emergence of the field of epigenetics, an increasing number of drug discovery companies are beginning to screen compound libraries against a range of epigenetic targets. This review discusses the potential for the use of low-volume liquid handling robots, for molecular biological applications such as quantitative PCR and epigenetics.

  3. Materials Handling. Module SH-01. Safety and Health.

    Science.gov (United States)

    Center for Occupational Research and Development, Inc., Waco, TX.

    This student module on materials handling is one of 50 modules concerned with job safety and health. It presents the procedures for safe materials handling. Discussed are manual handling methods (lifting and carrying by hand) and mechanical lifting (lifting by powered trucks, cranes or conveyors). Following the introduction, 15 objectives (each…

  4. 21 CFR 225.35 - Use of work areas, equipment, and storage areas for other manufacturing and storage purpose.

    Science.gov (United States)

    2010-04-01

    ... not intended for animal feed use, such as fertilizers, herbicides, insecticides, fungicides, rodenticides, and other pesticides. Manufacturing, storage, or handling of nonfeed and feed products in the... the manufacture of fertilizers, herbicides, insecticides, fungicides, rodenticides, and other...

  5. Safety of handling, storing and transportation of spent nuclear fuel and vitrified high-level wastes

    International Nuclear Information System (INIS)

    Ericsson, A.M.

    1977-11-01

    The safety of handling and transportation of spent fuel and vitrified high-level waste has been studied. Only the operations which are performed in Sweden are included. That is: - Transportation of spent fuel from the reactors to an independant spent fuel storage installation (ISFSI). - Temporary storage of spent fuel in the ISFSI. - Transportation of the spent fuel from the ISFSI to a foreign reprocessing plant. - Transportation of vitrified high-level waste to an interim storage facility. - Interim storage of vitrified high-level waste. - Handling of the vitrified high-level waste in a repository for ultimate disposal. For each stage in the handling sequence above the following items are given: - A brief technical description. - A description of precautionary measures considered in the design. - An analysis of the discharges of radioactive materials to the environment in normal operation. - An analysis of the discharges of radioactive materials due to postulated accidents. The dose to the public has been roughly and conservatively estimated for both normal and accident conditions. The expected rate of occurence are given for the accidents. The results show that above described handling sequence gives only a minor risk contribution to the public

  6. Spent fuel handling system for a geologic storage test at the Nevada Test Site

    International Nuclear Information System (INIS)

    Duncan, J.E.; House, P.A.; Wright, G.W.

    1980-01-01

    The Lawrence Livermore Laboratory is conducting a test of the geologic storage of encapsulated spent commercial reactor fuel assemblies in a granitic rock at the Nevada Test Site. The test, known as the Spent Fuel Test-Climax (SFT-C), is sponsored by the US Department of Energy, Nevada Operations Office. Eleven pressurized-water-reactor spent fuel assemblies are stored retrievably for three to five years in a linear array in the Climax stock at a depth of 420 m

  7. Waste Handling Shaft concrete liner degradation conclusions and recommendations

    International Nuclear Information System (INIS)

    1992-10-01

    The primary function of the Waste Handling Shaft (WHS) at the Waste Isolation Pilot Plant (WIPP) is to permit the transfer of radioactive waste from the surface waste handling building to the underground storage area. It also serves as an intake shaft for small volumes of air during normal storage operations and as an emergency escape route. Part of the construction was the placement of a concrete liner and steel reinforced key in 1984. During a routine shaft inspection in May 1990, some degradation of the WHS concrete liner was observed between the depths of 800 and 900 feet below the ground surface. Detailed investigations of the liner had been carried out by Sandia National Laboratories and by Westinghouse Electric Corporation Waste Isolation Division (WID) through Lankard Materials Laboratory. Observations, reports, and data support the conclusion that the concrete degradation, resulting from attack by chemically aggressive brine, is a localized phenomena. It is the opinion of the WID that the degradation is not considered an immediate or near term concern; this is supported by technical experts. WID recommendations have been made which, when implemented, will ensure an extended liner life. Based on the current assessment of available data and the proposed shaft liner monitoring program described in this report, it is reasonable to assume that the operational life of the concrete shaft liner can safely support the 25-year life of the WIPP. Analysis of data indicates that degradation of the shaft's concrete liner is attributed to chemically aggressive brine seeping through construction joints and shrinkage cracks from behind the liner in and around the 834-foot depth. Chemical and mechanical components of concrete degradation have been identified. Chemical attack is comprised of several stages of concrete alteration. The other component, mechanical degradation, results from the expansive forces of crystals forming in the concrete pore space

  8. Warmwassersphaere - handling and processing of hydrographic data

    Energy Technology Data Exchange (ETDEWEB)

    Sy, A

    1983-01-01

    This report reviews CTD data handling and the principle of processing for the profiling instrument 'Multisonde' as it is presently in use at the Institut fuer Meereskunde in Kiel, F.R.G., in the frame of the research programme 'Warmwassersphaere'. An introduction to the shipboard system of measuring and logging is given. An outline of both laboratory and in situ calibrations is presented. The main subject of this report is the processing of the data. Possible sources of errors in field measurements and their influence on data accuracy are discussed and the standard processing stages are described. A specific problem lies in data errors, which inhibit a routine processing. In order to edit these data a special filter, the median filter, is introduced. Its efficiency as well as the experiences gained through its practical application is described and discussed by means of comparison with conventional techniques. The data used for these tests were collected during the experiment Nordostatlantik '81.

  9. FFTF radioactive solid waste handling and transport

    International Nuclear Information System (INIS)

    Thomson, J.D.

    1982-01-01

    The equipment necessary for the disposal of radioactive solid waste from the Fast Flux Test Facility (FFTF) is scheduled to be available for operation in late 1982. The plan for disposal of radioactive waste from FFTF will utilize special waste containers, a reusable Solid Waste Cask (SWC) and a Disposable Solid Waste Cask (DSWC). The SWC will be used to transport the waste from the Reactor Containment Building to a concrete and steel DSWC. The DSWC will then be transported to a burial site on the Hanford Reservation near Richland, Washington. Radioactive solid waste generated during the operation of the FFTF consists of activated test assembly hardware, reflectors, in-core shim assemblies and control rods. This radioactive waste must be cleaned (sodium removed) prior to disposal. This paper provides a description of the solid waste disposal process, and the casks and equipment used for handling and transport

  10. Experience of safety and performance improvement for fuel handling equipment

    International Nuclear Information System (INIS)

    Gyoon Chang, Sang; Hee Lee, Dae

    2014-01-01

    The purpose of this study is to provide experience of safety and performance improvement of fuel handling equipment for nuclear power plants in Korea. The fuel handling equipment, which is used as an important part of critical processes during the refueling outage, has been improved to enhance safety and to optimize fuel handling procedures. Results of data measured during the fuel reloading are incorporated into design changes. The safety and performance improvement for fuel handling equipment could be achieved by simply modifying the components and improving the interlock system. The experience provided in this study can be useful lessons for further improvement of the fuel handling equipment. (authors)

  11. Remote handling recognition and display device

    International Nuclear Information System (INIS)

    Kimura, Motohiko.

    1979-01-01

    Purpose: To surely recognize the movements of remote handling equipments in a reactor by the use of a device in a simple structure. Constitution: A light emission surface and a light reception surface are provided, for example, putting therebetween a hook of a nob of a control rod as a remote control equipment. Depending on the position of the hook, there are two possible cases where the light can not arrive the light reception surface inhibited by the hook and where the light can be received not inhibited by the hook. By visually monitoring the presence or absence of the light reception from the outside of the reactor, the movement of the nob for the control rod can be recognized. Optical fibers connect the optical source with the light emission surface, and the light reception surface with the display surface. (Ikeda, J.)

  12. Enbridge system : crude types, transportation and handling systems

    Energy Technology Data Exchange (ETDEWEB)

    Anand, A. [Enbridge Corp., Edmonton, AB (Canada)

    2009-07-01

    The supply of crude oil from the Western Canada Sedimentary Basin is expected to increase by approximately 2.1 million barrels per day by 2015. The crudes that Enbridge handles range from 19 API to 40 API and 0.1 per cent sulphur to 4.7 per cent sulphur. The diverse supply of crude oil that the Enbridge system handles includes conventional heavy, synthetic heavy, heavy high tan, heavy low residual, medium, light sour, heavy sour, light sweet, light sweet synthetic, condensate and olefinic crudes. This presentation discussed Enbridge's plans for infrastructure expansion, crude types and quality assurance program. The company's infrastructure plans include the expansion of regional pipelines to bring more supplies to the mainline; expansion of the mainline capacity to existing markets; and providing pipeline access to new markets. Merchant storage terminals will be provided in some locations. The quality of various crude types will be maintained through judicious sequencing and tank bottoms crossings. tabs., figs.

  13. Equipment for the handling of thorium materials

    International Nuclear Information System (INIS)

    Heisler, S.W. Jr.; Mihalovich, G.S.

    1988-01-01

    The Feed Materials Production Center (FMPC) is the United States Department of Energy's storage facility for thorium. FMPC thorium handling and overpacking projects ensure the continued safe handling and storage of the thorium inventory until final disposition of the materials is determined and implemented. The handling and overpacking of the thorium materials requires the design of a system that utilizes remote handling and overpacking equipment not currently utilized at the FMPC in the handling of uranium materials. The use of remote equipment significantly reduces radiation exposure to personnel during the handling and overpacking efforts. The design system combines existing technologies from the nuclear industry, the materials processing and handling industry and the mining industry. The designed system consists of a modified fork lift truck for the transport of thorium containers, automated equipment for material identification and inventory control, and remote handling and overpacking equipment for material identification and inventory control, and remote handling and overpacking equipment for repackaging of the thorium materials

  14. Fusion potentials for Gk and handle squashing

    International Nuclear Information System (INIS)

    Crescimanno, M.

    1993-01-01

    Using Chern-Simons gauge theory, we show that the fusion ring of the conformal field theory G k (G any Lie algebra) is isomorphic to P[u]/(∇V) where (∇V) is the ideal generated by conditions ∇V=0. We explicitly construct V for all G k . We also derive a residue-like formula for the correlation functions in the Chern-Simons theory thus providing an RCFT version of the residue formula for the topological Landau-Ginzburg model. An operator that acts like a measure in this residue formula has the interpretation of a handle-squashing operator and explicit formulae for this operator are given. (orig.)

  15. Experience with failed or damaged spent fuel and its impacts on handling

    International Nuclear Information System (INIS)

    Bailey, W.J.

    1989-12-01

    Spent fuel management planning needs to include consideration of failed or damaged spent light-water reactor (LWR) fuel. Described in this paper, which was prepared under the Commercial Spent Fuel Management (CSFM) Program that is sponsored by the US Department of Energy (DOE), are the following: the importance of fuel integrity and the behavior of failed fuel, the quantity and burnup of failed or damaged fuel in storage, types of defects, difficulties in evaluating data on failed or damaged fuel, experience with wet storage, experience with dry storage, handling of failed or damaged fuel, transporting of fuel, experience with higher burnup fuel, and conclusions. 15 refs

  16. Apparatus and process for handling dangerous fluent material

    International Nuclear Information System (INIS)

    Stock, A.J.; Christofer, D.E.; Brinza, J.E.

    1976-01-01

    Systems, apparatus and methods are disclosed for disposing of radioactive waste materials by placing them into a container such as a steel drum, together with cement or other solidifying agent and water or other suitable liquid in amounts sufficient to provide eventually a solidified mixture of predetermined amounts of cement or other solidifying agent and radioactive material, closing the drum, agitating the mixture in the drum for mixing the contents, and then storing the drum for at least a period of time sufficient to permit partial decay of radioactive materials or to await available time for shipment. Also disclosed are remotely controlled apparatus for handling both empty and filled drums, for placing the drums in and removing drums from enclosed drumming equipment where they have been filled and agitated, for accurately placing the drums containing radioactive material in storage, and for removing the drums from storage and loading them on a vehicle for transportation. All of these operations are done by remote control with a high degree of safety to the operators and maintenance personnel from radiation and freedom of the ambient from radiation pollution

  17. Software for fast cameras and image handling on MAST

    International Nuclear Information System (INIS)

    Shibaev, S.

    2008-01-01

    The rapid progress in fast imaging gives new opportunities for fusion research. The data obtained by fast cameras play an important and ever-increasing role in analysis and understanding of plasma phenomena. The fast cameras produce a huge amount of data which creates considerable problems for acquisition, analysis, and storage. We use a number of fast cameras on the Mega-Amp Spherical Tokamak (MAST). They cover several spectral ranges: broadband visible, infra-red and narrow band filtered for spectroscopic studies. These cameras are controlled by programs developed in-house. The programs provide full camera configuration and image acquisition in the MAST shot cycle. Despite the great variety of image sources, all images should be stored in a single format. This simplifies development of data handling tools and hence the data analysis. A universal file format has been developed for MAST images which supports storage in both raw and compressed forms, using either lossless or lossy compression. A number of access and conversion routines have been developed for all languages used on MAST. Two movie-style display tools have been developed-Windows native and Qt based for Linux. The camera control programs run as autonomous data acquisition units with full camera configuration set and stored locally. This allows easy porting of the code to other data acquisition systems. The software developed for MAST fast cameras has been adapted for several other tokamaks where it is in regular use

  18. Spent fuel receipt and storage at the Morris Operation

    International Nuclear Information System (INIS)

    Astrom, K.A.; Eger, K.J.

    1978-06-01

    Operating and maintenance activities in an independent spent fuel storage facility are described, and current regulations governing such activities are summarized. This report is based on activities at General Electric's licensed storage facility located near Morris, Illinois, and includes photographs of cask and fuel handling equipment used during routine operations

  19. Development of remote handling tools and equipment

    International Nuclear Information System (INIS)

    Nakahira, Masataka; Oka, Kiyoshi; Taguchi, Kou; Ito, Akira; Fukatsu, Seiichi; Oda, Yasushi; Kajiura, Soji; Yamazaki, Seiichiro; Aoyama, Kazuo.

    1997-01-01

    The remote handling (RH) tools and equipment development in ITER focuses mainly on the welding and cutting technique, weld inspection and double-seal door which are essential factors in the replacement of in-vessel components such as divertor and blanket. The conceptual design of these RH tools and equipment has been defined through ITER engineering design activity (EDA). Similarly, elementary R and D of the RH tools and equipment have been extensively performed to accumulate a technological data base for process and performance qualification. Based on this data, fabrications of full-scale RH tools and equipment are under progress. A prototypical bore tool for pipe welding and cutting has already been fabricated and is currently undergoing integrated performance tests. This paper describes the design outline of the RH tools and equipment related to in-vessel components maintenance, and highlights the current status of RH tools and equipment development by the Japan Home Team as an ITER R and D program. This paper also includes an outline of insulation joint and quick-pipe connector development, which has also been conducted through the ITER R and D program in order to standardize RH operations and components. (author)

  20. Radioactive waste treatment and handling in France

    International Nuclear Information System (INIS)

    Sivintsev, Yu.V.

    1984-01-01

    Classification of radioactive wastes customary in France and the program of radiation protection in handling them are discussed. Various methods of radioactive waste processing and burial are considered. The French classification of radioactive wastes differs from one used in the other countries. Wastes are classified under three categories: A, B and C. A - low- and intermediate-level radioactive wastes with short-lived radionuclides (half-life - less than 30 years, negligible or heat release, small amount of long-lived radionuclides, especially such as plutonium, americium and neptunium); B - low- and intermediate-level radioactive wastes with long-lived radionuclides (considerable amounts of long-lived radionuclides including α-emitters, low and moderate-level activity of β- and γ-emitters, low and moderate heat release); C - high-level radioactive wastes with long-lived radionuclides (high-level activity of β- and γ-emitters, high heat release, considerable amount of long-lived radionuclides). Volumetric estimations of wastes of various categories and predictions of their growth are given. It is noted that the concept of closed fuel cycle with radiochemical processing of spent fuel is customary in France

  1. Electronic astronomical information handling and flexible publishing.

    Science.gov (United States)

    Heck, A.

    The current dramatic evolution in information technology is bringing major modifications in the way scientists work and communicate. The concept of electronic information handling encompasses the diverse types of information, the different media, as well as the various communication methodologies and technologies. It ranges from the very collection of data until the final publication of results and sharing of knowledge. New problems and challenges result also from the new information culture, especially on legal, ethical, and educational grounds. Electronic publishing will have to diverge from an electronic version of contributions on paper and will be part of a more general flexible-publishing policy. The benefits of private publishing are questioned. The procedures for validating published material and for evaluating scientific activities will have to be adjusted too. Provision of electronic refereed information independently from commercial publishers in now feasible. Scientists and scientific institutions have now the possibility to run an efficient information server with validated (refereed) material without the help of a commercial publishers.

  2. Preparation and handling of superconducting RF cavities

    International Nuclear Information System (INIS)

    Furuya, Takaaki

    1990-01-01

    The present paper outlines the recent preparation methods for superconducting cavities used in various laboratories and universities, and reports the problems of the cavity fabrication at KEK as an example of mass production. Preparation and handling are first addressed, focusing on material, fabrication, surface treatment, rinsing, clean environment, and heat treatment. Cavity production at KEK is then described, centering on defects on the surface and clean environments. Field gradients of more than 20 MV/m have been obtained by 1.5-3 GHz single cavities, for multi-cell cavities Eacc of 10 MV/m are available at any frequency range. The successful construction of thirty-two cavities for TRISTAN at KEK is due to the careful checking of the surface and quality control of all processes against the surface defects and contaminations. Eacc of 5 MV/m has been achieved by 94 % of the TRISTAN cavities at the first cold test, but 6 % of them had to be reworked because of the surface defects. These defects could not be detected by an X-ray photograph or visual inspections during the fabrication processes. (N.K.)

  3. NaK handling and removal

    International Nuclear Information System (INIS)

    Desreumaux, J.; Rodriguez, G.; Guigon, A.; Verdelli, J.; Thomine, G.

    1997-01-01

    Sodium-potassium alloy is used in specific application in French Fast Breeder Reactors as: cold traps, NaK bubbler for argon purification, valves and also in experimental irradiation devices. lt has been preferred to sodium because it is liquid from + 7 deg. C for the most common peritectic alloy. After its use, NaK is considered as a hazardous waste (nuclear or not) due to its high reactivity with air and water. The most important risk remains in handling NaK systems which have not been operated for some time. The NaK will be covered with a crust of the superoxide K02 which is a strong oxidising agent. Thermodynamically, K02 will react with most organic material or metallic dust or swarfs and can also react with additional NaK to give sufficient heat to boil part of the NaK, resulting in a sudden increase in pressure and small explosions. We describe the formation given to experimenters in our Sodium School and the CEA's experience in treating specific devices for transportation, decanting of tanks, tank opening and NaK removal. (author)

  4. Handling and disposal of radioactive scrap

    International Nuclear Information System (INIS)

    Witte, K.

    1975-01-01

    The 9th special course for journalists was in this year on the highly topical subject 'handling and disposal of radioactive scrap'. It was held on the 26th and 27th May 1975 at the Nuclear Research Centre at Karlsruhe. These courses have been held for several years by the Nuclear Research Association (GfK) in the School for Nuclear Engineering and are intended mainly to contribute to journalists of the daily papers, radio and television who are 'not previously technically trained' an introduction into the difficult subject matter of nuclear engineering with its ancillary areas. In view of the many discussions carried on in public the course is further intended to achieve that the problems discussed are treated by means of publicity which is free from emotion. In the journalists' course this year specially selected experts gave technical information prepared for general information as to how radioactive waste can be safely worked up and then finally stored without adverse effects on the environment. Since the interesting collection of questions was put forward in a compressed form and at the same time clearly presented, the author reports on the different separate subjects on which lectures were given. (orig.) [de

  5. Enhanced wood fuel handling: market and design studies

    Energy Technology Data Exchange (ETDEWEB)

    Landen, R.; Rippengal, R.; Redman, A.N.

    1997-09-01

    This report examines the potential for the manufacture and sale of novel wood fuel handling systems as a means of addressing users' concerns regarding current capital costs and potential high labour costs of non-automated systems. The report considers fuel handling technology that is basically appropriate for wood-fired heating systems of between c.100kW and c.1MW maximum continuous rating. This report details work done by the project collaborators in order to: (1) assess the current status of wood fuel handling technology; (2) evaluate the market appetite for improved wood fuel handling technology; (3) derive capital costs which are acceptable to customers; (4) review design options; and (5) select one or more design options worthy of further development. The current status of wood fuel handling technology is determined, and some basic modelling to give guidance on acceptable capital costs of 100-1000kW wood fuel handling systems is undertaken. (author)

  6. Fabrication and handling of bentonite blocks

    International Nuclear Information System (INIS)

    1978-06-01

    In accordance with the project for the final storage of spent nuclear fuel, the waste will be encapsulated into copper canisters, which will be deposited in a final repository located in rock 500 m below ground level. The canisters will be placed in vertical holes in the bottoms of the tunnels, where the copper cylinders will be surrounded by blocks of highly compacted bentonite. When the blocks are saturated with water and expansion is essentially retained as in the actual case, a very high swelling pressure will arise. The bentonite will be extremely impermeable and thus it will form a barrier against transport of corrosive matters to the canister. The blocks are fabricated by means of cold isostatic pressing of bentonite powder. The base material in the form of powder is enclosed in flexible forms, which are introduced into pressure vessels where the forms are surrounded by oil or water. Thus the powder is compacted into rigid bodies with a bulk density of about 2.2 t/m 3 for ''air dry'' bentonite, which might be compared with a specific density of about 2.7 t/m 3 . The placing of a canister is preceded by piling up bentonite blocks to a level just below the canister lid position, after which the slot around the blocks is filled with bentonite powder. The rest of the blocks are mounted after filling bentonite powder into the inner slot around the canister as well. Finally the storage tunnels will be sealed by filling them with a mixture o02067NRM 0000181 45

  7. Data handling and post-reconstruction analysis at next generation experiments

    International Nuclear Information System (INIS)

    Fischler, M.; Lammel, S.

    1995-11-01

    A new generation of experiments in high energy physics is approaching. With the approval of the LHC at CERN and the revised Main Injector project at Fermilab, high statistics experiments will start operation within 5 to 10 years. With luminosities Up to 10 34 /cm 2 /sec and several hundred thousand readout channels, data most likely cannot be handled and analysed using traditional HEP approaches. The CAP group at Fermilab is investigating different approaches to data handling and organization for post-reconstruction analysis. We discuss the approaches considered, their strengths and weaknesses, integration with hierarchical storage, and sharing of primary data resources

  8. FACSIM/MRS (Monitored Retrievable Storage)-2: Storage and shipping model documentation and user's guide

    Energy Technology Data Exchange (ETDEWEB)

    Huber, H.D.; Chockie, A.D.; Hostick, C.J.; Otis, P.T.; Sovers, R.A.

    1987-06-01

    The Pacific Northwest Laboratory (PNL) has developed a stochastic computer model, FACSIM/MRS, to assist in assessing the operational performance of the Monitored Retrievable Storage (MRS) waste-handling facility. This report provides the documentation and user's guide for FACSIM/MRS-2, which is also referred to as the back-end model. The FACSIM/MRS-2 model simulates the MRS storage and shipping operations, which include handling canistered spent fuel and secondary waste in the shielded canyon cells, in onsite yard storage, and in repository shipping cask loading areas.

  9. Legal provisions concerning the handling and disposal of radioactive waste in international and national law

    International Nuclear Information System (INIS)

    Bischof, W.

    1980-01-01

    The development and present state of legislation and regulation in the field of handling and disposal of radioactive waste is surveyed. On the basis of the comprehensive collection of all legal sources of atomic energy law, including the radiation protection law of the Institute of Public International Law of the Goettingen University (Germany, F.R.), the report will consider provisions of international organizations (IAEA, OECD-NEA, EURATOM-Basic Norms, ICRP), of international agreements (London, Barcelona, Paris, Helsinki Conventions; civil liability conventions) and of the national law of different countries (USA, UK, France, Germany, F.R. and D.R., Italy, Switzerland, Belgium, the Netherlands, Spain). The following subjects are considered: notion and definition of radioactive waste, license-system for handling, storage and disposal; exemptions; licensing of nuclear installations and waste disposal; obligation to deliver radioactive wastes; centralized interim and final storage installations; penalties. (H.K.)

  10. The PAMELA storage and control unit

    Energy Technology Data Exchange (ETDEWEB)

    Casolino, M. [INFN, Structure of Rome II, Physics Department, University of Rome II ' Tor Vergata' , I-00133 Rome (Italy)]. E-mail: Marco.Casolino@roma2.infn.it; Altamura, F. [INFN, Structure of Rome II, Physics Department, University of Rome II ' Tor Vergata' , I-00133 Rome (Italy); Basili, A. [INFN, Structure of Rome II, Physics Department, University of Rome II ' Tor Vergata' , I-00133 Rome (Italy); De Pascale, M.P. [INFN, Structure of Rome II, Physics Department, University of Rome II ' Tor Vergata' , I-00133 Rome (Italy); Minori, M. [INFN, Structure of Rome II, Physics Department, University of Rome II ' Tor Vergata' , I-00133 Rome (Italy); Nagni, M. [INFN, Structure of Rome II, Physics Department, University of Rome II ' Tor Vergata' , I-00133 Rome (Italy); Picozza, P. [INFN, Structure of Rome II, Physics Department, University of Rome II ' Tor Vergata' , I-00133 Rome (Italy); Sparvoli, R. [INFN, Structure of Rome II, Physics Department, University of Rome II ' Tor Vergata' , I-00133 Rome (Italy); Adriani, O. [INFN, Structure of Florence, Physics Department, University of Florence, I-50019 Sesto Fiorentino (Italy); Papini, P. [INFN, Structure of Florence, Physics Department, University of Florence, I-50019 Sesto Fiorentino (Italy); Spillantini, P. [INFN, Structure of Florence, Physics Department, University of Florence, I-50019 Sesto Fiorentino (Italy); Castellini, G. [CNR-Istituto di Fisica Applicata ' Nello Carrara' , I-50127 Florence (Italy); Boezio, M. [INFN, Structure of Trieste, Physics Department, University of Trieste, I-34147 Trieste (Italy)

    2007-03-01

    The PAMELA Storage and Control Unit (PSCU) comprises a Central Processing Unit (CPU) and a Mass Memory (MM). The CPU of the experiment is based on a ERC-32 architecture (a SPARC v7 implementation) running a real time operating system (RTEMS). The main purpose of the CPU is to handle slow control, acquisition and store data on a 2 GB MM. Communications between PAMELA and the satellite are done via a 1553B bus. Data acquisition from the sub-detectors is performed via a 2 MB/s interface. Download from the PAMELA MM towards the satellite main storage unit is handled by a 16 MB/s bus. The maximum daily amount of data transmitted to ground is about 20 GB.

  11. The PAMELA storage and control unit

    International Nuclear Information System (INIS)

    Casolino, M.; Altamura, F.; Basili, A.; De Pascale, M.P.; Minori, M.; Nagni, M.; Picozza, P.; Sparvoli, R.; Adriani, O.; Papini, P.; Spillantini, P.; Castellini, G.; Boezio, M.

    2007-01-01

    The PAMELA Storage and Control Unit (PSCU) comprises a Central Processing Unit (CPU) and a Mass Memory (MM). The CPU of the experiment is based on a ERC-32 architecture (a SPARC v7 implementation) running a real time operating system (RTEMS). The main purpose of the CPU is to handle slow control, acquisition and store data on a 2 GB MM. Communications between PAMELA and the satellite are done via a 1553B bus. Data acquisition from the sub-detectors is performed via a 2 MB/s interface. Download from the PAMELA MM towards the satellite main storage unit is handled by a 16 MB/s bus. The maximum daily amount of data transmitted to ground is about 20 GB

  12. Strategy for Handling and Treatment of INPP RBMK-1500 Irradiated Graphite

    International Nuclear Information System (INIS)

    Oryšaka, A.

    2016-01-01

    There are two RBMK-1500 water-cooled graphite-moderated channel-type power reactors at Ignalina NPP. After the final shutdown of the INPP, radioactive i-graphite dismantling, handling, conditioning, storage and disposal is an important part of the decommissioning activities. The core of the INPP unit 1 and 2 contains about 3600 tons of i-graphite. Formation of activation products strongly depends on the contents of impurities, operational mode and concentration of impurities in the graphite. The case study for INPP envisages the analysis of possibilities of graphite handling and treatment in the context of immediate decommissioning. (author)

  13. Remote-handled transuranic system assessment appendices. Volume 2

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-11-01

    Volume 2 of this report contains six appendices to the report: Inventory and generation of remote-handled transuranic waste; Remote-handled transuranic waste site storage; Characterization of remote-handled transuranic waste; RH-TRU waste treatment alternatives system analysis; Packaging and transportation study; and Remote-handled transuranic waste disposal alternatives.

  14. Remote-handled transuranic system assessment appendices. Volume 2

    International Nuclear Information System (INIS)

    1995-11-01

    Volume 2 of this report contains six appendices to the report: Inventory and generation of remote-handled transuranic waste; Remote-handled transuranic waste site storage; Characterization of remote-handled transuranic waste; RH-TRU waste treatment alternatives system analysis; Packaging and transportation study; and Remote-handled transuranic waste disposal alternatives

  15. Management and storage of radioactive waste

    International Nuclear Information System (INIS)

    Faussat, A.

    1995-01-01

    Management of radioactive waste is a matter of public concern. Such management, however, is today handled industrially in France, and when these techniques are well applied, its is possible to create storage centres. Waste having a short half-life is now stored in the Centre de l'Aube, which replaces the one begun in 1969 in the Department de la Manche. For waste with a long half-life, following the law passed in 1991, ANDRA is pursuing its programme of site prospecting to establish two underground laboratories for studying geological storage. (author). 2 figs., 1 tab

  16. 48 CFR 1852.211-70 - Packaging, handling, and transportation.

    Science.gov (United States)

    2010-10-01

    ... transportation. 1852.211-70 Section 1852.211-70 Federal Acquisition Regulations System NATIONAL AERONAUTICS AND... and Clauses 1852.211-70 Packaging, handling, and transportation. As prescribed in 1811.404-70, insert the following clause: Packaging, Handling, and Transportation (SEPT 2005) (a) The Contractor shall...

  17. Robotics and remote handling in the nuclear industry

    Energy Technology Data Exchange (ETDEWEB)

    1984-01-01

    This book presents the papers given at a conference on the use of remote handling equipment in nuclear facilities. Topics considered at the conference included dose reduction, artificial intelligence in nuclear plant maintenance, robotic welding, uncertainty covariances, reactor operation and inspection, reactor maintenance and repair, uranium mining, fuel fabrication, reactor component manufacture, irradiated fuel and radioactive waste management, and radioisotope handling.

  18. Complying with US and European complaint handling requirements.

    Science.gov (United States)

    Donawa, M E

    1997-09-01

    The importance of customer complaints for providing valuable information on the use of medical devices is clearly reflected in United States (US) and European quality system requirements for handling complaints. However, there are significant differences in US and European complaint handling requirements. This article will discuss those differences and methods for ensuring compliance.

  19. PND fuel handling decontamination program: specialized techniques and results

    International Nuclear Information System (INIS)

    Pan, R.; Hobbs, K.; Minnis, M.; Graham, K.

    1995-01-01

    The use of various decontamination techniques and equipment has become a critical part of Fuel Handling maintenance work at the Pickering Nuclear Station, an eight unit CANDU station located about 30 km east of Toronto. This paper presents an overview of the set up and techniques used for cleaning in the PND Fuel Handling Maintenance Facility, and the results achieved. (author)

  20. Apparatus and method for handling magnetic particles in a fluid

    Science.gov (United States)

    Holman, David A.; Grate, Jay W.; Bruckner-Lea, Cynthia J.

    2000-01-01

    The present invention is an apparatus and method for handling magnetic particles suspended in a fluid, relying upon the known features of a magnetic flux conductor that is permeable thereby permitting the magnetic particles and fluid to flow therethrough; and a controllable magnetic field for the handling. The present invention is an improvement wherein the magnetic flux conductor is a monolithic porous foam.

  1. Command and Data Handling Branch Internship

    Science.gov (United States)

    Billings, Rachel Mae

    2016-01-01

    Modular Integrated Stackable Layers (MISL) is a computer system designed for simple, fast, and cost effective flexible reconfiguration in space environments such as the ISS and Orion projects for various uses. Existing applications include wireless and wired communications, data acquisition and instrumentation, and camera systems, and potential applications include bus protocol converters and subsystem control. MISL is based on Texas Instruments (TI)' MSP430 16-bit ultra-low-power microcontroller device. The purpose of my project was to integrate the MISL system with a liquid crystal display (LCD) touchscreen. The LCD, manufactured by Crystalfontz and part number CFAF320240F-035T-TS, is a 320 by 240 RGB resistive color screen including an optional carrier board. The vast majority of the project was done with Altium Designer, a tool for printed circuit board (PCB) schematic capture, 3D design, and FPGA (Field Programmable Gate Array) development. The new PCB was to allow the LCD to directly stack to the rest of MISL. Research was done with datasheets for the TI microcontroller and touchscreen display in order to meet desired hardware specifications. Documentation on prior MISL projects was also utilized. The initial step was to create a schematic for the LCD, power bus, and data bus connections between components. A layout was then designed with the required physical dimensions, routed traces and vias, power and ground planes, layer stacks, and other specified design rules such as plane clearance and hole size. Multiple consultation sessions were held with Hester Yim, the technical discipline lead for the Command and Data Handling Branch, and Christy Herring, the lead PCB layout designer in the Electronic Design and Manufacturing Branch in order to ensure proper configuration. At the moment, the PCB is awaiting revision by the latter-mentioned branch. Afterwards, the board will begin to undergo the manufacturing and testing process. Throughout the internship at

  2. Handling wood shavings

    Energy Technology Data Exchange (ETDEWEB)

    1974-09-18

    Details of bulk handling equipment suitable for collection and compressing wood waste from commercial joinery works are discussed. The Redler Bin Discharger ensures free flow of chips from storage silo discharge prior to compression into briquettes for use as fuel or processing into chipboard.

  3. Challenges and innovative technologies on fuel handling systems for future sodium-cooled fast reactors

    International Nuclear Information System (INIS)

    Chassignet, Mathieu; Dumas, Sebastien; Penigot, Christophe; Prele, Gerard; Capitaine, Alain; Rodriguez, Gilles; Sanseigne, Emmanuel; Beauchamp, Francois

    2011-01-01

    The reactor refuelling system provides the means of transporting, storing, and handling reactor core subassemblies. The system consists of the facilities and equipment needed to accomplish the scheduled refuelling operations. The choice of a FHS impacts directly on the general design of the reactor vessel (primary vessel, storage, and final cooling before going to reprocessing), its construction cost, and its availability factor. Fuel handling design must take into account various items and in particular operating strategies such as core design and management and core configuration. Moreover, the FHS will have to cope with safety assessments: a permanent cooling strategy to prevent fuel clad rupture, plus provisions to handle short-cooled fuel and criteria to ensure safety during handling. In addition, the handling and elimination of residual sodium must be investigated; it implies specific cleaning treatment to prevent chemical risks such as corrosion or excess hydrogen production. The objective of this study is to identify the challenges of a SFR fuel handling system. It will then present the range of technical options incorporating innovative technologies under development to answer the GENERATION IV SFR requirements. (author)

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

    Energy Technology Data Exchange (ETDEWEB)

    Weiss, E.V.

    1997-03-06

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

  5. Highly active vitrification plant remote handling operational experience and improvements

    International Nuclear Information System (INIS)

    Milgate, I.

    1996-01-01

    All the main process plant and equipment at the Sellafield Waste Vitrification Plant (WVP) is enclosed in heavily shielded concrete walled cells. There is a large quantity of relatively complex plant and equipment which must be remotely operated, maintained or replaced in-cell in a severe environment. The WVP has five in-cell polar cranes which are of modular construction to aid replacement of failed components. Each can be withdrawn into a shielded cell extension for decontamination and hands-on maintenance. The cells have a total of 80 through wall tube positions to receive Master Slave Manipulators (MSMs). The MSMs are used where possible for ''pick and place'' purposes but are often called upon to position substantial pieces of mechanical equipment and thus are subject to heavy loading and high failure rates. An inward flow of air is maintained in the active cells. The discharged air passes through a filter cell where remote damper operation filter changing and maintenance is carried out by means of a PAR3000 manipulator. A Nuclear Engineered Advanced Teleoperated Robot (Neater) swabs the vitrified product container to ensure cleanliness before storage. There is a significant arising of solid radioactive waste from replaced in-cell items which undergoes sorting and size reduction in a breakdown cell equipped with a large reciprocating saw and a hydraulic shear. Improvements to the remote handling facilities made in the light of operational experience are described. (UK)

  6. A workflow for handling heterogeneous 3D models with the TOUGH2 family of codes: Applications to numerical modeling of CO 2 geological storage

    Science.gov (United States)

    Audigane, Pascal; Chiaberge, Christophe; Mathurin, Frédéric; Lions, Julie; Picot-Colbeaux, Géraldine

    2011-04-01

    This paper is addressed to the TOUGH2 user community. It presents a new tool for handling simulations run with the TOUGH2 code with specific application to CO 2 geological storage. This tool is composed of separate FORTRAN subroutines (or modules) that can be run independently, using input and output files in ASCII format for TOUGH2. These modules have been developed specifically for modeling of carbon dioxide geological storage and their use with TOUGH2 and the Equation of State module ECO2N, dedicated to CO 2-water-salt mixture systems, with TOUGHREACT, which is an adaptation of TOUGH2 with ECO2N and geochemical fluid-rock interactions, and with TOUGH2 and the EOS7C module dedicated to CO 2-CH 4 gas mixture is described. The objective is to save time for the pre-processing, execution and visualization of complex geometry for geological system representation. The workflow is rapid and user-friendly and future implementation to other TOUGH2 EOS modules for other contexts (e.g. nuclear waste disposal, geothermal production) is straightforward. Three examples are shown for validation: (i) leakage of CO 2 up through an abandoned well; (ii) 3D reactive transport modeling of CO 2 in a sandy aquifer formation in the Sleipner gas Field, (North Sea, Norway); and (iii) an estimation of enhanced gas recovery technology using CO 2 as the injected and stored gas to produce methane in the K12B Gas Field (North Sea, Denmark).

  7. Decree 2211: Standards to control the generation and handling of dangerous wastes

    International Nuclear Information System (INIS)

    1992-01-01

    This Decree has for object to establish the conditions under which should be carried out the activities of generation and handling of dangerous waste, in order to prevent damages to health and to the atmosphere. It includes: definitions; a list of sources of waste; a list of constituent of dangerous waste; the characteristics of danger; a lists of maximum permissible concentrations in leachates, handling of dangerous waste, criterion for transport, monitoring form, storage areas, treatment and final disposition, storage, elimination, incineration, recycling, reuse and recovery, installation and operation of security backfilling, book of waste record, control of activities, obligations in charge of those who manage dangerous waste, and trans border movements of dangerous waste [es

  8. Anticipated Radiological Dose to Worker for Plutonium Stabilization and Handling at PFP - Project W-460

    International Nuclear Information System (INIS)

    WEISS, E.V.

    2000-01-01

    This report provides estimates of the expected whole body and extremity radiological dose, expressed as dose equivalent (DE), to workers conducting planned plutonium (Pu) stabilization processes at the Hanford Site Plutonium Finishing Plant (PFP). The report is based on a time and motion dose study commissioned for Project W-460, Plutonium Stabilization and Handling, to provide personnel exposure estimates for construction work in the PFP storage vault area plus operation of stabilization and packaging equipment at PFP

  9. Anticipated Radiological Dose to Worker for Plutonium Stabilization and Handling at PFP - Project W-460

    CERN Document Server

    Weiss, E V

    2000-01-01

    This report provides estimates of the expected whole body and extremity radiological dose, expressed as dose equivalent (DE), to workers conducting planned plutonium (Pu) stabilization processes at the Hanford Site Plutonium Finishing Plant (PFP). The report is based on a time and motion dose study commissioned for Project W-460, Plutonium Stabilization and Handling, to provide personnel exposure estimates for construction work in the PFP storage vault area plus operation of stabilization and packaging equipment at PFP.

  10. Ergonomics and comfort in lawn mower handle positioning: An evaluation of handle geometry.

    Science.gov (United States)

    Lowndes, Bethany R; Heald, Elizabeth A; Hallbeck, M Susan

    2015-11-01

    Hand operation accompanied with any combination of large forces, awkward positions and repetition may lead to upper limb injury or illness and may be exacerbated by vibration. Commercial lawn mowers expose operators to these factors during actuation of hand controls and therefore may be a health concern. A nontraditional lawn mower control system may decrease upper limb illnesses and injuries through more neutral hand and body positioning. This study compared maximum grip strength in twelve different orientations (3 grip spans and 4 positions) and evaluated self-described comfortable handle positions. The results displayed force differences between nontraditional (X) and both vertical (V) and pistol (P) positions (p < 0.0001) and among the different grip spans (p < 0.0001). Based on these results, recommended designs should incorporate a tilt between 45 and 70°, handle rotations between 48 and 78°, and reduced force requirements or decreased grip spans to improve user health and comfort. Copyright © 2015 Elsevier Ltd and The Ergonomics Society. All rights reserved.

  11. General principles of the nuclear criticality safety for handling, processing and transportation fissile materials in the USSR

    International Nuclear Information System (INIS)

    Vnukov, V.S.; Rjazanov, B.G.; Sviridov, V.I.; Frolov, V.V.; Zubkov, Y.N.

    1991-01-01

    The paper describes the general principles of nuclear criticality safety for handling, processing, transportation and fissile materials storing. Measures to limit the consequences of critical accidents are discussed for the fuel processing plants and fissile materials storage. The system of scientific and technical measures on nuclear criticality safety as well as the system of control and state supervision based on the rules, limits and requirements are described. The criticality safety aspects for various stages of handling nuclear materials are considered. The paper gives descriptions of the methods and approaches for critical risk assessments for the processing facilities, plants and storages. (Author)

  12. Potential applications of advanced remote handling and maintenance technology to future waste handling facilities

    International Nuclear Information System (INIS)

    Kring, C.T.; Herndon, J.N.; Meacham, S.A.

    1987-01-01

    The Consolidated Fuel Reprocessing Program (CFRP) at the Oak Ridge National Laboratory (ORNL) has been advancing the technology in remote handling and remote maintenance of in-cell systems planned for future US nuclear fuel reprocessing plants. Much of the experience and technology developed over the past decade in this endeavor are directly applicable to the in-cell systems being considered for the facilities of the Federal Waste Management System (FWMS). The ORNL developments are based on the application of teleoperated force-reflecting servomanipulators controlled by an operator completely removed from the hazardous environment. These developments address the nonrepetitive nature of remote maintenance in the unstructured environments encountered in a waste handling facility. Employing technological advancements in dexterous manipulators, as well as basic design guidelines that have been developed for remotely maintained equipment and processes, can increase operation and maintenance system capabilities, thereby allowing the attainment of two Federal Waste Management System major objectives: decreasing plant personnel radiation exposure and increasing plant availability by decreasing the mean-time-to-repair in-cell maintenance and process equipment

  13. Potential applications of advanced remote handling and maintenance technology to future waste handling facilities

    International Nuclear Information System (INIS)

    Kring, C.T.; Herndon, J.N.; Meacham, S.A.

    1987-01-01

    The Consolidated Fuel Reprocessing Program (CFRP) at the Oak Ridge National Laboratory (ORNL) has been advancing the technology in remote handling and remote maintenance of in-cell systems planned for future U.S. nuclear fuel reprocessing plants. Much of the experience and technology developed over the past decade in this endeavor are directly applicable to the in-cell systems being considered for the facilities of the Federal Waste Management System (FWMS). The ORNL developments are based on the application of teleoperated force-reflecting servomanipulators controlled by an operator completely removed from the hazardous environment. These developments address the nonrepetitive nature of remote maintenance in the unstructured environments encountered in a waste handling facility. Employing technological advancements in dexterous manipulators, as well as basic design guidelines that have been developed for remotely maintained equipment and processes, can increase operation and maintenance system capabilities, thereby allowing the attainment of two Federal Waste Management System major objectives: decreasing plant personnel radiation exposure and increasing plant availability by decreasing the mean-time-to-repair in-cell maintenance and process equipment

  14. Energy Storage and Retrieval

    Indian Academy of Sciences (India)

    Annual Meetings · Mid Year Meetings · Discussion Meetings · Public Lectures · Lecture Workshops · Refresher Courses · Symposia · Live Streaming. Home; Journals; Resonance – Journal of Science Education; Volume 1; Issue 6. Energy Storage and Retrieval The Secondary Battery Route. A K Shukla P Vishnu Kamath.

  15. Carbon Capture and Storage

    NARCIS (Netherlands)

    Benson, S.M.; Bennaceur, K.; Cook, P.; Davison, J.; Coninck, H. de; Farhat, K.; Ramirez, C.A.; Simbeck, D.; Surles, T.; Verma, P.; Wright, I.

    2012-01-01

    Emissions of carbon dioxide, the most important long-lived anthropogenic greenhouse gas, can be reduced by Carbon Capture and Storage (CCS). CCS involves the integration of four elements: CO 2 capture, compression of the CO2 from a gas to a liquid or a denser gas, transportation of pressurized CO 2

  16. Handling and transfer operations for partially-spent nuclear fuel

    Energy Technology Data Exchange (ETDEWEB)

    Ibrahim, J K [PUSPATI, Kuala Lumpur (Malaysia)

    1983-12-01

    This project involved the handling and transfer of partially-spent reactor fuel from the Oregon State University TRIGA Reactor in Corvallis, Oregon to Hanford Engineering Development Laboratory in Richland, Washington. The method of handling is dependent upon the burn-up history of the fuel elements. Legal constraints imposed by standing U.S. nuclear regulations determine the selection of transport containers, transportation procedures, physical security arrangements in transit and nuclear material accountability documentation. Results of in-house safety evaluations of the project determine the extent of involvement of pertinent nuclear regulatory authorities. The actual handling activities and actual radiation dose rates are also presented.

  17. Handling and transfer operations for partially-spent nuclear fuel

    International Nuclear Information System (INIS)

    Ibrahim, J.K.

    1983-01-01

    This project involved the handling and transfer of partially-spent reactor fuel from the Oregon State University TRIGA Reactor in Corvallis, Oregon to Hanford Engineering Development Laboratory in Richland, Washington. The method of handling is dependent upon the burn-up history of the fuel elements. Legal constraints imposed by standing U.S. nuclear regulations determine the selection of transport containers, transportation procedures, physical security arrangements in transit and nuclear material accountability documentation. Results of in-house safety evaluations of the project determine the extent of involvement of pertinent nuclear regulatory authorities. The actual handling activities and actual radiation dose rates are also presented (author)

  18. Spent LWR fuel encapsulation and dry storage demonstration

    International Nuclear Information System (INIS)

    Bahorich, R.J.; Durrill, D.C.; Cross, T.E.; Unterzuber, R.

    1980-01-01

    In 1977 the Spent Fuel Handling and Packaging Program (SFHPP) was initiated by the Department of Energy to develop and test the capability to satisfactorily encapsulate typical spent fuel assemblies from commercial light-water nuclear power plants and to establish the suitability of one or more surface and near surface concepts for the interim dry storage of the encapsulated spent fuel assemblies. The E-MAD Facility at the Nevada Test Site, which is operated for the Department of Energy by the Advanced Energy Systems Division (AESD) of the Westinghouse Electric Corporation, was chosen as the location for this demonstration because of its extensive existing capabilities for handling highly radioactive components and because of the desirable site characteristics for the proposed storage concepts. This paper describes the remote operations related to the process steps of handling, encapsulating and subsequent dry storage of spent fuel in support of the Demonstration Program

  19. Plant Material Acquisition, Layout, and Handling for Flood Control Projects

    National Research Council Canada - National Science Library

    Fischenich, J

    2000-01-01

    .... Successful designs are based on consideration of hydraulic impacts and environmental benefits, the anticipated soils and hydrology, and the approach by which the vegetation is obtained, handled, and installed...

  20. Design guides for radioactive-material-handling facilities and equipment

    International Nuclear Information System (INIS)

    Doman, D.R.; Barker, R.E.

    1980-01-01

    Fourteen key areas relating to facilities and equipment for handling radioactive materials involved in examination, reprocessing, fusion fuel handling and remote maintenance have been defined and writing groups established to prepare design guides for each areas. The guides will give guidance applicable to design, construction, operation, maintenance and safety, together with examples and checklists. Each guide will be reviewed by an independent review group. The guides are expected to be compiled and published as a single document

  1. Ethical Infrastructure and Successful Handling of Workplace Bullying

    Directory of Open Access Journals (Sweden)

    Kari Einarsen

    2017-03-01

    Full Text Available Antecedents and consequences of workplace bullying are well documented. However, the mea- sures taken against workplace bullying, and the effectiveness of such measures, have received less attention. This study addresses this knowledge gap by exploring the role of ethical infrastructure in perceived successful handling of reported workplace bullying. Ethical infrastructure refers to formal and informal systems that enable ethical behavior and disable unethical behavior in organizations. A survey was sent to HR managers and elected head safety representatives (HSRs in all Norwegian municipality organizations. Overall, 216 organizations responded (response rate = 50.2 percent. The ethical infrastructure accounted for 39.4% of the variance in perceived suc- cessful handling of workplace bullying. Formal sanctions were the only unique and signi cant contributor to the perceived successful handling of workplace bullying. The results substantiate the argument that organizations’ ethical infrastructure relate to the HR managers and HSRs’ percep- tions regarding their organizations’ handling of workplace bullying.

  2. 340 Waste handling Facility Hazard Categorization and Safety Analysis

    International Nuclear Information System (INIS)

    Rodovsky, T.J.

    2010-01-01

    The analysis presented in this document provides the basis for categorizing the facility as less than Hazard Category 3. The final hazard categorization for the deactivated 340 Waste Handling Facility (340 Facility) is presented in this document. This hazard categorization was prepared in accordance with DOE-STD-1 027-92, Change Notice 1, Hazard Categorization and Accident Analysis Techniques for Compliance with Doe Order 5480.23, Nuclear Safety Analysis Reports. The analysis presented in this document provides the basis for categorizing the facility as less than Hazard Category (HC) 3. Routine nuclear waste receiving, storage, handling, and shipping operations at the 340 Facility have been deactivated, however, the facility contains a small amount of radioactive liquid and/or dry saltcake in two underground vault tanks. A seismic event and hydrogen deflagration were selected as bounding accidents. The generation of hydrogen in the vault tanks without active ventilation was determined to achieve a steady state volume of 0.33%, which is significantly less than the lower flammability limit of 4%. Therefore, a hydrogen deflagration is not possible in these tanks. The unmitigated release from a seismic event was used to categorize the facility consistent with the process defined in Nuclear Safety Technical Position (NSTP) 2002-2. The final sum-of-fractions calculation concluded that the facility is less than HC 3. The analysis did not identify any required engineered controls or design features. The Administrative Controls that were derived from the analysis are: (1) radiological inventory control, (2) facility change control, and (3) Safety Management Programs (SMPs). The facility configuration and radiological inventory shall be controlled to ensure that the assumptions in the analysis remain valid. The facility commitment to SMPs protects the integrity of the facility and environment by ensuring training, emergency response, and radiation protection. The full scale

  3. The prevention and handling of the missing data

    OpenAIRE

    Kang, Hyun

    2013-01-01

    Even in a well-designed and controlled study, missing data occurs in almost all research. Missing data can reduce the statistical power of a study and can produce biased estimates, leading to invalid conclusions. This manuscript reviews the problems and types of missing data, along with the techniques for handling missing data. The mechanisms by which missing data occurs are illustrated, and the methods for handling the missing data are discussed. The paper concludes with recommendations for ...

  4. Case Study in Biomimetic Design: Handling and Assembly of Microparts

    DEFF Research Database (Denmark)

    Shu, Li; Hansen, Hans Nørgaard; Gegeckaite, Asta

    2006-01-01

    This paper describes the application of the biomimetic design process to the development of automated gripping devices for microparts. Handling and assembly of micromechanical parts is complicated by size effects that occur when part dimensions are scaled down. A common complication involves stic...... and the abscission process in plants inspired concepts of new automated handling devices for microobjects. The design, development and testing of a gripping device based on biological principles for the automated handling and assembly of a microscrew is presented.......This paper describes the application of the biomimetic design process to the development of automated gripping devices for microparts. Handling and assembly of micromechanical parts is complicated by size effects that occur when part dimensions are scaled down. A common complication involves...

  5. Fissile materials principles of criticality safety in handling and processing

    International Nuclear Information System (INIS)

    1976-01-01

    This Swedish Standard consists of the English version of the International Standard ISO 1709-1975-Nuclear energy. Fissile materials. Principles of criticality safety in handling and processing. (author)

  6. SNS Target Test Facility for remote handling design and verification

    International Nuclear Information System (INIS)

    Spampinato, P.T.; Graves, V.B.; Schrock, S.L.

    1998-01-01

    The Target Test Facility will be a full-scale prototype of the Spallation Neutron Source Target Station. It will be used to demonstrate remote handling operations on various components of the mercury flow loop and for thermal/hydraulic testing. This paper describes the remote handling aspects of the Target Test Facility. Since the facility will contain approximately 1 cubic meter of mercury for the thermal/hydraulic tests, an enclosure will also be constructed that matches the actual Target Test Cell

  7. Core management and fuel handling for nuclear power plants. Safety guide

    International Nuclear Information System (INIS)

    2004-01-01

    This Safety Guide supplements and elaborates upon the safety requirements for core management and fuel handling that are presented in Section 5 of the Safety Requirements publication on the operation of nuclear power plants. The present publication supersedes the IAEA Safety Guide on Safety Aspects of Core Management and Fuel Handling, issued in 1985 as Safety Series No. 50-SG-010. It is also related to the Safety Guide on the Operating Organization for Nuclear Power Plants, which identifies fuel management as one of the various functions to be performed by the operating organization. The purpose of this Safety Guide is to provide recommendations for core management and fuel handling at nuclear power plants on the basis of current international good practice. The present Safety Guide addresses those aspects of fuel management activities that are necessary in order to allow optimum reactor core operation without compromising the limits imposed by the design safety considerations relating to the nuclear fuel and the plant as a whole. In this publication, 'core management' refers to those activities that are associated with fuel management in the core and reactivity control, and 'fuel handling' refers to the movement, storage and control of fresh and irradiated fuel. Fuel management comprises both core management and fuel handling. This Safety Guide deals with fuel management for all types of land based stationary thermal neutron power plants. It describes the safety objectives of core management, the tasks that have to be accomplished to meet these objectives and the activities undertaken to perform those tasks. It also deals with the receipt of fresh fuel, storage and handling of fuel and other core components, the loading and unloading of fuel and core components, and the insertion and removal of other reactor materials. In addition, it deals with loading a transport container with irradiated fuel and its preparation for transport off the site. Transport

  8. Core management and fuel handling for nuclear power plants. Safety guide

    International Nuclear Information System (INIS)

    2002-01-01

    This Safety Guide supplements and elaborates upon the safety requirements for core management and fuel handling that are presented in Section 5 of the Safety Requirements publication on the operation of nuclear power plants. The present publication supersedes the IAEA Safety Guide on Safety Aspects of Core Management and Fuel Handling, issued in 1985 as Safety Series No. 50-SG-010. It is also related to the Safety Guide on the Operating Organization for Nuclear Power Plants, which identifies fuel management as one of the various functions to be performed by the operating organization. The purpose of this Safety Guide is to provide recommendations for core management and fuel handling at nuclear power plants on the basis of current international good practice. The present Safety Guide addresses those aspects of fuel management activities that are necessary in order to allow optimum reactor core operation without compromising the limits imposed by the design safety considerations relating to the nuclear fuel and the plant as a whole. In this publication, 'core management' refers to those activities that are associated with fuel management in the core and reactivity control, and 'fuel handling' refers to the movement, storage and control of fresh and irradiated fuel. Fuel management comprises both core management and fuel handling. This Safety Guide deals with fuel management for all types of land based stationary thermal neutron power plants. It describes the safety objectives of core management, the tasks that have to be accomplished to meet these objectives and the activities undertaken to perform those tasks. It also deals with the receipt of fresh fuel, storage and handling of fuel and other core components, the loading and unloading of fuel and core components, and the insertion and removal of other reactor materials. In addition, it deals with loading a transport container with irradiated fuel and its preparation for transport off the site. Transport

  9. Effects of postharvest handling conditions on internalization and growth of Salmonella enterica in tomatoes.

    Science.gov (United States)

    Zhou, Bin; Luo, Yaguang; Nou, Xiangwu; Yang, Yang; Wu, Yunpeng; Wang, Qin

    2014-03-01

    Salmonella internalization in tomatoes during postharvest handling is a major food safety concern. This study was conducted to determine the effect of immersion time, immersion depth, and temperature differential between bacterial suspension and tomato pulp on the internalization of Salmonella enterica in tomato fruits. The effect of storage temperature and duration on the survival and growth of internalized Salmonella cells was also evaluated. Overall, immersion time significantly affected the incidence and extent of S. enterica internalization (P internalization. The depth of Salmonella internalization in tomato tissues also increased with increasing immersion time. Immersion time also significantly influenced the degree to which the temperature differential affected Salmonella internalization. With an immersion time of 2 min, the temperature differential had no significant effect on Salmonella internalization (P = 0.2536). However, with an immersion time of 15 min, a significantly larger Salmonella population became internalized in tomatoes immersed in solutions with a -30°F (-16.7°C) temperature differential. Internalized S. enterica cells persisted in the core tissues during 14 days of storage. Strain type and storage duration significantly affected (P internalized Salmonella recovered, but storage temperatures of 55 to 70°F (12.8 to 21.1°C) did not (P > 0.05). These findings indicate the importance of preventing pathogen internalization during postharvest handling.

  10. Behavior of spent nuclear fuel and storage system components in dry interim storage.

    Energy Technology Data Exchange (ETDEWEB)

    Johnson, A.B. Jr.; Gilbert, E.R.; Guenther, R.J.

    1982-08-01

    Irradiated nuclear fuel has been handled under dry conditions since the early days of nuclear reactor operation, and use of dry storage facilities for extended management of irradiated fuel began in 1964. Irradiated fuel is currently being stored dry in four types of facilities: dry wells, vaults, silos, and metal casks. Essentially all types of irradiated nuclear fuel are currently stored under dry conditions. Gas-cooled reactor (GCR) and liquid metal fast breeder reactor (LMFBR) fuels are stored in vaults and dry wells. Certain types of fuel are being stored in licensed dry storage facilities: Magnox fuel in vaults in the United Kingdom and organic-cooled reactor (OCR) fuel in silos in Canada. Dry storage demonstrations are under way for Zircaloy-clad fuel from boiling water reactors BWR's, pressurized heavy-water reactors (PHWRs), and pressurized water reactors (PWRs) in all four types of dry storage facilities. The demonstrations and related hot cell and laboratory tests are directed toward expanding the data base and establishing a licensing basis for dry storage of water reactor fuel. This report reviews the scope of dry interim storage technology, the performance of fuel and facility materials, the status of programs in several countries to license dry storage of water reactor fuel, and the characteristics of water reactor fuel that relate to dry storage conditions.

  11. Behavior of spent nuclear fuel and storage-system components in dry interim storage

    International Nuclear Information System (INIS)

    Johnson, A.B. Jr.; Gilbert, E.R.; Guenther, R.J.

    1982-08-01

    Irradiated nuclear fuel has been handled under dry conditions since the early days of nuclear reactor operation, and use of dry storage facilities for extended management of irradiated fuel began in 1964. Irradiated fuel is currently being stored dry in four types of facilities: dry wells, vaults, silos, and metal casks. Essentially all types of irradiated nuclear fuel are currently stored under dry conditions. Gas-cooled reactor (GCR) and liquid metal fast breeder reactor (LMFBR) fuels are stored in vaults and dry wells. Certain types of fuel are being stored in licensed dry storage facilities: Magnox fuel in vaults in the United Kingdom and organic-cooled reactor (OCR) fuel in silos in Canada. Dry storage demonstrations are under way for Zircaloy-clad fuel from boiling water reactors BWR's, pressurized heavy-water reactors (PHWRs), and pressurized water reactors (PWRs) in all four types of dry storage facilities. The demonstrations and related hot cell and laboratory tests are directed toward expanding the data base and establishing a licensing basis for dry storage of water reactor fuel. This report reviews the scope of dry interim storage technology, the performance of fuel and facility materials, the status of programs in several countries to license dry storage of water reactor fuel, and the characteristics of water reactor fuel that relate to dry storage conditions

  12. Federated data storage and management infrastructure

    International Nuclear Information System (INIS)

    Zarochentsev, A; Kiryanov, A; Klimentov, A; Krasnopevtsev, D; Hristov, P

    2016-01-01

    The Large Hadron Collider (LHC)’ operating at the international CERN Laboratory in Geneva, Switzerland, is leading Big Data driven scientific explorations. Experiments at the LHC explore the fundamental nature of matter and the basic forces that shape our universe. Computing models for the High Luminosity LHC era anticipate a growth of storage needs of at least orders of magnitude; it will require new approaches in data storage organization and data handling. In our project we address the fundamental problem of designing of architecture to integrate a distributed heterogeneous disk resources for LHC experiments and other data- intensive science applications and to provide access to data from heterogeneous computing facilities. We have prototyped a federated storage for Russian T1 and T2 centers located in Moscow, St.-Petersburg and Gatchina, as well as Russian / CERN federation. We have conducted extensive tests of underlying network infrastructure and storage endpoints with synthetic performance measurement tools as well as with HENP-specific workloads, including the ones running on supercomputing platform, cloud computing and Grid for ALICE and ATLAS experiments. We will present our current accomplishments with running LHC data analysis remotely and locally to demonstrate our ability to efficiently use federated data storage experiment wide within National Academic facilities for High Energy and Nuclear Physics as well as for other data-intensive science applications, such as bio-informatics. (paper)

  13. Logistics management for storing multiple cask plug and remote handling systems in ITER

    International Nuclear Information System (INIS)

    Ventura, Rodrigo; Ferreira, João; Filip, Iulian; Vale, Alberto

    2013-01-01

    Highlights: ► We model the logistics management problem in ITER, taking into account casks of multiple typologies. ► We propose a method to determine the best position of the casks inside a given storage area. ► Our method obtains the sequence of operations required to retrieve or store an arbitrary cask, given its storage place. ► We illustrate our method with simulation results in an example scenario. -- Abstract: During operation, maintenance inside the reactor building at ITER (International Thermonuclear Experimental Reactor) has to be performed by remote handling, due to the presence of activated materials. Maintenance operations involve the transportation and storage of large, heavyweight casks from and to the tokamak building. The transportation is carried out by autonomous vehicles that lift and move beneath these casks. The storage of these casks face several challenges, since (1) the cask storage area is limited in space, and (2) all casks have to be accessible for transportation by the vehicles. In particular, casks in the storage area may block other casks, so that the former has to be moved to a temporary position to give way to the latter. This paper addresses the challenge of managing the logistics of cask storage, where casks may have different typologies. In particular, we propose an approach to (1) determine the best position of the casks inside the storage area, and to (2) obtain the sequence of operations required to retrieve and store an arbitrary cask from/to a given storage place. A combinatorial optimization approach is used to obtain solutions to both these problems. Simulation results illustrate the application of the proposed method to a simple scenario

  14. Logistics management for storing multiple cask plug and remote handling systems in ITER

    Energy Technology Data Exchange (ETDEWEB)

    Ventura, Rodrigo, E-mail: rodrigo.ventura@isr.ist.utl.pt [Laboratório de Robótica e Sistemas em Engenharia e Ciência – Laboratório Associado, Instituto Superior Técnico, Universidade Técnica de Lisboa, Av. Rovisco Pais 1, 1049-001 Lisboa (Portugal); Ferreira, João, E-mail: jftferreira@ipfn.ist.utl.pt [Instituto de Plasmas e Fusão Nuclear – Laboratório Associado, Instituto Superior Técnico, Universidade Técnica de Lisboa, Av. Rovisco Pais 1, 1049-001 Lisboa (Portugal); Filip, Iulian, E-mail: ifilip@gmail.com [Faculty of Mechanical Engineering – Technical University Gheorghe Asachi of Iasi, 61 Dimitrie Mangeron Bldv., Iasi 700050 (Romania); Vale, Alberto, E-mail: avale@ipfn.ist.utl.pt [Instituto de Plasmas e Fusão Nuclear – Laboratório Associado, Instituto Superior Técnico, Universidade Técnica de Lisboa, Av. Rovisco Pais 1, 1049-001 Lisboa (Portugal)

    2013-10-15

    Highlights: ► We model the logistics management problem in ITER, taking into account casks of multiple typologies. ► We propose a method to determine the best position of the casks inside a given storage area. ► Our method obtains the sequence of operations required to retrieve or store an arbitrary cask, given its storage place. ► We illustrate our method with simulation results in an example scenario. -- Abstract: During operation, maintenance inside the reactor building at ITER (International Thermonuclear Experimental Reactor) has to be performed by remote handling, due to the presence of activated materials. Maintenance operations involve the transportation and storage of large, heavyweight casks from and to the tokamak building. The transportation is carried out by autonomous vehicles that lift and move beneath these casks. The storage of these casks face several challenges, since (1) the cask storage area is limited in space, and (2) all casks have to be accessible for transportation by the vehicles. In particular, casks in the storage area may block other casks, so that the former has to be moved to a temporary position to give way to the latter. This paper addresses the challenge of managing the logistics of cask storage, where casks may have different typologies. In particular, we propose an approach to (1) determine the best position of the casks inside the storage area, and to (2) obtain the sequence of operations required to retrieve and store an arbitrary cask from/to a given storage place. A combinatorial optimization approach is used to obtain solutions to both these problems. Simulation results illustrate the application of the proposed method to a simple scenario.

  15. Flexible Electrostatic Technologies for Capture and Handling, Phase 1

    Science.gov (United States)

    Bryan, Thomas

    2015-01-01

    Fundamental to many of NASA's in-space transportation missions is the capture and handling of various objects and vehicles in various orbits for servicing, debris disposal, sample retrieval, and assembly without the benefit of sufficient grapple fixtures and docking ports. To perform similar material handling tasks on Earth, pincher grippers, suction grippers, or magnetic chucks are used, but are unable to reliably grip aluminum and composite spacecraft, insulation, radiators, solar arrays, or extra-terrestrial objects in the vacuum of outer space without dedicated handles in the right places. The electronic Flexible Electrostatic Technologies for space Capture and Handling (FETCH) will enable reliable and compliant gripping (soft dock) of practically any object in various orbits or surfaces without dedicated mechanical features, very low impact capture, and built-in proximity sensing without any conventional actuators. Originally developed to handle semiconductor and glass wafers during vacuum chamber processing without contamination, the normal rigid wafer handling chucks are replaced with thin metal foil segments laminated in flexible insulation driven by commercial off-the-shelf solid state, high-voltage power supplies. Preliminary testing in NASA Marshall Space Flight Center's (MSFC's) Flat Floor Robotics Lab demonstrated compliant alignment and gripping with a full-sized, 150-lb microsat mockup and translation before a clean release with a flip of a switch. The flexible electrostatic gripper pads can be adapted to various space applications with different sizes, shapes, and foil electrode layouts even with openings through the gripper pads for addition of guidance sensors or injection of permanent adhesives. With gripping forces estimated between 0.5 and 2.5 lb/in2 or 70-300 lb/ft2 of surface contact, the FETCH can turn on and off rapidly and repeatedly to enable sample handling, soft docking, in-space assembly, precision relocation, and surface translation

  16. Encapsulation and handling of spent nuclear fuel for final disposal

    International Nuclear Information System (INIS)

    Loennerberg, B.; Larker, H.; Ageskog, L.

    1983-05-01

    The handling and embedding of those metal parts which arrive to the encapsulation station with the fuel is described. For the encapsulation of fuel two alternatives are presented, both with copper canisters but with filling of lead and copper powder respectively. The sealing method in the first case is electron beam welding, in the second case hot isostatic pressing. This has given the headline of the two chapters describing the methods: Welded copper canister and Pressed copper canister. Chapter 1, Welded copper canister, presents the handling of the fuel when it arrives to the encapsulation station, where it is first placed in a buffer pool. From this pool the fuel is transferred to the encapsulation process and thereby separated from fuel boxes and boron glass rod bundles, which are transported together with the fuel. The encapsulation process comprises charging into a copper canister, filling with molten lead, electron beam welding of the lid and final inspection. The transport to and handling in the final repository are described up to the deposition and sealing in the deposition hole. Handling of fuel residues is treated in one of the sections. In chapter 2, Pressed copper canister, only those parts of the handling, which differ from chapter 1 are described. The hot isostatic pressing process is given in the first sections. The handling includes drying, charging into the canister, filling with copper powder, seal lid application and hot isostatic pressing before the final inspection and deposition. In the third chapter, BWR boxes in concrete moulds, the handling of the metal parts, separated from the fuel, are dealt with. After being lifted from the buffer pool they are inserted in a concrete mould, the mould is filled with concrete, covered with a lid and after hardening transferred to its own repository. The deposition in this repository is described. (author)

  17. The natural angle between the hand and handle and the effect of handle orientation on wrist radial/ulnar deviation during maximal push exertions.

    Science.gov (United States)

    Young, Justin G; Lin, Jia-Hua; Chang, Chien-Chi; McGorry, Raymond W

    2013-01-01

    The purpose of this experiment was to quantify the natural angle between the hand and a handle, and to investigate three design factors: handle rotation, handle tilt and between-handle width on the natural angle as well as resultant wrist radial/ulnar deviation ('RUD') for pushing tasks. Photographs taken of the right upper limb of 31 participants (14 women and 17 men) performing maximal seated push exertions on different handles were analysed. Natural hand/handle angle and RUD were assessed. It was found that all of the three design factors significantly affected natural handle angle and wrist RUD, but participant gender did not. The natural angle between the hand and the cylindrical handle was 65 ± 7°. Wrist deviation was reduced for handles that were rotated 0° (horizontal) and at the narrow width (31 cm). Handles that were tilted forward 15° reduced radial deviation consistently (12-13°) across handle conditions. Manual materials handling (MMH) tasks involving pushing have been related to increased risk of musculoskeletal injury. This study shows that handle orientation influences hand and wrist posture during pushing, and suggests that the design of push handles on carts and other MMH aids can be improved by adjusting their orientation to fit the natural interface between the hand and handle.

  18. Fire and earthquake counter measures in radiation handling facilities

    International Nuclear Information System (INIS)

    1985-01-01

    'Fire countermeasures in radiation handling facilities' published in 1961 is still widely utilized as a valuable guideline for those handling radiation through the revision in 1972. However, science and technology rapidly advanced, and the relevant laws were revised after the publication, and many points which do not conform to the present state have become to be found. Therefore, it was decided to rewrite this book, and the new book has been completed. The title was changed to 'Fire and earthquake countermeasures in radiation handling facilities', and the countermeasures to earthquakes were added. Moreover, consideration was given so that the book is sufficiently useful also for those concerned with fire fighting, not only for those handling radiation. In this book, the way of thinking about the countermeasures against fires and earthquakes, the countermeasures in normal state and when a fire or an earthquake occurred, the countermeasures when the warning declaration has been announced, and the data on fires, earthquakes, the risk of radioisotopes, fire fighting equipment, the earthquake counter measures for equipment, protectors and radiation measuring instruments, first aid, the example of emergency system in radiation handling facilities, the activities of fire fighters, the example of accidents and so on are described. (Kako, I.)

  19. Animal Products and Handling: A Caution for Consumers and ...

    African Journals Online (AJOL)

    This study reviewed pertinent literature on edible animal products and handling with respect to contaminations and adulterations. Animal products include eggs, meat, milk, fish, skin/hide that are processed into other by products for human consumption. There is the need for awareness campaignsto consumers and ...

  20. Storage Policies and Optimal Shape of a Storage System

    NARCIS (Netherlands)

    Zaerpour, N.; De Koster, René; Yu, Yugang

    2013-01-01

    The response time of a storage system is mainly influenced by its shape (configuration), the storage assignment and retrieval policies, and the location of the input/output (I/O) points. In this paper, we show that the optimal shape of a storage system, which minimises the response time for single

  1. SALES, STORAGE AND SALVAGE

    CERN Multimedia

    Division SPL, groupe logistique; A. Notar

    2000-01-01

    From 3 January 2000 there will be a security barrier in front of the storage-recycling area in bldg 133, which will be accessible only to authorised staff and contractors.You are reminded that the equipment delivered to this area must be unpolluted and non-radioactive. The cost of recycling the equipment will be debited to the budget code of the Division concerned, with the prior approval of the Group Leader.Reminder relating to equipment salesThe Sales Section is open on Thursdays from 13.30 to 15.00 hours only.SPL DivisionLogistics GroupA. Notari

  2. Experience with fuel damage caused by abnormal conditions in handling and transporting operations

    International Nuclear Information System (INIS)

    Bailey, W.J.

    1983-01-01

    Pacific Northwest Laboratory (PNL) conducted a study to determine the expected condition of spent USA light-water reactor (LWR) fuel upon arrival at interim storage or fuel reprocessing facilities or, if fuel is declared a waste, at disposal facilities. Initial findings were described in an earlier PNL paper at PATRAM '80 and in a report. Updated findings are described in this paper, which includes an evaluation of information obtained from the literature and a compilation of cases of known or suspected damage to fuel as a result of handling and/or transporting operations. To date, PNL has evaluated 123 actual cases (98 USA and 25 non-USA). Irradiated fuel was involved in all but 10 of the cases. From this study, it is calculated that the frequency of unusual occurrences involving fuel damage from handling and transporting operations has been low. The damage that did occur was generally minor. The current base of experience with fuel handling and transporting operations indicates that nearly all of these unusual occurrences had only a minor or negligible effect on spent fuel storage facility operations

  3. Principles for the Safe Moving and Handling of Patients

    Directory of Open Access Journals (Sweden)

    Wanless Stephen

    2016-12-01

    Full Text Available Human movement when walking or running is a widely researched area. However, there is an increased incidence of musculoskeletal injury from poor positioning when moving and handling patients amongst healthcare professionals and is one of the main causes of long term musculoskeletal health problems. In the clinical area, an individual’s musculoskeletal health system is subjected to mechanical loading, increasing the body’s stress and strain limits, and once these are exceeded injury occurs. The risk of pain and injury has a direct relation from the over use of poor posture from poor moving and handling, which in turn can cause loss of strength and reduce musculoskeletal function. This can be changed through healthcare workers adopting safe biomechanical body movements during patient handling tasks.

  4. Development of nuclear fuel microsphere handling techniques and equipment

    International Nuclear Information System (INIS)

    Mack, J.E.; Suchomel, R.R.; Angelini, P.

    1979-01-01

    Considerable progress has been made in the development of microsphere handling techniques and equipment for nuclear applications. Work at Oak Ridge National Laboratory with microspherical fuel forms dates back to the early sixties with the development of the sol-gel process. Since that time a number of equipment items and systems specifically related to microsphere handling and characterization have been identified and developed for eventual application in a remote recycle facility. These include positive and negative pressure transfer systems, samplers, weighers, a blender-dispenser, and automated devices for particle size distribution and crushing strength analysis. The current status of these and other components and systems is discussed

  5. Study over problems related to fuel and ash handling systems; Probleminventering braensle- och askhantering

    Energy Technology Data Exchange (ETDEWEB)

    Njurell, Rolf; Wikman, Karin [AaF-Energi och Miljoe AB, Stockhom (Sweden)

    2003-10-01

    storage. In reality the problems with bad fuel quality are also often caused by an incorrect layout of the handling system. It is possible to handle frozen lumps and long bites of bark with the right layout. Equipment for this is available. In a similar way most of the ash handling problems are caused by odd things in the ash, for example iron pipes. Also in this case is it common that the equipment is unsuitable for the ash quality and the actual problem is not the ash type itself. For continuous moistening systems is it not possible at many plants to take care of ash flow variations, which results in a fly ash that is either too dry or too wet and thereby causes dusting or clogging. The expectation of this project is to make it possible for plants with problems related to fuel and ash handling systems to find each other and to solve the problems in cooperation. The suppliers also get some feedback, which might result in a decrease of problems in the future.

  6. Ammonia for hydrogen storage: challenges and opportunities

    DEFF Research Database (Denmark)

    Klerke, Asbjørn; Christensen, Claus H.; Nørskov, Jens Kehlet

    2008-01-01

    The possibility of using ammonia as a hydrogen carrier is discussed. Compared to other hydrogen storage materials, ammonia has the advantages of a high hydrogen density, a well-developed technology for synthesis and distribution, and easy catalytic decomposition. Compared to hydrocarbons...... and alcohols, it has the advantage that there is no CO2 emission at the end user. The drawbacks are mainly the toxicity of liquid ammonia and the problems related to trace amounts of ammonia in the hydrogen after decomposition. Storage of ammonia in metal ammine salts is discussed, and it is shown...... that this maintains the high volumetric hydrogen density while alleviating the problems of handling the ammonia. Some of the remaining challenges for research in ammonia as a hydrogen carrier are outlined....

  7. Remote systems and automation in radioactive waste package handling

    International Nuclear Information System (INIS)

    Gneiting, B.C.; Hayward, M.L.

    1987-01-01

    A proof-of-principle test was conducted at the Hanford Engineering Development Laboratory (HEDL) to demonstrate the feasibility of performing cask receiving and unloading operations in a remote and partially automated manner. This development testing showed feasibility of performing critical cask receipt, preparation, and unloading operations from a single control station using remote controls and indirect viewing. Using robotics and remote automation in a cask handling system can result in lower personnel exposure levels and cask turnaround times while maintaining operational flexibility. An automated cask handling system presents a flexible state-of-the-art, cost effective alternative solution to hands-on methods that have been used in the past

  8. Fuel elements handling device and method

    International Nuclear Information System (INIS)

    Jabsen, F.S.

    1976-01-01

    This invention relates to nuclear equipment and more particularly to methods and apparatus for the non-destructive inspection, manipulation, disassembly and assembly of reactor fuel elements and the like. (author)

  9. Handling and archiving of magnetic fusion data at DIII-D

    International Nuclear Information System (INIS)

    VanderLaan, J.F.; Miller, S.; McHarg, B.B. Jr.; Henline, P.A.

    1995-10-01

    Recent modifications to the computer network at DIII-D enhance the collection and distribution of newly acquired and archived experimental data. Linked clients and servers route new data from diagnostic computers to centralized mass storage and distribute data on demand to local and remote workstations and computers. Capacity for data handling exceeds the upper limit of DIII-D Tokamak data production of about 4 GBytes per day. Network users have fast access to new data stored on line. An interactive program handles requests for restoration of data archived off line. Disk management procedures retain selected data on line in preference to other data. Redundancy of all components on the archiving path from the network to magnetic media has prevented loss of data. Older data are rearchived as dictated by limited media life

  10. Handling of emergency situations: organization and plans

    International Nuclear Information System (INIS)

    Swindell, G.E.

    1975-01-01

    Sources of exposure and foreseeable types of accidents; responsibilities for the prevention and control of accidents; organization for controlling emergency situations; emergency control plans. (HP) [de

  11. Gender difference in safe and unsafe practice of pesticide handling in tobacco farmers of malaysia.

    Science.gov (United States)

    Bin Nordin, R; Araki, S; Sato, H; Yokoyama, K; Bin Wan Muda, W A; Win Kyi, D

    2001-01-01

    To identify gender difference in safe and unsafe practice of pesticide handling in tobacco farmers of Malaysia, we conducted a 20-item questionnaire interview on storage of pesticide (4 questions), mixing of pesticide (3 questions), use of personal protective equipment and clothing while spraying pesticide (7 questions), activities during and after spraying of pesticide (5 questions), and maintenance of pesticide sprayer (1 question) in 496 tobacco farmers (395 males and 101 females) in Bachok District, Kelantan, Malaysia. Duration of employment was significantly longer in females than those in males (pwork habit, (3) reading and following instructions on pesticide label, (4) security, storage and disposal of pesticide container, (5) safe work habit, (6) proper handling of pesticide and maintenance of pesticide sprayer, (7) use of personal protective clothing, and (8) safe handling of pesticide. Results of analysis of covariance for the eight factor scores of all male and female farmers, controlling for educational level and duration of employment, showed that: (1) factor scores for use of personal protective equipment (pwork habit (p0.05). We therefore conclude that: (1) for female tobacco farmers, choice of personal attire tend to result in lower scores on use of personal protective equipment and personal protective clothing while personal hygiene practices result in lower score on safe work habit; and, (2) for male tobacco farmers, the lower scores on reading and following instruction on pesticide label and mixing pesticide and maintenance of pesticide sprayer in good condition suggests that they were not primarily involved in these activities. It is postulated that these differences in safe and unsafe practices of pesticide handling across gender is related to the choice of personal attire, personal hygiene practices and division of labour within farming households which in turn is influenced by prevailing sociocultural norms in the community.

  12. The handling and disposal of fusion wastes

    International Nuclear Information System (INIS)

    Broden, K.; Hultgren, Aa.; Olsson, G.

    1985-02-01

    The radioactive wastes from fusion reactor operation will include spent components, wastes from repair operations, and decontamination waste. Various disposal routes may be considered depending on i.a. the contents of tritium and of long-lived nuclides, and on national regulations. The management philosophy and disposal technology developed in Sweden for light water reactor wastes has been studied at STUDSVIK during 1983--84 and found to be applicable also to fusion wastes, provided a detritiation stage is included. These studies will continue during 1985 and include experimental work on selected fusion activation nuclides. The work presented is associated to the CEC fusion research programme. Valuable discussions and contacts with people working in this programme at Saclay, Ispra and Garching are deeply appreciated. (author)

  13. Handling, treating and injecting of oilfield wastes

    International Nuclear Information System (INIS)

    Pippard, D.K.

    1997-01-01

    The waste management practices of the oil and gas industry in British Columbia were reviewed. Newalta is a waste management company that offers services to both the upstream (oilfield) and downstream (refined products) petroleum industries. The measures that this company has taken to comply with the new regulations in British Columbia were discussed. Issues regarding deep well disposal, oil and gas waste regulation, and liquid waste streams not authorized for disposal, were addressed. Oil and gas production waste liquids generated in British Columbia can be transported into Alberta for treatment and disposal under Alberta's hazardous wastes disposal legislation. The treatment of crude oil wastes, oilfield waste solids were also addressed. Solid wastes can be disposed of by in-situ treatment, by ex-situ, on-site treatment such as biodegradation and thermal treatment, and by ex-situ, off-site treatment

  14. Torus evacuation and tritium handling on NET

    International Nuclear Information System (INIS)

    Dinner, P.; Chazalon, M.; Iseli, M.

    1986-08-01

    The use of tritium as a fuel affects the design of many systems, as well as requiring several new systems not needed on non DT-burning Tokamaks. This paper summarizes: major tritium process interconnections, tritium flows and inventories; primary requirements, preferred design alternatives, and related development issues; design philosophy for tritium and primary vacuum systems. 14 refs

  15. Solid waste handling and decontamination facility

    International Nuclear Information System (INIS)

    Lampton, R.E.

    1979-01-01

    The Title 1 design of the decontamination part of the SWH and D facility is underway. Design criteria are listed. A flowsheet is given of the solid waste reduction. The incinerator scrubber is described. Design features of the Gunite Tank Sludge Removal and a schematic of the sluicer, TV camera, and recirculating system are given. 9 figures

  16. Early colorectal Cancer: focuses and handling

    International Nuclear Information System (INIS)

    Rojas, Oscar A; Martinez, Carlos E; Escobar, Jaime; Sanchez, William; Serrano, Juan M

    2001-01-01

    Currently, early colorectal cancer (ECC) constitutes only 10% of the total of diagnosed colorectal malignancy. This proportion is expected to show an important increase with the different screening protocols that are on the way, together with recent advances in diagnostic and therapeutic colonoscopy. We compare the histopathologic spectrum of ECC from the western and Japanese viewpoint, defining the anatomopathologic characteristics of this lesions, together with the natural history and new classification and staging systems; variables which are all oriented to establish the grade of local invasion and risk of nodal spread. The knowledge and integral analysis of the different biologic, clinical, histological and endoscopic characteristics of ECC, will determine the most rational individual therapeutic pathway from the prognostic point of view

  17. Uranium hexafluoride: handling procedures and container criteria

    International Nuclear Information System (INIS)

    1977-04-01

    The U.S. Energy Research and Development Administration's (ERDA) procedures for packaging, measuring, and transferring uranium hexafluoride (UF 6 ) have been undergoing continual review and revision for several years to keep them in phase with developing agreements for the supply of enriched uranium. This report, first issued in 1966, was reissued in 1967 to make editorial changes and to provide for minor revisions in procedural information. In 1968 and 1972, Revisions 2 and 3, respectively, were issued as part of the continuing effort to present updated information. This document, Revision 4, includes primarily revisions to UF 6 cylinders, valves, and methods of use. This revision supersedes all previous issues of this report. The procedures will normally apply in all transactions involving receipt or shipment of UF 6 by ERDA, unless stipulated otherwise by contracts or agreements with ERDA or by notices published in the Federal Register

  18. Production, handling and characterization of particulate materials

    CERN Document Server

    Meesters, Gabriel

    2016-01-01

    This edited volume presents most techniques and methods that have been developed by material scientists, chemists, chemical engineers and physicists for the commercial production of particulate materials, ranging from the millimeter to the nanometer scale.  The scope includes the physical and chemical background, experimental optimization of equipment and procedures, as well as an outlook on future methods. The books addresses  issues of industrial importance such as specifications, control parameter(s), control strategy, process models, energy consumption and discusses the various techniques in relation to potential applications. In addition to the production processes, all major unit operations and characterization methods are described in this book. It differs from other books which are devoted to a single technique or a single material. Contributors to this book are acknowledged experts in their field. The aim of the book is to facilitate comparison of the different unit operations leading to optimum...

  19. Sustainable Air Handling by Evaporation and Adsorption

    NARCIS (Netherlands)

    Esfandiari Nia, F.

    2011-01-01

    A considerable fraction of today's energy consumption is due to air-conditioning of buildings, involving both heating and cooling. Energy cost and environmental concerns force designers to find sustainable solutions. Desiccant cooling as a sustainable technology is attractive to be investigated for

  20. Properties of lithium and its handling

    International Nuclear Information System (INIS)

    Asada, Takashi; Kano, Shigeki; Tachi, Toshiaki; Kawai, Masataka

    2000-09-01

    Lithium is one of good coolants because of high boiling point (1317degC), small specific gravity (0.47 at 600degC) and large specific heat (1 cal/g/degC). Therefore if lithium will be used in fast reactor for coolant, the heat efficiency of reactor will largely increase. Here the fundamental properties of lithium and the results of examination on chemical reaction, combustion and extinction are shown. These examinations were also carried out on sodium to compare with lithium. The differences between both are that lithium reacts more moderately with water, not explosive, and is not combustible but after ignition burns at higher temperature and longer. (author)

  1. Tritium handling and processing experience at TSTA

    International Nuclear Information System (INIS)

    Anderson, J.L.; Okuno, K.

    1994-01-01

    In 1987, the Japan Atomic Energy Research Institute (JAERI) and the US Department of Energy (DOE) signed a collaborative agreement (Annex IV) for the joint funding and operation of the Tritium Systems Test Assembly (TSTA) at the Los Alamos National Laboratory (LANL) for a five year period ending June, 1992. After this initial five year collaboration, the Annex IV agreement was extended for another two year period ending June, 1994. During the first five years, a number of the integrated process loop tests of TSTA were conducted, as well as off-line testing of TSTA subsystems. During integrated loop testing the vacuum system, fuel cleanup systems, isotope separation system, transfer pumping system and gas analysis system, are interconnected and tested using 100 g-inventories of tritium to demonstrate steady-state operation of a tritium fuel processing cycle for a fusion reactor. These tests have resulted in a number of significant accomplishments and an experience data base on research, development and operation of the fuel processing system. One of the most significant accomplishments during the initial five year period was the continuous operation of the fuel processing loop for 25 days. During this 25-day extended operation, both the JAERI fuel cleanup system (J-FCU) and the original TSTA fuel cleanup system (FCU) were operated under similar conditions of flow, pressure, and impurity content of the DT gas. Both fuel cleanup systems were demonstrated to provide adequate impurity removal for plasma exhaust gas processing. The isotope separation system was operated continuously, producing pure tritium while rejecting protium as an impurity

  2. Sustainable Development and Handling of Uncertainties

    International Nuclear Information System (INIS)

    Vargas, C.

    1999-01-01

    It is insisted a lot in this article in the change of the scientist's attitude and of the technologist in order to evaluate in critic way of their own work taking into consideration the new mark of the sustainable development. Finally, I would like to indicate that in this article, there are only analyzed the uncertainties that are given at scientific and technological level. The uncertainty sources related to the social and political dimensions of the sustainable development are left aside. These other sources cannot separate the discussion on the sustainable development. In this article, we won't enter to discuss aspects related with the characteristics and dimensions of the sustainable development, or if it is an ideology or not. Regarding the first aspect we will take as a base the characterization of the sustainable development that is presented in the Program 21 of the United Nations. With regard to the second aspect, we will assume that it is a development model with which we should commit and to guide our efforts toward that development pattern to face some of the theoretical problems that arise. (Author) [es

  3. ST ECS error handling and detector safety

    CERN Document Server

    Esperante Pereira, D

    2010-01-01

    This note describes the automatic operation sequences that the ECS implements in order to operate the ST detector in a safe and reliable way. First, the start-up sequences to set the detector in a well known state are described. In addition the possible ST detector states based on the status of the different detector elements will be defined. The states are of crucial interest for the safe operation of the detector when the LHC beam is ready. Besides, the ECS automatic actions taken in case of abnormal status of any of the detector elements are reported. Next, the operational alarm ranges and the error recovery mechanisms are mentioned.

  4. Foster parenting, human imprinting and conventional handling ...

    African Journals Online (AJOL)

    ... the present study indicates that improvements can be made by adopting alternative approaches. Further studies are needed to ascertain how foster parenting and imprinting may be utilized to optimize chick performance, including the long-term consequences of these practices. Keywords: Parental care, Struthio camelus, ...

  5. System and method for slurry handling

    Science.gov (United States)

    Steele, Raymond Douglas; Oppenheim, Judith Pauline

    2015-12-29

    A system includes a slurry depressurizing system that includes a liquid expansion system configured to continuously receive a slurry at a first pressure and continuously discharge the slurry at a second pressure. For example, the slurry depressurizing system may include an expansion turbine to expand the slurry from the first pressure to the second pressure.

  6. MONITORING AND SAFETY OF HANDLING EQUIPMENT

    Directory of Open Access Journals (Sweden)

    Janusz JURASZEK

    2014-04-01

    Full Text Available The paper presents a new solution for continuous measurement of deformations of the beam of travelling crane based on optical fibre Bragg gratings system. A verification of obtained results was done using resistive strain gauge method and magnetic metal memory method was used. Usage of the results of continuous measurements of deformation of the structure of the crane as actual boundary conditions in FEM numerical simulations was proposed in order to enable the analysis of the behaviour of whole structure.

  7. Safety handling of beryllium for fusion technology R and D

    International Nuclear Information System (INIS)

    Yoshida, Hiroshi; Okamoto, Makoto; Terai, Takayuki; Odawara, Osamu; Ashibe, Kusuo; Ohara, Atsushi.

    1992-07-01

    Feasibility of beryllium use as a blanket neutron multiplier, first wall and plasma facing material has been studied for the D-T burning experiment reactors such as ITER. Various experimental work of beryllium and its compounds will be performed under the conditions of high temperature and high energy particle exposure simulating fusion reactor conditions. Beryllium is known as a hazardous substance and its handling has been carefully controlled by various health and safe guidances and/or regulations in many countries. Japanese regulations for hazardous substance provide various guidelines on beryllium for the protection of industrial workers and environment. This report was prepared for the safe handling of beryllium in a laboratory scale experiments for fusion technology R and D such as blanket development. Major items in this report are; (1) Brief review of guidances and regulations in USA, UK and Japan. (2) Safe handling and administration manuals at beryllium facilities in INEL, LANL and JET. (3) Conceptual design study of beryllium handling facility for small to mid-scale blanket R and D. (4) Data on beryllium toxicity, example of clinical diagnosis of beryllium disease, and environmental occurence of beryllium. (5) Personnel protection tools of Japanese Industrial Standard for hazardous substance. (author) 61 refs

  8. Micro and Nano Techniques for the Handling of Biological Samples

    DEFF Research Database (Denmark)

    Micro and Nano Techniques for the Handling of Biological Samples reviews the different techniques available to manipulate and integrate biological materials in a controlled manner, either by sliding them along a surface (2-D manipulation), or by gripping and moving them to a new position (3-D...

  9. Food handling and mastication in the carp (Cyprinus carpio L.)

    NARCIS (Netherlands)

    Sibbing, F.A.

    1984-01-01

    The process of food handling in the common carp ( Cyprinus carpio L.) and its structures associated with feeding are analyzed. The aim of this study is to explain the relation between the the architecture of the head and its functions in food processing and to

  10. Vehicle handling: relationships between subjective and objective measures

    NARCIS (Netherlands)

    Verschuren, R.M.A.F.; Hogema, J.H.

    2003-01-01

    TNO Human Factors and TNO Automotive are investigating relationships between subjective and objective measures in the area of vehicle handling. This paper presents a driving simulator study and a field experiment in which these relationships were investigated. First, in the driving simulator

  11. Application of Minicomputers and Microcomputers to Information Handling.

    Science.gov (United States)

    Griffiths, Jose-Marie

    This study assesses the application of both minicomputers and microcomputers to information-handling procedures and makes recommendations for automating such procedures, particularly in developing nations. The report is based on a survey of existing uses of small computing equipment in libraries, archives, and information centers which was…

  12. Evaluation of some handling and processing parameters for ...

    African Journals Online (AJOL)

    Biomass materials require reduction and densification for the purpose of handling and space requirements. Guinea corn (Sorghum bi-color) is a major source of biomass material in the tropic regions. The densification process involves some measurable parameters, namely: pressure, particles size and binder ratio. Guinea ...

  13. Sample handling for kinetics and molecular assembly in flow cytometry

    Energy Technology Data Exchange (ETDEWEB)

    Sklar, L.A. [Los Alamos National Lab., NM (United States). National Flow Cytometry Resource]|[Univ. of New Mexico, Albuquerque, NM (United States). School of Medicine; Seamer, L.C.; Kuckuck, F.; Prossnitz, E.; Edwards, B. [Univ. of New Mexico, Albuquerque, NM (United States). School of Medicine; Posner, G. [Northern Arizona Univ., Flagstaff, AZ (United States). Dept. of Chemistry

    1998-07-01

    Flow cytometry discriminates particle associated fluorescence from the fluorescence of the surrounding medium. It permits assemblies of macromolecular complexes on beads or cells to be detected in real-time with precision and specificity. The authors have investigated two types of robust sample handling systems which provide sub-second resolution and high throughput: (1) mixers which use stepper-motor driven syringes to initiate chemical reactions in msec time frames; and (2) flow injection controllers with valves and automated syringes used in chemical process control. In the former system, the authors used fast valves to overcome the disparity between mixing 100 {micro}ls of sample in 100 msecs and delivering sample to a flow cytometer at 1 {micro}l/sec. Particles were detected within 100 msec after mixing, but turbulence was created which lasted for 1 sec after injection of the sample into the flow cytometer. They used optical criteria to discriminate particles which were out of alignment due to the turbulent flow. Complex sample handling protocols involving multiple mixing steps and sample dilution have also been achieved. With the latter system they were able to automate sample handling and delivery with intervals of a few seconds. The authors used a fluidic approach to defeat turbulence caused by sample introduction. By controlling both sheath and sample with individual syringes, the period of turbulence was reduced to {approximately} 200 msecs. Automated sample handling and sub-second resolution should permit broad analytical and diagnostic applications of flow cytometry.

  14. PEASANTS ESTRATEGIES AND KNOWLEDGE IN THE NATURALS RESOURCES HANDLE

    Directory of Open Access Journals (Sweden)

    Andrés Pérez Magaña

    2008-08-01

    Full Text Available This contribution had as objective identifying the Knowledge and the strategies that have developed the peasants of a michoacana community for natural resources handle whit agriculturals objective. Starting from idea of that in the Sierra Purepecha region a little has been studied about folk knowledge and agricultural, and that had been unestimated, since the agrarians sciences, its potential for the rural development. Since the focus agroecologic it was studied a community of peasants of the Michoacan Stated using the techniques of participating observation, the agroecological transect and the semistructured individual interview. The results show that the peasants have developed knowledge, which permit to distinguish and identify environmental unities, and the handle the production space; it permit to handle different strategies of natural resources such as: the construction of boars, enclosures alive, reforestation, the use of dung the association crops, distribution space of the crops, expansion of the biodiversity and the handle of the germplasma. These actions are favored for the collective behavior of the community. In these actions are reflexeted a social construction, in which is present the knowledge of the peasants and their capacity of answer to adverses socioenvaironmental factors for assureting its production and reproduction.

  15. 48 CFR 415.207 - Handling proposals and information.

    Science.gov (United States)

    2010-10-01

    ... Information 415.207 Handling proposals and information. (a) Throughout the source selection process, agency... Proposals RFP Offeror 1. To the best of my knowledge and belief, no conflict of interest exists that may... otherwise result in a biased opinion or an unfair advantage. If a potential conflict of interest arises or...

  16. Model-Based Control for Postal Automation and Baggage Handling

    NARCIS (Netherlands)

    Tarau, A.N.

    2010-01-01

    In this thesis we focus on two specific transportation systems, namely postal automation and baggage handling. Postal automation: During the last decades the volume of magazines, catalogs, and other plastic wrapped mail items that have to be processed by post sorting centers has increased

  17. Sociodemographic characteristics and handling of life-threatening ...

    African Journals Online (AJOL)

    Most TBAs deliver 4 newborn monthly, i.e. 148 (22.6%), and the mean number of newborn delivered monthly was 3.9. Concerning the mode of handling of the difficult cases, majority, i.e. 338 ... agenda of many global efforts, such as the safe motherhood .... of rural women and training of health attendants in rural areas.

  18. How to handle and care for bulbs in ophthalmic equipment

    Directory of Open Access Journals (Sweden)

    Ismael Cordero

    2013-08-01

    Full Text Available Many devices used in eye care rely on light bulbs or lamps for their operation. All light bulbs have a limited lifespan and when the bulb fails the device becomes unusable. Therefore, knowing how to handle, how to inspect and how to replace bulbs is important. Just as important is keeping spare bulbs to hand!

  19. Handling and Transport of Oversized Accelerator Components and Physics Detectors

    CERN Document Server

    Prodon, S; Guinchard, M; Minginette, P

    2006-01-01

    For cost, planning and organisational reasons, it is often decided to install large pre-built accelerators components and physics detectors. As a result surface exceptional transports are required from the construction to the installation sites. Such heavy transports have been numerous during the LHC installation phase. This paper will describe the different types of transport techniques used to fit the particularities of accelerators and detectors components (weight, height, acceleration, planarity) as well as the measurement techniques for monitoring and the logistical aspects (organisation with the police, obstacles on the roads, etc). As far as oversized equipment is concerned, the lowering into the pit is challenging, as well as the transport in tunnel galleries in a very scare space and without handling means attached to the structure like overhead travelling cranes. From the PS accelerator to the LHC, handling systems have been developed at CERN to fit with these particular working conditions. This pap...

  20. Physical load handling and listening comprehension effects on balance control.

    Science.gov (United States)

    Qu, Xingda

    2010-12-01

    The purpose of this study was to determine the physical load handling and listening comprehension effects on balance control. A total of 16 young and 16 elderly participants were recruited in this study. The physical load handling task required holding a 5-kg load in each hand with arms at sides. The listening comprehension task involved attentive listening to a short conversation. Three short questions were asked regarding the conversation right after the testing trial to test the participants' attentiveness during the experiment. Balance control was assessed by centre of pressure-based measures, which were calculated from the force platform data when the participants were quietly standing upright on a force platform. Results from this study showed that both physical load handling and listening comprehension adversely affected balance control. Physical load handling had a more deleterious effect on balance control under the listening comprehension condition vs. no-listening comprehension condition. Based on the findings from this study, interventions for the improvement of balance could be focused on avoiding exposures to physically demanding tasks and cognitively demanding tasks simultaneously. STATEMENT OF RELEVANCE: Findings from this study can aid in better understanding how humans maintain balance, especially when physical and cognitive loads are applied. Such information is useful for developing interventions to prevent fall incidents and injuries in occupational settings and daily activities.

  1. Handling of plutonium and transplutonium elements and radioprotection

    Energy Technology Data Exchange (ETDEWEB)

    Rebiffe, J [CEA Centre d' Etudes de Valduc, 21 - Is-sur-Tille (France)

    1976-01-01

    Individual and collective protection procedures in the handling of significant amounts of plutonium have been adopted for many years; they are founded on its properties. Monitoring and counting techniques make it possible to follow the conditions of these protection procedures seriously. Minor or major failures in protection have never resulted in serious consequences for the public or for workers. Such a result has been obtained thanks to the existence of collective and individual protection procedures, the quality of prevention and the availability of efficient emergency means. The keeping of careful prevention, cooperation of all proficiencies, added to a long standing experience make it possible to state that plutonium handling does not present any more danger than many other (industrial or not) human activities.

  2. Handling of plutonium and transplutonium elements and radioprotection

    International Nuclear Information System (INIS)

    Rebiffe, J.

    1976-01-01

    Individual and collective protection procedures in the handling of significant amounts of plutonium have been adopted for many years; they are founded on its properties. Monitoring and counting techniques make it possible to follow the conditions of these protection procedures seriously. Minor or major failures in protection have never resulted in serious consequences for the public or for workers. Such a result has been obtained thanks to the existence of collective and individual protection procedures, the quality of prevention and the availability of efficient emergency means. The keeping of careful prevention, co-operation of all proficiencies, added to a long standing experience make it possible to state that plutonium handling does not present any more danger than many other (industrial or not) human activities [fr

  3. Effects of storage conditions and storage period on nutritional and ...

    African Journals Online (AJOL)

    In this work, the effects of storage conditions and storage period on the nutritional and other qualities of stored yam tubers were investigated. ... environment, signs of deterioration of the tuber such as sprouting, weight loss and rotting and some ...

  4. Safety requirements and feedback of commonly used material handling equipment

    International Nuclear Information System (INIS)

    Pathak, M.K.

    2009-01-01

    Different types of cranes, hoists, chain pulley blocks are the most commonly used material handling equipment in industry along with attachments like chains, wire rope slings, d-shackles, etc. These equipment are used at work for transferring loads from one place to another and attachments are used for anchoring, fixing or supporting the load. Selection of the correct equipment, identification of the equipment planning of material handling operation, examination/testing of the equipment, education and training of the persons engaged in operation of the material handling equipment can reduce the risks to safety of people in workplace. Different safety systems like boom angle indicator, overload tripping device, limit switches, etc. should be available in the cranes for their safe use. Safety requirement for safe operation of material handling equipment with emphasis on different cranes and attachments particularly wire rope slings and chain slings have been brought out in this paper. An attempt has also been made to bring out common nature of deficiencies observed during regulatory inspection carried out by AERB. (author)

  5. Supporting flexible processes with adaptive workflow and case handling

    NARCIS (Netherlands)

    Günther, C.W.; Reichert, M.; Aalst, van der W.M.P.

    2008-01-01

    Workflow management technology has profoundly transformed the way complex tasks are being handled in modern, large-scale organizations. However, it is mostly those systems' inherent lack of flexibility that hinders their broad acceptance, and that is perceived as annoyance by users. In this context,

  6. Adaptive and energy efficient SMA-based handling systems

    Science.gov (United States)

    Motzki, P.; Kunze, J.; Holz, B.; York, A.; Seelecke, S.

    2015-04-01

    Shape Memory Alloys (SMA's) are known as actuators with very high energy density. This fact allows for the construction of very light weight and energy-efficient systems. In the field of material handling and automated assembly process, the avoidance of big moments of inertia in robots and kinematic units is essential. High inertial forces require bigger and stronger robot actuators and thus higher energy consumption and costs. For material handling in assembly processes, many different individual grippers for various work piece geometries are used. If one robot has to handle different work pieces, the gripper has to be exchanged and the assembly process is interrupted, which results in higher costs. In this paper, the advantages of using high energy density Shape Memory Alloy actuators in applications of material-handling and gripping-technology are explored. In particular, light-weight SMA actuated prototypes of an adaptive end-effector and a vacuum-gripper are constructed via rapid-prototyping and evaluated. The adaptive end-effector can change its configuration according to the work piece geometry and allows the handling of multiple different shaped objects without exchanging gripper tooling. SMA wires are used to move four independent arms, each arm adds one degree of freedom to the kinematic unit. At the tips of these end-effector arms, SMA-activated suction cups can be installed. The suction cup prototypes are developed separately. The flexible membranes of these suction cups are pulled up by SMA wires and thus a vacuum is created between the membrane and the work piece surface. The self-sensing ability of the SMA wires are used in both prototypes for monitoring their actuation.

  7. Referenced-site environmental document for a Monitored Retrievable Storage facility: backup waste management option for handling 1800 MTU per year

    International Nuclear Information System (INIS)

    Silviera, D.J.; Aaberg, R.L.; Cushing, C.E.; Marshall, A.; Scott, M.J.; Sewart, G.H.; Strenge, D.L.

    1985-06-01

    This environmental document includes a discussion of the purpose of a monitored retrievable storage facility, a description of two facility design concepts (sealed storage cask and field drywell), a description of three reference sites (arid, warm-wet, and cold-wet), and a discussion and comparison of the impacts associated with each of the six site/concept combinations. This analysis is based on a 15,000-MTU storage capacity and a throughput rate of up to 1800 MTU per year

  8. Referenced-site environmental document for a Monitored Retrievable Storage facility: backup waste management option for handling 1800 MTU per year

    Energy Technology Data Exchange (ETDEWEB)

    Silviera, D.J.; Aaberg, R.L.; Cushing, C.E.; Marshall, A.; Scott, M.J.; Sewart, G.H.; Strenge, D.L.

    1985-06-01

    This environmental document includes a discussion of the purpose of a monitored retrievable storage facility, a description of two facility design concepts (sealed storage cask and field drywell), a description of three reference sites (arid, warm-wet, and cold-wet), and a discussion and comparison of the impacts associated with each of the six site/concept combinations. This analysis is based on a 15,000-MTU storage capacity and a throughput rate of up to 1800 MTU per year.

  9. Assessment of the polytank for fumigation and storage of cowpea

    International Nuclear Information System (INIS)

    Ademang Korletey, Francis

    2009-06-01

    Insect infestation of cowpea (Vigna unguiculata) in storage is identified as a major constraint facing cowpea farmers in Ghana. The major insect pest causing losses to stored cowpea in West Africa is the cowpea weevil (Callosobruchus maculatus). Fumigation is the most effective control method against cowpea weevil considering its mode of infestation. The jute sack lined with a plastic film bag commonly used by farmers for fumigation and storage is very delicate to handle, not sufficiently airtight for fumigation and easily attacked by rodents. The objectives of the project were to (1) assess the polytank for fumigation and storage of cowpea, and (2) compare the storage qualities of stored cowpea using the polytank and jute sack lined with a plastic film bag. The cowpea was fumigated using aluminium phosphide tablets for a period of 7 days and stored for six mouths. Data was collected, analysed and compared between the two storage containers on seed germination, seed vigour, grain moisture content, insect infestation, percentage usable proportion by number and by weight before, mid-storage and after the trial. The levels of phosphine gas concentration in the polytank and the jute sack were assessed daily for 7 days. The results showed no significant differences (1% probability) between the two storage containers in their performance as storage containers in terms of grain moisture content, seed germination, seed vigour, insect infestation, percentage usable proportion by number and by weight. There was also significant difference (5%) in phosphine gas concentration between the two storage containers in their performance as fumigation containers except on day one. However, it was found that fumigation and storage using the polytank had a greater advantage over the jute sack lined with plastic film bag in terms of air tightness, handling and resistance to rodent attacks. (au)

  10. Spent fuel storage and isolation

    International Nuclear Information System (INIS)

    Bensky, M.S.; Kurzeka, W.J.; Bauer, A.A.; Carr, J.A.; Matthews, S.C.

    1979-02-01

    The principal spent fuel activities conducted within the commercial waste and spent fuel within the Commercial Waste and Spent Fuel Packaging Program are: simulated near-surface (drywell) storage demonstrations at Hanford and the Nevada Test Site; surface (sealed storage cask) and drywell demonstrations at the Nevada Test Site; and spent fuel receiving and packaging facility conceptual design. These investigations are described

  11. Environmental and safety aspects. The best of 'powder handling and processing' 1989 - 1997. 'Bulk solids handling' 1992 - 1997 (H/2000)

    Energy Technology Data Exchange (ETDEWEB)

    Woehlbier, R.H. (ed.)

    2000-07-01

    The book contains articles published either during 1992-1997 in ''bulk solids handling'' or during 1989-1997 in ''powder handling and processing''. Main topics are aspects of safety and environmental protection in bulk solids handling: dusts, hazardous powders, prevention and mitigation of dust explosions, powdered coal handling, dedusting, filters, electrostatic precipitation, materials recovery, occupational safety.(uke)

  12. Electrochemistry and Storage Panel Report

    Science.gov (United States)

    Stedman, J. K.; Halpert, G.

    1984-01-01

    Design and performance requirements for electrochemical power storage systems are discussed and some of the approaches towards satisfying these constraints are described. Geosynchronous and low Earth orbit applications, radar type load constraints, and high voltage systems requirements are addressed. In addition, flywheel energy storage is discussed.

  13. Conditioning and handling of tritiated wastes at Canadian nuclear power facilities

    International Nuclear Information System (INIS)

    Krochmalnek, L.S.; Krasznai, J.P.; Carney, M.

    1987-04-01

    Ontario Hydro operates a 10,000 MW capacity nuclear power system utilizing the CANDU pressurized heavy water reactor design. The use of D 2 O as moderator and coolant results in the production of about 2400 Ci of tritium per MWe-yr. As a result, there is significant Canadian experience in the treatment, handling, transport and storage of tritiated wastes. Ontario Hydro operates its own reactor waste storage site which includes systems for volume reduction, immobilization and packaging of wastes. In addition, a facility to remove tritium from heavy water is presently being commissioned at the Darlington nuclear site. This facility will generate tritiated liquid and solid waste that will have to be properly conditioned prior to storage or disposal. The nature of these various wastes and the processes/packaging required to meet storage/disposal criteria are judged to have relevance to investigations in fusion facility waste arisings. Experience to date, planned operational procedures and ongoing R and D in this area are described

  14. Automated handling for SAF batch furnace and chemistry analysis operations

    International Nuclear Information System (INIS)

    Bowen, W.W.; Sherrell, D.L.; Wiemers, M.J.

    1981-01-01

    The Secure Automated Fabrication Program is developing a remotely operated breeder reactor fuel pin fabrication line. The equipment will be installed in the Fuels and Materials Examination Facility being constructed at Hanford, Washington. Production is scheduled to start in mid-1986. The application of small pneumatically operated industrial robots for loading and unloading product into and out of batch furnaces and for distribution and handling of chemistry samples is described

  15. Remote systems and automation in radioactive waste package handling

    International Nuclear Information System (INIS)

    Gneiting, B.C.; Hayward, M.L.

    1987-01-01

    A proof-of-principle test was conducted at the Hanford Engineering Development Laboratory (HEDL) to demonstrate the feasibility of performing cask receiving and unloading operations in a remote and partially automated manner. This development testing showed feasibility of performing critical cask receipt, preparation, and unloading operations from a single control station using remote controls and indirect viewing. Using robotics and remote automation in a cask handling system can result in lower personnel exposure levels and cask turnaround times while maintaining operational flexibility. An automated cask handling system presents a flexible state-of-the-art, cost effective alternative solution to hands-on methods that have been used in the past. 7 refs., 13 figs

  16. Acoustophoretic contactless transport and handling of matter in air.

    Science.gov (United States)

    Foresti, Daniele; Nabavi, Majid; Klingauf, Mirko; Ferrari, Aldo; Poulikakos, Dimos

    2013-07-30

    Levitation and controlled motion of matter in air have a wealth of potential applications ranging from materials processing to biochemistry and pharmaceuticals. We present a unique acoustophoretic concept for the contactless transport and handling of matter in air. Spatiotemporal modulation of the levitation acoustic field allows continuous planar transport and processing of multiple objects, from near-spherical (volume of 0.1-10 μL) to wire-like, without being limited by the acoustic wavelength. The independence of the handling principle from special material properties (magnetic, optical, or electrical) is illustrated with a wide palette of application experiments, such as contactless droplet coalescence and mixing, solid-liquid encapsulation, absorption, dissolution, and DNA transfection. More than a century after the pioneering work of Lord Rayleigh on acoustic radiation pressure, a path-breaking concept is proposed to harvest the significant benefits of acoustic levitation in air.

  17. Remotely-operated equipment for inspection, measurement and handling

    CERN Document Server

    Bertone, C; CERN. Geneva. TS Department

    2008-01-01

    As part of the application of ALARA radiation dose reduction principles at CERN, inspection, measurement and handling interventions in controlled areas are being studied in detail. A number of activities which could be carried out as remote operations have already been identified and equipment is being developed. Example applications include visual inspection to check for ice formation on LHC components or water leaks, measurement of radiation levels before allowing personnel access, measurement of collimator or magnet alignment, visual inspection or measurements before fire service access in the event of fire, gas leak or oxygen deficiency. For these applications, a modular monorail train, TIM, has been developed with inspection and measurement wagons. In addition TIM provides traction, power and data communication for lifting and handling units such as the remote collimator exchange module and vision for other remotely operated units such as the TAN detector exchange mini-cranes. This paper describes the eq...

  18. Transport and handling LHC components A permanent challenge

    CERN Document Server

    Bertone, C

    2004-01-01

    The LHC project, collider and experiments, is an assembly of thousands of elements, large or small, heavy or light, fragile or robust. Each element has its own transport requirements that constitute a real challenge to handle. Even simple manoeuvres could lead to difficulties in integration, routing and execution due to the complex environment and confined underground spaces. Examples of typical LHC elements transport and handling will be detailed such as the 16-m long, 34-t heavy, fragile cryomagnets from the surface to the final destination in the tunnel, or the delicate cryogenic cold-boxes down to pits and detector components. This challenge did not only require a lot of imagination but also a close cooperation between all the involved parties, in particular with colleagues from safety, cryogenics, civil engineering, integration and logistics.

  19. Development of a handling technology for underwater inspection and dismantling

    International Nuclear Information System (INIS)

    Rose, N.

    1994-01-01

    For the purpose of underwater inspection and dismantling of nuclear facilities, a prototype of a freely submersible, remote-controlled handling system was developed and tested under laboratory conditions. Particular interest was taken in the specific boundary conditions of the area of application and the methodological concept. The system was developed in three phases; in each phase, a prototype was constructed and tested. (orig.) [de

  20. Food handling and mastication in the carp (Cyprinus carpio L.)

    OpenAIRE

    Sibbing, F.A.

    1984-01-01

    The process of food handling in the common carp ( Cyprinus carpio L.) and its structures associated with feeding are analyzed. The aim of this study is to explain the relation between the the architecture of the head and its functions in food processing and to determine the specializations for some food types and the consequent restrictions for others. Such information improves our understanding of the trophic interrelations between different fish species living...

  1. Ethical Infrastructure and Successful Handling of Workplace Bullying

    OpenAIRE

    Einarsen, Kari; Mykletun, Reidar; Einarsen, Ståle Valvatna; Skogstad, Anders; Salin, Denise

    2017-01-01

    Antecedents and consequences of workplace bullying are well documented. However, the mea- sures taken against workplace bullying, and the effectiveness of such measures, have received less attention. This study addresses this knowledge gap by exploring the role of ethical infrastructure in perceived successful handling of reported workplace bullying. Ethical infrastructure refers to formal and informal systems that enable ethical behavior and disable unethical behavior in organizations. A sur...

  2. Development and implementation of automated radioactive materials handling systems

    International Nuclear Information System (INIS)

    Jacoboski, D.L.

    1992-12-01

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

  3. Design and Implementation of Company Tailored Automated Material Handling

    DEFF Research Database (Denmark)

    Langer, Gilad; Bilberg, Arne

    1996-01-01

    This article focuses on the problems of analysing automation of material handling systems in order to develop an efficient automated solution that is specifically tailored to the company. The research has resulted in development of new methods for evaluating factory automation from design...... to implementation. The goals of the research were to analyse and evaluate automation in order to obtain an advantageous combination of human and automated resources. The idea is to asses different solutions in a virtual environment, where experiments and analyses can be performed so that the company can justify...... for their application with computer aided information processing tools. The framework is named the "Automated Material Handling (AMH) Preference GuideLine". The research has been carried out in close co-operation with Danish and European industry, where implementations of automation can be referred to. It is our...

  4. Protecting worker health and safety using remote handling systems

    International Nuclear Information System (INIS)

    Dennison, D.K.; Merrill, R.D.; Reed, R.K.

    1995-03-01

    Lawrence Livermore National Laboratory (LLNL) is currently developing and installing two large-scale, remotely controlled systems for use in improving worker health and safety by minimizing exposure to hazardous and radioactive materials. The first system is a full-scale liquid feed system for use in delivering chemical reagents to LLNL's existing aqueous low-level radioactive and mixed waste treatment facility (Tank Farm). The Tank Farm facility is used to remove radioactive and toxic materials in aqueous wastes prior to discharge to the City of Livermore Water Reclamation Plant (LWRP), in accordance with established discharge limits. Installation of this new reagent feed system improves operational safety and process efficiency by eliminating the need to manually handle reagents used in the treatment processes. This was done by installing a system that can inject precisely metered amounts of various reagents into the treatment tanks and can be controlled either remotely or locally via a programmable logic controller (PLC). The second system uses a robotic manipulator to remotely handle, characterize, process, sort, and repackage hazardous wastes containing tritium. This system uses an IBM-developed gantry robot mounted within a special glove box enclosure designed to isolate tritiated wastes from system operators and minimize the potential for release of tritium to the atmosphere. Tritiated waste handling is performed remotely, using the robot in a teleoperational mode for one-of-a-kind functions and in an autonomous mode for repetitive operations. The system is compatible with an existing portable gas cleanup unit designed to capture any gas-phase tritium inadvertently released into the glove box during waste handling

  5. Recommended domestic handling of fruits and vegetables to preserve their nutritional value

    Directory of Open Access Journals (Sweden)

    Julio Basulto

    2014-06-01

    Full Text Available The health benefits of daily consumption of at least 5 portions of a variety of fruit and vegetables are well documented. The World Health Organization (WHO public health goal, established in 600 grams per person/day, is not achieved in Spain, so it is important to improve access to these foods, maintain their potential nutritive value and overcome barriers for their consumption. The objectives of this paper are: facilitate responsible decision-making regarding health; maximize the nutritional value of fruit and vegetables, help overcome barriers for fruit and vegetables consumption and report on how their storage at home, their handling and cooking affect to nutritional value of fruit and vegetables.In order to minimize nutrients loss and improve their bioavailability during fruit and vegetables handling, the Association for the promotion of fruit and vegetables “5 a day” (Spain recommends: avoid prolonged storage of fruit and vegetables in the fridge; use layers and outer leaves; peel and/or cut them just before consumption; wash the whole pieces and then chop them; controlling the soaking time of cut pieces; prefer cooking techniques that do not require direct contact with water; a shorter cooking time, less loss of nutrients; the correct frying retains nutrients very well, although it is a technique of which should not be abused; add a few drops of vinegar or lemon juice to the cooking water if it does not change the taste and dish acceptance; use the water of cooking to elaborate other foods (e.g. sauces, soups, purees, etc. except those coming from chard, spinach or beets. The “5 a day” Association (Spain recommends increasing consumption of fruit and vegetables, and state that theloss of nutrients during their home handling should not be understood as a barrier for their consumption.

  6. Sample handling and chemical procedures for efficacious trace analysis of urine by neutron activation analysis

    International Nuclear Information System (INIS)

    Blotcky, A.J.; Rack, E.P.; Roman, F.R.

    1988-01-01

    Important for the determination of trace elements, ions, or compounds in urine by chemical neutron activation analysis is the optimization of sample handling, preirradiation chemistry, and radioassay procedures necessary for viable analysis. Each element, because of its natural abundance in the earth's crust and, hence, its potential for reagent and environmental contamination, requires specific procedures for storage, handling, and preirradiation chemistry. Radioassay techniques for radionuclides vary depending on their half-lives and decay characteristics. Described in this paper are optimized procedures for aluminum and selenium. While 28 Al (T 1/2 = 2.24 min) and 77m Se(T 1/2 = 17.4s) have short half-lives, their gamma-ray spectra are quite different. Aluminum-28 decays by a 1779-keV gamma and 77m Se by a 162-keV gamma. Unlike selenium, aluminum is a ubiquitous element in the environment requiring special handling to minimize contamination in all phases of its analytical determination

  7. Ontario hydro waste storage concepts and facilities

    International Nuclear Information System (INIS)

    Carter, T.J.; Mentes, G.A.

    1976-01-01

    Ontario Hydro presently operates 2,200 MWe of CANDU heavy water reactors with a further 11,000 MWe under design or construction. The annual quantities of low and medium level solid wastes expected to be produced at these stations are tabulated. In order to manage these wastes, Ontario Hydro established a Radioactive Waste Operations Site within the Bruce Nuclear Power Development located on Lake Huron about 250 km northwest of Toronto. The Waste Operations Site includes a 19-acre Storage Site plus a Radioactive Waste Volume Reduction Facility consisting of an incinerator and waste compactor. Ontario has in use or under construction both in-ground and above-ground storage facilities. In-ground facilities have been used for a number of years while the above-ground facilities are a more recent approach. Water, either in the form of precipitation, surface or subsurface water, presents the greatest concern with respect to confinement integrity and safe waste handling and storage operations

  8. Handling radioactivity: a practical approach for scientists and engineers

    International Nuclear Information System (INIS)

    Stewart, D.C.

    1981-01-01

    The aim of this book is to present an overall view in a descriptive and essentially nonmathematical way of the practicalities of handling radioactivity. It is hoped that the material will be particularly helpful to those entering the nuclear field for the first time and to those working in related areas whose responsibilities require them to have a general knowledge of the subject of radioactivity handling and its vocabulary. The presentation is primarily for bench-scale operations. There is a considerable emphasis on facilities since these are fundamental to the safe handling of active materials. Facility design and detail is also unfortunately an area where the relevant information is largely scattered through literature sources that are not accessible to most readers. Some of the topics surveyed - such as dosimetry, shielding and nuclear criticality - are extremely complex and no pretense is made that the treatment here represents more than bare bone summaries of the fields. A considerable effort has been made to cite the key references in each area where more detailed information can be found. A few additional useful references not cited directly in the text appear in an abbreviated bibliography at the end of the book

  9. Tricks and tips on handling a powder diffractometers

    Energy Technology Data Exchange (ETDEWEB)

    Veroli, C [CNR, Montelibretti, Rome (Italy). Istituto Chimica dei Materiali

    1996-09-01

    In the present work, the authors illustrate the procedure to be followed when small quantities of powder have to be analysed, and they also report how to generally reduce the measurement background. In addition, they describe how the diffractometer can be used to collect thin-film spectra. The experimental procedure requires careful handling because inappropriate or careless use of the instrument can lead to its damage.

  10. Dust prevention in bulk material transportation and handling

    Science.gov (United States)

    Kirichenko, A. V.; Kuznetsov, A. L.; Pogodin, V. A.

    2017-10-01

    The environmental problem of territory and atmosphere pollution caused by transportation and handling of dust-generating bulk cargo materials is quite common for the whole world. The reducing of weight of fine class coal caused by air blowing reaches the level of 0.5-0.6 t per railcar over the 500 km transportation distance, which is equal to the loss of 1 % of the total weight. The studies showed that all over the country in the process of the railroad transportation, the industry loses 3-5 metric tonnes of coal annually. There are several common tactical measurers to prevent dust formation: treating the dust-producing materials at dispatch point with special liquid solutions; watering the stacks and open handling points of materials; frequent dust removing and working area cleaning. Recently there appeared several new radical measures for pollution prevention in export of ore and coal materials via sea port terminals, specifically: wind-dust protection screens, the container cargo handling system of delivery materials to the hold of the vessels. The article focuses on the discussion of these measures.

  11. Waste Handling Equipment Development Test and Evaluation Study

    International Nuclear Information System (INIS)

    R.L. Tome

    1998-01-01

    The purpose of this study is to identify candidate Monitored Geologic Repository (MGR) surface waste handling equipment for development testing. This study will also identify strategies for performing the development tests. Development testing shall be implemented to support detail design and reduce design risks. Development testing shall be conducted to confirm design concepts, evaluate alternative design concepts, show the availability of needed technology, and provide design documentation. The candidate equipment will be selected from MGR surface waste handling equipment that is the responsibility of the Management and Operating Contractor (M and O) Surface Design Department. The equipment identified in this study is based on Viability Assessment (VA) design. The ''Monitored Geologic Repository Test and Evaluation Plan'' (MGR T and EP), Reference 5.1, was used as a basis for this study. The MGR T and EP reflects the extent of test planning and analysis that can be conducted, given the current status of the MGR requirements and latest VA design information. The MGR T and EP supports the appropriate sections in the license application (LA) in accordance with 10 CFR 60.2 1(c)(14). The MGR T and EP describes the following test activities: site characterization to confirm, by test and analysis, the suitability of the Yucca Mountain site for housing a geologic repository; development testing to investigate and document design concepts to reduce risk; qualification testing to verify equipment compliance with design requirements, specifications, and regulatory requirements; system testing to validate compliance with MGR requirements, which include the receipt, handling, retrieval, and disposal of waste; periodic performance testing to verify preclosure requirements and to demonstrate safe and reliable MGR operation; and performance confirmation modeling, testing, and analysis to verify adherence to postclosure regulatory requirements. Development test activities can be

  12. Microbiological Safety and Food Handling Practices of Seed Sprout Products in the Australian State of Victoria.

    Science.gov (United States)

    Symes, Sally; Goldsmith, Paul; Haines, Heather

    2015-07-01

    Seed sprouts have been implicated as vehicles for numerous foodborne outbreaks worldwide. Seed sprouts pose a unique food safety concern because of the ease of microbiological seed contamination, the inherent ability of the sprouting process to support microbial growth, and their consumption either raw or lightly cooked. To examine seed sprout safety in the Australian state of Victoria, a survey was conducted to detect specific microbes in seed sprout samples and to investigate food handling practices relating to seed sprouts. A total of 298 seed sprout samples were collected from across 33 local council areas. Escherichia coli was detected in 14.8%, Listeria spp. in 12.3%, and Listeria monocytogenes in 1.3% of samples analyzed. Salmonella spp. were not detected in any of the samples. A range of seed sprout handling practices were identified as potential food safety issues in some food businesses, including temperature control, washing practices, length of storage, and storage in proximity to unpackaged ready-to-eat potentially hazardous foods.

  13. Characterization of the 309 building fuel transfer pit and storage basin

    International Nuclear Information System (INIS)

    Hale, N.S.

    1998-01-01

    This document identifies radiological, chemical and physical conditions inside the Fuel Transfer Pit and Fuel Storage Basins. These spaces are located inside the Plutonium Recycle Test Reactor structure (309 Building.) The fuel handling and storage feature of the PRTR were primarily located in these spaces. The conditions were assessed as part of overall 309 Building transition

  14. Handling and Emplacement Options for Deep Borehole Disposal Conceptual Design.

    Energy Technology Data Exchange (ETDEWEB)

    Cochran, John R. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Hardin, Ernest [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

    2015-07-01

    This report presents conceptual design information for a system to handle and emplace packages containing radioactive waste, in boreholes 16,400 ft deep or possibly deeper. Its intended use is for a design selection study that compares the costs and risks associated with two emplacement methods: drill-string and wireline emplacement. The deep borehole disposal (DBD) concept calls for siting a borehole (or array of boreholes) that penetrate crystalline basement rock to a depth below surface of about 16,400 ft (5 km). Waste packages would be emplaced in the lower 6,560 ft (2 km) of the borehole, with sealing of appropriate portions of the upper 9,840 ft (3 km). A deep borehole field test (DBFT) is planned to test and refine the DBD concept. The DBFT is a scientific and engineering experiment, conducted at full-scale, in-situ, without radioactive waste. Waste handling operations are conceptualized to begin with the onsite receipt of a purpose-built Type B shipping cask, that contains a waste package. Emplacement operations begin when the cask is upended over the borehole, locked to a receiving flange or collar. The scope of emplacement includes activities to lower waste packages to total depth, and to retrieve them back to the surface when necessary for any reason. This report describes three concepts for the handling and emplacement of the waste packages: 1) a concept proposed by Woodward-Clyde Consultants in 1983; 2) an updated version of the 1983 concept developed for the DBFT; and 3) a new concept in which individual waste packages would be lowered to depth using a wireline. The systems described here could be adapted to different waste forms, but for design of waste packaging, handling, and emplacement systems the reference waste forms are DOE-owned high- level waste including Cs/Sr capsules and bulk granular HLW from fuel processing. Handling and Emplacement Options for Deep Borehole Disposal Conceptual Design July 23, 2015 iv ACKNOWLEDGEMENTS This report has

  15. Flexible Electrostatic Technology for Capture and Handling Project

    Science.gov (United States)

    Keys, Andrew; Bryan, Tom; Horwitz, Chris; Rakoczy, John; Waggoner, Jason

    2015-01-01

    To NASA unfunded & planned missions: This new capability to sense proximity, flexibly align to, and attractively grip and capture practically any object in space without any pre-designed physical features or added sensors or actuators will enable or enhance many of MSFC's strategic emphasis areas in space transportation, and space systems such as: 1. A Flexible Electrostatic gripper can enable the capture, gripping and releasing of an extraterrestrial sample of different minerals or a sample canister (metallic or composite) without requiring a handle or grapple fixture.(B) 2. Flexible self-aligning in-space capture/soft docking or berthing of ISS resupply vehicles, pressurized modules, or nodes for in-space assembly and shielding, radiator, and solar Array deployment for space habitats (C) 3. The flexible electrostatic gripper when combined with a simple steerable extendible boom can grip, position, and release objects of various shapes and materials with low mass and power without any prior handles or physical accommodations or surface contamination for ISS experiment experiments and in-situ repair.(F)(G) 4. The Dexterous Docking concept previously proposed to allow simple commercial resupply ships to station-keep and capture either ISS or an Exploration vehicle for supply or fluid transfer lacked a self-sensing, compliant, soft capture gripper like FETCH that could retract and attach to a CBM. (I) 5. To enable a soft capture and de-orbit of a piece of orbital debris will require self-aligning gripping and holding an object wherever possible (thermal coverings or shields of various materials, radiators, solar arrays, antenna dishes) with little or no residual power while adding either drag or active low level thrust.(K) 6. With the scalability of the FETCH technology, small satellites can be captured and handled or can incorporate FETCH gripper to dock to and handle other small vehicles and larger objects for de-orbiting or mitigating Orbital debris (L) 7. Many of

  16. Oxygen Handling and Cooling Options in High Temperature Electrolysis Plants

    Energy Technology Data Exchange (ETDEWEB)

    Manohar S. Sohal; J. Stephen Herring

    2008-07-01

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

  17. Spent fuel storage - dry storage options and issues

    International Nuclear Information System (INIS)

    Akins, M.J.

    2007-01-01

    The increase in the number of nuclear energy power generation facilities will require the ability to store the spent nuclear fuel for a long period until the host countries develop reprocessing or disposal options. Plants have storage pools which are closely associated with the operating units. These are excellent for short term storage, but require active maintenance and operations support which are not desirable for the long term. Over the past 25 years, dry storage options have been developed and implemented throughout the world. In recent years, protection against terrorist attack has become an increasing source of design objectives for these facilities, as well as the main nuclear plant. This paper explores the current design options of dry storage cask systems and examines some of the current design issues for above ground , in-ground, or below-ground storage of spent fuel in dry casks. (author)

  18. Investigation into slipping and falling accidents and materials handling in the South African mining industry.

    CSIR Research Space (South Africa)

    Schutte, PC

    2003-03-01

    Full Text Available The objective of this study was to analyze information on slipping and falling accidents and materials handling activities in the South African mining industry. Accident data pertaining to slipping, falling and materials handling accidents...

  19. Design and Analysis of a Hydrogen Compression and Storage Station

    Science.gov (United States)

    2017-12-01

    standards relating to the production , transportation, handling, and storage of hydrogen gas. Four of CGAs standards were consulted during the design and...assessed as a low risk since the manufacturer had not experienced problems after several thousands of hours of work with their product . Future station...specified by their manufacturers . These pressure-temperature ratings are summarized for each tubing size in Table 6. A more rigorous design was

  20. K Basins fuel encapsulation and storage hazard categorization

    International Nuclear Information System (INIS)

    Porten, D.R.

    1994-12-01

    This document establishes the initial hazard categorization for K-Basin fuel encapsulation and storage in the 100 K Area of the Hanford site. The Hazard Categorization for K-Basins addresses the potential for release of radioactive and non-radioactive hazardous material located in the K-Basins and their supporting facilities. The Hazard Categorization covers the hazards associated with normal K-Basin fuel storage and handling operations, fuel encapsulation, sludge encapsulation, and canister clean-up and disposal. The criteria categorizes a facility based on total curies per radionuclide located in the facility. Tables 5-3 and 5-4 display the results in section 5.0. In accordance with DOE-STD-1027 and the analysis provided in section 5.0, the K East Basin fuel encapsulation and storage activity and the K West Basin storage are classified as a open-quotes Category 2close quotes Facility

  1. Licensing of spent fuel dry storage and consolidated rod storage

    International Nuclear Information System (INIS)

    Bailey, W.J.

    1990-02-01

    The results of this study, performed by Pacific Northwest Laboratory (PNL) and sponsored by the US Department of Energy (DOE), respond to the nuclear industry's recommendation that a report be prepared that collects and describes the licensing issues (and their resolutions) that confront a new applicant requesting approval from the US Nuclear Regulatory Commission (NRC) for dry storage of spent fuel or for large-scale storage of consolidated spent fuel rods in pools. The issues are identified in comments, questions, and requests from the NRC during its review of applicants' submittals. Included in the report are discussions of (1) the 18 topical reports on cask and module designs for dry storage fuel that have been submitted to the NRC, (2) the three license applications for dry storage of spent fuel at independent spent fuel storage installations (ISFSIs) that have been submitted to the NRC, and (3) the three applications (one of which was later withdrawn) for large-scale storage of consolidated fuel rods in existing spent fuel storage pools at reactors that were submitted tot he NRC. For each of the applications submitted, examples of some of the issues (and suggestions for their resolutions) are described. The issues and their resolutions are also covered in detail in an example in each of the three subject areas: (1) the application for the CASTOR V/21 dry spent fuel storage cask, (2) the application for the ISFSI for dry storage of spent fuel at Surry, and (3) the application for full-scale wet storage of consolidated spent fuel at Millstone-2. The conclusions in the report include examples of major issues that applicants have encountered. Recommendations for future applicants to follow are listed. 401 refs., 26 tabs

  2. Code of practice for the control and safe handling of radioactive sources used for therapeutic purposes (1988)

    International Nuclear Information System (INIS)

    1988-01-01

    This Code is intended as a guide to safe practices in the use of sealed and unsealed radioactive sources and in the management of patients being treated with them. It covers the procedures for the handling, preparation and use of radioactive sources, precautions to be taken for patients undergoing treatment, storage and transport of radioactive sources within a hospital or clinic, and routine testing of sealed sources [fr

  3. Handling system for nuclear reactor fuel and reflector elements

    International Nuclear Information System (INIS)

    Hawke, B.C.; Goldman, L.A.

    1980-01-01

    A system for canning, inspecting and transferring to a storage area fuel and reflector elements from a nuclear reactor is described. The canning mechanism operates in a sealed gaseous environment and visual and mechanical inspection of the elements is possible by an operator from a remote shielded area. (UK)

  4. Cryogenic Propellant Storage and Transfer

    Data.gov (United States)

    National Aeronautics and Space Administration — Space Flight Demonstration development has been canceled in favor of a ground test bed development for of passive/active cryogenic propellant storage, transfer, and...

  5. Storage Tank Legionella and Community

    Data.gov (United States)

    U.S. Environmental Protection Agency — Storage Tank Legionella and Community. This dataset is associated with the following publication: Qin, K., I. Struewing, J. Santodomingo, D. Lytle, and J. Lu....

  6. Neutronic and thermal hydraulic of dry cask storage systems

    International Nuclear Information System (INIS)

    Yavuz, U.

    2000-01-01

    Interim spent fuel storage systems must provide for the safe receipt, handling, retrieval and storage of spent nuclear fuel before reprocessing or disposal. In the context of achieving these objectives, the following features of the design are to be taken into consideration: to maintain fuel subcritical, to remove spent fuel residualheat, and to provide for radiation protection. These features in the design of a dry cask storage system were analyzed for normal operating conditions by employing COBRA-SFS, SCALE4.4 (ORIGEN, XSDOSE, CSAS6) codes. For a metal-shielded type storage system, appropriate designs, in accordance with safety assurance limits of IAEA, were obtained for spent fuel burned to 33000, 45000 and 55000 MW d/t and cooled for 5 and 10 years

  7. Freezing and refrigerated storage in fisheries

    National Research Council Canada - National Science Library

    Johnston, W. A

    1994-01-01

    ...; the factors affecting cold storage conditions, etc. In addition, the publication describes the methods used to calculate cold storage refrigeration loads as well as the costs of freezing and cold storage...

  8. Uranium hexafluoride: Safe handling, processing, and transporting: Conference proceedings

    Energy Technology Data Exchange (ETDEWEB)

    Strunk, W.D.; Thornton, S.G. (eds.)

    1988-01-01

    This conference seeks to provide a forum for the exchange of information and ideas of the safety aspects and technical issue related to the handling of uranium hexafluoride. By allowing operators, engineers, scientists, managers, educators, and others to meet and share experiences of mutual concern, the conference is also intended to provide the participants with a more complete knowledge of technical and operational issues. The topics for the papers in the proceedings are widely varied and include the results of chemical, metallurgical, mechanical, thermal, and analytical investigations, as well as the developed philosophies of operational, managerial, and regulatory guidelines. Papers have been entered individually into EDB and ERA. (LTN)

  9. Uranium hexafluoride: Safe handling, processing, and transporting: Conference proceedings

    International Nuclear Information System (INIS)

    Strunk, W.D.; Thornton, S.G.

    1988-01-01

    This conference seeks to provide a forum for the exchange of information and ideas of the safety aspects and technical issue related to the handling of uranium hexafluoride. By allowing operators, engineers, scientists, managers, educators, and others to meet and share experiences of mutual concern, the conference is also intended to provide the participants with a more complete knowledge of technical and operational issues. The topics for the papers in the proceedings are widely varied and include the results of chemical, metallurgical, mechanical, thermal, and analytical investigations, as well as the developed philosophies of operational, managerial, and regulatory guidelines. Papers have been entered individually into EDB and ERA

  10. Handling, conditioning and disposal of spent sealed sources

    International Nuclear Information System (INIS)

    1990-02-01

    The series entitled ''Technical Manual for the Management of Low and Intermediate Level Wastes Generated at Small Nuclear Research Centres and by Radioisotope Users in Medicine, Research and Industry'' will serve as reference material to experts on technical assistance missions and provide ''direct know-how'' for technical staff in developing countries. This document is the first in the series. It provides the technical guidance and know-how necessary to permit developing Member States to safely handle, condition and store spent sealed radiation sources. It covers: characterization of sealed sources, legislation and regulations, management of spent sealed sources, transportation and disposal of spent sealed sources. 5 refs, 10 figs, 6 tabs

  11. Neonatal handling affects durably bonding and social development.

    Directory of Open Access Journals (Sweden)

    Séverine Henry

    Full Text Available The neonatal period in humans and in most mammals is characterized by intense mother-young interactions favoring pair bonding and the adaptation of neonates to their new environment. However, in many post-delivery procedures, human babies commonly experience combined maternal separation and intense handling for about one hour post-birth. Currently, the effects of such disturbances on later attachment and on the development of newborns are still debated: clearly, further investigations are required. As animals present good models for controlled experimentation, we chose domestic horses to investigate this issue. Horses, like humans, are characterized by single births, long lactating periods and selective mother-infant bonds. Routine postnatal procedures for foals, as for human babies, also involve intense handling and maternal separation. In the present study, we monitored the behavior of foals from early stages of development to "adolescence", in a normal ecological context (social groups with adults and peers. Experimental foals, separated from their mothers and handled for only 1 hour post-birth, were compared to control foals, left undisturbed after birth. Our results revealed short- and long-term effects of this unique neonatal experience on attachment and subsequent social competences. Thus, experimental foals presented patterns of insecure attachment to their mothers (strong dependence on their mothers, little play and impaired social competences (social withdrawal, aggressiveness at all ages. We discuss these results in terms of mother-young interactions, timing of interactions and relationships between bonding and subsequent social competences. Our results indicate that this ungulate species could become an interesting animal model. To our knowledge, this is the first clear demonstration that intervention just after birth affects bonding and subsequent social competences (at least until "adolescence". It opens new research directions for

  12. Distributed and parallel approach for handle and perform huge datasets

    Science.gov (United States)

    Konopko, Joanna

    2015-12-01

    Big Data refers to the dynamic, large and disparate volumes of data comes from many different sources (tools, machines, sensors, mobile devices) uncorrelated with each others. It requires new, innovative and scalable technology to collect, host and analytically process the vast amount of data. Proper architecture of the system that perform huge data sets is needed. In this paper, the comparison of distributed and parallel system architecture is presented on the example of MapReduce (MR) Hadoop platform and parallel database platform (DBMS). This paper also analyzes the problem of performing and handling valuable information from petabytes of data. The both paradigms: MapReduce and parallel DBMS are described and compared. The hybrid architecture approach is also proposed and could be used to solve the analyzed problem of storing and processing Big Data.

  13. Nuclear robotics and remote handling at Harwell Laboratory

    International Nuclear Information System (INIS)

    Abel, E.; Brown, M.H.; Fischer, P.J.; Garlick, D.R.; Hanna, T.T.; Siva, K.V.

    1988-01-01

    After reviewing robotics technology and its possible application in nuclear remote handling systems of the future, six main research topics were identified where particular effort should be made. The Harwell Nuclear Robotics Programme is currently establishing sets of demonstration hardware which will allow generic research to be carried out on telerobotics, systems integration, the man machine interface, communications, servo systems and radiation tolerance. The objectives of the demonstrators are to allow validation of the techniques required for successful active facility applications such as decommissioning, decontamination, refurbishment, maintenance and repair, and to act as training aids to encourage plant designers and operators to adopt developments in new technology. (author)

  14. Post-irradiation handling and examination at the HFEF complex

    International Nuclear Information System (INIS)

    Bacca, J.P.

    1980-01-01

    The Hot Fuel Examination Facility provides postirradiation handling and examination of fast reactor irradiation experiments and safety tests for the United States Breeder Reactor Program. Nondestructive interim examinations and destructive terminal examinations at HFEF derive data from tests irradiated in the Experimental Breeder Reactor No. II, in the Transient Reactor Test Facility (TREAT), and in the Sodium Loop Safety Facility. Similar support will be provided in the near future for tests irradiated in the Fast Flux Test Facility, and for the larger sodium loops to be irradiated in TREAT

  15. AB Levitator and Electricity Storage

    OpenAIRE

    Bolonkin, Alexander

    2007-01-01

    The author researched this new idea - support of flight by any aerial vehicles at significant altitude solely by the magnetic field of the planet. It is shown that current technology allows humans to create a light propulsion (AB engine) which does not depend on air, water or ground terrain. Simultaniosly, this revolutionary thruster is a device for the storage of electricity which is extracted and is replenished (during braking) from/into the storage with 100 percent efficiency. The relative...

  16. Fuel assembly transfer and storage system for nuclear reactors

    International Nuclear Information System (INIS)

    Allain, Albert; Thomas, Claude.

    1981-01-01

    Transfer and storage system on a site comprising several reactors and at least one building housing the installations common to all these reactors. The system includes: transfer and storage modules for the fuel assemblies comprising a containment capable of containing several assemblies carried on a transport vehicle, a set of tracks for the modules between the reactors and the common installations, handling facilities associated with each reactor for moving the irradiated assemblies from the reactor to a transfer module placed in loading position on a track serving the reactor and conversely to move the new assemblies from the transfer module to the reactor, and at least one handling facility located in the common installation building for loading the modules with new assemblies [fr

  17. Off-line programming and simulation in handling nuclear components

    International Nuclear Information System (INIS)

    Baker, C.P.

    1993-10-01

    IGRIP was used to create a simulation of the robotic workcell design for handling components at the PANTEX nuclear arms facility. This initial simulation identified problems with the customer's proposed worker layout, and allowed a correction to be proposed. Refinement of the IGRIP simulation allowed the design and construction of a workcell mock-up and accurate off-line programming of the system. IGRIP's off-line programming capabilities are being used to develop the motion control code for the workcell. PNLs success in this area suggests that simulation and off-line programming may be valuable tools for developing robotics in some automation resistant industries

  18. Overview of DOE LLWMP waste treatment, packaging, and handling activities

    International Nuclear Information System (INIS)

    Pechin, W.H.

    1982-01-01

    The program objective is to develop the best available technology for waste treatment, packaging, and handling to meet the needs of shallow land burial disposal and for greater confinement than shallow land burial. The program has reviewed many of the hardware options for appropriate usage with low-level waste, but promising options remain to be evaluated. The testing of treatment technologies with actual radioactive process wastes has been initiated. The analysis of the interaction of treatment, solidification and disposal needs to be completed

  19. Assembly and handling apparatus for the EBFA Marx generator

    International Nuclear Information System (INIS)

    Staller, G.E.; Hiett, G.E.; Hamilton, I.D.; Aker, M.F.; Daniels, G.A.

    1979-05-01

    Marx generators, a major slow-pulsed power component in Sandia Laboratories' Electron Beam Fusion Accelerator (EBFA), were assembled at a remote facility modified to utilize an assembly-line technique. Due to the size and weight of the various components, as well as the final Marx generator assembly, special handling apparatus was designed. Time and manpower constraints required that this assembly be done in parallel with the construction of the Electron Beam Fusion Facility (EBFF). The completed Marx generators were temporarily stored and then moved from the assembly building to the EBFF using special transportation racks designed specifically for this purpose

  20. Cryogenic Propellant Storage and Transfer Engineering Development Unit Hydrogen Tank

    Science.gov (United States)

    Werkheiser, Arthur

    2015-01-01

    The Cryogenic Propellant Storage and Transfer (CPST) project has been a long-running program in the Space Technology Mission Directorate to enhance the knowledge and technology related to handling cryogenic propellants, specifically liquid hydrogen. This particular effort, the CPST engineering development unit (EDU), was a proof of manufacturability effort in support of a flight article. The EDU was built to find and overcome issues related to manufacturability and collect data to anchor the thermal models for use on the flight design.

  1. Options and processes for spent catalyst handling and utilization.

    Science.gov (United States)

    Marafi, M; Stanislaus, A

    2003-07-18

    The quantity of spent hydroprocessing catalysts discarded as solid wastes in the petroleum refining industries has increased remarkably in recent years due to a rapid growth in the hydroprocessing capacity to meet the rising demand for low-sulfur fuels. Due to their toxic nature, spent hydroprocessing catalysts have been branded as hazardous wastes, and the refiners are experiencing pressure from environmental authorities to handle them safely. Several alternative methods such as reclamation of metals, rejuvenation and reuse, disposal in landfills and preparation of useful materials using spent catalysts as raw materials are available to deal with the spent catalyst problem. The technical feasibility as well as the environmental and economic aspects of these options are reviewed. In addition, details of two bench-scale processes, one for rejuvenation of spent hydroprocessing catalysts, and the other for producing non-leachable synthetic aggregate materials that were developed in this laboratory, are presented in this paper.

  2. Study and Evaluation of Innovative Fuel Handling Systems for Sodium-Cooled Fast Reactors: Fuel Handling Route Optimization

    Directory of Open Access Journals (Sweden)

    Franck Dechelette

    2014-01-01

    Full Text Available The research for technological improvement and innovation in sodium-cooled fast reactor is a matter of concern in fuel handling systems in a view to perform a better load factor of the reactor thanks to a quicker fuelling/defueling process. An optimized fuel handling route will also limit its investment cost. In that field, CEA has engaged some innovation study either of complete FHR or on the optimization of some specific components. This paper presents the study of three SFR fuel handling route fully described and compared to a reference FHR option. In those three FHR, two use a gas corridor to transfer spent and fresh fuel assembly and the third uses two casks with a sodium pot to evacuate and load an assembly in parallel. All of them are designed for the ASTRID reactor (1500 MWth but can be extrapolated to power reactors and are compatible with the mutualisation of one FHS coupled with two reactors. These three concepts are then intercompared and evaluated with the reference FHR according to four criteria: performances, risk assessment, investment cost, and qualification time. This analysis reveals that the “mixed way” FHR presents interesting solutions mainly in terms of design simplicity and time reduction. Therefore its study will be pursued for ASTRID as an alternative option.

  3. Development and evaluation of online video teaching resources to enhance student knowledge of livestock handling.

    Science.gov (United States)

    Klupiec, C; Pope, S; Taylor, R; Carroll, D; Ward, M H; Celi, P

    2014-07-01

    To evaluate the effectiveness of online audiovisual materials to support the acquisition of animal handling skills by students of veterinary and animal science. A series of video clips (Livestock Handling modules) demonstrating livestock handling procedures was created and delivered online to students enrolled in the Faculty of Veterinary Science, University of Sydney. The effectiveness of these modules for supporting student learning was evaluated via an online survey. The survey also sought feedback on how students could be better prepared for handling livestock. The survey indicated that students found the videos a useful part of their learning experience, particularly by familiarising them with correct handling procedures and emphasising the importance of safety when handling livestock. Students also highlighted that online delivery supported flexible learning. Suggested improvements of the Livestock Handling modules centred around broadening the content of the videos and improving the user-friendliness of online access. Student feedback regarding how the Faculty could better prepare them for livestock handling was dominated by requests for more opportunities to practise animal handling using live animals. The Livestock Handling audiovisual tool is a valuable supplementary resource for developing students' proficiency in safe and effective handling of livestock. However, the results also clearly reveal a perception by students that more hands-on experience is required for acquisition of animal handling skills. These findings will inform future development of the Faculty's animal handling program. © 2014 Australian Veterinary Association.

  4. Storage and security of supply

    International Nuclear Information System (INIS)

    Svensson, B.R.

    1990-01-01

    The paper considers the relationship between energy security and the consumption, supply and storage of natural gas, as agreed between the IEA Member countries. Additional supplies of natural gas should be obtained from as diverse sources as possible with emphasis on indigenous OECD sources. Instruments for coping with supply disruptions, such as underground storage of gas, interruptible gas sales, and dual-fired capabilities should be strengthened. These instruments, however, in combination with contractual swing factors, are also used to cope with fluctuations in demand for natural gas. The future demand and supply of natural gas in OECD Europe and North America is discussed. In OECD Europe the growth in residential and commercial demand is expected to be sustained, and, in both OECD Europe and North America, there is a further potential demand for gas for electricity generation. As residential and commercial demand (which is very temperature-dependent) grows, the need for storage facilities, interruptible sales contracts, dual-fired capabilities and swing factors in contracts will increase in order to balance the load. An expansion of gas demand for baseload electricity generation could, however, increase the load factor. Figures for the size of the storage capacity in 1987 and plans for future increases show that storage capacity is increasing. It is concluded that new underground storage represents an important contribution to the strengthening of each country's ability both to balance loads and to deal with supply disruptions. The IEA countries rely on the gas utilities to provide storage and other instruments for both purposes. (author). 2 figs, 3 tabs

  5. Safe handling of renewable fuels and fuel mixtures

    Energy Technology Data Exchange (ETDEWEB)

    Wilen, C; Rautalin, A [VTT Energy, Espoo (Finland)

    1997-12-01

    VTT Energy has for several years carried out co-operation with many European research institutes on contractional basis on safety issues of fuels handling. A two-year co-operational project between VTT Energy and these research institutes was started in EU`s JOULE 3 programme in 1996, the total budget of which is 6.9 million FIM. Dust explosion testing method for `difficult` fuels, and for tests at elevated pressures and temperatures, will be developed in the task `Safe handling of renewable fuels and fuel mixtures`. Self- ignition and dust-explosion characteristics will be generated for wood and agro-biomass based biomasses and for the mixtures of them and coal. Inertization requirements will be studied, and the quenching method, combined with partial inertization, will be tested in 1.0 m{sup 3} test equipment. The ignition properties of the fuels under normal and elevated pressures will be characterised with thermobalances. The self-ignition tests with wood and forest residue dusts at 25 bar pressure have been carried out as scheduled. In addition to this, several fuels have undergone thermobalance tests, sieve analyses and microscopic studies for the characterisation of the fuels

  6. Remote handling and automation in back end of fuel cycle

    International Nuclear Information System (INIS)

    Nair, K.N.S.

    2010-01-01

    Full text: Indian nuclear programme is readying for a quantum leap and it is essential that technology is available for building advanced fuel recycle plants in the back end and for sustained operation of such plants. Remote technology and automation plays a big role to achieve this goal. With the introduction of advanced fuel cycles in indigenous programme and scenario of international cooperation it is essential to be ready with indigenous technology for meeting all challenges. Work has been progressing to develop locally support technology for remote handling and automation with good success. Essential RH tools such as master slave manipulators, power manipulators and hot cell viewing systems have been developed and commercial production has been established. Customised RH requirements for back end plants have been met and the designs have proven to be worthy for hot operations over the years. In the last few years stress has been on development of equipment and technology to meet the increasing demands of higher throughput plants. Substantial progress has been achieved in the head end and reconversion laboratory systems of reprocessing plants. Similarly successful efforts have also been made for establishing Thoria processing cells and also the RH in the reconversion operations. Custom designed equipment has been developed for decommissioning of ceramic melter, used glove boxes etc. Efforts are on hand to develop automated RH equipment for material handling in underground repositories. This paper aims at bringing out the theme based on some of our own experiences and some reports from plants in operation abroad. (author)

  7. Remote waste handling and feed preparation for Mixed Waste Management

    International Nuclear Information System (INIS)

    Couture, S.A.; Merrill, R.D.; Densley, P.J.

    1995-05-01

    The Mixed Waste Management Facility (MWMF) at the Lawrence Livermore National Laboratory (LLNL) will serve as a national testbed to demonstrate mature mixed waste handling and treatment technologies in a complete front-end to back-end --facility (1). Remote operations, modular processing units and telerobotics for initial waste characterization, sorting and feed preparation have been demonstrated at the bench scale and have been selected for demonstration in MWMF. The goal of the Feed Preparation design team was to design and deploy a robust system that meets the initial waste preparation flexibility and productivity needs while providing a smooth upgrade path to incorporate technology advances as they occur. The selection of telerobotics for remote handling in MWMF was made based on a number of factors -- personnel protection, waste generation, maturity, cost, flexibility and extendibility. Modular processing units were selected to enable processing flexibility and facilitate reconfiguration as new treatment processes or waste streams are brought on line for demonstration. Modularity will be achieved through standard interfaces for mechanical attachment as well as process utilities, feeds and effluents. This will facilitate reconfiguration of contaminated systems without drilling, cutting or welding of contaminated materials and with a minimum of operator contact. Modular interfaces also provide a standard connection and disconnection method that can be engineered to allow convenient remote operation

  8. Remote handling facility and equipment used for space truss assembly

    International Nuclear Information System (INIS)

    Burgess, T.W.

    1987-01-01

    The ACCESS truss remote handling experiments were performed at Oak Ridge National Laboratory's (ORNL's) Remote Operation and Maintenance Demonstration (ROMD) facility. The ROMD facility has been developed by the US Department of Energy's (DOE's) Consolidated Fuel Reprocessing Program to develop and demonstrate remote maintenance techniques for advanced nuclear fuel reprocessing equipment and other programs of national interest. The facility is a large-volume, high-bay area that encloses a complete, technologically advanced remote maintenance system that first began operation in FY 1982. The maintenance system consists of a full complement of teleoperated manipulators, manipulator transport systems, and overhead hoists that provide the capability of performing a large variety of remote handling tasks. This system has been used to demonstrate remote manipulation techniques for the DOE, the Power Reactor and Nuclear Fuel Development Corporation (PNC) of Japan, and the US Navy in addition to the National Aeronautics and Space Administration. ACCESS truss remote assembly was performed in the ROMD facility using the Central Research Laboratory's (CRL) model M-2 servomanipulator. The model M-2 is a dual-arm, bilateral force-reflecting, master/slave servomanipulator which was jointly developed by CRL and ORNL and represents the state of the art in teleoperated manipulators commercially available in the United States today. The model M-2 servomanipulator incorporates a distributed, microprocessor-based digital control system and was the first successful implementation of an entirely digitally controlled servomanipulator. The system has been in operation since FY 1983. 3 refs., 2 figs

  9. Systems for harvesting and handling cotton plant residue

    Energy Technology Data Exchange (ETDEWEB)

    Coates, W. [Univ. of Arizona, Tucson, AZ (United States)

    1993-12-31

    In the warmer regions of the United States, cotton plant residue must be buried to prevent it from serving as an overwintering site for insect pests such as the pink bollworm. Most of the field operations used to bury the residue are high energy consumers and tend to degrade soil structure, thereby increasing the potential for erosion. The residue is of little value as a soil amendment and consequently is considered a negative value biomass. A commercial system to harvest cotton plant residue would be of both economic and environmental benefit to cotton producers. Research has been underway at the University of Arizona since the spring of 1991 to develop a commercially viable system for harvesting cotton plant residue. Equipment durability, degree of densification, energy required, cleanliness of the harvested material, and ease of product handling and transport are some of the performance variables which have been measured. Two systems have proven superior. In both, the plants are pulled from the ground using an implement developed specifically for the purpose. In one system, the stalks are baled using a large round baler, while in the other the stalks are chopped with a forage harvester, and then made into packages using a cotton module maker. Field capacities, energy requirements, package density and durability, and ease of handling with commercially available equipment have been measured for both systems. Selection of an optimum system for a specific operation depends upon end use of the product, and upon equipment availability.

  10. Steller sea lion capture, marking, and handling data across their range 1985-2014

    Data.gov (United States)

    National Oceanic and Atmospheric Administration, Department of Commerce — This database contains information on individual sea lions that were marked or handled from 1985-2014. Individuals were handled for various projects including vital...

  11. Handling and Treatment of Poultry Hatchery Waste: A Review

    Directory of Open Access Journals (Sweden)

    Belinda Rodda

    2011-01-01

    Full Text Available A literature review was undertaken to identify methods being used to handle and treat hatchery waste. Hatchery waste can be separated into solid waste and liquid waste by centrifuging or by using screens. Potential methods for treating hatchery waste on site include use of a furnace to heat the waste to produce steam to run a turbine generator or to use an in line composter to stabilise the waste. There is also potential to use anaerobic digestion at hatcheries to produce methane and fertilisers. Hatcheries disposing wastewater into lagoons could establish a series of ponds where algae, zooplankton and fish utilise the nutrients using integrated aquaculture which cleans the water making it more suitable for irrigation. The ideal system to establish in a hatchery would be to incorporate separation and handling equipment to separate waste into its various components for further treatment. This would save disposal costs, produce biogas to reduce power costs at plants and produce a range of value added products. However the scale of operations at many hatcheries is too small and development of treatment systems may not be viable.

  12. Handling newborn monkeys alters later exploratory, cognitive, and social behaviors.

    Science.gov (United States)

    Simpson, Elizabeth A; Sclafani, Valentina; Paukner, Annika; Kaburu, Stefano S K; Suomi, Stephen J; Ferrari, Pier F

    2017-08-18

    Touch is one of the first senses to develop and one of the earliest modalities for infant-caregiver communication. While studies have explored the benefits of infant touch in terms of physical health and growth, the effects of social touch on infant behavior are relatively unexplored. Here, we investigated the influence of neonatal handling on a variety of domains, including memory, novelty seeking, and social interest, in infant monkeys (Macaca mulatta; n=48) from 2 to 12 weeks of age. Neonates were randomly assigned to receive extra holding, with or without accompanying face-to-face interactions. Extra-handled infants, compared to standard-reared infants, exhibited less stress-related behavior and more locomotion around a novel environment, faster approach of novel objects, better working memory, and less fear towards a novel social partner. In sum, infants who received more tactile stimulation in the neonatal period subsequently demonstrated more advanced motor, social, and cognitive skills-particularly in contexts involving exploration of novelty-in the first three months of life. These data suggest that social touch may support behavioral development, offering promising possibilities for designing future early interventions, particularly for infants who are at heightened risk for social disorders. Copyright © 2017. Published by Elsevier Ltd.

  13. Occupational Health and Safety: reflection on potential risks and the safety handling of nanomaterials

    Directory of Open Access Journals (Sweden)

    Guilherme Frederico Bernardo Lenz e Silva

    2013-11-01

    Full Text Available Every day the nanotechnology, that refers to a field whose theme is the control of matter on an atomic and molecular scale working with nanometric structures (<100 nm, is more present in the development of products and industrial processes. The particle manipulation of nanometric structures has created opportunities in the development of new products and materials. However, synthesis, handling, storage, stabilization and the incorporation of these materials, with nanometric dimensions, demand a new perspective of analysis and evaluation of old manufacturing processes, procedures and industrial devices, in order to guarantee collective and individual protection to workers and society. With the increasing of scale and production of nanoestrutuctured materials, a big part of labour community starts to be in contact with different nanomaterials (forms and ways. In this work the main aspects and involved risks of manufacture, storage, synthesis, stabilization and incorporation of nanomaterials on new products are evaluated in order to reduce, decrease and eliminate chemical, physical and biological risks for the employees. A bibliographic review was conducted about risk, safety and nanotechnology based on available English literature focusing safety and environmental agencies from different countries such as USA, Canada, EU (France, UK, Germany, Den-mark, Australia and Japan.

  14. Environmental stress responses and experimental handling artifacts of a model organism, the copepod Acartia tonsa (Dana)

    DEFF Research Database (Denmark)

    Nilsson, Birgitte; Jepsen, Per Meyer; Bucklin, Ann

    2018-01-01

    for these genes between 15 min and 24 h following exposure. Since handling stress clearly affects transcriptional patterns, it is important to consider handling when designing experiments, by either including additional controls or avoiding focus on impacted genes. Not considering handling in gene expression...... studies can lead to inaccurate conclusions. The present study provides a baseline for studying handling stress in future studies using this model organism and others....

  15. Review on Fuel Loading Process and Performance for Advanced Fuel Handling Equipment

    International Nuclear Information System (INIS)

    Chang, Sang-Gyoon; Lee, Dae-Hee; Kim, Young-Baik; Lee, Deuck-Soo

    2007-01-01

    The fuel loading process and the performance of the advanced fuel handling equipment for OPR 1000 (Optimized Power Plant) are analyzed and evaluated. The fuel handling equipment, which acts critical processes in the refueling outage, has been improved to reduce fuel handling time. The analysis of the fuel loading process can be a useful tool to improve the performance of the fuel handling equipment effectively. Some recommendations for further improvement are provided based on this study

  16. The handling, hazards, and maintenance of heavy liquids in the geologic laboratory

    Science.gov (United States)

    Hauff, Phoebe L.; Airey, Joseph

    1980-01-01

    In geologic laboratories the organic heavy liquids bromoform, methylene iodide, tetrabromoethane, and clerici compounds have been used for years in mineral separation processes. Because the volume of use of these compounds is low, insufficient data is available on their toxic properties. This report is an attempt to summarize the known data from published and industry sources. The physical properties, hazards of handling,proper storage facilities, and adequate protective Clothing are discussed for each compound as well as for their common and less-common solvents. Toxicity data for these materials is listed along with exposure symptoms and suggested first aid treatments. Safety for the worker is emphasized. Three reclamation methods which recover the solvent used as a dilutant and purify the heavy liquid are discussed and illustrated. These include: the water cascade, re fluxing-distillation-condensation, and flash evaporation methods. Various techniques for restoration and stabilization of these heavy liquids are also included.

  17. New aspects of blood collection and handling procedures for the assessment of t-PA and PAI-1 variables after the introduction of acid blood collection

    NARCIS (Netherlands)

    Meijer, P.; Kret, R.; Bloetjes, P.T.M.; Rosen, S.; Kluft, C.

    1994-01-01

    Blood collection and handling procedures for t-PA activity have thusfar been rather strict and have restrained the use in clinical practice. We evaluated simplifications in the procedures for specifically the use of Stabilyte® vacutainers with respect to time before centrifugation of blood, storage

  18. Quality assurance system in the production process of the gamma shielding devices used for transport and handling of radiopharmaceuticals and labelled compounds at Cuba

    International Nuclear Information System (INIS)

    Zuniga Santana, Juan F.; Fernandez Rondon, Manuel; Viante Garrido, Enrique; Berdeguez, Mirta B.T.; Rodriguez Perez, Hilario

    1999-01-01

    The paper shows how a Quality Assurance System for the process of production of gamma shielding devices has been conceived, designed and implemented. Special emphasis is given to the necessity of utilizing tools of control statistic in order to guaranteed the quality in the serial production process of such devices used in the transport, storage and handling of radioactive materials.(author)

  19. Carbon capture and storage (CCS)

    International Nuclear Information System (INIS)

    Martin-Amouroux, Jean-Marie

    2016-01-01

    The author first defines what carbon capture and storage (CCS)is, describes more precisely the various technologies, methods and processes involved in carbon capture, carbon transport, and carbon geological storage. He briefly evokes the various applications and uses of CCS. In the second part, he proposes an overview of advances and deadlocks of CCS in the world, of the status of installations and projects, of the development of capture practices in the industry, of some existing and important storage sites, of some pilot installations developed by various industrial actors in different countries (26 installations in the world). He indicates power stations equipped for CCS (in Canada, USA, United-Kingdom, Netherlands, Norway, China, South Korea and United Arab Emirates). He evokes projects which have been given up or postponed. He proposes an overview of policies implemented in different countries (USA, Canada, European Union, Australia, and others) to promote CCS

  20. Uranium hexafluoride handling. Proceedings

    Energy Technology Data Exchange (ETDEWEB)

    1991-12-31

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

  1. Uranium hexafluoride handling

    International Nuclear Information System (INIS)

    1991-01-01

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

  2. Superconductivity, energy storage and switching

    International Nuclear Information System (INIS)

    Laquer, H.L.

    1974-01-01

    The phenomenon of superconductivity can contribute to the technology of energy storage and switching in two distinct ways. On one hand the zero resistivity of the superconductor can produce essentially infinite time constants so that an inductive storage system can be charged from very low power sources. On the other hand, the recovery of finite resistivity in a normal-going superconducting switch can take place in extremely short times, so that a system can be made to deliver energy at a very high power level. Topics reviewed include: physics of superconductivity, limits to switching speed of superconductors, physical and engineering properties of superconducting materials and assemblies, switching methods, load impedance considerations, refrigeration economics, limitations imposed by present day and near term technology, performance of existing and planned energy storage systems, and a comparison with some alternative methods of storing and switching energy. (U.S.)

  3. Development of tritium-handling technique

    International Nuclear Information System (INIS)

    Ohmura, Hiroshi; Hosaka, Akio; Okamoto, Takahumi

    1988-01-01

    The overview of developing activities for tritium-handling techniques in IHI are presented. To establish a fusion power plant, tritium handling is one of the key technologies. Recently in JAERI, conceptual design of FER (Fusion Experimental Reactor) has been carried out, and the FER system requires a processing system for a large amount of tritium. IHI concentrate on investigation of fuel gas purification, isotope separation and storage systems under contract with Toshiba Corporation. Design results of the systems and each components are reviewed. IHI has been developing fundamental handling techniques which are the ZrNi bed for hydrogen isotope storage and isotope separation by laser. The ZrNi bed with a tritium storage capacity of 1000 Ci has been constructed and recovery capability of the hydrogen isotope until 10 -4 Torr {0.013 Pa} was confirmed. In laser isotope separation, the optimum laser wave length has been determined. (author)

  4. Effects of the European Community directive on lifting and handling practice.

    Science.gov (United States)

    Docker, S M

    1993-07-01

    The new legislation on lifting and handling requires the application of ergonomic principles to manual handling operations. A written assessment is required for all unavoidable manual handling operations which involve the risk of injury to employees. Employers are now expected to provide equipment to enable staff to avoid lifting heavy loads.

  5. Radioactive waste handling and disposal at King Faisal Specialist Hospital and Research Centre.

    Science.gov (United States)

    Al-Haj, Abdalla N; Lobriguito, Aida M; Al Anazi, Ibrahim

    2012-08-01

    King Faisal Specialist Hospital & Research Centre (KFSHRC) is the largest specialized medical center in Saudi Arabia. It performs highly specialized diagnostic imaging procedures with the use of various radionuclides required by sophisticated dual imaging systems. As a leading institution in cancer research, KFSHRC uses both long-lived and short-lived radionuclides. KFSHRC established the first cyclotron facility in the Middle East, which solved the in-house high demand for radionuclides and the difficulty in importing them. As both user and producer of high standard radiopharmaceuticals, KFSHRC generates large volumes of low and high level radioactive wastes. An old and small radioactive facility that was used for storage of radioactive waste was replaced with a bigger warehouse provided with facilities that will reduce radiation exposure of the staff, members of the public, and of the environment in the framework of "as low as reasonably achievable." The experiences and the effectiveness of the radiation protection program on handling and storage of radioactive wastes are presented.

  6. Orion Handling Qualities During ISS Rendezvous and Docking

    Science.gov (United States)

    Hart, Jeremy J.; Stephens, J. P.; Spehar, P.; Bilimoria, K.; Foster, C.; Gonzalex, R.; Sullivan, K.; Jackson, B.; Brazzel, J.; Hart, J.

    2011-01-01

    The Orion spacecraft was designed to rendezvous with multiple vehicles in low earth orbit (LEO) and beyond. To perform the required rendezvous and docking task, Orion must provide enough control authority to perform coarse translational maneuvers while maintaining precision to perform the delicate docking corrections. While Orion has autonomous docking capabilities, it is expected that final approach and docking operations with the International Space Station (ISS) will initially be performed in a manual mode. A series of evaluations was conducted by NASA and Lockheed Martin at the Johnson Space Center to determine the handling qualities (HQ) of the Orion spacecraft during different docking and rendezvous conditions using the Cooper-Harper scale. This paper will address the specifics of the handling qualities methodology, vehicle configuration, scenarios flown, data collection tools, and subject ratings and comments. The initial Orion HQ assessment examined Orion docking to the ISS. This scenario demonstrates the Translational Hand Controller (THC) handling qualities of Orion. During this initial assessment, two different scenarios were evaluated. The first was a nominal docking approach to a stable ISS, with Orion initializing with relative position dispersions and a closing rate of approximately 0.1 ft/sec. The second docking scenario was identical to the first, except the attitude motion of the ISS was modeled to simulate a stress case ( 1 degree deadband per axis and 0.01 deg/sec rate deadband per axis). For both scenarios, subjects started each run on final approach at a docking port-to-port range of 20 ft. Subjects used the THC in pulse mode with cues from the docking camera image, window views, and range and range rate data displayed on the Orion display units. As in the actual design, the attitude of the Orion vehicle was held by the automated flight control system at 0.5 degree deadband per axis. Several error sources were modeled including Reaction

  7. Combined solar collector and energy storage system

    Science.gov (United States)

    Jensen, R. N. (Inventor)

    1980-01-01

    A combined solar energy collector, fluid chiller and energy storage system is disclosed. A movable interior insulated panel in a storage tank is positionable flush against the storage tank wall to insulate the tank for energy storage. The movable interior insulated panel is alternately positionable to form a solar collector or fluid chiller through which the fluid flows by natural circulation.

  8. Handling and feeding of biomass to pressurized reactors: safety engineering

    Energy Technology Data Exchange (ETDEWEB)

    Wilen, Carl; Rautalin, Aimo (Valtion Teknillinen Tutkimuskeskus, Espoo (Finland). Lab. of Fuel and Process Technology)

    1993-01-01

    There are rather few literature references to or experience of the feed of biomass into a pressurized space. Alternatives given in the literature usually concern handling and feeding technology for coal. Some screw- or piston-operated plug feeders and coal and concrete pump equipment have, however, also been tested with biomasses. Explosion characteristics of fuels and their susceptibility to spontaneous ignition have been studied at both atmospheric and elevated pressures. The maximum explosion pressure and maximum rate of pressure rise, being critical factors in the process design and in the choice of safety equipment, have been determined under these conditions. In pressurized processes, the maintenance of sufficient inertization in fuel-feed systems is an especially critical factor. Peat, bark, and forest residues were used as biofuels, and lignite was used as reference fuel. The results obtained with a dynamic method for spontaneous ignition were compared with experience obtained from the operation of a commercial pressurized peat gasifier of 140 MW. (author)

  9. Alarm handling systems and techniques developed to match operator tasks

    Energy Technology Data Exchange (ETDEWEB)

    Bye, A; Moum, B R [Institutt for Energiteknikk, Halden (Norway). OECD Halden Reaktor Projekt

    1997-09-01

    This paper covers alarm handling methods and techniques explored at the Halden Project, and describes current status on the research activities on alarm systems. Alarm systems are often designed by application of a bottom-up strategy, generating alarms at component level. If no structuring of the alarms is applied, this may result in alarm avalanches in major plant disturbances, causing cognitive overload of the operator. An alarm structuring module should be designed using a top-down approach, analysing operator`s tasks, plant states, events and disturbances. One of the operator`s main tasks during plant disturbances is status identification, including determination of plant status and detection of plant anomalies. The main support of this is provided through the alarm systems, the process formats, the trends and possible diagnosis systems. The alarm system should both physically and conceptually be integrated with all these systems. 9 refs, 5 figs.

  10. Alarm handling systems and techniques developed to match operator tasks

    International Nuclear Information System (INIS)

    Bye, A.; Moum, B.R.

    1997-01-01

    This paper covers alarm handling methods and techniques explored at the Halden Project, and describes current status on the research activities on alarm systems. Alarm systems are often designed by application of a bottom-up strategy, generating alarms at component level. If no structuring of the alarms is applied, this may result in alarm avalanches in major plant disturbances, causing cognitive overload of the operator. An alarm structuring module should be designed using a top-down approach, analysing operator's tasks, plant states, events and disturbances. One of the operator's main tasks during plant disturbances is status identification, including determination of plant status and detection of plant anomalies. The main support of this is provided through the alarm systems, the process formats, the trends and possible diagnosis systems. The alarm system should both physically and conceptually be integrated with all these systems. 9 refs, 5 figs

  11. Optimal design and application of a compound cold storage system combining seasonal ice storage and chilled water storage

    NARCIS (Netherlands)

    Yan, C.; Shi, W.; Li, X.; Zhao, Y.

    2016-01-01

    Seasonal cold storage using natural cold sources for cooling is a sustainable cooling technique. However, this technique suffers from limitations such as large storage space and poor reliability. Combining seasonal storage with short-term storage might be a promising solution while it is not

  12. Underground transportation and handling system for Pollux-casks

    International Nuclear Information System (INIS)

    Schrimpf, C.

    1988-01-01

    The concept for the underground transportation and handling system for Pollux-casks was optimized in a first phase by dividing the process in the repository up into the several transportation and manipulation steps. For each step, the possibilities were described and evaluated by means of a list of criteria (technical, safety and economical criteria). The following concept for the transportation and handling was developed: The casks are transported to the unloading area of the surface facilities by railway or truck. After removal of the transport protection, the entry control is performed. The cask is lifted from the vehicle and placed on a railbound transportation vehicle. This transport unit is transferred to the shaft and placed there ready for shaft hoisting. With the hoisting cage protruding, the transport unit is placed on the hoisting cage by means of a pushing-on device, locked, and then conveyed underground. After arrival on the emplacement level, the transport unit is pulled-off from the hoisting cage and taken over by a mine locomotive and transferred through the transportation and access drifts as far as to the emplacement site. There the locomotive pushed the rail transport vehicle into the emplacement drift, as far as to the designated emplacement position. At the emplacement position, the cask is again lifted by means of hoisting equipment. The rail transport vehicle is pulled out of the emplacement drift and returned to the surface for reloading. After deposition of the cask on the drift floor, the emplacement equipment is pulled back in order to give the operation space free for the slinger backfill truck. Within preceding tests two different backfilling techniques were investigated under realistic conditions: pneumatic backfilling and slinger backfilling. The slinger truck was found to be the most suitable for the designated purpose

  13. NDMA guidelines on handling of nuclear and radiological emergencies

    Energy Technology Data Exchange (ETDEWEB)

    Abani, M C [National Disaster Management Authority, New Delhi (India)

    2010-07-01

    The vulnerability to the disasters is high in India due to the large population density, fast growing urbanization, industrialization and also because of poor economic conditions of people. Natural disasters have been recurring phenomena in India, leading to extensive loss of life, livelihood and property. The primary reason for such heavy losses can be attributed to the reactive and response-centric approach adopted in the past in handling of the disasters. Based on the Guidelines a holistic approach is to be adopted for Nuclear Emergency Management Framework that assigns the highest priority to prevention, mitigation and compliance to regulatory requirements, while strengthening preparedness, capacity development, response etc. It will be implemented through strengthening of the existing action plans or by preparing new action plans at national, state and district levels by the stakeholders at all levels of administration

  14. NDMA guidelines on handling of nuclear and radiological emergencies

    International Nuclear Information System (INIS)

    Abani, M.C.

    2010-01-01

    The vulnerability to the disasters is high in India due to the large population density, fast growing urbanization, industrialization and also because of poor economic conditions of people. Natural disasters have been recurring phenomena in India, leading to extensive loss of life, livelihood and property. The primary reason for such heavy losses can be attributed to the reactive and response-centric approach adopted in the past in handling of the disasters. Based on the Guidelines a holistic approach is to be adopted for Nuclear Emergency Management Framework that assigns the highest priority to prevention, mitigation and compliance to regulatory requirements, while strengthening preparedness, capacity development, response etc. It will be implemented through strengthening of the existing action plans or by preparing new action plans at national, state and district levels by the stakeholders at all levels of administration

  15. Risking existence: The experience and handling of depression.

    Science.gov (United States)

    Bygstad-Landro, Marte; Giske, Tove

    2018-02-01

    To gain insight into how people suffering from depression experience and manage life. Depression is the leading cause of incapacitation and constitutes the second largest healthcare burden worldwide, causing considerable discomfort for depression sufferers and their significant others. Depression must be understood against the backdrop of a person's context as well as biological, psychological and social factors. While various studies have been conducted on the process of depression, only a few studies have examined its existential aspects. A classical grounded theory methodology employing open and selective coding was used to identify the participants' main concern and the strategies they used to handle it. Data were collected in 2015-2016 during 18 in-depth interviews with people with current or former moderate depression. The data were analysed through constant comparisons until the grounded theory emerged. The main concern of the participants was Longing for belonging, and they handled their depression through a process named Risking existence. The process comprised four phases: (i) Ungraspable processing; (ii) Giving clues; (iii) Daring dependence; and (iv) Courage to be. The process of risking existence was accompanied from beginning to end by three essentials: to hope, to endure and shame. Working in mental health care involves encountering the pain, suffering and despair that humans endure. This challenges nurses to go beyond the symptoms and to listen for their meaning to each individual person. The grounded theory of risking existence provides a model by which nurses can orient themselves when working with people who are depressed. Each phase describes different strategies that patients use that can help the nurse recognise what is going on, thus enabling him or her to understand and guide his or her patients. © 2017 John Wiley & Sons Ltd.

  16. Handling stolen goods in Iranian and English criminal law

    Directory of Open Access Journals (Sweden)

    Sayyed Mohammad Hoseini

    2014-07-01

    Full Text Available Handling stolen goods has been recognized as an independent offence in both Iranian and English law. Committing this offence, tacitly support those actions that are called theft. However, penal policy of Iran’s legislator does not provide effective fighting against the handlers of stolen goods. In others words, comparing the two Iranian and English legal system, make this issue clear that criminalization of stolen goods has some restrictions about physical element as well as the amount of relevant punishment that we can have more effective fighting against supporting factors of larceny with eliminating them and hereto, in the course of exercising appropriate reaction to the handlers, reducing the offence of theft. The article seeks to recommend some solutions for a better penal policy, such as increasing punishment of the offence and extending the scope of its physical behaviour, through comparative analysis of the offence of stolen goods; meanwhile different elements of the offence have been studied.

  17. 324 Building liquid waste handling and removal system project plan

    Energy Technology Data Exchange (ETDEWEB)

    Ham, J.E.

    1998-07-29

    This report evaluates the modification options for handling radiological liquid waste generated during decontamination and cleanout of the 324 Building. Recent discussions indicate that the Hanford site railroad system will be closed by the end of FY 1998 necessitating the need for an alternate transfer method. The issue of handling of Radioactive Liquid Waste (RLW) from the 324 Building (assuming the 340 Facility is not available to accept the RLW) has been examined in at least two earlier engineering studies (Parsons 1997a and Hobart 1997). Each study identified a similar preferred alternative that included modifying the 324 Building RLWS to allow load-out of wastewater to a truck tanker, while making maximum use of existing piping, tanks, instrumentation, controls and other features to minimize costs and physical changes to the building. This alternative is accepted as the basis for further discussion presented in this study. The goal of this engineering study is to verify the path forward presented in the previous studies and assure that the selected alternative satisfies the 324 Building deactivation goals and objectives as currently described in the project management plan. This study will also evaluate options available to implement the preferred alternative and select the preferred option for implementation of the entire system. Items requiring further examination will also be identified. Finally, the study will provide a conceptual design, schedule and cost estimate for the required modifications to the 324 Building to allow removal of RLW. Attachment 5 is an excerpt from the project baseline schedule found in the Project Management Plan.

  18. Storage, transportation and disposal system for used nuclear fuel assemblies

    Science.gov (United States)

    Scaglione, John M.; Wagner, John C.

    2017-01-10

    An integrated storage, transportation and disposal system for used fuel assemblies is provided. The system includes a plurality of sealed canisters and a cask sized to receive the sealed canisters in side by side relationship. The plurality of sealed canisters include an internal basket structure to receive a plurality of used fuel assemblies. The internal basket structure includes a plurality of radiation-absorbing panels and a plurality of hemispherical ribs generally perpendicular to the canister sidewall. The sealed canisters are received within the cask for storage and transportation and are removed from the cask for disposal at a designated repository. The system of the present invention allows the handling of sealed canisters separately or collectively, while allowing storage and transportation of high burnup fuel and damaged fuel to the designated repository.

  19. Fuel handling, reprocessing, and waste and related nuclear data aspects

    International Nuclear Information System (INIS)

    Kuesters, H.; Lalovic, M.; Wiese, H.W.

    1979-06-01

    The essential processes in the out-of-pile nuclear fuel cycle are described, i.e. mining and milling of uranium ores, enrichment, fuel fabrication, storage, transportation, reprocessing of irradiated fuel, waste treatment and waste disposal. The aspects of radiation (mainly gammas and neutrons) and of heat production, as well as special safety considerations are outlined with respect to their potential operational impacts and long-term hazards. In this context the importance of nuclear data for the out-of-pile fuel cycle is discussed. Special weight is given to the LWR fuel cycle including recycling; the differences of LMFBR high burn-up fuel with large PuO 2 content are described. The HTR fuel cycle is discussed briefly as well as some alternative fuel cycle concepts. (orig.) [de

  20. Fischer-Tropsch Cobalt Catalyst Activation and Handling Through Wax Enclosure Methods

    Science.gov (United States)

    Klettlinger, Jennifer L. S.; Yen, Chia H.; Nakley, Leah M.; Surgenor, Angela D.

    2016-01-01

    Fischer-Tropsch (F-T) synthesis is considered a gas to liquid process which converts syn-gas, a gaseous mixture of hydrogen and carbon monoxide, into liquids of various hydrocarbon chain length and product distributions. Cobalt based catalysts are used in F-T synthesis and are the focus of this paper. One key concern with handling cobalt based catalysts is that the active form of catalyst is in a reduced state, metallic cobalt, which oxidizes readily in air. In laboratory experiments, the precursor cobalt oxide catalyst is activated in a fixed bed at 350 ?C then transferred into a continuous stirred tank reactor (CSTR) with inert gas. NASA has developed a process which involves the enclosure of active cobalt catalyst in a wax mold to prevent oxidation during storage and handling. This improved method allows for precise catalyst loading and delivery into a CSTR. Preliminary results indicate similar activity levels in the F-T reaction in comparison to the direct injection method. The work in this paper was supported by the NASA Fundamental Aeronautics Subsonics Fixed Wing Project.

  1. Cask and plug handling system design in port cell

    International Nuclear Information System (INIS)

    Martins, Jean-Pierre; Friconneau, Jean-Pierre; Gabellini, Eros; Keller, Delphine; Levesy, Bruno; Selvi, Anna; Tesini, Alessandro; Utin, Yuri; Wagrez, Julien

    2011-01-01

    The ITER maintenance strategy relies partly on the remote transfer of components from vacuum vessel to hot cells. This function will be fulfilled by transfer cask systems. This paper describes the recent design progresses on interfaces in order to increase components handling feasibility by implementing continuous guiding features that avoid cantilevered loads on the in-cask tractor. Also the design has progressed in order to allow generic docking of the casks. When the cask is connected to the port, it becomes part of the machine first confinement boundary, thus it must provide tightness continuity. This high level safety function was one of the main concerns of a finite element analysis study that has been performed to assess the behavior of the whole system. Numerical analysis methodology and results are explained and shown in order to highlight how it has reinforced the knowledge of the system.

  2. New International Initiatives on Enhancement of Biosafety and Biosecurity Regulations for Laboratories Handling Infectious Agents

    International Nuclear Information System (INIS)

    Netesov, S. V.; Drozdov, I. G.

    2007-01-01

    Before we entered the era of antibiotics, development of antiseptics rules and reliable water purification systems the infectious pathogens had played a major role in morbidity and mortality of global human population. The advances in revealing the nature of dangerous infections and studying their causative agents during the recent years have led not only to big progress in their control but also to the study of their potential as weapons. During the last fifty years, several attempts have been made to use them for criminal or terrorist purposes that demonstrated that even primitively organized terrorist attacks may lead to quite significant consequences. The October 2001 events showed that bioterrorism attacks may be prepared, probably, as a result of theft of the pathogen from a lab. All this led to the revision and radical improvement of current national rules and international recommendations in the field of handling, storage and transportation of infectious agents. As a result, during the past two years these rules have been significantly revised by both the World Health Organization and some countries. However, their harmonization of is still far from what is desired. Therefore, biosafety professionals in some countries, including those of the European Union, are establishing professional biosafety associations. In addition, new initiatives are being proposed to develop internationally harmonized biosecurity rules to govern dangerous pathogens handling and storage. The most important of them are as follows: 1. Development, under the auspices of WHO, of new recommendations concerning a set of requirements to provide physical security of both biological agents and laboratories involved in research on extremely hazardous infections; 2. Enhacement, under the auspices of WHO, of current international recommendations on inventory procedures and regulations, inventory monitoring, and transportation of specimens and strains of extremely hazardous infections; 3

  3. Enhancing hydrogen spillover and storage

    Science.gov (United States)

    Yang, Ralph T [Ann Arbor, MI; Li, Yingwel [Ann Arbor, MI; Lachawiec, Jr., Anthony J.

    2011-05-31

    Methods for enhancing hydrogen spillover and storage are disclosed. One embodiment of the method includes doping a hydrogen receptor with metal particles, and exposing the hydrogen receptor to ultrasonification as doping occurs. Another embodiment of the method includes doping a hydrogen receptor with metal particles, and exposing the doped hydrogen receptor to a plasma treatment.

  4. Krypton-85 removal and storage

    International Nuclear Information System (INIS)

    Gutierrez Fernandez, J.

    1978-01-01

    A literature survey was made in order to predict the atmospheric Kr-85 concentration in the future and it s effect on the population. As a consequence the need for its treatment and removal as a previous step to gaseous waste disposal is justified. A literature review of possible methods of Kr-85 removal and storage is also included. (Author) 43 refs

  5. BASIC overlay for CAMAC data and command handling

    Energy Technology Data Exchange (ETDEWEB)

    Ciftcioglu, O [Istanbul Technical Univ. (Turkey). Inst. for Nuclear Energy

    1979-11-15

    A BASIC overlay has been developed for the BASIC language run in the PDP-11 series of computers. The overlay has particularly been wirtten for a dedicated Camac Crate Controller DC-011 from Ortec. By means of the overlay, any command comprising C, N, A, F information can easily be issued by the host system to communicate with the peripherals connected to the CAMAC system, through the CAMAC interface. The overlay is particularly useful for rather slow control systems and data handling between two different operating systems with incompatible formats for the data files having the CAMAC system as a mutual system component controllable by each of the operating systems individually. The overlay can easily be modified to be used for a Standard controller (type A-1) or any other type of dedicated controller.

  6. [The Necessity and the Current Status of Safe Handling of Anticancer Drugs].

    Science.gov (United States)

    Kanda, Kiyoko

    2017-07-01

    Number of people who handle anticancer drugs in their profession is increasing. Anticancer drugs, which are hazardous drugs(HD), exert cytocidal effects on cancer cells, but many have also been shown to have mutagenicity, teratogenicity and carcinogenicity; therefore, safe handling of anticancer drugs is necessary. In July 2015, the first Japanese guidelines for exposure control measures, namely, the "Joint Guidelines for Safe Handling of Cancer Chemotherapy Drugs", were published jointly by 3 societies. Our guideline is the creation of the Japanese Society of Cancer Nursing(JSCN), Japanese Society of Medical Oncology(JSMO)and Japanese Society of Pharmaceutical Oncology(JASPO)and has a historical significance. This paper states the necessity of safe handling of anticancer drugs, Japan's recent movement of safe handling, the introduction of joint guidelines of safe handling of anticancer drugs, and new movement of safe handling of USP chapter 800 in the United States.

  7. Mobilization and mixing of settled solids in horizontal storage tanks

    International Nuclear Information System (INIS)

    Cummins, R.L.

    1995-01-01

    Studies were conducted using submerged jets for the mobilization and mixing of settled solids to form a suspension that can easily be removed from storage tanks. These studies focus on the specific problems relating to horizontal, cylindrical storage tanks. Of primary consideration are the storage tanks located at the Oak Ridge National Laboratory which are used for the collection of remote-handled, radioactive liquid wastes. These wastes are in two phases. A layer of undissolved, settled solids varying from 2 to 4 feet in depth under a layer of supernate. Using a surrogate of the tank contents and an approximate 2/3 dimensional scale tank, tests were performed to determine the optimum design and location of suction and discharge nozzles as well as the minimum discharge velocity required to achieve complete mobilization of the solids in the tank

  8. Storage and separation of gases

    International Nuclear Information System (INIS)

    Biloe, S.; Cagnon, B.; Goetz, V.; Guillot, A.; Mauran, S.; Mazet, N.; Menard, D.; Py, X.

    2005-01-01

    Various processes such as gas separation, gas storage (H 2 or CH 4 ) are known to be inhibited by intrinsic antagonistic material properties (texture, thermal conductivity, permeability). In the following document are gathered the last progress in adsorbent material elaboration and process engineering. (authors)

  9. Environmental Stress Responses and Experimental Handling Artifacts of a Model Organism, the Copepod Acartia tonsa (Dana

    Directory of Open Access Journals (Sweden)

    Birgitte Nilsson

    2018-05-01

    Full Text Available Handling animals during experiments potentially affects the differential expression of genes chosen as biomarkers of sub-lethal stress. RNA sequencing was used to examine whole-transcriptome responses caused by laboratory handling of the calanoid copepod, Acartia tonsa. Salinity shock (S = 35 to S = 5 was used as positive stress control; individuals not exposed to handling or other stressors served as negative stress control. All copepods were grown from eggs to adults without being handled or exposed to any stressors prior the experiment. Survival of nauplii and adults was estimated for up to 10 min of exposure to handling stress and salinity shock. Only adults exhibited decreased survival (44 ± 7% with 10 min of exposure in response to handling stress and were selected for definitive experiments for RNA sequencing. After 10 min of experimental exposures to handling stress or salinity shock, adults were incubated for 15 min or 24 h at normal culture conditions. A small number of significantly differentially expressed genes (DEGs were observed 15 min after exposure to handling stress (2 DEGs or salinity shock (7 DEGs. However, 24 h after exposure, handling stress resulted in 276 DEGs and salinity shock resulted in 573 DEGs, of which 174 DEGs were overlapping between the treatments. Among the DEGs observed 24 h after exposure to handling stress or salinity shock, some commonly-used stress biomarkers appeared at low levels. This suggests that a stress-response was induced at the transcriptional level for these genes between 15 min and 24 h following exposure. Since handling stress clearly affects transcriptional patterns, it is important to consider handling when designing experiments, by either including additional controls or avoiding focus on impacted genes. Not considering handling in gene expression studies can lead to inaccurate conclusions. The present study provides a baseline for studying handling stress in future studies using this

  10. Monitored Retrievable Storage/Multi-Purpose Canister analysis: Simulation and economics of automation

    International Nuclear Information System (INIS)

    Bennett, P.C.; Stringer, J.B.

    1994-01-01

    Robotic automation is examined as a possible alternative to manual spent nuclear fuel, transport cask and Multi-Purpose canister (MPC) handling at a Monitored Retrievable Storage (MRS) facility. Automation of key operational aspects for the MRS/MPC system are analyzed to determine equipment requirements, through-put times and equipment costs is described. The economic and radiation dose impacts resulting from this automation are compared to manual handling methods

  11. 9 CFR 201.82 - Care and promptness in weighing and handling livestock and live poultry.

    Science.gov (United States)

    2010-01-01

    ... handling livestock and live poultry. 201.82 Section 201.82 Animals and Animal Products GRAIN INSPECTION... handling livestock and live poultry. (a) Each stockyard owner, market agency, dealer, packer and live poultry dealer shall exercise reasonable care and promptness with respect to loading, transporting...

  12. Ergonomic design and evaluation of the handle for an endoscopic dissector.

    Science.gov (United States)

    Shimomura, Yoshihiro; Minowa, Keita; Kawahira, Hiroshi; Katsuura, Tetsuo

    2016-05-01

    The purpose of this study was to design an endoscopic dissector handle and objectively assess its usability. The handles were designed with increased contact area between the fingers and thumb and the eye rings, and the eye rings were modified to have a more perpendicular insertion angle to the finger midline. Four different handle models were compared, including a conventional product. Subjects performed dissection, exclusion, grasping, precision manipulation and precision handling tasks. Electromyography and subjective evaluations were measured. Compared to conventional handles, the designated handle reduced the muscle load in the extensor and flexor muscles of the forearm and increased subjective stability. The activity of the first dorsal interosseous muscle was sometimes influenced by the shape of the other parts. The ergonomically designed endoscopic dissector handle used in this study achieved high usability. Medical instrument designs based on ergonomic concepts should be assessed with objective indices. Practitioner Summary: The endoscopic dissector handles were designed with increased contact area and more suitable insertion angle between the fingers and thumb and the eye rings. Compared to conventional handles, the designated handle reduced the muscle load in the extensor and flexor muscles of the forearm and increased subjective stability.

  13. Conceptual design and cost estimation of dry cask storage facility for spent fuel

    International Nuclear Information System (INIS)

    Maki, Yasuro; Hironaga, Michihiko; Kitano, Koichi; Shidahara, Isao; Shiomi, Satoshi; Ohnuma, Hiroshi; Saegusa, Toshiari

    1985-01-01

    In order to propose an optimum storage method of spent fuel, studies on the technical and economical evaluation of various storage methods have been carried out. This report is one of the results of the study and deals with storage facility of dry cask storage. The basic condition of this work conforms to ''Basic Condition for Spent Fuel Storage'' prepared by Project Group of Spent Fuel Dry Storage at July 1984. Concerning the structural system of cask storage facilities, trench structure system and concrete silo system are selected for storage at reactor (AR), and a reinforced concrete structure of simple design and a structure with membrance roof are selected for away from reactor (AFR) storage. The basic thinking of this selection are (1) cask is put charge of safety against to radioactivity and (2) storage facility is simplified. Conceptual designs are made for the selected storage facilities according to the basic condition. Attached facilities of storage yard structure (these are cask handling facility, cask supervising facility, cask maintenance facility, radioactivity control facility, damaged fuel inspection and repack facility, waste management facility) are also designed. Cost estimation of cask storage facility are made on the basis of the conceptual design. (author)

  14. Radioisotope handling facilities and automation of radioisotope production

    International Nuclear Information System (INIS)

    2004-12-01

    If a survey is made of the advances in radioisotope handling facilities, as well as the technical conditions and equipment used for radioisotope production, it can be observed that no fundamental changes in the design principles and technical conditions of conventional manufacture have happened over the last several years. Recent developments are mainly based on previous experience aimed at providing safer and more reliable operations, more sophisticated maintenance technology and radioactive waste disposal. In addition to the above observation, significant improvements have been made in the production conditions of radioisotopes intended for medical use, by establishing aseptic conditions with clean areas and isolators, as well as by introducing quality assurance as governing principle in the production of pharmaceutical grade radioactive products. Requirements of the good manufacturing practice (GMP) are increasingly complied with by improving the technical and organizational conditions, as well as data registration and documentation. Technical conditions required for the aseptic production of pharmaceuticals and those required for radioactive materials conflicting in some aspects are because of the contrasting contamination mechanisms and due consideration of the radiation safety. These can be resolved by combining protection methods developed for pharmaceuticals and radioactive materials, with the necessary compromise in some cases. Automation serves to decrease the radiation dose to the operator and environment as well as to ensure more reliable and precise radiochemical processing. Automation has mainly been introduced in the production of sealed sources and PET radiopharmaceuticals. PC controlled technologies ensure high reliability for the production and product quality, whilst providing automatic data acquisition and registration required by quality assurance. PC control is also useful in the operation of measuring instruments and in devices used for

  15. Storage and distribution/Linear programming for storage operations

    Energy Technology Data Exchange (ETDEWEB)

    Coleman, D

    1978-07-15

    The techniques of linear programing to solve storage problems as applied in a tank farm tie-in with refinery throughput operation include: (1) the time-phased model which works on storage and refinery operations input parameters, e.g., production, distribution, cracking, etc., and is capable of representing product stockpiling in slack periods to meet future peak demands, and investigating alternative strategies such as exchange deals and purchase and leasing of additional storage, and (2) the Monte Carlo simulation method, which inputs parameters, e.g., arrival of crude products at refinery, tankage size, likely demand for products, etc., as probability distributions rather than single values, and is capable of showing the average utilization of facilities, potential bottlenecks, investment required to achieve an increase in utilization, and to enable the user to predict total investment, cash flow, and profit emanating from the original financing decision. The increasing use of computer techniques to solve refinery and storage problems is attributed to potential savings resulting from more effective planning, reduced computer costs, ease of access and more usable software. Diagrams.

  16. Simulating and visualizing deflections of a remote handling mechanism

    Energy Technology Data Exchange (ETDEWEB)

    Saarinen, Hannu, E-mail: hannu.saarinen@vtt.fi [VTT, Technical Research Centre of Finland, Tekniikankatu 1, 33720 Tampere (Finland); Hämäläinen, Vesa; Karjalainen, Jaakko; Määttä, Timo; Siuko, Mikko [VTT, Technical Research Centre of Finland, Tekniikankatu 1, 33720 Tampere (Finland); Esqué, Salvador [Fusion for Energy, Torres Diagonal Litoral B3, Josep Pla 2, 08019 Barcelona (Spain); Hamilton, David [ITER Organization, Route de Vinon sur Verdon, 13115 Saint Paul Lez Durance (France)

    2013-10-15

    Highlights: ► An infinitesimal transformation represents elastic deflections. ► Equivalent spring factor is used to combine several deformations. ► Initial VR model accuracy improved from 80 to 5 mm. ► The deflection model is capable of adapting to changes in load at the end-effector. ► The algorithms and approach described are generic and can be adopted for other mechanisms. -- Abstract: Continuing ITER divertor second cassette (SC) remote handling (RH) test campaign has been carried out at divertor test platform (DTP2) in Finland. One of the goals has been to develop and implement efficient algorithms and software tools for simulating and visualizing for the operator the non-instrumented deflections of the RH mechanisms under loading conditions. Based on assumptions of the classical beam theory, the presented solution suggests utilization of an infinitesimal transformation to represent elastic deflections in a mechanical structure. Both structural analysis and measurements of the real structure are utilised during the process. The solution suggests one possible implementation strategy of a software component called structural simulator (SS), which is a software component of the remote handling control system (RHCS) architectural model specified by ITER organisation. Utilisation of the proposed SS necessitates modification of the initial virtual reality (VR) model of RH equipment to a format, which can visually represent the structural deflections. In practise this means adding virtual joints into the model. This will improve the accuracy of the VR visualization and will ensure that the virtual representation of the RH equipment closely aligns with the actual RH equipment. Cassette multifunctional mover (CMM) and second cassette end effector (SCEE) carrying SC were selected to be the initial target system for developing the approach. Demonstrations proved that the approach used can give high levels of accuracy even in complex structures such as the CMM

  17. Simulating and visualizing deflections of a remote handling mechanism

    International Nuclear Information System (INIS)

    Saarinen, Hannu; Hämäläinen, Vesa; Karjalainen, Jaakko; Määttä, Timo; Siuko, Mikko; Esqué, Salvador; Hamilton, David

    2013-01-01

    Highlights: ► An infinitesimal transformation represents elastic deflections. ► Equivalent spring factor is used to combine several deformations. ► Initial VR model accuracy improved from 80 to 5 mm. ► The deflection model is capable of adapting to changes in load at the end-effector. ► The algorithms and approach described are generic and can be adopted for other mechanisms. -- Abstract: Continuing ITER divertor second cassette (SC) remote handling (RH) test campaign has been carried out at divertor test platform (DTP2) in Finland. One of the goals has been to develop and implement efficient algorithms and software tools for simulating and visualizing for the operator the non-instrumented deflections of the RH mechanisms under loading conditions. Based on assumptions of the classical beam theory, the presented solution suggests utilization of an infinitesimal transformation to represent elastic deflections in a mechanical structure. Both structural analysis and measurements of the real structure are utilised during the process. The solution suggests one possible implementation strategy of a software component called structural simulator (SS), which is a software component of the remote handling control system (RHCS) architectural model specified by ITER organisation. Utilisation of the proposed SS necessitates modification of the initial virtual reality (VR) model of RH equipment to a format, which can visually represent the structural deflections. In practise this means adding virtual joints into the model. This will improve the accuracy of the VR visualization and will ensure that the virtual representation of the RH equipment closely aligns with the actual RH equipment. Cassette multifunctional mover (CMM) and second cassette end effector (SCEE) carrying SC were selected to be the initial target system for developing the approach. Demonstrations proved that the approach used can give high levels of accuracy even in complex structures such as the CMM

  18. Ocean carbon uptake and storage

    International Nuclear Information System (INIS)

    Tilbrook, Bronte

    2007-01-01

    Full text: The ocean contains about 95% of the carbon in the atmosphere, ocean and land biosphere system, and is of fundamental importance in regulating atmospheric carbon dioxide concentrations. In the 1990s an international research effort involving Australia was established to determine the uptake and storage of anthropogenic C02 for all major ocean basins. The research showed that about 118 of the 244 + 20 billion tons of the anthropogenic carbon emitted through fossil fuel burning and cement production has been stored in the ocean since preindustrial times, thus helping reduce the rate of increase in atmospheric C02. The research also showed the terrestrial biosphere has been a small net source of C02 (39 ± 28 billion tons carbon) to the atmosphere over the same period. About 60% of the total ocean inventory of the anthropogenic C02 was found in the Southern Hemisphere, with most in the 30 0 S to 50 0 S latitude band. This mid-latitude band is where surface waters are subducted as Mode and Intermediate waters, which is a major pathway controlling ocean C02 uptake. High storage (23% of the total) also occurs in the North Atlantic, associated with deep water formation in that basin. The ocean uptake and storage is expected to increase in the coming decades as atmospheric C02 concentrations rise. However, a number of feedback mechanisms associated with surface warming, changes in circulation, and biological effects are likely to impact on the uptake capacity. The accumulation or storage-of the C02 in the ocean is also the major driver of ocean acidification with potential to disrupt marine ecosystems. This talk will describe the current understanding of the ocean C02 uptake and storage and a new international research strategy to detect how the ocean uptake and storage will evolve on interannual through decadal scales. Understanding the ocean response to increasing atmospheric C02 will be a key element in managing future C02 increases and establishing

  19. ASSIST - a package of Fortran routines for handling input under specified syntax rules and for management of data structures

    International Nuclear Information System (INIS)

    Sinclair, J.E.

    1991-02-01

    The ASSIST package (A Structured Storage and Input Syntax Tool) provides for Fortran programs a means for handling data structures more general than those provided by the Fortran language, and for obtaining input to the program from a file or terminal according to specified syntax rules. The syntax-controlled input can be interactive, with automatic generation of prompts, and dialogue to correct any input errors. The range of syntax rules possible is sufficient to handle lists of numbers and character strings, keywords, commands with optional clauses, and many kinds of variable-format constructions, such as algebraic expressions. ASSIST was developed for use in two large programs for the analysis of safety of radioactive waste disposal facilities, but it should prove useful for a wide variety of applications. (author)

  20. Yield, utilization, storage and ultimate storage of depleted uranium

    International Nuclear Information System (INIS)

    Aumueller, L.; Hermann, J.

    1977-11-01

    More than 80% of the uranium leaving uranium enrichment plants is depleted to a residual content of about 0,25% U 235. Due to the present ineconomical further depletion to the technically possible residual content of 0,1% U 235, the so-called 'tails' are first of all stored. The quantity of stored depleted uranium in the FRG should be about 100.000 t by the year 2000. It represents a strategic reserve for future energy supply regardless of profitableness. The study analysis the conceivable possible uses for the tails quantity considered. These are, besides further depletion whose profitableness is considered, also the use as breeder material in breeder reactors and the use in the non-nuclear field. The main part of the study deals with the various storage possibilities of the depleted uranium in oxidic or fluoride form. A comparison of costs of alternative storage concepts showed a clear advantage for the storage of UF 6 in 48 inch containers already in use. The conceivable accidents in storing are analyzed and measures to reduce the consequences are discussed. Finally, the problems of ultimate storage for the remaining waste after further depletion or use are investigated and the costs arising here are also estimated. (RB) [de

  1. Yeast prions: structure, biology, and prion-handling systems.

    Science.gov (United States)

    Wickner, Reed B; Shewmaker, Frank P; Bateman, David A; Edskes, Herman K; Gorkovskiy, Anton; Dayani, Yaron; Bezsonov, Evgeny E

    2015-03-01

    A prion is an infectious protein horizontally transmitting a disease or trait without a required nucleic acid. Yeast and fungal prions are nonchromosomal genes composed of protein, generally an altered form of a protein that catalyzes the same alteration of the protein. Yeast prions are thus transmitted both vertically (as genes composed of protein) and horizontally (as infectious proteins, or prions). Formation of amyloids (linear ordered β-sheet-rich protein aggregates with β-strands perpendicular to the long axis of the filament) underlies most yeast and fungal prions, and a single prion protein can have any of several distinct self-propagating amyloid forms with different biological properties (prion variants). Here we review the mechanism of faithful templating of protein conformation, the biological roles of these prions, and their interactions with cellular chaperones, the Btn2 and Cur1 aggregate-handling systems, and other cellular factors governing prion generation and propagation. Human amyloidoses include the PrP-based prion conditions and many other, more common amyloid-based diseases, several of which show prion-like features. Yeast prions increasingly are serving as models for the understanding and treatment of many mammalian amyloidoses. Patients with different clinical pictures of the same amyloidosis may be the equivalent of yeasts with different prion variants. Copyright © 2015, American Society for Microbiology. All Rights Reserved.

  2. Strategy development for anticipating and handling a disruptive technology.

    Science.gov (United States)

    Chan, Stephen

    2006-10-01

    The profession of radiology has greatly benefited from the introduction of new imaging technologies throughout its history. Therefore, it would seem reasonable for radiologists to believe that the emergence of a new imaging technology can generally be foreseen with sufficient advance notice to allow the appropriate levels of time, effort, and money to be devoted toward incorporating it into radiology practice. However, in his seminal work, Christiansen characterized a new form of technologic innovation, known as "disruptive technology," whose emergence often heralds the replacement of market leaders in an industry by competitors who are quicker in adopting and deploying the new technology. This article briefly describes the phenomenon of disruptive technology and addresses the challenges that organizations face in dealing with disruptive technology. The article raises 4 questions about the future of radiology: (1) Are health care and radiology vulnerable to disruptive technology? (2) What kinds of change may be in store for the radiology profession? (3) Can the radiology profession prepare itself to recognize and respond to a disruptive innovation among a group of new imaging technologies? and (4) How should a radiology organization decide whether to invest significant resources in a potentially disruptive technology? This article addresses these questions by reviewing key insights from leading "gurus" in the fields of competitive strategy and technology management and applying them to radiology. This illustrates how and why (despite past successes) the radiology profession may still have a blind spot in recognizing and handling disruptive technologies.

  3. Nuclear reactor internals and control rod handling device

    International Nuclear Information System (INIS)

    Betancourt, G.N.; Etzel, W.W.

    1981-01-01

    A method and apparatus for removing, in an essentially continuous operation, the control rods and the upper guide structure from a nuclear reactor vessel during refueling. The apparatus includes a rigid frame which is secured to the upper guide structure after the vessel head is removed. A platform is vertically reciprocable within the frame and is adapted to engage and lift simultaneously all control rod drive shafts to a maximum elevation within the frame. A mechanical interface between the platform and the frame is provided so that continuation of the lifting force on the platform transfers the lift force to the frame whereby the upper guide structure is lifted out of the vessel. Automatically operated stop means are provided to lock the platform and rods in the maximum elevation within the frame in order to prevent accidental dropping of the rods during transfer of the upper guide structure and control rods to a temporary storage area

  4. Energy Conversion and Storage Program

    Energy Technology Data Exchange (ETDEWEB)

    Cairns, E.J.

    1992-03-01

    The Energy Conversion and Storage Program applies chemistry and materials science principles to solve problems in (1) production of new synthetic fuels, (2) development of high-performance rechargeable batteries and fuel cells, (3) development of advanced thermochemical processes for energy conversion, (4) characterization of complex chemical processes, and (5) application of novel materials for energy conversion and transmission. Projects focus on transport-process principles, chemical kinetics, thermodynamics, separation processes, organic and physical chemistry, novel materials, and advanced methods of analysis. Electrochemistry research aims to develop advanced power systems for electric vehicle and stationary energy storage applications. Topics include identification of new electrochemical couples for advanced rechargeable batteries, improvements in battery and fuel-cell materials, and the establishment of engineering principles applicable to electrochemical energy storage and conversion. Chemical Applications research includes topics such as separations, catalysis, fuels, and chemical analyses. Included in this program area are projects to develop improved, energy-efficient methods for processing waste streams from synfuel plants and coal gasifiers. Other research projects seek to identify and characterize the constituents of liquid fuel-system streams and to devise energy-efficient means for their separation. Materials Applications research includes the evaluation of the properties of advanced materials, as well as the development of novel preparation techniques. For example, the use of advanced techniques, such as sputtering and laser ablation, are being used to produce high-temperature superconducting films.

  5. Disposal and handling of nuclear steam generator chemical cleaning wastes

    International Nuclear Information System (INIS)

    Larrick, A.P.; Schneidmiller, D.

    1978-01-01

    A large number of pressurized water nuclear reactor electrical generating plants have experienced a corrosion-related problem with their steam generators known as denting. Denting is a mechanical deformation of the steam generator tubes that occurs at the tube support plates. Corrosion of the tube support plates occurs within the annuli through which the tubes pass and the resulting corrosion oxides, which are larger in volume than the original metal, compress and deform the tubes. In some cases, the induced stresses have been severe enough to cause tube and/or support cracking. The problem was so severe at the Turkey Point and Surrey plants that the tubing is being replaced. For less severe cases, chemical cleaning of the oxides, and other materials which deposit in the annuli from the water, is being considered. A Department of Energy-sponsored program was conducted by Consolidated Edison Co. of New York which identified several suitable cleaning solvents and led to in-plant chemical cleaning pilot demonstrations in the Indian Point Unit 1 steam generators. Current programs to improve the technology are being conducted by the Electric Power Research Institute, and the three PWR NSSS vendors with the assistance of numerous consultants, vendors, and laboratories. These programs are expected to result in more effective, less corrosive solvents. However, after a chemical cleaning is conducted, a large problem still remains- that of disposing of the spent wastes. The paper summarizes some of the methods currently available for handling and disposal of the wastes

  6. Handling of network and database instabilities in CORAL

    International Nuclear Information System (INIS)

    Trentadue, R; Valassi, A; Kalkhof, A

    2012-01-01

    The CORAL software is widely used by the LHC experiments for storing and accessing data using relational database technologies. CORAL provides a C++ abstraction layer that supports data persistency for several back-ends and deployment models, direct client access to Oracle servers being one of the most important use cases. Since 2010, several problems have been reported by the LHC experiments in their use of Oracle through CORAL, involving application errors, hangs or crashes after the network or the database servers became temporarily unavailable. CORAL already provided some level of handling of these instabilities, which are due to external causes and cannot be avoided, but this proved to be insufficient in some cases and to be itself the cause of other problems, such as the hangs and crashes mentioned before, in other cases. As a consequence, a major redesign of the CORAL plugins has been implemented, with the aim of making the software more robust against these database and network glitches. The new implementation ensures that CORAL automatically reconnects to Oracle databases in a transparent way whenever possible and gently terminates the application when this is not possible. Internally, this is done by resetting all relevant parameters of the underlying back-end technology (OCI, the Oracle Call Interface). This presentation reports on the status of this work at the time of the CHEP2012 conference, covering the design and implementation of these new features and the outlook for future developments in this area.

  7. Storage of radioactive wastes

    International Nuclear Information System (INIS)

    1992-07-01

    Even if the best waste minimization measures are undertaken throughout radioisotope production or usage, significant radioactive wastes arise to make management measures essential. For developing countries with low isotope usage and little or no generation of nuclear materials, it may be possible to handle the generated waste by simply practicing decay storage for several half-lives of the radionuclides involved, followed by discharge or disposal without further processing. For those countries with much larger facilities, longer lived isotopes are produced and used. In this situation, storage is used not only for decay storage but also for in-process retention steps and for the key stage of interim storage of conditioned wastes pending final disposal. The report will serve as a technical manual providing reference material and direct step-by-step know-how to staff in radioisotope user establishments and research centres in the developing Member States without nuclear power generation. Considerations are limited to the simpler storage facilities. The restricted quantities and low activity associated with the relevant wastes will generally permit contact-handling and avoid the need for shielding requirements in the storage facilities or equipment used for handling. A small quantity of wastes from some radioisotope production cells and from reactor cooling water treatment may contain sufficient short lived activity from activated corrosion products to require some separate decay storage before contact-handling is suitable. 16 refs, 12 figs, 8 tabs

  8. Epidemiological and biomechanical evaluation of airline baggage handling.

    Science.gov (United States)

    Tafazzol, Alireza; Aref, Samin; Mardani, Majid; Haddad, Omid; Parnianpour, Mohamad

    2016-01-01

    Musculoskeletal disorders (MSDs) are prevalent among airline baggage handlers due to manual materials handling. In this study, the Nordic musculoskeletal questionnaire (NMQ), the revised National Institute for Occupational Safety and Health (NIOSH) lifting equation, and the University of Michigan 3D Static Strength Prediction Program™ (3DSSPP) were used to analyze MSDs among baggage handlers. The NMQ was filled out by 209 baggage handlers and 46 arbitrarily selected baggage handlers were evaluated using the NIOSH method and 3DSSPP. The obtained results showed that the most common MSDs occurred in the lower back region. The next risky regions included knees, neck, and upper back, respectively. The NIOSH results confirmed that the subjects lifted loads heavier than the permitted limit and their lifting postures were inappropriate. The results of the 3DSSPP also indicated that compression forces exceeded the NIOSH limit in these awkward postures. Relying on this study, holding compulsory ergonomic lifting training courses could be proposed for workers and regulations adjusting an upper limit for maximum baggage weight must be also enacted in order to improve occupational health and prevent the prevalence of increasing MSDs.

  9. Architecting Fault Tolerance with Exception Handling: Verification and Validation

    Institute of Scientific and Technical Information of China (English)

    Patrick H. S. Brito; Rogério de Lemos; Cecília M. F. Rubira; Eliane Martins

    2009-01-01

    When building dependable systems by integrating untrusted software components that were not originally designed to interact with each other, it is likely the occurrence of architectural mismatches related to assumptions in their failure behaviour. These mismatches, if not prevented during system design, have to be tolerated during runtime. This paper presents an architectural abstraction based on exception handling for structuring fault-tolerant software systems.This abstraction comprises several components and connectors that promote an existing untrusted software element into an idealised fault-tolerant architectural element. Moreover, it is considered in the context of a rigorous software development approach based on formal methods for representing the structure and behaviour of the software architecture. The proposed approach relies on a formal specification and verification for analysing exception propagation, and verifying important dependability properties, such as deadlock freedom, and scenarios of architectural reconfiguration. The formal models are automatically generated using model transformation from UML diagrams: component diagram representing the system structure, and sequence diagrams representing the system behaviour. Finally, the formal models are also used for generating unit and integration test cases that are used for assessing the correctness of the source code. The feasibility of the proposed architectural approach was evaluated on an embedded critical case study.

  10. Electrochemistry and Storage

    Science.gov (United States)

    Thaller, L. H.

    1984-01-01

    The term electrochemistry implies the use of devices that convert chemical energy into electrical energy and sometimes vice versa. These devices are usually composed of some number of individual cells that are connected together to form a battery. In the cases where these devices cannot be electrically recharged they are usually referred to as primary batteries, whereas if these batteries can be charged and recharged repeatedly, they are called secondary batteries. The past and present uses of primary and secondary batteries in aerospace applications are discussed.

  11. Air-handling energy efficiency and design practices

    Energy Technology Data Exchange (ETDEWEB)

    Nilsson, Lars J.

    1993-12-31

    With good design practices and life-cycle cost optimization, specific fan power for individual fans will be between 0.5 and 1kW/m{sup 3}/s. Data from nearly 1000 audited fans in Sweden show that the average measured SFPI weighted by drawn motor power is 1.5 kW/m{sup 3}/s and the situation appears to be similar in other countries. Contract forms used by Swedish builders, and consultants` design practices are analyzed here to search for an explanation to the low performance of installed systems. Identified as two major barriers to efficient system design are the lack of performance specifications when procuring systems and the incentive structure in the building sector. As a consequence, duct design methods, rules of thumb, and vendor recommendations are not leading to system optimization. The broad minima in life cycle costs over a range of air-handling unit sizes show that potential economic welfare losses from efficiency standards are likely to be smaller than the losses that result from today`s design practices. 73 refs, 4 figs, 3 tabs

  12. Air-handling energy efficiency and design practices

    Energy Technology Data Exchange (ETDEWEB)

    Nilsson, Lars J

    1994-12-31

    With good design practices and life-cycle cost optimization, specific fan power for individual fans will be between 0.5 and 1kW/m{sup 3}/s. Data from nearly 1000 audited fans in Sweden show that the average measured SFPI weighted by drawn motor power is 1.5 kW/m{sup 3}/s and the situation appears to be similar in other countries. Contract forms used by Swedish builders, and consultants` design practices are analyzed here to search for an explanation to the low performance of installed systems. Identified as two major barriers to efficient system design are the lack of performance specifications when procuring systems and the incentive structure in the building sector. As a consequence, duct design methods, rules of thumb, and vendor recommendations are not leading to system optimization. The broad minima in life cycle costs over a range of air-handling unit sizes show that potential economic welfare losses from efficiency standards are likely to be smaller than the losses that result from today`s design practices. 73 refs, 4 figs, 3 tabs

  13. Hydrogen storage and generation system

    Science.gov (United States)

    Dentinger, Paul M.; Crowell, Jeffrey A. W.

    2010-08-24

    A system for storing and generating hydrogen generally and, in particular, a system for storing and generating hydrogen for use in an H.sub.2/O.sub.2 fuel cell. The hydrogen storage system uses the beta particles from a beta particle emitting material to degrade an organic polymer material to release substantially pure hydrogen. In a preferred embodiment of the invention, beta particles from .sup.63Ni are used to release hydrogen from linear polyethylene.

  14. Carbon dioxide capture and storage

    International Nuclear Information System (INIS)

    Durand, B.

    2011-01-01

    The author first highlights the reasons why storing carbon dioxide in geological formations could be a solution in the struggle against global warming and climate change. Thus, he comments various evolutions and prospective data about carbon emissions or fossil energy consumption as well as various studies performed by international bodies and agencies which show the interest of carbon dioxide storage. He comments the evolution of CO 2 contributions of different industrial sectors and activities, notably in France. He presents the different storage modes and methods which concern different geological formations (saline aquifers, abandoned oil or gas fields, not exploitable coal seams) and different processes (sorption, carbonation). He discusses the risks associated with these storages, the storable quantities, evokes some existing installations in different countries. He comments different ways to capture carbon dioxide (in post-combustion, through oxy-combustion, by pre-combustion) and briefly evokes some existing installations. He evokes the issue of transport, and discusses efficiency and cost aspects, and finally has few words on legal aspects and social acceptability

  15. Forests and carbon storage

    Science.gov (United States)

    Michael G. Ryan

    2008-01-01

    Forests store much carbon and their growth can be a carbon sink if disturbance or harvesting has killed or removed trees or if trees that can now regrow are planted where they did not historically occur. Forests and long-lived wood products currently offset 310 million metric tons of U.S. fossil fuel emissions of carbon--20 percent of the total (Pacala et al. 2007)....

  16. Energy storage

    International Nuclear Information System (INIS)

    Anon.

    1992-01-01

    This chapter discusses the role that energy storage may have on the energy future of the US. The topics discussed in the chapter include historical aspects of energy storage, thermal energy storage including sensible heat storage, latent heat storage, thermochemical heat storage, and seasonal heat storage, electricity storage including batteries, pumped hydroelectric storage, compressed air energy storage, and superconducting magnetic energy storage, and production and combustion of hydrogen as an energy storage option

  17. Software for handling and replacement of missing data

    Directory of Open Access Journals (Sweden)

    Mayer, Benjamin

    2009-10-01

    Full Text Available In medical research missing values often arise in the course of a data analysis. This fact constitutes a problem for different reasons, so e.g. standard methods for analyzing data lead to biased estimates and a loss of statistical power due to missing values, since those methods require complete data sets and therefore omit incomplete cases for the analyses. Furthermore missing values imply a certain loss of information for what reason the validity of results of a study with missing values has to be rated less than in a case where all data had been available. For years there are methods for replacement of missing values (Rubin, Schafer to tackle these problems and solve them in parts. Hence in this article we want to present the existing software to handle and replace missing values on the one hand and give an outline about the available options to get information on the other hand. The methodological aspects of the replacement strategies are delineated just briefly in this article.

  18. A review on bicycle and motorcycle rider control with a perspective on handling qualities

    Science.gov (United States)

    Kooijman, J. D. G.; Schwab, A. L.

    2013-11-01

    This paper is a review study on handling and control of bicycles and motorcycles, the so-called single-track vehicles. The first part gives a brief overview on the modelling of the dynamics of single-track vehicles and the experimental validation. The second part focusses on a review of modelling and measuring human rider control. The third part deals with the concepts of handling and manoeuvrability and their experimental validation. Parallels are drawn with the literature on aircraft handling and pilot models. The paper concludes with the open ends and promising directions for future work in the field of handling and control of single-track vehicles.

  19. Conceptual design report for a Fusion Engineering Device sector-handling machine and movable manipulator system

    International Nuclear Information System (INIS)

    Watts, K.D.; Masson, L.S.; McPherson, R.S.

    1982-10-01

    Design requirements, trade studies, design descriptions, conceptual designs, and cost estimates have been completed for the Fusion Engineering Device sector handling machine, movable manipulator system, subcomponent handling machine, and limiter blade handling machine. This information will be used by the Fusion Engineering Design Center to begin to determine the cost and magnitude of the effort required to perform remote maintenance on the Fusion Engineering Device. The designs presented are by no means optimum, and the costs estimates are rough-order-of-magnitude

  20. Automated Storage Retrieval System (ASRS) Role Towards Achievement of Safety Objective and Safety Culture in Radioactive Storage Facilities

    International Nuclear Information System (INIS)

    Mohamad Hakiman Mohd Yusoff; Nurul Wahida Ahmad Khairuddin; Nik Marzukee Nik Ibrahim; Mat Bakar Mahusin; Muhammad, Z.A.; Nur Azna Mahmud; Norfazlina Zainal Abidin

    2012-01-01

    Waste Technology Development Centre (WasTeC) has been awarded with quality management system ISO 9001:2000 in June 2004 or now known as ISO 9001:2008. The scope of the unit's ISO certification is radioactive waste management and storage of radioactive material. To meet the objectives and requirements ISO 9001:2008, WasTeC has started a project known as Automated Storage and Retrieval System (ASRS). ASRS is a computing controlled method for automatically depositing and retrieving waste from defined locations. The system is used to replace the existing process of storage and retrieval of radioactive waste at storage facility at block 33.The main objective of this project is to reduced the radiation exposure to the worker and potential forklift accident occur during storage and retrieval of the radioactive waste. By using the ASRS system, WasTeC/ Nuclear Malaysia can provide a safe storage of radioactive waste and the use of this system can eliminate the repeat handling and can improve productivity. (author)

  1. Technologies and logistics for handling, transport and distribution of animal manures

    Science.gov (United States)

    Organizing and managing the whole manure handling chain from the animal house through transport to the point of use (e.g. in the field) is a challenging task requiring consideration of manure type and operating conditions. Solid and liquid manure must be handled differently, using very different tec...

  2. WISE TECHNOLOGY FOR HANDLING BIG DATA FEDERATIONS

    NARCIS (Netherlands)

    Valentijn, E; Begeman, Kornelis; Belikov, Andrey; Boxhoorn, Danny; Verdoes Kleijn, Gijs; McFarland, John; Vriend, Willem-Jan; Williams, Owen; Soille, P.; Marchetti, P.G.

    2014-01-01

    The effective use of Big Data in current and future scientific missions requires intelligent data handling systems which are able to interface the user to complicated distributed data collections. We review the WISE Concept of Scientific Information Systems and the WISE solutions for the storage and

  3. Environmental stress responses and experimental handling artifacts of a model organism, the copepod Acartia tonsa (Dana)

    DEFF Research Database (Denmark)

    Nilsson, Birgitte; Jepsen, Per Meyer; Bucklin, Ann

    2018-01-01

    Handling animals during experiments potentially affects the differential expression of genes chosen as biomarkers of sub-lethal stress. RNA sequencing was used to examine whole-transcriptome responses caused by laboratory handling of the calanoid copepod, Acartia tonsa. Salinity shock (S=35 to S=...... studies can lead to inaccurate conclusions. The present study provides a baseline for studying handling stress in future studies using this model organism and others....... for these genes between 15 min and 24 h following exposure. Since handling stress clearly affects transcriptional patterns, it is important to consider handling when designing experiments, by either including additional controls or avoiding focus on impacted genes. Not considering handling in gene expression...

  4. Revision and partial analysis of the information of Forestall Reserves, Districts of Integrated Handling of renewable natural resources and special handling areas, declared in Colombia

    International Nuclear Information System (INIS)

    Cortes Martinez, Ingrid Vanesa

    2002-01-01

    A revision and a partial analysis is made of the information of Forestall Reserves, Districts of Integrated Handling of renewable natural resources and Areas of Special Handling in Colombia whose main purpose is the conservation and the sustainable handling of the natural resources for the maintenance of the goods and services, derived of the forest, however, these areas are under constant intervention that which has caused the subtraction of considerable regions of the forestall reserves. With this revision and analysis it is looked for to support to the General Address of Ecosystems of the Environment Ministry, with the purpose of impelling the process of consolidation of an upgraded of information system that it guides the classification, handling and administration of these Areas

  5. Survey of technology for decommissioning of nuclear fuel cycle facilities. 8. Remote handling and cutting techniques

    Energy Technology Data Exchange (ETDEWEB)

    Ogawa, Ryuichiro; Ishijima, Noboru [Japan Nuclear Cycle Development Inst., Oarai, Ibaraki (Japan). Oarai Engineering Center

    1999-03-01

    In nuclear fuel cycle facility decommissioning and refurbishment, the remote handling techniques such as dismantling, waste handling and decontamination are needed to reduce personnel radiation exposure. The survey research for the status of R and D activities on remote handling tools suitable for nuclear facilities in the world and domestic existing commercial cutting tools applicable to decommissioning of the facilities was conducted. In addition, the drive mechanism, sensing element and control system applicable to the remote handling devices were also surveyed. This report presents brief surveyed summaries. (H. Itami)

  6. Guidelines for safe handling, use and disposal of nanoparticles

    International Nuclear Information System (INIS)

    Amoabediny, G H; Rashedi, H; Naderi, A; Malakootikhah, J; Koohi, M K; Mortazavi, S A; Naderi, M

    2009-01-01

    situations, performing administrative means of control constitute other ways of limiaiting the occupational exposure risks. Accordingly, to minimize the risks from know and unknown health, safety and invironment hazards in research and occupational setting of the country, guideline for safe handling, use and disposal of manopractical has provided.

  7. A multi-component patient-handling intervention improves attitudes and behaviors for safe patient handling and reduces aggression experienced by nursing staff

    DEFF Research Database (Denmark)

    Risør, Bettina Wulff; Casper, Sven Dalgas; Andersen, Lars L.

    2017-01-01

    This study evaluated an intervention for patient-handling equipment aimed to improve nursing staffs' use of patient handling equipment and improve their general health, reduce musculoskeletal problems, aggressive episodes, days of absence and work-related accidents. As a controlled before......-after study, questionnaire data were collected at baseline and 12-month follow-up among nursing staff at intervention and control wards at two hospitals. At 12-month follow-up, the intervention group had more positive attitudes towards patient-handling equipment and increased use of specific patient......-handling equipment. In addition, a lower proportion of nursing staff in the intervention group had experienced physically aggressive episodes. No significant change was observed in general health status, musculoskeletal problems, days of absence or work-related accidents. The intervention resulted in more positive...

  8. Constraint Handling Rules with Binders, Patterns and Generic Quantification

    NARCIS (Netherlands)

    Serrano, Alejandro; Hage, J.

    2017-01-01

    Constraint Handling Rules provide descriptions for constraint solvers. However, they fall short when those constraints specify some binding structure, like higher-rank types in a constraint-based type inference algorithm. In this paper, the term syntax of constraints is replaced by λ-tree syntax, in

  9. Hot gas handling device and motorized vehicle comprising the device

    NARCIS (Netherlands)

    Klein Geltink, J.; Beukers, A.; Van Tooren, M.J.L.; Koussios, S.

    2012-01-01

    The invention relates to a device for handling hot exhaust gasses discharged from an internal combustion engine. The device comprises a housing (2), enclosing a space (3) for transporting the exhaust gasses. The housing (2) is provided with an entrance - opening (4) for the exhaust gasses discharged

  10. The JET experience with remote handling equipment and future prospects

    International Nuclear Information System (INIS)

    Raimondi, T.

    1989-01-01

    The commissioning and testing of numerous pieces of equipment are now in progress at JET. Two microprocessor controlled force feedback MASCOT IV servomanipulators have shown comparable characteristics to those of the previous analogue types. Teach and repeat software permits precision welding and repetitive operations in a robotics mode. Other computer aids are planned to improve the man-machine interface: Tool-weight compensation, constraints along preferred lines or planes, automatic tracking of the TV cameras. The in-vessel transporter, provided with 5 vertical hinges, a pan-tilt-roll extension and special purpose end effectors, has been used under direct visual control to install 32 toroidal limiters and 8 radio frequency antennae. Test of remote installation in teach and repeat were done, using the JET spare octant as a mock-up, achieving repeatability of better than 5 mm. A considerable number of special remote handling tools were used inside the vessel hands-on to align, cut and weld diagnostics ports and water pipes. The cutting and welding trolleys were used hands-on, on a total of 250 m of lip joints. The ex-vessel transporter, a crane-mounted vertical telescope, 17 m high with a 10 m horizontal arm, is being manufactured. It will be equipped with manipulator and TV systems and controlled via joystick or keyboard or in teach and repeat. Image processing for collision avoidance is being studied. A low level transporter was used for turbo-pump replacement and is now being equipped with remote control. Mock-up work has started on the replacement of the Neutral Injector sources. Bench tests on flanges, heating jackets and connectors are being done to identify refinements needed. The in-vessel inspection system has been used at high temperature in vacuum. (orig.)

  11. The Jet experience with remote handling equipment and future prospects

    International Nuclear Information System (INIS)

    Raimondi, T.

    1989-01-01

    The commissioning and testing of numerous pieces of equipment are now in progress at JET. Two microprocessor controlled force feedback MASCOT IV servomanipulators have shown comparable characteristics to those of the previous analogue types. Teach and repeat software permits precision welding and repetitive operations in a robotics mode. Other computer aids are planned to improve the man-machine interface: tool-weight compensation, constraints along preferred lines or planes, automatic tracking of the TV cameras. The in-vessel transporter, provided with 5 vertical hinges, a pan-tilt-roll extension and special purpose end effectors, has been used under direct visual control to install 32 toroidal limiters and 8 radio frequency antennae. Tests of remote installation in teach and repeat were done, using the JET spare octant as a mock-up, achieving repeatability of better than 5mm. A considerable number of special remote handling tools were used inside the vessel hands-on to align, cut and weld diagnostics ports and water pipes. The cutting and welding trolleys were used hands-on, on a total of 250m of lip joints. The ex-vessel transporter, a crane-mounted vertical telescope, 17m high with a 10m horizontal arm, is being manufactured. It will be equipped with manipulator and TV systems and controlled via joystick or keyboard or in teach and repeat. Image processing for collision avoidance is being studied. A low level transporter was used for turbo-pump replacement and is now being equipped with remote control. Mock-up work has started on the replacement of the Neutral Injector sources. Bench tests on flanges, heating jackets and connectors are being done to identify refinements needed. The in-vessel inspection system has been used at high temperature in vacuum

  12. The JET experience with remote handling equipment and future prospects

    International Nuclear Information System (INIS)

    Raimondi, T.

    1989-01-01

    The commissioning and testing of numerous pieces of equipment are now in progress at JET. Two microprocessor controlled force feedback MASCOT IV servomanipulators have shown comparable characteristics to those of the previous analogue types. Teach and repeat software permits precision welding and repetitive operations in a robotics mode. Other computer aids are planned to improve the man-machine interface: tool-weigth compensation, constraints along preferred lines or planes, automatic tracking of the TV cameras. The in-vessel transporter, provided with 5 vertical hinges, a pan-tilt-roll extension and special purpose end effectors, has been used under direct visual control to install 32 toroidal limiters and 8 radio frequency antennae. Tests of remote installation in teach and repeat were done, using the JET spare octant as a mock-up, achieving repeatability of better than 5 mm. A considerable number of special remote handling tools were used inside the vessel hands-on to align, cut and weld diagnostics ports and water pipes. The cutting and welding trolleys were used hands-on, on a total of 250 m of lip joints. The ex-vessel transporter, a crane-mounted vertical telescope, 17 m high with a 10 m horizontal arm, is being manufactured. it will be equipped with manipulator and TV systems and controlled via joystick or keyboard or in teach and repeat. image processing for collision avoidance is being studied. A low level transporter was used for turbo-pump replacement and is now being equipped with remote control. Mock-up work has started on the replacement of the Neutral Injector sources. Bench tests on flanges, heating jackets and connectors are being done to identify refinements needed. The in-vessel inspection system has been used at high temperature in vacuum. (author). 14 refs.; 12 figs

  13. Cardiac tissue slices: preparation, handling, and successful optical mapping.

    Science.gov (United States)

    Wang, Ken; Lee, Peter; Mirams, Gary R; Sarathchandra, Padmini; Borg, Thomas K; Gavaghan, David J; Kohl, Peter; Bollensdorff, Christian

    2015-05-01

    Cardiac tissue slices are becoming increasingly popular as a model system for cardiac electrophysiology and pharmacology research and development. Here, we describe in detail the preparation, handling, and optical mapping of transmembrane potential and intracellular free calcium concentration transients (CaT) in ventricular tissue slices from guinea pigs and rabbits. Slices cut in the epicardium-tangential plane contained well-aligned in-slice myocardial cell strands ("fibers") in subepicardial and midmyocardial sections. Cut with a high-precision slow-advancing microtome at a thickness of 350 to 400 μm, tissue slices preserved essential action potential (AP) properties of the precutting Langendorff-perfused heart. We identified the need for a postcutting recovery period of 36 min (guinea pig) and 63 min (rabbit) to reach 97.5% of final steady-state values for AP duration (APD) (identified by exponential fitting). There was no significant difference between the postcutting recovery dynamics in slices obtained using 2,3-butanedione 2-monoxime or blebistatin as electromechanical uncouplers during the cutting process. A rapid increase in APD, seen after cutting, was caused by exposure to ice-cold solution during the slicing procedure, not by tissue injury, differences in uncouplers, or pH-buffers (bicarbonate; HEPES). To characterize intrinsic patterns of CaT, AP, and conduction, a combination of multipoint and field stimulation should be used to avoid misinterpretation based on source-sink effects. In summary, we describe in detail the preparation, mapping, and data analysis approaches for reproducible cardiac tissue slice-based investigations into AP and CaT dynamics. Copyright © 2015 the American Physiological Society.

  14. Plutonium safe handling

    International Nuclear Information System (INIS)

    Tvehlov, Yu.

    2000-01-01

    The abstract, prepared on the basis of materials of the IAEA new leadership on the plutonium safe handling and its storage (the publication no. 9 in the Safety Reports Series), aimed at presenting internationally acknowledged criteria on the radiation danger evaluation and summarizing the experience in the safe management of great quantities of plutonium, accumulated in the nuclear states, is presented. The data on the weapon-class and civil plutonium, the degree of its danger, the measures for provision of its safety, including the data on accident radiation consequences with the fission number 10 18 , are presented. The recommendations, making it possible to eliminate the super- criticality danger, as well as ignition and explosion, to maintain the tightness of the facility, aimed at excluding the radioactive contamination and the possibility of internal irradiation, to provide for the plutonium security, physical protection and to reduce irradiation are given [ru

  15. Influence of Freezing and Storage Procedure on Human Urine Samples in NMR-Based Metabolomics

    OpenAIRE

    Rist, Manuela; Muhle-Goll, Claudia; Görling, Benjamin; Bub, Achim; Heissler, Stefan; Watzl, Bernhard; Luy, Burkhard

    2013-01-01

    It is consensus in the metabolomics community that standardized protocols should be followed for sample handling, storage and analysis, as it is of utmost importance to maintain constant measurement conditions to identify subtle biological differences. The aim of this work, therefore, was to systematically investigate the influence of freezing procedures and storage temperatures and their effect on NMR spectra as a potentially disturbing aspect for NMR-based metabolomics studies. Urine sample...

  16. INFORMATION SECURITY AND SECURE SEARCH OVER ENCRYPTED DATA IN CLOUD STORAGE SERVICES

    OpenAIRE

    Mr. A Mustagees Shaikh *; Prof. Nitin B. Raut

    2016-01-01

    Cloud computing is most widely used as the next generation architecture of IT enterprises, that provide convenient remote access to data storage and application services. This cloud storage can potentially bring great economical savings for data owners and users, but due to wide concerns of data owners that their private data may be exposed or handled by cloud providers. Hence end-to-end encryption techniques and fuzzy fingerprint technique have been used as solutions for secure cloud data st...

  17. Calculations on safe storage and transportation of radioactive materials

    Energy Technology Data Exchange (ETDEWEB)

    Hathout, A M; El-Messiry, A M; Amin, E [National Center for Nuclear Safety and Radiation Control and AEA, Cairo (Egypt)

    1997-12-31

    In this work the safe storage and transportation of fresh fuel as a radioactive material studied. Egypt planned ET RR 2 reactor which is of relatively high power and would require adequate handling and transportation. Therefore, the present work is initiated to develop a procedure for safe handling and transportation of radioactive materials. The possibility of reducing the magnitude of radiation transmitted on the exterior of the packages is investigated. Neutron absorbers are used to decrease the neutron flux. Criticality calculations are carried out to ensure the achievement of subcriticality so that the inherent safety can be verified. The discrete ordinate transport code ANISN was used. The results show good agreement with other techniques. 2 figs., 2 tabs.

  18. Promoting positive states: the effect of early human handling on play and exploratory behaviour in pigs.

    Science.gov (United States)

    Zupan, M; Rehn, T; de Oliveira, D; Keeling, L J

    2016-01-01

    It is known that tactile stimulation (TS) during ontogeny modifies brain plasticity and enhances the motor and cognitive skills. Our hypothesis was that early handling including TS would increase play and exploratory behaviour in commercial pigs under standardized test conditions. Piglets from 13 litters were subjected to three handling treatments from 5 to 35 days of age: all the piglets were handled (H), none of the piglets were handled (NH) or half of the piglets in the litter were handled (50/50). At 42 days of age, the pigs' behaviour was observed in pairs in a novel pen with a 'toy' (tug rope). The main results were that more locomotor play was performed by pigs from litters where all or half of them had been handled, whereas social exploratory behaviour was more pronounced in pigs from litters where half of them had been handled. Although behaviour was affected by the interaction of treatment with sex or with weight category, we propose that the handling procedure does seem to have acted to increase locomotor skills and that handling half of the piglets in the litter may have triggered a series of socio-emotional interactions that were beneficial for the whole group.

  19. Thermal energy storage devices, systems, and thermal energy storage device monitoring methods

    Science.gov (United States)

    Tugurlan, Maria; Tuffner, Francis K; Chassin, David P.

    2016-09-13

    Thermal energy storage devices, systems, and thermal energy storage device monitoring methods are described. According to one aspect, a thermal energy storage device includes a reservoir configured to hold a thermal energy storage medium, a temperature control system configured to adjust a temperature of the thermal energy storage medium, and a state observation system configured to provide information regarding an energy state of the thermal energy storage device at a plurality of different moments in time.

  20. Concept study for interim storage of research reactor fuel elements in transport and storage casks. Transport and storage licensing procedure for the CASTOR MTR 2 cask. Final report

    International Nuclear Information System (INIS)

    Weiss, M.

    2001-01-01

    As a result of the project, a concept was to be developed for managing spent fuel elements from research reactors on the basis of the interim storage technology existing in Germany, in order to make the transition to direct disposal possible in the long term. This final report describes the studies for the spent fuel management concept as well as the development of a transport and storage cask for spent fuel elements from research reactors. The concept analyses were based on data of the fuel to be disposed of, as well as the handling conditions for casks at the German research reactors. Due to the quite different conditions for handling of casks at the individual reactors, it was necessary to examine different cask concepts as well as special solutions for loading the casks outside of the spent fuel pools. As a result of these analyses, a concept was elaborated on the basis of a newly developed transport and storage cask as well as a mobile fuel transfer system for the reactor stations, at which a direct loading of the cask is not possible, as the optimal variant. The cask necessary for this concept with the designation CASTOR trademark MTR 2 follows in ist design the tried and tested principles of the CASTOR trademark casks for transport and interim storage of spent LWR fuel. With the CASTOR trademark MTR 2, it is possible to transport and to place into long term interim storage various fuel element types, which have been and are currently used in German research reactors. The technical development of the cask has been completed, the documents for the transport license as type B(U)F package design and for obtaining the storage license at the interim storage facility of Ahaus have been prepared, submitted to the licensing authorities and to a large degree already evaluated positively. The transport license of the CASTOR trademark MTR 2 has been issued for the shipment of VKTA-contents and FRM II compact fuel elements. (orig.)

  1. Designing and Testing Composite Energy Storage Systems for Regulating the Outputs of Linear Wave Energy Converters

    Directory of Open Access Journals (Sweden)

    Zanxiang Nie

    2017-01-01

    Full Text Available Linear wave energy converters generate intrinsically intermittent power with variable frequency and amplitude. A composite energy storage system consisting of batteries and super capacitors has been developed and controlled by buck-boost converters. The purpose of the composite energy storage system is to handle the fluctuations and intermittent characteristics of the renewable source, and hence provide a steady output power. Linear wave energy converters working in conjunction with a system composed of various energy storage devices, is considered as a microsystem, which can function in a stand-alone or a grid connected mode. Simulation results have shown that by applying a boost H-bridge and a composite energy storage system more power could be extracted from linear wave energy converters. Simulation results have shown that the super capacitors charge and discharge often to handle the frequent power fluctuations, and the batteries charge and discharge slowly for handling the intermittent power of wave energy converters. Hardware systems have been constructed to control the linear wave energy converter and the composite energy storage system. The performance of the composite energy storage system has been verified in experiments by using electronics-based wave energy emulators.

  2. Furan Levels and Sensory Profiles of Commercial Coffee Products Under Various Handling Conditions.

    Science.gov (United States)

    Han, Jeesoo; Kim, Mina K; Lee, Kwang-Geun

    2017-11-01

    In this study, the levels of furan in coffee with consideration towards common coffee consumption was investigated. The concentration of furan in brewed coffee was the highest among the coffee types studied, with an average of 110.73 ng/mL, followed by canned coffee (28.08 ng/mL) and instant coffee (8.55 ng/mL). In instant and brewed coffee, the furan levels decreased by up to an average of 20% and 22%, after 5 min of pouring in a cup without a lid. The degree of reduction was greater when coffee was served without a lid, regardless of coffee type (P coffee, the level of furan decreased by an average of 14% after storage at 60 °C without a lid, and the degree of furan reduction in coffee was greater in coffee served warm (60 °C) than in coffee served cold (4 °C). A time-dependent intensities of sensory attributes in commercial coffees with various handling condition were different (P coffee kept in a cup with lid closed, holds the aroma of coffee longer than coffee in a cup without a lid. Consumption of coffee has increased rapidly in Korea over the past few years. Consequently, the probability of exposure to chemical hazards presence in coffee products increases. Furan is a heterocyclic compound, formed mainly from Maillard reaction, therefore present in coffee products. This work demonstrated the strategy to reduce the levels of furan in coffee products at individual consumer level, by investigating the levels of furan served in common handling scenarios of coffee in Korea: canned coffee, instant coffee, and brewed coffee. Findings of this study can practically guide industry, government, and consumer agencies to reduce the risk exposure to furan during coffee consumptions. © 2017 Institute of Food Technologists®.

  3. Groundwater and Terrestrial Water Storage

    Science.gov (United States)

    Rodell, Matthew; Chambers, Don P.; Famiglietti, James S.

    2011-01-01

    Most people think of groundwater as a resource, but it is also a useful indicator of climate variability and human impacts on the environment. Groundwater storage varies slowly relative to other non-frozen components of the water cycle, encapsulating long period variations and trends in surface meteorology. On seasonal to interannual timescales, groundwater is as dynamic as soil moisture, and it has been shown that groundwater storage changes have contributed to sea level variations. Groundwater monitoring well measurements are too sporadic and poorly assembled outside of the United States and a few other nations to permit direct global assessment of groundwater variability. However, observational estimates of terrestrial water storage (TWS) variations from the GRACE satellites largely represent groundwater storage variations on an interannual basis, save for high latitude/altitude (dominated by snow and ice) and wet tropical (surface water) regions. A figure maps changes in mean annual TWS from 2009 to 2010, based on GRACE, reflecting hydroclimatic conditions in 2010. Severe droughts impacted Russia and the Amazon, and drier than normal weather also affected the Indochinese peninsula, parts of central and southern Africa, and western Australia. Groundwater depletion continued in northern India, while heavy rains in California helped to replenish aquifers that have been depleted by drought and withdrawals for irrigation, though they are still below normal levels. Droughts in northern Argentina and western China similarly abated. Wet weather raised aquifer levels broadly across western Europe. Rains in eastern Australia caused flooding to the north and helped to mitigate a decade long drought in the south. Significant reductions in TWS seen in the coast of Alaska and the Patagonian Andes represent ongoing glacier melt, not groundwater depletion. Figures plot time series of zonal mean and global GRACE derived non-seasonal TWS anomalies (deviation from the mean of

  4. Groundwater and Terrestrial Water Storage

    Science.gov (United States)

    Rodell, Matthew; Chambers, Don P.; Famiglietti, James S.

    2014-01-01

    Terrestrial water storage (TWS) comprises groundwater, soil moisture, surface water, snow,and ice. Groundwater typically varies more slowly than the other TWS components because itis not in direct contact with the atmosphere, but often it has a larger range of variability onmultiannual timescales (Rodell and Famiglietti, 2001; Alley et al., 2002). In situ groundwaterdata are only archived and made available by a few countries. However, monthly TWSvariations observed by the Gravity Recovery and Climate Experiment (GRACE; Tapley et al.,2004) satellite mission, which launched in 2002, are a reasonable proxy for unconfinedgroundwater at climatic scales.

  5. Construction and commissioning of workrooms for handling of unsealed radioactive materials

    International Nuclear Information System (INIS)

    Weinhold, G.; Jost, E.; Koenig, W.

    1976-03-01

    The requirements prescribed for planning, design and construction of type II and III workrooms for handling of unsealed sources are outlined. The 'Guide Concerning Construction and Equipment of Rooms for Handling of Radioactive Materials' is explained and supplemented in part. Furthermore, problems of radiation protection organization and measuring techniques are discussed. (author)

  6. Properties of raw meat and meat curry from spent goat in relation with post-mortem handling conditions.

    Science.gov (United States)

    Narayan, Raj; Mendiratta, S K; Mane, B G

    2013-04-01

    The properties of raw meat and meat curry from spent goat meat in relation with post-mortem handling conditions were evaluated. The conditions evaluated were: cooking of meat within 1-2 h post-slaughter (condition 1); deboning meat storage at 25 ± 2 °C for 5-6 h and cooking (condition 2); post-slaughter storage of carcass at room temperature for 5-6 h, then deboning followed by storage of meat at refrigeration temperature for 5-6 h and cooking (condition 3); deboning and storage of meat at 25 ± 2 °C for 10-12 h and cooking (condition 4). Significant difference was observed in pH values in condition 1 (p meat as compared to the conditions 2, 3 and 4. However, the moisture content of cooked meat was significantly higher (p meat chunks, that is, the mean value was significantly higher (p < 0.01) for condition 2 and significantly lower for condition 1. Sensory scores were significantly higher in condition 1 and significantly lower in condition 2. However, sensory scores for condition 4 were almost similar to the condition 1.

  7. Safety in transport and storage of radioactive materials

    International Nuclear Information System (INIS)

    Mezrahi, A.; Xavier, A.M.

    1987-01-01

    The increasing utilization of radioisotopes in Industrial, Medical and Research Facilities as well as the processing of Nuclear Materials involve transport activities in a routine basis. The present work has the following main objectives: I) the identification of the safety aspects related to handling, transport and storage of radioactive materials; II) the orientation of the personnel responsible for the radiological safety of Radioactive Installations viewing the elaboration and implementation of procedures to minimize accidents; III) the report of case-examples of accidents that have occured in Brazil due to non-compliance with Transport Regulations. (author) [pt

  8. Exploiting database technology for object based event storage and retrieval

    International Nuclear Information System (INIS)

    Rawat, Anil; Rajan, Alpana; Tomar, Shailendra Singh; Bansal, Anurag

    2005-01-01

    This paper discusses the storage and retrieval of experimental data on relational databases. Physics experiments carried out using reactors and particle accelerators, generate huge amount of data. Also, most of the data analysis and simulation programs are developed using object oriented programming concepts. Hence, one of the most important design features of an experiment related software framework is the way object persistency is handled. We intend to discuss these issues in the light of the module developed by us for storing C++ objects in relational databases like Oracle. This module was developed under the POOL persistency framework being developed for LHC, CERN grid. (author)

  9. Guidelines for safe handling, use and disposal of nanoparticles

    Energy Technology Data Exchange (ETDEWEB)

    Amoabediny, G H; Rashedi, H [Department of Biotechnology, Faculty of Chemical Engineering, University of Tehran (Iran, Islamic Republic of)], E-mail: amoabedini@ut.ac.ir; Naderi, A [Department of Occupational Health, Faculty of Medical Science, University of Tarbiat Modares (Iran, Islamic Republic of); Malakootikhah, J [Nanotechnology Standardisation Committee, Iran Nanotechnology Initiative, Tehran (Iran, Islamic Republic of); Koohi, M K [Faculty of veterinary medicine, University of Tehran (Iran, Islamic Republic of); Mortazavi, S A [Department of Nanosafety, Research Centre for New Technology in life science Engineering, University of Tehran (Iran, Islamic Republic of); Naderi, M [University of Amirkabir (Iran, Islamic Republic of)

    2009-05-01

    situations, performing administrative means of control constitute other ways of limiaiting the occupational exposure risks. Accordingly, to minimize the risks from know and unknown health, safety and invironment hazards in research and occupational setting of the country, guideline for safe handling, use and disposal of manopractical has provided.

  10. 7 CFR 27.20 - Drawing and handling of samples of cotton; inspection of bales.

    Science.gov (United States)

    2010-01-01

    ... 7 Agriculture 2 2010-01-01 2010-01-01 false Drawing and handling of samples of cotton; inspection... Regulations Inspection and Samples § 27.20 Drawing and handling of samples of cotton; inspection of bales. One sample shall be drawn from the top side of each bale and one from the bottom side. Each such sample shall...

  11. Proceedings of the 6. international conference on stability and handling of liquid fuels. Volume 1

    Energy Technology Data Exchange (ETDEWEB)

    Giles, H.N. [ed.] [Deputy Assistant Secretary for Strategic Petroleum Reserve, Washington, DC (United States). Operations and Readiness Office

    1998-12-01

    Volume 1 of these proceedings contain 29 papers related to aviation fuels and long term and strategic storage. Studies investigated fuel contamination, separation processes, measurement techniques, thermal stability, compatibility with fuel system materials, oxidation reactions, and degradation during storage.

  12. Crude oil and finished fuel storage stability: An annotated review

    Energy Technology Data Exchange (ETDEWEB)

    Whisman, M.L.; Anderson, R.P.; Woodward, P.W.; Giles, H.N.

    1991-01-01

    A state-of-the-art review and assessment of storage effects on crude oil and product quality was undertaken through a literature search by computer accessing several data base sources. Pertinent citations from that literature search are tabulated for the years 1980 to the present. This 1990 revision supplements earlier reviews by Brinkman and others which covered stability publications through 1979 and an update in 1983 by Goetzinger and others that covered the period 1952--1982. For purposes of organization, citations are listed in the current revision chronologically starting with the earliest 1980 publications. The citations have also been divided according to primary subject matter. Consequently 11 sections appear including: alternate fuels, gasoline, distillate fuel, jet fuel, residual fuel, crude oil, biodegradation, analyses, reaction mechanisms, containment, and handling and storage. Each section contains a brief narrative followed by all the citations for that category.

  13. Effect of handling and processing on pesticide residues in food- a review.

    Science.gov (United States)

    Bajwa, Usha; Sandhu, Kulwant Singh

    2014-02-01

    pesticide. There is diversified information available in literature on the effect of preparation, processing and subsequent handling and storage of foods on pesticide residues which has been compiled in this article.

  14. Size Distribution and Rate of Dust Generated During Grain Elevator Handling

    Science.gov (United States)

    Dust generated during grain handling is an air pollutant that produces safety and health hazards. This study was conducted to characterize the particle size distribution (PSD) of dust generated during handling of wheat and shelled corn in the research elevator of the USDA Grain Marketing and Product...

  15. Requirements for the register of physical persons for the preparation, use and handling radioactive sources

    International Nuclear Information System (INIS)

    1998-07-01

    This norm establishes the process for register of superior level profession nals enabled to the preparation, using, and handling of radioactive sources. This norm applies to the physical persons candidates applying to the register for preparation, use and handling of radioactive sources in radioactive installations at the industry, agriculture, teaching and researching

  16. Possible use of dual purpose dry storage casks for transportation and future storage of spent nuclear fuel from IRT-Sofia

    International Nuclear Information System (INIS)

    Manev, L.; Baltiyski, M.

    2003-01-01

    Objectives: The main objective of the present paper is related to one of the priority goals stipulated in Bulgarian Governmental Decision No.332 from May 17, 1999 - removal of SNF from IRT-Sofia site and its exporting for reprocessing and/or for temporary storage at Kozloduy NPP site. The variant of using dual purpose dry storage casks for transportation and future temporary storage of SNF from IRT-Sofia aims to find out a reasonable alternative of the existing till now variant for temporary SNF storage under water in the existing Kozloduy NPP Spent Fuel Storage Facility until its export for reprocessing. Results: Based on the given data for the condition of 73 Spent Nuclear Fuel Assemblies (SNFA) stored in the storage pool and technical data as well as data for available equipment and IRT-Sofia layout the following framework are specified: draft technical features of dual purpose dry storage casks and their overall dimensions; the suitability of the available equipment for safety and reliable performance of transportation and handling operations of assemblies from storage pool to dual purpose dry storage casks; the necessity of new equipment for performance of the above mentioned operations; Assemblies' transportation and handling operations are described; requirements to and conditions for future safety and reliable storage of SNFA loaded casks are determined. When selecting the technical solutions for safety assurance during performance of site handling operations of IRT-Sofia and for description of the exemplary casks the Effective Bulgarian Regulations are considered. The experience of other countries in performance of transfer and transportation of SNFA from such types of research reactors is taken into account. Also, Kozloduy NPP experience in SNF handling operations is taken into account. Conclusions: The Decision of Council of Minister for refurbishment of research reactor into a low power one and its future utilization for experimental and training

  17. 78 FR 24132 - New Mailing Standards for Live Animals and Special Handling

    Science.gov (United States)

    2013-04-24

    ... POSTAL SERVICE 39 CFR Part 111 New Mailing Standards for Live Animals and Special Handling AGENCY... require special handling service for shipments containing certain types of live animals, to limit the mail classes available for use when shipping certain types of live animals, and to expand the mailability of...

  18. Generic Planning and Control of Automated Material Handling Systems: Practical Requirements Versus Existing Theroy.

    NARCIS (Netherlands)

    Haneyah, S.W.A.; Zijm, Willem H.M.; Schutten, Johannes M.J.; Schuur, Peter

    2011-01-01

    This paper discusses the problem of generic planning and control of Automated Material Handling Systems (AMHSs). The paper illustrates the relevance of this research direction, and then addresses three different market sectors where AMHSs are used. These market sectors are: baggage handling,

  19. 7 CFR 1944.425 - Handling and accounting for borrower loan funds.

    Science.gov (United States)

    2010-01-01

    ... 7 Agriculture 13 2010-01-01 2009-01-01 true Handling and accounting for borrower loan funds. 1944... Grants § 1944.425 Handling and accounting for borrower loan funds. Grantees will be required to...HA or its successor agency under Public Law 103-354's non-discrimination policies in receiving...

  20. Effects of angling and manual handling on pike behaviour investigated by high-resolution positional telemetry

    DEFF Research Database (Denmark)

    Baktoft, Henrik; Aarestrup, Kim; Berg, Søren

    2013-01-01

    Human disturbances such as angling and manual handling may have long-term effects on the behaviour of pike, Esox lucius L., an ecologically important species. Using continuous high-resolution positional telemetry, this study compared the swimming activity of handled and unhandled pike in a small...