WorldWideScience

Sample records for handling storage transportation

  1. 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.

  2. 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

  3. 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

  4. 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.)

  5. 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

  6. 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.

  7. 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

  8. 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

  9. 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

  10. 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.

  11. 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

  12. 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)

  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. 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,…

  15. 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

  16. 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

  17. 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

  18. 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

  19. 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.

  20. 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

  1. TRANSPORT/HANDLING REQUESTS

    CERN Multimedia

    Groupe ST/HM

    2002-01-01

    A new EDH document entitled 'Transport/Handling Request' will be in operation as of Monday, 11th February 2002, when the corresponding icon will be accessible from the EDH desktop, together with the application instructions. This EDH form will replace the paper-format transport/handling request form for all activities involving the transport of equipment and materials. However, the paper form will still be used for all vehicle-hire requests. The introduction of the EDH transport/handling request form is accompanied by the establishment of the following time limits for the various services concerned: 24 hours for the removal of office items, 48 hours for the transport of heavy items (of up to 6 metric tons and of standard road width), 5 working days for a crane operation, extra-heavy transport operation or complete removal, 5 working days for all transport operations relating to LHC installation. ST/HM Group, Logistics Section Tel: 72672 - 72202

  2. Standardized, utility-DOE compatible, spent fuel storage-transport systems

    International Nuclear Information System (INIS)

    Smith, M.L.

    1991-01-01

    Virginia Power has developed and licensed a facility for dry storage of spent nuclear fuel in metal spent fuel storage casks. The modifications to the design of these casks necessary for licensing for both storage and transport of spent fuel are discussed along with the operational advantages of dual purpose storage-transport casks. Dual purpose casks can be used for storage at utility and DOE sites (MRS or repository) and for shipment between these sites with minimal spent fuel handling. The cost for a standardized system of casks that are compatible for use at both DOE and utility sites is discussed along with possible arrangements for sharing both the cost and benefits of dual purpose storage-transport casks

  3. 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

  4. 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.

  5. 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

  6. 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.)

  7. 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

  8. 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.

  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. Transportation impacts on the Tennessee highway system proposed monitored retrievable storage

    Energy Technology Data Exchange (ETDEWEB)

    Cobble, C.

    1985-12-12

    The issue of the transport of spent fuels to the proposed monitored retrievable storage facility in Tennessee is discussed. Relevant issues include the ability of the roads and bridges on the transport routes to handle the weight of the trucks. (CBS)

  11. 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

  12. Transportation system (TRUPACT) for contact-handled transuranic wastes

    International Nuclear Information System (INIS)

    Romesberg, L.E.; Pope, R.B.; Burgoyne, R.M.

    1982-04-01

    Contact-handled transuranic defense waste is being, and will continue to be, moved between a number of locations in the United States. The DOE is sponsoring development of safe, efficient, licensable, and cost-effective transportation systems to handle this waste. The systems being developed have been named TRUPACT which stands for TRansUranic PACkage Transporter. The system will be compatible with Type A packagings used by waste generators, interim storage facilities, and repositories. TRUPACT is required to be a Type B packaging since larger than Type A quantities of some radionuclides (particularly plutonium) may be involved in the collection of Type A packagings. TRUPACT must provide structural and thermal protection to the waste in hypothetical accident environments specified in DOT regulations 49CFR173 and NRC regulations 10CFR71. Preliminary design of the systems has been completed and final design for a truck system is underway. The status of the development program is reviewed in this paper and the reference design is described. Tests that have been conducted are discussed and long-term program objectives are reviewed

  13. 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.)

  14. Demonstration of a transportable storage system for spent nuclear fuel

    International Nuclear Information System (INIS)

    Shetler, J.R.; Miller, K.R.; Jones, R.E.

    1993-01-01

    The purpose of this paper is to discuss the joint demonstration project between the Sacramento Municipal Utility District (SMUD) and the US Department of Energy (DOE) regarding the use of a transportable storage system for the long-term storage and subsequent transport of spent nuclear fuel. SMUD's Rancho Seco nuclear generating station was shut down permanently in June 1989. After the shutdown, SMUD began planning the decommissioning process, including the disposition of the spent nuclear fuel. Concurrently, Congress had directed the Secretary of Energy to develop a plan for the use of dual-purpose casks. Licensing and demonstrating a dual-purpose cask, or transportable storage system, would be a step toward achieving Congress's goal of demonstrating a technology that can be used to minimize the handling of spent nuclear fuel from the time the fuel is permanently removed from the reactor through to its ultimate disposal at a DOE facility. For SMUD, using a transportable storage system at the Rancho Seco Independent Spent-Fuel Storage Installation supports the goal of abandoning Rancho Seco's spent-fuel pool as decommissioning proceeds

  15. 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.

  16. Transportation impacts on the Tennessee highway system proposed monitored retrievable storage. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Cobble, C.

    1985-12-12

    The issue of the transport of spent fuels to the proposed monitored retrievable storage facility in Tennessee is discussed. Relevant issues include the ability of the roads and bridges on the transport routes to handle the weight of the trucks. (CBS)

  17. 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.

  18. 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.

  19. The Next Nuclear Gamble. Transportation and storage of nuclear waste

    International Nuclear Information System (INIS)

    Resnikoff, M.

    1985-01-01

    The Next Nuclear Gamble examines risks, costs, and alternatives in handling irradiated nuclear fuel. The debate over nuclear power and the disposal of its high-level radioactive waste is now nearly four decades old. Ever larger quantities of commercial radioactive fuel continue to accumulate in reactor storage pools throughout the country and no permanent storage solution has yet been designated. As an interim solution, the government and utilities prefer that radioactive wastes be transported to temporary storage facilities and subsequently to a permanent depository. If this temporary and centralized storage system is implemented, however, the number of nuclear waste shipments on the highway will increase one hundredfold over the next fifteen years. The question directly addressed is whether nuclear transport is safe or represents the American public's domestic nuclear gamble. This Council on Economic Priorities study, directed by Marvin Resnikoff, shows on the basis of hundreds of government and industry reports, interviews and surveys, and original research, that transportation of nuclear materials as currently practiced is unsafe

  20. 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

  1. 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

  2. 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)

  3. CASTORR 1000/19: Development and Design of a New Transport and Storage Cask

    International Nuclear Information System (INIS)

    Funke, Th.; Henig, Ch.

    2008-01-01

    The design of the new transport and storage cask type CASTOR R 1000/19 is presented in this paper. This cask was developed for the dry interim storage of spent VVER1000 fuel assemblies concerning the requirements of the Temelin NPP, Czech Republic. While the cask body is based on well-known ductile cast iron cask types with in-wall moderator, the basket follows a new concept. The basket is able to carry 19 fuel assemblies with a total decay heat power up to approximately 17 kW. The cask fulfils all requirements for a type B(U)F package. The main nuclear, mechanical and thermal properties of the cask are illustrated for normal conditions and for hypothetical accident scenarios during transport and storage. The main steps of the handling procedure such as loading the cask, drying the cavity and mounting the double lid system for tightness during interim storage are shown in principle. For this handling, boundary conditions at the NPP site such as dimensions, weight and the loading machine interface are considered. (authors)

  4. 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)

  5. 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

  6. Issues related to the transport of a transportable storage cask after storage

    International Nuclear Information System (INIS)

    McConnell, P.; Brimhall, J.L.; Creer, J.M.; Gilbert, E.R.; Sanders, T.L.; Jones, R.H.

    1991-01-01

    An evaluation was performed to assess whether the reliability of a transportable storage cask system and the risks associated with its use are comparable to those associated with existing transport cask systems and, if they are not, determine how the transportable storage cask system can be made as reliable as existing systems. Reliability and failure mode analyses of both transport-only casks and transportable storage casks and implementation options are compared. Current knowledge regarding the potential effects of a long-term dry storage environment on spent fuel and cask materials is reviewed. A summary assessment of the consideration for deploying a transportable storage cask (TSC) system with emphasis on preliminary design, validation and operational recommendations for TSC implementations is presented. The analyses conclude that a transportable storage cask can likely be shipped upopened by applying a combination of design considerations and operational constraints, including environmental monitoring and pretransport assessments of functional reliability of the cask. A proper mix of these constraints should yield risk parity with any existing transport cask

  7. 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

  8. 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

  9. 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

  10. Developing new transportable storage casks for interim dry storage

    International Nuclear Information System (INIS)

    Hayashi, K.; Iwasa, K.; Araki, K.; Asano, R.

    2004-01-01

    Transportable storage metal casks are to be consistently used during transport and storage for AFR interim dry storage facilities planning in Japan. The casks are required to comply with the technical standards of regulations for both transport (hereinafter called ''transport regulation'') and storage (hereafter called ''storage regulation'') to maintain safety functions (heat transfer, containment, shielding and sub-critical control). In addition to these requirements, it is not planned in normal state to change the seal materials during storage at the storage facility, therefore it is requested to use same seal materials when the casks are transported after storage period. The dry transportable storage metal casks that satisfy the requirements have been developed to meet the needs of the dry storage facilities. The basic policy of this development is to utilize proven technology achieved from our design and fabrication experience, to carry out necessary verification for new designs and to realize a safe and rational design with higher capacity and efficient fabrication

  11. 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 ...

  12. Developing new transportable storage casks for interim dry storage

    Energy Technology Data Exchange (ETDEWEB)

    Hayashi, K.; Iwasa, K.; Araki, K.; Asano, R. [Hitachi Zosen Diesel and Engineering Co., Ltd., Tokyo (Japan)

    2004-07-01

    Transportable storage metal casks are to be consistently used during transport and storage for AFR interim dry storage facilities planning in Japan. The casks are required to comply with the technical standards of regulations for both transport (hereinafter called ''transport regulation'') and storage (hereafter called ''storage regulation'') to maintain safety functions (heat transfer, containment, shielding and sub-critical control). In addition to these requirements, it is not planned in normal state to change the seal materials during storage at the storage facility, therefore it is requested to use same seal materials when the casks are transported after storage period. The dry transportable storage metal casks that satisfy the requirements have been developed to meet the needs of the dry storage facilities. The basic policy of this development is to utilize proven technology achieved from our design and fabrication experience, to carry out necessary verification for new designs and to realize a safe and rational design with higher capacity and efficient fabrication.

  13. 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...

  14. CASTOR{sup R} 1000/19: Development and Design of a New Transport and Storage Cask

    Energy Technology Data Exchange (ETDEWEB)

    Funke, Th.; Henig, Ch. [GNS mbH, Hollestrasse 7A, 45127 Essen (Germany)

    2008-07-01

    The design of the new transport and storage cask type CASTOR{sup R} 1000/19 is presented in this paper. This cask was developed for the dry interim storage of spent VVER1000 fuel assemblies concerning the requirements of the Temelin NPP, Czech Republic. While the cask body is based on well-known ductile cast iron cask types with in-wall moderator, the basket follows a new concept. The basket is able to carry 19 fuel assemblies with a total decay heat power up to approximately 17 kW. The cask fulfils all requirements for a type B(U)F package. The main nuclear, mechanical and thermal properties of the cask are illustrated for normal conditions and for hypothetical accident scenarios during transport and storage. The main steps of the handling procedure such as loading the cask, drying the cavity and mounting the double lid system for tightness during interim storage are shown in principle. For this handling, boundary conditions at the NPP site such as dimensions, weight and the loading machine interface are considered. (authors)

  15. 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.

  16. 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

  17. 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.

  18. 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

  19. 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.

  20. Manipulation technology optimization for the interim storage of HAW transport and storage containers; Optimierung der Handhabungstechnik zur Zwischenlagerung von HAW-Transport- und Lagerbehaeltern

    Energy Technology Data Exchange (ETDEWEB)

    Emmrich, Uwe; Krueger, Michael; Schulze, Hartmut [GNS Gesellschaft fuer Nuklear-Service mbH, Essen (Germany)

    2011-07-01

    The handling of high-level radioactive waste transport and storage containers from reprocessing plants is determined by the cask configuration and the radiation protection measures with respect to the safe enclosure of the radioactive inventory and shielding of gamma and neutron radiation. The new of CASTOR {sup registered} HAW28M was designed for higher radioactive inventories, the heat generation is has rarely been changed with respect to the former design. The essential structural modifications are shock absorbers that have to be demounted before storage in the interim storage facility Gorleben. Due to public acceptance forcings the ALARA principle is not the only basis for manipulation technology optimizations, the minimization of dose rate for the operational personnel is of increasing importance. The authors describe the optimizations and the resulting dose reductions.

  1. 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)

  2. 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

  3. 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)

  4. 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

  5. UFD Storage and Transportation - Transportation Working Group Report

    International Nuclear Information System (INIS)

    Maheras, Steven J.; Ross, Steven B.

    2011-01-01

    The Used Fuel Disposition (UFD) Transportation Task commenced in October 2010. As its first task, Pacific Northwest National Laboratory (PNNL) compiled a list of structures, systems, and components (SSCs) of transportation systems and their possible degradation mechanisms during extended storage. The list of SSCs and the associated degradation mechanisms (known as features, events, and processes (FEPs)) were based on the list of used nuclear fuel (UNF) storage system SSCs and degradation mechanisms developed by the UFD Storage Task (Hanson et al. 2011). Other sources of information surveyed to develop the list of SSCs and their degradation mechanisms included references such as Evaluation of the Technical Basis for Extended Dry Storage and Transportation of Used Nuclear Fuel (NWTRB 2010), Transportation, Aging and Disposal Canister System Performance Specification, Revision 1 (OCRWM 2008), Data Needs for Long-Term Storage of LWR Fuel (EPRI 1998), Technical Bases for Extended Dry Storage of Spent Nuclear Fuel (EPRI 2002), Used Fuel and High-Level Radioactive Waste Extended Storage Collaboration Program (EPRI 2010a), Industry Spent Fuel Storage Handbook (EPRI 2010b), and Transportation of Commercial Spent Nuclear Fuel, Issues Resolution (EPRI 2010c). SSCs include items such as the fuel, cladding, fuel baskets, neutron poisons, metal canisters, etc. Potential degradation mechanisms (FEPs) included mechanical, thermal, radiation and chemical stressors, such as fuel fragmentation, embrittlement of cladding by hydrogen, oxidation of cladding, metal fatigue, corrosion, etc. These degradation mechanisms are discussed in Section 2 of this report. The degradation mechanisms have been evaluated to determine if they would be influenced by extended storage or high burnup, the need for additional data, and their importance to transportation. These categories were used to identify the most significant transportation degradation mechanisms. As expected, for the most part, the

  6. 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

  7. Low-cost concepts for dry transfer of spent fuel and waste between storage and transportation casks

    International Nuclear Information System (INIS)

    Schneider, K.L.

    1984-01-01

    The federal government may provide interim storage for spent fuel from commercial nuclear power reactors that have used up their available storage capacity. One of the leading candidate concepts for this interim storage is to place spent fuel in large metal shielding casks. The Federal Interim Storage (FIS) site may not have the capability to transfer spent fuel from transportation casks to storage casks and vice versa. Thus, there may be an incentive to construct a relatively inexpensive but reliable intercask transfer system for use at an FIS site. This report documents the results of a preliminary study of preconceptual design and analysis of four intercask transfer concepts. The four concepts are: a large shielded cylindrical turntable that contains an integral fuel handling machine (turntable concept); a shielded fuel handling machine under which shipping and storage casks are moved horizontally (shuttle concept); a small hot cell containing equipment for transferring fuel betwee shipping and storage casks (that enter and leave the cell on carts) in a bifurcated trench (trench concept) and a large hot cell, shielded by an earthen berm, that houses equipment for handling fuel between casks that enter and leave the cell on a single cart (igloo concept). Information derived for each of the concepts is operating, capital and relocation costs; implementation and relocation time requirements; and overall characteristics

  8. Effects of Transport and Storage Conditions on Gene Expression in Blood Samples.

    Science.gov (United States)

    Malentacchi, Francesca; Pizzamiglio, Sara; Wyrich, Ralf; Verderio, Paolo; Ciniselli, Chiara; Pazzagli, Mario; Gelmini, Stefania

    2016-04-01

    Inappropriate handling of blood samples might induce or repress gene expression and/or lead to RNA degradation affecting downstream analysis. In particular, sample transport is a critical step for biobanking or multicenter studies because of uncontrolled variables (i.e., unstable temperature). We report the results of a pilot study implemented within the EC funded SPIDIA project, aimed to investigate the role of transport and storage of blood samples containing and not containing an RNA stabilizer. Blood was collected from a single donor both in EDTA and in PAXgene Blood RNA tubes. Half of the samples were sent to a second laboratory both at room temperature and at 4°C, whereas the remaining samples were stored at room temperature and at 4°C. Gene expression of selected genes (c-FOS, IL-1β, IL-8, and GAPDH) known to be induced or repressed by ex vivo blood handling and of blood-mRNA quality biomarkers identified and validated within the SPIDIA project, which allow for monitoring changes in unstabilized blood samples after collection and during transport and storage, were analyzed by RT-qPCR. If the shipment of blood in tubes not containing RNA stabilizer is not performed under a stable condition, gene profile studies can be affected by the effects of transport. Moreover, also controlled temperature shipment (4°C) can influence the expression of specific genes if blood is collected in tubes not containing a stabilizer. The use of dedicated biomarkers or time course experiments should be performed in order to verify potential bias on gene expression analysis due to sample shipment and storage conditions. Alternatively, the use of RNA stabilizer containing tubes can represent a reliable option to avoid ex vivo RNA changes.

  9. 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.

  10. 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.

  11. 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

  12. On-site transportation and handling of uranium-233 special nuclear material: Preliminary hazards and accident analysis. Final

    International Nuclear Information System (INIS)

    Solack, T.; West, D.; Ullman, D.; Coppock, G.; Cox, C.

    1995-01-01

    U-233 Special Nuclear Material (SNM) currently stored at the T-Building Storage Areas A and B must be transported to the SW/R Tritium Complex for repackaging. This SNM is in the form of oxide powder contained in glass jars which in turn are contained in heat sealed double polyethylene bags. These doubled-bagged glass jars have been primarily stored in structural steel casks and birdcages for approximately 20 years. The three casks, eight birdcages, and one pail/pressure vessel will be loaded onto a transport truck and moved over an eight day period. The Preliminary Hazards and Accident Analysis for the on-site transportation and handling of Uranium-233 Special Nuclear Material, documented herein, was performed in accordance with the format and content guidance of DOE-STD-3009-94, Preparation Guide for US Department of Energy Nonreactor Nuclear Facility Safety Analysis Reports, dated July 1994, specifically Chapter Three, Hazard and Accident Analysis. The Preliminary Hazards Analysis involved detailed walkdowns of all areas of the U-233 SNM movement route, including the T-Building Storage Area A and B, T-Building truck tunnel, and the roadway route. Extensive discussions were held with operations personnel from the Nuclear Material Control Group, Nuclear Materials Accountability Group, EG and G Mound Security and the Material Handling Systems Transportation Group. Existing documentation related to the on-site transportation of hazardous materials, T-Building and SW/R Tritium Complex SARs, and emergency preparedness/response documentation were also reviewed and analyzed to identify and develop the complete spectrum of energy source hazards

  13. Pituitary-adrenocortical adjustments to transport stress in horses with previous different handling and transport conditions

    Directory of Open Access Journals (Sweden)

    E. Fazio

    2016-08-01

    Full Text Available Aim: The changes of the hypothalamic pituitary adrenal (HPA axis response to a long distance transportation results in increase of adrenocorticotropic hormone (ACTH and cortisol levels. The purpose of the study was to quantify the level of short-term road transport stress on circulating ACTH and cortisol concentrations, related to the effect of previous handling and transport experience of horses. Materials and Methods: The study was performed on 56 healthy horses after short-term road transport of 30 km. The horses were divided into four groups, Groups A, B, C, and D, with respect to the handling quality: Good (Groups A and B, bad (Group D, and minimal handling (Group C conditions. According to the previous transport, experience horses were divided as follows: Horses of Groups A and D had been experienced long-distance transportation before; horses of Groups B and C had been limited experience of transportation. Results: One-way RM-ANOVA showed significant effects of transport on ACTH changes in Groups B and C and on cortisol changes in both Groups A and B. Groups A and B showed lower baseline ACTH and cortisol values than Groups C and D; Groups A and B showed lower post-transport ACTH values than Groups C and D. Groups A, B, and C showed lower post-transport cortisol values than Group D. Only Groups A and B horses have shown an adequate capacity of stress response to transportation. Conclusion: The previous transport experience and quality of handling could influence the HPA axis physiological responses of horses after short-term road transport.

  14. Automated cassette-to-cassette substrate handling system

    Science.gov (United States)

    Kraus, Joseph Arthur; Boyer, Jeremy James; Mack, Joseph; DeChellis, Michael; Koo, Michael

    2014-03-18

    An automated cassette-to-cassette substrate handling system includes a cassette storage module for storing a plurality of substrates in cassettes before and after processing. A substrate carrier storage module stores a plurality of substrate carriers. A substrate carrier loading/unloading module loads substrates from the cassette storage module onto the plurality of substrate carriers and unloads substrates from the plurality of substrate carriers to the cassette storage module. A transport mechanism transports the plurality of substrates between the cassette storage module and the plurality of substrate carriers and transports the plurality of substrate carriers between the substrate carrier loading/unloading module and a processing chamber. A vision system recognizes recesses in the plurality of substrate carriers corresponding to empty substrate positions in the substrate carrier. A processor receives data from the vision system and instructs the transport mechanism to transport substrates to positions on the substrate carrier in response to the received data.

  15. 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)

  16. 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).

  17. 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

  18. Considerations applicable to the transportability of a transportable storage cask at the end of the storage period

    International Nuclear Information System (INIS)

    Sanders, T.L.; Ottinger, C.A.; Brimhall, J.L.; Creer, J.M.; Gilbert, E.R.; Jones, R.H.; McConnell, P.E.

    1991-11-01

    Additional spent fuel storage capacity is needed at many nuclear power plant sites where spent fuel storage pools have either reached or are expected to reach maximum capacities before spent fuel can be removed. This analysis examines certain aspects of Transportable Storage Casks (TSC) to assist in the determination of their feasibility as an option for at-reactor dry storage. Factors that can affect in-transport reliability include: the quality of design, development, and fabrication activities; the possibilities of damage or error during loading and closure; in-storage deterioration or unanticipated storage conditions; and the potential for loss of storage period monitoring/measurement data necessary for verifying the TSC fitness-for-transport. The reported effort utilizes a relative reliability comparison of TSCs to Transport-Only Casks (TOC) to identify and prioritize those issues and activities that are unique to TSCs. TSC system recommendations combine certain design and operational features, such as in-service monitoring, pretransport assessments, and conservation design assumptions, which when implemented and verified, should sufficiently ensure that the system will perform as intended in a later transport environment

  19. 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.

  20. Steam coal processing technology: handling, high-order processing, COM, meth-coal

    Energy Technology Data Exchange (ETDEWEB)

    Kamata, H.; Onodera, J.

    1982-01-01

    Topics covered include: various handling techologies (overland and marine transport, storage, water removal, drying, comminution and sizing); various coal processing technologies (gravity concentration, magnetic separation, multi-stage flotation, liquid-phase pelletizing, chemical processing); production methods for coal-oil mixtures (COM), their physical properties, stability, storage, transport, advantages, plus recent trends in research and development; production of coal-methanol slurry (meth-coal), its stability, storage, transport, utilization and environmental problems, plus latest trends in research and development. (In Japanese)

  1. Risk from transportation and handling of butane; Etude de cas: jusqu`ou quantifier les risques lies aux facteurs humains ? Application au transport routier

    Energy Technology Data Exchange (ETDEWEB)

    Rao, B.; Celier, J.

    1997-12-31

    This paper presents the results and recommendations derived from a detailed assessment of a butane supply and butane transportation system. Based on a hazard and operability (HAZOP) study performed earlier, the need to undertake a more detailed assessment of the risks associated with the handling and transport of butane for the maleic anhydride (MAN) unit at a site was identified in order to ensure that all reasonable risk mitigation actions had been evaluated. Therefore, PLG initiated this study to quantify the likelihood and consequences of butane releases. The scope of the risk assessment includes all operations and activities with the handling and transport of butane, including: loading of butane trucks at the butane loading terminal; transport of butane by tank truck from the loading terminal to the plant site; unloading of the butane into the MAN unit storage sphere. Risks were quantified in terms of the likelihood of butane releases that could leas to a fire (pool or vapor cloud), an unconfined vapor cloud explosion (UVCE), or a boiling expanding vapor explosion (BLEVE), and the consequences of such releases in terms of the potential impact on both plant workers and the general public who live or work near the butane loading terminal, the transport route, or the plant site. (author)

  2. 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

  3. Calixarene-mediated liquid membrane transport of choline conjugates 3: The effect of handle variation on neurotransmitter transport.

    Science.gov (United States)

    Collins, James L; Fujii, Ayu; Roshandel, Sahar; To, Cuong-Alexander; Schramm, Michael P

    2017-07-01

    Upper rim phosphonic acid functionalized calix[4]arene affects selective transport of multiple molecular payloads through a liquid membrane. The secret is in the attachment of a receptor-complementary handle to the payload. We find that the trimethylammonium ethylene group present in choline is one of several general handles for the transport of drug and drug-like species. Herein we compare the effect of handle variation against the transport of serotonin and dopamine. We find that several ionizable amine termini handles are sufficient for transport and identify two ideal candidates. Their performance is significantly enhanced in HEPES buffered solutions. This inquiry completes a series of 3 studies aimed at optimization of this strategy. In completion a new approach towards synthetic receptor mediated selective small molecule transport has emerged; future work in vesicular and cellular systems will follow. Copyright © 2017 Elsevier Ltd. All rights reserved.

  4. Contributions to LWR spent fuel storage and transport

    International Nuclear Information System (INIS)

    The papers included in this document describe the aspects of spent LWR fuel storage and transport-behaviour of spent fuel during storage; use of compact storage packs; safety of storage; design of storage facilities AR and AFR; description of transport casks and transport procedures

  5. 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...

  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. 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...

  8. 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

  9. Apparatus for the storage of transport- and storage-containers containing radioactive fuel elements

    International Nuclear Information System (INIS)

    Vox, A.

    1983-01-01

    The invention concerns an apparatus for the storage of transport and storage containers containing radioactive fuel elements. For each transport or storage container there is a separate silo-type container of steel, concrete, prestressed concrete or suchlike breakproof and fireproof material, to be placed in the open, that can be opened for removal and placing of the transport or storage container respectively. (orig.) [de

  10. Double container system for the transport and storage of radioactive materials

    International Nuclear Information System (INIS)

    Popp, F.W.; Pontani, B.; Ernst, E.

    1987-01-01

    The double container system consists of an inner storage container made of steel for the gastight inclusion of the radioactive material to be stored and an outer shielding container which ensures the necessary shielding and mechanical safety in handling and transport. A neutron moderator layer of material containing hydrogen, preferably polyethylene, is present in the annular gap between the outer shielding container and the inner storage container. In order to achieve good shielding with simultaneous very good heat conduction from the inside to the outside, the moderator layer consists of individual polyethylene rings stacked above one another. There is an H profile ring made of heat conducting metal material between each two polyethylene rings. The legs of the H profile ring surround the sides of the two polyethylene rings for fixing it. (orig.) [de

  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. 78 FR 41993 - Transport Handling Specialists, Inc.-Continuance in Control Exemption-RSL Railroad, LLC

    Science.gov (United States)

    2013-07-12

    ... DEPARTMENT OF TRANSPORTATION Surface Transportation Board [Docket No. FD 35726] Transport Handling Specialists, Inc.--Continuance in Control Exemption--RSL Railroad, LLC Transport Handling Specialists, Inc. (THS), has filed a verified notice of exemption (Notice) under 49 CFR 1180.2(d)(2) to continue in...

  13. Storage and transport of hazardous materials

    International Nuclear Information System (INIS)

    Jaeger, P.; Haferkamp, K.

    1986-01-01

    The attempt has been made to characterise the present risk scenario, and to set out approaches or methods for remedy and risk control. For this purpose, a retrospective analysis has been made of accidents, damage and consequential damage that occurred in the past either during storage of hazardous materials, or during road transport. A risk-benefit model facilitates assessment of accident frequency. The history of accidents during storage or transport allows assessment of the dangerousness of various materials. Another important aspect discussed is the property and behaviour of containers used for storage or transport. (DG) [de

  14. Process & Quality procedures for transport & handling activities

    CERN Document Server

    Böttcher, O

    2002-01-01

    To respect the detailed and complex planning of the LHC installation project it is essential to reduce possible faults in every technical service that can cause delays in the schedule. In order to ensure proper execution of transport and handling activities it is important to get detailed information from the clients as early as possible in order to do the planning and the organisation of the required resources. One procedure that requires greater focus in the future is the preparation of the resources. The goal is to prevent equipment breakdowns and accidents while executing transport and handling activities. In the LEP dismantling project multiple breakdowns of important cranes caused serious problems in the project schedule. For the LHC installation project similar incidents in the reliability of the equipment cannot be accepted because of the high sensitivity of the whole schedule. This paper shall outline the efforts and methods that are put in place in order to meet the LHC installation requirements.

  15. 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.

  16. 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

  17. Application of advanced handling techniques to transportation cask design

    International Nuclear Information System (INIS)

    Bennett, P.C.

    1992-01-01

    Sandia National Laboratories supports the US Department of Energy (DOE) Office of Civilian Radioactive Waste Management (OCRWM) applying technology to the safe transport of nuclear waste. Part of that development effort includes investigation of advanced handling technologies for automation of cask operations at nuclear waste receiving facilities. Although low radiation levels are expected near transport cask surfaces, cumulative occupational exposure at a receiving facility can be significant. Remote automated cask handling has the potential to reduce both the occupational exposure and the time necessary to process a cask. Thus, automated handling is consistent with DOE efforts to reduce the lifecycle costs of the waste disposal system and to maintain public and occupational radiological risks as low as reasonably achievable. This paper describes the development of advanced handling laboratory mock-ups and demonstrations for spent fuel casks. Utilizing the control enhancements described below, demonstrations have been carried out including cask location and identification, contact and non-contact surveys, impact limiter removal, tiedown release, uprighting, swing-free movement, gas sampling, and lid removal operations. Manually controlled movement around a cask under off-normal conditions has also been demonstrated

  18. Performance of CASTORR HAW Cask Cold Trials for Loading, Transport and Storage of HAW canisters

    International Nuclear Information System (INIS)

    Wilmsmeier, Marco; Vossnacke, Andre

    2008-01-01

    On the basis of reprocessing contracts, concluded between the German Nuclear Utilities (GNUs) and the reprocessing companies in France (AREVA NC) and the UK (Nuclear Decommissioning Authority), GNS has the task to return the resulting residues to Germany. The high active waste (HAW) residuals from nuclear fuel reprocessing are vitrified and filled into steel cans, the HAW canisters. According to reprocessing contracts the equivalent number of HAW canisters to heavy metals delivered has to be returned to the country of origin and stored at an interim storage facility where applicable. The GNS' CASTOR R HAW casks are designed and licensed to fulfil the requirements for transport and long-term storage of HAW canisters. The new cask type CASTOR R HAW28M is capable of storing 28 HAW canisters with a maximum thermal power of 56 kW in total. Prior to the first active cask loading at a reprocessing facility it is required to demonstrate all important handling steps with the CASTOR R HAW28M cask according to a specific and approved sequence plan (MAP). These cold trials have to be carried out at the cask loading plant and at the reception area of an interim storage facility in Gorleben (TBL-G), witnessed by the licensing authorities and their independent experts. At transhipment stations GNS performs internal trials to demonstrate safe handling. A brand-new, empty CASTOR R HAW28M cask has been shipped from the GNS cask assembly facility in Muelheim to the TBL-G for cold trials. With this cask, GNS has to demonstrate the transhipment of casks at the Dannenberg transfer station from rail to road, transport to and reception at the TBL-G as well as incoming dose rate and contamination measurements and preparation for storage. After removal of all shock absorbers with a cask specific handling frame, tilting operation and assembly of the secondary lid with a pressure sensor, the helium leak tightness and 'Block-mass' tests have to be carried out as well. GNS long-term CASTOR R

  19. 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

  20. 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

  1. Special storage of leaking fuel at Paks NPP

    International Nuclear Information System (INIS)

    Biro, Janos; Szőke, L.; Burján, T.; Lukács, R.; Hózer, H.

    2015-01-01

    In this paper the activities related with spent, hermetic as well as leaking fuel handling and storage, including: Spent fuel pool; Transportation criteria for the spent fuel assemblies and Interim spent fuel dry storage; Short-term storage in the spent fuel pool; Identification of the leaking assemblies by the TS-device; Present conception of Identification, handling of the leaking FAs; Modified transport procedure for the leaking FAs; Calculation of solved activity inside the leaking fuel rod; Solved activity limit values for the leaking FAs; Long-term storage in the interim spent Fuel dry storage are presented. At the end authors’ concluded that: 1) The leaking FA can be transported to the interim dry storage together with the other spent fuel assemblies in the transport container. 2) The transport-documentation of the leaking FA has to contain: isotope inventory, calculated solved activity values of the failed FA and the quantity of failed fuel rods. 3) Performing three leakage tests of the identified leaking FA before the transportation in the 5FP. it is useful to decrease the solved activity concentration inside the leaking FA and give additional information about the extent of the leakage. 4) We can calculate simply the solved activity of the leaking FA. 5) The modified transport procedure will have to be authorized. 6) The radiological effects of the leaking FA are negligible relative to the natural background radiation

  2. Spent fuel storage and transport cask decontamination and modification. An overview of management requirements and applications based on practical experience

    International Nuclear Information System (INIS)

    1999-04-01

    A large increase in the number of casks required for transport and/or storage of spent fuel is forecast into the next century. The principal requirement will be for increased number of storage and dual purpose (transport/storage) casks for interim storage of spent fuel prior to reprocessing or permanent disposal in both on-site and off-site storage facilities. Through contact with radioactive materials spent fuel casks will be contaminated on both internal and external surfaces. In broad terms, cask contamination management can be defined by three components: minimisation, prevention and decontamination. This publication is a compilation of international experience with cask contamination problems and decontamination practices. The objective is to present current knowledge and experience as well as developments, trends and potential for new applications in this field. Furthermore, the report may assist in new design or modification of existing casks, cask handling systems and decontamination equipment

  3. 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)

  4. Safety improvement of start-up neutron source handling work by preparing new transport containers

    International Nuclear Information System (INIS)

    Shimazaki, Yosuke; Sawahata, Hiroaki; Yanagida, Yoshinori; Shinohara, Masanori; Kawamoto, Taiki; Takada, Shoji

    2016-01-01

    The conventional transport containers that have been used in HTTR start-up neutron source replacement work are not specialized type for HTTR start-up neutron source. As the risks associated with the safe handling of neutron source holders due to the above fact, the following three risks have been confirmed: (1) exposure risk due to leakage of neutron source or gamma rays, (2) risk of erroneous fall of neutron source holders, and (3) accident due to incorrect handling of transport containers. This paper reports the risks confirmed in the handling of neutron source holders associated with transport containers and the risk reduction measures, as well as the fabrication of new transport containers. By employing the size-reduction and simple structure, new transport containers have been completed at the same level of costs compared with the continuous use of the conventional transport containers, while satisfying the criteria of Type A transport materials and serving as risk preventive measures. Thus, new transport containers aimed at the risk prevention measures for the handling work of neutron source holders have been completed, and the safety of operation has been improved. (A.O.)

  5. Hydrogen transport and storage in engineered glass microspheres

    Energy Technology Data Exchange (ETDEWEB)

    Rambach, G.D.

    1994-04-20

    New, high-strength, hollow, glass microspheres filled with pressurized hydrogen exhibit storage densities which make them attractive for bulk hydrogen storage and transport. The hoop stress at failure of our engineered glass microspheres is about 150,000 psi, permitting a three-fold increase in pressure limit and storage capacity above commercial microspheres, which fail at wall stresses of 50,000 psi. For this project, microsphere material and structure will be optimized for storage capacity and charge/discharge kinetics to improve their commercial practicality. Microsphere production scale up will be performed, directed towards large-scale commercial use. Our analysis relating glass microspheres for hydrogen transport with infrastructure and economics` indicate that pressurized microspheres can be economically competitive with other forms of bulk rail and truck transport such as hydride beds, cryocarbons and pressurized tube transports. For microspheres made from advanced materials and processes, analysis will also be performed to identify the appropriate applications of the microspheres considering property variables, and different hydrogen infrastructure, end use, production and market scenarios. This report presents some of the recent modelling results for large beds of glass microspheres in hydrogen storage applications. It includes plans for experiments to identify the properties relevant to large-bed hydrogen transport and storage applications, of the best, currently producible, glass microspheres. This work began in March, 1994. Project successes will be manifest in the matching of cur-rent glass microspheres with a useful application in hydrogen bulk transport and storage, and in developing microsphere materials and processes that increase the storage density and reduce the storage energy requirement.

  6. 76 FR 47577 - Enstor Grama Ridge Storage and Transportation, L.L.C.; Enstor Katy Storage and Transportation, L...

    Science.gov (United States)

    2011-08-05

    ... DEPARTMENT OF ENERGY Federal Energy Regulatory Commission [Docket No. PR10-97-003; Docket No. PR10-101-003; Not Consolidated] Enstor Grama Ridge Storage and Transportation, L.L.C.; Enstor Katy Storage and Transportation, L.P.; Notice of Filing Take notice that on July 29, 2011, the applicants listed...

  7. 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

  8. 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.)

  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. 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...

  11. 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...

  12. Electronic Monitoring Of Storage And Transport Temperatures Of ...

    African Journals Online (AJOL)

    Electronic Monitoring Of Storage And Transport Temperatures Of Thermostable Newcastle ... 22) were monitored during storage and transport from vaccine production laboratory in Temeke, Dar es ... EMAIL FULL TEXT EMAIL FULL TEXT

  13. Decontamination of transport casks and of spent fuel storage facilities

    International Nuclear Information System (INIS)

    1990-06-01

    The present document provides an analysis of the technical papers presented at the meeting as well as a summary of the panel discussion. Conclusions and Recommendations: The meeting agreed that the primary source of contamination of transport casks is the production of radioactive isotopes in nuclear fuel and activation products of fuel components in nuclear reactors. The type, amount of mechanism for the release of these isotopes depend on the reactor type and fuel handling process. The widespread use of pools for the storage and handling of fuel provides an easy path for the transfer of contamination. Control of pool water conditions is essential for limiting the spread of contamination. For plants where casks are immersed in pools for loading, the immersion times should be minimised. Casks should be designed for ease of decontamination. The meeting discussed the use of stainless steel and suitable paints for coating casks. Designers should consider the appropriate coating for specific applications. The use of pressurized water for decontamination is recommended whenever possible. A number of commercially available reagents exist for decontaminating cask external surfaces. More work, however, is needed to cope with Pressurized Water Reactor crud within casks. Leaking fuel should be identified and isolated before storage in pools. Basic studies of the uptake and release of contamination from cask surfaces should be initiated. Standardization of methods of contamination measurement and instrumentation should be instituted. Refs, figs and tabs

  14. 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)

  15. 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)

  16. Multi-purpose canisters as an alternative for storage, transportation, and disposal of spent nuclear fuel

    International Nuclear Information System (INIS)

    Hollaway, W.R.; Rozier, R.; Nitti, D.A.; Williams, J.R.

    1993-01-01

    A study was conducted to assess the feasibility of using multi-purpose canisters to handle spent nuclear fuel throughout the Civilian Radioactive Waste Management System. Multi-purpose canisters would be sealed, metallic containers maintaining multiple spent fuel assemblies in a dry, inert environment and overpacked separately and uniquely for the various system elements of storage, transportation, and disposal. Using five implementation scenarios, the multi-purpose canister was evaluated with regard to several measures of effectiveness, including number of handlings, radiation exposure, cost, schedule and licensing considerations, and public perception. Advantages and disadvantages of the multi-purpose canister were identified relative to the current reference system within each scenario, and the scenarios were compared to determine the most effective method of implementation

  17. 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.

  18. 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.

  19. A Multi-function Cask for At-Reactor Storage of Short-Cooled Spent Fuel, Transport, and Disposal

    International Nuclear Information System (INIS)

    Forsberg, C.W.

    2004-01-01

    The spent nuclear fuel (SNF) system in the United States was designed with the assumptions that SNF would be stored for several years in an at-reactor pool and then transported to reprocessing plants for recovery of fissile materials, that security would not be a major issue, and that the SNF burnups would be low. The system has evolved into a once-through fuel cycle with high-burnup SNF, long-term storage at the reactor sites, and major requirements for safeguards and security. An alternative system is proposed to better meet these current requirements. The SNF is placed in multi-function casks with the casks used for at-reactor storage, transport, and repository disposal. The cask is the handling package, provides radiation shielding, and protects the SNF against accidents and assault. SNF assemblies are handled only once to minimize accident risks, maximize security and safeguards by minimizing access to SNF, and reduce costs. To maximize physical protection, the cask body is constructed of a cermet (oxide particles embedded in steel, the same class of materials used in tank armor) and contains no cooling channels or other penetrations that allow access to the SNF. To minimize pool storage of SNF, the cask is designed to accept short-cooled SNF. To maximize the capability of the cask to reject decay heat and to limit SNF temperatures from short-cooled SNF, the cask uses (1) natural circulation of inert gas mixtures inside the cask to transfer heat from the SNF to the cask body and (2) an overpack with external natural-circulation, liquid-cooled fins to transfer heat from the cask body to the atmosphere. This approach utilizes the entire cask body area for heat transfer to maximize heat removal rates-without any penetrations through the cask body that would reduce the physical protection capabilities of the cask body. After the SNF has cooled, the cooling overpack is removed. At the repository, the cask is placed in a corrosion-resistant overpack before disposal

  20. 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

  1. Team effort leads to versatile handling solution for pipe manufacturer

    Energy Technology Data Exchange (ETDEWEB)

    Anon.

    2010-09-15

    This article discussed the development of a new pipe-handling system that resulted in increased efficiencies in plant-to-yard transport for a custom steel pipe manufacturer. In the previous system, loaders would move finished pipe to the yard for storage. However, for transport loading, the pipe would have to be brought back indoors because only the inside cranes could handle loading the pipe without damaging the special outer coating on the pipe. In the new pipe-handling system, the loader is replaced with a Sennebogen 850 M rubber-tired material handler, which was developed for the steel recycling industry. The generator that comes on the material handler is retrofitted to power a purpose-built pipe-handler attachment. The machine's higher lifting reach allows for higher stacking, effectively increasing the capacity of the yard. The new pipe-handling machine allows trucks to be loaded right in the yard, eliminating the need to double-handle the pipe. 1 fig.

  2. Hydrogen transport and storage in engineered glass microspheres

    Energy Technology Data Exchange (ETDEWEB)

    Rambach, G.D.

    1995-02-28

    New, high strength glass microspheres filled with pressurized hydrogen exhibit densities which make them attractive for bulk hydrogen storage and transport. The membrane tensile stress at failure for engineered glass microspheres is about 150,000 psi, permitting a three-fold increase in pressure limit and storage capacity above commercial microspheres, which have been studied a decade ago and have been shown to fail at membrane stresses of 50,000 psi. This analysis relating glass microspheres for hydrogen transport with infrastructure and economics, indicate that pressurized microspheres can be economically competitive with other forms of bulk rail and truck transport such as pressurized tube transports and liquid hydrogen trailers. This paper will describe the matching of current glass microspheres with the useful application in commercial hydrogen bulk transport and storage.

  3. A concept of a nonfissile uranium hexafluoride overpack for storage, transport, and processing of corroded cylinders

    International Nuclear Information System (INIS)

    Pope, R.B.; Cash, J.M.; Singletary, B.H.

    1996-01-01

    There is a need to develop a means of safely transporting breached 48-in. cylinders containing depleted uranium hexafluoride (UF 6 ) from current storage locations to locations where the contents can be safely removed. There is also a need to provide a method of safely and easily transporting degraded cylinders that no longer meet the US Department of Transportation (DOT) and American National Standards Institute, Inc., (ANSI) requirements for shipments of depleted UF 6 . A study has shown that an overpack can be designed and fabricated to satisfy these needs. The envisioned overpack will handle cylinder models 48G, 48X, and 48Y and will also comply with the ANSI N14.1 and the American Society of Mechanical Engineers (ASME) Sect. 8 requirements

  4. Mockup of an automated material transport system for remote handling

    International Nuclear Information System (INIS)

    Porter, M.L.

    1992-01-01

    An Automated Material Transport System (AMTS) was identified for transport of samples within a Material and Process Control Laboratory (MPCL). The MPCL was designed with a dry sample handling laboratory and a wet chemistry analysis laboratory. Each laboratory contained several processing gloveboxes. The function of the AMTS was to automate the handling of materials, multiple process samples, and bulky items between process stations with a minimum of operator intervention and with minimum o[ waiting periods and nonproductive activities. This paper discusses the system design features, capabilities and results of initial testing. The overall performance of the AMTS is very good. No major problems or concerns were identified. System commands are simple and logical making the system user friendly. Operating principle and design of individual components is simple. With the addition of various track modules, the system can be configured in most any configuration. The AMTS lends itself very well for integration with other automated systems or products. The AMTS is suited for applications involving light payloads which require multiple sample and material handling, lot tracking, and system integration with other products

  5. 10 CFR 34.35 - Labeling, storage, and transportation.

    Science.gov (United States)

    2010-01-01

    ... 10 Energy 1 2010-01-01 2010-01-01 false Labeling, storage, and transportation. 34.35 Section 34.35 Energy NUCLEAR REGULATORY COMMISSION LICENSES FOR INDUSTRIAL RADIOGRAPHY AND RADIATION SAFETY REQUIREMENTS FOR INDUSTRIAL RADIOGRAPHIC OPERATIONS Equipment § 34.35 Labeling, storage, and transportation. (a...

  6. Storage/transport cask design and challenges

    International Nuclear Information System (INIS)

    Houston, J.V.; Viebrock, J.M.

    1989-01-01

    The concept of spent-fuel casks that could be used for both storage and for transport has been around for some years, but was only seriously evaluated when utilities started becoming concerned about adequate fuel storage. In the early 1980s, the U.S. Department of Energy proposed to solve the problem with their away-from-reactor storage facility concept. This was superceded by passage of the Nuclear Waste Policy Act of 1982, which directed the development of one or more waste repositories, the first of which was to be in operation by 1998. Delays in this program now indicate an opening data of 2003 or later. This, together with the lack of significant progress on a monitored retrievable storage facility, leaves the utility companies to solve their storage problems individually. One alternative is to use dual-purpose casks. The use of such a cask should eliminate the need to move the cask and fuel back into the spent-fuel pool for transfer to a transport cask. However, a dual-purpose cask must be licensed for use under both 10CFR71 and 10CFR72 of the U.S. Code of Federal Regulations. The purpose of this paper is to examine the differences between the requirements of 10CFR71 and 10CFR72, to note the changes over the past several years in the NRC's interpretation of 10CFR71 requirements, and to review the design modifications that the Nuclear Assurance Corporation (NAC) believes are required to make a licensed storage cask acceptable for transport under 10CFR71

  7. 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.

  8. Augmenting Transport versus Increasing Cold Storage to Improve Vaccine Supply Chains

    Science.gov (United States)

    Haidari, Leila A.; Connor, Diana L.; Wateska, Angela R.; Brown, Shawn T.; Mueller, Leslie E.; Norman, Bryan A.; Schmitz, Michelle M.; Paul, Proma; Rajgopal, Jayant; Welling, Joel S.; Leonard, Jim; Chen, Sheng-I; Lee, Bruce Y.

    2013-01-01

    Background When addressing the urgent task of improving vaccine supply chains, especially to accommodate the introduction of new vaccines, there is often a heavy emphasis on stationary storage. Currently, donations to vaccine supply chains occur largely in the form of storage equipment. Methods This study utilized a HERMES-generated detailed, dynamic, discrete event simulation model of the Niger vaccine supply chain to compare the impacts on vaccine availability of adding stationary cold storage versus transport capacity at different levels and to determine whether adding stationary storage capacity alone would be enough to relieve potential bottlenecks when pneumococcal and rotavirus vaccines are introduced by 2015. Results Relieving regional level storage bottlenecks increased vaccine availability (by 4%) more than relieving storage bottlenecks at the district (1% increase), central (no change), and clinic (no change) levels alone. Increasing transport frequency (or capacity) yielded far greater gains (e.g., 15% increase in vaccine availability when doubling transport frequency to the district level and 18% when tripling). In fact, relieving all stationary storage constraints could only increase vaccine availability by 11%, whereas doubling the transport frequency throughout the system led to a 26% increase and tripling the frequency led to a 30% increase. Increasing transport frequency also reduced the amount of stationary storage space needed in the supply chain. The supply chain required an additional 61,269L of storage to relieve constraints with the current transport frequency, 55,255L with transport frequency doubled, and 51,791L with transport frequency tripled. Conclusions When evaluating vaccine supply chains, it is important to understand the interplay between stationary storage and transport. The HERMES-generated dynamic simulation model showed how augmenting transport can result in greater gains than only augmenting stationary storage and can reduce

  9. Augmenting transport versus increasing cold storage to improve vaccine supply chains.

    Science.gov (United States)

    Haidari, Leila A; Connor, Diana L; Wateska, Angela R; Brown, Shawn T; Mueller, Leslie E; Norman, Bryan A; Schmitz, Michelle M; Paul, Proma; Rajgopal, Jayant; Welling, Joel S; Leonard, Jim; Chen, Sheng-I; Lee, Bruce Y

    2013-01-01

    When addressing the urgent task of improving vaccine supply chains, especially to accommodate the introduction of new vaccines, there is often a heavy emphasis on stationary storage. Currently, donations to vaccine supply chains occur largely in the form of storage equipment. This study utilized a HERMES-generated detailed, dynamic, discrete event simulation model of the Niger vaccine supply chain to compare the impacts on vaccine availability of adding stationary cold storage versus transport capacity at different levels and to determine whether adding stationary storage capacity alone would be enough to relieve potential bottlenecks when pneumococcal and rotavirus vaccines are introduced by 2015. Relieving regional level storage bottlenecks increased vaccine availability (by 4%) more than relieving storage bottlenecks at the district (1% increase), central (no change), and clinic (no change) levels alone. Increasing transport frequency (or capacity) yielded far greater gains (e.g., 15% increase in vaccine availability when doubling transport frequency to the district level and 18% when tripling). In fact, relieving all stationary storage constraints could only increase vaccine availability by 11%, whereas doubling the transport frequency throughout the system led to a 26% increase and tripling the frequency led to a 30% increase. Increasing transport frequency also reduced the amount of stationary storage space needed in the supply chain. The supply chain required an additional 61,269L of storage to relieve constraints with the current transport frequency, 55,255L with transport frequency doubled, and 51,791L with transport frequency tripled. When evaluating vaccine supply chains, it is important to understand the interplay between stationary storage and transport. The HERMES-generated dynamic simulation model showed how augmenting transport can result in greater gains than only augmenting stationary storage and can reduce stationary storage needs.

  10. 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.

  11. 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

  12. 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.

  13. MHSS: a material handling system simulator

    Energy Technology Data Exchange (ETDEWEB)

    Pomernacki, L.; Hollstien, R.B.

    1976-04-07

    A Material Handling System Simulator (MHSS) program is described that provides specialized functional blocks for modeling and simulation of nuclear material handling systems. Models of nuclear fuel fabrication plants may be built using functional blocks that simulate material receiving, storage, transport, inventory, processing, and shipping operations as well as the control and reporting tasks of operators or on-line computers. Blocks are also provided that allow the user to observe and gather statistical information on the dynamic behavior of simulated plants over single or replicated runs. Although it is currently being developed for the nuclear materials handling application, MHSS can be adapted to other industries in which material accountability is important. In this paper, emphasis is on the simulation methodology of the MHSS program with application to the nuclear material safeguards problem. (auth)

  14. 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.

  15. Evaluation of storage/transportation options to support criteria development for the Phase I MRS [Monitored Retrievable Storage

    International Nuclear Information System (INIS)

    Sorenson, K.B.; Brown, N.N.; Bennett, P.C.; Lake, W.

    1991-01-01

    The Department of Energy's (DOE) Office of Civilian Waste Management (OCRWM) plans to develop an interim storage facility to enable acceptance of spent fuel in 1998. It is estimated that this interim storage facility would be needed for about two years. A Monitored Retrievable Storage (MRS) facility is anticipated in 2000 and a repository in 2010. Acceptance and transport of spent fuel by DOE/OCRWM in 1998 will require an operating transportation system. Because this interim storage facility is not yet defined, development of an optimally compatible transportation system is not a certainty. In order to assure a transport capability for 1998 acceptance of spent fuel, it was decided that the OCRWM transportation program had to identify likely options for an interim storage facility, including identification of the components needed for compatibility between likely interim storage facility options and transportation. Primary attention was given to existing hardware, although conceptual designs were also considered. A systems-based probabilistic decision model was suggested by Sandia National Laboratories and accepted by DOE/OCRWM's transportation program. Performance of the evaluation task involved several elements of the transportation program. This paper describes the decision model developed to accomplish this task, along with some of the results and conclusions. 1 ref., 4 figs

  16. Transport casks help solve spent fuel interim storage problems

    International Nuclear Information System (INIS)

    Dierkes, P.; Janberg, K.; Baatz, H.; Weinhold, G.

    1980-01-01

    Transport casks can be used as storage modules, combining the inherent safety of passive cooling with the absence of secondary radioactive waste and the flexibility to build up storage capacity according to actual requirements. In the Federal Republic of Germany, transport casks are being developed as a solution to its interim storage problems. Criteria for their design and licensing are outlined. Details are given of the casks and the storage facility. Tests are illustrated. (U.K.)

  17. Criticality Safety Evaluation for 30B and 48X UF6 Cylinders for Transportation and Storage

    International Nuclear Information System (INIS)

    Mokhatri, Homami Zahra; Nematollahi, Mohammadreza; Kamyab, Shahabeddin

    2011-01-01

    30B and 48X cylinders are two standard containers have been used for transportation and storage of uranium hexafluoride with 21/2-ton and 10-ton loading capacity, respectively. For the sake of nuclear safety, the long-term safe storage and transportation of the cylinders are necessary to be concerned. Safe limits in handling and storage of 30B and 48X cylinders from the criticality safety considerations, has been investigated in this paper, by using the MCNP.4C code with ENDF/B-VI library data for the neutron cross sections. An infinite array model (with and without over pack) incorporating an internal H/U ratio of 0.088 was then developed to determine the optimal interstitial moderation. The maximum k eff value for the conditions of optimal interstitial moderation with the premise of no water leakage into the UF 6 cylinder has been shown to be 0.79209 ± 0.0011 for the 30B cylinder and 0.7625±0.0013 for 48X cylinder with 5 wt % 235 U enrichment. Based on this evaluation, the 30B and 48X UF 6 cylinders with 5 wt % 235 U enrichment meet the 10 CFR part 71 criteria for Fissile Class I packages, even in the worst case, and has a Transport Index (TI) of zero for criticality safety purposes

  18. 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

  19. Performance of CASTOR{sup R} HAW Cask Cold Trials for Loading, Transport and Storage of HAW canisters

    Energy Technology Data Exchange (ETDEWEB)

    Wilmsmeier, Marco; Vossnacke, Andre [GNS Gesellschaft fuer Nuklear-Service mbH, Hollestrasse 7A, D-45127 Essen (Germany)

    2008-07-01

    On the basis of reprocessing contracts, concluded between the German Nuclear Utilities (GNUs) and the reprocessing companies in France (AREVA NC) and the UK (Nuclear Decommissioning Authority), GNS has the task to return the resulting residues to Germany. The high active waste (HAW) residuals from nuclear fuel reprocessing are vitrified and filled into steel cans, the HAW canisters. According to reprocessing contracts the equivalent number of HAW canisters to heavy metals delivered has to be returned to the country of origin and stored at an interim storage facility where applicable. The GNS' CASTOR{sup R} HAW casks are designed and licensed to fulfil the requirements for transport and long-term storage of HAW canisters. The new cask type CASTOR{sup R} HAW28M is capable of storing 28 HAW canisters with a maximum thermal power of 56 kW in total. Prior to the first active cask loading at a reprocessing facility it is required to demonstrate all important handling steps with the CASTOR{sup R} HAW28M cask according to a specific and approved sequence plan (MAP). These cold trials have to be carried out at the cask loading plant and at the reception area of an interim storage facility in Gorleben (TBL-G), witnessed by the licensing authorities and their independent experts. At transhipment stations GNS performs internal trials to demonstrate safe handling. A brand-new, empty CASTOR{sup R} HAW28M cask has been shipped from the GNS cask assembly facility in Muelheim to the TBL-G for cold trials. With this cask, GNS has to demonstrate the transhipment of casks at the Dannenberg transfer station from rail to road, transport to and reception at the TBL-G as well as incoming dose rate and contamination measurements and preparation for storage. After removal of all shock absorbers with a cask specific handling frame, tilting operation and assembly of the secondary lid with a pressure sensor, the helium leak tightness and 'Block-mass' tests have to be carried out

  20. 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

  1. 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.

  2. Intermodal transport and distribution patterns in ports relationship to hinterland

    Science.gov (United States)

    Dinu, O.; Dragu, V.; Ruscă, F.; Ilie, A.; Oprea, C.

    2017-08-01

    It is of great importance to examine all interactions between ports, terminals, intermodal transport and logistic actors of distribution channels, as their optimization can lead to operational improvement. Proposed paper starts with a brief overview of different goods types and allocation of their logistic costs, with emphasis on storage component. Present trend is to optimize storage costs by means of port storage area buffer function, by making the best use of free storage time available, most of the ports offer. As a research methodology, starting point is to consider the cost structure of a generic intermodal transport (storage, handling and transport costs) and to link this to intermodal distribution patterns most frequently cast-off in port relationship to hinterland. The next step is to evaluate storage costs impact on distribution pattern selection. For a given value of port free storage time, a corresponding value of total storage time in the distribution channel can be identified, in order to substantiate a distribution pattern shift. Different scenarios for transport and handling costs variation, recorded when distribution pattern shift, are integrated in order to establish the reaction of the actors involved in port related logistic and intermodal transport costs evolution is analysed in order to optimize distribution pattern selection.

  3. Integrated System for Retrieval, Transportation and Consolidated Storage of Used Nuclear Fuel in the US - 13312

    International Nuclear Information System (INIS)

    Bracey, William; Bondre, Jayant; Shelton, Catherine; Edmonds, Robert

    2013-01-01

    The current inventory of used nuclear fuel assemblies (UNFAs) from commercial reactor operations in the United States totals approximately 65,000 metric tons or approximately 232,000 UNFAs primarily stored at the 104 operational reactors in the US and a small number of decommissioned reactors. This inventory is growing at a rate of roughly 2,000 to 2,400 metric tons each year, (Approx. 7,000 UNFAs) as a result of ongoing commercial reactor operations. Assuming an average of 10 metric tons per storage/transportation casks, this inventory of commercial UNFAs represents about 6,500 casks with an additional of about 220 casks every year. In January 2010, the Blue Ribbon Commission (BRC) [1] was directed to conduct a comprehensive review of policies for managing the back end of the nuclear fuel cycle and recommend a new plan. The BRC issued their final recommendations in January 2012. One of the main recommendations is for the United States to proceed promptly to develop one or more consolidated storage facilities (CSF) as part of an integrated, comprehensive plan for safely managing the back end of the nuclear fuel cycle. Based on its extensive experience in storage and transportation cask design, analysis, licensing, fabrication, and operations including transportation logistics, Transnuclear, Inc. (TN), an AREVA Subsidiary within the Logistics Business Unit, is engineering an integrated system that will address the complete process of commercial UNFA management. The system will deal with UNFAs in their current storage mode in various configurations, the preparation including handling and additional packaging where required and transportation of UNFAs to a CSF site, and subsequent storage, operation and maintenance at the CSF with eventual transportation to a future repository or recycling site. It is essential to proceed by steps to ensure that the system will be the most efficient and serve at best its purpose by defining: the problem to be resolved, the criteria to

  4. Integrated System for Retrieval, Transportation and Consolidated Storage of Used Nuclear Fuel in the US - 13312

    Energy Technology Data Exchange (ETDEWEB)

    Bracey, William; Bondre, Jayant; Shelton, Catherine [Transnuclear, Inc., 7135 Minstrel Way Suite 300, Columbia MD 21045 (United States); Edmonds, Robert [AREVA Federal Services, 7207 IBM Drive, Charlotte NC 28262 (United States)

    2013-07-01

    The current inventory of used nuclear fuel assemblies (UNFAs) from commercial reactor operations in the United States totals approximately 65,000 metric tons or approximately 232,000 UNFAs primarily stored at the 104 operational reactors in the US and a small number of decommissioned reactors. This inventory is growing at a rate of roughly 2,000 to 2,400 metric tons each year, (Approx. 7,000 UNFAs) as a result of ongoing commercial reactor operations. Assuming an average of 10 metric tons per storage/transportation casks, this inventory of commercial UNFAs represents about 6,500 casks with an additional of about 220 casks every year. In January 2010, the Blue Ribbon Commission (BRC) [1] was directed to conduct a comprehensive review of policies for managing the back end of the nuclear fuel cycle and recommend a new plan. The BRC issued their final recommendations in January 2012. One of the main recommendations is for the United States to proceed promptly to develop one or more consolidated storage facilities (CSF) as part of an integrated, comprehensive plan for safely managing the back end of the nuclear fuel cycle. Based on its extensive experience in storage and transportation cask design, analysis, licensing, fabrication, and operations including transportation logistics, Transnuclear, Inc. (TN), an AREVA Subsidiary within the Logistics Business Unit, is engineering an integrated system that will address the complete process of commercial UNFA management. The system will deal with UNFAs in their current storage mode in various configurations, the preparation including handling and additional packaging where required and transportation of UNFAs to a CSF site, and subsequent storage, operation and maintenance at the CSF with eventual transportation to a future repository or recycling site. It is essential to proceed by steps to ensure that the system will be the most efficient and serve at best its purpose by defining: the problem to be resolved, the criteria to

  5. 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

  6. 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

  7. Fuel transporting device

    International Nuclear Information System (INIS)

    Shiratori, Hirozo.

    1979-01-01

    Purpose: In a liquid-metal cooled reactor, to reduce the waiting time of fuel handling apparatuses and shorten the fuel exchange time. Constitution: A fuel transporting machine is arranged between a reactor vessel and an out-pile storage tank, thereby dividing the transportation line of the pot for contracting fuel and transporting the same. By assuming such a construction, the flow of fuel transportation which has heretofore been carried out through fuel transportation pipes is not limited to one direction but the take-out of fuels from the reactor and the take-in thereof from the storage tank can be carried out constantly, and much time is not required for fuel exchange. (Kamimura, M.)

  8. Advanced surveillance technologies for used fuel long-term storage and transportation - 59032

    International Nuclear Information System (INIS)

    Tsai, Hanchung; Liu, Yung Y.; Nutt, Mark; Shuler, James

    2012-01-01

    Utilities worldwide are using dry-cask storage systems to handle the ever-increasing number of discharged fuel assemblies from nuclear power plants. In the United States and possibly elsewhere, this trend will continue until an acceptable disposal path is established. The recent Fukushima nuclear power plant accident, specifically the events with the storage pools, may accelerate the drive to relocate more of the used fuel assemblies from pools into dry casks. Many of the newer cask systems incorporate dual-purpose (storage and transport) or multiple-purpose (storage, transport, and disposal) canister technologies. With the prospect looming for very long term storage - possibly over multiple decades - and deferred transport, condition- and performance-based aging management of cask structures and components is now a necessity that requires immediate attention. From the standpoint of consequences, one of the greatest concerns is the rupture of a substantial number of fuel rods that would affect fuel retrievability. Used fuel cladding may become susceptible to rupture due to radial-hydride-induced embrittlement caused by water-side corrosion during the reactor operation and subsequent drying/transfer process, through early stage of storage in a dry cask, especially for high burnup fuels. Radio frequency identification (RFID) is an automated data capture and remote-sensing technology ideally suited for monitoring sensitive assets on a long-term, continuous basis. One such system, called ARG-US, has been developed by Argonne National Laboratory for the U.S. Department of Energy's Packaging Certification Program for tracking and monitoring drums containing sensitive nuclear and radioactive materials. The ARG-US RFID system is versatile and can be readily adapted for dry-cask monitoring applications. The current built-in sensor suite consists of seal, temperature, humidity, shock, and radiation sensors. With the universal asynchronous receiver/transmitter interface in

  9. Hydrogen transport and storage in engineered glass microspheres

    Energy Technology Data Exchange (ETDEWEB)

    Rambach, G.D.

    1995-04-18

    New, high strength glass microspheres filled with pressurized hydrogen exhibit densities which make them attractive for bulk hydrogen storage and transport. The membrane tensile stress at failure for our engineered glass microspheres is about 150,000 psi, permitting a threefold increase in pressure limit and storage capacity above commercial microspheres, which have been studied a decade ago and have been shown to fail at membrane stresses of 50,000 psi. Our analysis relating glass microspheres for hydrogen transport with infrastructure and economics, indicate that pressurized microspheres can be economically competitive with other forms of bulk rail and truck transport such as pressurized tube transports and liquid hydrogen trailers.

  10. Capabilities for processing shipping casks at spent fuel storage facilities

    International Nuclear Information System (INIS)

    Baker, W.H.; Arnett, L.M.

    1978-01-01

    Spent fuel is received at a storage facility in heavily shielded casks transported either by rail or truck. The casks are inspected, cooled, emptied, decontaminated, and reshipped. The spent fuel is transferred to storage. The number of locations or space inside the building provided to perform each function in cask processing will determine the rate at which the facility can process shipping casks and transfer spent fuel to storage. Because of the high cost of construction of licensed spent fuel handling and storage facilities and the difficulty in retrofitting, it is desirable to correctly specify the space required. In this paper, the size of the cask handling facilities is specified as a function of rate at which spent fuel is received for storage. The minimum number of handling locations to achieve a given throughput of shipping casks has been determined by computer simulation of the process. The simulation program uses a Monte Carlo technique in which a large number of casks are received at a facility with a fixed number of handling locations in each process area. As a cask enters a handling location, the time to process the cask at that location is selected at random from the distribution of process time. Shipping cask handling times are based on experience at the General Electric Storage Facility, Morris, Illinois. Shipping cask capacity is based on the most recent survey available of the expected capability of reactors to handle existing rail or truck casks

  11. Integrated spent fuel storage and transportation system using NUHOMS

    International Nuclear Information System (INIS)

    Lehnert, R.; McConaghy, W.; Rosa, J.

    1990-01-01

    As utilities with nuclear power plants face increasing near term spent fuel store needs, various systems for dry storage such as the NUTECH Horizontal Modular Storage (NUHOMS) system are being implemented to augment existing spent fuel pool storage capacities. These decisions are based on a number of generic and utility specific considerations including both short term and long term economics. Since the US Department of Energy (DOE) is tasked by the Nuclear Waste Policy Act with the future responsibility of transporting spent fuel from commercial nuclear power plants to a Monitored Retrievable Storage (MRS) facility anchor a permanent geologic repository, the interfaces between the utilities at-reactor dry storage system and the DOE's away-from-reactor transportation system become important. This paper presents a study of the interfaces between the current at-reactor NUHOMS system and the future away-from-reactor DOE transportation system being developed under the Office of Civilian Radioactive Waste Management (OCRWM) program. 7 refs., 9 figs., 1 tab

  12. 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

  13. Mockup of an automated material transport system for remote handling

    International Nuclear Information System (INIS)

    Porter, M.L.

    1992-01-01

    The automated material transport system (AMTS) was conceived for the transport of samples within the material and process control laboratory (MPCL), located in the plutonium processing building of the special isotope separation (SIS) facility. The MPCL was designed with a dry sample handling laboratory and a wet chemistry analysis laboratory. Each laboratory contained several processing glove boxes. The function of the AMTS was to automate the handling of materials, multiple process samples, and bulky items between process stations with a minimum of operator intervention and with a minimum of waiting periods and nonproductive activities. The AMTS design requirements, design verification mockup plan, and AMTS mockup procurement specification were established prior to cancellation of the SIS project. Due to the AMTS's flexibility, the need for technology development, and applicability to other US Department of Energy facilities, mockup of the AMTS continued. This paper discusses the system design features, capabilities, and results of initial testing

  14. An Indian perspective for transportation and storage of spent fuel

    International Nuclear Information System (INIS)

    Dey, P.K.

    2005-01-01

    The spent fuel discharged from the reactors are temporarily stored at the reactor pool. After a certain cooling time, the spent fuel is moved to the storage locations either on or off reactor site depending on the spent fuel management strategy. As India has opted for a closed fuel cycle for its nuclear energy development, reprocessing of the spent fuel, recycling of the reprocessed plutonium and uranium and disposal of the wastes from the reprocessing operations forms the spent fuel management strategy. Since the reprocessing operations are planned to match the nuclear energy programme, storage of the spent fuel in ponds are adopted prior to reprocessing. Transport of the spent fuel to the storage locations are carried out adhering to international and national guide lines. India is having 14 operating power reactors and three research reactors. The spent fuel from the two safeguarded BWRs are stored at-reactor (AR) storage pond. A separate wet storage facility away-from-reactor (AFR) has been designed, constructed and made operational since 1991 for additional fuel storage. Storage facilities are provided in ARs at other reactor locations to cater to 10 reactor-years of operation. A much lower capacity spent fuel storage is provided in reprocessing plants on the same lines of AR fuel storage design. Since the reprocessing operations are carried out on a need basis, to cater to the increased storage needs two new spent fuel storage facilities (SFSF) are being designed and constructed near the existing nuclear plant sites. India has mastered the technology for design, construction and operation of wet spent fuel storage facility meeting all the international standards Wet storage of the spent fuel is the most commonly adopted mode all over the world. Recently an alternate mode viz. dry storage has also been considered. India has designed, constructed and operated lead shielded dry storage casks and is operational at one site. A dry storage cask made of concrete

  15. Sediment transport-storage relations for degrading, gravel bed channels

    Science.gov (United States)

    Thomas E. Lisle; Michael Church

    2002-01-01

    In a drainage network,sediment is transferred through a series of channel/valley segments (natural sediment storage reservoirs) that are distinguished from their neighbors by their particular capacity to store and transport sediment. We propose that the sediment transport capacity of each reservoir is a unique positive function of storage volume, which influences...

  16. 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.

  17. 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

  18. A central spent fuel storage in Sweden

    International Nuclear Information System (INIS)

    Gustafsson, B.; Hagberth, R.

    1978-01-01

    A planned central spent fuel storage facility in Sweden is described. The nuclear power program and quantities of spent fuel generated in Sweden is discussed. A general description of the facility is given with emphasis on the lay-out of the buildings, transport casks and fuel handling. Finally a possible design of a Swedish transportation system is discussed. (author)

  19. Universal storage/transport/disposal packages

    International Nuclear Information System (INIS)

    Smith, M.L.

    1992-01-01

    In this paper a concept for a more robust Engineered Barrier System (EBS) that is part of an integrated waste management system is presented. This integrated system uses a thick walled metal package as the basic component of an integrated system for utility site storage, MRS storage, transportation, and disposal. Overpacks are used where necessary to supplement the basic package in each application. This integrated system combines the advantages of a robust EBS (improved margin and confidence in the repository) with a systems approach that can simplify the waste management system and reduce costs

  20. Research on crude oil storage and transportation based on optimization algorithm

    Science.gov (United States)

    Yuan, Xuhua

    2018-04-01

    At present, the optimization theory and method have been widely used in the optimization scheduling and optimal operation scheme of complex production systems. Based on C++Builder 6 program development platform, the theoretical research results are implemented by computer. The simulation and intelligent decision system of crude oil storage and transportation inventory scheduling are designed. The system includes modules of project management, data management, graphics processing, simulation of oil depot operation scheme. It can realize the optimization of the scheduling scheme of crude oil storage and transportation system. A multi-point temperature measuring system for monitoring the temperature field of floating roof oil storage tank is developed. The results show that by optimizing operating parameters such as tank operating mode and temperature, the total transportation scheduling costs of the storage and transportation system can be reduced by 9.1%. Therefore, this method can realize safe and stable operation of crude oil storage and transportation system.

  1. AT-400A Type B transportation and storage package

    International Nuclear Information System (INIS)

    Cockrell, G.D.; Franklin, K.W.

    1995-01-01

    This paper discusses the design considerations for the AT-400A container which will meet the requirements for the transportation and long-term storage of plutonium pits. The AT-400A was designed by a joint effort between Sandia National Labs, Los Alamos National Labs, Lawrence Livermore National Laboratory, and Mason and Hanger Silas Mason Co., Inc.. The paper will outline the problems and impact on the design of the container necessitated by the need to meet DOT TYPE B transportation requirements and undefined requirements for the interim and long-term storage of pits. Areas covered will include: (1) determining the storage requirements, (2) surveillance program for interim storage, and (3) impact of storage requirements on the containment vessel and inner fixturing design

  2. Contact-handled transuranic transportation system structural analysis

    International Nuclear Information System (INIS)

    Lamoreaux, G.H.; Romesberg, L.E.; Sutherland, S.H.; Duffey, T.A.

    1980-01-01

    The Transuranic Package Transporter (TRUPACT) is a Type B overpack being developed for contact-handled transuranic waste. End-on, side-on, and corner impacts of the loaded TRUPACT due to a 9 m drop onto an unyielding surface have been analyzed. In each case the analyses progressed from simplified hand approaches to successively more complex finite element calculations. The first analysis of each series represents the hand calculations which were carried out to obtain initial thicknesses of foam. The remaining analyses were performed using the dynamic and nonlinear analysis capabilities of ADINA, a structural analysis finite element computer program

  3. Storage of hazardous substances in bonded warehouses

    International Nuclear Information System (INIS)

    Villalobos Artavia, Beatriz

    2008-01-01

    A variety of special regulations exist in Costa Rica for registration and transport of hazardous substances; these set the requirements for entry into the country and the security of transport units. However, the regulations mentioned no specific rules for storing hazardous substances. Tax deposits have been the initial place where are stored the substances that enter the country.The creation of basic rules that would be regulating the storage of hazardous substances has taken place through the analysis of regulations and national and international laws governing hazardous substances. The regulatory domain that currently exists will be established with a field research in fiscal deposits in the metropolitan area. The storage and security measures that have been used by the personnel handling the substances will be identified to be putting the reality with that the hazardous substances have been handled in tax deposits. A rule base for the storage of hazardous substances in tax deposits can be made, protecting the safety of the environment in which are manipulated and avoiding a possible accident causing a mess around. The rule will have the characteristics of the storage warehouses hazardous substances, such as safety standards, labeling standards, infrastructure features, common storage and transitional measures that must possess and meet all bonded warehouses to store hazardous substances. (author) [es

  4. 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

  5. Influence of geologic layering on heat transport and storage in an aquifer thermal energy storage system

    Science.gov (United States)

    Bridger, D. W.; Allen, D. M.

    2014-01-01

    A modeling study was carried out to evaluate the influence of aquifer heterogeneity, as represented by geologic layering, on heat transport and storage in an aquifer thermal energy storage (ATES) system in Agassiz, British Columbia, Canada. Two 3D heat transport models were developed and calibrated using the flow and heat transport code FEFLOW including: a "non-layered" model domain with homogeneous hydraulic and thermal properties; and, a "layered" model domain with variable hydraulic and thermal properties assigned to discrete geological units to represent aquifer heterogeneity. The base model (non-layered) shows limited sensitivity for the ranges of all thermal and hydraulic properties expected at the site; the model is most sensitive to vertical anisotropy and hydraulic gradient. Simulated and observed temperatures within the wells reflect a combination of screen placement and layering, with inconsistencies largely explained by the lateral continuity of high permeability layers represented in the model. Simulation of heat injection, storage and recovery show preferential transport along high permeability layers, resulting in longitudinal plume distortion, and overall higher short-term storage efficiencies.

  6. Handling and transport problems (1960); Problemes de manipulation et de transport (1960)

    Energy Technology Data Exchange (ETDEWEB)

    Pomarola, J; Savouyaud, J [Commissariat a l' Energie Atomique, Saclay (France).Centre d' Etudes Nucleaires

    1960-07-01

    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) [French] I. La manipulation et le transport des dechets radioactifs presentent des dangers d'irradiation et de contamination. Il est necessaire: - d'edicter des consignes speciales applicables a l'enlevement et au transport des dechets dans les centres ou de centre a centre; - de confier les transports a un groupe dont relevent des equipes specialisees; - on examine l'organisation, les moyens, le rendement de ces equipes. II. Certains transports sont particulierement dangereux et necessitent des engins speciaux et des installations fixes. C'est le cas, notamment de l'evacuation des liquides tres actifs. On decrit: - un engin de transport compose d'un ensemble a tracteur semi-remorque et d'un recipient qui contient 500 litres de liquide dont l'activite peut atteindre 1000 C/l; - les operations de transvasement, l'acheminement de l'engin, les precautions prises. (auteur)

  7. STP-ECRTS - THERMAL AND GAS ANALYSES FOR SLUDGE TRANSPORT AND STORAGE CONTAINER (STSC) STORAGE AT T PLANT

    Energy Technology Data Exchange (ETDEWEB)

    CROWE RD; APTHORPE R; LEE SJ; PLYS MG

    2010-04-29

    The Sludge Treatment Project (STP) is responsible for the disposition of sludge contained in the six engineered containers and Settler tank within the 105-K West (KW) Basin. The STP is retrieving and transferring sludge from the Settler tank into engineered container SCS-CON-230. Then, the STP will retrieve and transfer sludge from the six engineered containers in the KW Basin directly into a Sludge Transport and Storage Containers (STSC) contained in a Sludge Transport System (STS) cask. The STSC/STS cask will be transported to T Plant for interim storage of the STSC. The STS cask will be loaded with an empty STSC and returned to the KW Basin for loading of additional sludge for transportation and interim storage at T Plant. CH2MHILL Plateau Remediation Company (CHPRC) contracted with Fauske & Associates, LLC (FAI) to perform thermal and gas generation analyses for interim storage of STP sludge in the Sludge Transport and Storage Container (STSCs) at T Plant. The sludge types considered are settler sludge and sludge originating from the floor of the KW Basin and stored in containers 210 and 220, which are bounding compositions. The conditions specified by CHPRC for analysis are provided in Section 5. The FAI report (FAI/10-83, Thermal and Gas Analyses for a Sludge Transport and Storage Container (STSC) at T Plant) (refer to Attachment 1) documents the analyses. The process considered was passive, interim storage of sludge in various cells at T Plant. The FATE{trademark} code is used for the calculation. The results are shown in terms of the peak sludge temperature and hydrogen concentrations in the STSC and the T Plant cell. In particular, the concerns addressed were the thermal stability of the sludge and the potential for flammable gas mixtures. This work was performed with preliminary design information and a preliminary software configuration.

  8. Plutonium storage criteria

    Energy Technology Data Exchange (ETDEWEB)

    Chung, D. [Scientech, Inc., Germantown, MD (United States); Ascanio, X. [Dept. of Energy, Germantown, MD (United States)

    1996-05-01

    The Department of Energy has issued a technical standard for long-term (>50 years) storage and will soon issue a criteria document for interim (<20 years) storage of plutonium materials. The long-term technical standard, {open_quotes}Criteria for Safe Storage of Plutonium Metals and Oxides,{close_quotes} addresses the requirements for storing metals and oxides with greater than 50 wt % plutonium. It calls for a standardized package that meets both off-site transportation requirements, as well as remote handling requirements from future storage facilities. The interim criteria document, {open_quotes}Criteria for Interim Safe Storage of Plutonium-Bearing Solid Materials{close_quotes}, addresses requirements for storing materials with less than 50 wt% plutonium. The interim criteria document assumes the materials will be stored on existing sites, and existing facilities and equipment will be used for repackaging to improve the margin of safety.

  9. Transport of radioactive materials

    International Nuclear Information System (INIS)

    1988-07-01

    The norm which establishes the requirements of radiation protection and safety related to the transport of radioactive materials, aiming to keep a suitable control level of eventual exposure of personnels, materials and environment of ionizing radiation, including: specifications on radioactive materials for transport, selection of package type; specification of requirements of the design and assays of acceptance of packages; disposal related to the transport; and liability and administrative requirements, are presented. This norm is applied to: truckage, water carriage and air service; design, fabrication, assays and mantenaince of packages; preparation, despatching, handling, loading storage in transition and reception in the ultimate storage of packages; and transport of void packages which have been contained radioactive materials. (M.C.K.) [pt

  10. From producer to consumer: greenhouse tomato quality as affected by variety, maturity stage at harvest, transport conditions, and supermarket storage.

    Science.gov (United States)

    Verheul, Michèl J; Slimestad, Rune; Tjøstheim, Irene Holta

    2015-05-27

    Possible causes for differences in quality traits at the time of buying were studied in two widely different red tomato types. Three maturity stages were harvested from commercial greenhouses and transferred immediately to controlled environments simulating different storage, transport, and supermarket conditions. Results show significant differences in development of color, fruit firmness, contents of soluble solids (SSC), titratable acids (TTA), phenolics, and carotenoids from harvest to sale, as related to postharvest conditions. Fruit firmness, SSC, and TTA of vine-ripened red cherry tomatoes was 30, 55 and 11% higher than for those harvested at breakers and ripened to red. Temperature, light, UVC radiation, or ethylene during 4 days transport affected tomato quality traits, and differences persisted during 3 weeks of supermarket storage. Ethylene exposure gave a 3.7-fold increase in lycopene content in cherry tomatoes, whereas UVC hormesis revealed a 6-fold increase compared with the control. Results can be used to update recommendations concerning optimal handling.

  11. An optimized cask technology for conditioning, transportation and long term interim storage of 'End of Life' nuclear waste

    International Nuclear Information System (INIS)

    Lefort-Mary, Florence; Clement, Gilles; Lamouroux, Christine; Dumont, Bruno

    2016-01-01

    When preparing for the decommissioning of a nuclear facility, during its 'end of life' management and while performing the actual dismantling operations, one has to consider a large diversity of nuclear waste in term of types, volumes and activities. Customers are frequently faced with the obligation to undertake multiple and costly waste management operations including handling, reconditioning or re-transferring from one package to another, for example when moving from on-site storage to transportation. To address this issue, a new - highly flexible - cask system named TN R MW is being developed. This cask has a total weight of 10 T and is compliant with the 2012 IAEA regulations. It is developed on a flexible concept basis, adaptable to the various nuclear needs, including: from IP2 to B(U) / B(U)F; on-site/ international transportation; long term interim storage. Licensing and manufacturing of number of items of this TN R MW family is underway. (authors)

  12. 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.

  13. Storage Optimization for Export Containers in the Port of Izmir

    Directory of Open Access Journals (Sweden)

    Deniz Türsel Eliiyi

    2013-07-01

    Full Text Available In this study, we consider a real-life export container storage problem at an important container terminal in the Port of Izmir, Turkey. Currently, the container storage decisions at the port are taken by operators manually, which leads to continuous unnecessary re-handling movements of the containers. High transportation costs, waste of time, and inefficient capacity utilization in the container storage area are the consequences of non-optimal decisions. The main goal of this study is to minimize the transportation costs and the number of re-handling moves while storing the export containers at the terminal yard. We formulate the problem in two stages. While the first stage assigns the containers of the same vessel to a group of yard bays via an optimization model, the second stage decides on the exact location of each container with the help of an efficient heuristic approach. The experimental results with real data are presented and discussed.

  14. Constor steel concrete sandwich cask concept for transport and storage of spent nuclear fuel

    International Nuclear Information System (INIS)

    Diersch, R.; Dreier, G.; Gluschke, K.; Zubkov, A.; Danilin, B.; Fromzel, V.

    1998-01-01

    A spent nuclear fuel transport and storage sandwich cask concept has been developed together with the Russian company CKTI. Special consideration was given to an economical and effective way of manufacturing by using conventional mechanical engineering technologies and common materials. The main objective of this development was to fabricate these casks in countries not having highly specialized industries. Nevertheless, this sandwich cask concept fulfills both the internationally valid IAEA criteria for transportation and the German criteria for long-term intermediate storage. The basic cask concept has been designed for adaptation to different spent fuel specifications as well as handling conditions in the NPP. Recently, adaptations have been made for spent fuel from the RBMK and VVER reactors, and also for BWR spent fuel. The analyses of nuclear and thermal behaviour as well as of strength according to IAEA examination requirements (9-m-drop, 1-m-pin drop, 800 deg. C-fire test) and of the behaviour during accident scenarios at the storage site (drop, fire, gas cloud explosion, side impact) were carried out by means of recognized calculation methods and programmes. In a special experimental programme, the mechanical and thermodynamic properties of heavy concrete were examined and the reference values required for safety analyses were determined. The results of the safety analysis after drop tests according to IAEA-regulations as well as after 1 m-drops at the storage site were confirmed by means of a test programme using a scale model. The fabrication technology has been tested with help of a half scale cask model. The model has been prefabricated in Russia and completed in Germany. It has been shown that the CONSTOR cask can be fabricated in an effective and economic way. (authors)

  15. A software tool integrated risk assessment of spent fuel transpotation and storage

    Energy Technology Data Exchange (ETDEWEB)

    Yun, Mi Rae; Almomani, Belal; Ham, Jae Hyun; Kang, Hyun Gook [Dept. of Nuclear and Quantum Engineering, Korea Advanced Institute of Science and Technology, Daejeon (Korea, Republic of); Christian, Robby [Dept. of Mechanical, Aerospace, and Nuclear Engineering, Rensselaer Polytechnic Institute, Troy (Korea, Republic of); Kim, Bo Gyung [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of); Lee, Sang Hoon [Dept. of Mechanical and Automotive Engineering, Keimyung University, Daegu (Korea, Republic of)

    2017-06-15

    When temporary spent fuel storage pools at nuclear power plants reach their capacity limit, the spent fuel must be moved to an alternative storage facility. However, radioactive materials must be handled and stored carefully to avoid severe consequences to the environment. In this study, the risks of three potential accident scenarios (i.e., maritime transportation, an aircraft crashing into an interim storage facility, and on-site transportation) associated with the spent fuel transportation process were analyzed using a probabilistic approach. For each scenario, the probabilities and the consequences were calculated separately to assess the risks: the probabilities were calculated using existing data and statistical models, and the consequences were calculated using computation models. Risk assessment software was developed to conveniently integrate the three scenarios. The risks were analyzed using the developed software according to the shipment route, building characteristics, and spent fuel handling environment. As a result of the risk analysis with varying accident conditions, transportation and storage strategies with relatively low risk were developed for regulators and licensees. The focus of this study was the risk assessment methodology; however, the applied model and input data have some uncertainties. Further research to reduce these uncertainties will improve the accuracy of this mode.

  16. A software tool integrated risk assessment of spent fuel transpotation and storage

    International Nuclear Information System (INIS)

    Yun, Mi Rae; Almomani, Belal; Ham, Jae Hyun; Kang, Hyun Gook; Christian, Robby; Kim, Bo Gyung; Lee, Sang Hoon

    2017-01-01

    When temporary spent fuel storage pools at nuclear power plants reach their capacity limit, the spent fuel must be moved to an alternative storage facility. However, radioactive materials must be handled and stored carefully to avoid severe consequences to the environment. In this study, the risks of three potential accident scenarios (i.e., maritime transportation, an aircraft crashing into an interim storage facility, and on-site transportation) associated with the spent fuel transportation process were analyzed using a probabilistic approach. For each scenario, the probabilities and the consequences were calculated separately to assess the risks: the probabilities were calculated using existing data and statistical models, and the consequences were calculated using computation models. Risk assessment software was developed to conveniently integrate the three scenarios. The risks were analyzed using the developed software according to the shipment route, building characteristics, and spent fuel handling environment. As a result of the risk analysis with varying accident conditions, transportation and storage strategies with relatively low risk were developed for regulators and licensees. The focus of this study was the risk assessment methodology; however, the applied model and input data have some uncertainties. Further research to reduce these uncertainties will improve the accuracy of this mode

  17. Analysis of fuel-handling incidents (safety analysis detailed report no. 5). PEC Brasimone reactor design basis accidents

    Energy Technology Data Exchange (ETDEWEB)

    1988-01-15

    The features covered by this report deal with the equipment and cells in which the handling, examination, measurement, conditioning and storage of core elements are carried out. The operations covered range from the receiving of new element shipments to their insertion in the vessel (excluding handling inside the vessel itself, which is covered in report no. 2) and removal of the spent-elements from the vessel, transfer to their final storage and their ultimate loading into containers for transport outside the plant. The incident analysis along the path of the spent fuel was conducted with the same method adopted for other plant systems. It is treated separately here because the operation of the handling system is practically autonomous from reactor operation.

  18. German Approach for the Transport of Spent Fuel Packages after Interim Storage

    International Nuclear Information System (INIS)

    Wille, Frank; Wolff, Dietmar; Droste, Bernhard; Voelzke, Holger

    2014-01-01

    In Germany the concept of dry interim storage of spent nuclear fuel in dual purpose metal casks is implemented, currently for periods of up to 40 years. The casks being used have an approved package design in accordance with the international transport regulations. The license for dry storage is granted on the German Atomic Energy Act with respect to the recently (in 2012) revised 'Guidelines for dry cask storage of spent nuclear fuel and heat-generating waste' by the German Waste management Commission (ESK) which are very similar to the former RSK (reactor safety commission) guidelines. For transport on public routes between or after long term interim storage periods, it has to be ensured that the transport and storage casks fulfil the specifications of the transport approval or other sufficient properties which satisfy the proofs for the compliance of the safety objectives at that time. In recent years the validation period of transport approval certificates for manufactured, loaded and stored packages were discussed among authorities and applicants. A case dependent system of 3, 5 and 10 years was established. There are consequences for the safety cases in the Package Design Safety Report including evaluation of long term behavior of components and specific operating procedures of the package. Present research and knowledge concerning the long term behavior of transport and storage cask components have to be consulted as well as experiences from interim cask storage operations. Challenges in the safety assessment are e.g. the behavior of aged metal and elastomeric seals under IAEA test conditions to ensure that the results of drop tests can be transferred to the compliance of the safety objectives at the time of transport after the interim storage period (aged package). Assessment methods for the material compatibility, the behavior of fuel assemblies and the aging behavior of shielding parts are issues as well. This paper describes the state

  19. Risk Assessment of Structural Integrity of Transportation Casks after Extended Storage

    Energy Technology Data Exchange (ETDEWEB)

    Ibarra, Luis; Medina, Ricardo; Yang, Haori

    2018-03-23

    This study assessed the risk of loss of structural integrity of transportation casks and fuel cladding after extended storage. Although it is known that fuel rods discharged from NPPs have a small percentage of rod cladding defects, the behavior of fuel cladding and the structural elements of assemblies during transportation after long-term storage is not well understood. If the fuel degrades during extended storage, it could be susceptible to damage from vibration and impact loads during transport operations, releasing fission-product gases into the canister or the cask interior (NWTRB 2010). Degradation of cladding may occur due to mechanisms associated with hydrogen embrittlement, delayed hydride cracking, low temperature creep, and stress corrosion cracking (SCC) that may affect fuel cladding and canister components after extended storage of hundreds of years. Over extended periods at low temperatures, these mechanisms affect the ductility, strength, and fracture toughness of the fuel cladding, which becomes brittle. For transportation purposes, the fuel may be transferred from storage to shipping casks, or dual-purpose casks may be used for storage and transportation. Currently, most of the transportation casks will be the former case. A risk assessment evaluation is conducted based on results from experimental tests and simulations with advanced numerical models. A novel contribution of this study is the evaluation of the combined effect of component aging and vibration/impact loads in transportation scenarios. The expected levels of deterioration will be obtained from previous and current studies on the effect of aging on fuel and cask components. The emphasis of the study is placed on the structural integrity of fuel cladding and canisters.

  20. Only adding stationary storage to vaccine supply chains may create and worsen transport bottlenecks.

    Science.gov (United States)

    Haidari, Leila A; Connor, Diana L; Wateska, Angela R; Brown, Shawn T; Mueller, Leslie E; Norman, Bryan A; Schmitz, Michelle M; Paul, Proma; Rajgopal, Jayant; Welling, Joel S; Leonard, Jim; Claypool, Erin G; Weng, Yu-Ting; Chen, Sheng-I; Lee, Bruce Y

    2013-01-01

    Although vaccine supply chains in many countries require additional stationary storage and transport capacity to meet current and future needs, international donors tend to donate stationary storage devices far more often than transport equipment. To investigate the impact of only adding stationary storage equipment on the capacity requirements of transport devices and vehicles, we used HERMES (Highly Extensible Resource for Modeling Supply Chains) to construct a discrete event simulation model of the Niger vaccine supply chain. We measured the transport capacity requirement for each mode of transport used in the Niger vaccine cold chain, both before and after adding cold rooms and refrigerators to relieve all stationary storage constraints in the system. With the addition of necessary stationary storage, the average transport capacity requirement increased from 88% to 144% for cold trucks, from 101% to 197% for pickup trucks, and from 366% to 420% for vaccine carriers. Therefore, adding stationary storage alone may worsen or create new transport bottlenecks as more vaccines flow through the system, preventing many vaccines from reaching their target populations. Dynamic modeling can reveal such relationships between stationary storage capacity and transport constraints.

  1. 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

  2. Handle with care

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1965-03-15

    Full text: A film dealing with transport of radioactive materials by everyday means - rail, road, sea and air transport - has been made for IAEA. It illustrates in broad terms some of the simple precautions which should be followed by persons dealing with such materials during shipment. Throughout, the picture stresses the transport regulations drawn up and recommended by the Agency, and in particular the need to carry out carefully the instructions based on these regulations in order to ensure that there is no hazard to the public nor to those who handle radioactive materials in transit and storage. In straightforward language, the film addresses the porter of a goods wagon, an airline cargo clerk, a dockside crane operator, a truck driver and others who load and ship freight. It shows the various types of package used to contain different categories of radioactive substances according to the intensity of the radiation emitted. It also illustrates their robustness by a series of tests involving drops, fires, impact, crushing, etc. Clear instructions are conveyed on what to do in the event of an unlikely accident with any type of package. The film is entitled, 'The Safe Transport of Radioactive Materials', and is No. 3 in the series entitled, 'Handle with Care'. It was made for IAEA through the United Kingdom Atomic Energy Authority by the Film Producers' Guild in the United Kingdom. It is in 16 mm colour, optical sound, with a running time of 20 minutes. It is available for order at $50 either direct from IAEA or through any of its Member Governments. Prints can be supplied in English, French, Russian or Spanish. Copies are also available for adaptation for commentaries in other languages. (author)

  3. Used Fuel Logistics: Decades of Experience with transportation and Interim storage solutions

    Energy Technology Data Exchange (ETDEWEB)

    Orban, G.; Shelton, C.

    2015-07-01

    Used fuel inventories are growing worldwide. While some countries have opted for a closed cycle with recycling, numerous countries must expand their interim storage solutions as implementation of permanent repositories is taking more time than foreseen. In both cases transportation capabilities will have to be developed. AREVA TN has an unparalleled expertise with transportation of used fuel. For more than 50 years AREVA TN has safely shipped more than 7,000 used fuel transport casks. The transportation model that was initially developed in the 1970s has been adapted and enhanced over the years to meet more restrictive regulatory requirements and evolving customer needs, and to address public concerns. The numerous “lessons learned” have offered data and guidance that have allowed for also efficient and consistent improvement over the decades. AREVA TN has also an extensive experience with interim dry storage solutions in many countries on-site but also is working with partners to developed consolidated interim storage facility. Both expertise with storage and transportation contribute to safe, secure and smooth continuity of the operations. This paper will describe decades of experience with a very successful transportation program as well as interim storage solutions. (Author)

  4. 49 CFR 174.82 - General requirements for the handling of placarded rail cars, transport vehicles, freight...

    Science.gov (United States)

    2010-10-01

    ... rail cars, transport vehicles, freight containers, and bulk packages. 174.82 Section 174.82... Placarded Rail Cars, Transport Vehicles and Freight Containers § 174.82 General requirements for the handling of placarded rail cars, transport vehicles, freight containers, and bulk packages. (a) Unless...

  5. The single SNR fuel assembly container (ESBB) to transport unirradiated SNR 300 fuel assemblies

    International Nuclear Information System (INIS)

    Hilbert, F.; Hottenrott, G.

    1998-01-01

    In this paper a new type B(U) package design is presented. The Single SNR Fuel Assembly Container (ESBB) is designed for the transport and storage of a single SNR 300 fuel assembly. This package is the main component for the future interim storage of the fuel assemblies in heavy storage casks. Its benefits are that it is compatible with the Category I transport system of Nuclear Cargo + Service NCS) used in Germany and that it can be easily handled at the current storage locations as well as in an interim storage facility. In total 205 fuel assemblies are currently stored in Hanau, Germany and Dounreay, U.K. Former studies have shown, that heavy transport and storage casks can be handled there only with considerable efforts. But the required category I transport to an interim storage is not reasonably feasible. To overcome these problems the ESBB was designed. It consists of a stainless steel tube with welded bottom, a welded plug as closure system and shock absorbers 26 packages at maximum can be transported in one batch with the NCS security vehicle. The safety analysis shows that the package complies with IAEA 1996. Standard calculations methods and computer codes like HEATING 7.2 (Childs 1993) have been used for the analysis. Criticality safety assessment is based on conservative assumptions as required in IAEA 1996. Drop tests carried out by BAM will be used to verify the design. These tests are scheduled for mid 1998. For the validation of the design prototypes have already been manufactured. Handling tests show that the design complies with the requirements. Preliminary drop tests show that the certification drop tests will be passed positively. (authors)

  6. 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

  7. Thermal performance of a depleted uranium shielded storage, transportation, and disposal package

    International Nuclear Information System (INIS)

    Wix, S.D.; Yoshimura, H.R.

    1994-01-01

    The US Department of Energy (DOE) is responsible for management and disposal of large quantities of depleted uranium (DU) in the DOE complex. Viable economic options for the use and eventual disposal of the material are needed. One possible option is the use of DU as shielding material for vitrified Defense High-Level Waste (DHLW) storage, transportation, and disposal packages. Use of DU as a shielding material provides the potential benefit of disposing of significant quantities of DU during the DHLW storage and disposal process. Two DU package concepts have been developed by Sandia National Laboratories. The first concept is the Storage/Disposal plus Transportation (S/D+T) package. The S/D+T package consists of two major components: a storage/disposal (S/D) container and a transportation overpack. The second concept is the S/D/T package which is an integral storage, transportation, and disposal package. The package concept considered in this analysis is the S/D+T package with seven DHLW waste canisters

  8. 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 ...

  9. 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

  10. Evaluation of the Universal Viral Transport system for long-term storage of virus specimens for microbial forensics.

    Science.gov (United States)

    Hosokawa-Muto, Junji; Fujinami, Yoshihito; Mizuno, Natsuko

    2015-08-01

    Forensic microbial specimens, including bacteria and viruses, are collected at biocrime and bioterrorism scenes. Although it is preferable that the pathogens in these samples are alive and kept in a steady state, the samples may be stored for prolonged periods before analysis. Therefore, it is important to understand the effects of storage conditions on the pathogens contained within such samples. To evaluate the capacity to preserve viable virus and the viral genome, influenza virus was added to the transport medium of the Universal Viral Transport system and stored for over 3 months at various temperatures, after which virus titrations and quantitative analysis of the influenza hemagglutinin gene were performed. Although viable viruses became undetectable 29 days after the medium was stored at room temperature, viruses in the medium stored at 4°C were viable even after 99 days. A quantitative PCR analysis indicated that the hemagglutinin gene was maintained for 99 days at both 4°C and room temperature. Therefore, long-term storage at 4°C has little effect on viable virus and viral genes, so the Universal Viral Transport system can be useful for microbial forensics. This study provides important information for the handling of forensic virus specimens. Copyright © 2015 Elsevier Ltd and Faculty of Forensic and Legal Medicine. All rights reserved.

  11. Assessment of shielding analysis methods, codes, and data for spent fuel transport/storage applications

    International Nuclear Information System (INIS)

    Parks, C.V.; Broadhead, B.L.; Hermann, O.W.; Tang, J.S.; Cramer, S.N.; Gauthey, J.C.; Kirk, B.L.; Roussin, R.W.

    1988-07-01

    This report provides a preliminary assessment of the computational tools and existing methods used to obtain radiation dose rates from shielded spent nuclear fuel and high-level radioactive waste (HLW). Particular emphasis is placed on analysis tools and techniques applicable to facilities/equipment designed for the transport or storage of spent nuclear fuel or HLW. Applications to cask transport, storage, and facility handling are considered. The report reviews the analytic techniques for generating appropriate radiation sources, evaluating the radiation transport through the shield, and calculating the dose at a desired point or surface exterior to the shield. Discrete ordinates, Monte Carlo, and point kernel methods for evaluating radiation transport are reviewed, along with existing codes and data that utilize these methods. A literature survey was employed to select a cadre of codes and data libraries to be reviewed. The selection process was based on specific criteria presented in the report. Separate summaries were written for several codes (or family of codes) that provided information on the method of solution, limitations and advantages, availability, data access, ease of use, and known accuracy. For each data library, the summary covers the source of the data, applicability of these data, and known verification efforts. Finally, the report discusses the overall status of spent fuel shielding analysis techniques and attempts to illustrate areas where inaccuracy and/or uncertainty exist. The report notes the advantages and limitations of several analysis procedures and illustrates the importance of using adequate cross-section data sets. Additional work is recommended to enable final selection/validation of analysis tools that will best meet the US Department of Energy's requirements for use in developing a viable HLW management system. 188 refs., 16 figs., 27 tabs

  12. Design and fabrication of transport/storage packaging for spent fuels

    International Nuclear Information System (INIS)

    Nagahama, Hayao; Kakunai, Haruo

    1989-01-01

    Dry storage in containers is one of several methods for storing spent fuel dischaged from nuclear power plants. Kobe Steel and Transnucleaire (France) have jointly developed large-capacity, safe transport/storage packaging for use in this storage method. This paper outlines the packaging, the manufacturing of a prototype model, and an active storage demonstration test involving the prototype model. (author)

  13. Shielded Canister Transporter

    International Nuclear Information System (INIS)

    Eidem, G.G. Jr.; Fages, R.

    1993-01-01

    The Hanford Waste Vitrification Plant (HWVP) will produce canisters filled with high-level radioactive waste immobilized in borosilicate glass. This report discusses a Shielded Canister Transporter (SCT) which will provide the means for safe transportation and handling of the canisters from the Vitrification Building to the Canister Storage Building (CSB). The stainless steel canisters are 0.61 meters in diameter, 3.0 meters tall, and weigh approximately 2,135 kilograms, with a maximum exterior surface dose rate of 90,000 R/hr. The canisters are placed into storage tubes to a maximum of three tall (two for overpack canisters) with an impact limiter placed at the tube bottom and between each canister. A floor plug seals the top of the storage tube at the operating floor level of the CSB

  14. Thick nickel plating of spent fuel transport and storage casks CASTOR and POLLUX

    International Nuclear Information System (INIS)

    Wilbuer, K.

    1991-01-01

    Spent fuel elements have to be safely handled in containers for transport and storage. These large casks (100-120 t) are made by various firms according to the specifications given by the nuclear plant operator. For shielding and protection of the hazardous material, the casks' inner surface is coated with a nickel plating about 3000 μm thick. The product and the production process are subject to very stringent requirements, due to the hazardous potential of the material to be shipped or stored. Therefore, both the extremely high quality standards to be met by the nickel plating and the dimensions and capability of the plating plant required for the process are problems that cannot be solved by a usual commercial plating plant. The new concept and process that had to be established are explained in the paper. (orig./MM) [de

  15. Flexibility of the BNFL dry storage systems

    International Nuclear Information System (INIS)

    Dickson, R.M.

    1999-01-01

    To widen its range of spent fuel management services, BNFL entered the fuel storage market in 1995; entry was by acquisition rather than internal product development. The need for a transportable product was identified very early, but represents only the first phase of a philosophy of continuous improvement. Strong synergy exists between the new business area and existing fuel handling and transportation expertise, which has been of considerable assistance to the new business. (author)

  16. Evaluation of storage/transportation options to support criteria development for the Phase I MRS

    International Nuclear Information System (INIS)

    Sorenson, K.B.; Brown, N.N.; Bennett, P.C.; Lake, W.

    1991-01-01

    The DOE's Office of Civilian Waste Management (OCRWM) plans to develop an interim storage facility to enable acceptance of spent fuel in 1998. It is estimated that this interim storage facility would be needed for about two years. A Monitored Retrievable Storage (MRS) facility is anticipated in 2000 and a repository in 2010. Acceptance and transport of spent fuel by DOE/OCRWM in 1998 will require an operating transportation system. Because this interim storage facility is not yet defined, development of an optimally compatible transportation system is not a certainty. In order to assure a transport capability for 1998 acceptance of spent fuel, it was decided that the OCRWM transportation program had to identify likely options for an interim storage facility, including identification of the components needed for compatibility between likely interim storage facility options and transportation. Primary attention was given to existing hardware, although conceptual designs were also considered. A systems-based probabilistic decision model was suggested by Sandia National Labs. and accepted by DOE/OCRWM's transportation program. Performance of the evaluation task involved several elements of the transportation program. This paper describes the decision model developed to accomplish this task, along with some of the results and conclusions

  17. Feasibility study: Assess the feasibility of siting a monitored retrievable storage facility

    International Nuclear Information System (INIS)

    King, J.W.

    1993-01-01

    The purpose of phase one of this study are: To understand the waste management system and a monitored retrievable storage facility; and to determine whether the applicant has real interest in pursuing the feasibility assessment process. Contents of this report are: Generating electric power; facts about exposure to radiation; handling storage, and transportation techniques; description of a proposed monitored retrievable storage facility; and benefits to be received by host jurisdiction

  18. Separation of British Gas' transportation and storage business

    International Nuclear Information System (INIS)

    McGregor, G.

    1992-12-01

    In making his substantive reference of the transportation and storage business of British Gas to the Monopolies and Mergers Commission, the Director General of Gas Supply identified the following principal effects adverse to the public interest: ''The absence of provision for the establishment of an independent undertaking to operate the pipe-line system and other facilities used by British Gas for the conveyance and storage of gas which would not be subject to conflicting interests in securing (a) transparency of the prices charged, the costs incurred and the operating methods in respect of the conveyance and storage of gas; (b) proper allocation to various parts of the Gas Supply Business of costs incurred and returns by that business; and (c) protection of information relating to the conveyance and storage of gas from which British Gas might obtain unfair commercial advantage, and thereby avoid the restriction or distortion of competition between British Gas and other persons whose business consists of or includes the supply of gas''. This paper considers the structural issues associated with achieving effective competition and looks at how the relationship between the businesses of supply and transportation might be organised in the short and longer term. (Author)

  19. Thermal performance of a depleted uranium shielded storage, transportation, and disposal package

    International Nuclear Information System (INIS)

    Wix, S.D.; Yoshimura, H.R.

    1994-01-01

    The US Department of Energy (DOE) is responsible for management and disposal of large quantities of depleted uranium (DU) in the DOE complex. Viable economic options for the use and eventual disposal of the material are needed. One possible option is the use of DU as shielding material for vitrified Defense High-Level Waste (DHLW) storage, transportation, and disposal packages. Use of DU as a shielding material provides the potential benefit of disposing of significant quantities of DU during the DHLW storage and disposal process. Two DU package concepts have been developed by Sandia National Laboratories. The first concept is the Storage/Disposal plus Transportation (S/D+T) package. The S/D+T package consists of two major components: a storage/disposal (S/D) container and a transportation overpack. The second concept is the S/D/T package which is an integral storage, transportation, and disposal package. The package concept considered in this analysis is the S/D+T package with seven DHLW waste canisters. The S/D+T package provides shielding and containment for the DHLW waste canisters. The S/D container is intended to be used as an on-site storage and repository disposal container. In this analysis, the S/D container is constructed from a combination of stainless steel and DU. Other material combinations, such as mild steel and DU, are potential candidates. The transportation overpack is used to transport the S/D containers to a final geological repository and is not included in this analysis

  20. Safety analysis of sea transportation of solidified reactor wastes

    International Nuclear Information System (INIS)

    Devell, L.; Edlund, O.; Kjellbert, N.; Grundfelt, B.; Milchert, T.

    1980-06-01

    A central handling and storage facility (ALMA) for low- and medium-level reactor waste from Swedish nuclear power plants is being planned and the transportation to it will be by sea. A safety assessment devoted to the potential environmental impacts from the transportation is presented. (Auth.)

  1. Transport or Store? Synthesizing Flow-based Microfluidic Biochips using Distributed Channel Storage

    DEFF Research Database (Denmark)

    Liu, Chunfeng; Li, Bing; Yao, Hailong

    2017-01-01

    of the performance of biochips. In this paper, we propose the first architectural synthesis framework considering distributed storage constructed temporarily from transportation channels to cache fluid samples. Since distributed storage can be accessed more efficiently than a dedicated storage unit and channels can...... switch between the roles of transportation and storage easily, biochips with this distributed computing architecture can achieve a higher execution efficiency even with fewer resources. Experimental results confirm that the execution efficiency of a bioassay can be improved by up to 28% while the number...

  2. Integrated heat exchanger design for a cryogenic storage tank

    Energy Technology Data Exchange (ETDEWEB)

    Fesmire, J. E.; Bonner, T.; Oliveira, J. M.; Johnson, W. L.; Notardonato, W. U. [NASA Kennedy Space Center, Cryogenics Test Laboratory, NE-F6, KSC, FL 32899 (United States); Tomsik, T. M. [NASA Glenn Research Center, 21000 Brookpark Road, Cleveland, OH 44135 (United States); Conyers, H. J. [NASA Stennis Space Center, Building 3225, SSC, MS 39529 (United States)

    2014-01-29

    Field demonstrations of liquid hydrogen technology will be undertaken for the proliferation of advanced methods and applications in the use of cryofuels. Advancements in the use of cryofuels for transportation on Earth, from Earth, or in space are envisioned for automobiles, aircraft, rockets, and spacecraft. These advancements rely on practical ways of storage, transfer, and handling of liquid hydrogen. Focusing on storage, an integrated heat exchanger system has been designed for incorporation with an existing storage tank and a reverse Brayton cycle helium refrigerator of capacity 850 watts at 20 K. The storage tank is a 125,000-liter capacity horizontal cylindrical tank, with vacuum jacket and multilayer insulation, and a small 0.6-meter diameter manway opening. Addressed are the specific design challenges associated with the small opening, complete modularity, pressure systems re-certification for lower temperature and pressure service associated with hydrogen densification, and a large 8:1 length-to-diameter ratio for distribution of the cryogenic refrigeration. The approach, problem solving, and system design and analysis for integrated heat exchanger are detailed and discussed. Implications for future space launch facilities are also identified. The objective of the field demonstration will be to test various zero-loss and densified cryofuel handling concepts for future transportation applications.

  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. Achievement report for fiscal 1993. International clean energy system technology to utilize hydrogen (WE-NET) (Sub-task 5. Development of hydrogen transportation and storage technology) (Edition 5. Development of hydrogen absorbing alloys for discrete transportation and storage); 1993 nendo seika hokokusho. Suiso riyo kokusai clean energy system gijutsu (WE-NET) . Sub tusk 5. Suiso yuso chozo gijutsu no kaihatsu - Dai 5 hen. Bunsan yuso chozo you suiso kyuzo gokin no kaihatsu

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1994-03-01

    Surveys and researches have been performed with an objective to accumulate knowledge required for R and D of a hydrogen transportation and storage technology. With respect to the hydrogen absorbing alloys for hydrogen transportation and storage, surveys have been carried out on the rare earth-nickel based alloy, magnesium based alloy, titanium/zirconium based alloy, vanadium based alloy, and other alloys. Regarding the hydrogen transportation and storage technology using hydrogen absorbing alloys, surveys have been made on R and D cases for hydrogen transporting containers, stationary hydrogen storing equipment, and hydrogen fuel tank for mobile equipment such as automobiles. For the R and D situation in overseas countries, site surveys have been executed on research organizations in Germany and Switzerland, the leader nations in R and D of hydrogen absorbing alloys. As a result of the surveys, the hydrogen absorbing alloys were found to have such R and D assignments as increase of effective hydrogen absorbing quantity, compliance with operating conditions, life extension, development of alloys easy in initial activation and fast in hydrogen discharge speed, and cost reduction. Items of the transportation and storage equipment have such assignments as making them compact, acceleration of heat conduction in alloy filling layers, handling of volume variation and internal stress, and long-term durability. (NEDO)

  5. Regulatory status of burnup credit for storage and transport of spent fuel in Germany

    International Nuclear Information System (INIS)

    Neuber, J.C.; Schweer, H.H.; Johann, H.G.

    2001-01-01

    This paper describes the regulatory status of burnup credit applications to pond storage and dry-cask transport and storage of spent fuel in Germany. Burnup credit for wet storage of LWR fuel at nuclear power plants has to comply with the newly developed safety standard DIN 25471. This standard establishes the safety requirements for burnup credit criticality safety analysis of LWR fuel storage ponds and gives guidance on meeting these requirements. Licensing evaluations of dry transport systems are based on the application of the IAEA Safety Standards Series No.ST-1. However, because of the fact that burnup credit for dry-cask transport becomes more and more inevitable due to increasing initial enrichment of the fuel, and because of the increasing importance of dry-cask storage in Germany, the necessity of giving regulatory guidance on applying burnup credit to dry-cask transport and storage is seen. (author)

  6. Remote automated material handling of radioactive waste containers

    International Nuclear Information System (INIS)

    Greager, T.M.

    1994-09-01

    To enhance personnel safety, improve productivity, and reduce costs, the design team incorporated a remote, automated stacker/retriever, automatic inspection, and automated guidance vehicle for material handling at the Enhanced Radioactive and Mixed Waste Storage Facility - Phase V (Phase V Storage Facility) on the Hanford Site in south-central Washington State. The Phase V Storage Facility, scheduled to begin operation in mid-1997, is the first low-cost facility of its kind to use this technology for handling drums. Since 1970, the Hanford Site's suspect transuranic (TRU) wastes and, more recently, mixed wastes (both low-level and TRU) have been accumulating in storage awaiting treatment and disposal. Currently, the Hanford Site is only capable of onsite disposal of radioactive low-level waste (LLW). Nonradioactive hazardous wastes must be shipped off site for treatment. The Waste Receiving and Processing (WRAP) facilities will provide the primary treatment capability for solid-waste storage at the Hanford Site. The Phase V Storage Facility, which accommodates 27,000 drum equivalents of contact-handled waste, will provide the following critical functions for the efficient operation of the WRAP facilities: (1) Shipping/Receiving; (2) Head Space Gas Sampling; (3) Inventory Control; (4) Storage; (5) Automated/Manual Material Handling

  7. Red cell concentrate storage and transport temperature.

    Science.gov (United States)

    Hancock, V; Cardigan, R; Thomas, S

    2011-10-01

    This study investigated the current U.K. guidelines for storage and transport of red cell concentrates (RCC) in saline, adenine, glucose and mannitol (SAGM). The guidelines stipulate storage at 2-6 °C but allow exposure to between 1-10 °C core temperature in a single occurrence of less than 5 h and a surface temperature of 2-10 °C for no more than 12 h during transportation. Twenty RCC units in SAGM were selected on the day of blood collection (day 0) and in vitro quality was tested pre- and post-temperature deviation at 10 °C and up to day 42 of storage. Each group of 10 RCC units was incubated for either 12 h or for both 5 and 12 h. Haemolysis was below the 0·8% U.K. limit at day 42 in all units, although there was an unexpected trend towards lower haemolysis in packs incubated for 5 and 12 h rather than just 12 h alone. Supernatant potassium was significantly higher than reference data on day 35 (P levels of adenosine triphosphate and, 2,3-diphosphoglycerate to reference data from previous studies, throughout storage. These results suggest that exposure to 10 °C for 12 h or for 5 and 12 h did not adversely affect in vitro red cell quality for the remainder of the components shelf life. © 2011 The Authors. Transfusion Medicine © 2011 British Blood Transfusion Society.

  8. 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.)

  9. 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.

  10. Shipment and Storage Containers for Tritium Production Transportation Casks

    International Nuclear Information System (INIS)

    Massey, W.M.

    1998-04-01

    The need for a shipping and storage container for the Tritium production transportation casks is addressed in this report. It is concluded that a shipping and storage container is not required. A recommendation is made to eliminate the requirement for this container because structural support and inerting requirements can be satisfied completely by the cask with a removable basket

  11. Nuclear fuel handling apparatus

    International Nuclear Information System (INIS)

    Andrea, C.; Dupen, C.F.G.; Noyes, R.C.

    1977-01-01

    A fuel handling machine for a liquid metal cooled nuclear reactor in which a retractable handling tube and gripper are lowered into the reactor to withdraw a spent fuel assembly into the handling tube. The handling tube containing the fuel assembly immersed in liquid sodium is then withdrawn completely from the reactor into the outer barrel of the handling machine. The machine is then used to transport the spent fuel assembly directly to a remotely located decay tank. The fuel handling machine includes a decay heat removal system which continuously removes heat from the interior of the handling tube and which is capable of operating at its full cooling capacity at all times. The handling tube is supported in the machine from an articulated joint which enables it to readily align itself with the correct position in the core. An emergency sodium supply is carried directly by the machine to provide make up in the event of a loss of sodium from the handling tube during transport to the decay tank. 5 claims, 32 drawing figures

  12. Feasibility study: Assess the feasibility of siting a monitored retrievable storage facility. Phase 1

    Energy Technology Data Exchange (ETDEWEB)

    King, J.W.

    1993-08-01

    The purpose of phase one of this study are: To understand the waste management system and a monitored retrievable storage facility; and to determine whether the applicant has real interest in pursuing the feasibility assessment process. Contents of this report are: Generating electric power; facts about exposure to radiation; handling storage, and transportation techniques; description of a proposed monitored retrievable storage facility; and benefits to be received by host jurisdiction.

  13. 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

  14. 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

  15. 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

  16. 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

  17. Uncertainties in criticality analysis which affect the storage and transportation of LWR fuel

    International Nuclear Information System (INIS)

    Napolitani, D.G.

    1989-01-01

    Satisfying the design criteria for subcriticality with uncertainties affects: the capacity of LWR storage arrays, maximum allowable enrichment, minimum allowable burnup and economics of various storage options. There are uncertainties due to: calculational method, data libraries, geometric limitations, modelling bias, the number and quality of benchmarks performed and mechanical uncertainties in the array. Yankee Atomic Electric Co. (YAEC) has developed and benchmarked methods to handle: high density storage rack designs, pin consolidation, low density moderation and burnup credit. The uncertainties associated with such criticality analysis are quantified on the basis of clean criticals, power reactor criticals and intercomparison of independent analysis methods

  18. Spent nuclear fuel storage - Basic concept

    International Nuclear Information System (INIS)

    Krempel, Ascanio; Santos, Cicero D. Pacifici dos; Sato, Heitor Hitoshi; Magalhaes, Leonardo de

    2009-01-01

    According to the procedures adopted in others countries in the world, the spent nuclear fuel elements burned to produce electrical energy in the Brazilian Nuclear Power Plant of Angra do Reis, Central Nuclear Almirante Alvaro Alberto - CNAAA will be stored for a long time. Such procedure will allow the next generation to decide how they will handle those materials. In the future, the reprocessing of the nuclear fuel assemblies could be a good solution in order to have additional energy resource and also to decrease the volume of discarded materials. This decision will be done in the future according to the new studies and investigations that are being studied around the world. The present proposal to handle the nuclear spent fuel is to storage it for a long period of time, under institutional control. Therefore, the aim of this paper is to introduce a proposal of a basic concept of spent fuel storage, which involves the construction of a new storage building at site, in order to increase the present storage capacity of spent fuel assemblies in CNAAA installation; the concept of the spent fuel transportation casks that will transfer the spent fuel assemblies from the power plants to the Spent Fuel Complementary Storage Building and later on from this building to the Long Term Intermediate Storage of Spent Fuel; the concept of the spent fuel canister and finally the basic concept of the spent fuel long term storage. (author)

  19. Conditioning of spent fuel assemblies from the Rossendorf RFR research reactor in transport and storage containers of the type CASTOR MTR 2

    International Nuclear Information System (INIS)

    Schneider, B.; Hofmann, G.

    1994-09-01

    Most of the spent fuel assemblies are temporarily stored in the flooded fuel ponds AB 1 and AB 2 of the RFR, and some are still in the reactor core. The conditioning task described here is part of the RFR spent fuel management concept and covers the safe emplacement of the spent fuel elements in the CASTOR MTR 2 shipping containers and the sealing of the containers in compliance with the nuclear licence issued for the conditioning task. The transfer of the spent fuel assemblies from the present wet storage conditions to the dry storage conditions in the CASTOR MTR 2 containers is done by a mobile manipulation equipment consisting essentially of the transfer sluice gate and a transfer container. Subsequent to conditioning, the shipping containers are to be transported to a licensed intermediate storage facility to await their transport to a national radwaste repository. The technical handling tools for the transfer and manipulation are briefly described, as well as the process steps involved, putting emphasis on the detailed description of processes and the accompanying time frame, so that the conditioning task can be incorporated into the work plan of the entire project. The report further presents the EDP concept established for the task, including the required data archivation and documentation. (orig.) [de

  20. MANU. Handling of bentonite prior buffer block manufacturing

    International Nuclear Information System (INIS)

    Laaksonen, R.

    2010-01-01

    The aim of this study is to describe the entire bentonite handling process starting from freight from harbour to storage facility and ending up to the manufacturing filling process of the bentonite block moulds. This work describes the bentonite handling prior to the process in which bentonite blocks are manufactured in great quantities. This work included a study of relevant Nordic and international well documented cases of storage, processing and techniques involving bentonite material. Information about storage and handling processes from producers or re-sellers of bentonite was collected while keeping in mind the requirements coming from the Posiva side. Also a limited experiment was made for humidification of different material types. This work includes a detailed description of methods and equipment needed for bentonite storage and processing. Posiva Oy used Jauhetekniikka Oy as a consultant to prepare handling process flow charts for bentonite. Jauhetekniikka Oy also evaluated the content of this report. The handling of bentonite was based on the assumption that bentonite process work is done in one factory for 11 months of work time while the weekly volume is around 41-45 tons. Storage space needed in this case is about 300 tons of bentonite which equals about seven weeks of raw material consumption. This work concluded several things to be carefully considered: sampling at various phases of the process, the air quality at the production/storage facilities (humidity and temperature), the level of automation/process control of the manufacturing process and the means of producing/saving data from different phases of the process. (orig.)

  1. Logistics of Transport and Handling with the Waste in the Upper Gemer region

    Directory of Open Access Journals (Sweden)

    Ján Spišák

    2005-11-01

    Full Text Available In the future, not any society (even the most advanced society can exists without waste formed by production processes or by any human activity. Increasing of the waste volume as well as its structure influences the living space of the mankind in a negative way. Therefore, the production, disposal or the exploitation of the waste is not only ecological but also the economical problem for the whole society. New methods of handling and disposal of the waste are preferred. This contribution is oriented on the application of micrologistics proceedings in order to reach a more effective system of transporting and handling with the waste.

  2. 78 FR 15112 - Rulemaking Advisory Committee; Transport Airplane Performance and Handling Characteristics-New Task

    Science.gov (United States)

    2013-03-08

    ... Committee; Transport Airplane Performance and Handling Characteristics--New Task AGENCY: Federal Aviation Administration (FAA), DOT. ACTION: Notice of new task assignment for the Aviation Rulemaking Advisory Committee... findings. The Task The FAA tasked ARAC to consider several areas within the airplane performance and...

  3. Multi-purpose canister storage unit and transfer cask thermal analysis

    International Nuclear Information System (INIS)

    Montgomery, R.A.; Niemer, K.A.; Lindner, C.N.

    1997-01-01

    Spent Nuclear Fuel (SNF) generated at commercial nuclear power plants throughout the US is a concern because of continued delays in obtaining a safe, permanent disposal facility. Most utilities maintain their SNF in wet storage pools; however, after decades of use, many pools are filled to capacity. Unfortunately, DOE's proposed final repository at Yucca Mountain is at least 10 years from completion, and commercial power utilities have few options for SNF storage in the interim. The Multi-Purpose Canister (MPC) system, sponsored by DOE's Office of Civilian Radioactive Waste Management, is a viable solution to the interim storage problem. The system is designed for interim dry storage, transport, and ultimate disposal of commercial SNF. The MPC system consists of four separate components: an MPC, Transfer Cask, Storage Unit, and Transport Cask. The SNF assemblies are loaded and sealed inside the helium-filled steel MPC. Once sealed, the MPC is not reopened, eliminating the need to re-handle the individual spent fuel assemblies. The MPC is transferred, using the MPC Transfer Cask, into a cylindrical, reinforced-concrete Storage Unit for on-site dry storage. The MPC may be removed from the Storage Unit at any time and transferred into the MPC Transport Cask for transport to the final repository. This paper discusses the analytical approach used to evaluate the heat transfer characteristics of an MPC containing SNF assemblies in the MPC Transfer Cask and Storage Unit

  4. A complete NUHOMS {sup registered} solution for storage and transport of high burnup spent fuel

    Energy Technology Data Exchange (ETDEWEB)

    Bondre, J. [Transnuclear, Inc. (AREVA Group), Fremont, CA (United States)

    2004-07-01

    The discharge burnups of spent fuel from nuclear power plants keep increasing with plants discharging or planning to discharge fuel with burnups in excess of 60,000 MWD/MTU. Due to limited capacity of spent fuel pools, transfer of older cooler spent fuel from fuel pool to dry storage, and very limited options for transport of spent fuel, there is a critical need for dry storage of high burnup, higher heat load spent fuel so that plants could maintain their full core offload reserve capability. A typical NUHOMS {sup registered} solution for dry spent fuel storage is shown in the Figure 1. Transnuclear, Inc. offers two advanced NUHOMS {sup registered} solutions for the storage and transportation of high burnup fuel. One includes the NUHOMS {sup registered} 24PTH system for plants with 90.7 Metric Ton (MT) crane capacity; the other offers the higher capacity NUHOMS {sup registered} 32PTH system for higher crane capacity. These systems include NUHOMS {sup registered} - 24PTH and -32PTH Transportable Canisters stored in a concrete storage overpack (HSM-H). These canisters are designed to meet all the requirements of both storage and transport regulations. They are designed to be transported off-site either directly from the spent fuel pool or from the storage overpack in a suitable transport cask.

  5. Containment performance of transportable storage casks at 9m drop test

    Energy Technology Data Exchange (ETDEWEB)

    Tobita, H. [Hitachi Zosen Corp., Osaka (Japan); Araki, K. [Hitachi Zosen Diesel and Engineering Co., Ltd., Tokyo (Japan)

    2004-07-01

    Spent fuel transportable storage casks usually have a double lid closure system, which consists of primary and secondary lids, and gaskets, to keep the containment function during transportation and storage, and to monitor a leakage or containment function during storage. Metal gasket is planning to be used not only during storage but transportation of both before and after storage. As metal gasket will degrade its containment function by creep during storage period of 50 years, relative displacement such as opening and slide displacement between the flange of the containment vessel and the lid should be restricted to a small range. To maintain the containment performance, we provisionally adopted the maximum opening limit of 0.1mm and the maximum slide displacement limit of 3.0mm in the full-scale cask design based on the report of the fundamental experiment on the metal gasket which examines the relation between leakage rate and sealing gap. The purpose of this study is to analyse the behaviour of the sealed parts (lid and vessel body) under 9m-drop impact test conditions and to establish some analytical method to evaluate this behaviour. In this study, the drop test of 1/3scale model of Hitz-B69 cask with the double lids closure system was carried out, the behaviours of the seal part were measured by displacement sensors, and they were compared with the result of the numerical analysis carried out separateley.

  6. Thermal performance and heat transport in aquifer thermal energy storage

    Science.gov (United States)

    Sommer, W. T.; Doornenbal, P. J.; Drijver, B. C.; van Gaans, P. F. M.; Leusbrock, I.; Grotenhuis, J. T. C.; Rijnaarts, H. H. M.

    2014-01-01

    Aquifer thermal energy storage (ATES) is used for seasonal storage of large quantities of thermal energy. Due to the increasing demand for sustainable energy, the number of ATES systems has increased rapidly, which has raised questions on the effect of ATES systems on their surroundings as well as their thermal performance. Furthermore, the increasing density of systems generates concern regarding thermal interference between the wells of one system and between neighboring systems. An assessment is made of (1) the thermal storage performance, and (2) the heat transport around the wells of an existing ATES system in the Netherlands. Reconstruction of flow rates and injection and extraction temperatures from hourly logs of operational data from 2005 to 2012 show that the average thermal recovery is 82 % for cold storage and 68 % for heat storage. Subsurface heat transport is monitored using distributed temperature sensing. Although the measurements reveal unequal distribution of flow rate over different parts of the well screen and preferential flow due to aquifer heterogeneity, sufficient well spacing has avoided thermal interference. However, oversizing of well spacing may limit the number of systems that can be realized in an area and lower the potential of ATES.

  7. Classification of transportation packaging and dry spent fuel storage system components according to importance to safety

    International Nuclear Information System (INIS)

    McConnell, J.W., Jr; Ayers, A.L. Jr; Tyacke, M.J.

    1996-02-01

    This report provides a graded approach for classification of components used in transportation packaging and dry spent fuel storage systems. This approach provides a method for identifying, the classification of components according to importance to safety within transportation packagings and dry spent fuel storage systems. Record retention requirements are discussed to identify the documentation necessary to validate that the individual components were fabricated in accordance with their assigned classification. A review of the existing regulations pertaining to transportation packagings and dry storage systems was performed to identify current requirements The general types of transportation packagings and dry storage systems were identified. Discussions were held with suppliers and fabricators of packagings and storage systems to determine current practices. The methodology used in this report is based on Regulatory Guide 7.10, Establishing Quality Assurance Programs for Packaging Used in the Transport of Radioactive Material. This report also includes a list of generic components for each of the general types of transportation packagings and spent fuel storage systems. The safety importance of each component is discussed, and a classification category is assigned

  8. 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

  9. 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.

  10. Monitored Retrievable Storage conceptual system study: metal storage casks

    International Nuclear Information System (INIS)

    Unterzuber, R.; Cross, T.E.; Krasicki, B.R.

    1983-08-01

    A description of the metal cask storage facility concept is presented with the operations required to handle the spent fuel or high-level wastes and transuranic wastes. A generic Receiving and Handling Facility, provided by PNL, has been used for this study. Modifications to the storage delivery side of the handling facility, necessary to couple the Receiving and Handling Facility with the storage facility, are described. The equipment and support facilities needed for the storage facility are also described. Two separate storage facilities are presented herein: one for all spent fuel storage, and one for storage of high-level waste (HLW) and transuranic waste (TRU). Each facility is described for the capacities and rates defined by PNL in the Concept Technical Performance Criteria and Base Assumptions (see Table 1.3-1). Estimates of costs and time-distributions of expenditures have been developed to construct, operate, and decommission the conceptual MRS facilities in mid-1983 dollars, for the base cases given using the cost categories and percentages provided by PNL. Cost estimates and time-distributions of expenditures have also been developed to expand the facility throughput rate from 1800 MTU to 3000 MTU, and to expand the facility storage capacity from 15,000 MTU to 72,00 MTU. The life cycle cost of the facility for the bounding cases of all spent fuel and all HLW and TRU, using the time-distributions of costs developed above and assuming a two percent per year discount rate, are also presented. 3 references, 16 figures, 18 tables

  11. IAEA'S International Working Group on Integrated Transport and Storage Safety case for Dual Purpose Casks

    International Nuclear Information System (INIS)

    Kumano, Yumiko; Varley, Kasturi; ); Droste, Bernhard; Wolff, Dietmar; Hirose, Makoto; Harvey, John; Reiche, Ingo; McConnell, Paul

    2014-01-01

    Spent nuclear fuel is generated from the operation of nuclear reactors and it is imperative that it is safely managed following its removal from reactor cores. Reactor pools are usually designed based on the assumption that the fuel will be removed after a short period of time either for reprocessing, disposal, or further storage. As a result of storing higher burn-up fuel, significantly increased time-frame till disposal solutions are prepared, and delays in decisions on strategies for spent fuel management, the volume of spent fuel discharged from reactors which needs to be managed and stored is on the increase. Consequently, additional storage capacity is needed following the initial storage in reactor pools. Options for additional storage include wet storage or dry storage in a dedicated facility or in storage casks. One of these options is the use of a Dual Purpose Cask (DPC), which is a specially designed cask for both storage and transport. The management of spent fuel using a DPC generally involves on-site and off-site transportation before and after storage. Most countries require package design approval for the DPC to be transported. In addition, it is required in many countries to have a licence for storage of the spent fuel in the DPC or a licence for a storage facility that contains DPCs. Therefore, demonstration of compliance of the DPC with national and international transport regulations as well as with the storage requirements is necessary. In order to address this increasing need among Member States, the IAEA established an international working group in 2010 to develop a guidance for integrating safety cases for both storage and transport in a holistic manner. The working group consists of experts from regulatory bodies, Technical Support Organizations, operators for both transportation and storage, and research institutes. This activity is planned to be completed by 2013. Currently, a technical report has been drafted and is expected to be

  12. Safety analysis of spent fuel transport and storage casks under extreme impact conditions

    International Nuclear Information System (INIS)

    Wolff, D.; Wieser, G.; Ballheimer, V.; Voelzke, H.; Droste, B.

    2005-01-01

    Full text: Worldwide the security of transport and storage of spent fuel with respect to terrorism threats is a matter of concern. In Germany a spent nuclear fuel management program was developed by the government including a new concept of dry on-site interim storage instead of centralized interim storage. In order to minimize transports of spent fuel casks between nuclear power plants, reprocessing plants and central storage facilities, the operators of NPPs have to erect and to use interim storage facilities for spent nuclear fuel on the site or in the vicinity of nuclear power plants. Up to now, 11 on-site interim storage buildings, one storage tunnel and 4 on-site interim storage areas (preliminary cask storage till the on-site interim storage building is completed) have been licensed at 12 nuclear power plant sites. Inside the interim storage buildings the casks are kept in upright position, whereas at the preliminary interim storage areas horizontal storage of the casks on concrete slabs is used and each cask is covered by concrete elements. Storage buildings and concrete elements are designed only for gamma and neutron radiation shielding reasons and as weather protection. Therefore the security of spent fuel inside a dual purpose transport and storage cask depends on the inherent safety of the cask itself. For nearly three decades BAM has been investigating cask safety under severe accident conditions like drop tests from more than 9 m onto different targets and without impact limiters as well as artificially damaged prototype casks. Since the terror attacks of 11 September 2001 the determination of casks' inherent safety also under extreme impact conditions due to terrorist attacks has been of our increasing interest. With respect to spent fuel storage one of the most critical scenarios of a terrorist attack for a cask is the centric impact of a dynamic load onto the lid-seal-system caused e.g. by direct aircraft crash or its engine as well as by a

  13. 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.

  14. Safety Standard for Hydrogen and Hydrogen Systems: Guidelines for Hydrogen System Design, Materials Selection, Operations, Storage and Transportation. Revision

    Science.gov (United States)

    1997-01-01

    The NASA Safety Standard, which establishes a uniform process for hydrogen system design, materials selection, operation, storage, and transportation, is presented. The guidelines include suggestions for safely storing, handling, and using hydrogen in gaseous (GH2), liquid (LH2), or slush (SLH2) form whether used as a propellant or non-propellant. The handbook contains 9 chapters detailing properties and hazards, facility design, design of components, materials compatibility, detection, and transportation. Chapter 10 serves as a reference and the appendices contained therein include: assessment examples; scaling laws, explosions, blast effects, and fragmentation; codes, standards, and NASA directives; and relief devices along with a list of tables and figures, abbreviations, a glossary and an index for ease of use. The intent of the handbook is to provide enough information that it can be used alone, but at the same time, reference data sources that can provide much more detail if required.

  15. The remote handling of canisters containing nuclear waste in glass at the Savannah River Plant

    International Nuclear Information System (INIS)

    Callan, J.E.

    1986-01-01

    The Defense Waste Processing Facility (DWPF) is a complete production area being constructed at the Savannah River Plant for the immobilization of nuclear waste in glass. The remote handling of canisters filled with nuclear waste in glass is an essential part of the process of the DWPF at the Savannah River Plant. The canisters are filled with nuclear waste containing up to 235,000 curies of radioactivity. Handling and movement of these canisters must be accomplished remotely since they radiate up to 5000 R/h. Within the Vitrification Building during filling, cleaning, and sealing, canisters are moved using standard cranes and trolleys and a specially designed grapple. During transportation to the Glass Waste Storage Building, a one-of-a-kind, specially designed Shielded Canister Transporter (SCT) is used. 8 figs

  16. Use of burnup credit for transportation and storage

    International Nuclear Information System (INIS)

    Sanders, T.L.; Ewing, R.I.; Lake, W.H.

    1991-01-01

    Burnup credit is the application of the effects of fuel burnup to nuclear criticality design. When burnup credit is considered in the design of storage facilities and transportation casks for spent fuel, the objectives are to reduce the requirements for storage space and to increase the payload of casks with acceptable nuclear criticality safety margins. The spent-fuel carrying capacities of previous-generation transport casks have been limited primarily by requirements to remove heat and/or to provide shielding. Shielding and heat transfer requirements for casks designed to transport older spent fuel with longer decay times are reduced significantly. Thus a considerable weight margin is available to the designer for increasing the payload capacity. One method to achieve an increase in capacity is to reduce fuel assembly spacing. The amount of reduction in assembly spacing is limited by criticality and fuel support structural concerns. The optimum fuel assembly spacing provides the maximum cask loading within a basket that has adequate criticality control and sufficient structural integrity for regulatory accident scenarios. The incorporation of burnup credit in cask designs could result in considerable benefits in the transport of spent fuel. The acceptance of burnup credit for the design of transport casks depends on the resolution of system safety issues and the uncertainties that affect the determination of criticality safety margins. The remainder of this report will examine these issues and the integrated approach under way to resolve them. 20 refs., 2 figs

  17. Interim spent-fuel storage options at commercial nuclear power plants

    International Nuclear Information System (INIS)

    Thakkar, A.R.; Hylko, J.M.

    1991-01-01

    Although spent fuel can be stored safely in waterfilled pools at reactor sites, some utilities may not possess sufficient space for life-of-plant storage capability. In-pool storage capability may be increased by reracking assemblies, rod consolidation, double tiering spent-fuel racks, and by shipping spent fuel to other utility-owned facilities. Long-term on-site storage capability for spent fuel may be provided by installing (dry-type) metal casks, storage and transportation casks, concrete casks, horizontal concrete modules, modular concrete vaults, or by constructing additional (pool-type) storage installations. Experience to date has provided valuable information regarding dry-type or pool-type installations, cask handling and staffing requirements, security features, decommissioning activities, and radiological issues

  18. 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.

  19. 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.

  20. Managing supply chains : transport optimization and chain synchronization

    NARCIS (Netherlands)

    van Woensel, T.; Dabia, S.; de Kok, A.G.; van Nunen, J.A.E.E.; Huijbregts, P.; Rietveld, P.

    2011-01-01

    Transport optimization is part of the broad area of physical distribution and logistics management. Physical distribution involves the handling, movement, and storage of goods from the point of origin to their point of consumption or use, via various channels of distribution. Logistics management

  1. Storage facility for solid medium level waste at Eurochemic

    International Nuclear Information System (INIS)

    Balseyro-Castro, M.

    1976-01-01

    An engineered surface storage facility is described; it will serve for the interim storage of solid and solidified medium-level waste resulting from the reprocessing of irradiated fuels. Up till now, two storage bunkers have been constructed. Each of them is 64 m long, 12 m wide and 8 m high and can take up to about 5,000 drums of 220 1 volume. The drums are stored in a vertical position and in four layers. The waste product drums are transported by a wagon to the entrance of the bunkers from where they are transferred in to the bunker by an overhead crane which is remotely controlled by high-frequency modulated laser beams. A closed-circuit camera is used to watch the handling operations. The waste stored is fully retrievable, either by means of an overhead crane of a lift-truck and can then be transported to an ultimate storage site

  2. Japanese version transport/storage packaging 'TN24'

    International Nuclear Information System (INIS)

    Kakunai, H.; Iida, T.; Tsuda, K.; Akamatsu, H.

    1993-01-01

    Since 1983, Kobe Steel has been engaged jointly with the French company Transnucleaire in the development of 'TN24', a dry-type transport and storage packaging for irradiated fuel elements. This report describes the packaging, which has been adapted for use in domestic power stations using BWRs on the basis of the results of this development. (J.P.N.)

  3. The target vacuum storage facility at iThemba LABS

    Science.gov (United States)

    Neveling, R.; Kheswa, N. Y.; Papka, P.

    2018-05-01

    A number of nuclear physics experiments at iThemba LABS require target foils that consist of specific isotopes of elements which are reactive in air. Not only is it important to prepare these targets in a suitable environment to prevent oxidation, but consideration should also be given to the long term storage and handling facilities of such targets. The target vacuum storage facility at iThemba LABS, as well as additional hardware necessary to transport and install the target foils in the experimental chamber, will be discussed.

  4. 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

  5. A probabilistic safety assessment of radioactive materials transport. A risk analysis of LLW package handling at harbor

    International Nuclear Information System (INIS)

    Watabe, Naohito; Suzuki, Hiroshi; Kouno, Yutaka

    1997-01-01

    The Probabilistic Safety Assessment (PSA) method for radioactive materials (RAM) transport has been developed by CRIEPI. A case study was executed for the purpose of studying the adaptability of the PSA method to LLW package handling, which is one of the processes of the actual transport. The main results of the case study were as follows; 1) Accident scenarios for falling of package were extracted from the 25 ton-crane system chart and package handling manual. 2) Protection methods for each drop accident scenario were confirmed. 3) Important points of the crane system were extracted. 4) Fault trees, which describe accident scenarios, were developed. 5) Probabilities for each basic event and the top event on fault trees were calculated. Consequently, 'falling of a package' on the package handling process by the 25 ton-crane was revealed to be extremely low. Among the four major stages of handling process, i.e. 'Rolling-up', 'Horizontal travelling' 'Rolling-down' and 'Contact with loading platform', the 'Rolling-down' process was found to be a major process with occupies more than 50% of the probability of the falling accidents. According to those results, it was concluded that PSA method is adaptable to package handling from the view points of extraction of weak points and review of the effect of vestment for facility. (author)

  6. Handling encapsulated spent fuel in a geologic repository environment

    International Nuclear Information System (INIS)

    Ballou, L.B.

    1983-02-01

    In support of the Spent Fuel Test-Climate at the U.S. Department of Energy's Nevada Test Site, a spent-fuel canister handling system has been designed, deployed, and operated successfully during the past five years. This system transports encapsulated commercial spent-fuel assemblies between the packaging facility and the test site (approx. 100 km), transfers the canisters 420 m vertically to and from a geologic storage drift, and emplaces or retrieves the canisters from the storage holes in the floor of the drift. The spent-fuel canisters are maintained in a fully shielded configuration at all times during the handling cycle, permitting manned access at any time for response to any abnormal conditions. All normal operations are conducted by remote control, thus assuring as low as reasonably achievable exposures to operators; specifically, we have had no measurable exposure during 30 canister transfer operations. While not intended to be prototypical of repository handling operations, the system embodies a number of concepts, now demonstrated to be safe, reliable, and economical, which may be very useful in evaluating full-scale repository handling alternatives in the future. Among the potentially significant concepts are: Use of an integral shielding plug to minimize radiation streaming at all transfer interfaces. Hydraulically actuated transfer cask jacking and rotation features to reduce excavation headroom requirements. Use of a dedicated small diameter (0.5 m) drilled shaft for transfer between the surface and repository workings. A wire-line hoisting system with positive emergency braking device which travels with the load. Remotely activated grapples - three used in the system - which are insensitive to load orientation. Rail-mounted underground transfer vehicle operated with no personnel underground

  7. Handling Interfaces and Time-varying Properties in Radionuclide Transport Models

    International Nuclear Information System (INIS)

    Robinson, Peter; Watson, Claire

    2010-12-01

    single and multiple glacial episodes the time-dependency of model parameters did not result in much change to the calculated peak fluxes to the biosphere. This is because fluxes are calculated to be dominated by the poorly-sorbed radionuclides 129I and 36Cl. However, a small increase (less than an order of magnitude) in the overall flux contributed from the radium decay chain, which is important for long timescales, was calculated during the phase when the multiple glacial episodes are occurring. These conclusions are preliminary and could be changed if different radionuclides are important in the SR-Site assessment. The known shortcomings of its one-dimensional radionuclide transport modelling capability has led SKB to fund the development of the MARFA code, which it is understood will be used in addition to the existing methodology in SR-Site. A detailed review of this code and the associated documentation has been undertaken. New semi-analytic methods have been developed in order to provide a means of checking the accuracy of MARFA calculations. The key conclusions are that: - MARFA can handle large networks in practicable run times, generally works well for single radionuclides or short chains and accurately handles advective systems where matrix diffusion effects are dominant. - The code has, however, a number of important limitations. In particular, it is unable to handle long decay chains with short-lived radionuclides and calculations immediately after flow rate changes can be inaccurate. - The documentation and Quality Assurance are poor. A large number of errors have been found in the User Guide and the associated test cases do not adequately test the use of the code for the anticipated applications. - These limitations bring into question the code's suitability (in its present form) for performance assessment calculations for a deep radioactive waste repository

  8. Handling Interfaces and Time-varying Properties in Radionuclide Transport Models

    Energy Technology Data Exchange (ETDEWEB)

    Robinson, Peter; Watson, Claire (Quintessa Ltd., Henley-on-Thames (United Kingdom))

    2010-12-15

    sorption coefficients and flow rates. For both single and multiple glacial episodes the time-dependency of model parameters did not result in much change to the calculated peak fluxes to the biosphere. This is because fluxes are calculated to be dominated by the poorly-sorbed radionuclides 129I and 36Cl. However, a small increase (less than an order of magnitude) in the overall flux contributed from the radium decay chain, which is important for long timescales, was calculated during the phase when the multiple glacial episodes are occurring. These conclusions are preliminary and could be changed if different radionuclides are important in the SR-Site assessment. The known shortcomings of its one-dimensional radionuclide transport modelling capability has led SKB to fund the development of the MARFA code, which it is understood will be used in addition to the existing methodology in SR-Site. A detailed review of this code and the associated documentation has been undertaken. New semi-analytic methods have been developed in order to provide a means of checking the accuracy of MARFA calculations. The key conclusions are that: - MARFA can handle large networks in practicable run times, generally works well for single radionuclides or short chains and accurately handles advective systems where matrix diffusion effects are dominant. - The code has, however, a number of important limitations. In particular, it is unable to handle long decay chains with short-lived radionuclides and calculations immediately after flow rate changes can be inaccurate. - The documentation and Quality Assurance are poor. A large number of errors have been found in the User Guide and the associated test cases do not adequately test the use of the code for the anticipated applications. - These limitations bring into question the code's suitability (in its present form) for performance assessment calculations for a deep radioactive waste repository

  9. The Audit of Explosives Storage and Transport Within the Australian Defence Force

    Science.gov (United States)

    1994-08-01

    Headquarters Australian Defence Force Australian Ordnance Council THE AUDIT OF EXPLOSIVES STORAGE AND TRANSPORT WITHIN THE AUSTRALIAN DEFENCE FORCE...control number. 1. REPORT DATE AUG 1994 2. REPORT TYPE 3. DATES COVERED 00-00-1994 to 00-00-1994 4. TITLE AND SUBTITLE The Audit of Explosives...8-98) Prescribed by ANSI Std Z39-18 THE AUDIT OF EXPLOSIVES STORAGE AND TRANSPORT WITHIN THE AUSTRALIAN DFFENCE FORCE - by R.W. Johnson and M.J

  10. 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

  11. Risk assessment in spent fuel storage and transportation

    International Nuclear Information System (INIS)

    Pandimani, S.

    1989-01-01

    Risk assessment in various stages of nuclear fuel cycle is still an active area of Nuclear safety studies. From the results of risk assessment available in literature, it can be determined that the risk resulting from shipments of plutonium and spent-fuel are much greater than that resulting from the transport of other materials within the nuclear fuel cycle. In India spent fuels are kept in Spent Fuel Storage Pool (SFSP) for about 240-400 days, which is relatively a longer period compared to the usual 120 days as recommended by regulatory authorities. After cooling spent fuels are transported to the reprocessing sites which are mostly situated close to the plants. India has two high level waste treatment facilities, one PREFRE (Plutonium Reprocessing and Fuel Recycling) at Tarapur and the other one, a unit of Nuclear Fuel Complex at Hyderabad. This paper presents the risk associated with spent fuel storage and transportation for the Indian conditions. All calculations are based on a typical CANDU reactor system. Simple fault tree models are evolved for SFSP and for Transportation Accident Mode (TAM) for both road and rail. Fault tree quantification and risk assessment are done to each of these models. All necessary data for SFSP are taken mostly from Reactor Safety Study, (1975). Similarly, the data for rail TAM are taken from Annual Statistical Statements, (1987-8) and that for road TAM from Special Issue on Motor Vehicle Accident Statistics in India, (1986). Simulation method is used wherever necessary. Risk is also estimated for normal/accident free transport

  12. 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

  13. Classification of transportation packaging and dry spent fuel storage system components according to importance to safety

    International Nuclear Information System (INIS)

    Tyacke, M.J.; McConnell, J.W. Jr.; Ayers, A.L. Jr.; O'Connor, S.C.; Jankovich, J.P.

    1996-01-01

    The Idaho National Engineering Laboratory prepared a technical report for the Office of Nuclear Material Safety and Safeguards of the US Nuclear Regulatory Commission, entitled Classification of Transportation Packaging and Dry Spent Fuel Storage System Components According to Importance to Safety, NUREG/CR-6407. This paper provides the results of that report. It also presents the graded approach for classification of components used in transportation packagings and dry spent fuel storage systems. This approach provides a method for identifying the classification of components according to importance to safety within transportation packagings and dry spent fuel storage systems. Record retention requirements are discussed to identify the documentation necessary to validate that the individual components were fabricated in accordance with their assigned classification. A review of the existing regulations pertaining to transportation packagings and dry storage systems was performed to identify current requirements. The general types of transportation packagings and dry storage systems are identified. The methodology used in this paper is based on Regulatory Guide 7.10, Establishing Quality Assurance Programs for Packaging Used in the Transport of Radioactive Material. This paper also includes a list of generic components for each of the general types of transportation packagings and spent fuel storage systems, with a classification category assigned to each component. Several examples concerning the safety importance of components are presented

  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. Automation in a material processing/storage facility

    International Nuclear Information System (INIS)

    Peterson, K.; Gordon, J.

    1997-01-01

    The Savannah River Site (SRS) is currently developing a new facility, the Actinide Packaging and Storage Facility (APSF), to process and store legacy materials from the United States nuclear stockpile. A variety of materials, with a variety of properties, packaging and handling/storage requirements, will be processed and stored at the facility. Since these materials are hazardous and radioactive, automation will be used to minimize worker exposure. Other benefits derived from automation of the facility include increased throughput capacity and enhanced security. The diversity of materials and packaging geometries to be handled poses challenges to the automation of facility processes. In addition, the nature of the materials to be processed underscores the need for safety, reliability and serviceability. The application of automation in this facility must, therefore, be accomplished in a rational and disciplined manner to satisfy the strict operational requirements of the facility. Among the functions to be automated are the transport of containers between process and storage areas via an Automatic Guided Vehicle (AGV), and various processes in the Shipping Package Unpackaging (SPU) area, the Accountability Measurements (AM) area, the Special Isotope Storage (SIS) vault and the Special Nuclear Materials (SNM) vault. Other areas of the facility are also being automated, but are outside the scope of this paper

  16. 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.

  17. Design analysis of various transportation package options for BN-350 SNF in terms of nuclear radiation safety in planning for long-terms dry storage

    International Nuclear Information System (INIS)

    Aisabekov, A.Z.; Mukenova, S.A.; Tur, E.S.; Tsyngaev, V.M.

    2004-01-01

    Full text: This effort is performed under the BN-350 reactor facility decommissioning project. One of the project tasks - spent nuclear fuel handling - includes the following: fuel packaging into sealed canisters, transportation of the canisters in multi-seat metallo-concrete containers and placement of the containers for a long-term dry storage. The goal of this effort is to computationally validate nuclear and radiation safety of the SNF containers placed for storage both under normal storage conditions and probable accident situations. The basic unit structure and design configurations are presented: assemblies, canisters, transportation containers. The major factors influencing nuclear and radiation safety are presented: fuel burn-up, enrichment, fabrication tolerance, types of fuel assemblies, configuration of assemblies in the canister and canisters in the container, background of assemblies placed in the reactor and cooling pool. Conditions under which the SNF containers will be stored are described and probable accident situations are listed. Proceeding from the conservatism principle, selection of the assemblies posing the greatest nuclear hazard is validated. A neutron effective multiplication factor is calculated for the SNF containers under the normal storage conditions and for the case of emergency. The effective multiplication factor is shown to be within a standard value of 0.95 in any situation. Based on the experimental data on assembly and canister dose rates, canisters posing the highest radiation threat are selected. Activities of sources and gamma-radiation spectral composition are calculated. Distribution of the dose rate outside the containers both under the normal storage conditions and accident situations are calculated. The results obtained are analyzed

  18. 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.

  19. Plutonium storage phenomenology

    International Nuclear Information System (INIS)

    Szempruch, R.

    1995-12-01

    Plutonium has been produced, handled, and stored at Department of Energy (DOE) facilities since the 1940s. Many changes have occurred during the last 40 years in the sources, production demands, and end uses of plutonium. These have resulted in corresponding changes in the isotopic composition as well as the chemical and physical forms of the processed and stored plutonium. Thousands of ordinary food pack tin cans have been used successfully for many years to handle and store plutonium. Other containers have been used with equal success. This paper addressees the exceptions to this satisfactory experience. To aid in understanding the challenges of handling plutonium for storage or immobilization the lessons learned from past storage experience and the necessary countermeasures to improve storage performance are discussed

  20. Mobile heat storage containers and their transport by rail or road

    Energy Technology Data Exchange (ETDEWEB)

    Goldenberg, Philipp

    2013-10-15

    Mobile heat storage containers are capable of making a contribution to the meaningful use of energy which is needed for use at a location other than where it originates. The study presented in this report outlines the technology of mobile heat storage and analyses an example of its transport by rail or road. (orig.)

  1. Experimental and theoretical approach to the assessment of stability criteria for safe transport of ammonium nitrate based emulsions

    NARCIS (Netherlands)

    Fabiano, B.; Kersten, R.J.A.; Barbucci, A.; Boers, M.N.

    2013-01-01

    The safety issues connected to storage and transportation of ammonium nitrate and ammonium nitrate emulsions are to be considered of primary importance, as demonstrated by the Tolouse explosion and various handling and storage accidents in different countries. This paper is focused on the assessment

  2. A case study of electrostatic accidents in the process of oil-gas storage and transportation

    International Nuclear Information System (INIS)

    Hu, Yuqin; Liu, Jinyu; Gao, Jianshen; Wang, Diansheng

    2013-01-01

    Ninety nine electrostatic accidents were reviewed, based on information collected from published literature. All the accidents over the last 30 years occurred during the process of oil-gas storage and transportation. Statistical analysis of these accidents was performed based on the type of complex conditions where accidents occurred, type of tanks and contents, and type of accidents. It is shown that about 85% of the accidents occurred in tank farms, gas stations or petroleum refineries, and 96% of the accidents included fire or explosion. The fishbone diagram was used to summarize the effects and the causes of the effects. The results show that three major reasons were responsible for accidents, including improper operation during loading and unloading oil, poor grounding and static electricity on human bodies, which accounted for 29%, 24% and 13% of the accidents, respectively. Safety actions are suggested to help operating engineers to handle similar situations in the future.

  3. Extending Spent Fuel Storage until Transport for Reprocessing or Disposal

    Energy Technology Data Exchange (ETDEWEB)

    Carlsen, Brett; Chiguer, Mustapha; Grahn, Per; Sampson, Michele; Wolff, Dietmar; Bevilaqua, Arturo; Wasinger, Karl; Saegusa, Toshiari; Seelev, Igor

    2016-09-01

    Spent fuel (SF) must be stored until an end point such as reprocessing or geologic disposal is imple-mented. Selection and implementation of an end point for SF depends upon future funding, legisla-tion, licensing and other factors that cannot be predicted with certainty. Past presumptions related to the availability of an end point have often been wrong and resulted in missed opportunities for properly informing spent fuel management policies and strategies. For example, dry cask storage systems were originally conceived to free up needed space in reactor spent fuel pools and also to provide SFS of up to 20 years until reprocessing and/or deep geological disposal became available. Hundreds of dry cask storage systems are now employed throughout the world and will be relied upon well beyond the originally envisioned design life. Given present and projected rates for the use of nuclear power coupled with projections for SF repro-cessing and disposal capacities, one concludes that SF storage will be prolonged, potentially for several decades. The US Nuclear Regulatory Commission has recently considered 300 years of storage to be appropriate for the characterization and prediction of ageing effects and ageing management issues associated with extending SF storage and subsequent transport. This paper encourages addressing the uncertainty associated with the duration of SF storage by de-sign – rather than by default. It suggests ways that this uncertainty may be considered in design, li-censing, policy, and strategy decisions and proposes a framework for safely extending spent fuel storage until SF can be transported for reprocessing or disposal – regardless of how long that may be. The paper however is not intended to either encourage or facilitate needlessly extending spent fuel storage durations. Its intent is to ensure a design and safety basis with sufficient margin to accommodate the full range of potential future scenarios. Although the focus is primarily on

  4. Shipment and Storage Containers for Tritium Production Transportation Casks

    International Nuclear Information System (INIS)

    Massey, W.M.

    1998-01-01

    A shipping and storage container for the Tritium production transportation casks may be required but requirements for protection of the irradiated rods and radioactive contamination have not been finalized. This report documents the various possibilities for the container depending on the final requirements

  5. 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)

  6. Safety of Cargo Aircraft Handling Procedure

    Directory of Open Access Journals (Sweden)

    Daniel Hlavatý

    2017-07-01

    Full Text Available The aim of this paper is to get acquainted with the ways how to improve the safety management system during cargo aircraft handling. The first chapter is dedicated to general information about air cargo transportation. This includes the history or types of cargo aircraft handling, but also the means of handling. The second part is focused on detailed description of cargo aircraft handling, including a description of activities that are performed before and after handling. The following part of this paper covers a theoretical interpretation of safety, safety indicators and legislative provisions related to the safety of cargo aircraft handling. The fourth part of this paper analyzes the fault trees of events which might occur during handling. The factors found by this analysis are compared with safety reports of FedEx. Based on the comparison, there is a proposal on how to improve the safety management in this transportation company.

  7. Influence of methane in CO2 transport and storage for CCS technology.

    Science.gov (United States)

    Blanco, Sofía T; Rivas, Clara; Fernández, Javier; Artal, Manuela; Velasco, Inmaculada

    2012-12-04

    CO(2) Capture and Storage (CCS) is a good strategy to mitigate levels of atmospheric greenhouse gases. The type and quantity of impurities influence the properties and behavior of the anthropogenic CO(2), and so must be considered in the design and operation of CCS technology facilities. Their study is necessary for CO(2) transport and storage, and to develop theoretical models for specific engineering applications to CCS technology. In this work we determined the influence of CH(4), an important impurity of anthropogenic CO(2), within different steps of CCS technology: transport, injection, and geological storage. For this, we obtained new pressure-density-temperature (PρT) and vapor-liquid equilibrium (VLE) experimental data for six CO(2) + CH(4) mixtures at compositions which represent emissions from the main sources in the European Union and United States. The P and T ranges studied are within those estimated for CO(2) pipelines and geological storage sites. From these data we evaluated the minimal pressures for transport, regarding the density and pipeline's capacity requirements, and values for the solubility parameter of the mixtures, a factor which governs the solubility of substances present in the reservoir before injection. We concluded that the presence of CH(4) reduces the storage capacity and increases the buoyancy of the CO(2) plume, which diminishes the efficiency of solubility and residual trapping of CO(2), and reduces the injectivity into geological formations.

  8. Utilization of the organ care system as ex-vivo lung perfusion after cold storage transportation.

    Science.gov (United States)

    Mohite, P N; Maunz, O; Popov, A-F; Zych, B; Patil, N P; Simon, A R

    2015-11-01

    The Organ Care System (OCS) allows perfusion and ventilation of the donor lungs under physiological conditions. Ongoing trials to compare preservation with OCS Lung with standard cold storage do not include donor lungs with suboptimal gas exchange and donor lungs treated with OCS following cold storage transportation. We present a case of a 48-yr-old man who received such lungs after cold storage transportation treated with ex-vivo lung perfusion utilizing OCS. © The Author(s) 2015.

  9. 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

  10. Fuel removal, transport, and storage

    International Nuclear Information System (INIS)

    Reno, H.W.

    1986-01-01

    The March 1979 accident at Unit 2 of the Three Mile Island Nuclear Power Station (TMI-2) which damaged the core of the reactor resulted in numerous scientific and technical challenges. Some of those challenges involve removing the core debris from the reactor, packaging it into canisters, loading canisters into a rail cask, and transporting the debris to the Idaho National Engineering Laboratory (INEL) for storage, examination, and preparation for final disposal. This paper highlights how some challenges were resolved, including lessons learned and benefits derived therefrom. Key to some success at TMI was designing, testing, fabricating, and licensing two rail casks, which each provide double containment of the damaged fuel. 10 refs., 12 figs

  11. Robotic transport complex of automotive vehicles for handling of rock mass at the process of open cast mining

    Directory of Open Access Journals (Sweden)

    Anatoly KOLGA

    2015-06-01

    Full Text Available The article is concerned with the applicability of the robotic transportation complex of automotive barrows for haulage transportation along various transport routes of mining enterprises. The simultaneous application of robotic transport and telemetry links makes the door-to-door transportation possible, i.e. direct transportation from the starting to the final point avoiding intermediate storage and a considerable part of auxiliary equipment.

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

    International Nuclear Information System (INIS)

    Drotning, W.

    1991-02-01

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

  13. The development of a transportable storage cask

    International Nuclear Information System (INIS)

    Stuart, I.F.

    1991-01-01

    There are a number of different technologies for implementing interim storage of spent fuel at reactor sites. It is generally accepted that, if possible, expanding the capacity of existing fuel pools through the installation of compact racks and the use of fuel rod consolidation are the most economical first steps. Once these have been carried out, other alternatives must be employed if further capacity expansion is required. It is not the purpose of this paper to discuss the relative economics of these alternatives, since under specific constraints and conditions each one can be shown to have an economic benefit. However, it is the reduction in plant operations, the minimising of radiation exposure, the inherent flexibility and corresponding overall favourable economics that have led to the development of the dual purpose storage and transport cask in the past few years. (author)

  14. The Application of Online Check-in in the Process of Passenger Handling in Air Transportation

    Directory of Open Access Journals (Sweden)

    František Adamčík

    2017-11-01

    Full Text Available Passenger handling is one of the most important activities any passenger is obliged to carry out prior to boarding the plane to depart. For the handling process to be safeguarded, it is inevitable to perform the services involved in it fast and efficiently so as to prevent idle times or delays during the procedures potentially resulting in delay of flight. By gradual development of the so-called web-based information technologies, some of the activities involved in the handling process can be delegated to the passengers themselves, thereby achieving a faster course of the passenger handling process. In this contribution the authors are dealing with the status quo of the on-line web-based check-in process in air transportation forecasting the expected course of events in these services in the future. Next, based on analyzing functions and characteristics of similar solutions available in the market, the authors are putting forward their new proposal of their own design of a self-service, on-line system of passenger handling with the aim to simplify and expedite the entire handling process. It is the aim of the authors to develop a competitive design in terms of costs as well as new function and services not offered by the hitherto existing with emphasis on improving efficiency of passenger handling at the airports. The resulting solution thanks to internet based technologies is platform independent and fully applicable to the process of airport passenger handling. To an equal extent, the solutions are being applied by the authors to the educational process, as a training tool for the preparation of the aviation personnel and also as part of simulation models for research in the field of airport processes optimization.

  15. 21 CFR 864.3250 - Specimen transport and storage container.

    Science.gov (United States)

    2010-04-01

    ... 21 Food and Drugs 8 2010-04-01 2010-04-01 false Specimen transport and storage container. 864.3250 Section 864.3250 Food and Drugs FOOD AND DRUG ADMINISTRATION, DEPARTMENT OF HEALTH AND HUMAN SERVICES (CONTINUED) MEDICAL DEVICES HEMATOLOGY AND PATHOLOGY DEVICES Pathology Instrumentation and Accessories § 864...

  16. Vacuum technologies developed for at-400A Type B transportation and storage package

    International Nuclear Information System (INIS)

    Franklin, K.W.; Cockrell, G.D.

    1995-01-01

    The AT-400A TYPE B transportation and storage container will be used at Pantex Plant for the transportation and interim storage of plutonium pits. The AT-400A was designed by a joint effort between Sandia National Labs, Los Alamos National Labs, Lawrence Livermore National Laboratory, and Mason and Hanger-Silas Mason Co., Inc. In order to meet the requirements for transportation and storage, five different vacuum technologies had to be developed. The goals of the various vacuum technologies were to verify the plutonium pit was sealed, perform the assembly verification leak check in accordance with ANSI N-14.5 and to provide a final inert gas backfill in the containment vessel. This paper will discuss the following five vacuum technologies: (1) Pit Leak Testing, (2) Containment Vessel Purge and Backfill with tracer gas, (3) Containment Vessel Leak Testing, (4) Containment Vessel Purge and Final Backfill, and (5) Leak Testing of the Containment Vessel Gas Transfer tube

  17. 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.

  18. Transportation flow analysis in a centralised supply chain at Toyota Material Handling Europe

    OpenAIRE

    Gustavsson, Styrbjörn; Öberg, Mikael

    2010-01-01

    This report is the result of a Master Thesis written at Toyota Material Handling Europe (TMHE), with the purpose to map the existing spare part supply chain structure and to analyse future suggested supply chain structures with a focus on transportation flows. TMHE is one of the world’s largest producing forklift distributers with large market shares throughout Europe. Besides the main activity of forklifts the aftermarket of distributing spare parts is a major business. With a current decent...

  19. Transport and Storage Economics of CCS Networks in the Netherlands

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2013-04-15

    A team from the Rotterdam Climate Initiative, CATO-2 (the Dutch national R and D programme on CCS) and the Clinton Climate Initiative, developed a financial model to assess the economics of alternative CO2 transport and storage options in the North Sea, based on common user infrastructure. The purpose of the financial model is to introduce a simple planning tool relating to the transport and storage components of an integrated CCS project using readily available, non-confidential data. A steering group of major emitters with advanced plans for CCS projects in the Netherlands and Belgium guided the project. Although the report focusses on potential projects in the Netherlands (Rotterdam and Eemshaven) and Belgium (Antwerp) in the short to medium term, the analysis and lessons could be useful to other regions considering CO2 network solutions.

  20. DISPOSAL CONTAINER HANDLING SYSTEM DESCRIPTION DOCUMENT

    Energy Technology Data Exchange (ETDEWEB)

    E. F. Loros

    2000-06-30

    The Disposal Container Handling System receives and prepares new disposal containers (DCs) and transfers them to the Assembly Transfer System (ATS) or Canister Transfer System (CTS) for loading. The system receives the loaded DCs from ATS or CTS and welds the lids. When the welds are accepted the DCs are termed waste packages (WPs). The system may stage the WP for later transfer or transfer the WP directly to the Waste Emplacement/Retrieval System. The system can also transfer DCs/WPs to/from the Waste Package Remediation System. The Disposal Container Handling System begins with new DC preparation, which includes installing collars, tilting the DC upright, and outfitting the container for the specific fuel it is to receive. DCs and their lids are staged in the receipt area for transfer to the needed location. When called for, a DC is put on a cart and sent through an airlock into a hot cell. From this point on, all processes are done remotely. The DC transfer operation moves the DC to the ATS or CTS for loading and then receives the DC for welding. The DC welding operation receives loaded DCs directly from the waste handling lines or from interim lag storage for welding of the lids. The welding operation includes mounting the DC on a turntable, removing lid seals, and installing and welding the inner and outer lids. After the weld process and non-destructive examination are successfully completed, the WP is either staged or transferred to a tilting station. At the tilting station, the WP is tilted horizontally onto a cart and the collars removed. The cart is taken through an air lock where the WP is lifted, surveyed, decontaminated if required, and then moved into the Waste Emplacement/Retrieval System. DCs that do not meet the welding non-destructive examination criteria are transferred to the Waste Package Remediation System for weld preparation or removal of the lids. The Disposal Container Handling System is contained within the Waste Handling Building System

  1. 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

  2. Next nuclear gamble: transportation and storage of nuclear waste

    International Nuclear Information System (INIS)

    Resnikoff, M.

    1983-01-01

    Accidents during transport of nuclear waste are more threatening - though less likely - than a reactor meltdown because transportation accidents could occur in the middle of a populous city, affecting more people and property than a plant accident, according to the Council on Economic Priorities, a non-profit public service research organization. Transportation, as presently practiced, is unsafe. Shipping containers, called casks, are poorly designed and constructed, CEP says. The problem needs attention because the number of casks filled with nuclear waste on the nation's highways could increase a hundred times during the next 15 years under the Nuclear Waste Policy Act of 1982, which calls for storage areas. Recommendations, both technical and regulatory, for reducing the risks are presented

  3. Torus sector handling system

    International Nuclear Information System (INIS)

    Grisham, D.L.

    1981-01-01

    A remote handling system is proposed for moving a torus sector of the accelerator from under the cryostat to a point where it can be handled by a crane and for the reverse process for a new sector. Equipment recommendations are presented, as well as possible alignment schemes. Some general comments about future remote-handling methods and the present capabilities of existing systems will also be included. The specific task to be addressed is the removal and replacement of a 425 to 450 ton torus sector. This requires a horizontal movement of approx. 10 m from a normal operating position to a point where its further transport can be accomplished by more conventional means (crane or floor transporter). The same horizontal movement is required for reinstallation, but a positional tolerance of 2 cm is required to allow reasonable fit-up for the vacuum seal from the radial frames to the torus sector. Since the sectors are not only heavy but rather tall and narrow, the transport system must provide a safe, stable, and repeatable method fo sector movement. This limited study indicates that the LAMPF-based method of transporting torus sectors offers a proven method of moving heavy items. In addition, the present state of the art in remote equipment is adequate for FED maintenance

  4. Safe handling of radiation sources

    International Nuclear Information System (INIS)

    Abd Nasir Ibrahim; Azali Muhammad; Ab Razak Hamzah; Abd Aziz Mohamed; Mohammad Pauzi Ismail

    2004-01-01

    This chapter discussed the subjects related to the safe handling of radiation sources: type of radiation sources, method of use: transport within premises, transport outside premises; Disposal of Gamma Sources

  5. SUBTASK 2.19 – OPERATIONAL FLEXIBILITY OF CO2 TRANSPORT AND STORAGE

    Energy Technology Data Exchange (ETDEWEB)

    Jensen, Melanie; Schlasner, Steven; Sorensen, James; Hamling, John

    2014-12-31

    Carbon dioxide (CO2) is produced in large quantities during electricity generation and by industrial processes. These CO2 streams vary in terms of both composition and mass flow rate, sometimes substantially. The impact of a varying CO2 stream on pipeline and storage operation is not fully understood in terms of either operability or infrastructure robustness. This study was performed to summarize basic background from the literature on the topic of operational flexibility of CO2 transport and storage, but the primary focus was on compiling real-world lessons learned about flexible operation of CO2 pipelines and storage from both large-scale field demonstrations and commercial operating experience. Modeling and pilot-scale results of research in this area were included to illustrate some of the questions that exist relative to operation of carbon capture and storage (CCS) projects with variable CO2 streams. It is hoped that this report’s real-world findings provide readers with useful information on the topic of transport and storage of variable CO2 streams. The real-world results were obtained from two sources. The first source consisted of five full-scale, commercial transport–storage projects: Sleipner, Snøhvit, In Salah, Weyburn, and Illinois Basin–Decatur. These scenarios were reviewed to determine the information that is available about CO2 stream variability/intermittency on these demonstration-scale projects. The five projects all experienced mass flow variability or an interruption in flow. In each case, pipeline and/or injection engineers were able to accommodate any issues that arose. Significant variability in composition has not been an issue at these five sites. The second source of real- world results was telephone interviews conducted with experts in CO2 pipeline transport, injection, and storage during which commercial anecdotal information was acquired to augment that found during the literature search of the five full-scale projects. The

  6. Nuclear Industry Input to the Development of Concepts for the Consolidated Storage of Used Nuclear Fuel - 13411

    International Nuclear Information System (INIS)

    Phillips, Chris; Thomas, Ivan; McNiven, Steven; Lanthrum, Gary

    2013-01-01

    EnergySolutions and its team partners, NAC International, Exelon Nuclear Partners, Talisman International, TerranearPMC, Booz Allen Hamilton and Sargent and Lundy, have carried out a study to develop concepts for a Consolidated Storage Facility (CSF) for the USA's stocks of commercial Used Nuclear Fuel (UNF), and the packaging and transport provisions required to move the UNF to the CSF. The UNF is currently stored at all 65 operating nuclear reactor sites in the US, and at 10 shutdown sites. The study was funded by the US Department of Energy and followed the recommendations of the Blue Ribbon Commission on America's Nuclear Future (BRC), one of which was that the US should make prompt efforts to develop one or more consolidated storage facilities for commercial UNF. The study showed that viable schemes can be devised to move all UNF and store it at a CSF, but that a range of schemes is required to accommodate the present widely varying UNF storage arrangements. Although most UNF that is currently stored at operating reactor sites is in water-filled pools, a significant amount is now dry stored in concrete casks. At the shutdown sites, the UNF is dry stored at all but two of the ten sites. Various types of UNF dry storage configurations are used at the operating sites and shutdown sites that include vertical storage casks that are also licensed for transportation, vertical casks that are licensed for storage only, and horizontally orientated storage modules. The shutdown sites have limited to nonexistent UNF handling infrastructure and several no longer have railroad connections, complicating UNF handling and transport off the site. However four methods were identified that will satisfactorily retrieve the UNF canisters within the storage casks and transport them to the CSF. The study showed that all of the issues associated with the transportation and storage of UNF from all sites in the US can be accommodated by adopting a staged approach to the construction of

  7. Nuclear Industry Input to the Development of Concepts for the Consolidated Storage of Used Nuclear Fuel - 13411

    Energy Technology Data Exchange (ETDEWEB)

    Phillips, Chris; Thomas, Ivan; McNiven, Steven [EnergySolutions Federal EPC., 2345 Stevens Drive, Richland, WA, 99354 (United States); Lanthrum, Gary [NAC International, 3930 East Jones Bridge Road, Norcross, GA, 30092 (United States)

    2013-07-01

    EnergySolutions and its team partners, NAC International, Exelon Nuclear Partners, Talisman International, TerranearPMC, Booz Allen Hamilton and Sargent and Lundy, have carried out a study to develop concepts for a Consolidated Storage Facility (CSF) for the USA's stocks of commercial Used Nuclear Fuel (UNF), and the packaging and transport provisions required to move the UNF to the CSF. The UNF is currently stored at all 65 operating nuclear reactor sites in the US, and at 10 shutdown sites. The study was funded by the US Department of Energy and followed the recommendations of the Blue Ribbon Commission on America's Nuclear Future (BRC), one of which was that the US should make prompt efforts to develop one or more consolidated storage facilities for commercial UNF. The study showed that viable schemes can be devised to move all UNF and store it at a CSF, but that a range of schemes is required to accommodate the present widely varying UNF storage arrangements. Although most UNF that is currently stored at operating reactor sites is in water-filled pools, a significant amount is now dry stored in concrete casks. At the shutdown sites, the UNF is dry stored at all but two of the ten sites. Various types of UNF dry storage configurations are used at the operating sites and shutdown sites that include vertical storage casks that are also licensed for transportation, vertical casks that are licensed for storage only, and horizontally orientated storage modules. The shutdown sites have limited to nonexistent UNF handling infrastructure and several no longer have railroad connections, complicating UNF handling and transport off the site. However four methods were identified that will satisfactorily retrieve the UNF canisters within the storage casks and transport them to the CSF. The study showed that all of the issues associated with the transportation and storage of UNF from all sites in the US can be accommodated by adopting a staged approach to the

  8. Effect of sunlight, transport and storage vessels on drinking water ...

    African Journals Online (AJOL)

    Effect of sunlight, transport and storage vessels on drinking water quality in rural Ghana. ... on drinking water quality in rural Ghana. K Obiri-Danso, E Amevor, LA Andoh, K Jones ... Full Text: EMAIL FREE FULL TEXT EMAIL FREE FULL TEXT

  9. Investigation of diffusional transport of heat and its enhancement in phase-change thermal energy storage systems

    International Nuclear Information System (INIS)

    Saraswat, Amit; Bhattacharjee, Rajdeep; Verma, Ankit; Das, Malay K.; Khandekar, Sameer

    2017-01-01

    Thermal energy storage in general, and phase-change materials (PCMs) in particular, have been a major topic of research for the last thirty years. Due to their favorable thermo-dynamical characteristics, such as high density, specific heat and latent heat of fusion, PCMs are usually employed as working fluids for thermal storage. However, low thermal conductivities of organic PCMs have posed a continuous challenge in its large scale deployment. This study focuses on experimental and numerical investigation of the melting process of industrial grade paraffin wax inside a semi-cylindrical enclosure with a heating strip attached axially along the center of semi-cylinder. During the first part of the study, the solid-liquid interface location, the liquid flow patterns in the melt pool, and the spatial and temporal variation of PCM temperature were recorded. For numerical simulation of the system, open source library OpenFOAM® was used in order to solve the coupled Navier-Stokes and energy equations in the considered system. It is seen that the enthalpy-porosity technique implemented on OpenFOAM® is reasonably well suited for handling melting/solidification problems and can be employed for system level design. Next, to overcome the inherent thermal limitations of PCM storage material, the study further explored the potential of coupling the existing heat source with copper-water heat pipes, so as to help augment the rate of heat dissipation within the medium by increasing the effective system-level thermal conductivity. Integration of heat pipes led to enhanced transport, and hence, a substantial decrease in the total required melting time. The study provides a framework for designing of large systems with integration of heat pipes with PCM based thermal storage systems.

  10. The risk assesment in storage and transportation of dangerous substances - preoccupations and perspectives

    International Nuclear Information System (INIS)

    Lazar, Roxana Elena; Dumitrescu, Maria; Stefanescu, Ioan

    2001-01-01

    The paper presents a risk assessment model for dangerous substance storage and transportation. It will combine also qualitative and quantitative evaluation methods, the results being referred to the lethal risk at individual and social level. The model includes the main tasks to classify the risks and to achieve a scale of priorities. To achieve a proper analysis of a regional risk the following steps should be observed: a list of dangerous substances; the classification of storage and transportation activities in the area; the selection of those activities that can be included in the study; establishing the category of effects ; the estimation of consequences to the environment and people; the calculation of major accidents frequency; the risk level classification. Generally, in the global risk assessment in industrial sector one neglects the risk induced by the transport of dangerous substances. Because of that the decision process in the risk management field can be seriously affected and the initiatives to reduce the risk and to decrease the consequences of potential accidents can be reduced, too. The model will be applied to evaluate the risk due major accidents occurring in the storage of dangerous substances and their transportation on roads, railway or by pipes. It represents a prime action plan at national level to evaluate and analyze the transportation risk. (authors)

  11. Regulations concerning marine transport and storage of dangerous things (abridged)

    International Nuclear Information System (INIS)

    1987-01-01

    This report shows the Ordinances No.84 (1967) and No.30 (1957) of the Ministry of transport. The Ordinance No.84 has been published in detail elsewhere. The provisions concerning shipping transport and storage of dangerous substances deal with isolation of each dangerous substance, method for loading (cleaning of container, etc.), certificate for ship for transporting dangerous substances, renewal of certificate for ship for transporting dangerous substances, return of certificate, fee (for renewal and reissue of certificate), definition of terms, type of radioactive cargo (L-type cargo, A-type cargo, BM-type cargo, BU type cargo), transport of radioactive substances, type of fissionable cargo (Type I, Type II and Type III), confirmation of safety concerning radioactive cargo (conformity to standards, inspection, approval, etc.), limit of cargo volume, transport index, marking (type of cargo), confirmation of safety of transport, inspection of contamination, notice of transport, special measures, inspection of cargo (radioactive substances), requirements for container and package, etc. (Nogami, K.)

  12. Safe transport of spent fuels after long-term storage

    International Nuclear Information System (INIS)

    Aritomi, M.; Takeda, T.; Ozaki, S.

    2004-01-01

    Considering the scarcity of energy resources in Japan, a nuclear energy policy pertaining to the spent fuel storage has been adopted. The nuclear energy policy sets the rules that spent fuels generated from LWRs shall be reprocessed and that plutonium and unburnt uranium shall be recovered and reused. For this purpose, a reprocessing plant, which has a reprocessing capability of 800 ton/yr, is under construction at Rokkasho Village. However, it is anticipated that the start of its operation will be delayed. In addition, the amount of spent fuels generated from nuclear power plants exceeds its reprocessing capability. Therefore, the establishment of storage technology for spent fuels becomes an urgent problem in Japan in order to continue smoothly the LWR operations. In this paper, the background of nuclear power generation in Japan is introduced at first. Next, the policy of spent fuel storage in Japan and circumstances surrounding the spent fuels in Japan are mentioned. Furthermore, the major subjects for discussions to settle and improve 'Standard for Safety Design and Inspection of Metal Casks for Spent Fuel Interim Storage Facility' in Atomic Energy Society of Japan are discussed, such as the integrity of fuel cladding, basket, shielding material and metal gasket for the long term storage for achieving safe transport of spent fuels after the storage. Finally, solutions to the unsolved subject in establishing the spent fuel interim storage technologies ase introduced accordingly

  13. Quality assurance system in the production process of the gamma shielding devices used for transport and handling of radiopharmaceuticals and labelled compounds at Cuba; Sistema de aseguramiento de la calidad en el proceso de produccion de los dispositivos de blindaje gamma utilizados en el transporte y manipulacion de los radiofarmacos y compuestos marcados en Cuba

    Energy Technology Data Exchange (ETDEWEB)

    Zuniga Santa, Juan F.; Fernandez Rondon, Manuel; Viante Garrido, Enrique; Berdeguez, Mirta B.T. [Centro de Tecnologia Nuclear (CTN), La Habana (Cuba); Rodriguez Perez, Hilario [Instituto Superior Politecnico Jose Antonio Echeverria (ISPJAE), La Habana (Cuba)

    1999-11-01

    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) 14 refs., 4 figs., 4 tabs.; e-mail: ctn at ctnet.centis.edu.cu; bada at cujae.ispjae.edu.cu

  14. Refurbishment of the transportation equipment, Task 3.08/04-10

    International Nuclear Information System (INIS)

    Nikolic, M.; Bratic, A.

    1963-01-01

    Transportation equipment at the RA reactor includes the bridge crane in the reactor hall, another smaller crane, bridge crane in spent fuel storage space, crane for handling the fuel containers n the room 099 and cart of the transportation channel. Regular testing and maintenance during reactor operation was not considered sufficient, and for that reason the repair and maintenance actions were done during the refurbishment of the reactor while it has been shut-down

  15. 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

  16. Purinergic receptors stimulate Na+/Ca2+ exchange in pancreatic duct cells: possible role of proteins handling and transporting Ca2+

    DEFF Research Database (Denmark)

    Hansen, Mette R; Krabbe, Simon; Ankorina-Stark, Ieva

    2009-01-01

    ). Since NCX can also be connected with epithelial Ca(2+) transport, we also investigated expression of some Ca(2+)-handling/transporting proteins. Expression analysis revealed that pancreatic ducts of rat and human duct cell line CFPAC-1 (also PANC-1 and Capan-1) express the Na(+)/Ca(2+) exchanger (splice...

  17. 9 CFR 3.118 - Handling.

    Science.gov (United States)

    2010-01-01

    ... 9 Animals and Animal Products 1 2010-01-01 2010-01-01 false Handling. 3.118 Section 3.118 Animals and Animal Products ANIMAL AND PLANT HEALTH INSPECTION SERVICE, DEPARTMENT OF AGRICULTURE ANIMAL WELFARE STANDARDS Specifications for the Humane Handling, Care, Treatment, and Transportation of Marine...

  18. MRS [monitored retrievable storage] to transportation system interfaces

    International Nuclear Information System (INIS)

    Row, T.H.; Croff, A.G.

    1987-01-01

    In March 1987, the US Department of Energy presented to Congress the proposal to construct and operate a facility for the monitored retrievable storage (MRS) of spent fuel at a site on the Clinch River in the Roane County portions of Oak Ridge. In discussing the MRS to Transportation System Interfaces, the authors provide a blending of the technical and institutional issues, for they do not believe the solutions to success of this enterprise lie wholly in one area. The authors cover: early chronology of the MRS; comparison of total-system life cycle cost estimates of the authorized system and improved-performance system (i.e., the system that includes a facility for MRS); transportation costs resulting from shipping, security and cask; assumptions for dedicated rail transport from MRS to repository; and significant results from the Total System Life Cycle Cost (TSLCC) analysis of the improved performance system. (AT)

  19. Integration of transport and handling equipment at CERN criteria to satisfy operational needs and safety aspects

    CERN Document Server

    Bertone, C; CERN. Geneva. TS Department

    2004-01-01

    Within the last 4 years TS-IC-HM (former ST-HM group) integrated about 150 transport and handling supplies including 29 cranes, 20 fork lift trucks, 60 tunnel vehicles. Most of these are standardised supplies, but very often special functionality has been implemented and the complexity of the equipment has been increased. With the Rocla cryo-dipol transporters even prototype equipment was integrated that had been specially designed for CERN. This paper discusses the differences regarding the actions that have to be performed when the different kind of equipment have to be integrated.

  20. 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)

  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. Proposal for the award of a contract for the maintenance of industrial transport and handling equipment

    CERN Document Server

    European Organization for Nuclear Research

    2002-01-01

    This document concerns the award of a contract for the maintenance of industrial transport and handling equipment. Following a market survey carried out among 145 firms in sixteen Member States, a call for tenders (IT-3049/ST) was sent on 8 May 2002 to two firms and four consortia, one consortium consisting of three firms and three consortia consisting of two firms, in three Member States. By the closing date, CERN had received six tenders from six consortia in three Member States. The Finance Committee is invited to agree to the negotiation of a contract with the consortium CEGELEC (FR), SPIE-TRINDEL (FR), ELECTRON (NL) and FENWICK-LINDE (FR), the lowest bidder after alignment, for the maintenance of industrial transport and handling equipment for a total amount of 2 973 280 euros (4 346 900 Swiss francs), covering an initial period of three years starting on 1 October 2002, subject to revision for inflation from 1 October 2005. The contract will include an option for two further one-year extensions beyond t...

  3. Discussion of and guidance on the optimization of radiation protection in the transport of radioactive material

    International Nuclear Information System (INIS)

    1986-05-01

    The document provides guidance on one of the components of the system of dose limitation as it applies to the transport of radioactive material, namely the optimization of radiation protection. It focuses on the following parts of the transport system: design, maintenance, preparation for transport, transport, storage-in-transit and handling and it considers occupational and public exposures. The application is intended mainly for those transport situations within the regulatory requirements where potential radiation exposures could be beneficially reduced

  4. Status of Closure Welding Technology of Canister for Transportation and Storage of High Level Radioactive Material and Waste

    International Nuclear Information System (INIS)

    Lee, H. J.; Bang, K. S.; Seo, K. S.; Seo, C. S.

    2010-10-01

    Closure seal welding is one of the key technologies in fabricating and handling the canister which is used for transportation and storage of high radioactive material and waste. Simple industrial fabrication processes are used before filling the radioactive waste into the canister. But, automatic and remote processes should be used after filling the radioactive material because the thickness of canister is not sufficient to shield the high radiation from filled material or waste. In order to simplify the welding process the closure structure of canister and the sealing method are investigated and developed properly. Two types of radioactive materials such as vitrified waste and compacted solid waste are produced in nuclear industry. Because the filling method of two types of waste is different, the shapes of closure and opening of canister and welding method is also different. The canister shape and sealing method should be standardized to standardize the handling facilities and inspection process such as leak test after closure welding. In order to improve the productivity of disposal and compatibility of the canister, the structure and shape of canister should be standardized considering the type of waste. Two kind of welding process such as arc welding and resistance welding are reported and used in the field. In the arc welding process GTAW and PAW are considered proper processes for closure welding. The closure seal welding process can be selected by considering material of canister, thickness of body, productivity, and applicable codes and rules. Because the storage time of nuclear waste in canister is very long, at least 20 years, the long-time corrosion at the weld should be estimated including mechanical integrity. Recently, the mitigation of residual stress around weld region, which causes stress corrosion cracking, is also interesting research issue

  5. Storage and transport casks combine to bring benefits

    International Nuclear Information System (INIS)

    Thorup, C.

    1988-01-01

    The Nuclear Assurance Corporation is currently preparing a safety report on its new spent fuel storage/transport casks. The report is due to be submitted to the NRC in 1989, together with an application for a licence. The aim of the combined casks is to simplify the process of dealing with spent fuel, whilst keeping costs down. The design of the casks is described, together with questions relating to the licensing of the casks. (author)

  6. 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

  7. 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

  8. Heat and damp transport in cavity bricks. Waerme- und Feuchtetransport in Hochlochziegeln

    Energy Technology Data Exchange (ETDEWEB)

    Elsner, M

    1987-11-19

    The aim of this work is a systematic measurement of the structural effect of cavity bricks on the thermal insulation and thermal storage values depending on the material values of the bricks and the mortar. The arrangement and orientation of the hollow spaces and their dimensions should be varied. Brick shapes with socalled handle slots, which give more convenient handling, and with mortar pockets instead of mortar gaps, should be taken into account in the investigation. Special attention should be paid to the heat transport mechanism in the hollow spaces, where thermal conduction, thermal radiation and convection heat transport are superimposed on one another. The second main aim of the work is the calculation of the coupled heat and damp transport in hollow bricks. The heat and damp transport is described by a coupled system of differential equations, where the decisive transport coefficients should be shown as a function of the variables determining the transport processes. (orig./MM).

  9. Structure-function relationships in sapwood water transport and storage.

    Science.gov (United States)

    Barbara L. Gartner; Frederick C. Meinzer

    2005-01-01

    Primary production by plants requires the loss of substantial quantities of water when the stomata are open for carbon assimilation. The delivery of that water to the leaves occurs through the xylem. The structure, condition, and quantity of the xylem control not only the transport efficiency but also the release of water from storage. For example, if there is high...

  10. Effect of rearing conditions on behavioural and physiological responses of pigs to preslaughter handling and mixing at transport

    NARCIS (Netherlands)

    Jong, de I.C.; Prelle, I.T.; Burgwal, van de J.A.; Lambooij, E.; Korte, S.M.; Blokhuis, H.J.; Koolhaas, J.M.

    2000-01-01

    The physiological and behavioural responses of slaughter pigs reared in either a barren environment or in an enriched environment (larger pens with straw bedding) to preslaughter handling and mixing at transport were studied. Enriched-reared pigs had higher salivary cortisol concentrations in the

  11. Effects of rearing conditions on behavioural and physiological responses of pigs to preslaughter handling and mixing at transport

    NARCIS (Netherlands)

    de Jong, I.C; Prelle, I.T.; Lambooij, E.; Korte, S.M.; Blokhuis, H.J; Koolhaas, J.M.

    The physiological and behavioural responses of slaughter pigs reared in either a barren environment or in an enriched environment (larger pens with straw bedding) to preslaughter handling and mixing at transport were studied. Enriched-reared pigs had higher salivary cortisol concentrations in the

  12. Comparison of three media for transport and storage of the samples collected for detection of avian influenza virus.

    Science.gov (United States)

    Zhang, Xiao-Chun; Liu, Shuo; Hou, Guang-Yu; Zhuang, Qing-Ye; Wang, Kai-Cheng; Jiang, Wen-Ming; Wang, Su-Chun; Li, Jin-Ping; Yu, Jian-Min; Du, Xiang; Huang, Bao-Xu; Chen, Ji-Ming

    2015-09-15

    Detection of avian influenza viruses (AIVs) is important for diagnosis, surveillance and control of avian influenza which is of great economic and public health significance. Proper transport and storage of samples is critical for the detection when the samples cannot be detected immediately. As recommended by some international or national authoritative entities and some publications, phosphate buffered saline (PBS), PBS-glycerol and brain heart infusion broth (BHIB) are frequently used for transport and storage of the samples collected for detection of AIVs worldwide. In this study, we compared these three media for transport and storage of simulated and authentic swab and feces samples collected for detection of AIVs using virus isolation and reverse transcription-PCR. The results suggest that PBS-glycerol is superior to PBS and BHIB as the sample transport and storage media. The results also suggest that the samples collected for detection of AIVs should be detected as soon as possible because the virus concentration of the samples may decline rapidly during storage within days at 4 or -20°C. Copyright © 2015 Elsevier B.V. All rights reserved.

  13. Development of a container for the transportation and storage of plutonium bearing materials

    International Nuclear Information System (INIS)

    Ammerman, D.; Geinitz, R.; Thorp, D.; Rivera, M.

    1998-03-01

    There is a large backlog of plutonium contaminated materials at the Rocky Flats Environmental Technology Site near Denver, Colorado, USA. The clean-up of this site requires this material to be packaged in such a way as to allow for efficient transportation to other sites or to a permanent geologic repository. Prior to off-site shipment of the material, it may be stored on-site for a period of time. For this reason, it is desirable to have a container capable of meeting the requirements for storage as well as the requirements for transportation. Most of the off-site transportation is envisioned to take place using the TRUPACT-II Type B package, with the Waste Isolation Pilot Plant (WIPP) as the destination. Prior to the development of this new container, the TRUPACT-II had a limit of 325 FGE (fissile gram equivalents) of plutonium due to criticality control concerns. Because of the relatively high plutonium content in the material to be transported, transporting 325 FGE per TRUPACT-II is uneconomical. Thus, the purpose of the new containers is to provide criticality control to increase the allowed TRUPACT-II payload and to provide a safe method for on-site storage prior to transport. This paper will describe the analysis and testing used to demonstrate that the Pipe Overpack Container provides safe on-site storage of plutonium bearing materials in unhardened buildings and provides criticality control during transportation within the TRUPACT-II. Analyses included worst-case criticality analyses, analyses of fork-lift time impacts, and analyses of roof structure collapse onto the container. Testing included dynamic crush tests, bare pipe impact tests, a 30-minute totally engulfing pool-fire test, and multiple package impact tests in end-on and side-on orientations

  14. 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.

  15. The relationship between manual handling performance and recent flying experience in air transport pilots.

    Science.gov (United States)

    Ebbatson, Matt; Harris, Don; Huddlestone, John; Sears, Rodney

    2010-02-01

    Modern jet transport aircraft are typically flown using the on-board automation by the pilot programming commands into the auto-flight systems. Anecdotal evidence exists suggesting that pilots of highly automated aircraft experience manual flying skills decay as a result of a lack of opportunity to practise hand-flying during line operations. The ability of a pilot to revert to basic manual control is essential, for example, in cases where the aircraft's automatic capability is diminished or when reconfiguring the automatics is an ineffective use of crew capacity. However, there is a paucity of objective data to substantiate this perceived threat to flight safety. Furthermore, traditional performance measurement techniques may lack the ability to identify subtle but significant differences in pilots' manual handling ability in large transport aircraft. This study examines the relationship between pilot manual handling performance and their recent flying experience using both traditional flight path tracking measures and frequency-based control strategy measures. Significant relationships are identified between pilots' very recent flying experience and their manual control strategy. Statement of Relevance: The study demonstrates a novel application of frequency analysis, which produces a broader and more sensitive analysis of pilot performance than has been offered in previous research. Additionally, the relationships that are found to exist between recent flying experience and manual flying performance will help to guide future pilot assessment and training.

  16. Monitored retrievable storage and multi-purpose canister robotic applications: Feasibility, dose savings and cost analysis

    International Nuclear Information System (INIS)

    Bennett, P.C.

    1995-01-01

    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, and as an alternative to current MPC closure and welding methods at commercial nuclear reactor sites. Automation of key operational aspects is analyzed to determine equipment requirements, through-put times and equipment costs. The economic analysis approach is described, and economic and radiation dose impacts resulting from this automation are compared to manual handling methods. (author). 5 refs, 5 figs, 3 tabs

  17. National Ignition Facility subsystem design requirements transportation and handling, SSDR 1.1.1.3.2

    International Nuclear Information System (INIS)

    Yakuma, S.; McNairy, R.

    1996-01-01

    This Subsystem Design Requirement document is a development specification that establishes the performance, design, development, and test requirements for the Transportation ampersand Material Handling Systems (WBS 1.1.1.3.2) of the NIF Laser System (WBS 1.3 and 1.4). The NIF is a multi-pass, 192-beam, high-power, neodymium-glass laser that meets requirements set forth in the NIF SDR 002 (Laser System). 5 figs

  18. Transport and storage of spent nuclear fuel

    International Nuclear Information System (INIS)

    Lung, M.; Lenail, B.

    1987-01-01

    From a safety standpoint, spent fuel is clearly not ideal for permanent disposal and reprocessing is the best method of preparing wastes for long-term storage in a repository. Furthermore, the future may demonstrate that some fission products recovered in reprocessing have economic applications. Many countries have in fact reached the point at which the recycling of plutonium and uranium from spent fuel is economical in LWR's. Even in countries where this is not yet evident, (i.e., the United States), the French example shows that the day will come when spent fuel will be retrieved for reprocessing and recycle. It is highly questionable whether spent fuel will ever be considered and treated as waste in the same sense as fission products and processed as such, i.e., packaged in a waste form for permanent disposal. Even when recycled fuel material can no longer be reused in LWR's because of poor reactivity, it will be usable in FBR's. Based on the considerable experience gained by SGN and Cogema, this paper has provided practical discussion and illustrations of spent fuel transport and storage of a very important step in the nuclear fuel management process. The best of spent fuel storage depends on technical, economic and policy considerations. Each design has a role to play and we hope that the above discussion will help clarify certain issues

  19. 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.

  20. Safety Analysis of 'Older/Aged' Handling and Transportation Equipment for Heavy Loads, Radioactive Waste and Materials in Accordance with German Nuclear Standards KTA 3902, 3903 and 3905

    International Nuclear Information System (INIS)

    Macias, P.; Prucker, E.; Stang, W.

    2006-01-01

    The purpose of this paper is to present a general safety analysis of important handling and transportation processes and their related equipment ('load chains' consisting of cranes, load-bearing equipment and load-attaching points). This project was arranged by the responsible Bavarian ministry for environment, health and consumer protection (StMUGV) in agreement with the power plant operators of all Bavarian nuclear power plants to work out potential safety improvements. The range of the equipment (e.g. reactor building, crane, refuelling machine, load-bearing equipment and load-attaching points) covers the handling and transportation of fuel elements (e. g. with fuel flasks), heavy loads (e.g. reactor pressure vessel closure head, shielding slabs) and radioactive materials and waste (e.g. waste flasks, control elements, fuel channels, structure elements). The handling equipment was subjected to a general safety analysis taking into account the ageing of the equipment and the progress of standards. Compliance with the current valid requirements of the state of science and technology as required by German Atomic Act and particularly of the nuclear safety KTA-standards (3902, 3903 and 3905) was examined. The higher protection aims 'safe handling and transportation of heavy loads and safe handling of radioactive materials and waste' of the whole analysis are to avoid a criticality accident, the release of radioactivity and inadmissible effects on important technical equipment and buildings. The scope of the analysis was to check whether these protection aims were fulfilled for all important technical handling and transportation processes. In particularly the design and manufacturing of the components and the regulations of the handling itself were examined. (authors)

  1. The issue of safety in the transports of radioactive materials; Le probleme de la securite dans les transports de substances radioactives

    Energy Technology Data Exchange (ETDEWEB)

    Pallier, Lucien

    1961-11-20

    This report addresses and discusses the various hazards associated with transports of radioactive materials, their prevention, intervention measures, and precautions to be taken by rescuers, notably how these issues are addressed in regulations. For each of these issues, this report proposes guidelines, good practices, or procedures to handle the situation. The author first addresses hazards related to a transport of radioactive products: multiplicity of hazards, different hazards due to radioactivity, hazards due to transport modes, scale of dangerous doses. The second part addresses precautionary measures: for road transports, for air transports, for maritime transports, control procedures. The third part addresses the intervention in case of accident: case of a road accident with an unhurt or not vehicle crew, role of the first official rescuers, other kinds of accidents. The fourth part briefly addresses the case of transport of fissile materials. The fifth part discusses the implications of safety measures. Appendices indicate standards, and give guidelines for the construction of a storage building for radioactive products, for the control and storage of parcels containing radioactive products, and for the establishment of instructions for the first aid personnel.

  2. 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

  3. 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.

  4. A multi-purpose unit concept to integrate storage, transportation, and the engineered barrier system

    International Nuclear Information System (INIS)

    Hollaway, W.R.; Rozier, R.; Nitti, D.A.; Williams, J.R.

    1993-01-01

    The Multi-Purpose Unit (MPU) is a new concept for standardizing and integrating the waste management functions of spent fuel storage, transportation, and geologic disposal. The MPU concept would use one unit, composed of a relatively thick-walled inner canister with a multi-purpose overpack, to meet the requirements for storage in 10 CFR 72, transportation in 10 CFR 71, and the engineered barrier system in 10 CFR 60. The MPU concept differs from the recently proposed Multi-Purpose Canister (MPC) concept in that the MPU concept uses a single multi-purpose overpack for storage, transportation, and geologic disposal, while the MPC concept uses separate and unique overpacks for each of these system functions. A design concept for the MPU is presented along with an estimate of unit costs. An initial evaluation of overall system cost showed that the MPU concept could be economically competitive with the current reference system. The MPU concept provides the potential for significant reduction, simplification, and standardization of Civilian Radioactive Waste Management (CRWMS) facilities and operations, including those at the utilities, during waste acceptance and transportation, and at the Monitored Retrievable Storage (MRS) facility and the repository. The primary issues for the MPU concept relate to uncertainties with respect to licensing, and the programmatic risks associated with implementing the MPU concept before the repository design is finalized. The strong potential exhibited by the MPU concept demonstrates that this option merits additional development and should be considered in the next phase of work on multi-purpose concepts for the CRWMS

  5. A comparative study on uranium and ZrCo for the storage of tritium

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Summi; Paek, Seungwoo; Lee, Minsoo; Kim, Kwangrag; Ahn, Dohee [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of); Sohn, Soonhwan; Song, Kyumin [Korea Electric Power Research Institute, Daejeon (Korea, Republic of)

    2007-07-01

    Safe handling, transport, and storage of tritium requires several condition: very low equilibrium pressures over the tritide at room temperature, high dissociation pressure at moderate temperatures, existence of plateau regions in the loading/deloading isotherms, fast adsorption/desorption kinetics, no disproportionation, low reactivity of the metal/tritide system towards air and the major contaminants, low pyrophoricity, and low aging effects caused by the accumulated of He-3.

  6. A comparative study on uranium and ZrCo for the storage of tritium

    International Nuclear Information System (INIS)

    Kim, Summi; Paek, Seungwoo; Lee, Minsoo; Kim, Kwangrag; Ahn, Dohee; Sohn, Soonhwan; Song, Kyumin

    2007-01-01

    Safe handling, transport, and storage of tritium requires several condition: very low equilibrium pressures over the tritide at room temperature, high dissociation pressure at moderate temperatures, existence of plateau regions in the loading/deloading isotherms, fast adsorption/desorption kinetics, no disproportionation, low reactivity of the metal/tritide system towards air and the major contaminants, low pyrophoricity, and low aging effects caused by the accumulated of He-3

  7. The dry spent RBMK fuel cask storage site at the Ignalina NPP in Lithuania

    International Nuclear Information System (INIS)

    Penkov, V.V.; Diersch, R.

    1999-01-01

    At present, there are about 15,000 spent RBMK fuel assemblies stored in the water pools near the reactors at the Ignalina Nuclear Power Plant (INPP). Part of them are cut in two bundles and stored in standardized baskets in the pools. Each basket is loaded with 102 bundles. For long-term interim storage of this fuel, it was decided to use dry storage in casks. For this reason, the total activity to be stored is split into individual units (casks). Each cask represents a closed and independent safety system, fulfilling all safety-relevant requirements for both normal operational and hypothetical accidental conditions. The main safety relevant features of the storage cask system are: (1) Inherent safety system; (2) Double barrier system; (3) Passive cooling by natural convection; (4) Safety against accidents. The cask dry storage system is a cost effective and multi-functional system for storage, transport after the operation time and final disposal under consideration of additional protective elements. From an economical point of view, cask storage has a number of advantages. Two cask types have been intended for the INPP storage site: (1) The CASTOR RBMK cask made of ductile cast iron; (2) The CONSTOR RBMK sandwich cask made of an inner and outer steel shell and reinforced heavy concrete. The CASTOR RBMK and the CONSTOR RBMK casks are designed to withstand severe storage site accidents and with help of impact limiters - to fulfil the IAEA test criteria for type B(U)F packages. The INPP spent RBMK fuel storage site is designed as an open air storage for an operational time of 50 years. The casks are arranged on the concrete storage pad. The site is equipped with a crane for cask handling and technological buildings and security systems. The safety analyses for fuel and cask handling and for cask handling and for cask technology at the site have been made and accepted by the Lithuanian Competent Authority. (author)

  8. Assembly for transport and storage of radioactive nuclear fuel elements

    International Nuclear Information System (INIS)

    Myers, G.

    1978-01-01

    The invention concerns the self-control of coolant deficiencies on the transport of spent fuel elements from nuclear reactors. It guarantees that drying out of the fuel elements is prevented in case of a change of volume of the fluid contained in storage tanks and accumulators and serving as coolant and shielding medium. (TK) [de

  9. Transportation over long distance and thermal energy storage, coupling with energetic valuation processes from waste. State of art. Extended abstract

    International Nuclear Information System (INIS)

    Megret, O.; Bequet, L.; Manificat, A.; Weber, C.

    2011-12-01

    This study aims, on one hand, to realize a state of art about over long distance transport and heat energy storage and, on the other hand, to examine their coupling with waste valuation systems. After reminding the adequate context of development with those solutions and too showing the importance of the stake linked to the current work, we first expose the introductive elements in terms of storage and heat energy transport. The second chapter deals with the description of some materials, equipment and systems concerning heat storage energy. Afterward, the over long distance heat transport systems are detailed in the third chapter. In the fourth chapter, it is about waste valuation techniques and heat energy potentials users. The fifth chapter sums up the different techniques of storage and heat transport that are applicable to waste field according to the appropriate sector. Finally, the sixth chapter goes about 3 case-works in 3 fields: housing/commercial, industrial laundry and high temperature industry (steel industry). The purpose is to determine the implementation feasibility of the different techniques of storage and waste heat transport. (authors)

  10. 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.

  11. Alternatives for managing wastes from reactors and post-fission operations in the LWR fuel cycle. Volume 3. Alternatives for interim storage and transportation

    International Nuclear Information System (INIS)

    1976-05-01

    Volume III of the five-volume report contains information on alternatives for interim storage and transportation. Section titles are: interim storage of spent fuel elements; interim storage of chop-leach fuel bundle residues; tank storage of high-level liquid waste; interim storage of solid non-high-level wastes; interim storage of solidified high-level waste; and, transportation alternatives

  12. Intermediate storage of radioactive waste and spent nuclear fuel at the Kola Peninsula

    International Nuclear Information System (INIS)

    Bohmer, N.

    1999-01-01

    The problem of nuclear waste and disused nuclear submarines are a product of the arms race and the Cold War. Russia still continues to build new nuclear submarines, but there are very few provisions being made to properly store old nuclear submarines, and develop sufficient storage facilities for spent nuclear fuel and other radioactive waste. A solution to this problem is proposed: to construct a new regional interim storage facilities at Kola for the spent nuclear fuel instead of transporting it to Mayak, the existing reprocessing plant. This storage should have the capacity to handle the fuel in the existing storage and the fuel still on board of retired nuclear submarines. Its lifetime should be 50 years. later it would be possible to make a decision on the future of this fuel

  13. Transporting fuel debris from TMI-2 to INEL

    International Nuclear Information System (INIS)

    Quinn, G.J.; Burton, H.M.; Bixby, W.W.; McIntosh, T.W.; McGoff, O.J.; Barkonic, R.J.; Henrie, J.O.

    1986-06-01

    Transportation of the damaged fuel from Unit 2 of Three Mile Island (TMI-2) presented noteworthy technical challenges involving complex institutional issues. The program resulted from both a need to package and remove the accident debris and also the opportunity to receive and study damaged core components. These combined to establish the safe transport of the TMI-2 fuel debris as a high priority for many diverse organizations. The capability of the sending and receiving facilities to handle spent fuel transport casks in the most cost-effective manner was assessed and resulted in the development by Nuclear Packaging Inc. (NuPac) of the NuPac 125-B rail cask. This paper reviews the technical challenges in preparation of the TMI-2 core debris for transport from TMI-2 to the Idaho National Engineering Laboratory (INEL) and receipt and storage of that material at INEL. Challenges discussed include design and testing of fuel debris canisters; design, fabrication and licensing of a new rail cask for spent fuel transport; cask loading operations, equipment and facilities at TMI-2; transportation logistics; and, receipt, storage and core examination operations at INEL. 10 refs

  14. Essentials of energy technology sources, transport, storage, conservation

    CERN Document Server

    Fricke, Jochen

    2013-01-01

    An in-depth understanding of energy technology, sources, conversion, storage, transport and conservation is crucial for developing a sustainable and economically viable energy infrastructure. This need, for example, is addressed in university courses with a special focus on the energy mix of renewable and depletable energy resources. Energy makes our lives comfortable, and the existence of amenities such as heaters, cars, warm water, household appliances and electrical light is characteristic for a developed economy. Supplying the industrial or individual energy consumer with energy 24 hours

  15. Alternative configurations for the waste-handling building at the Yucca Mountain Repository

    International Nuclear Information System (INIS)

    1990-08-01

    Two alternative configurations of the waste-handling building have been developed for the proposed nuclear waste repository in tuff at Yucca Mountain, Nevada. One configuration is based on criteria and assumptions used in Case 2 (no monitored retrievable storage facility, no consolidation), and the other configuration is based on criteria and assumptions used in Case 5 (consolidation at the monitored retrievable storage facility) of the Monitored Retrievable Storage System Study for the Repository. Desirable waste-handling design concepts have been selected and are included in these configurations. For each configuration, general arrangement drawings, plot plans, block flow diagrams, and timeline diagrams are prepared

  16. 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

  17. 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

  18. Solute transport and storage mechanisms in wetlands of the Everglades, south Florida

    Science.gov (United States)

    Harvey, Judson W.; Saiers, James E.; Newlin, Jessica T.

    2005-01-01

    Solute transport and storage processes in wetlands play an important role in biogeochemical cycling and in wetland water quality functions. In the wetlands of the Everglades, there are few data or guidelines to characterize transport through the heterogeneous flow environment. Our goal was to conduct a tracer study to help quantify solute exchange between the relatively fast flowing water in the open part of the water column and much more slowly moving water in thick floating vegetation and in the pore water of the underlying peat. We performed a tracer experiment that consisted of a constant‐rate injection of a sodium bromide (NaBr) solution for 22 hours into a 3 m wide, open‐ended flume channel in Everglades National Park. Arrival of the bromide tracer was monitored at an array of surface water and subsurface samplers for 48 hours at a distance of 6.8 m downstream of the injection. A one‐dimensional transport model was used in combination with an optimization code to identify the values of transport parameters that best explained the tracer observations. Parameters included dimensions and mass transfer coefficients describing exchange with both short (hours) and longer (tens of hours) storage zones as well as the average rates of advection and longitudinal dispersion in the open part of the water column (referred to as the “main flow zone”). Comparison with a more detailed set of tracer measurements tested how well the model's storage zones approximated the average characteristics of tracer movement into and out of the layer of thick floating vegetation and the pore water in the underlying peat. The rate at which the relatively fast moving water in the open water column was exchanged with slowly moving water in the layer of floating vegetation and in sediment pore water amounted to 50 and 3% h−1, respectively. Storage processes decreased the depth‐averaged velocity of surface water by 50% relative to the water velocity in the open part of the water

  19. Transport container storage. Pt. 2

    International Nuclear Information System (INIS)

    Guenther, B.; Kuehn, H.D.; Schulz, E.

    1987-01-01

    In connection with mandatory licensing procedures and in the framework of quality control for serially produced containers from spheroidal graphite cast iron of quality grade GGG 40, destined to be used in the transport and storage of radioactive materials, each prototype and each production sample of a design is subjected to comprehensive destructive and non-destructive material tests. The data obtained are needed on the one hand to check whether specified, representative material characteristics are observed; on the other hand they are systematically evaluated to update knowledge and technical standards. The Federal Institute of Materials Research and Testing (BAM) has so far examined 528 individual containers (513 production samples and 15 prototypes) of wall thicknesses from 80 millimetres to 500 millimetres in this connection. It has turned out that the measures for quality assurance and quality control as substantiated by a concept of expertise definitely confirm the validity of component test results for production samples. (orig.) [de

  20. A Modular, Reusable Latch and Decking System for Securing Payloads During Launch and Planetary Surface Transport

    Science.gov (United States)

    Doggett, William R.; Dorsey, John T.; Jones, Thomas C.; King, Bruce D.; Mikulas, Martin M.

    2011-01-01

    Efficient handling of payloads destined for a planetary surface, such as the moon or mars, requires robust systems to secure the payloads during transport on the ground, in space and on the planetary surface. In addition, mechanisms to release the payloads need to be reliable to ensure successful transfer from one vehicle to another. An efficient payload handling strategy must also consider the devices available to support payload handling. Cranes used for overhead lifting are common to all phases of payload handling on Earth. Similarly, both recent and past studies have demonstrated that devices with comparable functionality will be needed to support lunar outpost operations. A first generation test-bed of a new high performance device that provides the capabilities of both a crane and a robotic manipulator, the Lunar Surface Manipulation System (LSMS), has been designed, built and field tested and is available for use in evaluating a system to secure payloads to transportation vehicles. A payload handling approach must address all phases of payload management including: ground transportation, launch, planetary transfer and installation in the final system. In addition, storage may be required during any phase of operations. Each of these phases requires the payload to be lifted and secured to a vehicle, transported, released and lifted in preparation for the next transportation or storage phase. A critical component of a successful payload handling approach is a latch and associated carrier system. The latch and carrier system should minimize requirements on the: payload, carrier support structure and payload handling devices as well as be able to accommodate a wide range of payload sizes. In addition, the latch should; be small and lightweight, support a method to apply preload, be reusable, integrate into a minimal set of hard-points and have manual interfaces to actuate the latch should a problem occur. A latching system which meets these requirements has been

  1. Silica desiccant packets for storage and transport of Streptococcus pneumoniae and other clinically relevant species.

    Directory of Open Access Journals (Sweden)

    Casey L Pell

    Full Text Available Bacterial isolates are often transported between laboratories for research and diagnostic purposes. Silica desiccant packets (SDPs, which are inexpensive and do not require freezing, were evaluated for storage and recovery of bacterial isolates. Conditions such as inoculum size, swab type and temperature of storage were investigated using ten Streptococcus pneumoniae isolates. The optimized protocol was then tested using 49 additional S. pneumoniae isolates representing 40 serogroups. Overall, S. pneumoniae growth was considered satisfactory (>100 colony forming units for 98/109 (89.9% and 20/20 (100% swabs after 14 days at room temperature or 28 days at 4° C, respectively. Storage in SDPs did not impact on the ability of S. pneumoniae isolates to be subsequently serotyped. When the survival of nine other clinically relevant bacterial species was tested, seven were viable after 28 days at room temperature, the exceptions being Neisseria gonorrhoeae and Haemophilus influenzae. SDPs are suitable for transport and short-term storage of bacterial species including S. pneumoniae.

  2. Developments in tokamak transport modeling

    International Nuclear Information System (INIS)

    Houlberg, W.A.; Attenberger; Lao, L.L.

    1981-01-01

    A variety of numerical methods for solving the time-dependent fluid transport equations for tokamak plasmas is presented. Among the problems discussed are techniques for solving the sometimes very stiff parabolic equations for particle and energy flow, treating convection-dominated energy transport that leads to large cell Reynolds numbers, optimizing the flow of a code to reduce the time spent updating the particle and energy source terms, coupling the one-dimensional (1-D) flux-surface-averaged fluid transport equations to solutions of the 2-D Grad-Shafranov equation for the plasma geometry, handling extremely fast transient problems such as internal MHD disruptions and pellet injection, and processing the output to summarize the physics parameters over the potential operating regime for reactors. Emphasis is placed on computational efficiency in both computer time and storage requirements

  3. Operation and maintenance of spent fuel storage and transportation casks/containers

    International Nuclear Information System (INIS)

    2007-01-01

    Member States have a growing need for casks for spent fuel storage and transportation. A variety of casks has been developed and is in use at an increasing number of sites. This has resulted in an accumulation of experience that will provide valuable information for other projects in spent fuel management. This publication provides a comprehensive review of information on the cask operation and maintenance associated with spent fuel storage. It draws upon generic knowledge from industrial experience and applications and is intended to serve as a basis for better planning and implementation in future projects

  4. Contribution to fissile materials transportation in transit storage

    International Nuclear Information System (INIS)

    Silva, Teresinha de Moraes da

    2005-01-01

    The national and international standards for the transportation of fissile materials establish two indexes: Transport Index (Tl) and Criticality Safety Index (ISC). Besides, in non-exclusive transit, the largest of these indexes cannot overtake the value 50. Considering several groups to be transported, the sum of the transportation indexes cannot overtake 200 and the distance between them should be 6 meters This work aimed, as a primary target, to verify when an index is superior to another, in relation to the fissile materials studied, i.e., uranium oxides UO 2 , U 3 O 8 and uranium silicide U 3 Si 2 , taking into account the different enrichment grades. The result found is that the criticality safety index is always greater. As a second goal, it was tried to verify if there is any alteration in the case of these compounds aging process, i.e., alteration in transport index (Tl) due to gamma radiation of daughters radioisotopes in secular equilibrium. No alteration, was verified as the daughters contribution although considerable related to the transport index is very small concerning the criticality safety index. As a third target, it was tried to justify a distance equal to 6 meters, between each group of fissile material. The result showed that, in air media, the distance of 1 meter is sufficient, except for the UO 2 compound at 100% of enrichment, which reaches 2 meter while in the water means the distance of 40cm is enough for the compounds studied. This fact is of great importance when the cost of the necessary area in the transportation and storage is taken into consideration. (author)

  5. Reversible deep storage: reversibility options for storage in deep geological formations

    International Nuclear Information System (INIS)

    2009-01-01

    This report describes the definition approach to reversibility conditions, presents the main characteristics of high-activity and intermediate-activity long-lived wastes, describes the storage in deep geological formations (safety functions, general description of the storage centre), discusses the design options for the different types of wastes (container, storage module, handling processes, phenomenological analysis, monitoring arrangements) and the decision process in support reversibility (steering of the storage process, progressive development and step-by-step closing), and reports and discusses the researches concerning the memory of the storage site

  6. Certifying the TN-BRP and TN-REG transportable storage demonstration casks

    International Nuclear Information System (INIS)

    Abbott, D.G.; Nolan, D.J.; Yoshimura, H.R.

    1991-01-01

    The US DOE has obtained US NRC certification to transport two transportable storage casks for a demonstration project. Because the casks had been built before the decision was made to obtain NRC certification, only limited modifications could be made to the casks. NRC's review resulted in several technical concerns that were subsequently resolved by design modifications, testing, and further analysis. Certification activities included qualifying the ferritic steel body material, modifying the borated stainless steel basket design, and extensive impact limiter testing. Recommendations for certifying future casks are presented based on experience with these casks

  7. Maximum overpressure in gastight containers of the storage and transport of dangerous liquids

    International Nuclear Information System (INIS)

    Steen, H.

    1977-11-01

    For a design of containers suitable under safety aspects for the transport and storage of dangerous liquids the maximum overpressure to be expected is an important value. The fundamentals for the determination of the internal pressure are pointed out for the simplified model of a rigid (i.e. not elastically or plastically deforming) and gastight container. By assuming of extreme storage and transport conditions (e.g. for the maximum liquid temperatures due to sun radiation) the figures of the maximum overpressure are calculated for about hundred liquids being of practical interest. The results show a significant influence of the compression of air in the ullage space caused by liquid expansion due to temperature rise (compression effect), particularly for liquids with a higher boiling point. The influence of the solubility of air in the liquid on the internal pressure can be neglected under the assumed transport conditions. The estimation of the volume increase of the container due to the effect of the internal pressure leads to the limitation, that the assumption of a rigid container is only justified for cylindrical and spherical steel tanks. The enlargement of the container volume due to a heating of the container shell does play no significant roll for all metal containers under the assumed conditions of storage and transport. The results obtained bear out essentially the stipulations for the test pressure and the filling limits laid down in the older German regulations for the transport of dangerous liquids in rail tank waggons and road tank vehicles without pressure relief valves. For the recently fixed and internationally harmonized regulations for tankcontainers the considerations and the results pointed out in this paper give rise to a review. (orig.) [de

  8. THE DURATION OF BORDER CONTROL PROCEDURES RELATED TO THE HANDLING OF FREIGHT TRANSPORTED BY MEANS OF SEA-ROAD TRANSPORT CHAINS AS A COMPONENT IN COMPETITIVENESS OF THE POLISH SEAPORTS

    Directory of Open Access Journals (Sweden)

    Michał Pluciński

    2017-09-01

    Full Text Available The duration of border control procedures related to the handling of freight transported by means of sea-road transport chains has become a significant component in competitiveness of seaports. The situation in this regard, existing in the Polish seaports, which was unfavourable against the background of other seaports providing services to the same supply base, resulted in the fact that a significant part of freight, i.e. mainly general containerized cargo, was handled outside the Polish seaports. The situation began to change when amendments to the regulations related to VAT (2011 and the so called “Porty 24” Package (2014 were adopted. In majority of the customs offices located in the biggest Polish seaports both the duration of services provided in relation to customs declaration and the duration of the so called “collective customs clearance” were reduced. The number of customs declarations under the simplified procedure also rose significantly. Between 2007 and 2015 customs duties and taxes in relation to the sea-land handling in Gdańsk, Gdynia, Szczecin and Świnoujście rose more than threefold.

  9. Decree 2210: by means of which technical standards and allowed proceedings for radioactive material handling are issued

    International Nuclear Information System (INIS)

    1992-01-01

    This Decree has the regulation and handling of radioactive material as object, in order to protect the health of people as well as the atmosphere. These regulations are applicable to: all natural or artificial person, public or private, that imports, manufacture, transport, store, trade, transfer or use with industrial, commercial, scientific, medical or any other aim; apparatuses capable to generate ionizing radiations whose quantum energy is superior to 5 k lo electron volts (KeV) or materials that contain radionuclides whose activities surpass the maxim exempt registration; notification and license concession. It includes: definitions; signalizing by means of basic symbol that must be included in all object, material and their mixtures, that emit ionizing radiations; control; production; import and export; trade; use; and transport of activities that involve materials and apparatuses capable to generate ionizing radiations; the category and labeled of bundles; the limits of activity for excepted bundles; the corresponding values for the different radionuclides; the limits of activity for the means of material haulage; the storage; and the handling of radioactive waste [es

  10. 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.

  11. 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.

  12. The issue of safety in the transports of radioactive materials

    International Nuclear Information System (INIS)

    Pallier, Lucien

    1961-01-01

    This report addresses and discusses the various hazards associated with transports of radioactive materials, their prevention, intervention measures, and precautions to be taken by rescuers, notably how these issues are addressed in regulations. For each of these issues, this report proposes guidelines, good practices, or procedures to handle the situation. The author first addresses hazards related to a transport of radioactive products: multiplicity of hazards, different hazards due to radioactivity, hazards due to transport modes, scale of dangerous doses. The second part addresses precautionary measures: for road transports, for air transports, for maritime transports, control procedures. The third part addresses the intervention in case of accident: case of a road accident with an unhurt or not vehicle crew, role of the first official rescuers, other kinds of accidents. The fourth part briefly addresses the case of transport of fissile materials. The fifth part discusses the implications of safety measures. Appendices indicate standards, and give guidelines for the construction of a storage building for radioactive products, for the control and storage of parcels containing radioactive products, and for the establishment of instructions for the first aid personnel

  13. Needs of anticipation for transport operations

    International Nuclear Information System (INIS)

    Galtier, J.

    2005-01-01

    COGEMA LOGISTICS (formerly Transnucleaire) has designed and manufactured several thousands of casks, and owns fleet of more than 4000 casks. Benefiting from more than 40 years of experience in cask shipment COGEMA LOGISTICS has demonstrated an outstanding performance in transportation and has integrated all feed back from past successful operations in current ones. Early anticipation of needs, i.e. at preliminary design step, is of major importance from a technical point of view (capacity, interface, handling means, licensing), and also in terms of political and public acceptance issues from the design step. This paper will highlight for each step required for the implementation of an optimal transport and storage system: Decision to proceed (including political aspects)-Design of casks to be used (including operational interface)-Licensing process-Manufacturing process-Transport plan, Public Acceptance-Loading Operations-Transport-Maintenance operations. (authors)

  14. Iron transport and storage in the coccolithophore: Emiliania huxleyi.

    Science.gov (United States)

    Hartnett, Andrej; Böttger, Lars H; Matzanke, Berthold F; Carrano, Carl J

    2012-11-01

    Iron is an essential element for all living organisms due to its ubiquitous role in redox and other enzymes, especially in the context of respiration and photosynthesis. The iron uptake and storage systems of terrestrial/higher plants are now reasonably well understood with two basic strategies for iron uptake being distinguished: strategy I plants use a mechanism involving soil acidification and induction of Fe(III)-chelate reductase (ferrireductase) and Fe(II) transporter proteins while strategy II plants have evolved sophisticated systems based on high-affinity, iron specific, binding compounds called phytosiderophores. In contrast, there is little knowledge about the corresponding systems in marine plant-like lineages. Herein we report a study of the iron uptake and storage mechanisms in the coccolithophore Emiliania huxleyi. Short term radio-iron uptake studies indicate that iron is taken up by Emiliania in a time and concentration dependent manner consistent with an active transport process. Based on inhibitor studies it appears that iron is taken up directly as Fe(iii). However if a reductive step is involved the Fe(II) must not be accessible to the external environment. Upon long term exposure to (57)Fe we have been able, using a combination of Mössbauer and XAS spectroscopies, to identify a single metabolite which displays spectral features similar to the phosphorus-rich mineral core of bacterial and plant ferritins.

  15. 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).

  16. Reserpine-induced reduction in norepinephrine transporter function requires catecholamine storage vesicles.

    Science.gov (United States)

    Mandela, Prashant; Chandley, Michelle; Xu, Yao-Yu; Zhu, Meng-Yang; Ordway, Gregory A

    2010-01-01

    Treatment of rats with reserpine, an inhibitor of the vesicular monoamine transporter (VMAT), depletes norepinephrine (NE) and regulates NE transporter (NET) expression. The present study examined the molecular mechanisms involved in regulation of the NET by reserpine using cultured cells. Exposure of rat PC12 cells to reserpine for a period as short as 5min decreased [(3)H]NE uptake capacity, an effect characterized by a robust decrease in the V(max) of the transport of [(3)H]NE. As expected, reserpine did not displace the binding of [(3)H]nisoxetine from the NET in membrane homogenates. The potency of reserpine for reducing [(3)H]NE uptake was dramatically lower in SK-N-SH cells that have reduced storage capacity for catecholamines. Reserpine had no effect on [(3)H]NE uptake in HEK-293 cells transfected with the rat NET (293-hNET), cells that lack catecholamine storage vesicles. NET regulation by reserpine was independent of trafficking of the NET from the cell surface. Pre-exposure of cells to inhibitors of several intracellular signaling cascades known to regulate the NET, including Ca(2+)/Ca(2+)-calmodulin dependent kinase and protein kinases A, C and G, did not affect the ability of reserpine to reduce [(3)H]NE uptake. Treatment of PC12 cells with the catecholamine depleting agent, alpha-methyl-p-tyrosine, increased [(3)H]NE uptake and eliminated the inhibitory effects of reserpine on [(3)H]NE uptake. Reserpine non-competitively inhibits NET activity through a Ca(2+)-independent process that requires catecholamine storage vesicles, revealing a novel pharmacological method to modify NET function. Further characterization of the molecular nature of reserpine's action could lead to the development of alternative therapeutic strategies for treating disorders known to be benefitted by treatment with traditional competitive NET inhibitors. Copyright 2010 Elsevier Ltd. All rights reserved.

  17. Container material and design considerations for storage of low-level radioactive waste

    International Nuclear Information System (INIS)

    Temus, C.J.

    1987-01-01

    With the threat of increased burial site restrictions and increased surcharges; the ease with which waste is sent to the burial site has been reduced. For many generators of waste the only alternative after maximizing volume reduction efforts is to store the waste. Even after working through the difficult decision of deciding what type of storage facility to have, the decision of what type of container to store the waste in has to still be made. This paper explores the many parameters that affect not only the material selection but also the design. The proper selection of materials affect the ability of the container to survive the storage period. The material selection also directly affects the design and utilization of the storage facility. The impacts to the facility include the functional aspects as well as its operational cost and liability as related to such things as fire insurance and active environmental control systems. The advantages and disadvantages of many of the common systems such as carbon steel, various coatings, polyethylene, stainless steel, composites and concrete will be discussed and evaluated. Recognizing that the waste is to be disposed of in the future differentiates it from waste that is shipped directly to the disposal site. The stored waste has to have the capability to be handled not only once like the disposal site waste but potentially several times before ultimate disposal. This handling may be by several different systems both at the storage facility and the burial site. Some of these systems due to ALARA considerations are usually remote requiring various interfaces, while not interfering with handling, transportation or disposal operations

  18. Performance of Four Transport and Storage Systems for Molecular Detection of Multidrug-Resistant Tuberculosis

    Science.gov (United States)

    Rabodoarivelo, Marie Sylvianne; Imperiale, Bélen; andrianiavomikotroka, Rina; Brandao, Angela; Kumar, Parveen; Singh, Sarman; Ferrazoli, Lucilaine; Morcillo, Nora; Rasolofo, Voahangy; Palomino, Juan Carlos; Vandamme, Peter; Martin, Anandi

    2015-01-01

    Background Detection of drug-resistant tuberculosis is essential for the control of the disease but it is often hampered by the limitation of transport and storage of samples from remote locations to the reference laboratory. We performed a retrospective field study to evaluate the performance of four supports enabling the transport and storage of samples to be used for molecular detection of drug resistance using the GenoType MTBDRplus. Methods Two hundred Mycobacterium tuberculosis strains were selected and spotted on slides, FTA cards, GenoCards, and in ethanol. GenoType MTBDRplus was subsequently performed with the DNA extracted from these supports. Sensitivity and specificity were calculated and compared to the results obtained by drug susceptibility testing. Results For all supports, the overall sensitivity and specificity for detection of resistance to RIF was between 95% and 100%, and for INH between 95% and 98%. Conclusion The four transport and storage supports showed a good sensitivity and specificity for the detection of resistance to RIF and INH in M. tuberculosis strains using the GenoType MTBDRplus. These supports can be maintained at room temperature and could represent an important alternative cost-effective method useful for rapid molecular detection of drug-resistant TB in low-resource settings. PMID:26431352

  19. Office of Storage and Transportation Systems quality assurance directive

    International Nuclear Information System (INIS)

    1986-10-01

    This Directive provides policy guidance, defines organizational authorities and responsibilities for quality assurance (QA) and establishes minimum acceptable requirements for assuring the quality of all programs under the overall direction of the OSTS. This directive provides guidance for preparation of subordinate QA documents (e.g., QA plans, procedures) for the major Office of Storage and Transportation Systems programs that support DOE licensing and/or certification objectives. In turn, those highly specific QA documents will amplify the general guidance presented in this Directive

  20. 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)

  1. 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

  2. Transport and storage of spent fuel in Germany - possibilities for more safety

    International Nuclear Information System (INIS)

    Brennecke, P.; Fasten, Ch.; Nitsche, F.

    2004-01-01

    The safe transport of spent fuel from nuclear power plants in Germany is ensured by compliance with the dangerous goods transport regulations of class 7 which are fully consistent with the IAEA Transport Regulations and in parallel with the regulations of the German Atomic Energy Act. The purpose of this paper is to give an overview of this legal basis and the appropriate regulations applicable to spent fuel transport in Germany. Some aspects of the status and the future development of spent fuel shipments are described including experiences since resumption of those shipments in 2001. Furthermore, the status of licensing of on-site interim storage, assessments of an terrorist attack as well as consequences resulting from changes in energy policy are given

  3. 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

    There have been a lot of problems related to fuel and ash handling systems since the combustion of different types of biofuels started in the 70s. Many measures have been taken to solve some of the problems, but others have become part of the daily work. The purpose of this study has been to do a compilation of the fuel and ash handling problems that exist at different types of heat and power plants. The study over problems related to fuel and ash handling systems has been carried out through a questionnaire via the Internet. Directors at about 150 energy production plants were contacted by phone or e-mail in the beginning of the project and asked to participate in the study. 72 of these plants accepted to fill in the questionnaire. After several reminders by e-mails and phone calls there were in the end 32 plants that completed the form. Together they reported about 25 problems related to fuel handling and 27 problems related to ash handling. In general each of the plants reported one problem of each kind. Even if the material from the questionnaire is not enough to make statistical analysis a few conclusions can be made about the most common problems, the cause of the problems and where they appear. Fuel handling problems that occur at several plants are stoppage in the conveying equipment, bridging in the boiler silo or the tipping bunker and problems with the sieve for separation. The distribution of the fuel handling problems is almost equal for all equipment parts (receiving, separation, transport etc.). For the ash handling systems problems with transport of dry bottom ash dominate, followed by and the moistening of fly ash and transport of wet bottom ash. Most of the problems related to fuel handling are caused by the fuel quality. For example several plants have reported that bark is a fuel that is hard to handle. Nevertheless the quality for a specific fuel is not always bad when it is delivered to the plant but the fuel quality might change during

  4. 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.

  5. A comparison of radiation doses and risks between spent fuel transport/storage and selected non-nuclear activities

    International Nuclear Information System (INIS)

    Pennington, C.W.

    2003-01-01

    Spent fuel transport and storage have achieved an exemplary safety record over four decades within both the United States (US) and the global community at large. This paper offers an assessment demonstrating the safety of spent fuel transport and storage packagings relative to currently accepted but unregulated non-nuclear activities and practices within society. Over the last quarter of a century, several spent fuel transport and storage packaging test programmes have produced data that allow calculation of potential releases and population doses resulting from a terrorist attack. The US Department of Energy (DOE) has used this information to develop projected worst-case, low probability population exposures as part of the Final Environmental Impact Statement (FEIS) for the Yucca Mountain repository. The paper discusses potential population exposures from these packagings based on analysis and testing under beyond-design-basis (BDB) events, including missile attacks, and then defines and defends an acceptance criterion for the bounding outcomes of these events, based upon current accepted activities within society that produce high radiation doses to the general public. These activities involve unregulated technologies and practices within society that yield population doses significantly exceeding those that would result from such hypothetical and highly improbable events as a terrorist missile attack on a spent fuel transport or storage packaging. In particular, technologically enhanced natural radiation (TENR) exposures from building materials, farming, and masonry construction are highlighted. Recent landmark work by the US National Academy of Sciences (NAS) and by the United Nations Scientific Committee on the Effects of Atomic Radiation (UNSCEAR) are cited in support of this assessment, along with work from the US Environmental Protection Agency (EPA). From this compelling evidence, it is concluded that spent fuel transport and storage represent a low

  6. Changes in chemical quality indices during long-term storage of palm-olein oil under heated storage and transport-type conditions

    CSIR Research Space (South Africa)

    Van der Merwe, GH

    2004-01-15

    Full Text Available of Food and Agriculture J Sci Food Agric 84:52?58 (online: 2003) DOI: 10.1002/jsfa.1609 Changes in chemical quality indices during long-term storage of palm-olein oil under heated storage and transport-type conditions Gretel H van der Merwe,1asteriskmath... Lourens M du Plessis1 and John RN Taylor2 1CSIR Bio/Chemtek, PO Box 395, Pretoria 0001, South Africa 2Department of Food Science, University of Pretoria, Pretoria 0002, South Africa Abstract: Six quality indices, namely free fatty acids (FFA), peroxide...

  7. 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.

  8. Transporting existing VSC-24 canisters using a risk-based licensing approach

    Energy Technology Data Exchange (ETDEWEB)

    Srinivasan, R.; Sisley, S.E.; Hopf, J.E. [BNFL Fuel Solutions, Campbell, CA (United States)

    2004-07-01

    The eventual disposition of the spent fuel assemblies loaded in canisters and casks currently designed and licensed only for on-site storage is an industry-wide issue. The canister-specific BUC evaluation approach developed by BFS can be used to license many of these storage canisters and casks for transportation. This will allow these storage canisters and casks to be transported intact to a long-term storage facility or repository, thereby minimizing fuel handling operations, impact on plant operations, and occupational exposure, as well as total infrastructure costs. Application of the proposed canister-specific BUC analysis approach to a preliminary evaluation of the 58 loaded MSBs demonstrates the benefits of this approach. The results of this preliminary evaluation show that a more rigorous analysis based on the known characteristics of the loaded spent fuel, rather than the design-basis fuel parameters, produces significantly lower maximum keff values and can be used to qualify many of the existing loaded storage canisters for transportation. Transportation certification for storage canisters having more reactive spent fuel payloads may require reliance on BUC approaches that are more aggressive than current NRC guidelines allow. Credit may be required for fission- product isotopes that do not have sufficient chemical assay data for benchmarking. In addition, reduced criticality safety margins may be required. For these more-aggressive BUC approaches, a risk assessment should be provided to support the NRC-approval basis. The risk assessment should evaluate the possibility and consequences of an accidental criticality event based upon inaccuracies in the characterization of the spent-fuel payloads.

  9. Transporting existing VSC-24 canisters using a risk-based licensing approach

    International Nuclear Information System (INIS)

    Srinivasan, R.; Sisley, S.E.; Hopf, J.E.

    2004-01-01

    The eventual disposition of the spent fuel assemblies loaded in canisters and casks currently designed and licensed only for on-site storage is an industry-wide issue. The canister-specific BUC evaluation approach developed by BFS can be used to license many of these storage canisters and casks for transportation. This will allow these storage canisters and casks to be transported intact to a long-term storage facility or repository, thereby minimizing fuel handling operations, impact on plant operations, and occupational exposure, as well as total infrastructure costs. Application of the proposed canister-specific BUC analysis approach to a preliminary evaluation of the 58 loaded MSBs demonstrates the benefits of this approach. The results of this preliminary evaluation show that a more rigorous analysis based on the known characteristics of the loaded spent fuel, rather than the design-basis fuel parameters, produces significantly lower maximum keff values and can be used to qualify many of the existing loaded storage canisters for transportation. Transportation certification for storage canisters having more reactive spent fuel payloads may require reliance on BUC approaches that are more aggressive than current NRC guidelines allow. Credit may be required for fission- product isotopes that do not have sufficient chemical assay data for benchmarking. In addition, reduced criticality safety margins may be required. For these more-aggressive BUC approaches, a risk assessment should be provided to support the NRC-approval basis. The risk assessment should evaluate the possibility and consequences of an accidental criticality event based upon inaccuracies in the characterization of the spent-fuel payloads

  10. Remote handling of canisters containing nuclear waste in glass at the Savannah River Plant

    International Nuclear Information System (INIS)

    Callan, J.E.

    1986-01-01

    The Defense Waste Processing Facility is being constructed at the Savannah River Plant at a cost of $870 million to immobilize the defense high-level radioactive waste. This radioactive waste is being added to borosilicate glass for later disposal in a federal repository. The borosilicate glass is poured into stainless steel canisters for storage. These canisters must be handled remotely because of their high radioactivity, up to 5000 R/h. After the glass has been poured into the canister which will be temporarily sealed, it is transferred to a decontamination cell and decontaminated. The canister is then transferred to the weld cell where a permanent cap is welded into place. The canisters must then be transported from the processing building to a storage vault on the plant until the federal repository is available. A shielded canister transporter (SCT) has been designed and constructed for this purpose. The design of the SCT vehicle allows the safe transport of a highly radioactive canister containing borosilicate glass weighing 2300 kg with a radiation level up to 5000 R/h from one building to another. The design provides shielding for the operator in the cab of the vehicle to be below 0.5 rem/h. The SCT may also be used to load the final shipping cask when the federal repository is ready to receive the canisters

  11. Test plan for K-Basin fuel handling tools

    International Nuclear Information System (INIS)

    Bridges, A.E.

    1995-01-01

    The purpose of this document is to provide the test plan and procedures for the acceptance testing of the handling tools enveloped for the removal of an N-Reactor fuel element from its storage canister in the K-Basins storage pool and insertion into the Single fuel Element Can for subsequent shipment to a Hot Cell for examination. Examination of these N-Reactor fuel elements is part of the overall characterization effort. New hand tools were required since previous fuel movement has involved grasping the fuel in a horizontal position. The 305 Building Cold Test Facility will be used to conduct the acceptance testing of the Fuel Handling Tools. Upon completion of this acceptance testing and any subsequent training of operators, the tools will be transferred to the 105 KW Basin for installation and use

  12. Update of Nuclear Waste Policy Act transportation activities

    International Nuclear Information System (INIS)

    Callaghan, E.F.

    1987-01-01

    As directed by the Nuclear Waste Policy Act of 1982 (NWPA), the Department of Energy (DOE) is developing a nationwide system for transporting spent nuclear fuel and high-level radioactive waste from commercial power plants to deep geologic repositories for disposal. Plans for the transportation system will consider the following factors: the President's 1985 decision to co-locate some defense high-level waste with commercial waste in a repository, the NWPA requirement that the private sector be used to the fullest extent possible in developing and operating the system, and the possible approval by Congress of the DOE's proposal for a Monitored Retrievable Storage (MRS) facility, submitted in March 1987. (The MRS, if approved, would provide for the consolidation, packaging, and perhaps the temporary storage of spent fuel from reactors.) The ''Transportation Business Plan'', published in January 1986, reflects these considerations. The transportation system, when operational, will consist of two elements: (1) the cask system, which includes the transportation casks, the vehicular conveyances, tie-downs, and associated equipment for handling the casks; and (2) the transportation support system which is comprised of facilities, equipment, and services to support waste transportation. Development of the transportation system incorporates the following work elements: operational planning, support systems development, cash system development, systems analysis, and institutional activities. This paper focusses on the technical aspects of the system

  13. Dynamics of water transport and storage in conifers studied with deuterium and heat tracing techniques.

    Science.gov (United States)

    F.C. Meinzer; J.R. Brooks; J.-C. Domec; B.L. Gartner; J.M. Warren; D.R. Woodruff; K. Bible; D.C. Shaw

    2006-01-01

    The volume and complexity of their vascular systems make the dynamics of tong-distance water transport in large trees difficult to study. We used heat and deuterated water (D20) as tracers to characterize whole-tree water transport and storage properties in individual trees belonging to the coniferous species Pseudotsuga menziesii...

  14. NAC's Modular, Advanced Generation, Nuclear All-purpose STORage (MAGNASTOR) system: new generation multipurpose spent fuel storage for global application

    International Nuclear Information System (INIS)

    Pennington, C.W.

    2004-01-01

    Multipurpose canister systems (MCS) have been designed, licensed, fabricated, constructed, and loaded over the last decade within the U.S. These systems are characterized as concrete-based storage overpacks containing transportable canisters utilizing redundantly welded closures. Canisters are designed and intended to be transferred into transport packagings for shipment off-site, and canister designs do not preclude their use in waste disposal overpacks. NAC has learned a number of significant lessons in the deployment of its first generation MCS. During this period prior to the next procurement phase, NAC has developed a new generation MCS, incorporating the lessons learned from the first generation while considering the capabilities of the plants populating the next phase. The system is identified as the Modular, Advanced Generation, Nuclear All-purpose STORage (MAGNASTOR) system, and this paper addresses its unique design, fabrication, and operations features. Among these are: a unique developed cell basket design, under patent review, that increases spent fuel capacities and simplifies fabrication while providing high strength and heat removal efficiency: a significantly enhanced canister closure design that improves welding time, personnel dose, and drying performance: a low profile vertical concrete cask design that improves on-site handling and site dose rates, offers tangible threat limitations for beyond-design-basis events, and maintains proven and simple construction/operation features: a simple, proven transfer system that facilitates transfer without excessive dose or handling: a new approach to water removal and canister drying, using a moisture entrainment, gas absorption vacuum (MEGAVAC) system. The paper includes design and licensing status of the MAGNASTOR system, and prototyping development that NAC has performed to date

  15. Deep reversible storage. Design options for the storage in deep geological formation - High-medium activity, long living wastes 2009 milestone

    International Nuclear Information System (INIS)

    2010-09-01

    This report aims at presenting a synthesis of currently studied solutions for the different components of the project of deep geological radioactive waste storage centre. For each of these elements, the report indicates the main operational objectives to be taken into account in relationship with safety functions or with reversibility. It identifies the currently proposed design options, presents the technical solutions (with sometime several possibilities), indicates industrial references (in the nuclear sector, in underground works) and comments results of technological tests performed by the ANDRA. After a description of functionalities and of the overall organisation of storage components, the different following elements and aspects are addressed: surface installations, underground architecture, parcel transfer between the surface and storage cells, storage container for medium-activity long-life (MAVL) waste, storage cell for medium-activity long-life waste, handling of MAVL parcels in storage cells, storage container for high-activity (HA) waste, storage cell for HA waste, handling of HA parcels in storage cells, and works for site closing

  16. Waste Handling Building Conceptual Study

    International Nuclear Information System (INIS)

    G.W. Rowe

    2000-01-01

    The objective of the ''Waste Handling Building Conceptual Study'' is to develop proposed design requirements for the repository Waste Handling System in sufficient detail to allow the surface facility design to proceed to the License Application effort if the proposed requirements are approved by DOE. Proposed requirements were developed to further refine waste handling facility performance characteristics and design constraints with an emphasis on supporting modular construction, minimizing fuel inventory, and optimizing facility maintainability and dry handling operations. To meet this objective, this study attempts to provide an alternative design to the Site Recommendation design that is flexible, simple, reliable, and can be constructed in phases. The design concept will be input to the ''Modular Design/Construction and Operation Options Report'', which will address the overall program objectives and direction, including options and issues associated with transportation, the subsurface facility, and Total System Life Cycle Cost. This study (herein) is limited to the Waste Handling System and associated fuel staging system

  17. Struggle against violations of the rules for radioactive materials storage, utilization, accounting and transport

    International Nuclear Information System (INIS)

    Iojrysh, A.I.

    1986-01-01

    Criminal punishments for violation of the rules of radioactive materials accounting, storage, utilization and transport or those for illegimate sending of these materials presupposed by the RSFSR criminal code are considered

  18. Criteria for recladding of spent light water reactor fuel before long term pool storage

    International Nuclear Information System (INIS)

    Pettersson, K.; Jansson, L.

    1979-01-01

    The question of the need for any special treatment of failed fuel elements prior to long term pool storage has been studied. It is concluded that the main problem appears to be hydride embrittlement of failed fuel rods, which may lead to increased damage during handling and transport of the failed fuel. Some mechanisms for the degradation of failed fuel rods have been identified. They can all be considered as relatively improbable, but further experimental evidence is needed before it can be concluded that these degradation mechanisms are insignificant during pool storage. The report also contains a review of methods for identification of leaking fuel bundles and fuel rods. (Auth.)

  19. Criteria for recladding of spent light water reactor fuel before long term pool storage

    International Nuclear Information System (INIS)

    Pettersson, K.; Jansson, L.

    1979-06-01

    The question of the need for any special treatment of failed fuel elements prior to long term pool storage has been studied. It is concluded that the main problem appears to be hydride embrittlement of failed fuel rods, which may lead to increased damage during handling and transport of the failed fuel. Some mechanisms for the degradation of failed fuel rods have been identified. They can all be considered as relatively improbable, but further experimental evidence is needed before it can be concluded that thede degradation mechanisms are insignificant during pool storage. The report also contains a review of methods for identification of leaking fuel bundles and fuel rods.(author)

  20. Transportation and storage studies on irradiated Alphonso mangoes

    International Nuclear Information System (INIS)

    Farkas, J.; Dharkar, S.D.; Sreenivasan, A.

    1972-01-01

    Control as well as skin coated (6% ''Myvacet'') and/or irradiated (25 to 35 krad) mangoes were packed in baskets in dry paddy straw and shipped by rail. After a storage at a temperature of 25 to 32 0 C for a period of 8 days, the baskets were shipped back. After receipt in the laboratory the fruits were kept under observation for 5 more days and then scored for ripening and marketability as assessed by appearance, skin gloss and typical flavour. 100 per cent of fruits skin-coated and irradiated were marketable at the end of the experiment. None of the unirradiated control fruits were saleable by this time, while 66%, of the irradiated fruits were in acceptable condition. In further experiments one dozen mangoes each from control, irradiated and skin-coated and irradiated groups were wrapped individually in tissue paper and packed tightly in a plyweed box. This consignment was air-lifted from Bombay to Budapest, a distance of about 5600 kilometers. The time interval between irradiation and their receipt in Hungary was 4 days. The mangoes were assessed for their storage characteristics by various parameters that included physiological loss in weight, puncture resistance of the skin, pulp texture, carotenoids, acidity and organoleptic attributes, at various periods during storage. It was found that ripening and senescence are strikingly delayed in mangoes by skin-coating and radiation treatment. The treated mangoes retained their skin-resistance while the disappearance of chlorophyl and formation of carotenoids were substantially delayed. Weight loss in storage was lower and reduction of acidity and formation of sugars in the fruit flesh took place later. Organoleptically, the fruits subjected to the combination treatment were good. These studies point to the feasibility of the combination treatment in prolonging the shelf life of fruits significantly to enable their transport to distant countries. (F.G.)

  1. Project B-589, 300 Area transuranic waste interim storage project engineering study

    International Nuclear Information System (INIS)

    Greenhalgh, W.O.

    1985-08-01

    The purpose of the study was to look at various alternatives of taking newly generated, remote-handled transuranic waste (caisson waste) in the 300 Area, performing necessary transloading operations and preparing the waste for storage. The prepared waste would then be retrieved when the Waste Isolation Pilot Plant becomes operational and transshipped to the repository in New Mexico with a minimum of inspection and packaging. The scope of this study consisted of evaluating options for the transloading of the TRU wastes for shipment to a 200 Area storage site. Preconceptual design information furnished as part of the engineering study is listed below: produce a design for a clean, sealed waste canister; hot cell loadout system for the waste; in-cell loading or handling equipment; determine transshipment cask options; determine assay system requirements (optional); design or specify transport equipment required; provide a SARP cost estimate; determine operator training requirements; determine waste compaction equipment needs if desirable; develop a cost estimate and approximate schedule for a workable system option; and update the results presented in WHC Document TC-2025

  2. Modification in existing SF6 gas handling system at 14UD BARC-TIFR Pelletron Accelerator, Mumbai

    International Nuclear Information System (INIS)

    Ninawe, N.G.; Gupta, S.K.; Ramjilal; Sparrow, Hillary; Sharma, S.C.; Bhagwat, P.V.; Salvi, S.B.

    2003-01-01

    BARC-TIFR 14 UD Pelletron Accelerator facility at TIFR, Mumbai is operational since inception 1989. The accelerator is housed inside a pressure vessel of 6 metre diameter, 25 metre long and 525m 3 volume. The accelerator tank is pressurized with SF 6 at 80 to 100 psig in order to achieve 14MV. The inventory of SF 6 gas is about 18,000 Kg (approximately) at 80 psig. SF 6 gas can be transported from Accelerator tank to storage tank using gas handling system, which consists of oil free compressor, vacuum pump, dust filters, oil filters, dryers etc

  3. Design support document for the K Basins Vertical Fuel Handling Tools

    International Nuclear Information System (INIS)

    Bridges, A.E.

    1995-01-01

    The purpose of this document is to provide the design support information for the Vertical Fuel Handling Tools, developed for the removal of N Reactor fuel elements from their storage canisters in the K Basins storage pool and insertion into the Single Fuel Element Can for subsequent shipment to a Hot Cell for examination. Examination of these N Reactor fuel elements is part of the overall characterization effort. These new hand tools are required since previous fuel movement has involved grasping the fuel in a horizontal position. These tools are required to lift an element vertically from the storage canister. Additionally, a Mark II storage canister Lip Seal Protector was designed and fabricated for use during fuel retrieval. This device was required to prevent damage to the canister lip should a fuel element accidentally be dropped during its retrieval, using the handling tools. Supporting documentation for this device is included in this document

  4. FY 1974 report on the results of the Sunshine Project. Study on a system to refine/transport/store hydrogen and the safety technology (Investigational study of the measuring control system for safety in the stage of low temperature storage and refining of hydrogen); 1974 nendo suiso no seisei, yuso, chozo system oyobi hoan gijutsu ni kansuru kenkyu seika hokokusho. Suiso no teion chozo, seisei dankai no anzen no tame no keisoku seigyo system ni kansuru chosa kenkyu

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1975-05-30

    Safety technology is necessary and indispensable for future materialization of a hydrogen energy system. The survey was made from a viewpoint of safety technology in refining hydrogen at low temperature and in storing it in a low temperature liquid state. Japan has so far had no experiences for the handling and consumption of liquid hydrogen except the partial use at laboratory. Accordingly, collected here was literature on the storage, transportation, handling, low temperature refining of the liquid, etc. The present state of technology in Japan and abroad was grasped and items in the safety relation were picked up. As to the existing literature on the hydrogen relation, there is much literature on the U.S. NASA project, and there is also much on practical business details such as the handling of a large quantity of liquid. Therefore, from each literature mostly on the above, the literature on the liquid storage, transportation use storage tank and refining method was reviewed and arranged, and at the same time, the items were picked up of the safe disposal method, disaster prevention relation, and measuring relation. The paper also arranged the results of surveying hydrogen physical properties and equipment materials which are closely related to safety general, in particular, and examples of disaster. (NEDO)

  5. 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.

  6. 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)

  7. Storage device of reactor fuel

    International Nuclear Information System (INIS)

    Nakamura, Masaaki.

    1997-01-01

    The present invention concerns storage of spent fuels and provides a storage device capable of securing container-cells in shielding water by remote handling and moving and securing the container-cells easily. Namely, a horizontal support plate has a plurality of openings formed in a lattice like form and is disposed in a pit filled with water. The container-cell has a rectangular cross section, and is inserted and disposed vertically in the openings. Securing members are put between the container-cells above the horizontal support plate, and constituted so as to be expandable from above by remote handling. The securing member is preferably comprised of a vertical screw member and an expandable urging member. Since securing members for securing the container-cells for incorporating reactor fuels are disposed to the horizontal support plate controllable from above by the remote handling, fuel storage device can be disposed without entering into a radiation atmosphere. The container-cells can be settled and exchanged easily after starting of the use of a fuel pit. (I.S.)

  8. 49 CFR 1510.11 - Handling of security service fees.

    Science.gov (United States)

    2010-10-01

    ... air carrier holds neither legal nor equitable interest in the security service fees except for the... 49 Transportation 9 2010-10-01 2010-10-01 false Handling of security service fees. 1510.11 Section 1510.11 Transportation Other Regulations Relating to Transportation (Continued) TRANSPORTATION SECURITY...

  9. Spatial and intertemporal arbitrage in the California natural gas transportation and storage network

    Science.gov (United States)

    Uria Martinez, Rocio

    Intertemporal and spatial price differentials should provide the necessary signals to allocate a commodity efficiently inside a network. This dissertation investigates the extent to which decisions in the California natural gas transportation and storage system are taken with an eye on arbitrage opportunities. Daily data about flows into and out of storage facilities in California over 2002-2006 and daily spreads on the NYMEX futures market are used to investigate whether the injection profile is consistent with the "supply-of-storage" curve first observed by Working for wheat. Spatial price differentials between California and producing regions fluctuate throughout the year, even though spot prices at trading hubs across North America are highly correlated. In an analysis of "residual supply", gas volumes directed to California are examined for the influence of those fluctuations in locational differentials. Daily storage decisions in California do seem to be influenced by a daily price signal that combines the intertemporal spread and the locational basis between California and the Henry Hub, in addition to strong seasonal and weekly cycles. The timing and magnitude of the response differs across storage facilities depending on the regulatory requirements they face and the type of customers they serve. In contrast, deviations in spatial price differentials from the levels dictated by relative seasonality in California versus competing regions do not trigger significant reallocations of flows into California. Available data for estimation of both the supply-of-storage and residual-supply curves aggregate the behavior of many individuals whose motivations and attentiveness to prices vary. The resulting inventory and flow profiles differ from those that a social planner would choose to minimize operating costs throughout the network. Such optimal allocation is deduced from a quadratic programming model, calibrated to 2004-2005, that acknowledges relative seasonality

  10. Licensing of spent nuclear fuel dry storage in Russia

    International Nuclear Information System (INIS)

    Kislov, A.I.; Kolesnikov, A.S.

    1999-01-01

    The Federal nuclear and radiation safety authority of Russia (Gosatomnadzor) being the state regulation body, organizes and carries out the state regulation and supervision for safety at handling, transport and storage of spent nuclear fuel. In Russia, the use of dry storage in casks will be the primary spent nuclear fuel storage option for the next twenty years. The cask for spent nuclear fuel must be applied for licensing by Gosatomnadzor for both storage and transportation. There are a number of regulations for transportation and storage of spent nuclear fuel in Russia. Up to now, there are no special regulations for dry storage of spent nuclear fuel. Such regulations will be prepared up to the end of 1998. Principally, it will be required that only type B(U)F, packages can be used for interim storage of spent nuclear fuel. Recently, there are two dual-purpose cask designs under consideration in Russia. One of them is the CONSTOR steel concrete cask, developed in Russia (NPO CKTI) under the leadership of GNB, Germany. The other cask design is the TUK-104 cask of KBSM, Russia. Both cask types were designed for spent nuclear RBMK fuel. The CONSTOR steel concrete cask was designed to be in full compliance with both Russian and IAEA regulations for transport of packages for radioactive material. The evaluation of the design criteria by Russian experts for the CONSTOR steel concrete cask project was performed at a first stage of licensing (1995 - 1997). The CONSTOR cask design has been assessed (strength analysis, thermal physics, nuclear physics and others) by different Russian experts. To show finally the compliance of the CONSTOR steel concrete cask with Russian and IAEA regulations, six drop tests have been performed with a 1:2 scale model manufactured in Russia. A test report was prepared. The test results have shown that the CONSTOR cask integrity is guaranteed under both transport and storage accident conditions. The final stage of the certification procedure

  11. Peak cladding temperature in a spent fuel storage or transportation cask

    International Nuclear Information System (INIS)

    Li, J.; Murakami, H.; Liu, Y.; Gomez, P.E.A.; Gudipati, M.; Greiner, M.

    2007-01-01

    From reactor discharge to eventual disposition, spent nuclear fuel assemblies from a commercial light water reactor are typically exposed to a variety of environments under which the peak cladding temperature (PCT) is an important parameter that can affect the characteristics and behavior of the cladding and, thus, the functions of the spent fuel during storage, transportation, and disposal. Three models have been identified to calculate the peak cladding temperature of spent fuel assemblies in a storage or transportation cask: a coupled effective thermal conductivity and edge conductance model developed by Manteufel and Todreas, an effective thermal conductivity model developed by Bahney and Lotz, and a computational fluid dynamics model. These models were used to estimate the PCT for spent fuel assemblies for light water reactors under helium, nitrogen, and vacuum environments with varying decay heat loads and temperature boundary conditions. The results show that the vacuum environment is more challening than the other gas environments in that the PCT limit is exceeded at a lower boundary temperature for a given decay heat load of the spent fuel assembly. This paper will highlight the PCT calculations, including a comparison of the PCTs obtained by different models.

  12. Specific transport and storage solutions: Waste management facing current and future stakes of the nuclear fuel cycle

    International Nuclear Information System (INIS)

    Deniau, Helene; Gagner, Laurent; Gendreau, Francoise; Presta, Anne

    2006-01-01

    With major projects ongoing or being planned, and also with the daily management of radioactive waste from nuclear facilities, the role of transport and/or storage packaging has been often overlooked. Indeed, the packaging development process and transport solutions implemented are a key part of the waste management challenge: protection of people and environment. During over four decades, the AREVA Group has developed a complete and coherent system for the transport of waste produced by nuclear industries. The transport solutions integrate the factors to consider, as industrial transportation needs, various waste forms, associated hazards and current regulations. Thus, COGEMA LOGISTICS has designed, licensed and manufactured a large number of different transport, storage and dual purpose cask models for residues and all kinds of radioactive wastes. The present paper proposes to illustrate how a company acting both as a cask designer and a carrier is key to the waste management issue and how it can support the waste management policy of nuclear producers through their operational choices. We will focus on the COGEMA LOGISTICS technical solutions implemented to guarantee safe and secure transportation and storage solutions. We will describe different aspects of the cask design process, insisting on how it enables to fulfill both customer needs and regulation requirements. We will also mention the associated services developed by the AREVA Business Unit Logistics (COGEMA LOGISTICS, TRANSNUCLEAR, MAINCO, and LEMARECHAL CELESTIN) in order to manage transportation of liquid and solid waste towards interim or final storage sites. The paper has the following contents: About radioactive waste; - Radioactive waste classification; - High level activity waste and long-lived intermediate level waste; - Long-lived low level waste; - Short-lived low- and intermediate level waste; - Very low level waste; - The radioactive waste in nuclear fuel cycle; - Packaging design and

  13. Japanese perspectives and research on packaging, transport and storage of spent fuel

    International Nuclear Information System (INIS)

    Saegusa, T.; Ito, C.; Yamakawa, H.; Shirai, K.

    2004-01-01

    The Japanese policy on spent fuel is reprocessing. Until, reprocessed, spent fuel shall be stored properly. This paper overviews current status of transport and storage of spent fuel with related research in Japan. The research was partly carried out under a contract of Ministry of Economy, Trade and Industry of the Japanese government

  14. Performance assessment of the proposed Monitored Retrievable Storage Facility

    International Nuclear Information System (INIS)

    Chockie, A.D.; Hostick, C.J.; Winter, C.

    1986-02-01

    Pacific Northwest laboratory (PNL) has completed a performance evaluation of the proposed monitored retrievable storage (MRS) facility. This study was undertaken as part of the Department of Energy MRS Program at PNL. The objective of the performance evaluation was to determine whether the conceptual MRS facility would be able to process spent fuel at the specified design rate of 3600 metric tons of uranium (MTU) per year. The performance of the proposed facility was assessed using the computer model COMPACT (Computer Optimization of Processing and Cask Transport) to simulate facility operations. The COMPACT model consisted of three application models each of which addressed a different aspect of the facility's operation: MRS/waste transportation interface; cask handling capability; and disassembly/consolidation (hot cell) operations. Our conclusions, based on the assessment of design criteria for the proposed facility, are as follows: Facilities and equipment throughout the facility have capability beyond the 3600 MTU/y design requirement. This added capability provides a reserve to compensate for unexpected perturbations in shipping or handling of the spent fuel. Calculations indicate that the facility's maximum maintainable processing capability is approximately 4800 MTU/y

  15. Handling and Transport Problems; Problemes de Manipulation et de Transport; 041f 0420 041e 0414 ; Problemas de Manipulacion y de Transporte

    Energy Technology Data Exchange (ETDEWEB)

    Pomarola, J.; Savouyaud, J. [Service de Controle des Radiations et de Genie Radioactif, Commissariat a l' Energie Atomique, Saclay (France)

    1960-07-01

    I. The handling and transport of radioactive waste involves the risk of irradiation and contamination. It is necessary to draw up special regulations governing the removal and transport of waste within the centres or from one centre to another, and to entrust transport to a group in charge of specialized teams. The organization, equipment and efficiency of such teams is then considered. II. Certain types of transport operation are particularly dangerous and require special transport units and fixed installations. This applies, in particular, to the disposal of highly radioactive liquids. A description is given of a composite transport unit, consisting of a towing vehicle, semi-trailer and tank holding 500 l of liquid with an activity of up to 1,000 c/l. The drawing-off of the liquid waste, routing of the transport unit and precautions to be taken are discussed. (author) [French] I - La manipulation et le j transport des dechets radioactifs presentent des dangers d'irradiation et de contamination. Il est necessaire: - d'edicter des consignes speciales applicables a l'enlevement et au transport des dechets dans les centres ou de centre a centre. - de confier les transports a un groupe dont relevent des equipes specialisees. On examine l'organisation, les moyens, le rendement de ces equipes. II - Certains transports sont particulierement dangereux et necessitent des engins speciaux et des installations fixes. C'est le cas, notamment, de l'evacuation des liquides tres actifs. On decrit : Inverted-Exclamation-Mark - un engin de transport compose d'un ensemble: tracteur, semi- remorque et d'un recipient qui contient 500 litres de liquide dont l'activite peut atteindre 1.000 c/l. - les operations de transvasement, l'acheminement de l'engin, les precautions prises. (author) [Spanish] I - La manipulacion y el transporte de desechos radiactivos ofrecen riesgos de irradiacion y de contaminacion. Es necesario: - dictar consignas especiales para retirar los desechos y para su

  16. 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

  17. 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

  18. Crane Scheduling for a Plate Storage

    DEFF Research Database (Denmark)

    Hansen, Jesper; Clausen, Jens

    2002-01-01

    Odense Steel Shipyard produces the worlds largest container ships. The first process of producing the steel ships is handling arrival and storage of steel plates until they are needed in production. This paper considers the problem of scheduling two cranes that carry out the movements of plates...... into, around and out of the storage. The system is required to create a daily schedule for the cranes, but also handle possible disruptions during the execution of the plan. The problem is solved with a Simulated Annealing algorithm....

  19. MRS systems study, Task F: Transportation impacts of a monitored retrievable storage facility

    Energy Technology Data Exchange (ETDEWEB)

    Brentlinger, L.A.; Gupta, S.; Plummer, A.M.; Smith, L.A.; Tzemos, S.

    1989-05-01

    The passage of the Nuclear Waste Policy Amendments Act of 1987 (NWPAA) modified the basis from which the Office of Civilian Radioactive Waste Management (OCRWM) had derived and developed the configuration of major elements of the waste system (repository, monitored retrievable storage, and transportation). While the key aspects of the Nuclear Waste Policy Act of 1982 remain unaltered, NWPAA provisions focusing site characterization solely at Yucca Mountain, authorizing a monitored retrievable storage (MRS) facility with specific linkages to the repository, and establishing an MRS Review Commission make it prudent for OCRWM to update its analysis of the role of the MRS in the overall waste system configuration. This report documents the differences in transportation costs and radiological dose under alternative scenarios pertaining to a nuclear waste management system with and without an MRS, to include the effect of various MRS packaging functions and locations. The analysis is limited to the impacts of activities related directly to the hauling of high-level radioactive waste (HLW), including the capital purchase and maintenance costs of the transportation cask system. Loading and unloading impacts are not included in this study because they are treated as facility costs in the other task reports. Transportation costs are based on shipments of 63,000 metric tons of uranium (MTU) of spent nuclear fuel and 7,000 MTU equivalent of HLW. 10 refs., 41 tabs.

  20. Legal precedents regarding use and defensibility of risk assessment in Federal transportation of SNF and HLW

    International Nuclear Information System (INIS)

    Bentz, E.J. Jr.; Bentz, C.B.; O'Hora, T.D.; Chen, S.Y.

    1997-01-01

    Risk assessment has become an increasingly important and essential tool in support of Federal decision-making regarding the handling, storage, disposal, and transportation of spent nuclear fuel (SNF) and high-level radioactive waste (HLW). This paper analyzes the current statutory and regulatory framework and related legal precedents with regard to SNF and HLW transportation. The authors identify key scientific and technical issues regarding the use and defensibility of risk assessment in Federal decision-making regarding anticipated shipments

  1. Hydrogen Storage Technologies for Future Energy Systems.

    Science.gov (United States)

    Preuster, Patrick; Alekseev, Alexander; Wasserscheid, Peter

    2017-06-07

    Future energy systems will be determined by the increasing relevance of solar and wind energy. Crude oil and gas prices are expected to increase in the long run, and penalties for CO 2 emissions will become a relevant economic factor. Solar- and wind-powered electricity will become significantly cheaper, such that hydrogen produced from electrolysis will be competitively priced against hydrogen manufactured from natural gas. However, to handle the unsteadiness of system input from fluctuating energy sources, energy storage technologies that cover the full scale of power (in megawatts) and energy storage amounts (in megawatt hours) are required. Hydrogen, in particular, is a promising secondary energy vector for storing, transporting, and distributing large and very large amounts of energy at the gigawatt-hour and terawatt-hour scales. However, we also discuss energy storage at the 120-200-kWh scale, for example, for onboard hydrogen storage in fuel cell vehicles using compressed hydrogen storage. This article focuses on the characteristics and development potential of hydrogen storage technologies in light of such a changing energy system and its related challenges. Technological factors that influence the dynamics, flexibility, and operating costs of unsteady operation are therefore highlighted in particular. Moreover, the potential for using renewable hydrogen in the mobility sector, industrial production, and the heat market is discussed, as this potential may determine to a significant extent the future economic value of hydrogen storage technology as it applies to other industries. This evaluation elucidates known and well-established options for hydrogen storage and may guide the development and direction of newer, less developed technologies.

  2. Analysis of radiation doses from operation of postulated commercial spent fuel transportation systems: Analysis of a system containing a monitored retrievable storage facility

    International Nuclear Information System (INIS)

    Smith, R.I.; Daling, P.M.; Faletti, D.W.

    1992-04-01

    This addendum report extends the original study of the estimated radiation doses to the public and to workers resulting from transporting spent nuclear fuel from commercial nuclear power reactor stations through the federal waste management system (FWMS), to a system that contains a monitored retrievable storage (MRS) facility. The system concepts and designs utilized herein are consistent with those used in the original study (circa 1985--1987). Because the FWMS design is still evolving, the results of these analyses may no longer apply to the design for casks and cask handling systems that are currently being considered. Four system scenarios are examined and compared with the reference No-MRS scenario (all spent fuel transported directly from the reactors to the western repository in standard-capacity truck and rail casks). In Scenarios 1 and 2, an MRS facility is located in eastern United States and ships either intact fuel assemblies or consolidated fuel rods and compacted assembly hardware in canisters. In Scenarios 3 and 4, an MRS facility is located in the western United States and ship either intact fuel assemblies or consolidated fuel rods and compacted assembly hardware in canisters

  3. Performance of CASTOR {sup registered} HAW cask cold trials for loading, Transport and storage of HAW canisters

    Energy Technology Data Exchange (ETDEWEB)

    Wilmsmeier, Marco; Horn, Thomas; Graf, Wilhelm [GNS Gesellschaft fuer Nuklear-Service mbH (Germany)

    2009-07-01

    With over 30 years of experience in the design, manufacturing, assembly and loading of CASTOR {sup registered} casks, GNS is one of the worldwide leading suppliers of casks for the transport and storage of spent fuel assemblies as well as for canisters with vitrified high active wastes (meanwhile over 1.000 casks loaded and stored and more than 1.500 ordered). GNS's products are used at around 30 sites worldwide for a wide range of inventories from pressurised and boiling water reactor fuels (PWR, VVER and BWR, RBMK), thorium high-temperature reactor fuels (THTR) and research reactor fuels (MTR) to vitrified high active wastes (HAW) from reprocessing plants. GNS is responsible for all nuclear wastes resulting from German Nuclear Power Plants and assists and/or performs in the loading and dispatch of CASTOR {sup registered} casks as well as their transport to and storage at central interim storage facilities and local interim storage areas. (orig.)

  4. 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

  5. Experimental insights into organic carbon oxidation potential during fluvial transport without floodplain storage

    Science.gov (United States)

    Scheingross, J. S.; Hovius, N.; Sachse, D.; Vieth-Hillebrand, A.; Turowski, J. M.; Hilton, R. G.

    2016-12-01

    Over geologic timescales, the exchange of organic carbon (OC) between the atmosphere, rock, and biosphere is thought to be a major control on global climate. CO2 flux estimates from oxidation of rock-derived OC and sequestration of biospheric OC during fluvial transit from source to sink are approximately the same order of magnitude or larger than those from silicate weathering. Despite field data showing loss of OC moving downstream in lowland rivers, it is unclear if losses occur primarily during active fluvial transport within the river, where OC is in continual motion within an aerated environment, or during longer periods when OC is temporarily stored in river floodplains which may be anoxic. This represents a major knowledge gap, as the unknown location of OC oxidation (i.e., river vs. floodplain) limits our ability to develop process-based models that can be employed to predict OC losses, constrain carbon budgets, and unravel links between climate, tectonics, and erosion. To fill this gap, we investigated the potential for OC oxidation in laboratory experiments simulating fluvial transport without floodplain storage. Mixtures of OC-rich and siliciclastic sediment were transported for distances of 2000 km in annular flumes while making time-series measurements of sediment TOC and water DOC concentrations. Initial results for transport of OC-rich soil show increasing DOC with transport distance to levels that represent a transfer of 2% of the total OC from the solid to the dissolved phase; however, we observed no detectable change in the solid-phase TOC. Similar results were obtained in a control experiment with identical sediment in still water. These preliminary results suggest minimal OC oxidation within our experiment, and, to the extent that such experiments represent natural transport through river systems, are consistent with the hypothesis that OC losses may occur primarily during floodplain storage rather than fluvial transport.

  6. Heat in the Barents Sea: transport, storage, and surface fluxes

    Directory of Open Access Journals (Sweden)

    L. H. Smedsrud

    2010-02-01

    Full Text Available A column model is set up for the Barents Sea to explore sensitivity of surface fluxes and heat storage from varying ocean heat transport. Mean monthly ocean transport and atmospheric forcing are synthesised and force the simulations. Results show that by using updated ocean transports of heat and freshwater the vertical mean hydrographic seasonal cycle can be reproduced fairly well.

    Our results indicate that the ~70 TW of heat transported to the Barents Sea by ocean currents is lost in the southern Barents Sea as latent, sensible, and long wave radiation, each contributing 23–39 TW to the total heat loss. Solar radiation adds 26 TW in the south, as there is no significant ice production.

    The northern Barents Sea receives little ocean heat transport. This leads to a mixed layer at the freezing point during winter and significant ice production. There is little net surface heat loss annually in the north. The balance is achieved by a heat loss through long wave radiation all year, removing most of the summer solar heating.

    During the last decade the Barents Sea has experienced an atmospheric warming and an increased ocean heat transport. The Barents Sea responds to such large changes by adjusting temperature and heat loss. Decreasing the ocean heat transport below 50 TW starts a transition towards Arctic conditions. The heat loss in the Barents Sea depend on the effective area for cooling, and an increased heat transport leads to a spreading of warm water further north.

  7. Ultimate storage of spent fuel elements from the AVR experimental nuclear power plant in the Asse Salt Mine

    Energy Technology Data Exchange (ETDEWEB)

    Wolf, J.

    1975-02-15

    The present paper is intended to serve as the basis for the licensing procedures both in respect of the transport and storage techniques and also for the ultimate storage itself. In regard to the technique it will be shown on the basis of design drawings and calculations that the handling, transport and storage of the fuel elements can be safely carried out in accordance with the regulations in force. In regard to the ultimate storage itself, since no highly radioactive wastes with a long-lived actinide content have yet been stored, it will be necessary to show that an unacceptable contamination of the biosphere will be avoided even in the long term under all anticipated conditions. It will further be necessary to show by calculations and suitable tests, in view of the radioactive gas and fissile material content, that no danger due to gas release from the fuel elements will arise during the operating life of the mine and that a nuclear criticality risk can be excluded for all time.

  8. Gas-handling system for studies of tritium-containing materials

    International Nuclear Information System (INIS)

    Carstens, D.H.W.

    1975-01-01

    A gas handling system for preparation and study of tritium containing compounds and materials is described. The system at any one time can handle amounts of DT gas up to about 3 moles and has provisions for purification, storage, and measurement of the gas. Experimental conditions covering the ranges 20 to 800 0 C and 0.1 Pa to 137 MPa (10 -2 torr to 20,000 psi) can be maintained. (auth)

  9. Fuel Behaviour in Transport after Dry Storage: a Key Issue for the Management of used Nuclear Fuel

    International Nuclear Information System (INIS)

    Issard, Herve

    2014-01-01

    Interim used fuel dry storage has been developed in many countries providing an intermediate solution while waiting for evaluation and decisions concerning future use (such as recycling) or disposal sites. There is an important industrial experience feedback and excellent safety records. It appears that the duration of interim storage may become longer than initially expected. At the start of storage operations 40 years was considered sufficiently long to make a decision on either recycling or direct disposal of used nuclear fuel. Now it is said that storage time may have to be extended. Whatever the choice for the management of used fuel, it will finally have to be transported from the storage facility to another location, for recycling or final disposal. Bearing in mind the important principle that radioactive waste shall be managed in such a way that undue burdens will not be imposed on future generations, there is no guarantee that the fuel characteristics can be maintained in perpetuity. On the other hand, transport accident conditions from applicable regulation (IAEA SSR-6) are very severe for irradiated materials. Therefore, in compliance with transport regulations, the safety analysis of the fuel in transport after storage is mandatory. This paper will give an overview of the current situation related to the used fuel behaviour in transport after dry storage. On this matter there are some elements of information already available as well as some gaps of knowledge. Several national R and D programs and international teams are presently addressing these gaps. A lot of R and D work has already been done. An objective of these R and D projects is to aid decision makers. It is important to fix a limit and not to multiply intermediate operations because it means higher costs and more uncertainties. The identified gaps concern the following issues especially for high burn-up (HBU) fuels: thermal model for casks, degradation process of fuel material, cladding creep

  10. Bionic design methodology for wear reduction of bulk solids handling equipment

    NARCIS (Netherlands)

    Chen, G.; Schott, D.L.; Lodewijks, G.

    2016-01-01

    Large-scale handling of particulate solids can cause severe wear on bulk solids handling equipment surfaces. Wear reduces equipment life span and increases maintenance cost. Examples of traditional methods to reduce wear of bulk solids handling equipment include optimizing transport operations

  11. 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

  12. Recovery Act: 'Carbonsheds' as a Framework for Optimizing United States Carbon Capture and Storage (CCS) Pipeline Transport on a Regional to National Scale

    Energy Technology Data Exchange (ETDEWEB)

    Pratson, Lincoln

    2012-11-30

    Carbonsheds are regions in which the estimated cost of transporting CO{sub 2} from any (plant) location in the region to the storage site it encompasses is cheaper than piping the CO{sub 2} to a storage site outside the region. We use carbonsheds to analyze the cost of transport and storage of CO{sub 2} in deploying CCS on land and offshore of the continental U.S. We find that onshore the average cost of transport and storage within carbonsheds is roughly $10/t when sources cooperate to reduce transport costs, with the costs increasing as storage options are depleted over time. Offshore transport and storage costs by comparison are found to be roughly twice as expensive but t may still be attractive because of easier access to property rights for sub-seafloor storage as well as a simpler regulatory system, and possibly lower MMV requirements, at least in the deep-ocean where pressures and temperatures would keep the CO{sub 2} negatively buoyant. Agent-based modeling of CCS deployment within carbonsheds under various policy scenarios suggests that the most cost-effective strategy at this point in time is to focus detailed geology characterization of storage potential on only the largest onshore reservoirs where the potential for mitigating emissions is greatest and the cost of storage appears that it will be among the cheapest.

  13. Refurbishment of the transportation equipment, Task 3.08/04-10; Podzadatak 3.08/04-10 Remont transportnih uredjaja

    Energy Technology Data Exchange (ETDEWEB)

    Nikolic, M; Bratic, A [Institute of Nuclear Sciences Boris Kidric, Reaktor RA, Vinca, Beograd (Serbia and Montenegro)

    1963-12-15

    Transportation equipment at the RA reactor includes the bridge crane in the reactor hall, another smaller crane, bridge crane in spent fuel storage space, crane for handling the fuel containers n the room 099 and cart of the transportation channel. Regular testing and maintenance during reactor operation was not considered sufficient, and for that reason the repair and maintenance actions were done during the refurbishment of the reactor while it has been shut-down.

  14. NAC's Modular, Advanced Generation, Nuclear All-purpose STORage (MAGNASTOR) system: new generation multipurpose spent fuel storage for global application

    Energy Technology Data Exchange (ETDEWEB)

    Pennington, C.W. [NAC International, Norcross, GA (United States)

    2004-07-01

    Multipurpose canister systems (MCS) have been designed, licensed, fabricated, constructed, and loaded over the last decade within the U.S. These systems are characterized as concrete-based storage overpacks containing transportable canisters utilizing redundantly welded closures. Canisters are designed and intended to be transferred into transport packagings for shipment off-site, and canister designs do not preclude their use in waste disposal overpacks. NAC has learned a number of significant lessons in the deployment of its first generation MCS. During this period prior to the next procurement phase, NAC has developed a new generation MCS, incorporating the lessons learned from the first generation while considering the capabilities of the plants populating the next phase. The system is identified as the Modular, Advanced Generation, Nuclear All-purpose STORage (MAGNASTOR) system, and this paper addresses its unique design, fabrication, and operations features. Among these are: a unique developed cell basket design, under patent review, that increases spent fuel capacities and simplifies fabrication while providing high strength and heat removal efficiency: a significantly enhanced canister closure design that improves welding time, personnel dose, and drying performance: a low profile vertical concrete cask design that improves on-site handling and site dose rates, offers tangible threat limitations for beyond-design-basis events, and maintains proven and simple construction/operation features: a simple, proven transfer system that facilitates transfer without excessive dose or handling: a new approach to water removal and canister drying, using a moisture entrainment, gas absorption vacuum (MEGAVAC) system. The paper includes design and licensing status of the MAGNASTOR system, and prototyping development that NAC has performed to date.

  15. 33 CFR 127.313 - Bulk storage.

    Science.gov (United States)

    2010-07-01

    ...) WATERFRONT FACILITIES WATERFRONT FACILITIES HANDLING LIQUEFIED NATURAL GAS AND LIQUEFIED HAZARDOUS GAS Waterfront Facilities Handling Liquefied Natural Gas Operations § 127.313 Bulk storage. (a) The operator...: (1) LNG. (2) LPG. (3) Vessel fuel. (4) Oily waste from vessels. (5) Solvents, lubricants, paints, and...

  16. Safety aspects of long-term dry interim storage of type-B spent fuel and HLW transport casks

    International Nuclear Information System (INIS)

    Wolff, D.; Probst, U.; Voelzke, H.; Droste, B.; Roedel, R.

    2004-01-01

    Based on the German decision to minimise transports of spent fuel casks between nuclear power plants, reprocessing plants and central storage facilities several on-site storage facilities have been licensed till the end of 2003. Because of the large amount of type-B transport casks which are going to be used for long-term interim storage the question of time limited type-B license maintenance during the storage period of up to 40 years has been discussed under different aspects. This paper describes present technical aspects of the discussion. A main aspect of transport cask qualification for interim storage is the long-term behaviour of the metallic seal lid system. Concerning this results from current experimental long-term tests with metallic ''Helicoflex''-seals in which pool water is enclosed are presented. The test series has been performed by the Federal Institute for Materials Research and Testing (BAM) on behalf of the Federal Office for Radiation Protection (BfS) since 2001. Finally, the paper presents a German concept for an authorities' and technical experts' exchange of experience, know-how and state of the art referring to cask dispatch in nuclear facilities. BAM has taken over a central role in this so-called ''co-ordinating institution for cask dispatching information'' (''KOBAF'') which contains an online data base and a technical working group meeting twice a year. The goal is to keep comparable technical standards for all nuclear sites and storage facilities which are going to load and dispatch casks of the same or similar types under the responsibility of different German state governments for the next decades

  17. 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

  18. Experience with the transport and storage casks CASTOR (registered) MTR 2 for spent nuclear fuel assemblies from research reactors

    Energy Technology Data Exchange (ETDEWEB)

    Jack, Allen; Rettenbacher, Katharina; Skrzyppek, Juergen [GNS Gesellschaft fuer Nuklear-Service mbH, Essen (Germany)

    2011-07-01

    The CASTOR (registered) MTR 2 cask was designed and manufactured by the company GNS during the 1990's for the transport and interim storage of spent nuclear fuel assemblies from various types of research reactors. Casks of this type have been used at the VKTA Research Centre in Rossendorf near Dresden, Germany as well as at the European Commission's Joint Research Centre at Petten and at the HOR reactor at Delft in the Netherlands. A total of 24 units have been used for the functions of transport and storage with various spent fuel types (VVER, HFR-HEU, and HOR-HEU) for more than ten years now. This type of packaging for radioactive material is a member of the CASTOR (registered) family of spent nuclear fuel casks used worldwide. Over 1000 units are loaded and in storage in Europe, Asia, Africa and North America. This paper presents the experience from the use of the casks for transport and storage in the past, as well as the prospects for the future. (author)

  19. On the development and benchmarking of an approach to model gas transport in fractured media with immobile water storage

    Science.gov (United States)

    Harp, D. R.; Ortiz, J. P.; Pandey, S.; Karra, S.; Viswanathan, H. S.; Stauffer, P. H.; Anderson, D. N.; Bradley, C. R.

    2017-12-01

    In unsaturated fractured media, the rate of gas transport is much greater than liquid transport in many applications (e.g., soil vapor extraction operations, methane leaks from hydraulic fracking, shallow CO2 transport from geologic sequestration operations, and later-time radionuclide gas transport from underground nuclear explosions). However, the relatively immobile pore water can inhibit or promote gas transport for soluble constituents by providing storage. In scenarios with constant pressure gradients, the gas transport will be retarded. In scenarios with reversing pressure gradients (i.e. barometric pressure variations) pore water storage can enhance gas transport by providing a ratcheting mechanism. Recognizing the computational efficiency that can be gained using a single-phase model and the necessity of considering pore water storage, we develop a Richard's solution approach that includes kinetic dissolution/volatilization of constituents. Henry's Law governs the equilibrium gaseous/aqueous phase partitioning in the approach. The approach is implemented in a development branch of the PFLOTRAN simulator. We verify the approach with analytical solutions of: (1) 1D gas diffusion, (2) 1D gas advection, (3) sinusoidal barometric pumping of a fracture, and (4) gas transport along a fracture with uniform flow and diffusive walls. We demonstrate the retardation of gas transport in cases with constant pressure gradients and the enhancement of gas transport with reversing pressure gradients. The figure presents the verification of our approach to the analytical solution of barometric pumping of a fracture from Nilson et al (1991) where the x-axis "Horizontal axis" is the distance into the matrix block from the fracture.

  20. 49 CFR 172.317 - KEEP AWAY FROM HEAT handling mark.

    Science.gov (United States)

    2010-10-01

    ... 49 Transportation 2 2010-10-01 2010-10-01 false KEEP AWAY FROM HEAT handling mark. 172.317 Section... REQUIREMENTS, AND SECURITY PLANS Marking § 172.317 KEEP AWAY FROM HEAT handling mark. (a) General. For... of Division 5.2 must be marked with the KEEP AWAY FROM HEAT handling mark specified in this section...

  1. CASTOR THTR transport/storage casks

    International Nuclear Information System (INIS)

    Laug, R.W.; Spilker, H.; Sappok, M.

    1998-01-01

    For the management of spent fuel from nuclear power plants, two possibilities are available in Germany. One possibility is the reprocessing of the spent fuel and the realization of a so called closed nuclear fuel cycle, the other is the direct disposal after a period of interim storage, without reprocessing. For the German GCR plants ''THTR 300'' and ''AVR'', only the way of direct disposal is available to date for managing the spent fuel (pebble-bed fuel). For the period of interim storage, dry storage in casks was selected. (author)

  2. 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...

  3. The incorporation of boron in fissile transport packages for the transport and interim storage of irradiated light water reactor fuels

    International Nuclear Information System (INIS)

    Hunter, I.J.

    1998-01-01

    Boron is widely used in the nuclear industry for capturing neutrons and it is particularly useful in the criticality control of packages for the transport and interim storage of irradiated light water reactor fuels. Such fuels are typically located in an internal frame of stainless steel or aluminium, referred to as a basket, which locates the fuel assemblies in channels. Transnucleaire has designed and supplied more than 100 baskets of varying types during the past 30 years. Boron has been incorporated in many forms. Early designs of baskets used boron in specific zones to contribute to the control of criticality. Later developments in new materials dispersed boron throughout the basket and gave designers more options for the basic forms which make up the channels. New basket concepts have been developed by Transnucleaire to meet the changing market needs for transport and interim storage and boron continues to play an important role as an efficient thermal neutron absorber. (author)

  4. Standard casks for the transport of LWR spent fuel. Storage/transport casks for long cooled spent fuel

    International Nuclear Information System (INIS)

    Blum, P.; Sert, G.; Gagnon, R.

    1983-01-01

    During the past decade, TRANSNUCLEAIRE has developed, licensed and marketed a family of standard casks for the transport of spent fuel from LWR reactors to reprocessing plants and the ancillary equipments necessary for their operation and transport. A large number of these casks are presently used for European and intercontinental transports and manufactured under TRANSNUCLEAIRE supervision in different countries. The main advantages of these casks are: - large payload for considered modes of transport, - moderate cost, - reliability due to the large experience gained by TRANSNUCLEAIRE as concerns fabrication and operation problems, - standardization faciliting fabrication, operation and spare part supply. Recently, TRANSNUCLEAIRE also developed a new generation of casks for the dry storage and occasional transport of LWR spent fuel which has been cooled for 5 years or 7 years in case of consolidated fuel rods. These casks have an optimum payload which takes into account the shielding requirements and the weight limitations at most sites. This paper deals more particularly with the TN 24 model which exists in 4 versions among which one for 24 PWR 900 fuel assemblies and another one for the consolidated fuel rods from 48 of same fuel assemblies

  5. Managing aging effects on dry cask storage systems for extended long-term storage and transportation of used fuel - rev. 0

    Energy Technology Data Exchange (ETDEWEB)

    Chopra, O.K.; Diercks, D.; Fabian, R.; Ma, D.; Shah, V.; Tam, S.W.; Liu, Y. (Decision and Information Sciences); ( EVS); ( NE)

    2012-07-06

    The cancellation of the Yucca Mountain repository program in the United States raises the prospect of extended long-term storage (i.e., >120 years) and deferred transportation of used fuel at operating and decommissioned nuclear power plant sites. Under U.S. federal regulations contained in Title 10 of the Code of Federal Regulations (CFR) 72.42, the initial license term for an Independent Spent Fuel Storage Installation (ISFSI) must not exceed 40 years from the date of issuance. Licenses may be renewed by the U.S. Nuclear Regulatory Commission (NRC) at the expiration of the license term upon application by the licensee for a period not to exceed 40 years. Application for ISFSI license renewals must include the following: (1) Time-limited aging analyses (TLAAs) that demonstrate that structures, systems, and components (SSCs) important to safety will continue to perform their intended function for the requested period of extended operation; and (2) a description of the aging management program (AMP) for management of issues associated with aging that could adversely affect SSCs important to safety. In addition, the application must also include design bases information as documented in the most recent updated final safety analysis report as required by 10 CFR 72.70. Information contained in previous applications, statements, or reports filed with the Commission under the license may be incorporated by reference provided that those references are clear and specific. The NRC has recently issued the Standard Review Plan (SRP) for renewal of used-fuel dry cask storage system (DCSS) licenses and Certificates of Compliance (CoCs), NUREG-1927, under which NRC may renew a specific license or a CoC for a term not to exceed 40 years. Both the license and the CoC renewal applications must contain revised technical requirements and operating conditions (fuel storage, surveillance and maintenance, and other requirements) for the ISFSI and DCSS that address aging effects that

  6. Preparation and characterization of nano-sized phase change emulsions as thermal energy storage and transport media

    International Nuclear Information System (INIS)

    Chen, J.; Zhang, P.

    2017-01-01

    Highlights: • The nano-sized phase change emulsions are prepared by using D-phase method. • The thermo-physical and transport properties are experimentally investigated. • The influence of surfactant on the melting temperature and latent heat of water is clarified. • The phase change emulsion can be used as the heat transfer fluid in a thermal energy storage system. - Abstract: Phase change emulsion (PCE) is a kind of two-phase heat transfer fluid with phase change material (PCM) dispersed in carrier fluid. It has received intensive attractions in recent years due to the fact that it can be used as both the thermal energy storage material and transport medium simultaneously in a thermal energy storage system. In the present study, nano-sized PCEs are prepared by the D-phase method with n-hexadecane and n-octadecane as PCMs. The thermo-physical and transport properties are characterized to facilitate the applications. The droplet size distribution of the PCE is measured by a Photon Correlation Spectroscopy, and the results show that the droplet size distributions are similar at different mass fractions. The rheological behavior and viscosity of the PCE are measured by a rheometer, which shows that the PCEs at mass fractions below 30.0 wt% are Newtonian fluids, and the viscosities are dependent on both the mass fraction and temperature. The differential scanning calorimetry (DSC) is employed to analyze the phase change characteristics of the PCE, and the results indicate large supercooling degree of water and PCM in the PCE. The melting temperature and latent heat of water in the PCE are much smaller than those of pure water. The thermal conductivities of the PCE with different mass fractions at different temperatures are measured by the transient hot-wire method. Furthermore, the energy transport characteristics of the PCEs are evaluated on the basis of the measured thermo-physical and transport properties. The results suggest that the PCEs show a drastic

  7. Effect of gamma radiation and storage on cashew apple (Anacardium occidentale L.) quality

    International Nuclear Information System (INIS)

    Souza, Adriana Régia Marques de; Brazaca, Solange Guidolin Canniatti; Arthur, Valter; Oliveira, Anderson Giovani Cândico; Spoto, Marta Helena Fillet; Walder, Júlio Marcos Melges

    2009-01-01

    The non-efficiency or absence of techniques for adequate handling, transport, and storage of cashew stalks associated with a high level of perishability, generates high economic loss in the commercialization of these fruits, hence the development of conservation methods becomes a necessity in order to enhance the profitability. Cashew apples from precocious dwarf cashew tree were irradiated with doses of 0, 0.5, and 1.0 kGy and stored during nine days under refrigeration at 4 ºC for evaluation of the quality stability during storage. Chemical analyses were performed to verify changes in reducing sugars, Brix, vitamin C, and pH. Alterations in the firmness and color were also observed. The levels of vitamin C decreased as a function of storage as well as a function of the radiation doses employed. The firmness of the fruits was influenced by both the radiation doses and storage time, increasing during storage and decreasing as the radiation doses increased. Irradiation was shown to be efficient in the prolongation of the shelf-life of cashew stalks. (author) [pt

  8. Regulations for the transport of radioactive material in Italy: the role of the Italian Competent Authority (ANPA)

    International Nuclear Information System (INIS)

    Orsini, A.; Trivelloni, S.

    1995-01-01

    In Italy four Ministries, Industry, Transport, Marine Merchandise and Interior, have the legal responsibility to issue and apply the transport safety regulations for radioactive material. ANPA, the National Agency for Environmental Protection, has the technical duty to issue the approval certificates and to support the various Ministries in authorizing carriers for all modes of transport, in updating the regulations and advising in the case of emergency conditions. ANPA is monitoring the quantity of radioactive material transported in Italy, the radiation doses of workers and public, and verifying the implementation of transport regulations through inspections of the carriers and during storage in transit and handling. (Author)

  9. Regulations for the transport of radioactive material in Italy: the role of the Italian Competent Authority (ANPA)

    International Nuclear Information System (INIS)

    Orsini, A.; Trivelloni, S.

    1995-01-01

    In Italy four Ministries, Industry, Transport, Marine Merchandise and Interior, have the legal responsibility to issue and apply the transport safety regulations for radioactive material. ANPA, the National Agency for Environmental Protection, has the technical duty to issue the approval certificates and to support the various Ministries in authorising carriers for all modes of transport, in updating the regulations and advising in the case of emergency conditions. ANPA is monitoring the quantity of radioactive material transported in Italy, the radiation doses of workers and public, and verifying the implementation of transport regulations through inspection of the carriers and during storage in transit and handling. (author)

  10. Modification Of Carry-Blair Transport Media For Storage Salmonella typhi

    Directory of Open Access Journals (Sweden)

    Yati Supriatin

    2016-09-01

    Full Text Available The aim of this study was to determine transport media modification as alternative media to replace Carry Blair. One type of transport media that often use to carry faeces specimens suspected to contain Salmonella typhi is Carry-Blair media. Studies have been conducted experimentally by storing Salmonella typhi on alternative transport media with Peptone composition, disodium Phosphate, Sodium chloride, Calcium chloride, which is made using a semi-solid and Carry-Blair as a control. Three variety of storage was done (0 hour,6 hours,9 hours at a temperature 4⁰-8⁰C and then Salmonella typhi was inoculated in Salmonella Shigella Agar using spread plate technique incubated during 24 hours at 37⁰C, counted the number of colonies by the plate count method using the colony counter. The results of ANOVA could be concluded that modification media could be use as alternative media replace Carry-Blair at 6 hours. Based on regression correlation test was assumed that the Salmonella typhi bacteria still life at less than 11 hours 54 minutes.

  11. Nuclear fuel storage facility

    International Nuclear Information System (INIS)

    Matsumoto, Takashi; Isaka, Shinji.

    1987-01-01

    Purpose: To increase the spent fuel storage capacity and reduce the installation cost in a nuclear fuel storage facility. Constitution: Fuels handled in the nuclear fuel storage device of the present invention include the following four types: (1) fresh fuels, (2) 100 % reactor core charged fuels, (3) spent fuels just after taking out and (4) fuels after a certain period (for example one half-year) from taking out of the reactor. Reactivity is high for the fuels (1), and some of fuels (2), while low in the fuels (3) (4), Source intensity is strong for the fuels (3) and some of the fuels (2), while it is low for the fuels (1) and (4). Taking notice of the fact that the reactivity, radioactive source intensity and generated after heat are different in the respective fuels, the size of the pool and the storage capacity are increased by the divided storage control. While on the other hand, since the division is made in one identical pool, the control method becomes important, and the working range is restricted by means of a template, interlock, etc., the operation mode of the handling machine is divided into four, etc. for preventing errors. (Kamimura, M.)

  12. Criticality safety evaluation report for the Cold Vacuum Drying Facility's process water handling system

    International Nuclear Information System (INIS)

    Roblyer, S.D.

    1998-01-01

    This report addresses the criticality concerns associated with process water handling in the Cold Vacuum Drying Facility (CVDF). The controls and limitations on equipment design and operations to control potential criticality occurrences are identified. The effectiveness of equipment design and operation controls in preventing criticality occurrences during normal and abnormal conditions is evaluated and documented in this report. Spent nuclear fuel (SNF) is removed from existing canisters in both the K East and K West Basins and loaded into a multicanister overpack (MCO) in the K Basin pool. The MCO is housed in a shipping cask surrounded by clean water in the annulus between the exterior of the MCO and the interior of the shipping cask. The fuel consists of spent N Reactor and some single pass reactor fuel. The MCO is transported to the CVDF near the K Basins to remove process water from the MCO interior and from the shipping cask annulus. After the bulk water is removed from the MCO, any remaining free liquid is removed by drawing a vacuum on the MCO's interior. After cold vacuum drying is completed, the MCO is filled with an inert cover gas, the lid is replaced on the shipping cask, and the MCO is transported to the Canister Storage Building. The process water removed from the MCO contains fissionable materials from metallic uranium corrosion. The process water from the MCO is first collected in a geometrically safe process water conditioning receiver tank. The process water in the process water conditioning receiver tank is tested, then filtered, demineralized, and collected in the storage tank. The process water is finally removed from the storage tank and transported from the CVDF by truck

  13. Nickel-hydrogen battery design for the Transporter Energy Storage Subsystem (TESS)

    Science.gov (United States)

    Lapinski, John R.; Bourland, Deborah S.

    1992-01-01

    Information is given in viewgraph form on nickel hydrogen battery design for the transporter energy storage subsystem (TESS). Information is given on use in the Space Station Freedom, the launch configuration, use in the Mobile Servicing Center, battery design requirements, TESS subassembley design, proof of principle testing of a 6-cell battery, possible downsizing of TESS to support the Mobile Rocket Servicer Base System (MBS) redesign, TESS output capacity, and cell testing.

  14. Analysis of near-term spent fuel transportation hardware requirements and transportation costs

    International Nuclear Information System (INIS)

    Daling, P.M.; Engel, R.L.

    1983-01-01

    A computer model was developed to quantify the transportation hardware requirements and transportation costs associated with shipping spent fuel in the commercial nucler fuel cycle in the near future. Results from this study indicate that alternative spent fuel shipping systems (consolidated or disassembled fuel elements and new casks designed for older fuel) will significantly reduce the transportation hardware requirements and costs for shipping spent fuel in the commercial nuclear fuel cycle, if there is no significant change in their operating/handling characteristics. It was also found that a more modest cost reduction results from increasing the fraction of spent fuel shipped by truck from 25% to 50%. Larger transportation cost reductions could be realized with further increases in the truck shipping fraction. Using the given set of assumptions, it was found that the existing spent fuel cask fleet size is generally adequate to perform the needed transportation services until a fuel reprocessing plant (FRP) begins to receive fuel (assumed in 1987). Once the FRP opens, up to 7 additional truck systems and 16 additional rail systems are required at the reference truck shipping fraction of 25%. For the 50% truck shipping fraction, 17 additional truck systems and 9 additional rail systems are required. If consolidated fuel only is shipped (25% by truck), 5 additional rail casks are required and the current truck cask fleet is more than adequate until at least 1995. Changes in assumptions could affect the results. Transportation costs for a federal interim storage program could total about $25M if the FRP begins receiving fuel in 1987 or about $95M if the FRP is delayed until 1989. This is due to an increased utilization of federal interim storage facility from 350 MTU for the reference scenario to about 750 MTU if reprocessing is delayed by two years

  15. Energy Storage Publications | Transportation Research | NREL

    Science.gov (United States)

    , California. 23 pp.; NREL Report No. PR-5400-60290. Optimal Sizing of Energy Storage and Photovoltaic Power (11) 2017 pp. 1095-1118. Life Prediction Model for Grid-Connected Li-ion Battery Energy Storage System Prediction Model for Grid-Connected Li-ion Battery Energy Storage System - Preprint Paper Source: Smith

  16. Development of a high integrity container for storage, transportation, and disposal of radioactive wastes from Three Mile Island unit II

    International Nuclear Information System (INIS)

    Holzworth, R.E.; Chapman, R.L.; Burton, H.M.; Bixby, W.W.

    1981-01-01

    The EPICOR II ion exchange system used to decontaminate approximately 1900 m 3 of contaminated water in the Auxiliary and Fuel Handling Building (AFHB) generated 50 highly loaded and 22 lesser loaded organic resin liners. The 22 lesser loaded resins were shipped to a commercial disposal site, but the highly loaded liners have been stored on the island since their generation. One highly loaded liner, or prefilter, was shipped to Battelle Columbus Laboratories (BCL) in May, 1981 as part of the United States Department of Energy (DOE) Three Mile Island Information and Examination Program. The prefilter is being characterized to determine the behavior of the waste form with respect to time and the internal environment and to provide an information base for use in management and regulatory decisions relative to the storage, processing, and disposal of these wastes. Due to the unique characteristics of these wastes, the US DOE is sponsoring programs, such as the BCL Sorbent Experiments Program, to evaluate their characteristics and to provide a High Integrity Container (HIC) Development Program which would improve waste suitability for disposal at a land burial facility. This paper addresses regulatory considerations, establishment of design criteria, proposed design concepts, system demonstration, and status of the HIC Development Program for storage, transportation, and disposal of high specific activity, low level radioactive wastes from Three Mile Island Unit II as typified by EPICOR II ion exchange media and liners

  17. Determination of prerequisites for the estimation of transportation cost of spent fuels

    International Nuclear Information System (INIS)

    Choi, Heui Joo; Lee, Jong Youl; Kim, Seong Ki; Cha, Jeong Hoon; Choi, Jong Won

    2007-10-01

    The cost for the spent fuel management includes the costs for the interim storage, the transportation, and the permanent disposal of the spent fuels. The scope of this report is limited to the cost for the spent fuel transportation. KAERI is developing a cost estimation method for the spent fuel transportation through a joint study with the French AREVA TN. Several prerequisites should be fixed in order to estimate the cost for the spent fuel transportation properly. In this report we produced them considering the Korean current status on the management of spent fuels. The representative characteristics of a spent fuel generated from the six nuclear reactors at the YG site were determined. Total 7,200 tons of spent fuels are projected with the lifespan of 60 years. As the transportation mode, sea transportation and road transportation is recommended considering the location of the YG site and the hypothetical Centralized Interim Storage Facility (CISF) and Final Repository (FR). The sea route and transportation time were analyzed by using a sea distance analysis program which the NORI (National Oceanographic Research Institute) supplies on a web. Based on the results of the analysis, the shipping rates were determined. The regulations related to the spent fuel transportation were reviewed. The characteristics of the transportation vessel and a trailer were suggested. The handling and transportation systems at the YG site, Centralized Interim Storage Facility, and the Final Repository were described in detail for the purpose of the cost estimation of the spent fuel transportation. From the detail description the major components of the transportation system were determined for the conceptual design. It is believed that the conceptual design of the transportation system developed in this report will be used for the analysis of transportation logistics and the cost estimation of spent fuels

  18. European experience in transport/storage cask for vitrified residues

    International Nuclear Information System (INIS)

    Otton, Camille; Sicard, Damien

    2007-01-01

    Available in abstract form only. Full text of publication follows: Because of the evolution of burnup of spent fuel to be reprocessed, the high activity vitrified residues would not be transported in the existing cask designs. Therefore, TN International has decided in the late nineties to develop a brand new design of casks with optimized capacity able to store and transport the most active and hottest canisters: the TN TM 81 casks currently in use in Switzerland and the TN TM 85 cask which shall permit in the near future in Germany the storage and the transport of the most active vitrified residues defining a thermal power of 56 kW (kilowatts). The challenges for the TN TM 81 and TN TM 85 cask designs were that the geometry entry data were very restrictive and were combined with a fairly wide range set by the AREVA NC Specification relative to vitrified residue canister. The TN TM 81 and the TN TM 85 casks have been designed to fully anticipate shipment constraints of the present vitrified residue production. It also used the feedback of current shipments and the operational constraints and experience of receiving and shipping facilities. The casks had to fit as much as possible in the existing procedures for the already existing flasks such as the TN TM 28 cask and TS 28 V cask, all along the logistics chain of loading, unloading, transport and maintenance. (authors)

  19. 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

  20. 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

  1. Transportation capabilities of the existing cask fleet

    International Nuclear Information System (INIS)

    Johnson, P.E.; Wankerl, M.W.; Joy, D.S.

    1991-01-01

    This paper describes a number of scenarios estimating the amount of spent nuclear fuel that could be transported to a Monitored Retrievable Storage (MRS) Facility by various combinations of existing cask fleets. To develop the scenarios, the data provided by the Transportation System Data Base (TSDB) were modified to reflect the additional time for cask turnaround resulting from various startup and transportation issues. With these more realistic speed and cask-handling assumptions, the annual transportation capability of a fleet consisting of all of the existing casks is approximately 465 metric tons of uranium (MTU). The most likely fleet of existing casks that would be made available to the DOE consists of two rail, three overweight truck, and six legal weight truck casks. Under the same transportation assumptions, this cask fleet is capable of approximately transporting 270 MTU/year. These ranges of capability is a result of the assumptions pertaining to the number of casks assumed to be available. It should be noted that this assessment assumes additional casks based on existing certifications are not fabricated

  2. Transportation capabilities of the existing cask fleet

    International Nuclear Information System (INIS)

    Johnson, P.E.; Joy, D.S.; Wankerl, M.W.

    1991-01-01

    This paper describes a number of scenarios estimating the amount of spent nuclear fuel that could be transported to a Monitored Retrievable Storage (MRS) Facility by various combinations of existing cask fleets. To develop the scenarios, the data provided by the Transportation System Data Base (TSDB) were modified to reflect the additional time for cask turnaround resulting from various startup and transportation issues. With these more realistic speed and cask-handling assumptions, the annual transportation capability of a fleet consisting of all of the existing casks is approximately 46 metric tons of uranium (MTU). The most likely fleet of existing casks that would be made available to the Department of Energy (DOE) consists of two rail, three overweight truck, and six legal weight truck casks. Under the same transportation assumptions, this cask fleet is capable of approximately transporting 270 MTU/year. These ranges of capability is a result of the assumptions pertaining to the number of casks assumed to be available. It should be noted that this assessment assumes additional casks based on existing certifications are not fabricated. 5 refs., 4 tabs

  3. Long-Term Dry Storage of High Burn-Up Spent Pressurized Water Reactor (PWR) Fuel in TAD (Transportation, Aging, and Disposal) Containers

    International Nuclear Information System (INIS)

    Hwang, Yong Soo

    2008-12-01

    A TAD canister, in conjunction with specially-designed over-packs can accomplish the functions of transportation, aging, and disposal (TAD) in the management of spent nuclear fuel (SNF). Industrial dry cask systems currently available for SNF are licensed for storage-only or for dual-purpose (i.e., storage and transportation). By extending the function to include the indefinite storage and perhaps, eventual geologic disposal, the TAD canister would have to be designed to enhance, among others, corrosion resistance, thermal stability, and criticality-safety control. This investigative paper introduces the use of these advanced iron-based, corrosion-resistant materials for SNF transportation, aging, and disposal.The objective of this investigative project is to explore the interest that KAERI would research and develop its specific SAM coating materials for the TAD canisters to satisfy the requirements of corrosion-resistance, thermal stability, and criticality-controls for long-term dry storage of high burn-up spent PWR fuel

  4. Safety aspects of long-term dry interim storage of Type B spent fuel and high-level transport casks

    International Nuclear Information System (INIS)

    Wolff, D.; Probst, U.; Voelzke, H.; Droste, B.; Roedel, R.

    2004-01-01

    Based on the German decision to minimise transport of spent fuel casks between nuclear power plants, reprocessing plants and central storage facilities several on-site storage facilities were licensed until the end of 2003. Because of the large amount of Type B(U) transport casks which are going to be used for long-term interim storage the question of time-limited Type B(U) licence maintenance during the storage period of up to 40 years has been discussed under different aspects. This paper describes present technical aspects of the discussion. A main aspect of qualification of transport casks for interim storage is the long-term behaviour of the metallic seal-lid system. Here we present results from current long-term experimental tests with metallic 'Helicoflex' seals in which pool water is enclosed. This series of tests has been performed by the Federal Institute for Materials Research and Testing (BAM) on behalf of the Federal Office for Radiation Protection (BfS) since 2001. Finally, the paper presents a German concept for an exchange of experience, know-how and state-of-the-art between authorities and technical experts with regard to cask dispatch in nuclear facilities. BAM has taken over a central role in this so-called 'coordinating institution for cask dispatching information' ('KOBAF') which entails management of an online database of cask-specific documents and a technical working group meeting twice a year. The goal is to keep comparable technical standards for all nuclear sites and storage facilities which are going to load and dispatch casks of the same or similar types under the responsibility of different German state governments for the coming decades. (author)

  5. CO2 storage in Sweden

    International Nuclear Information System (INIS)

    Ekstroem, Clas; Andersson, Annika; Kling, Aasa; Bernstone, Christian; Carlsson, Anders; Liljemark, Stefan; Wall, Caroline; Erstedt, Thomas; Lindroth, Maria; Tengborg, Per; Edstroem, Mikael

    2004-07-01

    with the expansions of natural gas networks for Sweden should be looked for. Issues that need more deep studies are how the injection infrastructures for aquifers need to be modified compared to those used for oil fields, successively improved validation of CO 2 handling costs for Europe and Sweden, regarding i.a. ship transport and industrial compression and cooling of large CO 2 flows in connection to CO 2 capture. It is likely that the local environment would be affected by a possible leakage. Many organisms and ecosystems are sensitive to small changes in the CO 2 concentration. Knowledge exists on how humans, animals and plants would be affected by enhanced contents of carbon dioxide in their immediate surroundings, and on how the physical part of soils and water would be influenced by higher CO 2 concentrations. How individual ecosystems would be affected will have to be assessed based on the conditions in each specific system. Further studies are needed on consequences for ecosystems, especially for ecosystems in the ground, particularly those deep in the ground. Severe environmental damages (large short-term emissions that would damage the surrounding environment, i.e. concentrations around 25 % CO 2 ) would be limited to a few tens of meters from the plant and will therefore not need to be considered. No calculations have been performed for any transport means besides pipelines. Two parallels to CO 2 transport and storage are geothermic projects and natural gas pipelines. For geothermic projects there is a basic positive attitude already before the project start and the operations take place deep in the ground, i.e. at a safe distance from those concerned, and no threatening picture has been felt. No overall legal framework applicable to CO 2 transport and storage exist today, neither within the national Swedish law nor within international/European law. There are however adjacent legal frameworks mainly regarding transport. Providing that the construction of

  6. Next generation storage facility

    International Nuclear Information System (INIS)

    Schlesser, J.A.

    1994-01-01

    With diminishing requirements for plutonium, a substantial quantity of this material requires special handling and ultimately, long-term storage. To meet this objective, we at Los Alamos, have been involved in the design of a storage facility with the goal of providing storage capabilities for this and other nuclear materials. This paper presents preliminary basic design data, not for the structure and physical plant, but for the container and arrays which might be configured within the facility, with strong emphasis on criticality safety features

  7. 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.

  8. Milk postharvest handling practices across the supply chain in Eastern Ethiopia

    Directory of Open Access Journals (Sweden)

    Tadele Amentie

    2016-06-01

    Full Text Available Objective: This study was conducted to assess hygienic cow milk handling practices of milk producers, traders (informal collectors, transporters and vendors and consumers across the milk supply chain in the Eastern Ethiopia. Materials and methods: A total of 160 milk producers in Babile district were selected using multistage stratified sampling technique. Moreover, a total of 54 milk collectors and transporters (5, 40, 9 from Jigjiga, Harar and Dire Dawa town, respectively, 152 vendors (40 from Bable, Harar and Dire Dawa town and 32 from Jigjiga town and 160 consumers (40 from each town were selected using snowball sampling technique. Data from the selected actors were collected using focus group discussion, questionnaire survey and observations. Results: The study revealed that the majority of milk handling operations in the study area is carried out by females. The majority of respondent milk producers (87.5-92.5%, collectors and transporters (88.9-100%, vendors (77.5-90.7% and some consumers (37.5-47.5% performing milk handling operations were illiterate. Most of the observed actors in the study area perform malpractices (such as failure to stop milk handling while showing disease symptoms, improper hand washing and handling of risk factors while working with milk. Majority of respondent milk producers (87.5-97.5%, all traders and some consumers (12.5-32.5% use plastic containers for milk handling. Milk handling equipments were commonly washed using warm water, detergent and sand; however, in most case they were not properly protected from risk factors after washing. Majority of respondent milk producers (55-65%, collectors and transporters (60-66.7%, and some vendors (0-50% and consumers (0-55% use water from non-tap sources for hygienic practices. Conclusion: In general; the findings indicated that milk handling practices performed across the supply chain in the study area were unhygienic and therefore suggested the need for improving

  9. Development of Safe Food Handling Guidelines for Korean Consumers.

    Science.gov (United States)

    Kang, Hee-Jin; Lee, Min-Woo; Hwang, In-Kyeong; Kim, Jeong-Weon

    2015-08-01

    The purpose of this study was to develop guidelines for Korean consumers with regard to safe food handling practices at home by identifying current food handling issues. Korean consumers' behaviors regarding their safe food handling were identified via survey questionnaires that included items on individual hygiene practices, prepreparation steps when cooking, the cooking process, and the storage of leftover foods. The subjects were 417 Korean parents with elementary school children living in Seoul and Gyeonggi Province in the central area of Korea. The survey results revealed gaps between the knowledge or practices of Korean consumers and scientific evidence pertaining to safe food handling practices. Based on these findings, a leaflet on safe food handling guidelines was developed in accordance with Korean food culture. These guidelines suggest personal hygiene practices as well as fundamental principles and procedures for safe food handling from the stage of food purchase to that of keeping leftover dishes. A pilot application study with 50 consumers revealed that the guidelines effectively improved Korean consumers' safe food handling practices, suggesting that they can serve as practical educational material suitable for Korean consumers.

  10. 1.2.1.1 Harvest, Collection and Storage Quarter 3 Milestone Report

    Energy Technology Data Exchange (ETDEWEB)

    Wendt, Lynn M. [Idaho National Lab. (INL), Idaho Falls, ID (United States); Smith, William A. [Idaho National Lab. (INL), Idaho Falls, ID (United States); Cafferty, Kara G. [Idaho National Lab. (INL), Idaho Falls, ID (United States); Bonner, Ian J. [Idaho National Lab. (INL), Idaho Falls, ID (United States); Huang, Qiyang [Idaho National Lab. (INL), Idaho Falls, ID (United States); Colby, Rachel D. [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2014-07-01

    Single pass baling of corn stover is required in order to meet targets for the herbaceous biomass 2017 logistics design case. Single-pass pass stover harvest is based on the grain harvest and generally results in stover with a moisture content of 30-50% wet basis (w.b). Aerobic storage of corn stover with high moisture results in high levels of dry matter loss (DML), up to 25%. Anaerobic storage (ensiling) reduces DML to less than 5%, but additional costs are associated with handling and transporting the extra moisture in the biomass. This milestone provides a best-estimate of costs for using high moisture feedstock within the conventional baled logistics system. The costs of three (3) anaerobic storage systems that reduce dry matter losses (bale wrap, silage tube, and silage drive over pile) are detailed in this milestone and compared to both a conventional dry-baled corn stover case and a high moisture bale case, both stored aerobically. The total logistics cost (harvest, collection, storage, and transportation) of the scenarios are as follows: the conventional multi-pass dry bale case and the single-pass high moisture case stored aerobically were nearly equivalent at $61.15 and $61.24/DMT. The single-pass bale wrap case was the lowest at $57.63/DMT. The bulk anaerobic cases were the most expensive at $84.33 for the silage tube case and $75.97 for the drive over pile, which reflect the additional expense of transporting high-moisture bulk material; however, a reduction in preprocessing costs may occur because these feedstocks are size reduced in the field. In summary, the costs estimates presented in this milestone report can be used to determine if anaerobic storage of high-moisture corn stover is an economical option for dry matter preservation.

  11. Simulation of Multi Canister Overpack (MCO) Handling Machine Impact with Cask and MCO During Insertion into the Transfer Pit (FDT-137)

    Energy Technology Data Exchange (ETDEWEB)

    BAZINET, G.D.

    2000-04-13

    The K-Basin Cask and Transportation System will be used for safely packaging and transporting approximately 2,100 metric tons of unprocessed, spent nuclear fuel from the 105 K East and K West Basins to the 200 E Area Canister Storage Building (CSB). Portions of the system will also be used for drying the spent fuel under cold vacuum conditions prior to placement in interim storage. The spent nuclear fuel is currently stored underwater in the two K-Basins. The K-Basins loadout pit is the area selected for loading spent nuclear fuel into the Multi-Canister Overpack (MCO) which in turn is located within the transportation cask. This Cask/MCO unit is secured.in the pit with a pail load out structure whose primary function is lo suspend and support the Cask/MCO unit at.the desired elevations and to protect the unit from the contaminated K-Basin water. The fuel elements will be placed in special baskets and stacked in the MCO that have been previously placed in the cask. The casks will be removed from the K Basin load out areas and taken to the cold vacuum drying station. Then the cask will be prepared for transportation to the CSB. The shipments will occur exclusively on the Hanford Site between K-Basins and the CSB. Travel will be by road with one cask per trailer. At the CSB receiving area the cask will be removed from the trailer. A gantry crane will then move the cask over to the transfer pit and load the cask into the transfer pit. From the transfer pit the MCO will be removed from the cask by the MCO Handling Machine (MHM). The MHM will move the MCO from the transfer pit to a canister storage tube in the CSB. MCOs will be piled two high in each canister Storage tube.

  12. Simulation of Multi Canister Overpack (MCO) Handling Machine Impact with Cask and MCO During Insertion into the Transfer Pit (FDT-137)

    International Nuclear Information System (INIS)

    BAZINET, G.D.

    2000-01-01

    The K-Basin Cask and Transportation System will be used for safely packaging and transporting approximately 2,100 metric tons of unprocessed, spent nuclear fuel from the 105 K East and K West Basins to the 200 E Area Canister Storage Building (CSB). Portions of the system will also be used for drying the spent fuel under cold vacuum conditions prior to placement in interim storage. The spent nuclear fuel is currently stored underwater in the two K-Basins. The K-Basins loadout pit is the area selected for loading spent nuclear fuel into the Multi-Canister Overpack (MCO) which in turn is located within the transportation cask. This Cask/MCO unit is secured.in the pit with a pail load out structure whose primary function is lo suspend and support the Cask/MCO unit at.the desired elevations and to protect the unit from the contaminated K-Basin water. The fuel elements will be placed in special baskets and stacked in the MCO that have been previously placed in the cask. The casks will be removed from the K Basin load out areas and taken to the cold vacuum drying station. Then the cask will be prepared for transportation to the CSB. The shipments will occur exclusively on the Hanford Site between K-Basins and the CSB. Travel will be by road with one cask per trailer. At the CSB receiving area the cask will be removed from the trailer. A gantry crane will then move the cask over to the transfer pit and load the cask into the transfer pit. From the transfer pit the MCO will be removed from the cask by the MCO Handling Machine (MHM). The MHM will move the MCO from the transfer pit to a canister storage tube in the CSB. MCOs will be piled two high in each canister Storage tube

  13. Evaluation of a handling system for ley crop used in biogas production. Capacities and costs for a centralised system

    Energy Technology Data Exchange (ETDEWEB)

    Vaagstroem, Lena

    2005-07-01

    Within the Vaextkraft project in Vaesteraas, Sweden, biogas is to be produced out of ley crop and organic waste. The aim of this study has been to estimate the capacities within the handling system used for the ley crop harvest, and the resources needed. For this purpose a model in the form of a calculation program in Excel was built. The model makes it possible to vary parameters such as transport system design, distance from fields to storage, dry matter content and yield. The results showed that it is essential to match the capacities between chopper and transport to minimise the time and cost connected to the harvest. To avoid creating costly bottlenecks in the Vaextkraft case the transport system has to consist of at least two trucks with trailers. The estimates made with the model suggests that the distance to storage is strongly linked to the dimensioning of the transport system, whereas the number of fields and their size has a lesser impact on harvest time and cost. Variation of the dry matter yield from a base scenario had an impact on the cost for harvesting, but not on the choice of transport system. The model couldn't detect any reliable differences in total costs due to the variation of dry matter content between 25-45%. The choice of chopping machinery in the Vaextkraft project leads to small timeliness costs. Together with a reasonable choice of transport system they will only constitute a few percent of the total costs for harvesting.

  14. Operational experience in the spent fuel receipt and storage facility at the Tokai Reprocessing Plant

    International Nuclear Information System (INIS)

    Nakashima, S.; Yamaguchi, Y.; Iimura, I.; Yamamura, O.; Ogata, Y.

    1992-01-01

    The development of the double containment system led to the reduction of labor time for the cask decontamination to one-tenth compared to the original manner. And also it led to the great decrease of floor contamination in the receipt and storage facility. The decrease permitted as many as about 20,000 visitors to take tours in the fuel receipt and storage facility in the past three years without contamination trouble with the visitors. Different types of spent fuels can be easily handled and stored by the specially designed tools in the pool water. The exchange of the cooling water in the transport cask before unloading and the use of the storage container keep contamination of the pool water to a minimum. The pool water treatment system has been successfully operated. As result, the pool water condition has been well-controlled

  15. Defense Remote Handled Transuranic Waste Cost/Schedule Optimization Study

    International Nuclear Information System (INIS)

    Pierce, G.D.; Wolaver, R.W.; Carson, P.H.

    1986-11-01

    The purpose of this study is to provide the DOE information with which it can establish the most efficient program for the long management and disposal, in the Waste Isolation Pilot Plant (WIPP), of remote handled (RH) transuranic (TRU) waste. To fulfill this purpose, a comprehensive review of waste characteristics, existing and projected waste inventories, processing and transportation options, and WIPP requirements was made. Cost differences between waste management alternatives were analyzed and compared to an established baseline. The result of this study is an information package that DOE can use as the basis for policy decisions. As part of this study, a comprehensive list of alternatives for each element of the baseline was developed and reviewed with the sites. The principle conclusions of the study follow. A single processing facility for RH TRU waste is both necessary and sufficient. The RH TRU processing facility should be located at Oak Ridge National Laboratory (ORNL). Shielding of RH TRU to contact handled levels is not an economic alternative in general, but is an acceptable alternative for specific waste streams. Compaction is only cost effective at the ORNL processing facility, with a possible exception at Hanford for small compaction of paint cans of newly generated glovebox waste. It is more cost effective to ship certified waste to WIPP in 55-gal drums than in canisters, assuming a suitable drum cask becomes available. Some waste forms cannot be packaged in drums, a canister/shielded cask capability is also required. To achieve the desired disposal rate, the ORNL processing facility must be operational by 1996. Implementing the conclusions of this study can save approximately $110 million, compared to the baseline, in facility, transportation, and interim storage costs through the year 2013. 10 figs., 28 tabs

  16. Integral Monitored Retrievable Storage (MRS) Facility conceptual design report

    International Nuclear Information System (INIS)

    1985-09-01

    This document, Volume 6 Book 1, contains information on design studies of a Monitored Retrievable Storage (MRS) facility. Topics include materials handling; processing; support systems; support utilities; spent fuel; high-level waste and alpha-bearing waste storage facilities; and field drywell storage

  17. Fluid dynamic studies for a simulated Melton Valley Storage Tank slurry

    International Nuclear Information System (INIS)

    Hylton, T.D.; Youngblood, E.L.; Cummins, R.L.

    1994-07-01

    The Melton Valley Storage Tanks (MVSTs), are used for the collection and storage of remote-handled radioactive liquid wastes. These wastes, which were typically acidic when generated, were neutralized with the addition of sodium hydroxide to protect the storage tanks from corrosion, but this caused the transuranic and heavy metals to precipitate. These wastes will eventually need to be removed from the tanks for ultimate disposal. The objective of the research activities discussed in this report is to support the design of a pipeline transport system between the MVSTs and a treatment facility. Since the wastes in the MVSTs are highly radioactive, a surrogate slurry was developed for this study. Rheological properties of the simulated slurry were determined in a test loop in which the slurry was circulated through three pipeline viscometers of different diameters. Pressure drop data at varying flow rates were used to obtain shear stress and shear rate data. The data were analyzed, and the slurry rheological properties were analyzed by the Power Law model and the Bingham plastic model. The plastic viscosity and yield stress data obtained from the rheological tests were used as inputs for a piping design software package, and the pressure drops predicted by the software compared well with the pressure drop data obtained from the test loop. The minimum transport velocity was determine for the slurry by adding known nominal sizes of glass spheres to the slurry. However, it was shown that the surrogate slurry exhibited hindered settling, which may substantially decrease the minimum transport velocity. Therefore, it may be desired to perform additional tests with a surrogate with a lower concentration of suspended solids to determine the minimum transport velocity

  18. US Department of Energy Automated Transportation Management System

    International Nuclear Information System (INIS)

    Portsmouth, J.H.

    1994-01-01

    The U.S. Department of Energy (DOE) Transportation Management Division (TMD) is responsible for managing its various programs via a diverse combination of Government-Owned/Contractor-Operated facilities. TMD is seeking to update it automation capabilities in capturing and processing DOE transportation information. TMD's Transportation Information Network (TIN) is an attempt to bring together transportation management, shipment tracking, research activities and software products in various stages of development. The TMD's Automated Transportation Management System (ATMS) proposes to assist the DOE and its contractors in performing their daily transportation management activities and to assist the DOE Environmental Management Division in its waste management responsibilities throughout the DOE complex. The ATMS system will center about the storage, handling and documentation involved in the environmental clean-up of DOE sites. Waste shipments will be moved to approved Treatment, Storage and Disposal (TSD) facilities and/or nuclear material repositories. An additional investment in shipping samples to analytical laboratories also involves packaging and documentation according to all applicable U.S. Department of Transportation (DOT) or International Air Transport Association (IATA) regulations. The most immediate goal of effectively managing DOE transportation management functions during the 1990's is an increase in automation capabilities of the DOE and its contractors. Subject-matter experts from various DOE site locations will be brought together to develop and refine these capabilities through the maximum use of computer applications. A major part of this effort will be the identification of the most economical modes of transportation and enhanced management reporting capabilities for transportation analysis. The ATMS system will also provide for increased strategic and shipment analysis during the 1990's and beyond in support of the DOE environmental mission

  19. BWR - Spent Fuel Transport and Storage with the TNTM9/4 and TNTM24BH Casks

    International Nuclear Information System (INIS)

    Wattez, L.; Marguerat, Y.; Hoesli, C.

    2006-01-01

    The Swiss Nuclear Utilities have started in 2001 to store spent fuel in dry metallic dual-purpose casks at ZWILAG, the Swiss interim storage facility. BKW FMB Energy Ltd., the Muehleberg Nuclear Power Plant owner, is involved in this process and has elected to store its BWR spent fuel in a new high capacity dual-purpose cask, the TNeTeM24BH from the COGEMA Logistics/TRANSNUCLEAR TN TM 24 family. The Muehleberg BWR spent fuels are transported by road in a medium size shuttle transport cask and then transferred to a heavy transport/storage cask (dry transfer) in the hot cell of ZWILAG site. For that purpose, COGEMA Logistics designed and supplied: - Two shuttle casks, TN TM 9/4, mainly devoted to transport of spent fuel from Muehleberg NPP to ZWILAG. Licensed according to IAEA 1996, the TN TM 9/4 is a 40 ton transport cask, for 7 BWR high bum-up spent fuel assemblies. - A series of new high capacity dual-purpose casks, TN TM 24BH, holding 69 BWR spent fuels. Two transport campaigns took place in 2003 and 2004. For each campaign, ten TN TM 9/4 round trips are performed, and one TN TM 24BH is loaded. 5 additional TN TM 24BH are being manufactured for BKW, and the next transport campaigns are scheduled from 2006. The TN TM 24BH high capacity dual purpose cask and the TN TM 9/4 transport cask characteristics and capabilities will then be detailed. (authors)

  20. LACIE data-handling techniques

    Science.gov (United States)

    Waits, G. H. (Principal Investigator)

    1979-01-01

    Techniques implemented to facilitate processing of LANDSAT multispectral data between 1975 and 1978 are described. The data that were handled during the large area crop inventory experiment and the storage mechanisms used for the various types of data are defined. The overall data flow, from the placing of the LANDSAT orders through the actual analysis of the data set, is discussed. An overview is provided of the status and tracking system that was developed and of the data base maintenance and operational task. The archiving of the LACIE data is explained.

  1. 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

  2. Advisory Material for the IAEA Regulations for the Safe Transport of Radioactive Material. Safety Guide (Spanish Edition)

    International Nuclear Information System (INIS)

    2010-01-01

    This Safety Guide provides recommendations on achieving and demonstrating compliance with IAEA Safety Standards Series No. TS-R-1, Regulations for the Safe Transport of Radioactive Material, 2005 Edition, establishing safety requirements to be applied to the national and international transport of radioactive material. Transport is deemed to comprise all operations and conditions associated with and involved in the movement of radioactive material; these include the design, fabrication and maintenance of packaging, and the preparation, consigning, handling, carriage, storage in transit and receipt at the final destination of packages. This publication supersedes IAEA Safety Series No. TS-G-1.1, 2002 Edition

  3. Transportation safety training

    International Nuclear Information System (INIS)

    Jones, E.

    1990-01-01

    Over the past 25 years extensive federal legislation involving the handling and transport of hazardous materials/waste has been passed that has resulted in numerous overlapping regulations administered and enforced by different federal agencies. The handling and transport of hazardous materials/waste involves a significant number of workers who are subject to a varying degree of risk should an accident occur during handling or transport. Effective transportation training can help workers address these risks and mitigate them, and at the same time enable ORNL to comply with the federal regulations concerning the transport of hazardous materials/waste. This presentation will outline how the Environmental and Health Protection Division's Technical Resources and Training Section at the Oak Ridge National Laboratory, working with transportation and waste disposal personnel, have developed and implemented a comprehensive transportation safety training program to meet the needs of our workers while satisfying appropriate federal regulations. 8 refs., 3 tabs

  4. Cask system design guidance for robotic handling

    International Nuclear Information System (INIS)

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

    1990-10-01

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

  5. 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

  6. Integrated management platform of nuclear fuel storage and transportation based on RFID

    International Nuclear Information System (INIS)

    Song Yafeng; Ma Yanqin; Chen Liyu; Jiang Yong; Wu Jianlei; Yang Haibo; Zhang Haiyan

    2012-01-01

    This paper describes integrated system model to improve work efficiency and optimize control measures of nuclear fuel storage and transportation, RFID and information integration technology is introduced, traditional management processes are innovated in data acquisition and monitoring fields as well, system solutions and design model are given by emphasizing on the following key technologies: cascade protection of information system, security protocol of RFID information, algorithm of collision. (authors)

  7. Center for Electrocatalysis, Transport Phenomena, and Materials (CETM) for Innovative Energy Storage - Final Report

    Energy Technology Data Exchange (ETDEWEB)

    Soloveichik, Grigorii [GE Global Research, Niskayuna, New York (United States)

    2015-11-30

    EFRC vision. The direct use of organic hydrides in fuel cells as virtual hydrogen carriers that generate stable organic molecules, protons, and electrons upon electro-oxidation and can be electrochemically charged by re-hydrogenating the oxidized carrier was the major focus of the Center for Electrocatalysis, Transport Phenomena and Materials for Innovative Energy Storage (EFRC-ETM). Compared to a hydrogen-on-demand design that includes thermal decomposition of organic hydrides in a catalytic reactor, the proposed approach is much simpler and does not require additional dehydrogenation catalysts or heat exchangers. Further, this approach utilizes the advantages of a flow battery (i.e., separation of power and energy, ease of transport and storage of liquid fuels) with fuels that have system energy densities similar to current hydrogen PEM fuel cells. EFRC challenges. Two major EFRC challenges were electrocatalysis and transport phenomena. The electrocatalysis challenge addresses fundamental processes which occur at a single molecular catalyst (microscopic level) and involve electron and proton transfer between the hydrogen rich and hydrogen depleted forms of organic liquid fuel and the catalyst. To form stable, non-radical dehydrogenation products from the organic liquid fuel, it is necessary to ensure fast transport of at least two electrons and two protons (per double bond formation). The same is true for the reverse hydrogenation reaction. The transport phenomena challenge addresses transport of electrons to/from the electrocatalyst and the current collector as well as protons across the polymer membrane. Additionally it addresses prevention of organic liquid fuel, water and oxygen transport through the PEM. In this challenge, the transport of protons or molecules involves multiple sites or a continuum (macroscopic level) and water serves as a proton conducting medium for the majority of known sulfonic acid based PEMs. Proton transfer in the presence of

  8. Design characteristics of pantograph type in vessel fuel handling system in SFR

    International Nuclear Information System (INIS)

    Kim, S. H.; Koo, G. H.

    2012-01-01

    The pantograph type in vessel fuel handling system in a sodium cooled fast reactor (SFR), which requires installation space for the slot in the upper internal structure attached under the rotating plug, is composed of an in vessel transfer machine (IVTM), a single rotating plug, in vessel storage, and a fuel transfer port (FTP). The pantograph type IVTM can exchange fuel assemblies through a slot, the design requirement of which should be essentially considered in the design of the in vessel fuel handling system. In addition, the spent fuel assemblies temporarily stored in the in vessel storage of the reactor vessel are removed to the outside of the reactor vessel through the FTP. The fuel transfer basket is then provided in the FTP, and a fuel transfer is performed by using it. In this study, the design characteristics for a pantograph type in vessel fuel handling system are reviewed, and the preconceptual designs are studied

  9. Design characteristics of pantograph type in vessel fuel handling system in SFR

    Energy Technology Data Exchange (ETDEWEB)

    Kim, S. H.; Koo, G. H. [KAERI, Daejeon (Korea, Republic of)

    2012-10-15

    The pantograph type in vessel fuel handling system in a sodium cooled fast reactor (SFR), which requires installation space for the slot in the upper internal structure attached under the rotating plug, is composed of an in vessel transfer machine (IVTM), a single rotating plug, in vessel storage, and a fuel transfer port (FTP). The pantograph type IVTM can exchange fuel assemblies through a slot, the design requirement of which should be essentially considered in the design of the in vessel fuel handling system. In addition, the spent fuel assemblies temporarily stored in the in vessel storage of the reactor vessel are removed to the outside of the reactor vessel through the FTP. The fuel transfer basket is then provided in the FTP, and a fuel transfer is performed by using it. In this study, the design characteristics for a pantograph type in vessel fuel handling system are reviewed, and the preconceptual designs are studied.

  10. Organization and costs of repurchasing, transportation, warehousing and storage of raspberry fruit

    Directory of Open Access Journals (Sweden)

    Kalanović-Bulatović Branka

    2015-01-01

    Full Text Available Due to its characteristic, apart from nutritive and medical significance, raspberry is particularly important for our country in social and economic terms, since its export attracts foreign currency inflow. Since the quality of raspberry decreases rapidly after picking, it is utterly important that the whole process, from picking to cold storage of fruit, should be rationally organized, thus finally reducing the costs and increasing the production value. For these reasons precisely the research deals with organization of the entire process, from repurchase to cold storage of raspberry fruits, as well as the analysis of pertaining costs. Necessary information for the preparation of the paper has been obtained from cold storage plants engaged in raspberry storage and preservation. Necessary information has been gathered using several methods, viz: observation, interview and content analysis methods. Furthermore, analysis, comparison and calculation methods have also been used in the preparation of the paper. The raspberry fruit repurchase, transport and storage costs range from 1,6 to 1,8 EUR per kg, exclusive of storage (store-housing. To this one should add store-housing costs ranging from 0,009 to 0,013 EUR per kg on a monthly basis. Modern organization of production and communication between producers, repurchasers, processors and exporters is essential in order to decrease fluctuations in repurchase and sales price of fresh raspberry and its products and the improvement of overall financial effect of all links within the chain of this economy activity. Cold storage plants, even if of minor capacities, are beneficial not only for the immediate participants in the producer-buyer chain, but it also makes an important stimulating factor for rural development and economy of the country.

  11. Salinity does not alter the effectiveness of menthol as an anesthetic and sedative during the handling and transport of juvenile fat snook (Centropomus parallelus

    Directory of Open Access Journals (Sweden)

    L. C. O.’R. Sepulchro

    Full Text Available Abstract The effectiveness of menthol as anesthetic and sedative for fat snook (Centropomus parallelus was tested at different salinities. In the first experiment, the fish were exposed to different concentrations of menthol (25, 37 and 50 mg L–1 in water at different salinities (0, 17 and 36 ppt. In the second experiment, the fish were transported for 10 hours in water with menthol at concentrations of 0, 3.7 and 7.4 mg L–1 under different salinities. Na+ and K+ ions from fish body and water were analyzed after transport. The optimal concentrations of menthol for a short handling period and surgical induction was 37 and 50 mg L–1, respectively, and these values were independent of salinity. After transport, neither mortality nor significant changes in ammonia or dissolved oxygen were observed between treatments at the different salinities. The nitrite levels were lower in freshwater than in brackish and saltwater, but did not change with mentol. The total body levels of Na+ increased with the salinity increase. Menthol is an effective anesthetic for handling of juvenile fat snook at different salinities. Menthol did not influence the measured water parameters and body ions, and it is not necessary for the transport of fat snook.

  12. Salinity does not alter the effectiveness of menthol as an anesthetic and sedative during the handling and transport of juvenile fat snook (Centropomus parallelus).

    Science.gov (United States)

    Sepulchro, L C O 'r; Carvalho, M A G; Gomes, L C

    2016-04-19

    The effectiveness of menthol as anesthetic and sedative for fat snook (Centropomus parallelus) was tested at different salinities. In the first experiment, the fish were exposed to different concentrations of menthol (25, 37 and 50 mg L-1) in water at different salinities (0, 17 and 36 ppt). In the second experiment, the fish were transported for 10 hours in water with menthol at concentrations of 0, 3.7 and 7.4 mg L-1 under different salinities. Na+ and K+ ions from fish body and water were analyzed after transport. The optimal concentrations of menthol for a short handling period and surgical induction was 37 and 50 mg L-1, respectively, and these values were independent of salinity. After transport, neither mortality nor significant changes in ammonia or dissolved oxygen were observed between treatments at the different salinities. The nitrite levels were lower in freshwater than in brackish and saltwater, but did not change with mentol. The total body levels of Na+ increased with the salinity increase. Menthol is an effective anesthetic for handling of juvenile fat snook at different salinities. Menthol did not influence the measured water parameters and body ions, and it is not necessary for the transport of fat snook.

  13. ASRS application in radioactive material handling

    International Nuclear Information System (INIS)

    Shalina Sheik Muhamad and Rosli Darmawan

    2007-01-01

    ASRS is a computer controlled methods for automatically depositing and retrieving loads from defined storage locations. It consists of several major components which are the Controls System, Storage Structure (Racks), Storage/Retrieval (S/R) Machines, Fire Protection Systems, Pickup and Delivery (P and D) Stations, Storage Modules (Pallets, Baskets, Containers), Aisle Hardware, Aisle Transfer Cars, Conveyors and other transportation equipment. This paper aims to provide an overview of the potential application of the ASRS in Nuclear Malaysia. The need to use the system, operating principle and potential application will be discussed. (Author)

  14. 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.

  15. Work plan for development of K-Basin fuel handling tools

    International Nuclear Information System (INIS)

    Bridges, A.E.

    1994-01-01

    The purpose of this document is to provide the engineering work plan for the development of handling tools for the removal of N-Reactor fuel elements from their storage canisters in the K-Basins storage pool and insertion into the Single Fuel Element Cans for subsequent shipment to a Hot Cell for examination. Examination of these N-Reactor fuel elements is part of the overall characterization effort. New hand tools are required since previous fuel movement has involved grasping the fuel in a horizontal position. These tools are required to lift an element from the storage canister

  16. [The design of heat dissipation of the field low temperature box for storage and transportation].

    Science.gov (United States)

    Wei, Jiancang; Suin, Jianjun; Wu, Jian

    2013-02-01

    Because of the compact structure of the field low temperature box for storage and transportation, which is due to the same small space where the compressor, the condenser, the control circuit, the battery and the power supply device are all placed in, the design for heat dissipation and ventilation is of critical importance for the stability and reliability of the box. Several design schemes of the heat dissipation design of the box were simulated using the FLOEFD hot fluid analysis software in this study. Different distributions of the temperature field in every design scheme were constructed intimately in the present study. It is well concluded that according to the result of the simulation analysis, the optimal heat dissipation design is decent for the field low temperature box for storage and transportation, and the box can operate smoothly for a long time using the results of the design.

  17. Surface contamination of hazardous drug pharmacy storage bins and pharmacy distributor shipping containers.

    Science.gov (United States)

    Redic, Kimberly A; Fang, Kayleen; Christen, Catherine; Chaffee, Bruce W

    2018-03-01

    Purpose This study was conducted to determine whether there is contamination on exterior drug packaging using shipping totes from the distributor and carousel storage bins as surrogate markers of external packaging contamination. Methods A two-part study was conducted to measure the presence of 5-fluorouracil, ifosfamide, cyclophosphamide, docetaxel and paclitaxel using surrogate markers for external drug packaging. In Part I, 10 drug distributor shipping totes designated for transport of hazardous drugs provided a snapshot view of contamination from regular use and transit in and out of the pharmacy. An additional two totes designated for transport of non-hazardous drugs served as controls. In Part II, old carousel storage bins (i.e. those in use pre-study) were wiped for snapshot view of hazardous drug contamination on storage bins. New carousel storage bins were then put into use for storage of the five tested drugs and used for routine storage and inventory maintenance activities. Carousel bins were wiped at time intervals 0, 8, 16 and 52 weeks to measure surface contamination. Results Two of the 10 hazardous shipping totes were contaminated. Three of the five-old carousel bins were contaminated with cyclophosphamide. One of the old carousel bins was also contaminated with ifosfamide. There were no detectable levels of hazardous drugs on any of the new storage bins at time 0, 8 or 16 weeks. However, at the Week 52, there was a detectable level of 5-FU present in the 5-FU carousel bin. Conclusions Contamination of the surrogate markers suggests that external packaging for hazardous drugs is contaminated, either during the manufacturing process or during routine chain of custody activities. These results demonstrate that occupational exposure may occur due to contamination from shipping totes and storage bins, and that handling practices including use of personal protective equipment is warranted.

  18. Environmental and thermodynamic evaluation of CO2 capture, transport and storage with and without enhanced resource recovery

    International Nuclear Information System (INIS)

    Iribarren, Diego; Petrakopoulou, Fontina; Dufour, Javier

    2013-01-01

    This study evaluates the environmental and thermodynamic performance of six coal-fired power plants with CO 2 capture and storage. The technologies examined are post-combustion capture using monoethanolamine, membrane separation, cryogenic fractionation and pressure swing adsorption, pre-combustion capture through coal gasification, and capture performing conventional oxy-fuel combustion. The incorporation of CO 2 capture is evaluated both on its own and in combination with CO 2 transport and geological storage, with and without beneficial use. Overall, we find that pre-combustion CO 2 capture and post-combustion through membrane separation present relatively low life-cycle environmental impacts and high exergetic efficiencies. When accounting for transport and storage, the environmental impacts increase and the efficiencies decrease. However, a better environmental performance can be achieved for CO 2 capture, transport and storage when incorporating beneficial use through enhanced oil recovery. The performance with enhanced coal-bed methane recovery, on the other hand, depends on the impact categories evaluated. The incorporation of methane recovery results in a better thermodynamic performance, when compared to the incorporation of oil recovery. The cumulative energy demand shows that the integration of enhanced resource recovery strategies is necessary to attain favourable life-cycle energy balances. - Highlights: ► Evaluation of six different CO 2 capture technologies for coal-fired power plants. ► Calculation of life-cycle environmental impacts and exergetic efficiencies. ► Suitability of post-combustion capture with membrane separation. ► Suitability of pre-combustion capture through coal gasification. ► Improved performance when incorporating enhanced resource recovery

  19. Evaluation of greenhouse gas emission risks from storage of wood residue

    International Nuclear Information System (INIS)

    Wihersaari, Margareta

    2005-01-01

    The use of renewable energy sources instead of fossil fuels is one of the most important means of limiting greenhouse gas emissions in the near future. In Finland, wood energy is considered to be a very important potential energy source in this sense. There might, however, still be some elements of uncertainty when evaluating biofuel production chains. By combining data from a stack of composting biodegradable materials and forest residue storage research there was an indication that rather great amounts of greenhouse gases maybe released during storage of wood chip, especially if there is rapid decomposition. Unfortunately, there have not been many evaluations of greenhouse gas emissions of biomass handling and storage heaps. The greenhouse gas emissions are probably methane, when the temperature in the fuel stack is above the ambient temperature, and nitrous oxide, when the temperature is falling and the decaying process is slowing down. Nowadays it is still rather unusual to store logging residue as chips, because the production is small, but in Finland storage of bark and other by-products from the forest industry is a normal process. The evaluations made indicate that greenhouse gas emissions from storage can, in some cases, be much greater than emissions from the rest of the biofuel production and transportation chain

  20. Safety for fuel assembly handling in the nuclear ship Mutsu

    International Nuclear Information System (INIS)

    Ando, Yoshio

    1978-01-01

    The safety for fuel assembly handling in the nuclear ship Mutsu is deliberated by the committee of general inspection and repair technique examination for Mutsu. The result of deliberation for both cases of removing fuel assemblies and keeping them in the reactor is outlined. The specification of fuel assemblies, and the nuclides and designed radioactivity of fission products of fuel are described. The possibility of shielding repair work and general safety inspection keeping the fuel assemblies in the reactor, the safety consideration when the fuel assemblies are removed at a quay, in a dry dock and on the ocean, the safety of fuel transport in special casks and fuel storage are explained. It is concluded finally that the safety of shielding repair work and general inspection work is secured when the fuel assemblies are kept in the reactor and also when the fuel assemblies are removed from the reactor by cautious working. (Nakai, Y.)

  1. 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

  2. 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

  3. Perry Nuclear Plant's Plans for on-site storage

    International Nuclear Information System (INIS)

    Ratchen, J.T.

    1993-01-01

    Because of current radwaste disposal legislation and the eventual denial of access to the Barnwell, Richland, and Beatty burial sites, it was imperative for the Perry nuclear power plant to develop alternative means for handling its generated radioactive waste. The previous radwaste facilities at Perry were developed for processing, packaging, short-term storage, and shipment for burial. In order to meet the changing needs, new facilities have been constructed to handle the processing, packaging, and 5-yr interim storage of both dry active waste (DAW) and dewatered or solidified resin, filter media, etc

  4. Remote handling assessment of attachment concepts for DEMO blanket segments

    Energy Technology Data Exchange (ETDEWEB)

    Iglesias, Daniel, E-mail: daniel.iglesias@ccfe.ac.uk [CCFE, Culham Science Centre, Abingdon, Oxon OX14 3DB (United Kingdom); Bastow, Roger; Cooper, Dave; Crowe, Robert; Middleton-Gear, Dave [CCFE, Culham Science Centre, Abingdon, Oxon OX14 3DB (United Kingdom); Sibois, Romain [VTT, Technical Research Centre of Finland, Industrial Systems, ROViR, Tampere (Finland); Carloni, Dario [Institute of Neutron Physics and Reactor Technology, Karlsruhe Institute of Technology (KIT) (Germany); Vizvary, Zsolt; Crofts, Oliver [CCFE, Culham Science Centre, Abingdon, Oxon OX14 3DB (United Kingdom); Harman, Jon [EFDA Close Support Unit Garching, Boltzmannstaße 2, D-85748 Garching bei München (Germany); Loving, Antony [CCFE, Culham Science Centre, Abingdon, Oxon OX14 3DB (United Kingdom)

    2015-10-15

    Highlights: • Challenges are identified for the remote handling of blanket segments’ attachments. • Two attachment design approaches are assessed for remote handling (RH) feasibility. • An alternative is proposed, which potentially simplifies and speeds-up RH operations. • Up to three different assemblies are proposed for the remote handling of the attachments. • Proposed integrated design of upper port is compatible with the attachment systems. - Abstract: The replacement strategy of the massive Multi-Module Blanket Segments (MMS) is a key driver in the design of several DEMO systems. These include the blankets themselves, the vacuum vessel (VV) and its ports and the Remote Maintenance System (RMS). Common challenges to any blanket attachment system have been identified, such as the need for applying a preload to the MMS manifold, the effects of the decay heat and several uncertainties related to permanent deformations when removing the blanket segments after service. The WP12 kinematics of the MMS in-vessel transportation was adapted to the requirements of each of the supports during 2013 and 2014 design activities. The RM equipment envisaged for handling attachments and earth connections may be composed of up to three different assemblies. An In-Vessel Mover at the divertor level handles the lower support and earth bonding, and could stabilize the MMS during transportation. A Shield Plug crane with a 6 DoF manipulator operates the upper attachment and earth straps. And a Vertical Maintenance Crane is responsible for the in-vessel MMS transportation and can handle the removable upper support pins. A final proposal is presented which can potentially reduce the number of required systems, at the same time that speeds-up the RMS global operations.

  5. 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

  6. Examples of remote handling of irradiated fuel assemblies in Germany

    International Nuclear Information System (INIS)

    Peehs, M.; Knecht, K.

    1999-01-01

    Examples for the remote handling of irradiated fuel in Germany are presented in the following areas: - fuel assembling pool service activities; - early encapsulation of spent fuel in the pool of a nuclear power plant (NPP) at the end of the wet storage period. All development in remote fuel assembly handling envisages minimization of the radioactive dose applied to the operating staff. In the service area a further key objective for applying advanced methods is to perform the work faster and at a higher quality standard. The early encapsulation is a new technology to provide the final packaging of spent fuel already in the pool of a NPP to ensure reliable handling for all further back end processes. (author)

  7. Handling of Highly Radioactive Radiation Sources in a Hot Cell Using a Mechanically Driven Cell Crane - 13452

    Energy Technology Data Exchange (ETDEWEB)

    Klute, Stefan; Huber, Wolfgang-Bruno [Siempelkamp Nukleartechnik GmbH, Am Taubenfeld 25/1, 69123 Heidelberg (Germany); Meyer, Franz [Nuclear Engineering Seibersdorf GmbH, 2444 Seibersdorf (Austria)

    2013-07-01

    In 2010, Siempelkamp Nukleartechnik GmbH was awarded the contract for design and erection of a Hot Cell for handling and storage of highly radioactive radiation sources. This Hot Cell is part of a new hot cell laboratory, constructed for the NHZ (Neues Handhabungszentrum = New Handling Center) of the Nuclear Engineering Seibersdorf GmbH (NES). All incurring radioactive materials from Austria are collected in the NHZ, where they are safely conditioned and stored temporarily until their final storage. The main tasks of the NES include, apart from the collection, conditioning and storage of radioactive waste, also the reprocessing and the decontamination of facilities and laboratories originating from 45 years of research and development at the Seibersdorf site as well as the operation of the Hot Cell Laboratory [1]. The new Hot Cell Laboratory inside the NHZ consists of the following room areas: - One hot cell, placed in the center, for remote controlled, radiation protected handling of radioactive materials, including an integrated floor storage for the long-term temporary storage of highly radioactive radiation sources; - An anteroom for the loading and unloading of the hot cell; - One control room for the remote controlling of the hot cell equipment; - One floor storage, placed laterally to the hot cell, for burial, interim storage and removal of fissionable radioactive material in leak-proof packed units in 100 l drums. The specific design activity of the hot cell of 1.85 Pbq relating to 1-Me-Radiator including the integrated floor storage influences realization and design of the components used in the cell significantly. (authors)

  8. Heat and Moisture Transport and Storage Parameters of Bricks Affected by the Environment

    Science.gov (United States)

    Kočí, Václav; Čáchová, Monika; Koňáková, Dana; Vejmelková, Eva; Jerman, Miloš; Keppert, Martin; Maděra, Jiří; Černý, Robert

    2018-05-01

    The effect of external environment on heat and moisture transport and storage properties of the traditional fired clay brick, sand-lime brick and highly perforated ceramic block commonly used in the Czech Republic and on their hygrothermal performance in building envelopes is analyzed by a combination of experimental and computational techniques. The experimental measurements of thermal, hygric and basic physical parameters are carried out in the reference state and after a 3-year exposure of the bricks to real climatic conditions of the city of Prague. The obtained results showed that after 3 years of weathering the porosity of the analyzed bricks increased up to five percentage points which led to an increase in liquid and gaseous moisture transport parameters and a decrease in thermal conductivity. Computational modeling of hygrothermal performance of building envelopes made of the studied bricks was done using both reference and weather-affected data. The simulated results indicated an improvement in the annual energy balances and a decrease in the time-of-wetness functions as a result of the use of data obtained after the 3-year exposure to the environment. The effects of weathering on both heat and moisture transport and storage parameters of the analyzed bricks and on their hygrothermal performance were found significant despite the occurrence of warm winters in the time period of 2012-2015 when the brick specimens were exposed to the environment.

  9. Analysis of multi cloud storage applications for resource constrained mobile devices

    Directory of Open Access Journals (Sweden)

    Rajeev Kumar Bedi

    2016-09-01

    Full Text Available Cloud storage, which can be a surrogate for all physical hardware storage devices, is a term which gives a reflection of an enormous advancement in engineering (Hung et al., 2012. However, there are many issues that need to be handled when accessing cloud storage on resource constrained mobile devices due to inherent limitations of mobile devices as limited storage capacity, processing power and battery backup (Yeo et al., 2014. There are many multi cloud storage applications available, which handle issues faced by single cloud storage applications. In this paper, we are providing analysis of different multi cloud storage applications developed for resource constrained mobile devices to check their performance on the basis of parameters as battery consumption, CPU usage, data usage and time consumed by using mobile phone device Sony Xperia ZL (smart phone on WiFi network. Lastly, conclusion and open research challenges in these multi cloud storage apps are discussed.

  10. Seven years of experience in storage of solid radioactive wastes of low and medium activity on the surface or in concrete ditches

    International Nuclear Information System (INIS)

    Bardet, G.

    This experience in the transport and storage of radioactive waste leads to several reflections pertinent to large-scale nuclear installations throughout the world. The experience demonstrates that products of this kind can be centralized and confined by relatively simple processes which are safe and of reasonable cost. The necessary liaison between the producer of radioactive wastes and the group which takes charge of storage is emphasized for the choice of the waste conditioning procedure. It is a consistent part of the experience that the initial conditioning determines in large measure the handling and storage techniques. It is certain that the absence of a solution for long-term storage of radioactive wastes will lead the producers to consider and carry out conditioning which, although valuable, does not have all the same advantages for final disposition of the product. In the field of transport, the volumes and weights are important. It is desirable that a permanent storage center be near a railroad. It is stated that storage can be ensured under safe conditions and with acceptable costs of all solid wastes of low and average activity except those having more than a certain amount of alpha activity. For the latter products a solution can be found which is safe

  11. TRU [transuranic] waste certification compliance requirements for acceptance of newly generated contact-handled wastes to be shipped to the Waste Isolation Pilot Plant: Revision 2

    International Nuclear Information System (INIS)

    1989-01-01

    Compliance requirements are presented for certifying that unclassified, newly generated (NG), contact-handled (CH) transuranic (TRU) solid wastes from defense programs meet the Waste Isolation Pilot Plant (WIPP) Waste Acceptance Criteria (WAC). Where appropriate, transportation and interim storage requirements are incorporated; however, interim storage sites may have additional requirements consistent with these requirements. All applicable Department of Energy (DOE) orders must continue to be met. The compliance requirements for stored or buried waste are not addressed in this document. The compliance requirements are divided into four sections, primarily determined by the general feature that the requirements address. These sections are General Requirements, Waste Container Requirements, Waste Form Requirements, and Waste Package Requirements. The waste package is the combination of waste container and waste. 10 refs., 1 fig

  12. 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

  13. Proposal for the award of an industrial support contract for transport and handling services

    CERN Document Server

    1999-01-01

    This document concerns the award of an industrial support contract for transport and handling services. Following a market survey carried out among 49 firms in nine Member States, a call for tenders (IT-2395/ST/Revised) was sent on 7 April 1999 to two firms and six consortia in seven Member States. By the closing date, CERN had received six tenders. The Finance Committee is invited to agree to the negotiation of a contract with the consortium DELATTRE-LEVIVIER (FR) ? BELLELI (IT) ? SETROVA (PT) the lowest bidder complying with the specification, for an initial period of three years, from 1st May 2000, for a total amount not exceeding 22 000 000 Swiss francs, not subject to revision until 30 April 2003. The contract will include an option for two one-year extensions beyond the initial three-year period.

  14. Sample handling in surface sensitive chemical and biological sensing: a practical review of basic fluidics and analyte transport.

    Science.gov (United States)

    Orgovan, Norbert; Patko, Daniel; Hos, Csaba; Kurunczi, Sándor; Szabó, Bálint; Ramsden, Jeremy J; Horvath, Robert

    2014-09-01

    This paper gives an overview of the advantages and associated caveats of the most common sample handling methods in surface-sensitive chemical and biological sensing. We summarize the basic theoretical and practical considerations one faces when designing and assembling the fluidic part of the sensor devices. The influence of analyte size, the use of closed and flow-through cuvettes, the importance of flow rate, tubing length and diameter, bubble traps, pressure-driven pumping, cuvette dead volumes, and sample injection systems are all discussed. Typical application areas of particular arrangements are also highlighted, such as the monitoring of cellular adhesion, biomolecule adsorption-desorption and ligand-receptor affinity binding. Our work is a practical review in the sense that for every sample handling arrangement considered we present our own experimental data and critically review our experience with the given arrangement. In the experimental part we focus on sample handling in optical waveguide lightmode spectroscopy (OWLS) measurements, but the present study is equally applicable for other biosensing technologies in which an analyte in solution is captured at a surface and its presence is monitored. Explicit attention is given to features that are expected to play an increasingly decisive role in determining the reliability of (bio)chemical sensing measurements, such as analyte transport to the sensor surface; the distorting influence of dead volumes in the fluidic system; and the appropriate sample handling of cell suspensions (e.g. their quasi-simultaneous deposition). At the appropriate places, biological aspects closely related to fluidics (e.g. cellular mechanotransduction, competitive adsorption, blood flow in veins) are also discussed, particularly with regard to their models used in biosensing. Copyright © 2014 Elsevier B.V. All rights reserved.

  15. Spent fuel transport and storage system for NOK: The TN52L, TN97L, TN24 BHL and TN24 GB casks

    International Nuclear Information System (INIS)

    Wattez, L.; Verdier, A.; Monsigny, P.-A.

    2007-01-01

    NOK nuclear power plants in Switzerland, LEIBSTADT (KKL) BWR nuclear power plant and BEZNAU (KKB) PWR nuclear power plant have opted to ship spent fuel to a central facility called ZWILAG for interim storage. In the mid-nineties, COGEMA LOGISTICS was contracted by KKL for the supply of the TN52L and TN97L transport and storage casks for BWR fuel types. In 2003, KKL also ordered from COGEMA LOGISTICS the supply of six TN24 BHL transport and storage casks. This paper shows how all the three cask designs have responded to the KKL needs to ship and store BWR spent fuel. In addition, it highlights the already significant operational feedback of the TN52L and TN97L casks by the KKL and ZWILAG operators. In 2004, NOK also ordered three TN24 GB transport and storage casks for PWR fuel types. These casks are presently being manufactured. (author)

  16. Templated assembly of photoswitches significantly increases the energy-storage capacity of solar thermal fuels.

    Science.gov (United States)

    Kucharski, Timothy J; Ferralis, Nicola; Kolpak, Alexie M; Zheng, Jennie O; Nocera, Daniel G; Grossman, Jeffrey C

    2014-05-01

    Large-scale utilization of solar-energy resources will require considerable advances in energy-storage technologies to meet ever-increasing global energy demands. Other than liquid fuels, existing energy-storage materials do not provide the requisite combination of high energy density, high stability, easy handling, transportability and low cost. New hybrid solar thermal fuels, composed of photoswitchable molecules on rigid, low-mass nanostructures, transcend the physical limitations of molecular solar thermal fuels by introducing local sterically constrained environments in which interactions between chromophores can be tuned. We demonstrate this principle of a hybrid solar thermal fuel using azobenzene-functionalized carbon nanotubes. We show that, on composite bundling, the amount of energy stored per azobenzene more than doubles from 58 to 120 kJ mol(-1), and the material also maintains robust cyclability and stability. Our results demonstrate that solar thermal fuels composed of molecule-nanostructure hybrids can exhibit significantly enhanced energy-storage capabilities through the generation of template-enforced steric strain.

  17. Contributions to optimization of storage and transporting industrial goods

    Science.gov (United States)

    Babanatsas, T.; Babanatis Merce, R. M.; Glăvan, D. O.; Glăvan, A.

    2018-01-01

    Optimization of storage and transporting industrial goods in a factory either from a constructive, functional, or technological point of view is a determinant parameter in programming the manufacturing process, the performance of the whole process being determined by the correlation realized taking in consideration those two factors (optimization and programming the process). It is imperative to take into consideration each type of production program (range), to restrain as much as possible the area that we are using and to minimize the times of execution, all of these in order to satisfy the client’s needs, to try to classify them in order to be able to define a global software (with general rules) that is expected to fulfil each client’s needs.

  18. Online mass storage system detailed requirements document

    Science.gov (United States)

    1976-01-01

    The requirements for an online high density magnetic tape data storage system that can be implemented in a multipurpose, multihost environment is set forth. The objective of the mass storage system is to provide a facility for the compact storage of large quantities of data and to make this data accessible to computer systems with minimum operator handling. The results of a market survey and analysis of candidate vendor who presently market high density tape data storage systems are included.

  19. Evaluation and analysis method for natural gas hydrate storage and transportation processes

    International Nuclear Information System (INIS)

    Hao Wenfeng; Wang Jinqu; Fan Shuanshi; Hao Wenbin

    2008-01-01

    An evaluation and analysis method is presented to investigate an approach to scale-up a hydration reactor and to solve some economic problems by looking at the natural gas hydrate storage and transportation process as a whole. Experiments with the methane hydration process are used to evaluate the whole natural gas hydrate storage and transportation process. The specific contents and conclusions are as follows: first, batch stirring effects and load coefficients are studied in a semi-continuous stirred-tank reactor. Results indicate that batch stirring and appropriate load coefficients are effective in improving hydrate storage capacity. In the experiments, appropriate values for stirring velocity, stirring time and load coefficient were found to be 320 rpm, 30 min and 0.289, respectively. Second, throughput and energy consumption of the reactor for producing methane hydrates are calculated by mass and energy balance. Results show that throughput of this is 1.06 kg/d, with a product containing 12.4% methane gas. Energy consumption is 0.19 kJ, while methane hydrates containing 1 kJ heat are produced. Third, an energy consumption evaluation parameter is introduced to provide a single energy consumption evaluation rule for different hydration reactors. Parameter analyses indicate that process simplicity or process integration can decrease energy consumption. If experimental gas comes from a small-scale natural gas field and the energy consumption is 0.02 kJ when methane hydrates containing 1 kJ heat are produced, then the decrease is 87.9%. Moreover, the energy consumption evaluation parameter used as an economic criterion is converted into a process evaluation parameter. Analyses indicate that the process evaluation parameter is relevant to technology level and resource consumption for a system, which can make it applicable to economic analysis and venture forecasting for optimal capital utilization

  20. 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.