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Sample records for dismantling operations level

  1. Feedback from dismantling operations (level 2) on EDF's first generation reactors

    International Nuclear Information System (INIS)

    West, J P.; Dionisio-Gomes, A.; Kus, J P.; Mervaux, P.; Bernet, P.; Dalmas, R.

    2003-01-01

    EDF's policy as regards the dismantling of the reactors that have ceased commercial operation, namely the eight power plants of the first generation and the Creys-Malville power plant, is explained. Generally speaking, prior to the year 2001, EDF had opted for the de-construction of these power plants to comply with a 'long wait' scenario, which consisted of waiting for a period of 5 to 10 years to achieve IAEA level 2 (partial release of the site), then postponing the total de-construction of the facilities for 25 to 50 years. Today, EDF has decided to undertake the total de-construction of these reactors, which have ceased commercial operation, over a period of 25 years. The purpose of this document is to present: - The reactors concerned, their background and their 'regulatory' situation, - The main operations performed and/or currently in progress, - The main elements of feedback from such operations, shedding light on the approach adopted in 2001. The installations concerned by the de-construction programme are as follows: - The 8 power plants of the first generation, which were built during the fifties and sixties and ceased commercial operation between 1973 and 1994, namely: Brennilis (industrial prototype using heavy water technology, jointly operated by EDF and CEA), the 6 power units of the NUGG type (natural uranium gas graphite) at Chinon, Saint-Laurent des Eaux and Bugey and the PWR reactor at Chooz A, - The storage silos at Saint-Laurent, where the sleeves for the fuel assemblies of reactors SLA1 and SLA2 are stored, corresponding to approximately 2000 tonnes of graphite, - The Creys-Malville reactor, FBR (fast breeder reactor) shut down in accordance with a government decision, which is currently undergoing decommissioning. At the current stage, our feedback from the dismantling operations carried out on nuclear facilities is based on (i) the work carried out or in progress that will make it possible to achieve the equivalent of IAEA level 2 in the

  2. Long-term management of wastes resulting from dismantling operations. Storing the very low-level activity wastes at Morvilliers

    International Nuclear Information System (INIS)

    Duret, F.; Dutzer, M.; Beranger, V.; Lecoq, P.

    2003-01-01

    Extension of dismantling operations in France in the years to come poses the question of availability of long-term waste facility. Large amount of such wastes will be produced after progressive shutdown of the 58 pressurized water reactors now in operation, not before 2010. However, France is already confronted with dismantling of 9 power reactors (6 of which of gas cooled graphite type), the first reprocessing plant at Marcoule, as well as, dismantling of other installations, for instance the CEA reactors or laboratories. The systems of processing the dismantling waste are not different from those used for wastes resulting from nuclear operations. For the high-level or long-term intermediate level activity disposal the debates must start by 2006, as based on the results of the research conducted according to different provisions of the December 30, 1991 law. These wastes represent however small amounts from the dismantling (around 2000 t for the 9 reactors at shutdown) and they will be stored until a decision will be made. A specific storing system should be implemented by 2008-2010 for the graphite wastes (around 23,000 t) which contain significant amount of long-lived radioelements, although their gross activity is low. But the most significant amount will come from low-level or intermediate-level of short lifetime or from wastes of very low activity. The first category is stored at Storage Center at Aube (CSA), its capacity being of 1,000,000 m 3 of drums. The total volume stored by the end of 2002 amounted 136,500 m 3 with an annual delivering of 12-15,000 m 3 at design rate of 30,000 m 3 /y. This center will be able to absorb the flux increase resulting from dismantling of the decommissioned nuclear installations (around 50,000 t from the dismantling of the 9 power reactor). The Center at Aube can be also adapted for storing wastes of large sizes as for instance the lid of the reactor vessel. According to the French regulation, the wastes produced within a

  3. Temperature buffer test. Dismantling operation

    Energy Technology Data Exchange (ETDEWEB)

    Aakesson, Mattias [Clay Technology AB, Lund (Sweden)

    2010-12-15

    The Temperature Buffer Test (TBT) is a joint project between SKB/ANDRA and supported by ENRESA (modelling) and DBE (instrumentation), which aims at improving the understanding and to model the thermo-hydro-mechanical behavior of buffers made of swelling clay submitted to high temperatures (over 100 deg C) during the water saturation process. The test has been carried out in a KBS-3 deposition hole at Aespoe HRL. It was installed during the spring of 2003. Two heaters (3 m long, 0.6 m diameter) and two buffer arrangements have been investigated: the lower heater was surrounded by bentonite in the usual way, whereas the upper heater was surrounded by a ring of sand. The test was dismantled and sampled during a period from the end of October 2009 to the end of April 2010, and this report describes this operation. Different types of samples have been obtained during this operation. A large number of diameter 50 mm bentonite cores have been taken for analysis of water content and density. Large pieces, so-called big sectors, have been taken for hydro-mechanical and chemical characterizations. Finally, there has been an interest to obtain different types of interface samples in which bentonite were in contact with sand, iron or concrete. One goal has been to investigate the retrievability of the upper heater, given the possibility to remove the surrounding sand shield, and a retrieval test has therefore been performed. The sand in the shield was first removed with an industrial vacuum cleaner after loosening the material through mechanical means (with hammer drill and core machine). A front loader was subsequently used for applying a sufficient lifting force to release the heater from the bentonite underneath. The experiment has been documented in different aspects: measurements of the coordinate (height or radius) of different interfaces (between bentonite blocks and between bentonite and sand); verification of sensor positions and retrieval of sensors for subsequent

  4. Temperature buffer test. Dismantling operation

    International Nuclear Information System (INIS)

    Aakesson, Mattias

    2010-12-01

    The Temperature Buffer Test (TBT) is a joint project between SKB/ANDRA and supported by ENRESA (modelling) and DBE (instrumentation), which aims at improving the understanding and to model the thermo-hydro-mechanical behavior of buffers made of swelling clay submitted to high temperatures (over 100 deg C) during the water saturation process. The test has been carried out in a KBS-3 deposition hole at Aespoe HRL. It was installed during the spring of 2003. Two heaters (3 m long, 0.6 m diameter) and two buffer arrangements have been investigated: the lower heater was surrounded by bentonite in the usual way, whereas the upper heater was surrounded by a ring of sand. The test was dismantled and sampled during a period from the end of October 2009 to the end of April 2010, and this report describes this operation. Different types of samples have been obtained during this operation. A large number of diameter 50 mm bentonite cores have been taken for analysis of water content and density. Large pieces, so-called big sectors, have been taken for hydro-mechanical and chemical characterizations. Finally, there has been an interest to obtain different types of interface samples in which bentonite were in contact with sand, iron or concrete. One goal has been to investigate the retrievability of the upper heater, given the possibility to remove the surrounding sand shield, and a retrieval test has therefore been performed. The sand in the shield was first removed with an industrial vacuum cleaner after loosening the material through mechanical means (with hammer drill and core machine). A front loader was subsequently used for applying a sufficient lifting force to release the heater from the bentonite underneath. The experiment has been documented in different aspects: measurements of the coordinate (height or radius) of different interfaces (between bentonite blocks and between bentonite and sand); verification of sensor positions and retrieval of sensors for subsequent

  5. Consideration of dismantling operations in the design

    International Nuclear Information System (INIS)

    Dubourg; Bonin.

    1984-12-01

    This analysis shows that the parameters and the constraints taken into account at the design level to facilitate the exploitation and the maintenance make the dismantling and its preparation easier [fr

  6. Remote tool development for nuclear dismantling operations

    International Nuclear Information System (INIS)

    Craig, G.; Ferlay, J.C.; Ieracitano, F.

    2003-01-01

    Remote tool systems to undertake nuclear dismantling operations require careful design and development not only to perform their given duty but to perform it safely within the constraints imposed by harsh environmental conditions. Framatome ANP NUCLEAR SERVICES has for a long time developed and qualified equipment to undertake specific maintenance operations of nuclear reactors. The tool development methodology from this activity has since been adapted to resolve some very challenging reactor dismantling operations which are demonstrated in this paper. Each nuclear decommissioning project is a unique case, technical characterisation data is generally incomplete. The development of the dismantling methodology and associated equipment is by and large an iterative process combining design and simulation with feasibility and validation testing. The first stage of the development process involves feasibility testing of industrial tools and examining adaptations necessary to control and deploy the tool remotely with respect to the chosen methodology and environmental constraints. This results in a prototype tool and deployment system to validate the basic process. The second stage involves detailed design which integrates any remaining technical and environmental constraints. At the end of this stage, tools and deployment systems, operators and operating procedures are qualified on full scale mock ups. (authors)

  7. Nuclear cleanup and decontamination for dismantling operations

    International Nuclear Information System (INIS)

    Bargues, S.; Solignac, Y.; Lapierre, Y.

    2003-01-01

    In the May 2003 issue of the review 'Controle', the French Nuclear Safety Authority (Autorite de Surete Nucleaire or ASN) reviewed the radiation protection and waste management principles applicable to dismantling operations carried out on nuclear installations, i.e. reactors, research laboratories, fuel cycle installations and nuclear power reactors. Estelle Chapelain, of the DGSNR (French General Directorate for Nuclear Safety and Radiation Protection), pointed out that dismantling work does not involve the same radioactive risks as operating an installation. For instance, 'the risk of disseminating radioactive material is generally greater because the dismantling process supposes the removal of one or more containment barriers'. In addition to this risk of internal exposure, the possibility of external irradiation of personnel must be taken into account due to the nature of the work carried out by the operators. The probability of conventional hazards is also accentuated, these hazards varying as work progresses (fire hazards during cutting operations, hazards associated with handling tasks, etc). Other risks must also be considered: hazards due to the ageing of installations, to loss of traceability, and finally the risks associated with waste management. Waste management falls within a strict regulatory framework specified by the decree dated December 31, 1999, which makes it compulsory to carry out a 'waste survey' with the aim of producing an inventory of waste and improving waste management. These surveys include 'waste zoning' to identify those areas liable to have been contaminated. These requirements lead operators to adapt their cleanup methodology in order to distinguish suspect rooms or equipment from those that can be deemed with certainty to be conventional. In its conclusion, the safety authority recalls the importance of 'the safety and radiation protection of dismantling operations being effectively managed and optimised, without imposing

  8. Simulation for preparation of dismantling operations

    International Nuclear Information System (INIS)

    Carrere, J.M.; Idasiak, J.M.

    2003-01-01

    New applications of 3D models are still emerging. At first, simulation of dismantling operations has been used to illustrate the proposed scenarios, with 3D views or animated films, for: - internal and external communication; - technical reviews; - presentation to Safety Authorities. It helps a lot to explain the structure of the facility to dismantle, the proposed solutions, to convince people that the study is detailed enough. But 3D modelling is an investment in time and money. A lot of time is spent in collecting the drawings, and checking them with pictures, videos, interviews of operators, new measurements. This investment can be much more exploited, during all the life time of the decommissioning project, to avoid problems during operations, and so to save a lot of money. It is possible to have navigation or even immersion inside 3D models of facilities to dismantle, so that the project team or the operators can be familiar with the configuration of rooms, of accesses, with the location of equipment. A 3D model can hardly be as detailed as the real facility. Some simplifications have to be done, to avoid having too heavy models. But in a training process, 3D-models help to have rapidly an overview of complex environments. Dose uptake simulation is becoming also a tool for decommissioning projects. It is possible to compute either off line, or even in real time, the dose uptake of the operators, and to compare easily different options for the ALARA principle: decontamination or not, use of shielding or not. It requires to have not only the geometrical model, but also a radiological model of the facility, but with the use of gamma camera and spectrometry, it becomes easier. 3D-models can be used to integrate in an user-friendly way all the knowledge of a facility to decommission, and to update that knowledge during operations: reports on construction, on exploitation, on shut-down, physical and radiological measurements, traceability of wastes. Progress are

  9. Importance of low-level radioactive wastes in dismantling strategy in CEA (FRANCE)

    International Nuclear Information System (INIS)

    Lafaille, C.

    1991-01-01

    This paper describes the advance used in C.E.A. to realize dismantling operations in the best technical and economical conditions. Particularly, for low-level radioactive waste management CEA's advance defines, first, the final destination of dismantling materials: - recycling in public lands for level activity inferior to 1 Bq/g; directly or after transformation (melting, calcination, extrusion) - storage in a ground disposal, after compacting, encapsulation or drumming. Two examples are given: - Marcoule G2 - G3 reactor dismantling - Gaseous diffusion plants demolition (COGEMA Pierrelatte)

  10. Dismantling of a hot cell of high level activity. Method and tools used

    International Nuclear Information System (INIS)

    Jeantet, E.; Miquel, P.; Baudoin, J.C.; Moutonnet, A.

    1981-05-01

    The aim of this operation is the removal of all the equipment and the material introduced and used in the hot cell 'Attila' and its decontamination to obtain an irradiation level as low as possible to allow direct intervention. The Attila facilitie was build in 1964-1966 to study dry processing of irradiated fuels by halogenide volatility process. Dismantling of the out-cell and of the laboratory associated to the shielded cell, dismantling inside the shielded cell with the remote handling equipment of the cell and tools used for these operations are described in this article [fr

  11. Vandellos 1 NPP. Dismantling at the level 1

    International Nuclear Information System (INIS)

    Pla, E.; Perez Pallares, J.

    1998-01-01

    Because of the fire in a main turbogenerator in October 1989, the Spanish Ministry of Industry ordered the definitive shutdown of Vandellos 1 NPP. The tasks allowed to the owner in the Ministerial Order were: the reactor defueling, the operation radwaste conditioning. The size of the reactor core needed to prepare an adequate defueling plan in order to prevent the potential reactivity oscillations and ensure the refrigeration of the nuclear fuel remaining in the core. The operation radwastes were divided in four types, according to the conditioning method: the low level solid radwaste, the irradiated metallic materials, the resins and zeolites used for decontaminating the liquid effluents, the radwaste stored in three graphite silos. The low level solid radwastes were stored during operation in drums of 220 litres. Recently they were compacted at a pressure of 40 tones before to be shipped to en ENRESA disposal. The irradiated metallic materials are, essentially, some parts of the refuelling machine. For deactivating the liquid effluents, Vandellos 1 used both organic resins and zeolites. The presence of zeolites helps the cementation, but its rough surface makes difficult to flow in the pipes of the cementation plant. 35 m 3 of this mixture have been conditioned into 670 drums of 220 liters. Vandellos 1 has three silos designed to store the graphite sleeves (reactor fuel support). In the silo number 1 some other radwastes were stored, as low level solid radwastes and two fuel elements. An international request for tenders was made in order to undertake the extraction and conditioning all these radwastes. The project was awarded to the Spanish/French Consortium EQUIPOS NUCLEARES-FRAMATOME. The achievement of the graphite silos project needed to design specific devices for separating irradiated wires from graphite, and searching and extracting two fuel elements jumbled up with the graphite sleeves. The spent fuel ponds have been emptied and its internals confined

  12. Achievements and prospects of robotics in dismantling operations

    International Nuclear Information System (INIS)

    Clement, G.; Goetghebeur, S.; Ravera, J.P.

    1993-01-01

    After a definition of 'robotic systems' (poly functionality is the main concept), the nuclear facilities that have used robotic systems for their dismantling are reviewed; the various robot intervention domains in dismantling, the different types of machines and the work carried out by robots are presented. Difficulties arising from robot utilization for reactor dismantling, robot design considerations, reliability, personnel training needs, tooling and costs are discussed. Applicability criteria are derived concerning radio protection, hard working conditions, task complexity, multiplicity and quality, and costs

  13. Taking into account dismantling and decommissioning waste management in conception and operation phases

    International Nuclear Information System (INIS)

    Poncet, Philippe

    2016-01-01

    Managing waste during the Dismantling and Decommissioning (D and D) phase is quite specific and different from what it was during the operation phase. Indeed, waste generated during dismantling could present some analogy especially with regards to the radionuclides spectrum and contents. However waste from dismantling and cleanup could actually presents a lower level of radiologic activity but produced in much larger quantities, which requires new solutions. Moreover the characteristics and quantities of waste to be managed during D and D are highly depending on the way the facility was designed and also how it was actually operated during its life time. Taking future D and D into consideration in the early design as well as during the operation of new facilities is becoming more and more mandatory. It is now an explicit requirement set by safety authorities, to provide - in the license application for news plants - a description of design provisions and future plans for D and D as well as anticipated technical and financial impacts,. Two major aspects are driving the cost and complexity of future D and D operations: waste volumes by categories and occupational exposure while performing the work. To reduce such impacts, key approaches are to maintain areas clean, segregate the waste types and provide appropriate provisions in the design. The paper's first part describes the related design and operation concepts derived from lessons learned, and illustrations by examples are presented in a second part. (author)

  14. Rosie: A mobile worksystem for decontamination and dismantlement operations

    International Nuclear Information System (INIS)

    Thompson, B.R.; Conley, L.

    1996-01-01

    RedZone Robotics, Inc. and Carnegie Mellon University's Field Robotics Center have undertaken a contract to develop a next-generation worksystem for decommissioning and dismantlement tasks in Department of Energy (DOE) facilities. Currently, the authors are closing the second phase of this three phase effort and have completed the design and fabrication of the worksystem: Rosie. Rosie includes a locomotor, heavy manipulator, control center, and control system for robot operation. The locomotor is an omni-directional platform with tether management and hydraulic power capabilities. The heavy manipulator is a high-payload, long-reach system intended to deploy tools into the work area. The heavy manipulator is capable of deploying systems such as the Dual-Arm Work Module--a five degree-of-freedom platform supporting two highly dexterous manipulators--or a single manipulator for performing simpler, less dexterous tasks. Rosie is telerobotic to the point of having servo-controlled motions which can be operated and coordinated through the control center

  15. Rosie: A mobile workstation for decontamination and dismantlement operations

    International Nuclear Information System (INIS)

    1994-01-01

    RedZone Robotics, Inc. and Carnegie Mellon University's Field Robotics Center have undertaken a contract to develop a next-generation worksystem for decommissioning and dismantlement tasks in Department of Energy (DOE) facilities. Currently, the authors are in the second phase of this three phase effort and are completing the design of the worksystem. Within this project RedZone is designing and fabricating a worksystem: Rosie. Rosie will include a locomotor, heavy manipulator, control center, and control system for robot operation. The locomotor is an omni-directional platform with tether management and hydraulic power capabilities. The heavy manipulator is a high-payload, long-reach system to deploy tools into the work area. The heavy manipulator will be capable of deploying systems such as the Dual-Arm Work Module--a five degree-of-freedom platform supporting two highly dexterous manipulators--or a single manipulator for performing simpler, less dexterous tasks. Rosie will be telerobotic to the point of having servo-controlled motions which can be operated and coordinated through the control center. This report describes the design of the systems. In phase three Rosie will be radiation-hardened and perform a demonstration in a contaminated facility

  16. NucLab Marcoule. A laboratory facility dedicated to support dismantling operations

    International Nuclear Information System (INIS)

    Dugne, O.; Houssin, A.; Pierre, D.; Bec-Espitalier, L.

    2013-06-01

    Formerly dedicated to plutonium production support, NucLab was renovated to perform a wide range of analyses for dismantling, plant operation and process development activities mainly on Marcoule site but also outside (Veurey, Fontenay aux Roses). The Laboratory is under a CEA AREVA partnership as a CEA entity operated by AREVA employees. It provides services to several industrial operators (nuclear process and power plant) in the fields of analytical chemistry, radioactivity measurements, in situ nuclear measurements, decontamination processes and industrial chemistry processes, waste treatments to meet the following analysis requirements. NucLab today is able to support research, production and dismantling activities in all part of dismantling operations. (authors)

  17. Dismantling of Radium-226 Coal Level Gauges: Encountered Problems and How to Solve

    International Nuclear Information System (INIS)

    Punnachaiya, M.; Nuanjan, P.; Moombansao, K.; Sawangsri, T.; Pruantonsai, P.; Srichom, K.

    2006-01-01

    This paper describes the techniques for dismantling of disused-sealed Radium-226 (Ra-226) coal level gauges which the source specifications and documents were not available, including problems occurred during dismantling stage and the decision making in solving all those obstacles. The 2 mCi (20 pieces), 6 mCi (20 pieces) and 6.6 mCi (30 pieces) of Ra-226 hemi-spherically-shaped with lead-filled coal level gauges were used in industrial applications for electric power generation. All sources needed to be dismantled for further conditioning as requested by the International Atomic Energy Agency (IAEA). One of the 2 mCi Ra-226 source was dismantled under the supervision of IAEA expert. Before conditioning period, each of the 6 mCi and 6.6 mCi sources were dismantled and inspected. It was found that coal level gauges had two different source types: the sealed cylindrical source (diameter 2 cm x 2 cm length) locked with spring in lead housing for 2 mCi and 6.6 mCi; while the 6 mCi was an embedded capsule inside source holder stud assembly in lead-filled housing. Dismantling Ra-226 coal level gauges comprised of 6 operational steps: confirmation of the surface dose rate on each source activity, calculation of working time within the effective occupational dose limit, cutting the weld of lead container by electrical blade, confirmation of the Ra-226 embedded capsule size using radiation scanning technique and gamma radiography, automatic sawing of the source holder stud assembly, and transferring the source to store in lead safe box. The embedded length of 6 mCi Ra-226 capsule in its diameter 2 cm x 14.7 cm length stud assembly was identified, the results from scanning technique and radiographic film revealed the embedded source length of about 2 cm, therefore all the 6 mCi sources were safely cut at 3 cm using the automatic saw. Another occurring problem was one of the 6.6 mCi spring type source stuck inside its housing because the spring was deformed and there was

  18. The challenges of dismantling

    International Nuclear Information System (INIS)

    Sene, Monique; Lheureux, Yves; Leroyer, Veronique; Rollinger, Francois; Gauthier, Florence; Depauw, Denis; Reynal, Nathalie; Fraysse, Thierry; Burger, Eric; Bertrand, Adrien; Vallat, Christophe; Bernet, Philippe; Eimer, Michel; Boutin, Dominique; Bietrix, Philippe; Richard, Francoise; Piketty, Laurence; Mouchet, Chantal; Charre, Jean-Pierre

    2014-01-01

    This document gathers Power Point presentations which address the contexts and challenges of dismantling (legal framework, safety and radiation protection challenges, waste processing industry), and propose illustrations of dismantling challenges (example of operations to prepare EURODIF dismantling and CLIGEET work-group on EURODIF dismantling, examples of dismantling of EDF installations and CLIs' opinion on the dismantling of EDF installations, Brennilis dismantling follow-up performed by the CLI, examples of dismantling of CEA installations and opinion of a CLI on the dismantling of CEA installations)

  19. Challenges of dismantling

    International Nuclear Information System (INIS)

    Chevet, P.F.; Schilz, F.; Rondeau, J.M.; Piketty, L.; Dupraz, B.; Conte, D.; Duguey, M.; Louet, C.A.; Dorison, A.; Dutzer, M.; Boucau, J.; Eimer, M.; Boutin, D.; Revilla, J.L.; Golshan, M.; Smith, G.

    2015-01-01

    This document is made up of short articles whose issue is reactor dismantling. The first article presents the French strategy that can be featured by immediate dismantling (the dismantling process is prepared a long time before decommissioning and begins as soon as the reactor is shut down) and massive dismantling (a lot of nuclear facilities will be decommissioned in a near future). The following 4 articles give the viewpoints of ASN (Nuclear Safety Authority), EDF (for its fleet of PWRs), CEA (for its experimental reactors and nuclear facilities) and AREVA (for the EURODIF George Besse plant). Costs and financing are dealt with in an article that says that the cost is greatly dependent on the final state: a complete nuclear-free area or an area whose radioactivity is below safe standards and that law implies to constitute provisions all along the operating life of the facility to cover dismantling costs. Dismantling generates a huge amount of very low-level radioactive wastes particularly metal scraps that might be recycled and get out of nuclear industry, an article details the feasibility of such recycling. Another article shows the impact of massive dismantling on the management of radioactive wastes. In an article Westinghouse presents its experience in the cutting of internal equipment of the reactor core. The last 2 articles presents the dismantling strategies in Spain and in the UK. (A.C.)

  20. National School of Dismantling

    International Nuclear Information System (INIS)

    Ivaldi, Fabienne

    2003-01-01

    The National Institut of Nuclear Sciences and Techniques founded of 2001 a National School of Dismantling, NSD, at the end, which was validated by CEA, COGEMA, EDF and ANDRA. This school addresses four major issues: Decontamination; Dismantling; Demolition and waste Disposal (4D). Dedicated for instructing scientific and technical knowledge and know-how, needed in dismantling the nuclear installations, NSD has as targets: - personnel at engineering and operational level; - personnel occupied with involved trades from conception through intervention; - students and employees on leave; - employees while training on the job. Initial basic education for students in collaboration with schools and universities concerns: - master degree in radioactive waste management; - master degree in dismantling; - professional license in 3 D; - pro 4 D graduation. NSD is also engaged in continual formation for employees qualified, or not, adapted to the needs generated by the following tasks and personnel: - introduction in dismantling; - project team; - specialist engineer; - team head; - agent for remedial action; - agent for dismantling. The National School of Dismantling joins a network of human and technological capabilities confined within the 4 D frame, namely: - scientific and technical competencies (experts, instructors working in the nuclear field and dismantling); - pedagogical competence (professionals from basic and continual education); - specific material means such as those used by construction site schools, mock-ups, rooms for practical training etc

  1. Drafting of the dismantling operations of the MAR 200 workshop with the help of virtual reality

    International Nuclear Information System (INIS)

    Chabal, C.; Soulabaille, Y.; Garnier, T.; Callixte, O.

    2014-01-01

    In order to optimize future dismantling operations of nuclear installations virtual reality allows the validation of predefined scenarios and their adequacy with the environment. CEA uses an immersion and interactive room to validate maintenance and dismantling operations. The equipment of this room is composed of a video wall that gives a 3-dimensional view of the virtual environment, and of a system for motion capture. For the simulation of handling operations a haptic interface has been designed, it allows the user to receive a tactic and effort-feeling feed back. The immersion is completed by a phonic ambience that creates sounds for virtual operations. The use of the immersion room for optimizing the dismantling of a spent fuel dissolver (MAR 200) used in hot cell is presented. (A.C.)

  2. Remote dismantlement tasks for the CP5 reactor: Implementation, operations, and lessons learned

    International Nuclear Information System (INIS)

    Noakes, M.W.

    1998-01-01

    This paper presents a developer's perspective on lessons learned from one example of the integration of new prototype technology into a traditional operations environment. The dual arm work module was developed by the Robotics Technology Development Program as a research and development activity to examine manipulator controller modes and deployment options. It was later reconfigured for the dismantlement of the Argonne National Laboratory Chicago Pile number-sign 5 reactor vessel as the crane-deployed dual arm work platform. Development staff worked along side operations staff during a significant part of the deployment to provide training, maintenance, and tooling support. Operations staff completed all actual remote dismantlement tasks. At the end of available development support funding, the Dual Arm Work Platform was turned over to the operations staff, who is still using it to complete their dismantlement tasks

  3. Manually-Operated Crate Dismantlement System for Los Alamos National Laboratory

    International Nuclear Information System (INIS)

    Laffitte, John; Lagos, Leo; Morales, Miguel

    2002-01-01

    Los Alamos National Laboratory currently possesses between 500 and 800 fiberglass-reinforced plywood crates that contain hazardous materials that need to be decontaminated. To access the hazardous material, a system is needed to dismantle the crate. Currently, crates are dismantled by workers using hand-held tools. This technique has numerous disadvantages. One disadvantage is that it is difficult for a worker to hold the tool for an extended period of time in the awkward angles and positions necessary to fully size-reduce the crate. Other disadvantages of using hand tools include managing power cords and vacuum hoses, which become entangled or can act as tripping hazards. In order to improve the crate opening and size-reduction task, Florida International University's Hemispheric Center for Environmental Technology (HCET) is developing a manually operated crate dismantlement system. This versatile system is expected to greatly increase worker efficiency while decreasing fatigue and the possibility of accidents. (authors)

  4. U P1, an example for advanced techniques applied to high level activity dismantling

    International Nuclear Information System (INIS)

    Michel-Noel, M.; Calixte, O.; Blanchard, S.; Bani, J.; Girones, P.; Moitrier, C.; Terry, G.; Bourdy, R.

    2014-01-01

    The U P1 plant on the CEA Marcoule site was dedicated to the processing of spend fuels from the G1, G2 and G3 plutonium-producing reactors. This plant represents 20.000 m 2 of workshops housing about 1000 hot cells. In 1998, a huge program for the dismantling and cleaning-up of the UP1 plant was launched. CEA has developed new techniques to face the complexity of the dismantling operations. These techniques include immersive virtual reality, laser cutting, a specific manipulator arm called MAESTRO and remote handling. (A.C.)

  5. EDF's dismantling experience

    International Nuclear Information System (INIS)

    Mira, J.J.

    1993-01-01

    The dismantling policy at EDF, taking into account technical, economical and socio-political factors, is presented. The various current realizations are reviewed and their dismantling solution discussed: Chinon A2, Chinon A1, Marcoule G1, G2, G3, Brennilis (EL4). Several dismantling projects are also described (Chinon A3, St-Laurent A1-A2, Chooz A). The various dismantling operations are presented and scheduled

  6. Some regulation aspects in dismantling

    International Nuclear Information System (INIS)

    Niel, J.C.

    1993-01-01

    In the French regulation framework, operations linked to dismantling are controlled by an overall technical and legislative system applied to all the different stages of the facility (commissioning, etc.). Government control on facilities under dismantling is aimed at dismantling operation safety and security, and dismantling waste processing in order to ensure public and environmental protection

  7. The Japan Power Demonstration Reactor (JPDR) dismantling activities. Management of JPDR dismantling waste

    International Nuclear Information System (INIS)

    Abe, Masayoshi; Nakata, Susumu; Ito, Shinichi

    1996-01-01

    The management of wastes, both radioactive and non-radioactive, is one of the most important issues for a safe and reasonable dismantling operation of nuclear power plants. A large amount of radioactive wastes is arising from a reactor dismantling operation in a relatively short period time, ranging in a wide variety from very low level to relatively high level. Moreover non-radioactive waste is also in a huge amount. The dismantling operation of Japan Power Demonstration Reactor (JPDR) resulted in 24,440 tons of dismantling wastes, of which about 15% was radioactive and 85% non-radioactive. These wastes were managed successfully implementing a well developed management plan for JPDR dismantling waste. Research and development works for handling of JPDR dismantling wastes were performed, including fixation of loose contamination on surface, volume reduction and waste containers for on-site transportation and interim storage. The JPDR dismantling wastes generated were classified and categorized depending on their materials, characteristics and activity level. Approximately 2,100 tons of radioactive wastes were stored in the interim storage facilities on site using developed containers, and 1,670 tons of radioactive concrete waste were used for a safe demonstration test of a simple near-surface disposal for very low level waste. Other dismantling wastes such as steel and concrete which were categorized as non-radioactive were recycled and reused as useful resources. This paper describes the management of the JPDR dismantling wastes. (author)

  8. Characterization and impact of incandescent particles in the ventilation networks during dismantling operations

    International Nuclear Information System (INIS)

    Marchal, Pierre

    2014-01-01

    Fire hazards while metal cutting on dismantling operations led IRSN to focus a study on incandescent particles emitted by these cutting tools and their impact on air filter. If micronic particles (≤ 10 μm) have been studied for their negative impact on human health, few studies are dealing with incandescent particles, despite their strong thermal energy. These particles are mainly made of iron, coming from the metal cutting, and the exothermic oxidation reaction coupled to a high temperature emission causes them to molt. An experimental system was designed, representative of dismantling operations with instrumentations adapted for in-flight particles measurement, such as size, velocity and temperature. The particles are characterized from the emission source (automated cut-off grinder) and all along their path into the ventilation duct to their impact on a filter. An analytical approach of the impact of these particles on the filter shows that the temperature of the particles, greater than 430 C damages the filter medium, and may reduce the filter thickness or perforate it, which leads to a decrease of its filtration efficiency determined according to the French standard. Comparison between the characteristics of the particles and the filtration efficiency has permitted to establish empirical correlations in order to predict the loss of filtration efficiency versus the cutting parameters and some good practices have been proposed to protect the filter. (author)

  9. CP-5 reactor remote dismantlement activities: Lessons learned in the integration of new technology in an operations environment

    International Nuclear Information System (INIS)

    Noakes, M.W.

    1998-01-01

    This paper presents the developer's perspective on lessons learned from one example of the integration of new prototype technology into a traditional operations environment. The dual arm work module was developed by the Robotics Technology Development Program as a research and development activity to examine manipulator controller modes and deployment options. It was later reconfigured for the dismantlement of the Argonne National Laboratory Chicago Pile No. 5 reactor vessel as the crane-deployed dual arm work platform. Development staff worked along side operations staff during a significant part of the deployment to provide training, maintenance, and tooling support. Operations staff completed all actual remote dismantlement tasks. At the end of available development support funding, the Dual Arm Work Platform was turned over to the operations staff, who are still using it to complete their dismantlement tasks

  10. Dismantling of nuclear facilities

    International Nuclear Information System (INIS)

    Tallec, M.; Kus, J.P.

    2009-01-01

    Nuclear facilities have a long estimable lifetime but necessarily limited in time. At the end of their operation period, basic nuclear installations are the object of cleansing operations and transformations that will lead to their definitive decommissioning and then to their dismantling. Because each facility is somewhere unique, cleansing and dismantling require specific techniques. The dismantlement consists in the disassembly and disposing off of big equipments, in the elimination of radioactivity in all rooms of the facility, in the demolition of buildings and eventually in the reconversion of all or part of the facility. This article describes these different steps: 1 - dismantling strategy: main de-construction guidelines, expected final state; 2 - industries and sites: cleansing and dismantling at the CEA, EDF's sites under de-construction; 3 - de-construction: main steps, definitive shutdown, preparation of dismantling, electromechanical dismantling, cleansing/decommissioning, demolition, dismantling taken into account at the design stage, management of polluted soils; 4 - waste management: dismantlement wastes, national policy of radioactive waste management, management of dismantlement wastes; 5 - mastery of risks: risk analysis, conformability of risk management with reference documents, main risks encountered at de-construction works; 6 - regulatory procedures; 7 - international overview; 8 - conclusion. (J.S.)

  11. The dismantling of nuclear installations

    International Nuclear Information System (INIS)

    Lacoste, A.C.; Duthe, M.; Mignon, H.; Lambert, F.; Pradel, Ph.; Hillewaere, J.P.; Dupre la Tour, St.; Mandil, C.; Weil, L.; Eickelpasch, N.; Finsterwalder, L.

    1997-01-01

    for nuclear installations, the dismantling is an important part of their exploitation. The technology of dismantling is existing and to get a benefit from the radioactive decay, it seems more easy for operating company such E.D.F. to wait for fifty years before dismantling. But in order to get the knowledge of this operation, the Safety Authority wanted to devote this issue of 'Controle'to the dismantling method. This issue includes: the legal aspects, the risks assessment, the dismantling policy at E.D.F., the site of Brennilis (first French experience of dismantling), the dismantling techniques, the first dismantling of a fuel reprocessing plant, comparison with classical installations, economic aspect, some German experiences, the cleansing of the american site of Handford. (N.C.)

  12. General Research and Development problems in dismantling

    International Nuclear Information System (INIS)

    Lorin, C.

    1993-01-01

    R and D studies for dismantling nuclear facilities have been conducted in several domains: safety evaluation (3D cameras, gamma camera, gamma low level control bench, alpha measures); general studies (such as the Baladin software, an expert system for dismantling); decontamination techniques (utilisation of acid or base liquids, laser, ...); cutting techniques and tools (remote controlled grinder, remote controlled robot, carrier crane); robotics for remote operations and handling; waste processing

  13. Study on safety evaluation for unrestricted recycling criteria of radioactive waste from dismantling operation

    International Nuclear Information System (INIS)

    Yoshimori, Michiro; Ohkoshi, Minoru; Abe, Masayoshi

    1995-01-01

    The study on safety evaluation was done, under contracting with the Science and Technology Agency, for recycling scrap metal arising from dismantling of reactor facilities. An object of this study is to contribute to the examination of establishing criteria and safety regulation for unrestricted recycling steel scrap. To define amount of market flow of iron material in Japan and the amount of radioactive waste generated from dismantling of reactor facilities, investigation had been carried out. On basis of these investigation results and data in several literature, individual doses to workers and to the members of the public have been calculated as well as collective doses. (author)

  14. The dismantling of CEA nuclear installations

    International Nuclear Information System (INIS)

    Piketty, Laurence

    2016-03-01

    After having indicated locations of French nuclear installations which are currently being dismantled (about 30 installations), and recalled the different categories of radioactive wastes with respect to their activity level and the associated storage options, this article gives an overview of various aspects of dismantling, more precisely in the case of installations owned and managed by the CEA. These operations comprise the dismantling itself, the recovery and packaging of wastes, old effluents and spent fuels. The organisation and responsible departments within the CEA are presented, and the author outlines some operational problematic issues met due to the age of installations (traceability of activities, regulation evolutions). The issue of financing is then discussed, and its uncertainties are outlined. The dismantling strategy within the CEA-DEN is described, with reference to legal and regulatory frameworks. The next parts of the article address the organisation and the economic impact of these decontamination and dismantling activities within the CEA-DEN, highlight how R and D and advanced technology are a support to this activities as R and D actions address all scientific and technical fields of nuclear decontamination and dismantling. An overview of three important dismantling works is proposed: Fontenay-aux-Roses, the Marcoule CEA centre (a reference centre in the field of nuclear dismantling and decontamination) and the Grenoble CEA centre (reconversion in R and D activities in the fields of technologies of information, of communication, technologies, for health, and in renewable energies). The last part addresses the participation to the Strategic Committee of the Nuclear Sector (CSFN)

  15. FEBEX-DP. Dismantling the ''full-scale engineered barrier experiment'' after 18 years of operation at the Grimsel Test Site, Switzerland

    Energy Technology Data Exchange (ETDEWEB)

    Kober, Florian; Gaus, Irina [Nagra, Wettingen (Switzerland)

    2015-07-01

    The FEBEX experiment at the Grimsel Test Site (GTS) consists of an in-situ full-scale engineered barrier system (EBS) test for the disposal of high-level waste (HLW). It is performed under natural conditions in crystalline rock in which the canisters are placed horizontally in drifts and are surrounded by a clay barrier constructed of highly compacted bentonite blocks. A partial dismantling and sampling of the EBS was carried out during 2002. Heating of the FEBEX started in 1997 and since then a constant temperature of 100 deg C has been maintained, while the bentonite buffer has been slowly hydrating in a natural way. A total of 632 sensors in the bentonite barrier, the rock mass, the heaters and the service zone record temperature, water saturation, humidity, total pressure, displacement, and water pressure. The hydration pattern is relatively symmetric, with no major differences along the axis. Although the host rock is characterized by heterogeneities with zones of higher permeability, the resaturation process is driven by the suction of the bentonite rather than by the availability of water in the rock, especially in the early phase. After 17 years, the water content in the buffer close to the heater still continues to increase slowly. The hydraulic pore pressures in the buffer and the geosphere have practically stabilized. The total pressure in general continues to increase in most points into the buffer, where in some parts pressures of over 6 MPa are registered. The long monitoring phase and the partial dismantling in 2002 indicate that the EBS has largely performed as expected and the major processes and couplings affecting the buffer saturation during the initial thermal period identified prior to the start of the experiment have been confirmed. A comprehensive report documents and reviews the state of the FEBEX (Lanyon and Gaus, 2013). After 18 years of operation the experiment will be excavated and dismantled in 2015. The main objectives of the FEBEX

  16. Dismantling techniques

    International Nuclear Information System (INIS)

    Wiese, E.

    1998-01-01

    Most of the dismantling techniques used in a Decontamination and Dismantlement (D and D) project are taken from conventional demolition practices. Some modifications to the techniques are made to limit exposure to the workers or to lessen the spread of contamination to the work area. When working on a D and D project, it is best to keep the dismantling techniques and tools as simple as possible. The workers will be more efficient and safer using techniques that are familiar to them. Prior experience with the technique or use of mock-ups is the best way to keep workers safe and to keep the project on schedule

  17. Dismantling techniques

    Energy Technology Data Exchange (ETDEWEB)

    Wiese, E.

    1998-03-13

    Most of the dismantling techniques used in a Decontamination and Dismantlement (D and D) project are taken from conventional demolition practices. Some modifications to the techniques are made to limit exposure to the workers or to lessen the spread of contamination to the work area. When working on a D and D project, it is best to keep the dismantling techniques and tools as simple as possible. The workers will be more efficient and safer using techniques that are familiar to them. Prior experience with the technique or use of mock-ups is the best way to keep workers safe and to keep the project on schedule.

  18. Machine for dismantling metal parts

    Energy Technology Data Exchange (ETDEWEB)

    Prokopov, O.I.; Loginovskiy, V.I.; Yagudin, S.Z.

    1982-01-01

    The purpose of the invention is to reduce the outlays of time for dismantling metal parts under conditions of eliminating open gas and oil gushers in operational drilling. This goal is achieved because the machine for dismantling the metal parts is equipped with a set of clamping elements arranged on the chassis, where each of them has a drive.

  19. Dismantlement and Radioactive Waste Management of DPRK Nuclear Facilities

    International Nuclear Information System (INIS)

    Jooho, W.; Baldwin, G.T.

    2005-01-01

    One critical aspect of any denuclearization of the Democratic People's Republic of Korea (DPRK) involves dismantlement of its nuclear facilities and management of their associated radioactive wastes. The decommissioning problem for its two principal operational plutonium facilities at Yongbyun, the 5MWe nuclear reactor and the Radiochemical Laboratory reprocessing facility, alone present a formidable challenge. Dismantling those facilities will create radioactive waste in addition to existing inventories of spent fuel and reprocessing wastes. Negotiations with the DPRK, such as the Six Party Talks, need to appreciate the enormous scale of the radioactive waste management problem resulting from dismantlement. The two operating plutonium facilities, along with their legacy wastes, will result in anywhere from 50 to 100 metric tons of uranium spent fuel, as much as 500,000 liters of liquid high-level waste, as well as miscellaneous high-level waste sources from the Radiochemical Laboratory. A substantial quantity of intermediate-level waste will result from disposing 600 metric tons of graphite from the reactor, an undetermined quantity of chemical decladding liquid waste from reprocessing, and hundreds of tons of contaminated concrete and metal from facility dismantlement. Various facilities for dismantlement, decontamination, waste treatment and packaging, and storage will be needed. The shipment of spent fuel and liquid high level waste out of the DPRK is also likely to be required. Nuclear facility dismantlement and radioactive waste management in the DPRK are all the more difficult because of nuclear nonproliferation constraints, including the call by the United States for 'complete, verifiable and irreversible dismantlement,' or 'CVID.' It is desirable to accomplish dismantlement quickly, but many aspects of the radioactive waste management cannot be achieved without careful assessment, planning and preparation, sustained commitment, and long completion times

  20. User Interface Technology to Reduce Mental Transformations for Tangible Remote Dismantling Simulator

    Energy Technology Data Exchange (ETDEWEB)

    Hyun, Dongjun; Kim, Ikjune; Lee, Jonghwan; Kim, Geun-Ho; Jeong, Kwan-Seong; Choi, Byung-Seon; Moon, Jeikwon; Choi, Jong-Won [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2015-10-15

    High-level radiation of the major components restricts access by human workers, and makes an accident or outage during the dismantling process more difficult to deal with. Since unexpected situations causes waste of budget and an aggravation of safety, the preliminary verification of the dismantling processes and equipment by the tangible remote dismantling simulator is very important. The design optimization of the dismantling processes and equipment is one of the most important objectives of the tangible remote dismantling simulator, as well. This paper proposes a user interface technology to reduce mental transformations for the tangible remote dismantling simulator. At the dismantling process simulation using the tangible remote dismantling simulator, the most difficult work is the remote operation handling the high degrees-of-freedom (DOF) manipulator due to complex mental transformations. The proposed user interface technology reduces mental transformations with constraints using the point projection and direction projection. The test result of the cutting process over the closure head of the RPV demonstrates that the proposed mental transformation reduction technology is operated successfully in the tangible remote dismantling simulator, and lets the operator be easy to control the high DOF manipulator even in the most difficult operation by reducing DOFs to be controlled manually.

  1. User Interface Technology to Reduce Mental Transformations for Tangible Remote Dismantling Simulator

    International Nuclear Information System (INIS)

    Hyun, Dongjun; Kim, Ikjune; Lee, Jonghwan; Kim, Geun-Ho; Jeong, Kwan-Seong; Choi, Byung-Seon; Moon, Jeikwon; Choi, Jong-Won

    2015-01-01

    High-level radiation of the major components restricts access by human workers, and makes an accident or outage during the dismantling process more difficult to deal with. Since unexpected situations causes waste of budget and an aggravation of safety, the preliminary verification of the dismantling processes and equipment by the tangible remote dismantling simulator is very important. The design optimization of the dismantling processes and equipment is one of the most important objectives of the tangible remote dismantling simulator, as well. This paper proposes a user interface technology to reduce mental transformations for the tangible remote dismantling simulator. At the dismantling process simulation using the tangible remote dismantling simulator, the most difficult work is the remote operation handling the high degrees-of-freedom (DOF) manipulator due to complex mental transformations. The proposed user interface technology reduces mental transformations with constraints using the point projection and direction projection. The test result of the cutting process over the closure head of the RPV demonstrates that the proposed mental transformation reduction technology is operated successfully in the tangible remote dismantling simulator, and lets the operator be easy to control the high DOF manipulator even in the most difficult operation by reducing DOFs to be controlled manually

  2. Dismantling of nuclear facilities

    International Nuclear Information System (INIS)

    Tallec, Michele; Kus, Jean-Pierre; Mogavero, Robert; Genelot, Gabriel

    2009-01-01

    Although the operational life of nuclear plants is long (around 60 years for French reactors) it is nonetheless limited in time, the stopping of it being essentially due to the obsolescence of materials and processes or to economic or safety considerations. The nuclear power plants are then subjected to cleanup and dismantling operations which have different objectives and require specific techniques. The cleanup and/or dismantling of a nuclear power produces significant quantities of waste which is generally of a different nature to that produced during the operation of the concerned plant. The radioactive waste produced by these operations is destined to be sent to the waste disposal facilities of the French National Agency for the Management of Nuclear Waste. (authors)

  3. LEP dismantling starts

    CERN Multimedia

    2000-01-01

    Since the end of November, various teams have been getting stuck into dismantling the LEP accelerator and its four experiments. After making the installations safe, the dismantling and removal of 40,000 tonnes of equipment is underway. Down in the tunnel, it is a solemn moment. It is 10 o'clock on 13 December and Daniel Regin, one of those heading the dismantling work, moves in on a magnet, armed with a hydraulic machine. Surrounded by teams gathered there for a course in dismantling, he makes the first cut into LEP. The great deconstruction has begun. In little over than a year, the accelerator will have been cleared away to make room for its successor, the LHC. The start of the operation goes back to 27 November. Because before setting about the machine with hydraulic shears and monkey wrenches, LEP had first to be made safe - it was important to make sure the machine could be taken apart without risk. All the SPS beam injection systems to LEP were cut off. The fluids used for cooling the magnets and superc...

  4. Decontamination and remote dismantling tests in the Itrec reprocessing plant

    International Nuclear Information System (INIS)

    Candelieri, T.; Gerardi, A.; Soffietto, G.

    1993-01-01

    The scope of this research is to evaluate the advantages of the rack removal system in the dismantling of reprocessing installations. The objective of this work is to verify experimentally the possibility of the decontamination of any particular module and the capability of the remote dismantling of components installed in the mobile rack. In particular, the main objective is to develop remotely operated equipment for the dismantling of centrifugal contactors. The decontamination of the equipment which represents the most important preliminary phase of the decommissioning operation, allowed to obtain low-level radioactivity. A supporting programme has been performed in order to collect sufficient data for the project and design of the remote dismantling machine. On the basis of technological cold test results, the project of the dismantling machine's construction has been optimized. Positive results obtained during the hot dismantling operations on the Rack 6 bis attested the effectiveness of the rack removal system as an original design which facilitates decommissioning of reprocessing plants. 2 tabs., 18 figs

  5. Nuclear installations: decommissioning and dismantling

    International Nuclear Information System (INIS)

    Anon.

    1995-01-01

    This document is a compilation of seven talks given during the 1995 EUROFORUM conference about decommissioning and dismantling of Nuclear installations in the European Community. The first two papers give a detailed description of the legal, financial and regulatory framework of decommissioning and dismantling of nuclear facilities in the European Union and a review of the currently available decommissioning techniques for inventory, disassembly, decontamination, remote operations and management of wastes. Other papers describe some legal and technical aspects of reactor and plants dismantling in UK, Germany, Spain and France. (J.S.)

  6. Radioactive waste management, decommissioning, spent fuel storage. V. 1. Waste management principles, decommissioning, dismantling, operations in hot environment

    International Nuclear Information System (INIS)

    1985-01-01

    This book deals mainly with decommissioning problems concerning more particularly dismantling and decontamination techniques, and radioactive waste processing. Radioactive waste management in France and the French regulation are tackled. Equipments developed for works in hostile environment are also presented [fr

  7. Dismantling system of concrete thermal shielding walls

    International Nuclear Information System (INIS)

    Machida, Nobuhiro; Saiki, Yoshikuni; Ono, Yorimasa; Tokioka, Masatake; Ogino, Nobuyuki.

    1985-01-01

    Purpose: To enable safety and efficient dismantling of concrete thermal shielding walls in nuclear reactors. Method: Concrete thermal shielding walls are cut and dismantled into dismantled blocks by a plasma cutting tool while sealing the top opening of bioshielding structures. The dismantled blocks are gripped and conveyed. The cutting tool is remote-handled while monitoring on a television receiver. Slugs and dusts produced by cutting are removed to recover. Since the dismantling work is carried out while sealing the working circumstance and by the remote control of the cutting tool, the operators' safety can be secured. Further, since the thermal sealing walls are cut and dismantled into blocks, dismantling work can be done efficiently. (Moriyama, K.)

  8. Definition of a dismantling project

    International Nuclear Information System (INIS)

    Meyers, H.; Claes, J.; Geens, L.

    1988-01-01

    The shutdown of the fuel reprocessing plant of Eurochemic having been decided, a study for defining the facilities to be dismantled and how to do it, was conducted by Belgoprocess. The cost of the operation was estimated by an accurate investigation and by a pilot project on the dismantling of the wastes storage building. The work carried out up to now and the problems to be solved are summarized [fr

  9. BRET fuel assembly dismantling machine

    International Nuclear Information System (INIS)

    Titzler, P.A.; Bennett, K.L.; Kelley, R.S. Jr.; Stringer, J.L.

    1984-08-01

    An automated remote nuclear fuel assembly milling and dismantling machine has been designed, developed, and demonstrated at the Hanford Engineering Development Laboratory (HEDL) in Richland, Washington. The machine can be used to dismantle irradiated breeder fuel assemblies from the Fast Flux Test Facility prior to fuel reprocessing. It can be installed in an existing remotely operated shielded hot cell facility, the Fuels and Materials Examination Facility (FMEF), at the Hanford Site in Richland, Washington

  10. Method for dismantling shields

    International Nuclear Information System (INIS)

    Fukuzawa, Rokuro; Kondo, Nobuhiro; Kamiyama, Yoshinori; Kawasato, Ken; Hiraga, Tomoaki.

    1990-01-01

    The object of the present invention is to enable operators to dismantle shieldings contaminated by radioactivity easily and in a short period of time without danger of radiation exposure. A plurality of introduction pipes are embedded previously to the shielding walls of shielding members which contain a reactor core in a state where both ends of the introduction pipes are in communication with the outside. A wire saw is inserted into the introduction pipes to cut the shieldings upon dismantling. Then, shieldings can be dismantled easily in a short period of time with no radiation exposure to operator's. Further, according to the present invention, since the wire saw can be set easily and a large area can be cut at once, operation efficiency is improved. Further, since remote control is possible, cutting can be conducted in water and complicated places of the reactor. Biting upon starting the wire saw in the introduction pipe is reduced to facilitate startup for the rotation. (I.S.)

  11. Rosie - mobile robot worksystem for decommissioning and dismantling operations. Final report, April 1, 1996--January 31, 1997

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-12-31

    RedZone Robotics, Inc. has undertaken development of an advanced remote worksystem - Rosie - specifically designed to meet the challenges of performing a wide range of decontamination and dismantlement (D&D) operations in nuclear environments. The Rosie worksystem includes a locomotor, heavy manipulator, operator console, and control system for remote operations. The locomotor is a highly mobile platform with tether management and hydraulic power onboard. The heavy manipulator is a high-payload, long-reach boom used to deploy a wide variety of tools and/or sensors into the work area. Rosie`s advanced control system, broad work capabilities, and hardening/reliability for hazardous duty make it a new and unique capability that facilitates completion of significant cleanup projects throughout the Department of Energy (DOE) and private sector. Endurance testing of the first Rosie system from September 1995 to March 1996 has proven its capabilities and appropriateness for D&D applications. Design enhancements were incorporated into the second Rosie system to improve and add features necessary for deployment at a DOE facility decommissioning. This second Rosie unit was deployed to the Argonne National Laboratory`s CP-5 reactor facility in early December 1996, and it is currently being used in the decommissioning of the reactor there. This report will overview this second Rosie system and the design enhancements made to it based on the lessons learned during the design, fabrication, and testing of the first Rosie system. The Rosie system has been designed to be a versatile and adaptable tool that can be used in many different applications in D&D work at nuclear facilities. It can carry a wide variety of tooling, sensors, and other robotic equipment at the tip of its heavy manipulator, and it can deploy those items to many different hazardous work areas. Rosie`s capabilities and system design address the need for durability and reliability in these environments.

  12. Rosie - mobile robot worksystem for decommissioning and dismantling operations. Final report, April 1, 1996 - January 31, 1997

    International Nuclear Information System (INIS)

    1998-01-01

    RedZone Robotics, Inc. has undertaken development of an advanced remote worksystem - Rosie - specifically designed to meet the challenges of performing a wide range of decontamination and dismantlement (D ampersand D) operations in nuclear environments. The Rosie worksystem includes a locomotor, heavy manipulator, operator console, and control system for remote operations. The locomotor is a highly mobile platform with tether management and hydraulic power onboard. The heavy manipulator is a high-payload, long-reach boom used to deploy a wide variety of tools and/or sensors into the work area. Rosie's advanced control system, broad work capabilities, and hardening/reliability for hazardous duty make it a new and unique capability that facilitates completion of significant cleanup projects throughout the Department of Energy (DOE) and private sector. Endurance testing of the first Rosie system from September 1995 to March 1996 has proven its capabilities and appropriateness for D ampersand D applications. Design enhancements were incorporated into the second Rosie system to improve and add features necessary for deployment at a DOE facility decommissioning. This second Rosie unit was deployed to the Argonne National Laboratory's CP-5 reactor facility in early December 1996, and it is currently being used in the decommissioning of the reactor there. This report will overview this second Rosie system and the design enhancements made to it based on the lessons learned during the design, fabrication, and testing of the first Rosie system. The Rosie system has been designed to be a versatile and adaptable tool that can be used in many different applications in D ampersand D work at nuclear facilities. It can carry a wide variety of tooling, sensors, and other robotic equipment at the tip of its heavy manipulator, and it can deploy those items to many different hazardous work areas. Rosie's capabilities and system design address the need for durability and reliability in

  13. Effect of Bizhongxiao decoction and its dismantled formulae on IL-1 and TNF levels in collagen-induced arthritis in rat synovial joints

    Directory of Open Access Journals (Sweden)

    Guo Ya-jing

    2012-11-01

    Full Text Available Abstract Background Rheumatoid arthritis (RA, a chronic autoimmune disease, affects sufferers in many different ways. Treatment of this chronic condition is particularly challenging. Traditional Chinese Medicine (TCM provides alternatives. Bizhongxiao decoction (BZX is a TCM complex, which has been used clinically for many years to treat RA. The purpose of this study is to compare the effects of BZX decoction and its dismantled formulae on IL-1 and TNF-1 levels in rats with RA, and to elucidate its mechanism of action. Methods Ninety healthy normal female SD rats were randomly divided into six groups: normal (control, model, BZX decoction, and the three dismantled formulae (I: heat-clearing and detoxication, II: dissipating dampness, and III: blood circulation promotion. Apart from the normal (control group, the rats in each group were injected subcutaneously with bovine type II collagen and complete Freund adjuvant to establish a collagen-induced arthritis model, so that inhibition of foot swelling in the rats by BZX decoction and its dismantled formulae could be observed. Immunohistochemistry was used to assess the levels of the inflammatory cytokines IL-1 and TNF in synovial joints at various time points. Results Twenty-one days after the model was established, the levels of TNF and IL-1 were significantly higher in the model group, BZX decoction group and dismantled formula groups I, II and III than in the normal controls (P  Conclusions BZX decoction and the three dismantled formulae examined down-regulated the inflammatory factors IL-1 and TNF in collagen-induced arthritis rat models, but BZX exerted the strongest effect.

  14. Effects of environmental lead pollution on blood lead and sex hormone levels among occupationally exposed group in an E-waste dismantling area.

    Science.gov (United States)

    Yang, Yan; Lu, Xiao Song; Li, Ding Long; Yu, Yun Jiang

    2013-06-01

    To study the effects of environmental multi-media lead pollution on blood lead and sex hormone levels among lead exposed males engaged in E-waste dismantling, and the correlation between confounding factors and sex hormone levels. An E-waste dismantling area in Taizhou of Zhejiang Province was selected as the research site. One hundred and fifty two samples were collected from the groundwater, soil, rice, corn, chicken, and pork in the dismantling area. The effects of the multi-media lead pollution on the male blood lead and sex hormone levels of FSH, LH, and T, as well as the correlation with confounding factors, were studied. The blood lead concentrations in the males aged under 31, from 31 to 45 and from 46 to 60 were 98.55, 100.23, and 101.45 μg/L, respectively. Of all the environmental media lead exposures, the groundwater, rice and soil were main contributing factors to the lead accumulation in humans. FSH and LH levels increased with the age while the T levels decreased with the age instead. There was a significant correlation between the FSH and LH levels and wearing masks. There was correlation between the FSH, LH, and T levels, and the mean values of lead concentrations in environmental media, and the sex hormone levels were correlated with the confounding factor of wearing masks. Copyright © 2013 The Editorial Board of Biomedical and Environmental Sciences. Published by China CDC. All rights reserved.

  15. Brennilis, laboratory of dismantlement

    International Nuclear Information System (INIS)

    Dupin, L.

    2011-01-01

    This article comments some aspects of the dismantlement activity on the Brennilis site (in Brittany) where a heavy water reactor has been operated from 1966 to 1985. Half of the deconstruction work has been performed between 1996 and 2006. As the model proposed by EDF for this operation raised some questions, works have been stopped for a while, until July 2011 when a decree authorized them again, but for some parts of the site only. The reactor block must wait as no technical solution exists for storage. But, the experience from this site will be used for eight other first generation power plants

  16. LEP Dismantling: Wagons Roll!

    CERN Multimedia

    2001-01-01

    The first trucks transporting material from LEP and its four experiments left CERN on 31 January. Since the LEP dismantling operation began, the material had been waiting to be removed from the sites of the four experiments and the special transit area on the Prévessin site. On the evening of 30 January, the French customs authorities gave the green light for the transport operation to begin. So first thing the next day, the two companies in charge of recycling the material, Jaeger & Bosshard (Switzerland) and Excoffier (France), set to work. Only 1500 truckloads to go before everything has been removed!

  17. Dismantlement and Radioactive Waste Management of DPRK Nuclear Facilities

    Energy Technology Data Exchange (ETDEWEB)

    Jooho, W.; Baldwin, G. T.

    2005-04-01

    One critical aspect of any denuclearization of the Democratic People’s Republic of Korea (DPRK) involves dismantlement of its nuclear facilities and management of their associated radioactive wastes. The decommissioning problem for its two principal operational plutonium facilities at Yongbyun, the 5MWe nuclear reactor and the Radiochemical Laboratory reprocessing facility, alone present a formidable challenge. Dismantling those facilities will create radioactive waste in addition to existing inventories of spent fuel and reprocessing wastes. Negotiations with the DPRK, such as the Six Party Talks, need to appreciate the enormous scale of the radioactive waste management problem resulting from dismantlement. The two operating plutonium facilities, along with their legacy wastes, will result in anywhere from 50 to 100 metric tons of uranium spent fuel, as much as 500,000 liters of liquid high-level waste, as well as miscellaneous high-level waste sources from the Radiochemical Laboratory. A substantial quantity of intermediate-level waste will result from disposing 600 metric tons of graphite from the reactor, an undetermined quantity of chemical decladding liquid waste from reprocessing, and hundreds of tons of contaminated concrete and metal from facility dismantlement. Various facilities for dismantlement, decontamination, waste treatment and packaging, and storage will be needed. The shipment of spent fuel and liquid high level waste out of the DPRK is also likely to be required. Nuclear facility dismantlement and radioactive waste management in the DPRK are all the more difficult because of nuclear nonproliferation constraints, including the call by the United States for “complete, verifiable and irreversible dismantlement,” or “CVID.” It is desirable to accomplish dismantlement quickly, but many aspects of the radioactive waste management cannot be achieved without careful assessment, planning and preparation, sustained commitment, and long

  18. Dismantling technologies trends

    International Nuclear Information System (INIS)

    Devaux, P.

    2009-01-01

    In this work dismantling technologies trends realized by the CEA are reviewed. There following technologies are presented: Data acquisition from facilities; Scenario studies; Remote handling and carriers; Dismantling techniques; Decontamination.

  19. Association of PCB, PBDE and PCDD/F body burdens with hormone levels for children in an e-waste dismantling area of Zhejiang Province, China

    Energy Technology Data Exchange (ETDEWEB)

    Xu, Peiwei, E-mail: pwxu@cdc.zj.cn; Lou, Xiaoming; Ding, Gangqiang; Shen, Haitao; Wu, Lizhi; Chen, Zhijian; Han, Jianlong; Han, Guangen; Wang, Xiaofeng, E-mail: zjcdcwxf@gmail.com

    2014-11-15

    Increased electronic waste (e-waste) has raised public concerns regarding exposure to numerous toxic contaminants, particularly polychlorinated biphenyls (PCBs), polybrominated diphenyl ethers (PBDEs) and polychlorinated dibenzo-p-dioxins and dibenzofurans (PCDD/Fs). In China, the body burdens of PCBs, PBDEs and PCDD/Fs are associated with thyroid hormones in populations from e-waste dismantling sites; however, it is unclear whether this association occurs in children. In this study, we determined the serum levels of PCBs, PBDEs and PCDD/Fs and the endocrine hormones including free triiodothyronine (FT3), total triiodothyronine (TT3), free thyroxine (FT4), total thyroxine (TT4), thyroid-stimulating hormone (TSH), adrenocorticotropic hormone (ACTH), cortisol and growth hormone (GH) in 21 children from an e-waste dismantling area and 24 children from a control area. The results showed that the mean levels of ∑ PCBs and ∑ PBDEs in the exposure group were significantly higher than in the control group (40.56 and 32.09 ng g{sup −1} lipid vs. 20.69 and 8.43 ng g{sup −1} lipid, respectively, p < 0.01 for each), and the mean level of ∑ PCDD/Fs in the exposure group was higher than in the control group, but the difference was not significant (206.17 vs. 160.27 pg g{sup −1} lipid, p > 0.05). For the endocrine hormones, we did not find significant differences between the exposed and control groups, although the mean levels of FT3, TT3, TT4, ACTH, cortisol and GH were higher, whereas the mean levels of FT4 and TSH were lower in the exposed group. The mean level of ∑ PBDEs was positively correlated with the mean levels of ∑ PCBs (r = 0.60, p < 0.05) and ∑ PCDD/Fs (r = 0.61, p < 0.05). Furthermore, the mean level of ∑ PBDEs was positively correlated with ACTH (r = 0.61, p < 0.05). In conclusion, our data suggested that exposure to e-waste dismantling environment increased the body burdens of PCBs and PBDEs in local children and that these contaminants

  20. Association of PCB, PBDE and PCDD/F body burdens with hormone levels for children in an e-waste dismantling area of Zhejiang Province, China

    International Nuclear Information System (INIS)

    Xu, Peiwei; Lou, Xiaoming; Ding, Gangqiang; Shen, Haitao; Wu, Lizhi; Chen, Zhijian; Han, Jianlong; Han, Guangen; Wang, Xiaofeng

    2014-01-01

    Increased electronic waste (e-waste) has raised public concerns regarding exposure to numerous toxic contaminants, particularly polychlorinated biphenyls (PCBs), polybrominated diphenyl ethers (PBDEs) and polychlorinated dibenzo-p-dioxins and dibenzofurans (PCDD/Fs). In China, the body burdens of PCBs, PBDEs and PCDD/Fs are associated with thyroid hormones in populations from e-waste dismantling sites; however, it is unclear whether this association occurs in children. In this study, we determined the serum levels of PCBs, PBDEs and PCDD/Fs and the endocrine hormones including free triiodothyronine (FT3), total triiodothyronine (TT3), free thyroxine (FT4), total thyroxine (TT4), thyroid-stimulating hormone (TSH), adrenocorticotropic hormone (ACTH), cortisol and growth hormone (GH) in 21 children from an e-waste dismantling area and 24 children from a control area. The results showed that the mean levels of ∑ PCBs and ∑ PBDEs in the exposure group were significantly higher than in the control group (40.56 and 32.09 ng g −1 lipid vs. 20.69 and 8.43 ng g −1 lipid, respectively, p < 0.01 for each), and the mean level of ∑ PCDD/Fs in the exposure group was higher than in the control group, but the difference was not significant (206.17 vs. 160.27 pg g −1 lipid, p > 0.05). For the endocrine hormones, we did not find significant differences between the exposed and control groups, although the mean levels of FT3, TT3, TT4, ACTH, cortisol and GH were higher, whereas the mean levels of FT4 and TSH were lower in the exposed group. The mean level of ∑ PBDEs was positively correlated with the mean levels of ∑ PCBs (r = 0.60, p < 0.05) and ∑ PCDD/Fs (r = 0.61, p < 0.05). Furthermore, the mean level of ∑ PBDEs was positively correlated with ACTH (r = 0.61, p < 0.05). In conclusion, our data suggested that exposure to e-waste dismantling environment increased the body burdens of PCBs and PBDEs in local children and that these contaminants released from the e

  1. Overall strategy of Creys Malville power station dismantling

    International Nuclear Information System (INIS)

    Alphonse, P.

    2002-01-01

    The power station was stopped by a government decision following the elections in 1997. This shutdown was then made official by a letter dated April 1998 and the decree of December 1998. This was a non-technical shutdown and as such had not been envisaged; there has been no early warning. Current dismantling strategy: The studies leading to shutdown and then dismantling were engaged in 1998 based on a scenario with a status corresponding to IAEA level 2 until 2046. In 2001, EDF management made the decision to dismantle all the first generation power stations and Creys Malville between now and 2025. It should be noted that the presence of strongly irradiated stellite in the Creys Malville reactor would still require remote systems for working in the reactor block after 2046. The sequence of operations dictated by the dismantling strategy is as follows: eliminate the risks as soon as possible and in particular the risk related to the sodium, 3300 tonnes of which is kept in liquid form in the reactor vessel; dismantle the most active parts which are too radioactive to be sent to the existing or planned storage centres. This may lead to on-site storage to allow decay to occur before sending to a storage centre; planning of the work interventions in order to limit the costs

  2. EL-3 dismantling of an experimental reactor

    International Nuclear Information System (INIS)

    1989-01-01

    The EL3 experimental reactor has been definitively stopped in march 1979. Its decommissioning has been pronounced in the end of 1982. This article is consecrated at decontamination and dismantling works necessited by its passage at the dismantling level 2 [fr

  3. Cleansing and dismantling of CEA-Saclay nuclear licensed facilities

    International Nuclear Information System (INIS)

    Jeanjacques, Michel; Delaire, Isabelle; Glevarec, Rebecca; Mandard, Lionel; Martin, Jean-Louis; Serrano, Roger

    2013-01-01

    This summary presents the cleansing and dismantling operations currently realized on the CEA center of Saclay (CEA-Saclay). It was initiated at the beginning of the 2000 years a cleansing and dismantling program of the old Nuclear Licensed Facilities (NLF). Currently this program relates the dismantling operations to the Hot Laboratories (Laboratoires de Haute Activite: LHA) and the old workshops of the Liquid Waste Treatment Plant (Station des Effluents Liquides: STEL), the dismantling preparation of Ulysse reactor and the dismantling studies to the Solid Waste Management Plant (SWMP; Zone de Gestion des Dechets Solides) and the Osiris reactor. (authors)

  4. Decommissioning of nuclear facilities: COGEMA expertise devoted to UP1 reprocessing plant dismantling programme

    International Nuclear Information System (INIS)

    Gay, A.

    2001-01-01

    Over the last past decades, the French nuclear industry has acquired a great experience and know-how in the field of dismantling. Today this experience amounts to more than 200,000 hours. The fundamental aims within dismantling strategy are the same as for all nuclear facilities: minimising doses received by workers, minimising waste volume and adapting waste management to radioactivity levels, minimising costs. French experience is based on technologies which are currently used in nuclear maintenance facilities. Dismantling is a dynamic process especially in the field of decontamination (chemical and mechanical), cleaning, robotics and remote control operations. The strategy for the dismantling of former UP1 reprocessing plant is based on the feedback of experience gained through the dismantling of other facilities such as the AT1 workshop at La Hague. This workshop, a pilot plant for reprocessing of fast-breeder reactor fuels (Rapsodie and Phenix) has to be dismantled to IAEA level 3 (unrestricted site use), excluding civil works structures. Currently conducted by trained shifts, this dismantling project should end in 1999. The experience already acquired proves that chemical rinsings with the use of specific reagents is sufficient to decontaminate the hot cells and that the use of remote operations or robotics is not as important as previously envisaged. The UP1 reprocessing plant of Marcoule operated from 1958 to 1997. End of the operation was pronounced on the 31st of December 1997. 20,000 tons of spent fuels were reprocessed at UP1. The cleaning and dismantling operations at the Marcoule site depend upon the CEA, EDF and COGEMA. The Defence and Industry Ministries asked for a specific structure to be set up. An economic interest group called CODEM was created in May 1996. CODEM decides, finances and supervises dismantling operations, while respecting the constraints of nuclear safety, environmental protection and cost-effectiveness. The cleaning operations of

  5. The Pierrelatte's military factories dismantling

    International Nuclear Information System (INIS)

    Bourrelier, P.; Kassel, Ch.

    1999-01-01

    The site of Pierrelatte in France, receives since 1958 gaseous diffusion plants assigned to the uranium enrichment for military uses. Since 1996 Cogema implements, by order of the Cea, a dismantling operation of the site. The operation which will begin in 2000, is going to last ten years. This project shows difficulties that make it innovative. Its originality, the planning, the risks, the program progressing and the regulation aspects are detailed in this paper. Beyond the complicated technical operations, the wastes management is of primary importance for the good development of the operations. (A.L.B.)

  6. The Superphenix dismantling

    International Nuclear Information System (INIS)

    Carle, R.

    1999-01-01

    This document presents selected abstracts of Remy Carle's presentation on the dismantling of Superphenix (october 1998). The author wonders about the consequences of such a decision. After a chronological account of this fast reactor project, its cost and the scientific and technical contribution, the dismantling problem is considered. For EDF (Electricite De France) the dismantling dimension is considered at the same time of the design. The main problem is the liquid sodium reprocessing: a technical but also a financing problem. The end of the speech deals with the political aspects of Superphenix and the relations with the public. (A.L.B.)

  7. Decontamination and partial dismantling of the Eurochemic plant. Part 1

    International Nuclear Information System (INIS)

    Detilleux, E.; Geens, L.; Hild, W.; Klonk, W.

    1980-09-01

    A description is given of the partial dismantling of the dissolver used for fuel elements of up to 1.6 wt % 235 U enrichment, and of the total dismantling of the dissolver for highly enriched fuel elements. The corresponding head-end cells have been decontaminated, allowing prolonged interventions, either in view of refurbishing or complete dismantling. An assessment of required manpower, dose commitments, material consumption, and waste production for all operations is given. (author)

  8. Lessons learned. Optimization of the plant structure at the beginning of the dismantling process

    International Nuclear Information System (INIS)

    Sesterhenn, Kurt

    2008-01-01

    The processes of shutdown and dismantling of the NPP Muehlheim-Kaerlich included several steps: conservation operation including fuel element removal, decontamination and radiological characterization, conservation of components that may still be used, removal and disposal of operating supply items, preparation of concepts for the dismantling process and realization of dismantling. The authors describe in detail the safety concept, the waste tracking program, the operational organization and reduction of area subject to radiological surveillance during the dismantling and renaturation project.

  9. STMI: several years of experience in nuclear plant dismantling

    International Nuclear Information System (INIS)

    Moreau, J.C.

    1985-01-01

    Since 1977, when STMI performed its first dismantling operation, the Company appreciably improved in that field through important operations: the dismantling of the calciothermy and fluoration metal Pu preparation facility, in La Hague reprocessing plant; the dismantling of the slag treatment chain, associated to calciothermy and fluoration processes, in La Hague reprocessing plant; and the cleaning of EL4 cell in Marcoule. To perform these operations, STMI's operating teams, on top of decontamination and dismantling technologies, strived to improve handling and transportation technologies, and to nuclearize many equipments. In order to increase its technical efficiency, STMI signed a cooperation agreement with FRAMATOME company. Therefore, the union between the operational know-hows of STMI and the design experience of TECHNICATOME allow the needs of any customs facing a dismantling case to be satisfied [fr

  10. Dismantling without contaminating: The EUREX plant experience

    International Nuclear Information System (INIS)

    2001-01-01

    constrains of the dismantling programme do not permit a characterization of metallic waste produced in real time and a special traceability system has been then put in place. Every single piece produced is numbered, associated with the original pipe line record (process stream data): it will be then easier, in the future characterization step, to post the liquid stream data of past process samplings to the contamination spectrum awaited for each piece. Another minimization of contamination spread risk during operations has been the accurate drying of components: after the emptying to dead volume of tanks, their upper pipes have been cut and a thin plastic hose has been introduced to evacuate the remaining bottom liquid. Where the pipelines bending may retain a residual liquid if present, the pipe is deformed in straight and draining shape before cutting. If this operation cannot be performed, a small drain drilling is made. According to the actual experience, it is possible to reduce, with direct human operation, special training and tailored techniques and tools, the spread of contamination during dismantling to very low levels, even in a tight schedule

  11. Remote dismantling of the French Brennilis nuclear power plant

    International Nuclear Information System (INIS)

    Studenski, Joerg

    2009-01-01

    The paper deals with the remote dismantling of the decommissioned EL4 prototype power plant Brennilis in France. The block contains the reactor pressure vessel including internals and biological shield, the piping and the control systems. The authors describe the general operation principle of the reactor to illustrate the peculiarities of the dismantling concept and the concept-related challenges. Detailed information is given concerning the following issues: creation of an access to the reactor block, the used remote technology, dismantling of the coolant piping and the axial shield, dismantling of the reactor pressure vessel and the lateral shield. Special attention is given on the minimization of the produced radioactive waste.

  12. Remote dismantling of the French Brennilis nuclear power plant

    Energy Technology Data Exchange (ETDEWEB)

    Studenski, Joerg [NUKEM Technologies GmbH (Germany)

    2009-07-01

    The paper deals with the remote dismantling of the decommissioned EL4 prototype power plant Brennilis in France. The block contains the reactor pressure vessel including internals and biological shield, the piping and the control systems. The authors describe the general operation principle of the reactor to illustrate the peculiarities of the dismantling concept and the concept-related challenges. Detailed information is given concerning the following issues: creation of an access to the reactor block, the used remote technology, dismantling of the coolant piping and the axial shield, dismantling of the reactor pressure vessel and the lateral shield. Special attention is given on the minimization of the produced radioactive waste.

  13. Dismantling and decontamination of Piver prototype vitrification plant

    International Nuclear Information System (INIS)

    Jouan, A.; Roudil, S.; Thomas, F.

    1991-01-01

    The PIVER prototype was targeted for dismantling in order to install a new pilot facility for the french continuous vitrification process. Most of the work involved the vitrification cell containing the process equipments, which had to be cleared out and thoroughly decontaminated; this implied disassembling, cutting up, conditioning and removing all the equipment installed in the cell. Remote manipulation, handling and cutting devices were used and some prior modifications were implemented in the cell environment. The dismantling procedure was conducted under a detailed programme defining the methodology for each operation. After equipment items and active zones were identified, the waste materials were removed, and several liquid decontamination operations were implemented. Removed activity, levels of irradiation in the cell and doses integrated by personnel were monitored to control progress and to adapt procedures to the conditions encountered. At the end of December 1989, the PIVER cleanup programme was at 87% complete and the total activity removed was 2.11 X 10 14 Bq (5712 Ci). The objective now is to obtain suitable working conditions in order to allow operators to enter the cell to remove items that are inaccessible or which cannot be dismantled by remote manipulators and to complete the decontamination procedure

  14. Dismantling the nuclear research reactor Thetis

    Energy Technology Data Exchange (ETDEWEB)

    Michiels, P. [Belgoprocess, 2480 Dessel (Belgium)

    2013-07-01

    The research reactor Thetis, in service since 1967 and stopped in 2003, is part of the laboratories of the institution of nuclear science of the University of Ghent. The reactor, of the pool-type, was used as a neutron-source for the production of radio-isotopes and for activation analyses. The reactor is situated in a water pool with inner diameter of 3 m. and a depth of 7.5 m. The reactor core is situated 5.3 m under water level. Besides the reactor, the pool contains pneumatic loops, handling tools, graphite blocks for neutron moderation and other experimental equipment. The building houses storage rooms for fissile material and sources, a pneumatic circuit for transportation of samples, primary and secondary cooling circuits, water cleaning resin circuits, a ventilation system and other necessary devices. Because of the experimental character of the reactor, laboratories with glove boxes and other tools were needed and are included in the dismantling program. The building is in 3 levels with a crawl-space. The ground-floor contains the ventilation installation, the purification circuits with tanks, cooling circuits and pneumatic transport system. On the first floor, around the reactor hall, the control-room, visiting area, end-station for pneumatic transport, waste-storage room, fuel storage room and the labs are located. The second floor contains a few laboratories and end stations of the two high speed transfer tubes. The lowest level of the pool is situated under ground level. The reactor has been operated at a power of 150 kW and had a max operating power of 250 kW. Belgoprocess has been selected to decommission the reactor, the labs, storage halls and associated circuits to free release the building for conventional reuse and for the removal of all its internals as legal defined. Besides the dose-rate risk and contamination risk, there is also an asbestos risk of contamination. During construction of the installation, asbestos-containing materials were

  15. UDIN's dismantling projects

    International Nuclear Information System (INIS)

    Laffaille, C.

    1993-01-01

    The role of UDIN (Central unit for nuclear facility decommissioning) at the CEA is reviewed together with the main specific aspects of nuclear dismantling: the different options and dismantling strategies and costs. The characteristics of the main on-going projects are described: graphite-gas reactors (G2/G3), RAPSODIE (RNR), AT1 (pilot RNR fuel reprocessing plant), ELAN II B (Cesium source conditioning plant), EL4 (heavy water/CO2 reactor), RM2 (fuel control radio-metallurgical laboratory) and UB-UM (Uranium enrichment plant)

  16. Study on treatment of dust by dismantling

    International Nuclear Information System (INIS)

    Torikai, K.; Suzuki, K.

    1987-01-01

    In dismantling of nuclear reactors, various kinds of treatment of dust generated by cutting or dismantling concrete structures of components of reactors are evaluated for safety, cost, and performance comparing the work in air with water. A method of dust treatment for work in air is discussed. The dry method has an easy operation in practice and a good performance in the equipment, but has problem on the prevention from radioactive contamination by diffusion of dust in air. For the purpose of advancing the strong points and eliminating the weak points in dry method, an improved venturi scrubber system is proposed for dismantling work as a dust collecting system. The system consists of dust absorbing pipe, dust collector, separator of dust and water and dust transfer equipment to a storage of waste. This system would be expected to have better performance and lower operating cost in decommissioning nuclear reactors, especially, the number of dust filters, for example, HEPA filters, will be considerably saved

  17. Development of equipments for remote dismantling of joule heated ceramic melter

    International Nuclear Information System (INIS)

    Badgujar, Kiran T.; Usarkar, Sachin G.; Kumar, Binu; Nair, K.N.S.

    2011-01-01

    Joule Heated Ceramic Melter (JHCM) technology has been adopted for industrial scale vitrification of high level liquid waste (HLLW) at Tarapur and Kalpakkam. The melter installed at Advanced Vitrification System (AVS), Tarapur has immobilized 175 m 3 of HLLW in 113 canisters containing 11533Kg of Vitrified Waste Product (VWP). The melter has been in operation for 3 years before shutdown. It is intended to demonstrate the complete procedure of dismantling of Joule Melter in 1:1 scale prior to going in for actual dismantling in the hot cell. The Melter consists of an assembly of Inconel/SS pipes and plates, fuse cast refractories, thermal insulations of various types inside a SS casing and possibly some glass which is left over in the melter. Dismantling of melter involves remote cutting of the outer casing, pipe connections, electrical connections and removal, sizing and packing of internals in a sequential manner to minimise generation of secondary waste. The challenge involves development of remotely operated multi-degrees of freedom fixtures, modification and performance testing of standard industrial cutting and breaking tools and adapting them for remote operations. The work also involves development of equipments for collection of waste generated during the dismantling operation and packaging thus in special packages. Remotely actuated fixtures have been developed for remote top plate and side electrodes cutting. Remotely operated grab has been developed for handling of loose material and grippers have been developed for handling of refractory blocks. Industrial vacuum suction device has been modified into split units to enable for reducing the spread of powder material, while dismantling in progress. The performance test of developed fixtures, equipments, cutting and breaking tools have been carried on 1:1 scale melter model. Various parameters like cutting speed, cutting tool performance, generation of waste volume has been measured and analysed for

  18. Nuclab Marcoule: a dedicated waste management and dismantling support laboratory

    International Nuclear Information System (INIS)

    Dugne, Olivier; Bec-Espitalier, Lionel; Rosen, Jeremy

    2014-01-01

    Formerly dedicated to plutonium production support, NucLab was renovated to perform a wide range of analyses for dismantling, plant operation and process development activities mainly at Marcoule but also for external clients. The laboratory is a CEA entity in the Nuclear Energy Division. It provides services to several industrial operators (nuclear processes and power plants) in the fields of analytical chemistry, radioactivity measurements, in situ nuclear measurements, decontamination processes, industrial chemistry processes, and waste treatment. NucLab supports research, production, and dismantling activities in all areas of dismantling operations (authors)

  19. Contaminated Metal Components in Dismantling by Hot Cutting Processes

    International Nuclear Information System (INIS)

    Cesari, Franco G.; Conforti, Gianmario; Rogante, Massimo; Giostri, Angelo

    2006-01-01

    During the preparatory dismantling activities of Caorso's Nuclear Power Plant (NPP), an experimental campaign using plasma and oxyacetylene metal cutting processes has been performed and applied to plates and tubes exposed to the coolant steam of the reactor. The plant (Boiling Water Reactor, 870 MWe) was designed and built in the 70's, and it was fully operating by 1981 to 1986 being shut down after 1987 Italy's poll that abrogated nuclear power based on U235 fission. The campaign concerns no activated materials, even if the analyses have been performed of by use contaminated components under the free release level, not yet taking into account radioactivity. In this paper, the parameters related to inhalable aerosol, solid and volatile residuals production have been, studied during hot processes which applies the same characteristics of the cutting in field for the dismantling programs of Caorso NPP. The technical parameters such as cutting time and cutting rate vs. pipe diameter/thickness/schedule or plate thickness for ferritic alloys and the emissions composition coming from the sectioning are also reported. The results underline the sort of trouble that can emerge in the cutting processes, in particular focusing on the effects comparison between the two cutting processes and the chemical composition of powders captured by filtering the gaseous emission. Some preliminary considerations on methodology to be used during the dismantling have been presented. (authors)

  20. Jose Cabrera dismantling and decommissioning project

    International Nuclear Information System (INIS)

    Ondaro, Manuel

    2013-01-01

    The Jose Cabrera Nuclear Power Plant (NPP) was the first commercial power reactor (Westinghouse 1 loop PWR 510 MWth, 160 MWe) commissioned in Spain and provided the base for future development and training. The reactor construction started in 1963 and it was officially on-line by 1969. The NPP operated from 1969 until 2006 when it became the first reactor to be shut down after completing its operational period. The containment is reinforced concrete with a stainless steel head. In 2010 responsibility for D and D was transferred to Enresa to achieve IAEA level 3 (a green field site available for unrestricted re-uses) by 2017. Of the total of more than 104,000 tons of materials that will be generated during dismantling, it is estimated that only ∼4,000 tons will be radioactive waste, some of which, 40 t are considered as intermediate level long-lived wastes and the rest (3,960 t) will be categorized as VLLW and ILLW. The Project is divided into five phases: Phase 0 - Removal of fuel and preliminary work.. Phase 1 - Preparatory Activities for D and D. complete. Phase 2 - Dismantling of Major Components. Phase 3 - Removal of Auxiliary Installations, Decontamination and Demolition. Phase 4 - Environmental Restoration. Phase 2, is currently ongoing (50% completed). To manage the diverse aspects of decommissioning operations, Enresa uses an internally developed computerized project management tool. The tool, based on knowledge gathered from other Enresa projects, can process operations management, maintenance operations, materials, waste, storage areas, procedures, work permits, operator dose management and records. Enresa considers that communication is important for both internal and external stakeholder relations and can be used to inform, to neutralize negative opinions and attitudes, to remove false expectations and for training. Enresa has created a new multi-purpose area (exhibition/visitor centre) and encourages visits from the public, local schools, local and

  1. Jose Cabrera dismantling and decommissioning project

    Energy Technology Data Exchange (ETDEWEB)

    Ondaro, Manuel [ENRESA, Madrid (Spain)

    2013-07-01

    The Jose Cabrera Nuclear Power Plant (NPP) was the first commercial power reactor (Westinghouse 1 loop PWR 510 MWth, 160 MWe) commissioned in Spain and provided the base for future development and training. The reactor construction started in 1963 and it was officially on-line by 1969. The NPP operated from 1969 until 2006 when it became the first reactor to be shut down after completing its operational period. The containment is reinforced concrete with a stainless steel head. In 2010 responsibility for D and D was transferred to Enresa to achieve IAEA level 3 (a green field site available for unrestricted re-uses) by 2017. Of the total of more than 104,000 tons of materials that will be generated during dismantling, it is estimated that only ∼4,000 tons will be radioactive waste, some of which, 40 t are considered as intermediate level long-lived wastes and the rest (3,960 t) will be categorized as VLLW and ILLW. The Project is divided into five phases: Phase 0 - Removal of fuel and preliminary work.. Phase 1 - Preparatory Activities for D and D. complete. Phase 2 - Dismantling of Major Components. Phase 3 - Removal of Auxiliary Installations, Decontamination and Demolition. Phase 4 - Environmental Restoration. Phase 2, is currently ongoing (50% completed). To manage the diverse aspects of decommissioning operations, Enresa uses an internally developed computerized project management tool. The tool, based on knowledge gathered from other Enresa projects, can process operations management, maintenance operations, materials, waste, storage areas, procedures, work permits, operator dose management and records. Enresa considers that communication is important for both internal and external stakeholder relations and can be used to inform, to neutralize negative opinions and attitudes, to remove false expectations and for training. Enresa has created a new multi-purpose area (exhibition/visitor centre) and encourages visits from the public, local schools, local and

  2. Dismantling of Vandellos I

    International Nuclear Information System (INIS)

    Armada, J. R.

    2003-01-01

    Spain is witnessing the phase-out of a nuclear power plant. It is a unique experience in our country and therefore the dismantling work has been watched closely, not only from here but also from abroad. The Empresa Nacional de Residuos Radiactivos (ENRESA) is in charge of managing the dismantling and decommissioning work of the Vandellos-I nuclear power plant, located in the municipality of L'Hospitalet de l'Infant (Tarragona). the work began five years ago and has been executed on schedule. the appearance of what was one of the first Spanish commercial nuclear power plants has been changed radically to leave premises suitable for any other activity. (Author)

  3. Abrasive water jet cutting technique for biological shield concrete dismantlement

    International Nuclear Information System (INIS)

    Konno, T.; Narazaki, T.; Yokota, M.; Yoshida, H.; Miura, M.; Miyazaki, Y.

    1987-01-01

    The Japan Atomic Energy Research Institute (JAERI) is developing the abrasive-water jet cutting system to be applied to dismantling the biological shield walls of the JPDR as a part of the reactor dismantling technology development project. This is a total system for dismantling highly activated concrete. The concrete biological shield wall is cut into blocks by driving the abrasive-water jet nozzle, which is operated with a remote, automated control system. In this system, the concrete blocks are removed to a container, while the slurry and dust/mist which are generated during cutting are collected and treated, both automatically. It is a very practical method and will quite probably by used for actual dismantling of commercial power reactors in the future because it can minimize workers' exposure to radioactivity during dismantling, contributes to preventing diffusion of radiation, and reduces the volume of contaminated secondary waste

  4. The WAK decommissioning and dismantling program

    International Nuclear Information System (INIS)

    Eiben, K.; Fritz, P.

    1995-01-01

    After an extensive rinsing of the reprocessing equipment the operation in the plant was terminated in 1991 following the principal political decision to abolish reprocessing of nuclear fuel in Germany. Since July 1991 only the safety relevant units are still in operation including the waste storage facilities for 80 m 3 of high active waste concentrate (HAWC). The decommissioning and dismantling will be achieved in six steps taking into account that some of the reprocessing equipment can be dismantled before and the rest only after the HAWC has been vitrified approximately by mid 2000. So far two licenses for decommissioning have been granted. An application for the dismantling of twelve systems in the process building including headend and tailend facilities will be licensed in 1995. The remote dismantling of equipment from the hot cells in the process building is being planned and will be executed between 1998--2001. New remote handling equipment will be cold tested in a test facility scheduled to start in the middle of this year. The final task is the green meadow after demolishing of the building and remediation of the site which is scheduled for 2005

  5. Decommissioning and dismantling: evaluation of possible radiological impacts from exceeding clearance levels at nuclear facilities. Final report

    International Nuclear Information System (INIS)

    Kirchhoff, J.; Stasch, W.P.; Thierfeldt, S.; Kugeler, E.

    2001-01-01

    On June 14, 2000 the German power utilities have reached an agreement with the German government (energy consent). According to that all nuclear power plants in Germany shall be shut down approximately until the year 2020 and shall be decommissioned afterwards. Almost 95% of the mass of a nuclear power plant can be re-used or recycled as normal material and waste after the necessary handling (decontamination) and clearance measurements. For the release of the entire mass of a NPP several hundreds of thousand radioactivity measurements (so called free release measurements) are necessary. With this huge number of measurements mistakes cannot be excluded. The study includes several radiological scenarios which could result from mistakes during the release/clearance procedure. The radiation doses calculated during the simulation show that some faulty releases can give rise to doses above the trivial dose level of some 10 μSv. An effective dose up to 400 μSv for individuals has been determined. However, with a high certainty it can be excluded that the individual effective dose will reach the range of 1000 μSv even with a hypothetical consideration of a concatenation of several conditions. Because of the low probability of appearance and their minimal radiological effects mistakes during the release procedure pose no hazards. (orig.) [de

  6. Remotely-Controlled Shear for Dismantling Highly Radioactive Tools In Rokkasho Vitrification Facility - 12204

    Energy Technology Data Exchange (ETDEWEB)

    Mitsui, Takashi; Sawa, Shusuke; Sadaki, Akira; Awano, Toshihiko [IHI Corporation, 1 Shin-Nakahara-cho, Isogo-ku, Yokohama, Kanagawa (Japan); Cole, Matt [S.A. Technology Inc, 3985 S. Lincoln Ave., Ste. 100, Loveland CO 80537 (United States); Miura, Yasuhiko; Ino, Tooru [Japan Nuclear Fuel Limited, 4-108, Aza Okitsuke, Oaza Obuchi, Rokkasho-Mura, Kamikita-gun, Aomori (Japan)

    2012-07-01

    A high-level liquid waste vitrification facility in the Japanese Rokkasho Reprocessing Plant (RRP) is right in the middle of hot commissioning tests toward starting operation in fall of 2012. In these tests, various tools were applied to address issues occurring in the vitrification cell. Because of these tools' unplanned placement in the cell it has been necessary to dismantle and dispose of them promptly. One of the tools requiring removal is a rod used in the glass melter to improve glass pouring. It is composed of a long rod made of Inconel 601 or 625 and has been highly contaminated. In order to dismantle these tools and to remotely put them in a designated waste basket, a custom electric shear machine was developed. It was installed in a dismantling area of the vitrification cell by remote cranes and manipulators and has been successfully operated. It can be remotely dismantled and placed in a waste basket for interim storage. This is a very good example of a successful deployment of a specialty remote tool in a hot cell environment. This paper also highlights how commissioning and operations are done in the Japanese Rokkasho Reprocessing Plant. (authors)

  7. Dismantling and decontamination of the PIVER prototype vitrification facility

    International Nuclear Information System (INIS)

    Jouan, A.

    1989-01-01

    The PIVER facility was dismantled for replacement by a new continuous pilot plant. The more important operation concerns the vitrification cell, containing equipments of the process, for complete disposal and maximum decontamination, requiring dismantling, cutting, conditioning and removal of equipment inside the cell. Manipulators, handling and cutting tools were used. Activity of removed material and irradiation of personal are followed during the work for matching intervention means to operation conditions [fr

  8. SGDES: Management system dismantling of ENRESA

    International Nuclear Information System (INIS)

    Julian, A. de; Fernandez, M.; Vidaechea, S.

    2013-01-01

    ENRESA, the Spanish public company responsible for managing radioactive waste and nuclear facilities decommissioning, has developed a management information system (SGDES) for the decommissioning of nuclear power plants. Dismantling activities require a rigorous operations control within highly specialized, process systematization and safety framework, both under human and technological point of view. SGDES system is capable of responding to the mentioned operational needs, efficiently and safely.

  9. Dismantling and waste management: CEA's strategy and research programs

    International Nuclear Information System (INIS)

    Behar, C.

    2012-01-01

    There are 3 main dismantling operations in CEA. First, the dismantling of the UP1 facility in the Marcoule site. UP1 was a reprocessing plant of nuclear fuels that operated from 1958 to 1997 and is now the biggest dismantling operation in the world. Its dismantling operation follows a 6-step scheme that will end in 2050. Secondly, the Passage project on the Grenoble site that concerns the dismantling of 3 research reactors (Siloette, Melusine and Siloe), of a laboratory dedicated to the analysis of active materials (Lama) and of a station for the processing of waste (Sted). Thirdly the Aladin project that concerns the installations of the Fontenay-aux-Roses site. The dismantling operations are complex because all the first research programs on high activity chemistry and on transuranium elements were performed in Fontenay-aux-Roses facilities and because ancient activities have to leave a clean place to be replaced by new ones. The radioactive waste produced by CEA enter the flow of waste that is normally processed and managed by ANDRA. Only high-activities waste have not yet a definitive solution, they are stored in waiting the opening of a geological repository. CEA leads research programs on the separation and transmutation of minor actinides and on the long-term behaviour of waste packages put in deep geological layers. (A.C.)

  10. Dismantling of transuranic contaminated facilities

    International Nuclear Information System (INIS)

    Roux, P.

    1985-01-01

    The dismantling of transuranic contaminated facilities raises specific problems. A large part of these problems relates to the management of the waste resulting from dismantling. From the experience gained in the different centers CEA and COGEMA it appears that there are industrial solutions in the group CEA and that an engineering company such as SGN can export them [fr

  11. MIPAS level 2 operational analysis

    Directory of Open Access Journals (Sweden)

    P. Raspollini

    2006-01-01

    Full Text Available The MIPAS (Michelson Interferometer for Passive Atmospheric Sounding instrument has been operating on-board the ENVISAT satellite since March 2002. In the first two years, it acquired in a nearly continuous manner high resolution (0.025 cm−1 unapodized emission spectra of the Earth's atmosphere at limb in the middle infrared region. This paper describes the level 2 near real-time (NRT and off-line (OL ESA processors that have been used to derive level 2 geophysical products from the calibrated and geolocated level 1b spectra. The design of the code and the analysis methodology have been driven by the requirements for NRT processing. This paper reviews the performance of the optimized retrieval strategy that has been implemented to achieve these requirements and provides estimated error budgets for the target products: pressure, temperature, O3, H2O, CH4, HNO3, N2O and NO2, in the altitude measurement range from 6 to 68 km. From application to real MIPAS data, it was found that no change was needed in the developed code although an external algorithm was introduced to identify clouds with high opacity and to exclude affected spectra from the analysis. In addition, a number of updates were made to the set-up parameters and to auxiliary data. In particular, a new version of the MIPAS dedicated spectroscopic database was used and, in the OL analysis, the retrieval range was extended to reduce errors due to uncertainties in extrapolation of the profile outside the retrieval range and more stringent convergence criteria were implemented. A statistical analysis on the χ2 values obtained in one year of measurements shows good agreement with the a priori estimate of the forward model errors. On the basis of the first two years of MIPAS measurements the estimates of the forward model and instrument errors are in general found to be conservative with excellent performance demonstrated for frequency calibration. It is noted that the total retrieval

  12. Laser dismantling of a glovebox

    International Nuclear Information System (INIS)

    Johnson, R.; Fender, M.

    1985-01-01

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

  13. Dismantling of nuclear facilities and related problems - Conference proceedings

    International Nuclear Information System (INIS)

    Tournebize, Frederic; Bordet, Didier; Charlety, Philippe; Gore, Thierry; Estrade, Jerome; Lemaire, Hermine; Ginet, Annick; Fabrier, Lionel; Evrard, Lydie; Furois, Timothee; Butez, Marc; Dutzer, Michel; Faure, Vincent; Billarand, Yann; Menuet, Lise; Lahaye, Thierry; Pin, Alain; Mougnard, Philippe; Charavy, Sylvain; Poncet, Philippe; Moggia, Fabrice; Dochy, Arnaud; Benjamin, Patrick; Poncet, Pierre-Emmanuel; Beneteau, Yannick; Richard, Jean-Baptiste; Pellenz, Gilles; Ollivier Dehaye, Catherine; Gerard, Stephane; Denissen, Luc; Davain, Henri; Duveau, Florent; Guyot, Jean-Luc; Ardellier, Luc

    2012-11-01

    The oldest French nuclear facilities, built for some of them in the 1950's for research or power generation purposes, have reached more or less the end of their life. More than 30 facilities have entered the shutdown or dismantling phase, among which 8 reactors of the very first generations of Electricite de France (EdF) reactors. The aim of this two-days conference is to take stock of the present day status and perspectives of the dismantling activity, to approach the question of the management of the wastes produced, and to share experience about large scale operations already carried out. This document gathers the available presentations given during this conference: 1 - the 'Passage' project (F. Tournebize); 2 - CEA-Grenoble: from Louis Neel to key enabling technologies (D. Bordet); 3 - Dismantling actions in France (L. Evrard); 4 - Securing control of long-term charges funding (T. Furois); 5 - Waste disposal projects and their contribution to the management of dismantling wastes (M. Butez); 6 - Specificities linked with dismantling activities (Y. Billarand); 7 - Dismantling safety: the ASN's point of view (L. Evrad); 8 - Labor Ministry viewpoint about the dismantling related questions (T. Lahaye); 9 - Consideration of organizational and human factors in dismantling operations: a new deal in the operators-service providers relation (L. Menuet); 10 - Diploma and training experience (A. Pin); 11 - Glove-boxes dismantling at La Hague plant - status and experience feedback (P. Mougnard); 12 - Dismantling of Siloe reactor (CEA-Grenoble): application of the ALARA approach (P. Charlety); 13 - BR3 - a complex dismantling: the neutron shield tank (NST) in remote operation and indirect vision (L. Denissen); 14 - Cleansing and dismantling of the Phebus PF containment (S. Charavy); 15 - Integration of dismantling at the design and exploitation stages of nuclear facilities (P. Poncet); 16 - Consideration during the design and exploitation stages of dispositions aiming at

  14. Decommissioning of the AVR reactor, concept for the total dismantling

    International Nuclear Information System (INIS)

    Marnet, C.; Wimmers, M.; Birkhold, U.

    1998-01-01

    After more than 21 years of operation, the 15 MWe AVR experimental nuclear power plant with pebble bed high temperature gas-cooled reactor was shout down in 1988. Safestore decommissioning began in 1994. In order to completely dismantle the plant, a concept for Continued dismantling was developed according to which the plant could be dismantled in a step-wise procedure. After each step, there is the possibility to transform the plant into a new state of safe enclosure. The continued dismantling comprises three further steps following Safestore decommissioning: 1. Dismantling the reactor vessels with internals; 2. Dismantling the containment and the auxiliary units; 3. Gauging the buildings to radiation limit, release from the validity range of the AtG (Nuclear Act), and demolition of the buildings. For these steps, various technical procedures and concepts were developed, resulting in a reference concept in which the containment will essentially remain intact (in-situ concept). Over the top of the outer reactor vessel a disassembling area for remotely controlled tools will be erected that tightens on that vessel and can move down on the vessel according to the dismantling progress. (author)

  15. Towards the creation of an industrial sector dedicated to nuclear dismantling

    International Nuclear Information System (INIS)

    Anon.

    2015-01-01

    In next decades the business of nuclear dismantling is expected to grow exponentially due to the decommissioning of nuclear facilities that will have reached the end of their operating life. Dismantling has 2 main features: dismantling operations on a same site can span decades and dismantling is a new activity in which innovations are likely to appear and may benefit other sectors. In France regional authorities have promoted public-private partnerships in order to make working together small enterprises very specialized in sectors like robotic, laser cutting, waste processing, remote operations... with public laboratories dedicated to nuclear research, and with graduate schools to include dismantling in curriculum and with major industrial operators of the nuclear industry. The aim is the creation of jobs and the building of an industrial sector able to win market shares in the worldwide business of nuclear dismantling. (A.C.)

  16. Cutting and decontamination technologies for nuclear facility dismantling; Technologien zur Zerlegung und zur Dekontamination von kerntechnischen Anlagen

    Energy Technology Data Exchange (ETDEWEB)

    Huebner, Felix; Grone, Georg von; Schultmann, Frank

    2017-03-15

    The German Government's decision to phase-out nuclear power will lead to a substantial increase of the number of nuclear decommissioning and dismantling projects. The decommissioning of nuclear facilities must meet the requirements of the radiation protection ordinance. This study deals with the decontamination and dismantling technologies available to meet radiation protection requirements. The aim of this study is to determine the state of the art in the field of decommissioning and dismantling technologies. Furthermore, future trends in the development and application of such technologies should be identified. A detailed study of current literature provides an overview of established decommissioning technologies. Moreover, experts were consulted in order to facilitate a practical assessment. The experts' statements indicate that (apart from the chemical decontamination of the primary circuit) the use of mechanical methods is generally preferred. Abrasive methods are rated as particularly efficient. According to the experts, the development of new decontamination technologies may allow a more efficient decontamination. However, the success of a new technology will be subject to its application costs. Mechanical technologies are preferred for the dismantling of nuclear facilities. The band saw has been identified as a standard tool in nuclear dismantling. The survey has concluded that there is no need for new dismantling technologies. The potential lies in the optimization of existing processes and techniques. With regard to remotely operated systems, experts' opinions vary on whether the use of these systems will increase in future. Most areas inside a nuclear facility have low radiation levels that allow the use of human labour for the dismantling. However, there is a need for an improvement in the allocation and management of decommissioning projects.

  17. Clean-up and dismantling, Dismantling - legacy of the past, prospects for the future: CEA, a pioneer in the dismantling process, nuclear dismantling, research and innovation dedicated to dismantling

    International Nuclear Information System (INIS)

    Lorec, Amelie

    2016-01-01

    France - a world leader in the whole nuclear power cycle - is also responsible for the clean-up and dismantling of its end-of-life nuclear facilities. Here, the CEA is considered to be a pioneer both in the project ownership of work sites and in the R and D for optimising the timescales, costs and safety of those work sites. Its responsibilities range from defining the most appropriate scenario, characterising the radiological state of equipment and decontaminating premises, carrying out dismantling and optimising the resulting waste. With this wide range of skills and the diversity of its facilities, the CEA Nuclear Energy Division is developing innovative solutions which are already the subject of industrial transfers. Two-thirds of France's end-of-life nuclear facilities belong to the CEA - a situation connected with its history. This implies setting up clean-up and dismantling work sites which have unprecedented scientific, human and financial challenges. Every regulated nuclear installation (INB) (nuclear reactors, laboratories, etc.) has a limited operating life. When it stops being used, it is first cleaned up (removal of radioactive substances), then dismantled (disassembly of components) in accordance with the baseline safety requirements, and finally decommissioned so that it can be used for other purposes or be demolished. Cleanup and dismantling operations concern all the facility's components, such as hot (shielded) cells which can be found in some laboratories. As the owner of its clean-up and dismantling projects, the CEA also devotes a significant amount of R and D to reducing the timescales, costs and waste from current and future programmes, while improving their safety. The resulting innovations often lead to industrial transfers. (authors)

  18. Method of freezing type dismantling for wasted reactors

    International Nuclear Information System (INIS)

    Tatsumi, Toshiyuki.

    1985-01-01

    Purpose: To enable to operate a cutting device in the air by placing a working table on ice while utilizing the ice as radiation shielding materials thereby prevent the diffusion of air contaminations. Method: Upon dismantling a BWR type reactor, ice is packed into a reactor container and a pressure vessel and frozen state is maintained by cooling coils disposed to the outer circumference of the pressure vessel. Then, an airtight hood is covered over the pressure vessel and a working table is rotatably disposed therein. Upon working, when the upper layer ice is melted by a heat pump and discharged, the airtight hood is lowered to a predetermined level. After freezing the melted portion again at the lowered level, cutting work is conducted by an operator in the hood. The cut pieces are conveyed after hoisting the airtight hood by a crane. The pressure vessel is dismantled by repeating the foregoing procedures. In this way, cut pieces can be recovered without falling them to the reactor bottom as in the conventional work in water. In addition, since the procedures are conducted while covering the airtight hood, diffusion of air contaminations can be prevented. (Kamimura, M.)

  19. Analysis of dismantling possibility and unloading efforts of fuel assemblies from core of WWER

    International Nuclear Information System (INIS)

    Danilov, V.; Dobrov, V.; Semishkin, V.; Vasilchenko, I.

    2006-01-01

    The computation methods of optimal dismantling sequence of fuel assemblies (FA) from core of WWER after different operating periods and accident conditions are considered. The algorithms of fuel dismantling sequence are constructed both on the basis of analysis of mutual spacer grid overlaps of adjacent fuel assemblies and numerical structure analysis of efforts required for FA removal as FA heaving from the core. Computation results for core dismantling sequence after 3-year operating period and LB LOCA are presented in the paper

  20. DISMANTLING OF THE FUEL CELL LABORATORY AT RESEARCH CENTRE JUELICH

    International Nuclear Information System (INIS)

    Stahn, B.; Matela, K.; Bensch, D.; Ambos, Frank

    2003-01-01

    The fuel cell laboratory was constructed in three phases and taken into operation in the years 1962 to 1966. The last experimental work was carried out in 1996. After all cell internals had been disassembled, the fuel cell laboratory was transferred to shutdown operation in 1997. Three cell complexes, which differed, in particular, by the type of shielding (lead, cast steel, concrete), were available until then for activities at nuclear components. After approval by the regulatory authority, the actual dismantling of the fuel cell laboratory started in March 2000. The BZ I laboratory area consisted of 7 cells with lead shieldings of 100 to 250 mm thickness. This area was dismantled from April to September 2000. Among other things, approx. 30,000 lead bricks with a total weight of approx. 300 Mg were dismantled and disposed of. The BZ III laboratory area essentially consisted of cells with concrete shieldings of 1200 to 1400 mm thickness. The dismantling of this area started in the fir st half of 2001 and was completed in November 2002. Among other things, approx. 900 Mg of concrete was dismantled and disposed of. Since more than 90 % of the dismantled materials was measurable for clearance, various clearance measurement devices were used during dismantling. The BZ II laboratory area essentially consists of cells with cast steel shieldings of 400 to 460 mm thickness. In September 2002 it was decided to continue using this laboratory area for future tasks. The dismantling of the fuel cell laboratory was thus completed. After appropriate refurbishment, the fuel cell laboratory will probably take up operation again in late 2003

  1. The dismantling of nuclear power plants which are not in use

    International Nuclear Information System (INIS)

    Tanguy, P.

    1987-01-01

    At the end of its life span, a nuclear power plant contains big quantities of radioactive products. The corresponding risks must be controlled and over the long range, all radioactivity must be definitively removed. The latter operation is called dismantling. In France, at the beginning of 1987, five nuclear units which were permanently put out of use have to be dismantled. These units are presented in this article. From this presentation, it can be seen that there are now techniques which provide for complete control of the risks corresponding to radioactivity. However, in France, as in the rest of the world, the dismantling of nuclear plants will not attain its full industrial level until the 21st Century. The problems which have to be solved are known, but better performing technologies have to be developed in order to obtain a superior protection of dismantling work crews and a reduction of costs. This article concludes with an appeal for high French interest in international activities in this field [fr

  2. The Operational Level of War

    Science.gov (United States)

    1985-12-01

    Lessons from the Russo-Japanese War." United Service Magazine 30 (October 1904-March 1905):112+. Caemmerer, Rudolf von. The Development of Strategical...over the German operational plan for the western offensive, 1940.] Wiesbaden: Franz Steiner Verlag, 1957. This is the best work on the subject. Kissel

  3. Technology and costs for dismantling a Swedish nuclear power plant

    International Nuclear Information System (INIS)

    1979-10-01

    Various estimates concerning the costs of decommissioning a redundant nuclear power reactor to the green fields state are given in the literature. The purpose of this study is to provide background material for the Swedish nuclear power utilities to estimate the costs and time required to dismantle an ASEA-ATOM Boiling Water Reactor. The units Oskarshamn II and Barsebeck 1, both with an installed capacity of approximately 600 MW, serve as reference plants. The time of operation before final shutdown is assumed to be 40 years. Dismantling operations are initiated one year after shutdown. When the dismantling of the plant is finished, the site is to be released for unrestricted use. The costs for dismantling and subsequent final disposal of the radioactive waste are estimated at approximately SEK 500 million (approximately US dollars 120 million) in terms of 1979 prices. The sum includes 25% contingency. The dismantling cost is equivalent to 10-15% of the installation cost of an equivalent new nuclear power plant. The exact percentage is dependent on the interest rate during the construction period. It is shown in the study that a total dismantling can be accomplished in less than five years. This report is a compilation of studies performed by ASEA-ATOM and VBB based on premises given by KBS. The reports from these studies are presented in appendices. (Auth.)

  4. Remote Fiber Laser Cutting System for Dismantling Glass Melter - 13071

    Energy Technology Data Exchange (ETDEWEB)

    Mitsui, Takashi; Miura, Noriaki [IHI Corporation, 1 Shin-Nakahara-cho, Isogo-ku, Yokohama, Kanagawa (Japan); Oowaki, Katsura; Kawaguchi, Isao [IHI Inspection and Instrumentation Co., Ltd, 1 Shin-Nakahara-cho, Isogo-ku, Yokohama, Kanagawa (Japan); Miura, Yasuhiko; Ino, Tooru [Japan Nuclear Fuel Limited, 4-108, Aza Okitsuke, Oaza Obuchi, Rokkasho-Mura, Kamikita-gun, Aomori (Japan)

    2013-07-01

    Since 2008, the equipment for dismantling the used glass melter has been developed in High-level Liquid Waste (HLW) Vitrification Facility in the Japanese Rokkasho Reprocessing Plant (RRP). Due to the high radioactivity of the glass melter, the equipment requires a fully-remote operation in the vitrification cell. The remote fiber laser cutting system was adopted as one of the major pieces of equipment. An output power of fiber laser is typically higher than other types of laser and so can provide high-cutting performance. The fiber laser can cut thick stainless steel and Inconel, which are parts of the glass melter such as casings, electrodes and nozzles. As a result, it can make the whole of the dismantling work efficiently done for a shorter period. Various conditions of the cutting test have been evaluated in the process of developing the remote fiber cutting system. In addition, the expected remote operations of the power manipulator with the laser torch have been fully verified and optimized using 3D simulations. (authors)

  5. Technical challenges for dismantlement verification

    International Nuclear Information System (INIS)

    Olinger, C.T.; Stanbro, W.D.; Johnston, R.G.; Nakhleh, C.W.; Dreicer, J.S.

    1997-01-01

    In preparation for future nuclear arms reduction treaties, including any potential successor treaties to START I and II, the authors have been examining possible methods for bilateral warhead dismantlement verification. Warhead dismantlement verification raises significant challenges in the political, legal, and technical arenas. This discussion will focus on the technical issues raised by warhead arms controls. Technical complications arise from several sources. These will be discussed under the headings of warhead authentication, chain-of-custody, dismantlement verification, non-nuclear component tracking, component monitoring, and irreversibility. The authors will discuss possible technical options to address these challenges as applied to a generic dismantlement and disposition process, in the process identifying limitations and vulnerabilities. They expect that these considerations will play a large role in any future arms reduction effort and, therefore, should be addressed in a timely fashion

  6. The promising opportunity of dismantlement

    International Nuclear Information System (INIS)

    Anon.

    2009-01-01

    Civil engineering, mechanics and waste conditioning companies are thriving around the market of nuclear facilities dismantlement which is promised to a huge development in the coming decade. This paper presents a map of the opportunities of the dismantlement market throughout Europe (research and power reactors, fuel fabrication plants, spent fuel reprocessing plants) and a cost estimation of a given dismantling work with respect to the different steps of the work. In France a small core of about twenty companies is involved in nuclear dismantlement but the French market is also looking towards foreign specialists of this activity. The British market is also targeted by the French companies but for all the actors the technological or commercial advance gained today will be determining for the future markets. (J.S.)

  7. LEP Dismantling Reaches Half-Way Stage

    CERN Multimedia

    2001-01-01

    LEP's last superconducting module leaves its home port... Just seven months into the operation, LEP dismantling is forging ahead. Two of the eight arcs which form the tunnel have already been emptied and the last of the accelerator's radiofrequency (RF) cavities has just been raised to the surface. The 160 people working on LEP dismantling have reason to feel pleased with their progress. All of the accelerator's 72 superconducting RF modules have already been brought to the surface, with the last one being extracted on 2nd May. This represents an important step in the dismantling process, as head of the project, John Poole, explains. 'This was the most delicate part of the project, because the modules are very big and they could only come out at one place', he says. The shaft at point 1.8 through which the RF cavity modules pass is 18 metres in diameter, while each module is 11.5 metres long. Some modules had to travel more than 10 kilometres to reach the shaft. ... is lifted up the PM 1.8 shaft, after a m...

  8. Dismantling of an alpha contaminated hot cell at the Marcoule Pilot Plant

    International Nuclear Information System (INIS)

    Tachon, M.

    1988-01-01

    For the remodeling of Marcoule Pilot Plant, the cell 82: old unit for plutonium solution purification by extraction, was dismantled. About 42 tons of wastes were evacuated. Some wastes wen decontaminated by mechanical means other wastes with higher residual activity were stored for subsequent processing. The operation shows that dismantling of a hot cell is possible even if incorporated in an operating plant [fr

  9. S.T.M.I.: Several years of experience in nuclear plant dismantling

    International Nuclear Information System (INIS)

    Moreau, J.C.

    1986-01-01

    Since 1977, when STMI performed its first dismantling operation, the Company appreciably improved in that field through important operations: the dismantling of the calciothermy and fluoration metal Pu preparation facility, in La Hague reprocessing plant, the dismantling of the slag treatment chain, associated to calciothermy and fluoration processes, in La Hague reprocessing plant, the cleaning of EL4 cell in Marcoule. To perform these operations, STMI's operating teams, on top of decontamination and dismantling technologies, strived to improve handling and transportation technologies, and to nuclearize many equipments. In order to increase its technical efficiency, STMI signed a cooperation agreement with TECHNICATOME company. Therefore, the union between the operational know-hows of STMI and the design experience of TECHNICATOME allow the needs of any customs facing a dismantling case to be satisfied [fr

  10. Nuclear safety training program (NSTP) for dismantling

    International Nuclear Information System (INIS)

    Cretskens, Pieter; Lenie, Koen; Mulier, Guido

    2014-01-01

    European Control Services (GDF Suez) has developed and is still developing specific training programs for the dismantling and decontamination of nuclear installations. The main topic in these programs is nuclear safety culture. We therefore do not focus on technical training but on developing the right human behavior to work in a 'safety culture' environment. The vision and techniques behind these programs have already been tested in different environments: for example the dismantling of the BN MOX Plant in Dessel (Belgium), Nuclear Safety Culture Training for Electrabel NPP Doel..., but also in the non-nuclear industry. The expertise to do so was found in combining the know-how of the Training and the Nuclear Department of ECS. In training, ECS is one of the main providers of education in risky tasks, like elevation and manipulation of charges, working in confined spaces... but it does also develop training on demand to improve safety in a certain topic. Radiation Protection is the core business in the Nuclear Department with a presence on most of the nuclear sites in Belgium. Combining these two domains in a nuclear safety training program, NSTP, is an important stage in a dismantling project due to specific contamination, technical and other risks. It increases the level of safety and leads to a harmonization of different working cultures. The modular training program makes it possible to evaluate constantly as well as in group or individually. (authors)

  11. Development of multi-functional telerobotic systems for reactor dismantlement

    International Nuclear Information System (INIS)

    Fujii, Yoshio; Usui, Hozumi; Shinohara, Yoshikuni

    1992-01-01

    This report summarizes technological features of advanced telerobotic systems for reactor dismantling application developed at the Japan Atomic Energy Research Institute. Taking into consideration the special environmental conditions in reactor dismantling, major effort was made to develop multifunctional telerobotic system of high reliability which can be used to perform various complex tasks in an unstructured environment and operated in an easy and flexible manner. The system development was carried out through constructing three systems in seccession; a light-duty and a heavy-duty system as a prototype system for engineering test in cold environment, and a demonstration system for practical on-site application to dismantling highly radioactive reactor internals of an experimental boiling water reactor JPDR (Japan Power Demonstration Reactor). Each system was equipped with one or two amphibious manipulators which can be operated in either a push-button manual, a bilateral master-slave, a teach-and-playback or a programmed control mode. Different scheme was adopted in each system at designing the manipulator, transporter and man-machine interface so as to compare their advantages and disadvantages. According to the JPDR decommissioning program, the demonstration system was successfully operated to dismantle a portion of the radioactive reactor internals of the JPDR, which used underwater plasma arc cutting method and proved the usefulness of the multi-functional telerobotic system for reducing the occupational hazards and enhancing the work efficiency in the course of dismantling highly radioactive reactor components. (author)

  12. Dismantling at the CEA's Nuclear Energy Division: strategy and programmes

    International Nuclear Information System (INIS)

    Lecomte, C.; Prunele, D. de; Rozain, J.P.; Nokhamzon, J.G.; Tallec, M.

    2008-01-01

    The CEA's Nuclear Energy Division (DEN) nuclear facilities currently include seventeen reactors and thirty six other miscellaneous facilities, particularly laboratories, fuel processing units and facilities specific to waste management. Some of these are currently being dismantled or must be dismantled soon so that the DEN, the Nuclear Energy Division, can construct new equipment and thus have available a range of R and D facilities in line with the issues of the nuclear industry of the future. At CEA, the first nuclear facility dismantling operations go back several dozen years and involve numerous and varied facilities. The first operations of any significance took place in the 1960's and 1970's and covered, for example, the first plutonium plant at Fontenay-aux-Roses (total dismantling) and small research reactors or critical models - CESAR and PEGGY at Cadarache and MINERVE at Fontenay-aux Roses (civil engineering cleaned up and kept). At La Hague, the dismantling of AT1, a pilot workshop used by the CEA during the 1970's to process irradiated fuels from fast neutron reactors, was completed in March 2001 (IAEA former stage 3, excluding civil engineering demolition). On the other hand, during this period of first dismantling, the intermediate-sized reactors (G1, Rapsodie) were only partially dismantled after shut down, mainly due to the lack of graphite and sodium waste management routes at the time. About twenty facilities were thus dealt with up to 2001, in other words about half of all the nuclear facilities shut down permanently before this date. (authors)

  13. The good wealth of dismantlement

    International Nuclear Information System (INIS)

    Maincent, G.

    2009-01-01

    Civil engineering, mechanical and waste conditioning companies are working hard on the market of nuclear facilities dismantling. This market has a great future ahead of it in the ten years to come. According to the European Commission, 50 to 60 reactors among the 157 actually in service in the European Union should be dismantled by 2025. The cost per reactor is estimated to 10-15% of the initial investment, which represents an enormous amount of money, estimated to 20-39 billion euros for the only French nuclear park. In France, this market is shared by a core of about 20 companies, like Spie Nucleaire, Onet, Vinci (Nuvia) and Areva. Some dismantling sites require a specific skill, in particular those in relation with the research activity of the CEA (the French atomic energy commission) or involving specific technologies (research reactors, spent fuel reprocessing plants, sodium-cooled rectors..). (J.S.)

  14. Qualification of a laser cutting process for nuclear dismantling operations AREVA NC BU Valorisation - CEA/DPAD - IRSN/DSU/SERAC

    International Nuclear Information System (INIS)

    2008-01-01

    A major decommissioning project is under way on the Marcoule French Atomic Site (CEA) at the UP1 reprocessing plant where AREVA plays the role of prime contractor. Due to severe radiological levels on certain cells, these require remote operations. The cutting tools commonly used today are mainly mechanical such as grinders, saws and hydraulic shears. Nowadays, the feed-back shows that the implementation of these mechanical techniques: *?Is the main factor of mechanical failures of the remote arms. *?Requires a lot of spare parts (saw blades, discs...) The future cutting operations to be done in the UP1 reprocessing plant needs to be more industrial and productive. That is why CEA and AREVA NC are evaluating a new cutting process based on a laser set up on a remote arm. The laser cutting is already widely used in none nuclear environment and the goal is to evaluate if this thermal process may be used in nuclear installations with existing remote control arms. (authors)

  15. Qualification of a laser cutting process for nuclear dismantling operations AREVA NC BU Valorisation - CEA/DPAD - IRSN/DSU/SERAC

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2008-07-01

    A major decommissioning project is under way on the Marcoule French Atomic Site (CEA) at the UP1 reprocessing plant where AREVA plays the role of prime contractor. Due to severe radiological levels on certain cells, these require remote operations. The cutting tools commonly used today are mainly mechanical such as grinders, saws and hydraulic shears. Nowadays, the feed-back shows that the implementation of these mechanical techniques: *?Is the main factor of mechanical failures of the remote arms. *?Requires a lot of spare parts (saw blades, discs...) The future cutting operations to be done in the UP1 reprocessing plant needs to be more industrial and productive. That is why CEA and AREVA NC are evaluating a new cutting process based on a laser set up on a remote arm. The laser cutting is already widely used in none nuclear environment and the goal is to evaluate if this thermal process may be used in nuclear installations with existing remote control arms. (authors)

  16. Note n. SD3-DEM-01 regulations procedures relative to the based nuclear installations dismantling

    International Nuclear Information System (INIS)

    2003-02-01

    This note aims to define the regulations procedures relative to the safety of based nuclear installations dismantling defined by the decree of the 11 december 1963 modified. The first part describes the two main phases of a based nuclear installation life, the operating and the dismantling phase. The second part is devoted to the procedures. (A.L.B.)

  17. Experience acquired by EDF in implementation of its dismantling programme

    Energy Technology Data Exchange (ETDEWEB)

    Klaeyle, S.; Dalmas, R.; Davoust, M. [EDF - Centre d' Ingenerie Deconstruction Environnement (CIDEN), 69 - Villeurbanne (France)

    2008-07-01

    EDF decided in 2001 to implement immediate dismantling of its first generation nuclear plants. Seven years after this decision, the physical progress of the programme is 24% and is due to reach 50 % by 2013. This paper presents the experiences acquired in the fields of organization, project and programme management, purchasing strategies and waste management. Until now, the principal works involve Brennilis (Heavy water), ChoozA (PWR) and Creys Malville (fast breeder reactor). The detailed pre-project concerning the first of the six gas graphite reactors is complete and the call for bids process has been launched. The organization to manage projects, established at the De-construction and Environment Engineering Center (CIDEN), is effective and productive. Estimates of costs and expenses are coherent, which makes the forecasts put together to finance the programme secure. CIDEN has carried out significant engineering work over the last six years, making it possible to apply for the administrative authorizations which have now been obtained or are in the process of being obtained. Technical specifications are prepared at an optimized level of detail according to a contractual policy adapted to the complexity of the operations and the sharing of risk with manufacturers. The ChoozA contractualization process has been launched and the first dismantling work has begun in the nuclear auxiliary part. The main Brennilis contract will be completed in mid- 2008 and dismantling works will restart after renewal of the decree which was cancelled in mid-2007. Treatment of sodium from Creys Malville is about to begin, leading to elimination of the sodium risk by 2013. The very low activity waste (TFA) and low to medium activity waste (FA-MA) removal chains are operational. The intermediate activity/long lived (MA-VL) waste will be stored in a facility which will be brought into operational service in 2012. The graphite storage center is due to open between 2017 and 2019

  18. Reforming the Interagency at the Operational Level

    National Research Council Canada - National Science Library

    Halvorsen, Peter

    2005-01-01

    The informal and ad hoc construct of the interagency process at the operational, specifically regional, level of command is insufficient to meet the changed security environment of the post-Soviet world...

  19. On the level order for Dirac operators

    International Nuclear Information System (INIS)

    Grosse, H.

    1987-01-01

    We start from the Dirac operator for the Coulomb potential and prove within first order perturbation theory that degenerate levels split in a definite way depending on the sign of the Laplacian of the perturbing potential. 9 refs. (Author)

  20. The timing of reactor dismantling

    International Nuclear Information System (INIS)

    Roberts, P.

    2000-01-01

    Work has been progressing across the world for the decommissioning of nuclear reactors. The initial work focused on the early, complete dismantling but this was associated with small size reactors and was done for experimental or demonstration purposes. The situation now is that an increasing number of full size power reactors are being shutdown and decision are being made as to the decommissioning strategy to be applied, e.g. with respect to the appropriate timing of reactor dismantling. There are two basic approaches to the timing of reactor dismantling, which are to either proceed with dismantling on an early time scale or to delay it for a period of years. There are a number of examples worldwide of both approaches being taken but one common feature of the approach taken by most countries is that decisions are made on a case by case basis, taking account of relevant factors, and as a result the strategy can vary from reactor to reactor and from country to country. Decisions on timing take account of the following main factors: safety, radioactive decay, financial factors, radioactive waste, reactor type, technology, repository availability, site re-use, regulatory standards, plant knowledge/records, other issues

  1. Technical report on dismantling of incinerator building of JNC with strict environmental assessments especially for the contamination of surroundings of incinerator by Dioxin's in soil

    International Nuclear Information System (INIS)

    Aizawa, Masanori; Ohmori, Koji; Nomura, Takeshi; Numano, Tatuo; Usui, Kazuya; Irinouchi, Shigenori

    2003-03-01

    Building of incinerator for general waste located at Tokai of Japan Nuclear Cycle Development Institute (JNC in short) were dismantled form April 2002 to March 2003 under environmental control According to the regulation entitled 'Outline for the prevention of exposure of Dioxin's to operators engaged in dismantling of waste incinerator' issued on June 01, 2000 by Ministry of Health, Labor and Welfare in Japan, the regulation requests proper protection methodology to dismantling the incinerator and surroundings contaminated by Dioxin's. This report consists of Environmental assessment under Japanese law and regulations and Procedure of actual dismantling of incinerator building with law-abiding stand point. 1. Environmental assessment; Survey of several laws and regulations concerning on the Dioxin's and actual site assessment to analyze the content of Dioxin's for surroundings of incinerator building. Ground design of dismantling procedures, waste management for disposed during dismantling and scheduling for dismantling of building. 2. Dismantling procedures; Prior to dismantling operation, contamination map by Dioxin's were established then restricted areas were determined. Protection methodology to dioxin's exposure for operators were selected and started dismantling operation after getting permission from the Labor Standards Bureau of Ibaraki Prefecture. Dismantling operations were carried out with respect o above mentioned regulations to prevent the operators exposure to Dioxin's if they are exists in soil or surroundings of building. Finally, dismantling operations were completed without accidents and confirmed no-exposure of Dioxin's to operators of dismantling. Waste generated during dismantling were recycled using specialized recycling companies in Ibaraki prefecture. Dismantling operation of incinerator was first experience at Ibaraki Prefecture, so the officials of Labor Standards Bureau were carried out on-the-spot inspection and have no claim from

  2. Dismantling and waste managing benefit from digital technologies

    International Nuclear Information System (INIS)

    Moitrier, C.

    2017-01-01

    Dismantling is a very important challenge for nuclear industry as its success will prove the ability of the industry to deal with all the stages of a nuclear power plant from design to the end. A dismantling project is constraint by costs, time, feasibility, safety and environment protection and all of this implies a perfect knowledge of both the initial state of the facility at the beginning of the dismantling and the supply chain to avoid delays and extra-costs. Digital tools have a very important role to play as a provider of a 3-dimensional digital twin of the facility. This digital model allows: a remote preparation of the dismantling actions, to assess and optimize the radiation exposure during the intervention, to simulate various scenarios and select the most adequate, to ease collaborative work between various teams, to assess the volume and kind of waste at a very early stage of the dismantling, and to train operators and workers for x. (A.C.)

  3. Experience of partial dismantling and large component removal of light water reactors

    International Nuclear Information System (INIS)

    Dubourg, M.

    1987-01-01

    Not any of the French PWR reactors need to be decommissioned before the next decade or early 2000. However, feasibility studies of decommissioning have been undertaken and several dismantling scenarios have been considered including the dismantling of four PWR units and the on-site entombment of the active components into a reactor building for interim disposal. In addition to theoretical evaluation of radwaste volume and activity, several operations of partial dismantling of active components and decontamination activities have been conducted in view of dismantling for both PWR and BWR units. By analyzing the concept of both 900 and 1300 MWe PWR's, it appears that the design improvements taken into account for reducing occupational dose exposure of maintenance personnel and the development of automated tools for performing maintenance and repairs of major components, contribute to facilitate future dismantling and decommissioning operations

  4. Decision support system for the dismantling of building in nuclear facilities

    International Nuclear Information System (INIS)

    Zeiher, M.

    2009-01-01

    In case of decommissioning and dismantling the complex structure of nuclear facilities requires a thorough selection of dismantling methods and a detailed operations planning. The decision for an appropriate technology with respect to economic, environmental and radiation protection aspects has to take into account that the different procedural steps are coordinated. Component specific boundary conditions and process parameters have to be considered. A data base was established that includes the process parameters for different dismantling methodologies. The next step is the determination of specific requirements of plant operators and engineers in order to identify the tasks in the frame of the dismantling process. The authors describes the decision support algorithm that allows to enhance the dismantling efficiency.

  5. Mock-up test of remote controlled dismantling apparatus for large-sized vessels (contract research)

    Energy Technology Data Exchange (ETDEWEB)

    Myodo, Masato; Miyajima, Kazutoshi [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment; Okane, Shogo [Japan Atomic Energy Research Inst., Oarai, Ibaraki (Japan). Oarai Research Establishment

    2001-03-01

    The Remote dismantling apparatus, which is equipped with multi-units for functioning of washing, cutting, collection of cut pieces and so on, has been constructed to dismantle the large-sized vessels in the JAERI's Reprocessing Test Facility (JRTF). The apparatus has five-axis movement capability and its operation is performed remotely. The mock-up tests were performed to evaluate the applicability of the apparatus to actual dismantling activities by using the mock-ups of LV-3 and LV-5 in the facility. It was confirmed that each unit was satisfactory functioned by remote operation. Efficient procedures for dismantling the large-sized vessel was studied and various date was obtained in the mock-up tests. This apparatus was found to be applicable for the actual dismantling activity in JRTF. (author)

  6. Mock-up test of remote controlled dismantling apparatus for large-sized vessels (contract research)

    International Nuclear Information System (INIS)

    Myodo, Masato; Miyajima, Kazutoshi; Okane, Shogo

    2001-03-01

    The Remote dismantling apparatus, which is equipped with multi-units for functioning of washing, cutting, collection of cut pieces and so on, has been constructed to dismantle the large-sized vessels in the JAERI's Reprocessing Test Facility (JRTF). The apparatus has five-axis movement capability and its operation is performed remotely. The mock-up tests were performed to evaluate the applicability of the apparatus to actual dismantling activities by using the mock-ups of LV-3 and LV-5 in the facility. It was confirmed that each unit was satisfactory functioned by remote operation. Efficient procedures for dismantling the large-sized vessel was studied and various date was obtained in the mock-up tests. This apparatus was found to be applicable for the actual dismantling activity in JRTF. (author)

  7. Development of telerobotic manipulators for reactor dismantling work

    International Nuclear Information System (INIS)

    Shinohara, Yoshikuni; Usui, Hozumi; Fujii, Yoshio

    1991-01-01

    This paper describes the amphibious electrical manipulators JARM-10, JART-25, JART-100 and JARM-25 which were developed in the program of reactor decommissioning technology development carried out by the Japan Atomic Energy Research Institute. They are multi-functional telerobotic light-duty (10 and 25 daN) and heavy-duty (100 daN) Manipulators which can be used in hostile environments in reactor dismantling work such as high radiation, underwater work and electrical noise. Each manipulator can be operated in either a bilateral master-slave, a teach-and-playback or a programmed control mode. By combining these modes appropriately, it is possible to perform complex tasks of remote handling. The usefulness of the telerobotic systems for dismantling nuclear reactors has been demonstrated by successful application of the JARM-25 for remote underwater dismantlement of highly radioactive reactor internals of complex form of an experimental nuclear power reactor. (author)

  8. Provisions for the dismantling of nuclear facilities are sufficient

    International Nuclear Information System (INIS)

    Le Ngoc, B.

    2016-01-01

    The European Union has assessed the provisions made by the nuclear plant operators to face the future costs of dismantling. The United-Kingdom and the Netherlands are the single E.U. members to have provisions covering the whole of the expenses (respectively 100% and 94%). The figure for France is very low 33% (far below the European average of 56%). According to French authorities the provisions for the dismantling of nuclear facilities are strictly defined by law: they must be made progressively till the decommissioning and they must be composed by dedicated assets. The costs of the dismantling is regularly re-assessed for taking into account technological progress and changes in regulation. Furthermore the French system limits the period in which provisions are made to the initial operating life of the plant: mostly 40 years which is a prudent measure. In other E.U. members like Germany, the provisions are not covered by dedicated assets which might endanger the capacity of the operator to face the future costs. The progressiveness of the French systems of provision-making is fair because the dismantling costs are spread equally over the entire operating period of the facility. (A.C.)

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

    International Nuclear Information System (INIS)

    Asazuma, Shinichiroh; Takeda, Shinsoh; Tajima, Shoichi

    2004-11-01

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

  10. Cutting Method of the CAD model of the Nuclear facility for Dismantling Simulation

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Ikjune; Choi, ByungSeon; Hyun, Dongjun; Jeong, KwanSeong; Kim, GeunHo; Lee, Jonghwan [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2015-05-15

    Current methods for process simulation cannot simulate the cutting operation flexibly. As is, to simulate a cutting operation, user needs to prepare the result models of cutting operation based on pre-define cutting path, depth and thickness with respect to a dismantle scenario in advance. And those preparations should be built again as scenario changes. To be, user can change parameters and scenarios dynamically within a simulation configuration process so that the user saves time and efforts to simulate cutting operations. This study presents the methodology of cutting operation which can be applied to all the procedure in the simulation of dismantling of nuclear facilities. We developed the cutting simulation module for cutting operation in the dismantling of the nuclear facilities based on proposed cutting methodology. We defined the requirement of model cutting methodology based on the requirement of the dismantling of nuclear facilities. And we implemented cutting simulation module based on API of the commercial CAD system.

  11. Development of an augmented reality based simulation system for cooperative plant dismantling work

    International Nuclear Information System (INIS)

    Ishii, Hirotake; Man, Zhiyuan; Yan, Weida; Shimoda, Hiroshi; Izumi, Masanori

    2015-01-01

    An augmented reality-based simulation system for cooperative plant dismantling work has been developed and evaluated. In the system, behaviors of virtual objects such as the dismantling target, chain blocks, and trolleys are physically simulated. Their appearance is superimposed on camera images captured with cameras on users' tablet devices. The users can manipulate virtual objects cooperatively via touch operation. They can cut the dismantling targets, lift them on the trolleys using chain blocks, and convey them through narrow passages to ascertain whether the dismantling targets can be conducted without colliding with the passages. During the simulation, collisions between the virtual objects and real work environment are detected based on their three-dimensional shape data measured in advance. The collided parts are visualized using augmented reality superimposition. Four evaluators assessed the simulation system. Results show that the simulation system can be useful for prior examination of dismantling works, but some points were also found to need improvement. (author)

  12. Chooz A: a model for the dismantling of water-cooled reactors

    International Nuclear Information System (INIS)

    Anon.

    2017-01-01

    The specificity of Chooz-A, the first French pressurized water reactor (PWR), is that the reactor and its major components (pumps, exchangers and cooling circuits) are installed in 2 caves dug out in a hill slope. Chooz-A was operating from 1967 to 1991, in 1993 the fuel was removed and in 2007 EDF received the authorization to dismantle the reactor. In 2012, EDF completed the dismantling of the cave containing the elements of the cooling circuit, a cornerstone was the removing of the four 14 m high steam generators. The dismantling of the pressure vessel began in march 2017, it is the same tools and the same processes that were used for the dismantling of the pressure vessel of the Zorita plant (Spain) in 2016. The end of the Chooz-A dismantling is expected in 2022. The feedback experience will help to standardize practices for the French fleet of PWRs. (A.C.)

  13. Method of dismantling cylindrical structure by cutting

    International Nuclear Information System (INIS)

    Harada, Minoru; Mitsuo, Kohei; Yokota, Isoya; Nakamura, Kenjiro.

    1989-01-01

    This invention concerns a method of cutting and removing cylindrical structures, for example, iron-reinforced concrete materials such as thermal shielding walls in BWR type power plants into block-like form. That is, in a method of cutting and removing the cylindrical structure from the side of the outer wall, the structural material is cut from above to below successively in the axial direction and the circumferential direction by means abrasive jet by remote operation and cut into blocks each of a predetermined size. The cut out blocks are successively taken out. Cutting of the material from above to below by remote operation and taking out of small blocks causes no hazards to human body. Upon practicing the present invention, it is preferred to use a processing device for slurry and exhaust gases for preventing scattering of activated dismantled pieces or powdery dusts. (K.M.)

  14. The Rossendorf research reactor. Operating and dismantling from a point of view of the emission control; Der Rossendorfer Forschungsreaktor. Betrieb und Rueckbau aus Sicht der Emissionsueberwachung

    Energy Technology Data Exchange (ETDEWEB)

    Bauer, B.; Beutmann, A.; Kaden, M.; Scheibke, J. [VKTA, Dresden (Germany); Boessert, W.; Jansen, K.; Walter, M.

    2016-07-01

    The Rossendorf research reactor went in operation in 1957 as GDR's first nuclear reactor and Germanys second after FRM Garching. It was a heterogeneously structured, light-water moderated and cooled tank-reactor of the Soviet type WWR-S. During his time of operation, he served both the research and the production of radioisotopes. The history of exhaust air emission monitoring and its results are presented. With view to the decommissioning time selected results are discussed. The estimated discharges are compared by the actually recognized.

  15. Scientific Explanations and Piagetian Operational Levels.

    Science.gov (United States)

    Bass, Joel E.; Maddux, Cleborne D.

    1982-01-01

    Examined effects of operational levels of ninth-grade (N=16) and college (N=40) students on causal explanations they recalled after instruction. Results indicate concrete/formal students recalled explanations requiring chaining of two implication statements while formal subjects outperformed concrete subjects in reconstruction of complex…

  16. The market of nuclear plant dismantling. The new EDF's strategy, process standardisation, robotization: which perspectives for the market by 2030?

    International Nuclear Information System (INIS)

    2017-09-01

    Dismantling appears as the most promising activity in the nuclear sector due to ageing plants, to ambitious objectives of reduction of the nuclear share in the energy mix, or to high expertise of French companies in robotic and digital solutions for deconstruction in radioactive environments. However, the development of the dismantling market depends on EDF decisions: the extension of nuclear reactor lifetime postpones the development of this market. In this context, this study aims at giving an anticipated view of the plant dismantling market by 2030, at deciphering growth levers for the sector actors, and at understanding the sector operation and the business model of operators. Thus, the report presents the main components of the market (key figures, dismantling types, dismantling steps, sector ecosystem, barriers to enter the market, costs, contractual relationships), proposes an analysis of the market and of its perspectives (situation in France, and at the world level, predictive scenario for 2030), and discusses the development axes and demand evolutions (robotization and digitalisation, elaboration of standardised processes, management of wastes produced by nuclear dismantling, internationalisation of French actors). It also proposes an overview of actors in France, and identity sheets for commissioners (EDF, New Areva), contractors (Onet, Vinci, Engie), and other actors (Veolia, Assystem, Ortec, Cybernetix, Oreka Group). The last part proposes synthetic sheets for more than 110 companies of the sector (general information, management and financial performance data under the form of tables and figures) and comparative tables according to 5 key indicators. Data are presented for a period ranging from 2010 to 2016

  17. Experience of the remote dismantling of the Windscale advanced gas-cooled reactor and Windscale pile chimneys

    International Nuclear Information System (INIS)

    Wright, E.M.

    1993-01-01

    This paper gives brief descriptions of some of the remote dismantling work and equipment used on two large decommissioning projects: the BNFL Windscale Pile Chimneys Project (remote handling machine, waste packaging machine, remotely controlled excavator, remotely controlled demolition machine) and the AEA Windscale Advanced Gas-cooled Reactor Project (remote dismantling machine, operational waste, bulk removal techniques, semi-remote cutting operations)

  18. EDF decommissioning and dismantling policy a global commitment to safety, environment and cost efficiency of nuclear energy

    International Nuclear Information System (INIS)

    Rondeau, J.

    2001-01-01

    Until recently, EDF's policy regarding the dismantling of its decommissioned nuclear power plants was to reach 'level 2' (release of non-nuclear facilities) and to postpone final dismantling for another 30-40 years. Today, some studies suggest that a full deconstruction program of the first generation NPPs (9 units) could be optimized over the period 2000 - 2025. EDF has acquired during the last ten years an unique experience, both as an operator and as an engineering company, in the frame of the decommissioning programme of its own NPPs. Many types of reactors, including graphite moderated one, PWR, are at varying stages of the dismantling process.Plant operation quality is at the core of a satisfactory control of releases. Over the last decade, as a result of the efforts of all operating sites associated with good in-house operating practice feedback, the overall release volume has been divided by two, and the release activity by one hundred. Another issue given increased attention is radiological cleanliness. EDF-DPN launched a 'radiological cleanliness' action plan revolving around two main themes: increased monitoring of nuclear-related transportations, site entrance and access to controlled areas, along with on-site radiological cleanliness, particularly during maintenance work tasks. Progress is already apparent in several points at issue and the overall objective of the action plan should be attained. (author)

  19. Features of rotary pump diagnostics without dismantling

    Directory of Open Access Journals (Sweden)

    Sergeev K. О.

    2017-12-01

    Full Text Available In ship power plants, rotor pumps have become very popular providing the transfer of various viscous fluids: fuels, oils, etc. Like all ship's mechanisms, pumps need proper maintenance and monitoring of technical condition. The most expedient is maintenance and repair carried out according to the results of dismantling diagnosis. The methods of vibrodiagnostics are mostly widespread for the diagnosis of pumps. Vibrodiagnosis of rotary pumps has a number of features due to the nature and condition of pumped fluids. The norms of the Russian Maritime Register of Shipping are used for setting standards of vibration and diagnostics of the rotary pumps' technical condition. To clarify the features of vibration diagnostics of rotary pumps some measurements have been made on a special bench that simulates various modes of ship's pumps' operation: different pressure in the system and temperature of the pumped medium. As a result of measurements one-third octave and narrow-band vibration spectra of pumps have been obtained at various developed pressures and temperatures of the pumped fluid. The performed analysis has shown that the RMRS norms for diagnostics of ship rotary pumps have insufficient informative value inasmuch they do not take into account the dependence of the vibrational signal spectrum on the developed pressure and temperature of the pumped fluid. The nature of the received signals shows that the levels of a third-octave spectrum of the vibration velocity depend significantly on the temperature of the pumped fluids, this fact must be taken into account when applying the RMRS norms. The fluid temperature has a great influence on the nature of the narrow-band vibration acceleration spectrum in the area of medium frequencies, less influence – on the nature of the vibration velocity spectrum. The conclusions have been drawn about the advisability of using the narrow-band vibration spectra and the envelope spectra of the high

  20. Decommissioning and Dismantling of the Floating Maintenance Base 'Lepse' - 13316

    International Nuclear Information System (INIS)

    Field, D.; Mizen, K.

    2013-01-01

    The Lepse was built in Russia in 1934 and commissioned as a dry cargo ship. In 1961 she was re-equipped for use as a nuclear service ship (NSS), specifically a floating maintenance base (FMB), to support the operation of the civilian nuclear fleet (ice-breakers) of the USSR. In 1988 Lepse was taken out of service and in 1990 she was re-classified as a 'berth connected ship', located at a berth near the port of Murmansk under the ownership of Federal State Unitary Enterprise (FSUE) Atomflot. Lepse has special storage facilities for spent nuclear fuel assemblies (SFA) that have been used to store several hundred SFAs for nearly 40 years. High and intermediate-level liquid radioactive waste (LRW) is also present in the spent nuclear fuel assembly storage channels, in special tanks and also in the SFA cooling circuit. Many of the SFAs stored in Lepse are classified as damaged and cannot be removed using standard procedures. The removal of the SFA and LRW from the Lepse storage facilities is a hazardous task and requires specially designed tools, equipment and an infrastructure in which these can be deployed safely. Lepse is a significant environmental hazard in the North West of Russia. Storing spent nuclear fuel and high-level liquid radioactive waste on board Lepse in the current conditions is not acceptable with respect to Russian Federation health, safety and environmental standards and with international best practice. The approved concept design for the removal of the SFA and LRW and dismantling of Lepse requires that the ship be transported to Nerpa shipyard where specialist infrastructure will be constructed and equipment installed. One of the main complexities of the Project lies within the number of interested stakeholders involved in the Project. The Lepse project has been high focus on the international stage for many years with previous international efforts failing to make significant progress towards the objective of decommissioning Lepse. The Northern

  1. Chooz A, First Pressurized Water Reactor to be Dismantled in France - 13445

    Energy Technology Data Exchange (ETDEWEB)

    Boucau, Joseph [Westinghouse Electric Company, 43 rue de l' Industrie, Nivelles (Belgium); Mirabella, C. [Westinghouse Electric France, Orsay (France); Nilsson, Lennart [Westinghouse Electric Sweden, Vaesteraas (Sweden); Kreitman, Paul J. [Westinghouse Electric Company, Lake Bluff, IL 60048 (United States); Obert, Estelle [EDF - DPI - CIDEN, Lyon (France)

    2013-07-01

    Nine commercial nuclear power plants have been permanently shut down in France to date, of which the Chooz A plant underwent an extensive decommissioning and dismantling program. Chooz Nuclear Power Station is located in the municipality of Chooz, Ardennes region, in the northeast part of France. Chooz B1 and B2 are 1,500 megawatt electric (MWe) pressurized water reactors (PWRs) currently in operation. Chooz A, a 305 MWe PWR implanted in two caves within a hill, began operations in 1967 and closed in 1991, and will now become the first PWR in France to be fully dismantled. EDF CIDEN (Engineering Center for Dismantling and Environment) has awarded Westinghouse a contract for the dismantling of its Chooz A reactor vessel (RV). The project began in January 2010. Westinghouse is leading the project in a consortium with Nuvia France. The project scope includes overall project management, conditioning of the reactor vessel (RV) head, RV and RV internals segmentation, reactor nozzle cutting for lifting the RV out of the pit and seal it afterwards, dismantling of the RV thermal insulation, ALARA (As Low As Reasonably Achievable) forecast to ensure acceptable doses for the personnel, complementary vacuum cleaner to catch the chips during the segmentation work, needs and facilities, waste characterization and packaging, civil work modifications, licensing documentation. The RV and RV internals will be segmented based on the mechanical cutting technology that Westinghouse applied successfully for more than 13 years. The segmentation activities cover the cutting and packaging plan, tooling design and qualification, personnel training and site implementation. Since Chooz A is located inside two caves, the project will involve waste transportation from the reactor cave through long galleries to the waste buffer area. The project will end after the entire dismantling work is completed, and the waste storage is outside the caves and ready to be shipped either to the ANDRA (French

  2. Dismantling of the rooms 82 to 100 at Marcoule

    International Nuclear Information System (INIS)

    Fiol, A.

    1988-01-01

    The dismantling of the rooms 82 to 100 at Marcoule is up to now, the most important decommissioning operation. The COGEMA Marcoule had the responsibility of studying and organizing the operation. On the works site the work was performed by STMI. The construction of a complete nuclear waste processing system was necessary, to protect against Pu contamination. Moreover, the efficiency of the work, was improved by the development and use of large special cutting tools [fr

  3. Prefiltration of gaseous effluents in plant dismantling

    International Nuclear Information System (INIS)

    Pilot, G.; Pourprix, M.

    1991-01-01

    The dismantling techniques and mainly the thermal cutting tools can create large amounts of airbone dust, possibly contaminated in the case of the cutting of radioactive materials. Among the secondary solid emissions, the aerosols constitute the most mobile part which can disseminate contamination in the cell where the cutting operation takes place and in the ventilation ducts up to the HEPA filters. An optimised prefiltration coupled with a captation device at the aerosol generating source allows to avoid the dissemination of the contamination, to increase the life of HEPA filters and thus to reduce the amount of solid wastes. The object in this work was to select one or several cleaning devices, selection that can be done from the knowledge of the physico-chemical characteristics of the gas and aerosols to deal with, the available cleaning devices and the implied facility

  4. Decree no. 2004-48 from January 12, 2004 authorizing the French atomic energy commission to proceed to the definitive decommissioning and dismantling operations of the nuclear facility no. 43, named Saclay linear accelerator (ALS), on the territory of Saint-Aubin town (Essonne)

    International Nuclear Information System (INIS)

    2004-01-01

    The linear accelerator of Saclay (ALS) has been the object of a commissioning permission given by decree by the French prime minister in October 8, 1965. It is submitted to the regime of basic nuclear facilities as defined in the decree no. 63-1228 from December 11, 1963. The French atomic energy commission (CEA) put down a request for the definitive decommissioning and dismantling of this facility on May 30, 2002. The duration foreseen for these operations is of 4 years. After the safety examination of the request by the DGSNR and the institute of radioprotection and nuclear safety (IRSN), a favorable and conformable advice has been given by the different ministries (health, finances and industry, ecology and sustainable development) and has led to this decree which precises the different protection measures to be implemented during the dismantling work. (J.S.)

  5. Shutdown, dismantling and decommissioning of nuclear facilities in France - Guide no. 6 - Update of 30/08/2016

    International Nuclear Information System (INIS)

    2016-01-01

    After a recall of the regulatory context and references, this guide addresses the strategy for an immediate dismantling of an installation, the dismantling planning, the different phases of the end of life of nuclear base installations, the authorization of definitive stop and dismantling, the preliminary phase preparing the definitive stop (regulatory context, technical aspects), the dismantling phase (regulatory context, technical aspects for the concerned operations, the security functions, hardware important for security, taking ageing into account), and the final status of installations (downgrading, constraints)

  6. Dismantling of JPDR begins: to demonstrate advanced technology

    Energy Technology Data Exchange (ETDEWEB)

    1986-12-01

    The first dismantling of the Japan Power Demonstration Reactor (JPDR, BWR, 90 MWt, 12.5 MWe) began on December 4, 1986, claiming the attention of nuclear interests in Japan and overseas. The Japan Atomic Energy Research Institute undertook the project as the second phase of the six year program for dismantling the JPDR at the Tokai Research Establishment. It is the demonstration of the technology developed in the first phase of the program from 1981 to 1986, aiming at establishing a total system for dismantling commercial nuclear power plants in the furture. At the ceremony for the beginning of dismantling held on December 4 at the site, a special switch was operated to fire a gas burner, and cutting of the upper head of the reactor pressure vessel on the service floor of the reactor building began. The long term program on the development and utilization of nuclear energy in 1982 decided the basic policy on reactor decommissioning. Under this policy, in July, 1984, the nuclear subcommittee of the Advisory Committee for Energy set up the guideline for standardized decommissioning suitable to the actual situation in Japan. The schedule of the program, the development of eight fundamental techniques, disassembling techniques, decontamination, measurement and robotics are described. (Kako, I.).

  7. Decontamination and dismantling of large plutonium-contamined glove boxes

    International Nuclear Information System (INIS)

    Draulans, J.

    1991-01-01

    This report describes the work performed in the frame of two C.E.C. - Contracts FI1D-002400-B Decommissioning of very large glove boxes and FI1D-0058 Decommissioning of a complex glove box structure to be dismounted partially on place. Detailed information is given about each glove box. The selection of the solution Transportation of the glove boxes to a specialized dismantling plant is justified. The necessary contacts inside the BELGONUCLEAIRE MOX plant and between the latter and other organizations are explained. The problems of manipulating large gloves are listed and the retained solution of building a so called Stiffening frame around each glove box is described. Furthermore information is given concerning required operators time for cleaning, manipulating, packing and dismantling together with received doses and quantities of waste produced. Concerning the glove box unit partially to be dismounted on place, detailed information is given about the way the glove boxes have been treated prior to this partial dismantling on place and about the way this partial dismantling has been performed. From these results one can conclude that such a delicate task can be performed without major difficulties. Finally information is given of the decontamination test of a highly Pu contaminated glove box with freon with rather poor results and of the preliminary CO 2 blasting tests on non active samples

  8. Current conserving theory at the operator level

    Science.gov (United States)

    Yuan, Jiangtao; Wang, Yin; Wang, Jian

    The basic assumption of quantum transport in mesoscopic systems is that the total charge inside the scattering region is zero. This means that the potential deep inside reservoirs is effectively screened and therefore the electric field at interface of scattering region is zero. Thus the current conservation condition can be satisfied automatically which is an important condition in mesoscopic transport. So far the current conserving ac theory is well developed by considering the displacement current which is due to Coulomb interaction if we just focus on the average current. However, the frequency dependent shot noise does not satisfy the conservation condition since we do not consider the current conservation at the operator level. In this work, we formulate a generalized current conserving theory at the operator level using non-equilibrium Green's function theory which could be applied to both average current and frequency dependent shot noise. A displacement operator is derived for the first time so that the frequency dependent correlation of displacement currents could be investigated. Moreover, the equilibrium shot noise is investigated and a generalized fluctuation-dissipation relationship is presented.

  9. Experience in the decontamination and dismantling of alpha facilities

    International Nuclear Information System (INIS)

    Charamathieu, A.

    1988-01-01

    Experience in dismantling alpha-containing radiochemical installations in France is described. The dismantling programme undertaken by the Societe des Techniques en Milieu Ionisant since 1977 is tabulated. This includes the dismantling of CALCIO and FLUO (plutonium metal), the dismantling of a slag processing plant, the dismantling of part of a medium activity plutonium mine and the dismantling of rooms 82-100 at Marcoule, France. (author)

  10. Clearance of radioactive materials during reactor dismantling. Permanent enclosure instead of demolition and renaturation?

    International Nuclear Information System (INIS)

    2016-01-01

    During reactor dismantling besides high-level radioactive wastes a large amount of low-level contaminated steel and concrete has to be disposed. In case that radioactivity falls below defined dose limits (10 micro Sv/person and year) these materials may be disposed in domestic waste landfill or in municipal incineration facilities. The issue is discussed in detail including the fact that many power plants are dismantled at the same time so that the contaminated materials might accumulate. Another issue is the occupational safety of contract workers during dismantling. The permanent enclosure could avoid this environmental contamination of decommissioned power plants might also be less expensive.

  11. Radiation protection procedures for the dismantling and decontamination of nuclear facility

    International Nuclear Information System (INIS)

    Almeida, C.C.; Garcia, R.H.L.; Cambises, P.B.S.; Silva, T.M. da; Paiva, J.E.; Carneiro, J.C.G.G.; Rodrigues, D.L.

    2013-01-01

    This work presents the operational procedures and conditions to ensure the required level of protection and safety during the dismantling and decontamination of a natural uranium purification facility at IPEN-CNEN/SP, Brazil. The facility was designed for chemical processing of natural uranium, aiming to obtain the uranyl nitrate, nuclear-grade. Afterwards, the installation operated in treatment and washing of thorium sulfate and thorium oxycarbonate dissolution, to get thorium nitrate as final product. A global evaluation of the potential exposure situation was carried out by radioprotection team in order to carry out the operations planned. For the facility dismantling, was established both measures to control the radiation exposure at workplace and individual monitoring of workers. A combination of physical, chemical and mechanical methods was used in the decontamination procedure applied in this unit. Concerning the internal operation procedures of IPEN-CNEN/SP, the radioactive waste control, the transport of the radioactive materials and authorization of use of decontaminated equipment were also subject of study. (author)

  12. Decontamination and dismantling at the CEA

    International Nuclear Information System (INIS)

    2006-01-01

    This document presents the dismantling policy at the CEA (French Research Center on the atomic energy), the financing of the decontamination and the dismantling, the regulatory framework, the knowledge and the technology developed at the CEA, the radiation protection, the environment monitoring and the installations. (A.L.B.)

  13. Dismantling and decommissioning of Jose Cabrera nuclear power plant

    International Nuclear Information System (INIS)

    Rodriguez, A.

    2009-01-01

    With the start of the dismantling works at the Jose Cabrera nuclear power plant now in sight, this is an appropriate moment to look back and consider recent history. The first time that the issue of nuclear power plant dismantling was dealt with was in 1975, at a conference in Paris entitled Nuclear Energy Maturity. Up until then the entire question had been one of design, construction and operation, but since that moment and it has been quite a while since that conference dismantling has begun to be seen as just another activity in the nuclear cycle, a final activity that will sooner or later affect all the facilities, an activity different from its predecessors and with the ultimate objective of restoring the sites for whatever use might be determined. During the 1960s and 1970s, the construction of nuclear power plants was widespread across the entire world. It was the baby boom of nuclear energy and now, forty or fifty years later, we are seeing the arrival of the end of the service lifetime of these plants and are faced with the corresponding general process of dismantling these installations. The dismantling of nuclear power plants has ceased to be an emerging issue and is now consolidated as a regular activity in the nuclear industry, albeit an activity that lacks adequate financing or specific regulation in certain countries. Fortunately this is not the case in Spain, since economic provisions have been planned and the regulatory framework developed. In view of the above, the dismantling of the nuclear power plants is an industrial activity involving specific technologies that implies new professional and business opportunities that should be absorbed and seized by society. In Spain the path followed in this direction has been a long one, as is underlined by the experiences of dismantling the Argos (Barcelona, 1998- 2004) and Arbi (Bilbao, 2002-2005) research reactors, the Andujar Uranium Mill (Jaen, 1991-1995), the Vandellos I nuclear power plant

  14. Waste management concept during dismantling of KKS NPP in Germany

    International Nuclear Information System (INIS)

    Bacmeister, Georg U.

    2008-01-01

    Full text: This paper gives an overview on the waste management of NPP Stade during dismantling. The general idea is to reduce the radioactive waste to about three percentage of the complete dismantling mass. The NPP Stade in Germany was shut down in November 2003. After a transient phase the license for dismantling was given in 2005. In the following 8 years about 20.000 tones of steel and 120.000 tones of concrete will be put out by the dismantling. The yearly output of steel will by about 100 times higher than during the running time of the NNP. For this a new processes for waste management had to be installed. The waste management during dismantling focus on free release (about 97%). Beside some minor exception, the rest is deemed to be radioactive waste. This will be collected in 1000 packages, which are ready to be sent to a final storage. As until now in Germany no final storage is open (and sending of radioactive waste to another country is forbidden), the NNP Stade build an intermediate storage, where the packages may by saved for longest 40 years. The clearance procedure in Germany is regulated in the radiation protection ordinances. It is based on a nuclide specific set of clearance levels. To fulfil these demands the NNP Stade chose a semi automated system for characterization and documentation, which we develop in accordance to our release license. It guaranties a most accurate determination of the relevant nuclides for a set of dismantling material (some 10 to 100 tones). After the characterization only the gamma-activity of the material is measured in boxes of about 500 kg. A short comparison of the chosen procedure with other options, possible in Germany will be given and the decision from the collaboration with the NPP in Barsebaeck, Sweden, will be withdrawn. Beside the free release different options are used for waste management, like incineration, sending to landfill or reuse in nuclear industry. The waste management of the NNP Stade take

  15. System approach as a tool for optimization of the dismantling technological process of NPP decommissioning

    International Nuclear Information System (INIS)

    Bylkin, B.K.; Shpitser, V.Ya.

    1994-01-01

    The concept of NPP unit decommissioning has been considered. Special attention was paid to the stage of dismantling of NPP unit equipment. Employment of systematic approach as a tool for optimization of dismantling processes permits formalizing manipulations with certified indices of quality and it permits an objective assessment of the dismantling technology level attained during designing as compared with the basic one. It seems appropriate to develop a basic project of NPP unit decommissioning as a technical means of planning, predicting and evaluating ecological and social aftereffects

  16. Proposed radiation hardened mobile vehicle for Chernobyl dismantlement and nuclear accident response

    International Nuclear Information System (INIS)

    Rowland, M.S.; Holliday, M.A.; Karpachov, J.A.

    1995-01-01

    Researchers are developing a radiation hardened, Telerobotic Dismantling System (TDS) to remediate the Chernobyl facility. To withstand the severe radiation fields, the robotic system, will rely on electrical motors, actuators, and relays proven in the Chernobyl power station. Due to its dust suppression characteristics and ability to cut arbitrary materials the authors propose using a water knife as the principle tool to slice up the large fuel containing masses. The front end of the robot will use a minimum number of moving parts by locating most of the susceptible and bulky components outside the work area. Hardened and shielded video cameras will be designed for remote control and viewing of the robotic functions. Operators will supervise and control robot movements based on feedback from a suite of sensory systems that would include vision systems, radiation detection and measurement systems and force reflection systems. A gripper will be instrumented with a variety of sensors (e.g. force, torque, or tactile), allowing varying debris surface properties to be grasped. The gripper will allow the operator to manipulate and segregate debris items without entering the radiologically and physically dangerous dismantlement operations area. The robots will initially size reduce the FCM's to reduce the primary sources of the airborne radionuclides. The robot will then remove the high level waste for packaging or decontamination, and storage nearby

  17. The nuclear installations dismantling and the management of radioactive wastes; Le demantelement des installations nucleaires et la gestion des dechets radioactifs

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2005-01-15

    As other industrial activities, the nuclear industry causes risks. The risks bound to the dismantling operations are known and controlled. After a presentation of the dismantling and radioactive wastes challenge, this document proposes recommendations based on the first experiences of dismantling and wastes storage. It aims then to answer to the questions relative to the cost and the financing of the operations. Finally it wonders on the public information modalities. (A.L.B.)

  18. Decontamination of the HFR dismantling cell

    International Nuclear Information System (INIS)

    Cloes, K.; Husmann, K.; Hardt, P. von der.

    1976-05-01

    The Commission of the European Communities operates in the Petten Establishment of the Joint Research Centre (EURATOM), a 45 MW light-water cooled materials testing reactor, the HFR. Inside the reactor containment building, on top of a side wing of the main pool, a hot cell had been constructed for the dismantling, of irradiated equipment, and brought into active service in July 1966. Early in 1973, the cell was contaminated by 0.1 to 1 Ci of Po 210 , originating from an irradiation capsule containing Bi impregnated graphite specimens. Due to the elevated radiotoxicity of this isotope, and to numerous potential ways of spreading out the contamination it was decided to stop routine operation of the cell until a satisfactory degree of decontamination had been reached. Two years have been spent for preparation of specialized equipment and thorough clean-up and overhaul work of the cell. It went back into normal operation on February 21st, 1975 and has since then been working very successfully

  19. Decree no. 2005-79 from January 26, 2005, authorizing the Atomic Energy Commission to proceed to the definitive shutdown and dismantling operations of the nuclear facility no.21, named Siloette research reactor, in the Grenoble city territory (Isere)

    International Nuclear Information System (INIS)

    2005-02-01

    On May 26, 2003, the French atomic energy commission (CEA) addressed an authorization demand for the definitive shutdown and dismantling of the Siloette research reactor. After a technical and administrative instruction of this demand by the French nuclear safety authority (ASN), a project of decree has been presented on July 6, 2004 at the permanent section of the inter-ministry commission of basic nuclear facilities. The commission gave its favourable judgment which is the object of this decree. (J.S.)

  20. Decree no. 2005-78 from January 26, 2005, authorizing the Atomic Energy Commission to proceed to the definitive shutdown and dismantling operations of the nuclear facility no.20, named Siloe reactor, in the Grenoble city territory (Isere)

    International Nuclear Information System (INIS)

    2005-02-01

    On March 19, 2003, the French atomic energy commission (CEA) addressed an authorization demand for the definitive shutdown and dismantling of the Siloe reactor. After a technical and administrative instruction of this demand by the French nuclear safety authority (ASN), a project of decree has been presented on July 6, 2004 at the permanent section of the inter-ministry commission of basic nuclear facilities. The commission gave its favourable judgment which is the object of this decree. (J.S.)

  1. On evaluation of assessments of accruals of future dismantling costs

    Energy Technology Data Exchange (ETDEWEB)

    Labor, Bea [B D Projects 2013, Gdansk (Poland); Lindskog, Staffan [Swedish Radiation Safety Authority, Solna (Sweden)

    2013-07-01

    A major prerequisite in order for civilian commercial nuclear energy production to qualify as sustainable energy production is that systems for the management of the nuclear waste legacy are in operation. These waste types are present in a range from very low short lived waste (VLLW) to long lived high level waste (HLW) (including the used nuclear fuel). The second prerequisite is that financial responsibilities or other constraints must not be passed on to coming generations. The first condition for qualification corresponds to the Polluters Pays Principle (PPP) which demands that the responsibility for the waste management rests solely with the polluter. The second qualification corresponds to the principle of fairness between generations and thus concerns the appropriate distribution of responsibilities between the generations. It is important to note that these two conditions must be met simultaneously, and that compliance with both is a necessary prerequisite in order for commercial use of nuclear power to qualify as a semi-sustainable energy source. Financial and technical planning for dismantling and decommissioning of nuclear installations cannot be regarded as successful unless it rests upon a distinctive way to describe and explain the well-founded values of different groups of stakeholders. This cumbersome task can be underpinned by transparent and easy to grasp models for calculation and estimation of future environmental liabilities. It essential that a systematic classification is done of all types of costs and that an effort is done to evaluate the precision level in the cost estimates. In this paper, a systematic and transparent way to develop a parametric approach that rest upon basic accounting standards is combined with data about younger stakeholder's values towards decommissioning and dismantling of nuclear installation. The former entity rests upon theoretical and practical methods from business administration, whilst the latter is based

  2. On evaluation of assessments of accruals of future dismantling costs

    International Nuclear Information System (INIS)

    Labor, Bea; Lindskog, Staffan

    2013-01-01

    A major prerequisite in order for civilian commercial nuclear energy production to qualify as sustainable energy production is that systems for the management of the nuclear waste legacy are in operation. These waste types are present in a range from very low short lived waste (VLLW) to long lived high level waste (HLW) (including the used nuclear fuel). The second prerequisite is that financial responsibilities or other constraints must not be passed on to coming generations. The first condition for qualification corresponds to the Polluters Pays Principle (PPP) which demands that the responsibility for the waste management rests solely with the polluter. The second qualification corresponds to the principle of fairness between generations and thus concerns the appropriate distribution of responsibilities between the generations. It is important to note that these two conditions must be met simultaneously, and that compliance with both is a necessary prerequisite in order for commercial use of nuclear power to qualify as a semi-sustainable energy source. Financial and technical planning for dismantling and decommissioning of nuclear installations cannot be regarded as successful unless it rests upon a distinctive way to describe and explain the well-founded values of different groups of stakeholders. This cumbersome task can be underpinned by transparent and easy to grasp models for calculation and estimation of future environmental liabilities. It essential that a systematic classification is done of all types of costs and that an effort is done to evaluate the precision level in the cost estimates. In this paper, a systematic and transparent way to develop a parametric approach that rest upon basic accounting standards is combined with data about younger stakeholder's values towards decommissioning and dismantling of nuclear installation. The former entity rests upon theoretical and practical methods from business administration, whilst the latter is based

  3. Dismantling institutional racism: theory and action.

    Science.gov (United States)

    Griffith, Derek M; Mason, Mondi; Yonas, Michael; Eng, Eugenia; Jeffries, Vanessa; Plihcik, Suzanne; Parks, Barton

    2007-06-01

    Despite a strong commitment to promoting social change and liberation, there are few community psychology models for creating systems change to address oppression. Given how embedded racism is in institutions such as healthcare, a significant shift in the system's policies, practices, and procedures is required to address institutional racism and create organizational and institutional change. This paper describes a systemic intervention to address racial inequities in healthcare quality called dismantling racism. The dismantling racism approach assumes healthcare disparities are the result of the intersection of a complex system (healthcare) and a complex problem (racism). Thus, dismantling racism is a systemic and systematic intervention designed to illuminate where and how to intervene in a given healthcare system to address proximal and distal factors associated with healthcare disparities. This paper describes the theory behind dismantling racism, the elements of the intervention strategy, and the strengths and limitations of this systems change approach.

  4. Weapons dismantlement issues in independent Ukraine

    International Nuclear Information System (INIS)

    Zack, N.R.

    1995-01-01

    The American Association for the Advancement of Science sponsored a seminar during September 1993 in Kiev, Ukraine, titled, ''Toward a Nuclear-Free Future--Barriers and Problems.'' It brought together Ukrainians, Belarusians and Americans to discuss the legal, political, economic, technical, and safeguards and security dimensions of nuclear weapons dismantlement and destruction. US representatives initiated discussions on legal and treaty requirements and constraints, safeguards and security issues surrounding dismantlement, storage and disposition of nuclear materials, warhead transportation, and economic considerations. Ukrainians gave presentations on arguments for and against the Ukraine keeping nuclear weapons, the Ukrainian Parliament's nonapproval of START 1, alternative strategies for dismantling silos and launchers, and economic and security implications of nuclear weapons removal from the Ukraine. Participants from Belarus discussed proliferation and control regime issues. This paper will highlight and detail the issues, concerns and possible impacts of the Ukraine's dismantlement of its nuclear weapons

  5. The installation and dismantling of electrolytic cells

    International Nuclear Information System (INIS)

    Galushkin, N.V.

    1995-01-01

    This chapter of monograph is devoted to construction of aluminium electrolytic cells, their installation and dismantling. Therefore, the general characteristic and classification of aluminium electrolytic cells was considered. The anode and cathode structure was studied. The lining of cathode casing, the process of collection of anode gases, electrolytic cell cover, and electrical insulation was studied as well. The installation and dismantling of aluminium electrolytic cells was described.

  6. Dismantling of the 50 MW steam generator test facility

    International Nuclear Information System (INIS)

    Nakai, S.; Onojima, T.; Yamamoto, S.; Akai, M.; Isozaki, T.; Gunji, M.; Yatabe, T.

    1997-01-01

    We have been dismantling the 50MW Steam Generator Test Facility (50MWSGTF). The objectives of the dismantling are reuse of sodium components to a planned large scale thermal hydraulics sodium test facility and the material examination of component that have been operated for long time in sodium. The facility consisted of primary sodium loop with sodium heater by gas burner as heat source instead of reactor, secondary sodium loop with auxiliary cooling system (ACS) and water/steam system with steam temperature and pressure reducer instead of turbine. It simulated the 1 loop of the Monju cooling system. The rated power of the facility was 50MWt and it was about 1/5 of the Monju power plant. Several sodium removal methods are applied. As for the components to be dismantled such as piping, intermediate heat exchanger (IHX), air cooled heat exchangers (AC), sodium is removed by steam with nitrogen gas in the air or sodium is burned in the air. As for steam generators which material tests are planned, sodium is removed by steam injection with nitrogen gas to the steam generator. The steam generator vessel is filled with nitrogen and no air in the steam generator during sodium removal. As for sodium pumps, pump internal structure is pulled out from the casing and installed into the tank. After the installation, sodium is removed by the same method of steam generator. As for relatively small reuse components such as sodium valves, electromagnet flow meters (EMFs) etc., sodium is removed by alcohol process. (author)

  7. Parameters of Dismantling Techniques Related to Costs for Decommissioning of Nuclear Facilities

    International Nuclear Information System (INIS)

    Jeong, Kwanseong; Moon, Jeikwon; Choi, Byungseon

    2012-01-01

    Reliable cost estimating is one of the most important elements of decommissioning operation. Reliable cost estimating is one of the most important elements of decommissioning planning. Alternative technologies may be evaluated and compared on their efficiency and effectiveness, and measured against a baseline cost as to the feasibility and benefit derived from the technology. This principle ensures that the cost consideration is economically sound and practical for funding. This paper provides a list with basic review of cutting and dismantling techniques, including some typical characteristics if available, as well as aspects of implementation, parameters of cutting and dismantling techniques in decommissioning costing. This paper gives an overview of the principles of the unit factor approach and its implementation in costing in relation to dismantling activities. In general, proper evaluation of decommissioning costs is important for following issues and relevant measures for achieving the listed aspects are: · Selection of a decommissioning strategy and activities: several decommissioning options should be evaluated: · Support to a cost-benefit analysis to ensure that the principle of optimization and reasonably practicable measures are applied: the extent of evaluated decommissioning options should cover all possible scenarios for dismantling activities; · Estimate of required financial resources for the selected strategy: the selected option should involve the dismantling activities in a structure and extent relevant to real procedure of dismantling activities; · Preparation of the project schedule, workforce requirements and phased funding needs: dismantling activities should be structured according to the tasks of the decommissioning schedule; · Definition of measures for proper management and maintenance of resources for safe and timely decommissioning: the time distribution and safety related parameters of dismantling activities should be known

  8. Dismantling of civilian nuclear powered fleet technical support vessels. engineering solutions - 59386

    International Nuclear Information System (INIS)

    Kulikov, Konstantin N.; Nizamutdinov, Rinat A.; Abramov, Andrey N.

    2012-01-01

    At the present time six nuclear technical support vessels are operated and maintained by Atomflot. Two of them (Volodarsky FTB (floating technical base) and Lepse FTB) were taken out of service for decommissioning and are stored afloat. One more vessel Lotta FTB should be decommissioned during next two years. The nuclear technological support ships carrying spent nuclear fuel (SNF), liquid and solid radioactive wastes (LRW and SRW) appear to be a possible radiation contamination of Murmansk region and Kola Bay because the Ship long-term storage afloat has the negative effect on hull's structures technical condition. As a result of this in the context of the Federal Program 'Nuclear and Radiation Safety' (2008-2015) NIPTB Onega OAO was engaged by state corporation Rosatom to develop the dismantling procedure for Volodarsky FTB and Lotta FTB. Before developing of nuclear technological support ships decommissioning projects the technical and economic assessment of decommissioning/dismantling was carried out. The following options were examined: - formation of module as one-piece Ship's hull for long-term storage at Saida Bay; - formation of separated modules for long-term storage at Saida Bay; - complete dismantling of hull's structures, systems and equipment with packing all generated SRW into certified long-term storage containers. This paper contains description of options, research procedure, comparative analysis of options of decommissioning and dismantling (D and D) of nuclear technological support ships and its difference with dismantling of nuclear submarine. On the basis of the technical and economic assessment of FTB D and D options the least expensive on the first D and D stage and the least duration option is the option 1 (Formation of module as one-piece Ship's hull for long-term storage at Saida Bay). By the implementation of the given option there will be the need of large areas for modules storage at Saida Bay. It was not considered while working out

  9. Method of processing dismantled products of radiation-contaminated equipments and transportation container therefor

    International Nuclear Information System (INIS)

    Komura, Shiro; Heki, Hideaki.

    1991-01-01

    In a method of decontaminating dismantled products of radiation-contaminated equipments removed at nuclear power facilities and classifying the dismantled products depending on their remaining radioactivity levels measured at a processing facility, the dismantled products are contained in a transportation container, to which decontamination liquids are injected and they are transferred to the processing facility. The decontaminated liquid wastes are drained from the transportation container, the dismantled products are washed while being contained in the transportation container as they are. Then, they are transferred to a step for measuring their remaining radioactivity level. This can shorten the time from the containment of the dismantled products to the transportation container to the completion of the decontamination, to improve the efficiency for the decontamination processing. Further, by separately containing the dismantled products on every kind of materials to respective containers, the processing time can be appropriately controlled respectively even if the dissolving efficiency to the decontamination liquids is different depending on the materials. (T.M.)

  10. Iraq nuclear facility dismantlement and disposal project

    Energy Technology Data Exchange (ETDEWEB)

    Cochran, J R; Danneels, J [Sandia National Laboratories, Albuquerque, NM (United States); Kenagy, W D [U.S. Department of State, Bureau of International Security and Nonproliferation, Office of Nuclear Energy, Safety and Security, Washington, DC (United States); Phillips, C J; Chesser, R K [Center for Environmental Radiation Studies, Texas Tech University, Lubbock, TX (United States)

    2007-07-01

    The Al Tuwaitha nuclear complex near Baghdad contains a significant number of nuclear facilities from Saddam Hussein's dictatorship. Because of past military operations, lack of upkeep and looting there is now an enormous radioactive waste problem at Al Tuwaitha. Al Tuwaitha contains uncharacterised radioactive wastes, yellow cake, sealed radioactive sources, and contaminated metals. The current security situation in Iraq hampers all aspects of radioactive waste management. Further, Iraq has never had a radioactive waste disposal facility, which means that ever increasing quantities of radioactive waste and material must be held in guarded storage. The Iraq Nuclear Facility Dismantlement and Disposal Program (the NDs Program) has been initiated by the U.S. Department of State (DOS) to assist the Government of Iraq (GOI) in eliminating the threats from poorly controlled radioactive materials, while building human capacities so that the GOI can manage other environmental cleanups in their country. The DOS has funded the International Atomic Energy Agency (IAEA) to provide technical assistance to the GOI via a Technical Cooperation Project. Program coordination will be provided by the DOS, consistent with U.S. and GOI policies, and Sandia National Laboratories will be responsible for coordination of participants and for providing waste management support. Texas Tech University will continue to provide in-country assistance, including radioactive waste characterization and the stand-up of the Iraq Nuclear Services Company. The GOI owns the problems in Iraq and will be responsible for the vast majority of the implementation of the NDs Program. (authors)

  11. Decommissioning and dismantling of the Rossendorf Isotope Production

    International Nuclear Information System (INIS)

    Grahnert, Thomas

    2016-01-01

    After just over 40 years of production operation 2000, the operation of the Rossendorf Isotope Production was finally stopped. In the last few years of production already sections of the Rossendorf Isotope Production have been decommissioned. With the end of the isotope production the decommissioning of the entire complex started. In the two-part report, the decommissioning and dismantling of the Rossendorf Isotope production is presented. In part 1 (atw 5/2016) mainly the authorisation procedures and the realised decommissioning concept are presented. Part 2 (atw 6/2016) deals with special selected aspects of the implementation of the decommissioning programme.

  12. Decommissioning and dismantling of nuclear research facilities in Switzerland: lessons learned

    International Nuclear Information System (INIS)

    Leibundgut, Fritz

    2017-01-01

    Paul Scherrer Institute is the largest research institute for natural and engineering science in Switzerland. It operated various nuclear facilities from 1960 to 2011: Research reactors DIORIT, SAPHIR and PROTEUS, and an incineration plant for low and medium level radioactive waste. Concerning SAPHIR research reactor: in operation from 1958 to 1993, planning of decommissioning from 1998 to 2000. Decommissioning work started in 2004. Finishing is planned for 2019. Concerning DIORIT research reactor: operation as DIORIT I (20 MWth) from 1960 to 1967, then reconstruction to DIORIT II (30 MWth) and operation from 1970 until 1977. Planning of decommissioning from 1992 to 1994. Decommissioning work started in 1994 and was finished in 2012. Concerning PROTEUS research reactor: in operation from 1966 to 2011. Planning of decommissioning from 2013 to 2014. Starting of decommissioning work is planned for 2017, finishing is planned for the end of 2018 Incineration plant: In operation from 1974 to 2002. Planning of decommissioning from 2011 to 2012. Starting of decommissioning work in 2016. Finishing planned for end of 2019. Treatment of various material categories from dismantling: Concerning aluminum: because of the production of H_2 during solidification in concrete, it was necessary to minimize the surface area. When dismantling research reactors, the aluminum removed was melted in an induction furnace and poured into a 4.5 m"3 concrete container to solidify. Cutting the metal and handling it was largely accomplished remote control, using conventional technology. Concerning Steel/Cast-iron: the storage containers to be filled determined the method used for reducing the size of these materials, and the technique used for handling them. The goal was to optimize the packing density to reduce repository costs. The selected method of reducing the size of components is to cut them up using diamond-tipped tools, like saw blades. Concerning Graphite: for graphite, grinding was the

  13. Operational factors affecting microgravity levels in orbit

    Science.gov (United States)

    Olsen, R. E.; Mockovciak, J., Jr.

    1980-01-01

    Microgravity levels desired for proposed materials processing payloads are fundamental considerations in the design of future space platforms. Disturbance sources, such as aerodynamic drag, attitude control torques, crew motion and orbital dynamics, influence the microgravity levels attainable in orbit. The nature of these effects are assessed relative to platform design parameters such as orbital altitude and configuration geometry, and examples are presented for a representative spacecraft configuration. The possible applications of control techniques to provide extremely low acceleration levels are also discussed.

  14. Cleaning of dismantled metals by electropolishing

    International Nuclear Information System (INIS)

    Wei, T.Y.; Chung, Z.J.; Lu, D.L.; Hsieh, J.C.

    1995-01-01

    A project of cleaning dismantled metals is going on at INER. The test work has been performed. Results showed that the activity decreased from 45 microSv/h to background level after 20 minutes electrolytic polishing. These cleaned metals could be reused through melting and fabricating. These metals could also be classified as BRC waste to facilitate the waste management if they can pass the identification and be admitted by the government authority. In order to achieve the planned target, some electro-decontamination facilities have been established. An automatic electropolishing facility with six cells was designed to clean the contaminated metals in plate type with dimensions less than 50 cm x 50 cm. Another automatic electropolishing facility was specially designed for treating the contaminated pipes. In addition, mobile electropolishing facilities were also established for large pieces of metal and some fixed equipment. In this cleaning project, a practical recycling and treatment method for electrolyte has been developed in order to comply with the requirement of secondary waste minimization

  15. CRITICALITY CONTROL DURING THE DISMANTLING OF A URANIUM CONVERSION PLANT

    International Nuclear Information System (INIS)

    LADURELLE, Laurent; LISBONNE, Pierre

    2003-01-01

    Within the Commissariat a l'Energie Atomique, in the Cadarache Research Center in southern France, the production at the Enriched Uranium Treatment Workshops started in 1965 and ended in 1995. The dismantling is in progress and will last until 2006. The decommissioning is planned in 2007. Since the authorized enrichment in 235U was 10% in some parts of the plant, and unlimited in others, the equipment and procedures were designed for criticality control during the operating period. Despite the best previous removing of the uranium in the inner parts of the equipment, evaluation of the mass of remaining fissile material by in site gamma spectrometry measurement shows that the safety of the ''clean up'' operations requires specific criticality control procedures, this mass being higher than the safe mass. The chosen method is therefore based on the mapping of fissile material in the contaminated parts of the equipment and on the respect of particular rules set for meeting the criticality control standards through mass control. The process equipment is partitioned in separated campaign, and for each campaign the equipment dismantling is conducted with a precise traceability of the pieces, from the equipment to the drum of waste, and the best final evaluation of the mass of fissile material in the drum. The first results show that the mass of uranium found in the dismantled equipment is less than the previous evaluation, and they enable us to confirm that the criticality was safely controlled during the operations. The mass of fissile material remaining in the equipment can be then carefully calculated, when it is lower than the minimal critical mass, and on the basis of a safety analysis, we will be free of any constraints regarding criticality control, this allowing to make procedures easier, and to speed up the operations

  16. Aspects of reactor dismantling planning following the safe entombment in the NPP Lingen (KWL); Aspekte der Abbauplanung nach dem Sicheren Einschluss im Kernkraftwerk Lingen (KWL)

    Energy Technology Data Exchange (ETDEWEB)

    Priesmeyer, U.; Rojahn, T.; Fries, B. [Kernkraftwerk Lingen GmbH (Germany)

    2009-07-01

    The NPP Lingen (KWL) was shut-down in 1977. Due to the fact that no final repository was available the safe entombment for 25 years was chosen following the decommissioning. The conventional plant components were dismantled and removed from the plant site. The licensing procedure for reactor dismantling with final disposal in Schacht Konrad has been started. The beginning of dismantling operation is scheduled for 2013. The authors describe the preparatory work, the boundary conditions for the dismantling, radiation protection considerations with respect to manual demolition work after the rather long decay time.

  17. Dismantling the Curriculum in Higher Education

    Directory of Open Access Journals (Sweden)

    Richard Hall

    2016-04-01

    Full Text Available The higher education curriculum in the global North is increasingly co-opted for the production of measurable outcomes, framed by determinist narratives of employability and enterprise. Such co-option is immanent to processes of financialisation and marketisation, which encourage the production of quantifiable curriculum activities and tradable academic services. Yet the university is also affected by global socio-economic and socio-environmental crises, which can be expressed as a function of a broader crisis of social reproduction or sociability. As the labour of academics and students is increasingly driven by a commodity-valuation rooted in the measurement of performance, the ability for academics and students to respond to crises from inside the university is constrained by the market. This article argues that in understanding the relationship between the university and society, and in responding to a crisis of sociability, revealing the bounded nature of the curriculum is central. One possible way to address this crisis is by re-imagining the university through the co-operative practices of groups like the Dismantling the Masters House community and the Social Science Centre. Such an exploration, rooted in the organising principles of the curriculum, asks educators to consider how their curriculum reproduces an on-going colonisation by Capital. It is argued that such work enables a re-imagination of higher education that is rooted in a co-operative curriculum, and which might enable activist-educators to build an engaged curriculum, through which students and academics no longer simply learn to internalise, monitor and manage their own alienation.

  18. State level operations and interaction with facility level systems

    International Nuclear Information System (INIS)

    Bellinger, J.

    1989-01-01

    The role of the State System of Accounting for and Control of Nuclear Materials at the State level, particularly the role of the National Authority, in ensuring that both national and international safeguards objectives are met is discussed. The legislative basis for the National Authority is examined. The activities of Australia's National Authority - the Australian Safeguards Office - are described

  19. Vandellos-I Dismantling nearing completion

    International Nuclear Information System (INIS)

    Armada, J. R.

    2004-01-01

    Spain is witnessing the phase-out of a nuclear power plant. It is a unique experience in our country and therefore the dismantling work has been watched closely, not only from here but also from abroad. The Empresa Nacional de Residuos Radiactivos (ENRESA) is in charge of managring the dismantling and decommissioning work of the Vandellos-1 nuclear power plant, located in the municipally of l' Hospitalet de l'Infant (Tarragona). The work began five years ago and has been executed on schedule. The appearance of what was one of the first Spanish commercial nuclear power plants has been changed radically to leave premises suitable for any other activity. (Author)

  20. Economical dismantling of nuclear power stations

    International Nuclear Information System (INIS)

    Mallok, J.; Andermann, H.

    1999-01-01

    The dismantling of nuclear power stations requires a high degree of security and economic efficiency due to the strong contamination of components and the close spatial conditions. In order to protect involved staff from radiation, modern remote-controlled technology is applied in sectors with heavy radioactive contamination such as reactor pressure vessels. The article shows, that the dismantling of reactor pressure vessels using a remote-controlled milling machine developed by the Siemens subsidiary Mechanik Center Erlangen GmbH, can be done in a secure and efficient way. (orig.) [de

  1. The level of recycling operations in Botswana | Ketlogetswe ...

    African Journals Online (AJOL)

    This paper describes a case study that evaluated the level of recycling operations in Botswana. Recycling operations are now recommended as effective waste management strategies for reducing the amount of municipal solid waste disposed at landfill sites. In assessing the level of recycling operations in Botswana, two ...

  2. Some steps of the dismantling of the hot cell ATTILA

    International Nuclear Information System (INIS)

    Terrasson, L.

    1989-01-01

    This paper describes the dismantling, during 2 years and just finished now, of a large hot cell (11.6 m x 5.90 m x 5.80 m) at Fontenay-aux-Roses (France) characterised by an importand irradiation and contamination mean dose rate 7 rads/hr, in some places 20 rads/hr, coming at 98 % from Cesium 137 (beta decay radioisotope). Put into operation in March 1967, the Attila cell was used for spent fuel processing using halogenides [fr

  3. Processing of LLW arising from dismantling activities in a reprocessing facility

    International Nuclear Information System (INIS)

    Geens, L.G.; Geens, L.P.; Vandeven, I.

    1990-01-01

    The Eurochemic reprocessing facility, at the Mol-Dessel site in Belgium was in active operation from July 1966 until January 1975. In total, about 210 Mg of various types of irradiated nuclear fuels were processed. After the shut-down the plant has been partially decontaminated in view of recommissioning. When the recommissioning option was abandoned, the decision was taken in 1986 to dismantle the plant. A 2 years study resulted in the start of a pilot project: the dismantling of two smaller buildings, previously used for storage of uranyl nitrate and used solvent. The minimization of radioactive waste generation was also one of the major goals of this project. The report deals with the different steps in the minimization of radioactive waste generation during the dismantling activities. First, an estimation of the amounts of radioactive waste, expected to be generated, was made. In a second step the actual waste production during dismantling operations was minimized and compared with the estimations. Finally, a large part of the primary radioactive dismantling waste has been completely decontaminated, resulting in much lower amounts of nuclear waste generated. 2 refs., 3 figs., 2 tabs

  4. Progress in the development of tooling and dismantling methodologies for the Windscale advanced gas cooled reactor (WAGR)

    International Nuclear Information System (INIS)

    Cross, M.T.; Wareing, M.I.; Dixon, C.

    1998-01-01

    Decommissioning of the Windscale Advanced Gas-Cooled Reactor (WAGR) is a major UK reactor decommissioning project co-funded by the UK Government, the European Commission and Magnox Electric. WAGR was a CO 2 cooled, graphite moderated reactor which served as a test bed for the development of Advanced Gas-Cooled Reactor technology in the UK. It operated from 1963 until shutdown in 1981. AEA Technology plc are currently the Managing Agents on behalf of UKAEA for the WAGR decommissioning project and are responsible for the co-ordination of the project up to the point when the contents of the reactor core and associated radioactive materials are removed and either disposed of or packaged for disposal at some time in the future. Decommissioning has progressed to the point where the reactor has been dismantled down to the level of the hot gas collection manifold with the removal of the top biological shield, the refuelling standpipes and the top section of the reactor pressure vessel. The 4 heat exchangers have also been removed and committed to shallow land burial. This paper describes the work carried out by AEA Technology under separate contracts of UKAEA in developing some of the equipment and deployment methods for the next phase of active operations required in preparation for the dismantling of the core structure. Most recent work has concentrated on the development of specialist tooling for removal of items of operational waste stored within the reactor core, equipment for cutting and removal of the highly radioactive stainless steel 'loop' pressure tubes, diamond wire cutting equipment for sectioning large diameter pipework, and equipment for dismantling the reactor neutron shield. The paper emphasises the process of adaptation and extension of existing technologies for cost-effective application in the decommissioning environment, the need for adequate forward planning of decommissioning methodologies together with large-scale 'mock-up' testing of equipment to

  5. Radioactivity, radiation protection and monitoring during dismantling of light-water reactors

    International Nuclear Information System (INIS)

    Hummel, L.; Zech, J.B.

    2005-01-01

    Based on the radioactivity inventory in the systems and components of light-water reactors observed during operation, the impact of actions during plant emptying after the conclusion of power operation and possible subsequent long-term safe enclosure concerning the composition of the nuclide inventory of the plant to be dismantled will be described. Derived from this will be the effects on radioactivity monitoring in the plant, physical radiation protection monitoring, and the measured characterization of the residual materials resulting from the dismantling. The impact of long-term interim storage will also be addressed in the discussion. The talk should provide an overview of the interrelationships between source terms, decay times and the radioactivity monitoring requirements of the various dismantling concepts for commercial light-water reactors. (orig.)

  6. Conception of dismantling cell for glove box with alpha contamination

    International Nuclear Information System (INIS)

    Mangin, D.

    1987-01-01

    The new dismantling cell of Valduc treats particularly alpha glove boxes. This cell is conceived to reduce the intervention inside for man with ventilated clothes and to reduce the volume of alpha wastes by utilization of manipulators and appropriate tools. The respect of low level norms (0.1 Ci/ton) for storage of alpha wastes conductes us to make a first decontamination, to ameliorate the detection in quantity of plutonium in the wastes and for wastes with a level upper the norm to make studies on decontamination by Freon 113 [fr

  7. Building dismantlement and site remediation at the Apollo Fuel Plant: When is technology the answer?

    International Nuclear Information System (INIS)

    Walton, L.

    1995-01-01

    The Apollo fuel plant was located in Pennsylvania on a site known to have been used continuously for stell production from before the Civil War until after World War II. Then the site became a nuclear fuel chemical processing plants. Finally it was used to convert uranium hexafluoride to various oxide fuel forms. After the fuel manufacturing operations were teminated, the processing equipment was partially decontaminated, removed, packaged and shipped to a licensed low-level radioactive waste burial site. The work was completed in 1984. In 1990 a detailed site characterization was initiated to establishe the extent of contamination and to plan the building dismantlement and soil remediation efforts. This article discusses the site characterization and remedial action at the site in the following subsections: characterization; criticality control; mobile containment; soil washing; in-process measurements; and the final outcome of the project

  8. SGN's Dismantling and Decommissioning engineering, projects experience and capabilities

    International Nuclear Information System (INIS)

    Destrait, L.

    1998-01-01

    Its experience in waste treatment, conditioning, storage and disposal, its cooperation with CEA and COGEMA Group in license agreements give SGN expertise in the decommissioning field. SGN's experience and background in all areas of nuclear facility decommissioning, such as chemical and mechanical cells, nuclear advanced reactors, reprocessing facilities result in fruitful references to the customers. The poster is presenting different achievements and projects with SGN's participation such as: - The decommissioning of Windscale Advanced Gas cooled Reactors (WAGR), in particular providing methodology and equipment to dismantle the Pressure and Insulation Vessel of the reactor. - The decommissioning plan of Ignalina (Lithuania) and Paldiski (Estonia), defining strategies, scenarios, necessary equipments and tools and choosing the best solutions to decommission the site under different influencing parameters such as cost, dose rate exposure, etc... - Th One Site Assistance Team (OSAT) at Chernobyl regarding the preparation works for the waste management and decommissioning of the plant. - The decommissioning of French nuclear facilities such as reprocessing (UP1) and reactor (EL4) plants. The important experience acquired during the facility management and during the first dismantling and decommissioning operations is an important factor for the smooth running of these techniques for the future. The challenge to come is to control all the operations, the choice of strategies, the waste management, the efficiency of tools and equipments, and to provide nuclear operators with a full range of proven techniques to optimise costs and minimize decommissioning personnel exposure. (Author)

  9. Augmented Reality at the Tactical and Operational Levels of War

    Science.gov (United States)

    2015-10-24

    Lee & Alex Kirlik (Eds.) The Oxford Handbook of Cognitive Engineering, 2013), pp. 37-56. 105 David Oderberg, Perceptual Relativism , (Philosophia...operational level build upon the concerns raised at the tactical level. However, some of the concerns differ based on cultural differences between...within operational level staffs and organizations will be overcoming anti-technology cultural biases. Most operational leaders and their staffs are more

  10. Method and apparatus for dismantling mechanical anchors

    Energy Technology Data Exchange (ETDEWEB)

    Dubovskiy, Yu P; Chendev, F S; Gritsayuk, B I; Gubin, N I; Osipov, S P

    1982-01-01

    This apparatus is designed to reduce the amount of labor required to dismantle mechanical anchors while at the same time lowering expenditures for lumber. Longwall beams and timber skips are used to support the cap and any fractured rock faces. The apparatus itself has grooves, vertical guides, and a drive system to position the longwall beams.

  11. Method of dismantling nuclear fuel elements

    International Nuclear Information System (INIS)

    Adams, G.J.

    1983-01-01

    Nuclear fuel assemblies of the kind comprising fuel pins in dimpled cellular grids are freed from the grids to aid dismantling of the assemblies by causing a rotary sleeve to pass concentrically over the pins to remove the dimples in the grids and thereby increase the freedom of the pins in the cells of the grids. (author)

  12. Taking into account of dismantling constraints in the design of nuclear facilities

    International Nuclear Information System (INIS)

    Gouhier, E.; Moitrier, C.; Girones, P.; Pitrou, Y.; Poncet, P.; O'Sullivan, P.

    2014-01-01

    The taking into account of dismantling constraints in the design of nuclear facilities allows the reduction of the dosimetry during the dismantling operations, the reduction of the amount of wastes to manage and the saving of time and money by foreseeing an adequate and simple solution for each component. It is to notice that the strategy of life-extension strengthens that of dismantling because life-extension implies the possibility for any component of the reactor except the pressure vessel to be replaced. The feedback experience capitalized on various types of nuclear facilities have enabled IAEA and OECD to publish recommendations to facilitate dismantling. For instance, pipes and ventilation ducts must be designed to minimize the deposit of dust and residues, the natural porosity of concrete must be limited through the use of polishing products or a metal liner, the type and concentrations of impurities present in the structure materials must be controlled to limit radioactivation, the documentation describing the facility must be kept up to date, or the history of contamination events must be recorded all along the life of the facility. The integration of the dismantling constraints in the design stage is illustrated with 3 examples: the Georges Besse 2 enrichment fuel plant, new reactors (EPR, ASTRID and RJH), and ITER. (A.C.)

  13. Metal Radioactive Waste Recycling from the Dismantling of Nuclear Facilities

    International Nuclear Information System (INIS)

    Fajt, B.; Prah, M.

    1996-01-01

    In the dismantling process of nuclear power plants a large amount of metal residues are generated. The residues of interest are stainless steel, copper and aluminium and can be reprocessed either for restricted or unrestricted use. Although there are many questions about the further use of these materials it should be convenient to recycle them. This paper discusses the complexity of the management of these metals. The radiation protection requirements are the most important principles. For these purposes great efforts in the decontamination have to be made. Regulatory aspects, clearance levels as well as characteristic of steel recycling industry, radiological impact and new developments are discussed. (author)

  14. FY 1994 report on the results of the project supplementary to the New Sunshine Project - Development of the coal utilization hydrogen production technology. Ninth year - Part 2. Study using a pilot plant (Design/construction/operation study of the pilot plant and the dismantling study); 1994 nendo New Sunshine keikaku hojo jigyo Dai 9 nenji bun seika hokokusho - 2. Sekitan riyo suiso seizo gijutsu kaihatsu - Pilot plant ni yoru kenkyu (Pilot plant no sekkei kensetsu unten kenkyu)

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-03-01

    In the R and D of the high temperature coal gasification technology by the entrained bed system which is the core technology of the coal utilization hydrogen production technology, the paper carried out the dismantling study of pilot plant and the summarization of the results. About the summarization of the results, as the results of the HYCOL operation study, there were insufficiencies in expansion of the coal kind used and acquisition of scale-up data, but it was verified that the conceptual design of the HYCOL method was fully applicable to the higher gasification efficiency, higher reliability, adaptability to many kinds of coal and compactness of facilities (low construction cost) which were the final subjects for the realization of commercial plant. This was highly evaluated. Especially, the greatest characteristic of the HYCOL method is the freedom in selection of temperature difference between the upper stage and lower stage, that is, temperatures can be controlled to temperatures they want in each of the upper stage and lower stage in the one-chamber gasifier according to coal properties and slagging control. The verification of this freedom was the base of the total results. Moreover, a reputation was being made that the gasification efficiency and process reliability are at the world's highest level. (NEDO)

  15. In-situ dismantling of plutonium-contaminated glove box

    International Nuclear Information System (INIS)

    Numata, Koji; Watanabe, Hisashi; Ishikawa, Hisashi; Miyo, Hiroaki; Ohtsuka, Katsuyuki

    1980-01-01

    A plutonium-contaminated glove box was dismantled along with the development of the treatment techniques for plutonium-bearing wastes. The objectives of this in-situ dismantling of the glove box are to reuse the Plutonium Fuel Fabrication Facility more efficiently, to reduce the volume of wastes generated during the dismantling, and to acquire dismantling techniques for decommissioning the Plutonium Fuel Fabrication Facility in the future. Prior to the dismantling works, a greenhouse for decontamination was installed, and the decontamination with surfactants was performed. Unremovable contamination was coated with paint. After this greenhouse was removed, the main greenhouse for dismantling and three greenhouses for contamination control were assembled. The main workers wearing protective devices engaged in dismantling works in the greenhouse. As the protective devices, anorak type PVC suits with air line masks, Howell type pressurized suits, and respirators were used. The tools used for the dismantling are a plasma cutter, an electric nibbler, an electric disk grinder, an electric circular saw and an electric jig saw. The results of the dismantling in-situ were compared with two previous cases of dismantling carried out by different procedures. In the case of in-situ dismantling, the volume of wastes was 1.6 - 1.8 m 3 /m 3 of glove box, and considerable reduction was realized. (Kako, I.)

  16. Failure prevention with stress measurement for dismantling of nuclear facilities. Final report

    International Nuclear Information System (INIS)

    Komber, T.; Reimche, W.; Bach, F.W.

    2003-07-01

    The dismantling of nuclear facilities is in progress since 20 years in Germany. Practical experiences in decommissioning have shown, that problem can occur during dismantling operations caused by release of residual stresses. In this case cutting parts or cutting tools get jammed if mechanical cutting techniques are used. The aim of this research work was to develop measuring techniques for the determination of the stress state in RPV, to predict the deformation during dismantling operations. This can serve as additional base for improved decommissioning planning and for time optimised dismantling. For determination of the stress state in components two small and inexpensive measuring techniques were new designed, for remote-controlled on-site use in atmosphere and under water. For the nondestructive determination of the directional stress state, based on the magnetostriction and the Harmonic-Analysis of alternating magnetic fields, a new developed rotating sensor is in use with a principal magnetisation direction. Because of the mainly isotropic material properties and the directional stresses, measured Harmonic values are influenced mainly by the stress state in the surface areas. In this way it is possible to determine the stress state qualitatively and the direction of principal stresses in the surface areas of the component. As an alternative to the established wire strain gauge, which remote-controlled application is still not possible under water, a new slot jet cutting strain control technique was designed. This technique detects the deformation in the surface after stresses are cut free by a water jet. So the stress state could be determined quantitatively in the surface and assessed in the depth. With the help of these two measuring techniques it is possible to characterize the stress state along a planned cutting line. The use of an adapted FEM simulation enables to calculate and determine the deformation of the cutting gap beforehand. These information

  17. On-site disposal of decontaminated and dismantled (D and D) materials: A management approach

    International Nuclear Information System (INIS)

    Hall, J.S.; Davis, M.J.; Picel, K.C.

    1995-01-01

    The Fernald Environmental Management Project (FEMP) is a federal facility located near Cincinnati, Ohio that is being remediated. Operable Unit 3 (OU3) of the FEMP consists of 232 buildings and other structures that formerly housed various uranium and thorium metallurgical and chemical processes. The buildings are constructed primarily of steel and concrete, with transite siding. The structures are being decontaminated and dismantled using an interim remedial action approach. The disposition of the debris and other waste materials generated by the interim action is being addressed by the final remedial action for the operable unit. The preferred alternative is disposal of most of the material in an engineered disposal cell located on the FEMP property. This is complicated by the fact that the FEMP is located in an environmentally sensitive area and by the complex nature of the materials. The principal aquifer located beneath the site, the Great Miami Aquifer, is designated as a sole-source aquifer under the Safe Drinking Water Act. Disposal of any wastes at the FEMP must be protective of the aquifer. Dismantlement of OU3 structures will result in a very heterogeneous waste stream, both in terms of types of materials and levels of contamination. Wastes to be managed also include contaminated production equipment and drummed materials associated with former production activities, as well as structural materials. All of these factors complicate the management of OU3 materials. This paper discusses the approach proposed by the FEMP for the management of materials resulting from the interim remedial action. The components of the management approach being used to address disposal of the heterogeneous wastes from OU3 in an environmentally sensitive manner are discussed, followed by some conclusions

  18. Influence of disturbances on bacteria level in an operating room

    DEFF Research Database (Denmark)

    Brohus, Henrik; Hyldig, Mikkel; Kamper, Simon

    2008-01-01

    In operating rooms great effort is manifested to reduce the bacteria level in order to decrease the risk of infections. The main source of bacteria is the staff and the patient, thus, the resulting bacteria concentration is roughly speaking a combination of the ventilation system and the emission...... from the occupants. This study investigates the influence of two main disturbances in an operating room namely the door opening during the operation and the activity level of the staff. It is found that the frequent door opening in this case does not cause significant transport of air from outside...... the operating room to the wound area of the patient. However, a significant influence of the activity level on the bacteria emission and concentration is found. Counting the number of persons in an operating room to estimate the bacteria source strength is not sufficient, the corresponding activity level must...

  19. Decommissioning and dismantling reactors and managing waste

    International Nuclear Information System (INIS)

    Bensoussan, E.; Reicher-Fournel, N.

    2005-01-01

    In the early forties/fifties, a number of countries launched the first developments in the field of nuclear power. Some of them now have large numbers of nuclear facilities and nuclear power plants which have met, and continue to meet, the objectives for which they were designed and built. Other plants, including nuclear fuel production and enrichment plants, experimental reactors or research reactors, will have to be dismantled and demolished in the near future. These activities are handled differently in different countries as a function of specific energy policies, advanced development plants, current financial resources, the availability of qualified engineers and specialized industries able to handle projects of this kind, as well as other factors. All dismantling and demolition projects serve the purpose of returning the respective sites to green-field conditions. (orig.)

  20. Dismantling method for reactor shielding wall and device therefor

    International Nuclear Information System (INIS)

    Akagawa, Katsuhiko.

    1995-01-01

    A ring member having an outer diameter slightly smaller than an inner diameter of a reactor shielding wall to be dismantled is lowered in the inside of the reactor shielding wall while keeping a horizontal posture. A cutting device is disposed at the lower peripheral edge of the ring member. The cutting device can move along the peripheral edge of the circular shape of the ring member. The ring member is urged against the inner surface of the reactor shielding wall by using an urging member to immobilize the ring member. Then, the cutting device is operated to cut the reactor shielding wall into a plurality of ring-like blocks at a plurality of inner horizontal ribs or block connection ribs. Then, the blocks of the cut reactor shielding wall are supported by the ring member, and transported out of the reactor container by a lift. The cut blocks transported to the outside are finely dismantled for every block in a closed chamber. (I.N.)

  1. A Study on Dismantling of Westinghouse Type Nuclear Reactor

    International Nuclear Information System (INIS)

    Jeong, Woo-Tae; Lee, Sang-Guk

    2014-01-01

    KHNP started a research project this year to develop a methodology to dismantle nuclear reactors and internals. In this paper, we reviewed 3D design model of the reactor and suggested feasible cutting scheme.. Using 3-D CAD model of Westinghouse type nuclear reactor and its internals, we reviewed possible options for disposal. Among various options of dismantling the nuclear reactor, plasma cutting was selected to be the best feasible and economical method. The upper internals could be segmented by using a band saw. It is relatively fast, and easily maintained. For cutting the lower internals, plasma torch was chosen to be the best efficient tool. Disassembling the baffle and the former plate by removing the baffle former bolts was also recommended for minimizing storage volume. When using plasma torch for cutting the reactor vessel and its internal, installation of a ventilation system for preventing pollution of atmosphere was recommended. For minimizing radiation exposure during the cutting operation, remotely controlled robotic tool was recommended to be used

  2. Advanced robotics for decontamination and dismantlement

    International Nuclear Information System (INIS)

    Hamel, W.R.; Haley, D.C.

    1994-01-01

    The decontamination and dismantlement (D ampersand D) robotics technology application area of the US Department of Energy's Robotics Technology Development Program is explained and described. D ampersand D robotic systems show real promise for the reduction of human exposure to hazards, for improvement of productivity, and for the reduction of secondary waste generation. Current research and development pertaining to automated floor characterization, robotic equipment removal, and special inspection is summarized. Future research directions for these and emerging activities is given

  3. Operating safety requirements for the intermediate level liquid waste system

    International Nuclear Information System (INIS)

    1980-07-01

    The operation of the Intermediate Level Liquid Waste (ILW) System, which is described in the Final Safety Analysis, consists of two types of operations, namely: (1) the operation of a tank farm which involves the storage and transportation through pipelines of various radioactive liquids; and (2) concentration of the radioactive liquids by evaporation including rejection of the decontaminated condensate to the Waste Treatment Plant and retention of the concentrate. The following safety requirements in regard to these operations are presented: safety limits and limiting control settings; limiting conditions for operation; and surveillance requirements. Staffing requirements, reporting requirements, and steps to be taken in the event of an abnormal occurrence are also described

  4. Provision of the technical infrastructure for the dismantling of the WAK HAWC container. Design and realization

    International Nuclear Information System (INIS)

    Marquard, C.; Ripholz, M.; Lutz, W.

    2013-01-01

    The dismantling concept of the WAK HAWC (high-level liquid waste concentrate) containers includes remote handling equipment. Due to the solid deposits that formed during the concentrate storage time the activity and the dose rates of the containers are very high (2.6x10E15 Bq alpha and beta, dose rates higher 100 Sv/h). Therefore appropriate radiation protection measures have to be installed to protect personnel and environment. The provision of the technical infrastructure for the remote HAWC container dismantling is described in detail.

  5. Method and jig for dismantling nuclear fuel assembly

    International Nuclear Information System (INIS)

    Urata, Megumi; Watahiki, Minoru.

    1989-01-01

    The object of the present inention is to extract a fuel element from a lower tie plate safely and at high efficiency by a remote control operation. That is, a forked top end of a lever of a dismantling jig is inserted between the tapered portion of a lower end plug and a lower tie plate. Then, a load is applied to the counter-lower end side of the lever by a motor. This exerts an elevating force to the fuel elements to easily release fixture between the lower end plug and the lower tie plate. Since the fuel can of fuel elements is not applied with a force by this mehtod, operation safety can be improved. (I.J.)

  6. Decision Analysis Science Modeling for Application and Fielding Selection Applied to Equipment Dismantlement Technologies. Topical Report January 1998

    International Nuclear Information System (INIS)

    Ebadian, M.A.

    1998-01-01

    The dismantlement of radioactively contaminated process equipment is a major concern during the D and D process. As buildings undergo the D and D process, metallic equipment contaminated with radionuclides such as uranium and plutonium must be dismantled before final disposal.The primary objective for equipment dismantlement is to reduce the potential for personnel and environmental exposure to contaminants during the decommissioning of the nuclear facility. The selection of the appropriate technologies to meet the dismantlement objectives for a given site is a difficult process in the absence of comprehensive and comparable data. Choosing the wrong technology could result in increased exposure of personnel to contaminants and an increase in D and D project costs. Innovative technologies are being developed with the goal of providing safer and more cost-effective alternatives that generate less secondary waste, thereby decreasing the operating costs for dismantlement. During the development and implementation process, performance indicators for the success of these technologies must be reviewed to ensure that these aims are being met. This project provides a mechanism for the assessment of innovative and commercially available nuclear and non-nuclear technologies for equipment dismantlement

  7. Level 3 decommissioning of Triton - Nereide research reactor

    International Nuclear Information System (INIS)

    Lopes, E.; Pillette-Cousin, L.

    2002-01-01

    The French Atomic Energy Commission Center located at Fontenay-Aux-Roses has launched an extensive programme of site cleanup and decommissioning of nuclear facilities. This programme includes the level 3 decommissioning of the Triton and Nereide piles. These pool type research reactors were constructed in the late 1950's, primarily for R and D activities related to neutron physics studies, radiological shielding experiments and radioelement production. As of 1982, a level 2 decommissioning was achieved and over the the last twenty years, no activities were carried out in the facility. During 2001, there has been extensive investigation work carried out to acquire a better knowledge of the radiological status of the facility, in order to set up dismantling scenarios and to reduce the volume of generated radioactive waste. Indeed, one of the first and main operations to be carried out for dismantling Triton and Nereide piles is waste zoning, by using the facility layout, operating conditions and history, as well as the present radiological inventory. The paper describes the investigations and studies carried out to implement waste zoning. The paper also describes the preliminary dismantling operations undertaken on equipment and studies conducted to optimize the dismantling and cleanup of the facility. Finally, the paper presents the outline of the preferred dismantling and decommissioning options and the progress of the work to date. (author)

  8. Decree no. 2004-48 from January 12, 2004 authorizing the French atomic energy commission to proceed to the definitive decommissioning and dismantling operations of the nuclear facility no. 43, named Saclay linear accelerator (ALS), on the territory of Saint-Aubin town (Essonne); Decret no. 2004-48 du 12 janvier 2004 autorisant le Commissariat a l'energie atomique a proceder aux operations de mise a l'arret definitif et de demantelement de l'installation nucleaire de base no. 43 denommee accelerateur lineaire de Saclay (ALS) sur le territoire de la Commune de Saint-Aubin (Essonne)

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2004-01-01

    The linear accelerator of Saclay (ALS) has been the object of a commissioning permission given by decree by the French prime minister in October 8, 1965. It is submitted to the regime of basic nuclear facilities as defined in the decree no. 63-1228 from December 11, 1963. The French atomic energy commission (CEA) put down a request for the definitive decommissioning and dismantling of this facility on May 30, 2002. The duration foreseen for these operations is of 4 years. After the safety examination of the request by the DGSNR and the institute of radioprotection and nuclear safety (IRSN), a favorable and conformable advice has been given by the different ministries (health, finances and industry, ecology and sustainable development) and has led to this decree which precises the different protection measures to be implemented during the dismantling work. (J.S.)

  9. The management of waste originating from the dismantling of nuclear power stations, a growth business that has yet to be optimized

    International Nuclear Information System (INIS)

    Cahen, B.

    2013-01-01

    The dismantling of a nuclear power plant consists of all the operations undertaken by the operator after the definitive shutdown, until such time that risks to humanity and the environment on the site are strictly limited or totally removed. Thus, the dismantling process may necessitate stripping and decontaminating a building which will be reusable, or it can go as far as the total demolition of machinery, equipment and structures. Cleaning up the land is an integral part of the dismantling brief. In France, dismantling requires prior authorization by government decree, after approval by the Nuclear Safety Authority. The decree stipulates the terms and nature of all the operations to be undertaken and the final state to be obtained by the operator. (author)

  10. Regional Approach to Building Operational Level Capacity for ...

    African Journals Online (AJOL)

    In order to strengthen public health disaster management capacities at the operational level in six countries of the Eastern Africa region, the USAID-funded leadership project worked through the HEALTH Alliance, a network of seven schools of public health from six countries in the region to train district-level teams.

  11. Discovery of high-level tasks in the operating room

    NARCIS (Netherlands)

    Bouarfa, L.; Jonker, P.P.; Dankelman, J.

    2010-01-01

    Recognizing and understanding surgical high-level tasks from sensor readings is important for surgical workflow analysis. Surgical high-level task recognition is also a challenging task in ubiquitous computing because of the inherent uncertainty of sensor data and the complexity of the operating

  12. Decommissioning and Dismantling of the Floating Maintenance Base 'Lepse' - 13316

    Energy Technology Data Exchange (ETDEWEB)

    Field, D.; Mizen, K. [Nuvia Limited (United Kingdom)

    2013-07-01

    The Lepse was built in Russia in 1934 and commissioned as a dry cargo ship. In 1961 she was re-equipped for use as a nuclear service ship (NSS), specifically a floating maintenance base (FMB), to support the operation of the civilian nuclear fleet (ice-breakers) of the USSR. In 1988 Lepse was taken out of service and in 1990 she was re-classified as a 'berth connected ship', located at a berth near the port of Murmansk under the ownership of Federal State Unitary Enterprise (FSUE) Atomflot. Lepse has special storage facilities for spent nuclear fuel assemblies (SFA) that have been used to store several hundred SFAs for nearly 40 years. High and intermediate-level liquid radioactive waste (LRW) is also present in the spent nuclear fuel assembly storage channels, in special tanks and also in the SFA cooling circuit. Many of the SFAs stored in Lepse are classified as damaged and cannot be removed using standard procedures. The removal of the SFA and LRW from the Lepse storage facilities is a hazardous task and requires specially designed tools, equipment and an infrastructure in which these can be deployed safely. Lepse is a significant environmental hazard in the North West of Russia. Storing spent nuclear fuel and high-level liquid radioactive waste on board Lepse in the current conditions is not acceptable with respect to Russian Federation health, safety and environmental standards and with international best practice. The approved concept design for the removal of the SFA and LRW and dismantling of Lepse requires that the ship be transported to Nerpa shipyard where specialist infrastructure will be constructed and equipment installed. One of the main complexities of the Project lies within the number of interested stakeholders involved in the Project. The Lepse project has been high focus on the international stage for many years with previous international efforts failing to make significant progress towards the objective of decommissioning Lepse. The

  13. Component-Level Electronic-Assembly Repair (CLEAR) Operational Concept

    Science.gov (United States)

    Oeftering, Richard C.; Bradish, Martin A.; Juergens, Jeffrey R.; Lewis, Michael J.; Vrnak, Daniel R.

    2011-01-01

    This Component-Level Electronic-Assembly Repair (CLEAR) Operational Concept document was developed as a first step in developing the Component-Level Electronic-Assembly Repair (CLEAR) System Architecture (NASA/TM-2011-216956). The CLEAR operational concept defines how the system will be used by the Constellation Program and what needs it meets. The document creates scenarios for major elements of the CLEAR architecture. These scenarios are generic enough to apply to near-Earth, Moon, and Mars missions. The CLEAR operational concept involves basic assumptions about the overall program architecture and interactions with the CLEAR system architecture. The assumptions include spacecraft and operational constraints for near-Earth orbit, Moon, and Mars missions. This document addresses an incremental development strategy where capabilities evolve over time, but it is structured to prevent obsolescence. The approach minimizes flight hardware by exploiting Internet-like telecommunications that enables CLEAR capabilities to remain on Earth and to be uplinked as needed. To minimize crew time and operational cost, CLEAR exploits offline development and validation to support online teleoperations. Operational concept scenarios are developed for diagnostics, repair, and functional test operations. Many of the supporting functions defined in these operational scenarios are further defined as technologies in NASA/TM-2011-216956.

  14. SGDES: Management system dismantling of ENRESA; SGDES: Sistema de gestion de desmantelamiento de ENRESA

    Energy Technology Data Exchange (ETDEWEB)

    Julian, A. de; Fernandez, M.; Vidaechea, S.

    2013-07-01

    ENRESA, the Spanish public company responsible for managing radioactive waste and nuclear facilities decommissioning, has developed a management information system (SGDES) for the decommissioning of nuclear power plants. Dismantling activities require a rigorous operations control within highly specialized, process systematization and safety framework, both under human and technological point of view. SGDES system is capable of responding to the mentioned operational needs, efficiently and safely.

  15. The Dismantling Project for the Large Electron Positron (LEP) Collider

    CERN Document Server

    Poole, John

    2002-01-01

    The LEP accelerator was installed in a circular tunnel 27 km in length with nine access points distributed around the circumference in the countryside and villages which surround CERN's sites. The dismantling project involved the removal in less than 15 months of around 29000 tonnes of equipment from the accelerator itself and a further 10000 tonnes from the four experiments - all of which were located at an average depth of 100 m below ground level. There was no contamination risk in the project and less than 3% of the materials removed were classified as radioactive. However, the materials which were classified as radioactive have to be temporarily stored and they consume considerable resources. The major difficulties for the project were in the establishment of the theoretical radiological zoning, implementation of the traceability systems and making appropriate radiation measurements to confirm the zoning. The absence of detailed guidelines from the French authorities, having no threshold levels for relea...

  16. Large components dismantlement flow chart in the United States

    International Nuclear Information System (INIS)

    Szilagyi, Andrew

    2012-01-01

    The beginning steps are identical for large or regular components. The starting point of this flowchart assumes that it has already been determined the component has been categorized as waste. The first step is to make sure that all components are handled safely, that ALARA is followed, that any security concerns are managed, and that the dismantlement cost or any other cost is constantly reviewed. After this, the process knowledge and acceptable knowledge should be reviewed; this will help in the following step which is characterization with non-destructive assay. At this point, the project manager is presented with the first three alternatives which will determine the path to follow: Low level waste (LLW) disposal flowchart, part 1 to 3 , Transuranic waste (TRU) disposal flowchart, part 1 and 2 , or High level waste (HLW) disposal flowchart

  17. The dismantling of fast reactors: sodium processing

    International Nuclear Information System (INIS)

    Rodriguez, G.; Berte, M.; Serpante, J.P.

    1999-01-01

    Fast reactors require a coolant that does not slow down neutrons so water can not be used. Metallic sodium has been chosen because of its outstanding neutronic and thermal properties but sodium reacts easily with air and water and this implies that sodium-smeary components can not be considered as usual nuclear wastes. A stage of sodium neutralizing is necessary in the processing of wastes from fast reactors. Metallic sodium is turned into a chemically stable compound: soda, carbonates or sodium salts. This article presents several methods used by Framatome in an industrial way when dismantling sodium-cooled reactors. (A.C.)

  18. Capacitive tool standoff sensor for dismantlement tasks

    International Nuclear Information System (INIS)

    Schmitt, D.J.; Weber, T.M.; Liu, J.C.

    1996-01-01

    A capacitive sensing technology has been applied to develop a Standoff Sensor System for control of robotically deployed tools utilized in Decontamination and Dismantlement (D and D) activities. The system combines four individual sensor elements to provide non-contact, multiple degree-of-freedom control of tools at distances up to five inches from a surface. The Standoff Sensor has been successfully integrated to a metal cutting router and a pyrometer, and utilized for real-time control of each of these tools. Experiments demonstrate that the system can locate stationary surfaces with a repeatability of 0.034 millimeters

  19. Decommissioning and dismantling policy in Spain

    International Nuclear Information System (INIS)

    Landa, J.

    2004-01-01

    Decommissioning and dismantling nuclear installations is an increasingly important topic for governments, regulators, industries and civil society. There are many aspects that have to be carefully considered and planned, in many cases well in advance when they really need to be implemented. In my speech I am going to focus on policy-making considerations. Firstly I will go briefly over the current Spanish strategy on D and D, discussing the know-how we have gained from past experience. Then I will review the challenges that we will have to face in the near future, suggesting possible alternatives and approaches. I will finish talking a little bit about the international scene. (author)

  20. Operating room sound level hazards for patients and physicians.

    Science.gov (United States)

    Fritsch, Michael H; Chacko, Chris E; Patterson, Emily B

    2010-07-01

    Exposure to certain new surgical instruments and operating room devices during procedures could cause hearing damage to patients and personnel. Surgical instruments and related equipment generate significant sound levels during routine usage. Both patients and physicians are exposed to these levels during the operative cases, many of which can last for hours. The noise loads during cases are cumulative. Occupational Safety and Health Administration (OSHA) and National Institute for Occupational Safety and Health (NIOSH) standards are inconsistent in their appraisals of potential damage. Implications of the newer power instruments are not widely recognized. Bruel and Kjaer sound meter spectral recordings for 20 major instruments from 5 surgical specialties were obtained at the ear levels for the patient and the surgeon between 32 and 20 kHz. Routinely used instruments generated sound levels as high as 131 dB. Patient and operator exposures differed. There were unilateral dominant exposures. Many instruments had levels that became hazardous well within the length of an average surgical procedure. The OSHA and NIOSH systems gave contradicting results when applied to individual instruments and types of cases. Background noise, especially in its intermittent form, was also of significant nature. Some patients and personnel have additional predisposing physiologic factors. Instrument noise levels for average length surgical cases may exceed OSHA and NIOSH recommendations for hearing safety. Specialties such as Otolaryngology, Orthopedics, and Neurosurgery use instruments that regularly exceed limits. General operating room noise also contributes to overall personnel exposures. Innovative countermeasures are suggested.

  1. Cutting techniques for facilities dismantling in decommissioning projects

    International Nuclear Information System (INIS)

    Lainetti, Paulo E.O.

    2011-01-01

    Fuel cycle related activities were accomplished in IPEN-CNEN/SP in laboratory and pilot plant scale and most facilities were built in the 70-80 years. Nevertheless, radical changes of the Brazilian nuclear policy in the beginning of 90's determined the interruption of several fuel cycle activities and facilities shutdown. Some laboratory and pilot plant decommissioning activities have been performed in IPEN in the last years. During the operational activities in the decommissioning of old nuclear fuel cycle facilities, the personnel involved in the task had to face several problems. In old facilities, the need of large components dismantling and material removal use to present some difficulties, such as lack of available and near electricity supply. Besides this, the spread out of the superficial contamination in the form of dust or aerosols and the exposure of workers should be as much as possible avoided. Then, the selection and availability of suitable tools for the task, mainly those employed for cutting and segmentation of different materials is of significant importance. Slight hand tools, mainly those powered by rechargeable batteries, facilitate the work, especially in areas where the access is difficult. Based on the experience in the dismantling of some old nuclear facilities of IPEN-CNEN/SP, some tools that would have facilitated the operations were identified and their availability could have improved the quality and efficiency of different individual tasks. In this paper different cutting problems and techniques, as well as some available commercial hand tools, are presented as suggestion for future activities. (author)

  2. Cold trap dismantling and sodium removal at a fast breeder reactor

    Energy Technology Data Exchange (ETDEWEB)

    Graf, Anja; Petrick, Holger; Stutz, Uwe [WAK GmbH, Eggenstein-Leopoldshafen (Germany). Hauptabt. Dekontaminationsbetriebe Rueckbau Kompakte Natriumgekuehlte Kernreaktoranlage (KNK); Hosking, Paul [Nuclear Decommissioning Services Limited (NDSL), Sutherland, Dornoch (United Kingdom)

    2013-11-15

    The first German prototype Fast Breeder Nuclear Reactor (KNK) is currently being dismantled after being the only operating Fast Breeder-type reactor in Germany. As this reactor type used sodium as a coolant in its primary and secondary circuit, 7 cold traps containing various amounts of partially activated sodium needed to be disposed of as part of the dismantling. The resulting combined difficulties of radioactive contamination and high chemical reactivity were handled by treating the cold traps differently depending on their size and the amount of sodium contained inside. Six small cold traps were processed on-site by cutting them up into small parts using a band saw under a protective atmosphere. The sodium was then converted to sodium hydroxide by using water. The remaining large cold trap could not be handled in the same way due to its dimensions (2.9 m x 1.1 m) and the declared amount of sodium inside (1,700 kg). It was therefore manually dismantled inside a large box filled with a protective atmosphere, while the resulting pieces were packaged for later burning in a special facility. The experiences gained by KNK during this process may be advantageous for future dismantling projects in similar sodium-cooled reactors worldwide. (orig.)

  3. The Dismantling of Nuclear Installations in France

    International Nuclear Information System (INIS)

    Bonnaure, P.

    2011-01-01

    As we saw in the previous article by Pierre Bonnaure, though it has long been decried for the dangers inherent in its production structures and the very long-lived waste that it generates, nuclear power may yet recover its credibility, particularly in France. However, on close examination, we see that the nuclear industry is beset by a number of unresolved questions, beginning with the dismantling of installations that have become obsolete or are set to become so. Nuclear power took off after the Second World War, but several generations of technology have been developed since then, and most currently functioning power-stations - mainly second-generation installations - are theoretically nearing the end of their useful lives, at least in terms of what was said when they were being built. The problem therefore arises of their dismantling and the clean-up of the sites on which they were built, a thorny question on which Pierre Bonnaure casts light in this article (prospects, strategies, financing, management of waste etc.). Unfortunately, it emerges that in France nothing has really been resolved, that public debate on the matter is decidedly limited and that investment (both financial investment and research) is not commensurate with the needs of a sector which is, after all, the source of three quarters of national electricity production. (author)

  4. Decontamination and dismantlement plan for international reviewing

    International Nuclear Information System (INIS)

    Wells, P.B.; Earle, O.K.; Klepikov, A.Kh.

    2000-01-01

    When developing a decommissioning plan, several factors need to be included. First and foremost is the issue of outline and scope. Specific to the BN-350, are issues related to short term tasks required to support the safe storage of the reactor for the next 50 years, and long term tasks required to dismantle the reactor, leaving some sort of final state, (brown field, green field, etc.) In addition, issues such as personnel and physical safety as well as environmental concerns must be addressed to ensure the shut down and dismantlement of the reactor is done in a safe manner, both for personnel and the environment. In addition to being the base document in which to support work, a D and D plan can also be utilized to obtain financial resources necessary to complete the plan, as is the case for the BN-350 Reactor located in Aktau, Kazakhstan. By providing a clear and complete D and D plan, which includes costs and schedules for each item, it is anticipated that donor countries will have the ability to review, approve, and provide financial support to complete the work described in the plan

  5. Clearance of radioactive materials during reactor dismantling. Permanent enclosure instead of demolition and renaturation?; Freigabe radioaktiven Materials beim AKW-Abriss. Dauerhafter Einschluss statt Rueckbau?

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2016-07-01

    During reactor dismantling besides high-level radioactive wastes a large amount of low-level contaminated steel and concrete has to be disposed. In case that radioactivity falls below defined dose limits (10 micro Sv/person and year) these materials may be disposed in domestic waste landfill or in municipal incineration facilities. The issue is discussed in detail including the fact that many power plants are dismantled at the same time so that the contaminated materials might accumulate. Another issue is the occupational safety of contract workers during dismantling. The permanent enclosure could avoid this environmental contamination of decommissioned power plants might also be less expensive.

  6. Cleanup and Dismantling of Highly Contaminated Ventilation Systems Using Robotic Tools - 13162

    International Nuclear Information System (INIS)

    Chambon, Frederic; CIZEL, Jean-Pierre; Blanchard, Samuel

    2013-01-01

    The UP1 plant reprocessed nearly 20,000 tons of used natural uranium gas cooled reactor fuel coming from the first generation of civil nuclear reactors in France. Following operating incidents in the eighties, the ventilation system of the continuous dissolution line facility was shut down and replaced. Two types of remote controlled tool carriers were developed to perform the decontamination and dismantling operations of the highly contaminated ventilation duct network. The first one, a dedicated small robot, was designed from scratch to retrieve a thick powder deposit within a duct. The robot, managed and confined by two dedicated glove boxes, was equipped for intervention inside the ventilation duct and used for carrying various cleanup and inspection tools. The second type, consisting of robotic tools developed on the base of an industrial platform, was used for the clean-up and dismantling of the ventilation duct system. Depending on the type of work to be performed, on the shape constraints of the rooms and any equipment to be dismantled, different kinds of robotic tools were developed and installed on a Brokk 40 carrier. After more than ten years of ventilation duct D and D operations at the UP1 plant, a lot of experience was acquired about remote operations. The three main important lessons learned in terms of remote controlled operation are: characterizing the initial conditions as much as reasonably possible, performing non-radioactive full scale testing and making it as simple and modular as possible. (authors)

  7. Cleanup and Dismantling of Highly Contaminated Ventilation Systems Using Robotic Tools - 13162

    Energy Technology Data Exchange (ETDEWEB)

    Chambon, Frederic [AREVA FEDERAL SERVICES, Columbia MD (United States); CIZEL, Jean-Pierre [AREVA BE/NV, Marcoule (France); Blanchard, Samuel [CEA DEN/DPAD, Marcoule (France)

    2013-07-01

    The UP1 plant reprocessed nearly 20,000 tons of used natural uranium gas cooled reactor fuel coming from the first generation of civil nuclear reactors in France. Following operating incidents in the eighties, the ventilation system of the continuous dissolution line facility was shut down and replaced. Two types of remote controlled tool carriers were developed to perform the decontamination and dismantling operations of the highly contaminated ventilation duct network. The first one, a dedicated small robot, was designed from scratch to retrieve a thick powder deposit within a duct. The robot, managed and confined by two dedicated glove boxes, was equipped for intervention inside the ventilation duct and used for carrying various cleanup and inspection tools. The second type, consisting of robotic tools developed on the base of an industrial platform, was used for the clean-up and dismantling of the ventilation duct system. Depending on the type of work to be performed, on the shape constraints of the rooms and any equipment to be dismantled, different kinds of robotic tools were developed and installed on a Brokk 40 carrier. After more than ten years of ventilation duct D and D operations at the UP1 plant, a lot of experience was acquired about remote operations. The three main important lessons learned in terms of remote controlled operation are: characterizing the initial conditions as much as reasonably possible, performing non-radioactive full scale testing and making it as simple and modular as possible. (authors)

  8. Operate to Know: An Operational and Intelligence for the Operational Level of War

    Science.gov (United States)

    2014-06-13

    operationalizing induction, redefining the role of the commander as well as rebalancing the functions of operations and intelligence. Complexity...the Task: A Memoir (New York: Portfolio Hardcover, 2013), 149-154. 68 Mitchell, Complexity: A Guided Tour, 169-185. 47 a mix of both passive...Wehrmacht evolved as a result of a rebalancing and harmonizing of physical-military capabilities, a new combined arms system is emerging where intelligence

  9. Process cells dismantling of EUREX pant: previous activities

    International Nuclear Information System (INIS)

    Gili, M.

    1998-01-01

    In the '98-'99 period some process cells of the EUREX pant will be dismantled, in order to place there the liquid wastes conditioning plant 'CORA'. This report resumes the previous activities (plant rinsing campaigns and inactive Cell 014 dismantling), run in the past three years and the drawn experience [it

  10. The Japan Power Demonstration Reactor dismantling project. Radiation control

    International Nuclear Information System (INIS)

    Tomii, Hiroyuki; Seiki, Yoshihiro

    1996-01-01

    In the Japan Power Demonstration Reactor (JPDR) dismantling project, radiation control was performed properly with routine and special monitoring to keep the occupational safety and to collect data necessary for future dismantling of nuclear facilities. This report describes a summary of radiation control in the dismantling activities and some results of parametric analysis on dose equivalent evaluation, and introduces the following knowledge on radiological protection effectiveness of the dismantling systems applied in the project. a) Use of remote dismantling systems was effective in reducing equivalent workplace exposure. b) Utilization of existing facilities as radiation shield or radioactivity containment was effective in reducing workplace exposure, and also in increasing work efficiency. c) Use of underwater cutting systems was useful to minimize air contamination, and to reduce the dose equivalent rate in the working area. d) In the planning of dismantling, it is necessary to optimize the radiation protection by analyzing dismantling work procedures and evaluating radiological features of the dismantling systems applied, including additional work which the systems require brought from such activities. (author)

  11. Shielded Cells D ampersand D and Dismantlement System Requirements

    International Nuclear Information System (INIS)

    Witherspoon, R.L.

    1995-01-01

    This document describes the basis for the development of the System for Highly Radioactive Equipment Dismantlement or SHRED. It is the result of a thorough investigation into current and past dismantlement practices at shielded cell facilities around the DOE complex. This information has been used to formulate the development requirements for the SHRED

  12. Cleaning and dismantling of a high activity laboratory (abstract and presentation slides)

    Energy Technology Data Exchange (ETDEWEB)

    Bredel; Thierry; Buzare, Alain

    2005-01-01

    The high activity laboratories have been built at the end of the 50ies. The particularity of this facility was that about 14 different laboratories worked in 14 different fields (biology, production of Cs and Cf sources, metallurgy, mechanical testing ...). Because of the optimization of the nuclear research, the CEA decided to close progressively this facility and to transfer the different experiments in other places. This action began in 1997 and is planed to end in 2010. 6 laboratories have been closed from 1997 to 2001 and the dismantling of the shielded cells has begun since 2002. Therefore, several laboratories have been cleaned of the materials and experiments. Nevertheless, the main particularity of this subject is that some experimental activities have been pursued during the cleaning and dismantling of other laboratories. For example, we describe the dismantling of the laboratory that performed metallurgical and mechanical characterization of irradiated materials. This laboratory occupied 20 lead cells and 2 glove boxes. The exploitation of those cells has been stopped progressively (12 at the end of 2001 and 5 at the end of 2003). The end of the last 3 cell exploitation is planed to end 2005. Since the end of 2001, 9 lead cells have been cleaned. Their dismantling is planed for next the two years. In parallel, we will clean all the other cells. During this phase we will have also to transfer all the irradiated samples (about 5000) that are still in the laboratory to the waste treatment facility of the CEA centre or to the new laboratory which has been presented during the previous hotlab meeting in Saclay. The paper gives details for background about ended operations: Organization, waste production, specific designs which improve radioprotection, waste destinations and costs, Difficulties and feedback experience of dismantling. (Author)

  13. Education and research when dismantling nuclear plants at the Technical University Dresden

    International Nuclear Information System (INIS)

    Hurtado, A.; Anthofer, A.; Cloppenborg, T.; Schreier, M.

    2013-01-01

    With the decision by the German government in 2011 to revoke the operating permission from 8 of the existing 17 German nuclear power plants, the responsibility of decommissioning and dismantling these plants has moved back into the focus of public awareness. Under the current legal conditions, the last nuclear plant will be disconnected from the grid on 31.12.2022 and this will create an enormous challenge for all the involved approving authorities, expert organisations, as well as companies involved in dismantling the plants. The development of new and efficient dismantling technologies and strategies is required to perform these highly responsible tasks. On the other hand, the nuclear competence and knowhow, as well as the promotion of young talents in the relevant scientific fields must be preserved. Technological and economic solutions are in demand for the various plants due to the different specifics of nuclear power plants. This will still require e.g. in the field of radiation protection highly qualified and well trained staff in future. The training of these skilled employees will require expanding the subject matter taught at universities, colleges and polytechnics to suit the changed parameters. The chair for hydrogen and nuclear energy technology at the TU Dresden will in future offer lectures as part of a new teaching discipline with the focus on dismantling and disposal. The course 'Dismantling nuclear power plants' took place for the first time in the summer semester 2013. It is organised as a three-day block seminar with an excursion to the company NIS Ingenieurgesellschaft mbH in Alzenau. The company NIS is a subsidiary of the Siempelkamp Nukleartechnik GmbH. This article intends to provide an overview of the contents of the courses and the impressions of the participants. In this way the TU Dresden is making a further contribution to preserving nuclear competence and inter-disciplinary dialogue. (orig.)

  14. Radiological impact of very slightly radioactive copper and aluminium recovered from dismantled nuclear facilities

    International Nuclear Information System (INIS)

    Garbay, H.; Chapuis, A.M.; Cahuzac, O.; Guetat, P.; Haristoy, D.; Renaud, P.

    1991-01-01

    This work is in keeping with a large evaluation of doses likely to be received by public and non nuclear workers when dismantling nuclear installations. A bibliographic study and inquiries are realized, in the nuclear field to evaluate quantities of very slightly radioactive materials, in the conventional copper and aluminium recovery fields: waste recovery, metal refinery and processing, occupational or domestic uses of the metals or their alloys. In fact copper and aluminium waste arising from the dismantling of nuclear installations are mainly electrical cables constituents including insulation material which is mainly polyvinyle chloride (PVC). Estimated quantities are relatively low compared to steel quantities arising from dismantling. The study is based on the hypothesis of two PWRs dismantled per year, estimated quantities are 200 tonnes of copper, 40 tonnes of aluminium and 500 tonnes of PVC. A special case is also studied, which is the dismantling of low and medium uranium enrichment plant in Pierrelatte (France); the plant pipework is mainly made of an aluminium and magnesium alloy: AG3. From these informations, one can define exposure scenarios which may occur with a non negligible probability. The doses likely to be received under the foreseen conditions are calculated. Reference doses are established from recommendations of international organisations as ICRP, IAEA, NEA. Comparing the calculated doses and the reference doses, the activity level of the initial waste can be deduced as to follow the recommendations. The mean specific activity of main beta-gamma emitters in copper, aluminium and PVC are of the same order of magnitude, 10Bq.g -1 . In the case of alpha emitters specific activity levels depend on the material and on the radionuclide, from 2 Bq.g -1 to 10 Bq.g -1 in copper, from 10 Bq.g -1 to 50 Bq.g -1 in aluminium

  15. Development and evaluation of a dismantling planning support system based on augmented reality technology

    International Nuclear Information System (INIS)

    Ishii, Hirotake; Oshita, Satoshi; Yan Weida; Shimoda, Hiroshi; Izumi, Masanori

    2011-01-01

    For this study, a Dismantling Planning Support System (DPSS) based on Augmented Reality technology was developed. Its effectiveness and applicability to a real working field were evaluated using a subjective experiment. The DPSS operators can simulate how to locate scaffolding and temporary enclosures (greenhouses) in a real dismantling field in order to decide their layout and to predict the amounts of necessary parts. An interview and questionnaire survey were conducted with Fugen Decommissioning Engineering Center (DEC) staff and a human interface expert, who used DPSS along with a scenario in which scaffolding and greenhouses were located in a turbine cooling water room of Fugen DEC. The experimental results show that the operation for locating the virtual scaffolding and greenhouses using marker boards is intuitive and comprehensive. However, additional research needs to be undertaken in order to improve the DPSS, particularly with respect to its graphical user interface. (author)

  16. Low-level radioactive gas monitor for natural gas operations

    International Nuclear Information System (INIS)

    Armstrong, F.E.

    1969-11-01

    A portable radioactivity detection system for monitoring the tritium content of natural gas under field conditions has been developed. The sensing device employed is a complex proportional counting assembly operated without the use of massive shielding previously employed with such low-level radiation detectors. The practical limit of detection for the system is a tritium content of 10 -9 microcurie per cc of natural gas. All components of the system are packaged in three waterproof cases weighing slightly less than 30 kg each. Power requirement is 500 watts of 120 volt, 60 Hz current. Operation is fully automatic with a printed record produced at predetermined time intervals

  17. Computerized low-level waste assay system operation manual

    International Nuclear Information System (INIS)

    Jones, D.F.; Cowder, L.R.; Martin, E.R.

    1976-01-01

    An operation and maintenance manual for the computerized low-level waste box counter is presented, which describes routine assay techniques as well as theory of operation treated in sufficient depth so that an experienced assayist can make nonroutine assays. In addition, complete system schematics are included, along with a complete circuit description to facilitate not only maintenance and troubleshooting, but also reproduction of the instrument if desired. Complete software system descriptions are included so far as calculational algorithms are concerned, although detailed instruction listings would have to be obtained from Group R-1 at LASL in order to make machine-language code changes

  18. Sandia National Laboratories support of the Iraq Nuclear Facility Dismantlement and Disposal Program.

    Energy Technology Data Exchange (ETDEWEB)

    Cochran, John Russell; Danneels, Jeffrey John

    2009-03-01

    Because of past military operations, lack of upkeep and looting there are now enormous radioactive waste problems in Iraq. These waste problems include destroyed nuclear facilities, uncharacterized radioactive wastes, liquid radioactive waste in underground tanks, wastes related to the production of yellow cake, sealed radioactive sources, activated metals and contaminated metals that must be constantly guarded. Iraq currently lacks the trained personnel, regulatory and physical infrastructure to safely and securely manage these facilities and wastes. In 2005 the International Atomic Energy Agency (IAEA) agreed to organize an international cooperative program to assist Iraq with these issues. Soon after, the Iraq Nuclear Facility Dismantlement and Disposal Program (the NDs Program) was initiated by the U.S. Department of State (DOS) to support the IAEA and assist the Government of Iraq (GOI) in eliminating the threats from poorly controlled radioactive materials. The Iraq NDs Program is providing support for the IAEA plus training, consultation and limited equipment to the GOI. The GOI owns the problems and will be responsible for implementation of the Iraq NDs Program. Sandia National Laboratories (Sandia) is a part of the DOS's team implementing the Iraq NDs Program. This report documents Sandia's support of the Iraq NDs Program, which has developed into three principal work streams: (1) training and technical consultation; (2) introducing Iraqis to modern decommissioning and waste management practices; and (3) supporting the IAEA, as they assist the GOI. Examples of each of these work streams include: (1) presentation of a three-day training workshop on 'Practical Concepts for Safe Disposal of Low-Level Radioactive Waste in Arid Settings;' (2) leading GOI representatives on a tour of two operating low level radioactive waste disposal facilities in the U.S.; and (3) supporting the IAEA's Technical Meeting with the GOI from April 21

  19. Sea Level Forecasts Aggregated from Established Operational Systems

    Directory of Open Access Journals (Sweden)

    Andy Taylor

    2017-08-01

    Full Text Available A system for providing routine seven-day forecasts of sea level observable at tide gauge locations is described and evaluated. Forecast time series are aggregated from well-established operational systems of the Australian Bureau of Meteorology; although following some adjustments these systems are only quasi-complimentary. Target applications are routine coastal decision processes under non-extreme conditions. The configuration aims to be relatively robust to operational realities such as version upgrades, data gaps and metadata ambiguities. Forecast skill is evaluated against hourly tide gauge observations. Characteristics of the bias correction term are demonstrated to be primarily static in time, with time varying signals showing regional coherence. This simple approach to exploiting existing complex systems can offer valuable levels of skill at a range of Australian locations. The prospect of interpolation between observation sites and exploitation of lagged-ensemble uncertainty estimates could be meaningfully pursued. Skill characteristics define a benchmark against which new operational sea level forecasting systems can be measured. More generally, an aggregation approach may prove to be optimal for routine sea level forecast services given the physically inhomogeneous processes involved and ability to incorporate ongoing improvements and extensions of source systems.

  20. Evaluation of Radiation Exposure during Construction and Operation of Concrete Bridge Reinforced with Very Low Level Radioactive Steel

    International Nuclear Information System (INIS)

    Panik, M.; Necas, V.

    2012-01-01

    A lot of nuclear power plants are approaching the end of their lifetime and they will be phased out. Decommissioning of these nuclear power plants involve complete dismantling of technologies and demolition of buildings. During this process it is produced plenty of waste material of different categories. Significant portion of decommissioning materials comprise radionuclides what is caused by contamination and activation processes mostly from the operational period of nuclear power plant. Attention in this paper is paid to waste steel from the decommissioning of nuclear power plants with the specific activity just slightly exceeding legislation limits for the unconditional release into the environment. From the traditional point of view this material should be treated, conditioned and disposed on the radioactive waste repository. Second possibility is to release this material conditionally and reuse it in chosen industrial application. Very low level radioactive steel scrap should be melted and melting products should be processed into products that can be applied in industry. First option requires considerable financial investment, human resources and repository capacity. Second option saves some financial funds and it enables to reuse and save potentially valuable material for the future. Paper comprises evaluation of external and internal exposure during construction and operation of concrete bridges that utilize very low level radioactive steel as part of their reinforcement. Two models of representative concrete bridges were created. External gamma exposure and exposure from inhalation and ingestion of radionuclides were calculated using suitable computational tools. VISIPLAN 3D ALARA planning tool was chosen for the calculation of external gamma exposure. Software GOLDSIM enables to calculate transport of radionuclides initially contained in conditionally released reinforcement steel through subsoil and sequential exposure of people caused by inhalation of

  1. Decommissioning and dismantling of 305-M test pile at the Savannah River Plant

    International Nuclear Information System (INIS)

    Horton, H.L.

    1985-01-01

    The 305-M Test Pile was started up at the Savannah River Plant in 1952 and operated until 1981. The pile was used to measure the uranium content of reactor fuel. In 1984 work began to decommission and dismantle the pile. Extensive procedures were used that included a detailed description of the radiological controls and safety measures. These controls allowed the job to be completed with radiation doses as low as reasonably achievable

  2. Decommissioning and dismantling of nuclear installations

    International Nuclear Information System (INIS)

    Pelzer, N.

    1993-01-01

    The German law governing decommissioning and dismantling of nuclear installations can be called to be embryonic as compared to other areas of the nuclear regulatory system, and this is why the AIDN/INLA regional meeting organised by the German national committee in July 1992 in Schwerin has been intended to elaborate an assessment of the current legal situation and on this basis establish proposals for enhancement and development, taking into account the experience reported by experts from abroad. The proceedings comprise the paper of the opening session, 'Engineering and safety aspects of the decommissioning of nuclear installations', and the papers and discussions of the technical sessions entitled: - Comparative assessment of the regulatory regimes. - Legislation governing the decommissioning of nuclear installations in Germany. - Analysis of the purpose and law making substance of existing regulatory provisions for the decommissioning of nuclear installations. All seventeen papers of the meeting have been prepared for separate retrieval from the database. (orig./HSCH) [de

  3. The Grenoble CEA Center: dismantled and rehabilitated

    International Nuclear Information System (INIS)

    Anon.

    2013-01-01

    The denuclearization program of the CEA center in Grenoble was launched in 2001. It involves 6 nuclear facilities (3 research reactors: Melusine, Siloette, and Siloe, and 1 laboratory (LAMA) and 2 units for processing wastes). The dismantling works were finished at the end of 2012 and the 2013 program concerns: the demolition of the buildings homing Melusine and Siloe reactors, the final rehabilitation of the Siloe raft, and the final rehabilitation of the laboratory and of the waste processing units. The budget is 117*10 6 euros for Siloe, 28*10 6 euros for Melusine, 6*10 6 euros for Siloette, 70*10 6 euros for the LAMA, and 90*10 6 euros for the 2 waste processing units. (A.C.)

  4. Heat sink management during CANDU low level operation

    International Nuclear Information System (INIS)

    Wang Liansheng

    2008-01-01

    This paper introduces the practice of low-level operation with opening on the main heat transport system during an outage for a Candu-6 nuclear power plant, analyses the risks of losing heat sink during this condition, and points out the safety measures and management requirement for controlling such risks. This paper can be used as a reference for improving and optimizing the heat sink management for the coming outages. (author)

  5. The dismantling of nuclear installations in the Grenoble CEA centre - Press book 2013

    International Nuclear Information System (INIS)

    Laveissiere, Stephane; Coronini, Vincent

    2013-01-01

    After having outlined the importance of the project for the Grenoble CEA centre, this document presents the objectives, issues and challenges of dismantling activities performed on various nuclear installations located in the CEA centre of Grenoble. Objectives are presented in terms of agenda, predicted production of radioactive wastes, budget, personnel and steering committee. The various nuclear installations are presented: experimental reactors (Melusine, Siloe, Siloette), LAMA (laboratory of analysis of active materials), STED (station for the treatment of effluents and wastes). The safety and protection of workers is addressed in terms of protection and monitoring measures, and of exposure to radiations. The next part deals with the monitoring of the environment (actors, history of control of the centre's releases, control points, releases, atmosphere monitoring, and hydrological monitoring). A second part presents the global strategy of the CEA for its activities of sanitation and nuclear dismantling: present operations, dismantling activities in Fontenay-aux-Roses and in Marcoule, economic organization, contribution of advanced technology in radiological measurement and control, simulation and modelling, decontamination techniques, cutting operations, and remotely controlled operations

  6. Dismantling of nuclear facilities: the industrial know-how

    International Nuclear Information System (INIS)

    Lellament, R.

    2004-01-01

    Numerous nuclear facilities in laboratories or research reactors have been decommissioned and dismantled over the 2 last decades throughout the world. The valuable feedback experience has allowed nuclear industry to design, upgrade and test specific techniques for dismantling. These techniques are efficient although they have been validated on a reduced number of nuclear power plants. In France only 3 power units have been dismantled: Chinon A1, A2 and Brennilis (EL4) and they are not representative of the real park of EDF'reactors. 6 PWR-type reactors have already been dismantled in the Usa. The results of a survey concerning 26 countries shows that the dismantling cost is around 320 dollars/kWe, it represents 15% of the construction cost which is far from being excessive as it is often read in the media. The dismantling costs can be broken into: - de-construction (25-55%), - wastes from dismantling (17-43%), - security and monitoring (8-13%), - site reclamation (5-13%), and - engineering and project management (5-24%). (A.C.)

  7. The dismantling of nuclear installations: The dismantling of nuclear installations at the CEA's Directorate for nuclear energy; The CEA's sanitation and dismantling works: example of one of the Marcoule UP1 program lots; Research and innovation in sanitation-dismantling; Global optimisation of the management of dismantling radioactive wastes

    International Nuclear Information System (INIS)

    Hauet, Jean-Pierre; Piketty, Laurence; Moitrier, Cyril; Blanchard, Samuel; Soulabaille, Yves; Georges, Christine; Dutzer, Michel; Legee, Frederic

    2016-01-01

    This publication proposes a set of four articles which addresses issues related to the dismantling of nuclear installations in France, notably for the different involved actors such as the CEA and the ANDRA. The authors more particularly address the issue and the general strategy of dismantling within the Directorate for nuclear energy of the CEA; comment the example of one of the Marcoule UP1 program lots to highlight sanitation and dismantling works performed by the CEA; discuss current research and innovation activities within the CEA regarding sanitation and dismantling; and comment how to globally optimise the management of radioactive wastes produced by dismantling activities

  8. Evaluation formulas of manpower needs for dismantling of equipment in FUGEN-3. Dismantling process of the condenser removal

    International Nuclear Information System (INIS)

    Kubota, Shintaro; Izumo, Sari; Usui, Hideo; Kawagoshi, Hiroshi; Koda, Yuya; Nanko, Takashi

    2014-07-01

    Japan Atomic Energy Agency (JAEA) has been developing the PRODIA code which supports to make decommissioning plan and has been preparing evaluation formulas. Manpower needs for the dismantling of the condenser that had conducted from 2010 to 2012 was analyzed and compared with existing evaluation formulas. Applicability of evaluation formulas for a large scale reactor facility was confirmed in dismantling of the heat insulating materials and reliability of unit productivity factor was improved. The evaluation formula of work for clearance was made in dismantling of pipes and supports. Unit productivity factor of dismantling of feed water heaters which is applicable for a large scale reactor facility was derived. For derivation of unit productivity factor, statistically meaningful data was provided from the dismantling of the condenser. Manpower needs for dismantling of the condenser has positive correlation to the weight of equipment and can be described in linear expression. Reliability of each unit productivity factor will be improved with accumulating actual dismantling data in future. (author)

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

    International Nuclear Information System (INIS)

    Kersten, J.K.

    1998-01-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

    Kersten, J.K.

    1998-02-19

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

  11. Dismantlement and removal of Old Hydrofracture Facility bulk storage bins and water tank, Oak Ridge National Laboratory, Oak Ridge, Tennessee

    International Nuclear Information System (INIS)

    1998-03-01

    The Old Hydrofracture Facility (OHF), located at Oak Ridge National Laboratory (ORNL), was constructed in 1963 to allow experimentation and operations with an integrated solid storage, mixing, and grout injection facility. During its operation, OHF blended liquid low-level waste with grout and used a hydrofracture process to pump the waste into a deep low-permeable shale formation. Since the OHF Facility was taken out of service in 1980, the four bulk storage bins located adjacent to Building 7852 had deteriorated to the point that they were a serious safety hazard. The ORNL Surveillance and Maintenance Program requested and received permission from the US Department of Energy to dismantle the bins as a maintenance action and send the free-released metal to an approved scrap metal vendor. A 25,000-gal stainless steel water tank located at the OHF site was included in the scope. A fixed-price subcontract was signed with Allied Technology Group, Inc., to remove the four bulk storage bins and water tank to a staging area where certified Health Physics personnel could survey, segregate, package, and send the radiologically clean scrap metal to an approved scrap metal vendor. All radiologically contaminated metal and metal that could not be surveyed was packaged and staged for later disposal. Permissible personnel exposure limits were not exceeded, no injuries were incurred, and no health and safety violations occurred throughout the duration of the project. Upon completion of the dismantlement, the project had generated 53,660 lb of clean scrap metal (see Appendix D). This resulted in $3,410 of revenue generated and a cost avoidance of an estimated $100,000 in waste disposal fees

  12. The Molten Salt Reactor option for beneficial use of fissile material from dismantled weapons

    International Nuclear Information System (INIS)

    Gat, U.; Engel, J.R.; Dodds, H.L.

    1991-01-01

    The Molten Salt Reactor (MSR) option for burning fissile fuel from dismantled weapons is examined. It is concluded that MSRs are very suitable for beneficial utilization of the dismantled fuel. The MSRs can utilize any fissile fuel in continuous operation with no special modifications, as demonstrated in the Molten Salt Reactor Experiment. Thus MSRs are flexible while maintaining their economy. MSRs further require a minimum of special fuel preparation and can tolerate denaturing and dilution of the fuel. Fuel shipments can be arbitrarily small, all of which supports nonproliferation and averts diversion. MSRs have inherent safety features which make them acceptable and attractive. They can burn a fuel type completely and convert it to other fuels. MSRs also have the potential for burning the actinides and delivering the waste in an optimal form, thus contributing to the solution of one of the major remaining problems for deployment of nuclear power. 19 refs

  13. Operational experience with Seibersdorf low-level incinerator

    International Nuclear Information System (INIS)

    Chalupa, G.

    1987-01-01

    This report contains information about an excess air incinerator which burned low level β and γ wastes (also α up to determined limits). The incinerator was started up in 1980 and it is clear that in a technical plant of such magnitude, some changes and alterations will be needed to be overcome according to the experiences of operation. This paper - after a short description of the incinerator plant itself - gives a summary of some of the operation and the changes which are made in the plant according to these facts. A partial redesign of the incinerator plant in the first half of 1985 resulted in a very satisfying new design, which proved its superiority during the runs in 1985 and 1986

  14. Tools and tool application for the dismantling of the nuclear power plant Brennilis in France

    International Nuclear Information System (INIS)

    Bienia, Harald; Welbers, Philipp; Krueger, Peter; Noll, Thomas

    2012-01-01

    The EL-4 reactor in the NPP Brennilis in France is a CO2 cooled heavy water moderated test reactor with net power of 70 MW, the reactor started operation in 1967 and was decommissioned in 1985. Due to the construction features it was not necessary to enter the reactor area during operation, therefore the reactor pressure vessel and the surrounding piping systems are built in a very compact way. The dismantling procedures are therefore different from German BWR or PWR systems, the remote cutting and handling tools have to be adapted to the different features. Because of the high local dosage rate in the reactor hall it is also necessary to perform the erection of the dismantling equipment by robot systems. For cutting of the piping system a new plasma cutting technique, the hot wire method will be used. Other mechanical cutting techniques have to be used for instance for zircaloy containing components due to fire prevention purposes. The required time for tool and manipulator changes, including wearing part replacements constitute a significant part of the dismantling schedule. The suction/exhaust system for radioactive dust removal allowed a reduction of the total personal dose by one third of the allowed dose.

  15. Decontamination and radioactivity measurement on building surfaces related to dismantling of Japan power demonstration reactor (JPDR)

    International Nuclear Information System (INIS)

    Hatakeyama, Mutsuo; Tachibana, Mitsuo; Yanagihara, Satoshi

    1997-12-01

    In the final stage of dismantling activities for decommissioning a nuclear power plant, building structures have to be demolished to release the site for unrestricted use. Since building structures are generally made from massive reinforced concrete materials, it is not a rational way to treat all concrete materials arising from its demolition as radioactive waste. Segregation of radioactive parts from building structures is therefore indispensable. The rational procedures were studied for demolition of building structures by treating arising waste as non-radioactive materials, based on the concept established by Nuclear Safety Commission, then these were implemented in the following way by the JPDR dismantling demonstration project. Areas of the JPDR facilities are categorized into two groups : possibly contaminated areas, and possibly non-contaminated areas, based on the document of the reactor operation. Radioactivity on the building surfaces was then measured to confirm that the qualitative categorization is reasonable. After that, building surfaces were decontaminated in such a way that the contaminated layers were removed with enough margin to separate radioactive parts from non-radioactive building structures. Thought it might be possible to demolish the building structures by treating arising waste as non-radioactive materials, confirmation survey for radioactivity was conducted to show that there is no artificial radioactive nuclides produced by operation in the facility. This report describes the procedures studied on measurement of radioactivity and decontamination, and the results of its implementation in the JPDR dismantling demonstration project. (author)

  16. Nuclear and non-nuclear safety aspects in nuclear facilities dismantling. The example of a PWR pilot decommissioning project

    International Nuclear Information System (INIS)

    Massaut, V.; Deboodt, P.; Dadoumont, J.; Valenduc, P.; Denissen, L.

    2002-01-01

    The dismantling of nuclear facilities, and in particular of nuclear power plants, involves new challenges for the nuclear industry. Although the dismantling of various activated and contaminated components is nowadays considered as almost industrial practice, the safety aspects of decommissioning bring some specific features which are not always taken into account in the operation of the plants. Moreover, most of the plants and facilities currently decommissioned are rather old and were never foreseen to be decommissioned. The operations involved in dismantling and decontamination, often imply new or unforeseen situations. On the nuclear, or radiological side, the radioprotection optimisation of the operations involved often requires to model the environment and to analyse different scenarios to tackle the operation. Recent 3-D software (like the Visiplan software) allowing representation of the actual environment and the influence of the various sources present, is really needed to be able to minimise the radiological impact on the operators. The risk of contamination spread, by opening loops and components or by the dismantling process itself, is also an important aspect of the radiological protection study. Nevertheless, the radiological aspects of the safety approach are not the only ones to be dealt with when decommissioning nuclear facilities. Indeed, classical industrial safety aspects are also important: the dismantling can bring handling and transporting risk (heavy loads, difficult ways, uneasy access, etc.) but also the handling of toxic or hazardous materials. For instance, the removal of asbestos in contaminated areas can lead to additional hazard; the presence of alkali metals (like Na or NaK), of toxic metals (like e.g. Beryllium) or of corrosive fluids (acid,...) have to be tackled often in unstructured environment, and sometimes with limited knowledge of the actual situation. This leads to approach the operations following the ASARA principle (As

  17. The management of radioactive wastes and the dismantling of nuclear installations in Spain

    International Nuclear Information System (INIS)

    Bouchet, Bertrand

    2014-08-01

    This report first presents the Spanish institutional framework, briefly presents the multi-year national plan of management of radioactive wastes, and indicates the origin and volume of radioactive wastes produced in Spain. It addresses the management of low and medium level wastes, the case of spent fuel and high level wastes (storage in pool and installations of temporary warehousing, project of a centralized temporary storage, the question of definitive management), and proposes an overview of R and D activities in the different domains of waste management in Spain: waste technology, technologies and processes of treatment, packaging and dismantling, materials and containment systems, behaviour and safety assessment, radiological protection and associated modelling, infrastructure and cooperation. The two last parts briefly address the funding of waste management and the dismantling of nuclear installations

  18. LEXICAL OPERATIONS AND HIGH -LEVEL SYNTACTIC OPERATIONS WITH OLD ENGLISH -A, -E, -O, AND -U

    Directory of Open Access Journals (Sweden)

    Miguel Lacalle Palacios

    2011-10-01

    Full Text Available The aim of this article is to explain the lexical and high-level syntactic operations comprising the Old English suffixes -a, -e, -o and -u. Previous research has dealt with these suffixes, which constitute an area of overlapping between inflection and derivation, in terms of inflection, zero derivation or continuity between inflection and derivation. The position adopted in this article is that these affixes are fully derivational, although interesting points of convergence with inflection arise that deserve discussion. In this respect, a fundamental difference is made between explicit and implicit morphological relations. Such relations are considered in the derivational and the inflectional dimensions. Regarding lexical operations, the analysis concentrates on the subjective and objective functions realized by these suffixes, while, as far as high-level syntactic operations are concerned, a distinction is drawn between motivated and unmotivated inflective relations. The fact that most of the suffixes under scrutiny perform the subjective and the objective function is in keeping with the Separation Hypothesis, in terms of which grammatical morphemes are the output of phonological operations independent of the semantic operations that they realize. The results are also in accordance with the Universal Grammatical Function Theory, which predicts that the functions of inflectional and lexical derivation are the same.

  19. Treatment of concrete bars from the dismantling of hot cells

    International Nuclear Information System (INIS)

    Graf, A.; Stutz, U.; Valencia, L.

    2002-01-01

    The Central Decontamination Operations Department (HDB) of the Karlsruhe Research Center operates facilities for the disposal of radioactive waste. In general, their objective is to decontaminate radioactive residues for unrestricted release in order to minimize the volume of waste products suitable for repository storage. In the case of about 120 concrete bars from the dismantling of hot cells, we reduce the volume of radioactive waste by sawing off the most contaminated parts of the bar. If there are no insertions such as cables or ventilation systems, the rest of the bar is sandblasted and its activity manually measured to ensure compliance with the release criteria. Otherwise, the bar is minced into small pieces by a power shovel. Afterwards, the rubble is filled into drums and its activity is measured by the clearance measurement facility. If the rubble and the sandblasted bars do not exceed the activity limit specified by the release criteria, the material is disposed of without further regulations for unrestricted use. Those parts of the bars which can not be released must be stored in special containers suitable for the KONRAD final disposal. Using this method, about 70 % of the total mass can be released. (author)

  20. Dismantling of nuclear facilities. From a structural engineering perspective

    International Nuclear Information System (INIS)

    Block, Carsten; Henkel, Fritz-Otto; Bauer, Thomas

    2014-01-01

    The paper summarizes some important aspects, requirements and technical boundary conditions that need to be considered in dismantling projects in the nuclear sector from a structural engineering perspective. Besides general requirements regarding radiation protection, occupational safety, efficiency and cost effectiveness it is important to take into account other conditions which have a direct impact on technical details and the structural assessment of the dismantling project. These are the main aspects highlighted in this paper: - The structural assessment of dismantling projects has to be based on the as-built situation. - The limitations in terms of available equipment and space have to be taken into account. - The structural assessments are often non-standardized engineering evaluations. A selection of five dismantling projects illustrates the various structural aspects. (orig.)

  1. Environmental Assessment for decontamination and dismantlement, Pinellas Plant

    International Nuclear Information System (INIS)

    1995-06-01

    The US Department of Energy (DOE) has prepared an Environmental Assessment (EA) (DOE/EA-1092) of the proposed decontamination and dismantlement of the Pinellas Plant in Largo, Florida. Under the Decontamination and Dismantlement EA, the DOE proposes to clean up facilities, structures, and utilities; dismantle specific structures; and mitigate or eliminate any environmental impacts associated with the cleanup, dismantlement, and related activities. Related activities include utilization of specific areas by new tenants prior to full-scale cleanup. Based on the analyses in the EA, the DOE has determined that the proposed action is not a major Federal action significantly affecting the quality of the human environment, within the meaning of the National Environmental Policy Act of 1969. Therefore, the preparation of an environmental impact statement is not required. This report contains the Environmental Assessment, as well as the Finding of No Significant Impact (FONSI)

  2. Operation for Rokkasho Low Level Radioactive Waste Disposal Center

    International Nuclear Information System (INIS)

    Kamizono, Hideki

    2008-01-01

    The Rokkasho Low Level Radioactive Waste (LLW) Disposal Center is located in Oishitai, Rokkasho-mura, Kamikitagun, of Aomori Prefecture. This district is situated in the southern part of Shimohita Peninsula in the northeastern corner of the prefecture, which lies at the northern tip of Honshu, Japan's main island. The Rokkasho LLW Disposal Center deals with only LLW generated by operating of nuclear power plants. The No.1 and No.2 disposal facility are now in operation. The disposal facilities in operation have a total dispose capacity of 80,000m 3 (equivalent to 400,000 drums). Our final business scope is to dispose of radioactive waste corresponding to 600,000 m 3 (equivalent to 3000,000 drums). For No.1 disposal facility, we have been disposing of homogeneous waste, including condensed liquid waste, spent resin, solidified with cement and asphalt, etc. For No.2 disposal facility, we can bury a solid waste solidified with mortar, such as activated metals and plastics, etc. Using an improved construction technology for an artificial barrier, the concrete pits in No.2 disposal facility could be constructed more economical and spacious than that of No.1. Both No.1 and No.2 facility will be able to bury about 200,000 waste packages (drums) each corresponding to 40,000 m 3 . As of March 17, 2008, Approximately 200,00 waste drums summing up No.1 and No.2 disposal facility have been received from Nuclear power plants and buried. (author)

  3. Method of dismantling a nuclear reactor

    International Nuclear Information System (INIS)

    Shirai, Masato; Hashimoto, Osamu.

    1984-01-01

    Purpose: To enable rapid and simple positioning for a plasma arc torch disposed to the inside of a nuclear reactor main body. Method: After removing the upper semi-spherical portion, fuel portion and control rod portion of a nuclear reactor, a rotary type girder is placed on the upper edge of a cylindrical portion remained after the removal of the upper semi-spherical portion. Then, the upper portion of a supporting rod provided with a swing arm having a plasma arc torch at the top end is situated at the center of the reactor main body. Then, the top end of the support rod is inserted to fix in the housing of control rod drives. Then, the swing arm is actuated to situate the plasma arc torch to a desired position to be cut, whereafter cutting is initiated while rotating the rotary type girder. Thus, plasma arc torch is moved horizontally along an arcuate trace, whereby pipeways, accessories or the likes disposed to the inside of the main body are at first cut and then the cylindrical portion constituting the main body is cut to dismantle the reactor. (Moriyama, K.)

  4. Mobile worksystems for decontamination and dismantlement

    International Nuclear Information System (INIS)

    Osborn, J.; Bares, L.C.; Thompson, B.R.

    1995-01-01

    Many DOE nuclear facilities have aged beyond their useful lifetimes. They need to be decommissioned in order to be safe for human presence in the short term, to eventually recover valuable materials they contain, and ultimately to be transitioned to alternative uses or green field conditions. Decontamination and dismantlement are broad classes of activities that will enable these changes to occur. Most of these facilities - uranium enrichment plants, weapons assembly plants, research and production reactors, and fuel recycling facilities - are dormant, though periodic inspection, surveillance and maintenance activities within them are on-going. DOE estimates that there are over 5000 buildings that require deactivation to reduce the costs of performing such work with manual labor. In the long term, 1200 buildings will be decommissioned, and millions of metric tons of metal and concrete will have to be recycled or disposed of The magnitude of the problem calls for new approaches that are far more cost effective than currently available techniques. This paper describes two technologies that are viable solutions for facility D ampersand D

  5. Mobile worksystems for decontamination and dismantlement

    Energy Technology Data Exchange (ETDEWEB)

    Osborn, J. [Carnegie Mellon Univ., Pittsburgh, PA (United States); Bares, L.C.; Thompson, B.R. [RedZone Robotics, Inc., Pittsburgh, PA (United States)

    1995-10-01

    Many DOE nuclear facilities have aged beyond their useful lifetimes. They need to be decommissioned in order to be safe for human presence in the short term, to eventually recover valuable materials they contain, and ultimately to be transitioned to alternative uses or green field conditions. Decontamination and dismantlement are broad classes of activities that will enable these changes to occur. Most of these facilities - uranium enrichment plants, weapons assembly plants, research and production reactors, and fuel recycling facilities - are dormant, though periodic inspection, surveillance and maintenance activities within them are on-going. DOE estimates that there are over 5000 buildings that require deactivation to reduce the costs of performing such work with manual labor. In the long term, 1200 buildings will be decommissioned, and millions of metric tons of metal and concrete will have to be recycled or disposed of. The magnitude of the problem calls for new approaches that are far more cost effective than currently available techniques. This paper describes a mobile workstation termed ROSIE, which provides remote work capabilities for D&D activities.

  6. Dismantling method for nuclear fuel assembly

    International Nuclear Information System (INIS)

    Yamazaki, Shuji; Kato, Akihiro; Yoshida, Masafumi.

    1993-01-01

    An upper nozzle is detached from a control rod guide tube and an instrumentation tube. Subsequently, slots (slits) having a predetermined width are formed longitudinally at enlarged diameter portions of the control rod guide tube and the instrumentation tube. Then, the control rod guide tube and the instrumentation tube are separated from a lower nozzle, and pulled out from the lattice space of each of the support lattices. Thereafter, a predetermined key is inserted to a key insertion window formed at each of the support lattices, to distort a spring and take the fuel rod out of the lattice space of each of the support lattices. With such procedures, when the control rod guide tube and the instrumentation tube are pulled out of the lattice space of the support lattice, the enlarged diameter portion is narrowed to reduce the diameter, thereby enabling to take them out easily. Accordingly, since the space for inserting the key can be ensured, the nuclear fuel assemblies can easily be dismantled. In addition, fuel rods can be taken out smoothly and in an intact state. (I.N.)

  7. Review of dismantling activities in Europe and worldwide: Current state and perspectives

    International Nuclear Information System (INIS)

    Leclercq, J.

    2003-01-01

    This analysis adopts deliberately the point of view of 'dismantling companies' and aims to draw up a coherent overview of the presentations made per country or major contractors. Aside from the programs, or intentions, that may have been published, its goal is to take stock of the actions undertaken in the last few years and the significant changes that have been observed. In view of the diversity of the 'business models', depending on whether research institutes, major electrical power companies or industrial companies in charge of fuel-related activities are involved, the objective of this presentation is also to assess the solutions retained on both a technical and industrial level for the entire 'de-construction sector'. In conclusion, this presentation seeks to highlight the major challenges that open dismantling industry will have to meet. (author)

  8. An approach to evaluate the cutting time for the nuclear dismantling simulation

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Jonghwan; Hyun, Dongjun; Kang, Sinyoung; Kim, Ikjune; Jeong, Kwan-Seong; Choi, Byung-Seon; Moon, Jeikwon [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2016-10-15

    Nuclear power plant (NPP) decommissioning involves various processes and technologies. Decommissioning should be performed after a comprehensive review of the information related to these processes and technologies. There are various means of prior examination and evaluation to ensure the feasibility and safety of the decommissioning process plan. Our dismantling simulation system aims to simulate and evaluate whole processes related to the dismantlement of core equipment of NPP such as the device preparation, cutting operation, waste transfer, and so on. This paper introduces the estimation methodology of the time required for the cutting processes based on real cutting conditions in order to provide effective economic evaluation functionalities used for the system. The methodology to estimate the time required for the remote cutting process in the nuclear dismantling simulation system was proposed. Among the factors which mainly determine the time, the cutting trace was directly calculated from the simulation system and the continuous cutting speed was obtained by proper order of the spline fitting with constraint conditions.

  9. Use of laser cutting techniques for dismantling tasks in nuclear facilities

    International Nuclear Information System (INIS)

    Haferkamp, H.; Drygalla, M.; Goede, M.

    2001-01-01

    A handguided laser processing system developed by laser zentrum Hannover e.V. (LZH) allows impressive cutting, notching, and material removal applications for the dismantling of nuclear power plants. The handguided unit is equipped with a motor drive for consistent processing results and flexible processing for as long as desired. It offers the possibility to adjust the nozzle as well as focal position in order that various materials with different material thicknesses may be processed. The set process parameters may be viewed on a display which also indicates the laser processing programme selected. An integrated exhaust system guarantees a shielded process. The operator is not only protected against process emissions but also against laser beam reflexions. The handguided unit is connected to the laser beam source via an optical fibre and can be used for laser output powers of up to 1500 W with a high beam quality. For handguided laser material processing low emissions at high feed rates as well as cutting kerf widths between 0.5 and 0.3 mm for special applications such as the dismantling of large facilities or units, etc. are decisive, especially when cutting metal sheets for the dismantling of nuclear power plants. (orig.)

  10. Use of laser cutting techniques for dismantling tasks in nuclear facilities

    Energy Technology Data Exchange (ETDEWEB)

    Haferkamp, H.; Drygalla, M.; Goede, M. [Laser Zentrum Hannover e.V. (Germany)

    2001-07-01

    A handguided laser processing system developed by laser zentrum Hannover e.V. (LZH) allows impressive cutting, notching, and material removal applications for the dismantling of nuclear power plants. The handguided unit is equipped with a motor drive for consistent processing results and flexible processing for as long as desired. It offers the possibility to adjust the nozzle as well as focal position in order that various materials with different material thicknesses may be processed. The set process parameters may be viewed on a display which also indicates the laser processing programme selected. An integrated exhaust system guarantees a shielded process. The operator is not only protected against process emissions but also against laser beam reflexions. The handguided unit is connected to the laser beam source via an optical fibre and can be used for laser output powers of up to 1500 W with a high beam quality. For handguided laser material processing low emissions at high feed rates as well as cutting kerf widths between 0.5 and 0.3 mm for special applications such as the dismantling of large facilities or units, etc. are decisive, especially when cutting metal sheets for the dismantling of nuclear power plants. (orig.)

  11. Measurement of radioactive aerosol behavior during dismantling and reflection to the exposure dose evaluation - 16107

    International Nuclear Information System (INIS)

    Iguchi, Yukihiro; Kato, Masami

    2009-01-01

    Radioactive aerosol disperses slightly via contamination prevention systems such as control enclosures and filters when the nuclear installation is dismantled, and it might impact the environment. Therefore, when decommissioning is planned, it is necessary to assess the safety such as exposure dose evaluation to the public. For the radioactive aerosol, it is possible that the dispersion ratio is different according to the contamination condition, the dismantlement method of the material, nuclides (elements), etc. The radiation exposure evaluation for the decommissioning plan has been executed by operators in Japan based on a number of experiments (mostly cold tests) and overseas results. The decommissioning is now being carried out at the Tokai Power Station (GCR) and Fugen Decommissioning Engineering Center in Japan. In this study, the results data is acquired at the decommissioning sites, and the methodology and data for the exposure dose evaluation are verified and confirmed. These examination results will lead to the upgrading and improvement of the exposure evaluation methodology. In particular, the dismantlement work of connected piping of the heat exchanger (steam generator) was executed in the Tokai Power Station in 2008. In this study, we paid attention to the radionuclides of Co-60 and Cs-137 that adhered to piping, and the dispersion behavior of aerosol was measured and contamination prevention effect was assured. As a result, the data show that the cesium concentrates about four times higher than cobalt. Moreover, the effects of the prevention measures of contamination were confirmed and the behavior of the radioactive aerosol became clear and the effective findings about the dose evaluation of the dismantling were collected. (authors)

  12. Disposition of excess weapons plutonium from dismantled weapons

    International Nuclear Information System (INIS)

    Jardine, L.J.

    1997-01-01

    With the end of the Cold War and the implementation of various nuclear arms reduction agreements, US and Russia have been actively dismantling tens of thousands of nuclear weapons. As a result,large quantities of fissile materials, including more than 100 (tonnes?) of weapons-grade Pu, have become excess to both countries' military needs. To meet nonproliferation goals and to ensure the irreversibility of nuclear arms reductions, this excess weapons Pu must be placed in secure storage and then, in timely manner, either used in nuclear reactors as fuel or discarded in geologic repositories as solid waste. This disposition in US and Russia must be accomplished in a safe, secure manner and as quickly as practical. Storage of this Pu is a prerequisite to any disposition process, but the length of storage time is unknown. Whether by use as fuel or discard as solid waste, disposition of that amount of Pu will require decades--and perhaps longer, if disposition operations encounter delays. Neither US nor Russia believes that long-term secure storage is a substitute for timely disposition of excess Pu, but long-term, safe, secure storage is a critical element of all excess Pu disposition activities

  13. Disposal of fissionable material from dismantled nuclear weapons

    International Nuclear Information System (INIS)

    Taylor, J.J.

    1991-01-01

    The reduction in tensions between the United States and the Soviet Union has improved the prospects for nuclear disarmament, making it more likely that significant numbers of nuclear warheads will be dismantled by the United States and USSR in the foreseeable future. Thus, the question becomes more urgent as to the disposition of the weapons materials, highly enriched uranium and plutonium. It is timely, therefore, to develop specific plans for such disposal. The overall process for disposal of weapons materials by the burnup option involves the following steps: (1) removing the weapons material from the warheads, (2) converting the material to a fuel form suitable for power reactors, (3) burning it up as a power reactor fuel, and (4) removing the spent fuel and placing it in a permanent repository. This paper examines these four steps with the purpose of answering the following questions. What facilities would be appropriate for the disposal process? Do they need to be dedicated facilities, or could industrial facilities be used? What is the present projection of the economics of the burnup process, both the capital investment and the operating costs? How does one assure that fissionable materials will not be diverted to military use during the disposal process? Is the spent fuel remaining from the burnup process proliferation resistant? Would the disposal of spent fuel add an additional burden to the spent fuel permanent repository? The suggested answers are those of the author and do not represent a position by the Electric Power Research Institute

  14. Characterization of radioactive graphite and concrete of the reactor ULYSSE/INSTN at CEA/Saclay to be dismantled

    International Nuclear Information System (INIS)

    Van Lauwe, Aymeric; Ridikas, Danas; Damoy, Francois; Blideanu, Valentin; Fajardo, Christophe; Aubert, Marie-Cecile; Foulon, Francois

    2006-01-01

    Decommissioning and dismantling of nuclear installations after their service life are connected with the necessity of the disassembling, handling and disposing of a large amount of radioactive material. In order to optimize the disassembling operations, to reduce the undesirable volume to the minimum and to successfully plan the dismantling and disposal of radioactive materials to storage facilities, the radiological characterisation of the material present in the reactor and around its environment should be accurately evaluated. The present work has been done in the framework of the decommissioning and dismantling of the experimental reactor ULYSSE that is presently operating in INSTN/Saclay and will be closed in the middle of 2006. A methodology, already successfully used for another research reactor, is proposed for determining accurately the long-term induced activity of the materials present in the active reactor core and its surroundings. The comparison of theoretical predictions, based on Monte Carlo technique, with experimental values validated the approach and the methodology used in the present study. The goal is to plan efficiently the disassembling and dismantling of the system and to optimise the mass flow going to different waste repositories. We show that this approach might reduce substantially the total cost of decommissioning. (authors)

  15. Loviisa starts low-level operating waste disposal in 1997

    International Nuclear Information System (INIS)

    Snellman, J.

    1996-01-01

    At an early stage Imatran Voima Oy (IVO) decided to construct a waste repository for Loviisa NPP. The suitability of the power plant site for final disposal of low- and intermediate- level operating waste was studied. In the site report in 1982 the plant site was found to be geologically suitable and economically feasible for construction. The necessary preparations started in 1992. The repository will be constructed in three phases. The first phase will cover the transport tunnel, construction of one maintenance waste tunnel and the excavation of another maintenance waste tunnel together with a hall for solidified wastes. This phase will be finished by the end of 1996. During the second phase in the beginning of next century the remaining already excavated rooms will be furnished. Finally in the third phase the repository will be extended for the decommissioning waste somewhere around years 2020-2025. (3 figs., 1 tab.)

  16. New reactor safety circuit for low-power-level operation

    International Nuclear Information System (INIS)

    McDowell, W.P.; Keefe, D.J.; Rusch, G.K.

    1978-01-01

    In the operation of nuclear reactors at low-power levels, one of the primary instrumentation problems is that the statistical fluctuations of reactor neutron population are accentuated by conventional log-count-rate and differentiating circuits and can cause frequent spurious scrams unless long time constants are incorporated in the circuit. Excessive time constants may introduce undesirable delay in the circuit response to legitimate scram signals. The paper develops the concept of a count doubling-time monitor which generates a scram signal if the number of counts from a pulse type neutron detector doubles in a given period of time. The paper demonstrates the theoretical relation between count doubling time and asymptomatic periods. A practical circuit to implement the function is described

  17. Dismantling, conditioning and repatriation of disused sealed radioactive sources

    International Nuclear Information System (INIS)

    Aguilar, S.L.; Miranda, C.A.; Saire, A.E.; Ontiveros, G.P.

    2015-01-01

    In Bolivia sealed radioactive sources for medical, industrial and research applications are used; radioactive sources containing a wide range of radionuclides and have different levels of activity and half-lives, they generated a problem when they stop being used. At the end of its useful life these sources are considered obsolete. However, residual levels of radioactivity, which have these sources can be high constituting a potential hazard to personnel and applies to those who benefit from its use and the general public. The aim of this work has been focused mainly on safety issues in the safe handling and management of disused sealed sources. Assignments listed below: 1. Dismantling; 2. Packaging; 3. Return of disused sealed radioactive sources. The actions taken were carried out by the technical teams of the Bolivian Institute of Nuclear Science and Technology (IBTEN) and Los Alamos National Laboratory (LANS) which supports the program 'Global Threat Reduction Initiative's' (GTRI) in the implementation of 'Off -site Source Recovery Program' (OSRP). [es

  18. Extension of TFTR operations to higher toroidal field levels

    International Nuclear Information System (INIS)

    Woolley, R.D.

    1995-01-01

    For the past year, TFTR has sometimes operated at extended toroidal field (TF) levels. The extension to 5.6 Tesla (79 kA) was crucial for TFTR's November 1994 10.7 MW DT fusion power record. The extension to 6.0 Tesla (85 kA) was commissioned on 9 September 1995. There are several reasons that one could expect the TF coils to survive the higher stresses that develop at higher fields. They were designed to operate at 5.2 Tesla with a vertical field of 0.5 Tesla, whereas the actual vertical field needed for the plasma does not exceed 0.35 Tesla. Their design specification explicitly required they survive some pulses at 6.0 Tesla. TF coil mechanical analysis computer models available during coil design were crude, leading to conservative design. And design analyses also had to consider worst-case misoperations that TFTR's real time Coil Protection Calculators (CPCs) now positively prevent from occurring

  19. CEA contribution to power plant operation with high burnup level

    International Nuclear Information System (INIS)

    1981-03-01

    High level burnup in PWR leads to investigate again the choices carried out in the field of fuel management. French CEA has studied the economic importance of reshuffling technique, cycle length, discharge burnup, and non-operation period between two cycles. Power plants operators wish to work with increased length cycles of 18 months instead of 12. That leads to control problems because the core reactivity cannot be controlled with the only soluble boron: moderator temperature coefficient must be negative. With such cycles, it is necessary to use burnable poisons and for economic reasons with a low penalty in end of cycle. CEA has studied the use of Gd 2 O 3 mixed with fuel or with inert element like Al 2 O 3 . Parametric studies of specific weights, efficacities relatively to the fuel burnup and the fuel enrichment have been carried out. Particular studies of 1 month cycles with Gd 2 O 3 have shown the possibility to control power distribution with a very low reactivity penalty in EOC. In the same time, in the 100 MW PWR-CAP, control reactivity has been made with large use of gadolinia in parallel with soluble boron for the two first cycles

  20. TSTA loop operation with 100 grams-level of tritium

    International Nuclear Information System (INIS)

    Yoshida, Hiroshi; Hirata, Shingo; Naito, Taisei

    1988-10-01

    The first loop operation tests of Tritium Systems Test Assembly (TSTA) with 100 grams-level of tritium were carried out at Los Alamos National Laboratory(LANL) on June and July, 1987. The tests were one of the milestones for TSTA goal scheduled in June, 1987 through June, 1988. The objectives were (i) to operate TSTA process loop composed of tritium supply system, fuel gas purification system, hydrogen isotope separation system, etc, (ii) to demonstrate TSTA safety subsystems such as secondary containment system, tritium waste treatment system and tritium monitoring system, and (iii) to accumulate handling experience of a large amount of tritium. This report describes the plan and procedures of the milestone run done in June and the summary results especially on the safety aspects. Analysis of the emergency shutdown of the process loop, which happened in the June run, is also reported. A brief description of the process and safety subsystems as well as the summary of the TSTA safety analysis report is included. (author)

  1. Operation of the Upgraded ATLAS Level-1 Central Trigger System

    CERN Document Server

    Glatzer, Julian Maximilian Volker; The ATLAS collaboration

    2015-01-01

    The ATLAS Level-1 Central Trigger (L1CT) system is a central part of ATLAS data-taking and has undergone a major upgrade for Run 2 of the LHC, in order to cope with the expected increase of instantaneous luminosity of a factor of 2 with respect to Run 1. The upgraded hardware offers more flexibility in the trigger decisions due to the double amount of trigger inputs and usable trigger channels. It also provides an interface to the new topological trigger system. Operationally - particularly useful for commissioning, calibration and test runs - it allows concurrent running of up to 3 different sub-detector combinations. In this contribution, we give an overview of the operational software framework of the L1CT system with particular emphasis of the configuration, controls and monitoring aspects. The software framework allows a consistent configuration with respect to the ATLAS experiment and the LHC machine, upstream and downstream trigger processors, and the data acquisition. Trigger and dead-time rates are m...

  2. French Regulatory Framework for the Recycling/Reuse of Nuclear Waste and the Dismantling of George Besse Gaseous Diffusion Plant

    Energy Technology Data Exchange (ETDEWEB)

    Themines, R., E-mail: robert.themines@areva.com [AREVA (France)

    2011-07-15

    The regulatory framework in France governing the management of materials containing low levels of radionuclides is described. The plans for the management of the materials arising from the dismantling of the Georges Besse Gaseous Diffusion Plant are described as an example of the application of the regulations. (author)

  3. Operational intervention levels for reactor emergencies IAEA recommendations

    Energy Technology Data Exchange (ETDEWEB)

    Aguiar, Laís A. de; Reis, Arlene A. dos; Santos, Raul dos, E-mail: laguiar@ird.gov.br, E-mail: arlene@ird.gov.br, E-mail: raul@ird.gov.br [Instituto de Radioproteção e Dosimetria (IRD/CNEN-RJ), Rio de Janeiro, RJ (Brazil)

    2017-07-01

    The IAEA publication EPR-NPP-OILs-2017, Operational Intervention Levels for Reactor Emergences and Methodology for their Derivation, provides selected default OIL values, describing a methodology for their derivation, as well as practical tools and recommendations for their use. IAEA recommends that tools and default OIL values be directly integrated into national emergency arrangements or reviewed and modified as necessary to meet the specific emergency preparedness and response arrangements. The Institute of Radiation Protection and Dosimetry (IRD) has a Radiological Assessment TEAM (EAR) as pare of its Radiation Emergency Response System. Brazilian regulatory standards address actions for radiation emergencies encompassing necessary measures to assess public exposures, intervention levels to protect the public and recommendations for protective actions as, evacuation, relocation, sheltering and food restrictions. The objective of this paper is to present a discussion the use these OILs, to compare those ones established by the Brazilian standards and to propose a methodology on how OILs can be used by EAR/IRD in case of an emergency at the Brazilian NPP. (author)

  4. Operational intervention levels for reactor emergencies IAEA recommendations

    International Nuclear Information System (INIS)

    Aguiar, Laís A. de; Reis, Arlene A. dos; Santos, Raul dos

    2017-01-01

    The IAEA publication EPR-NPP-OILs-2017, Operational Intervention Levels for Reactor Emergences and Methodology for their Derivation, provides selected default OIL values, describing a methodology for their derivation, as well as practical tools and recommendations for their use. IAEA recommends that tools and default OIL values be directly integrated into national emergency arrangements or reviewed and modified as necessary to meet the specific emergency preparedness and response arrangements. The Institute of Radiation Protection and Dosimetry (IRD) has a Radiological Assessment TEAM (EAR) as pare of its Radiation Emergency Response System. Brazilian regulatory standards address actions for radiation emergencies encompassing necessary measures to assess public exposures, intervention levels to protect the public and recommendations for protective actions as, evacuation, relocation, sheltering and food restrictions. The objective of this paper is to present a discussion the use these OILs, to compare those ones established by the Brazilian standards and to propose a methodology on how OILs can be used by EAR/IRD in case of an emergency at the Brazilian NPP. (author)

  5. Dismantling large components at the Jose-Cabrera NPP (CNJC) in Spain

    International Nuclear Information System (INIS)

    Santiago, Juan Luis

    2012-01-01

    Located in central Spain, near Madrid, the Jose-Cabrera NPP (also known as Zorita) is the first PWR to be dismantled in Spain. The unit is a one-loop Westinghouse PWR, with a capacity of 150 MW. The plant was shut down in 1996 and ENRESA (Empresa Nacional de Residuos Radioactivos) has decided its prompt decommissioning, starting in 2010. In preparation for decommissioning, a full system decontamination (FSD) of the whole reactor cooling system (including the reactor vessel in the flow path) was carried out in 2006-7. The large components to be dismantled include: the reactor pressure vessel (RPV) and the internals; the vessel head; the SG; the pressurizer and the surge line; the reactor coolant pump, and the primary loop piping The objective of the project is not only to ensure the safe and efficient dismantling of those large components, but also to gain experience and to learn lessons to be applied during the future decommissioning and dismantling of the remaining six operating PWRs in Spain, whose operational lives are currently planned to end between 2021 and 2028. ENRESA has defined a waste-management policy for decommissioning activities, which includes Waste-management routes and optimisation. A case study describes the results obtained by ENRESA in the specific case of CNJC large components (including the RPV) dismantling project: Removal and conditioning of large components as a single piece is not considered a viable option. Segmentation therefore is required and 2 options have been analysed: large pieces for disposal in a large container and small pieces for disposal in approved concrete packages (CE-2a and the smaller CE-2b). The use of the CE-2b package is a feasible option and is easy to implement as a logical extension from the CE-2a. The use of the CE-2b package results in an important reduction in the total volume of final waste packages and does not require, in itself, any changes in the current waste handling and kinematics. The large size

  6. Performance Evaluation at the Hardware Architecture Level and the Operating System Kernel Design Level.

    Science.gov (United States)

    1977-12-01

    program utilizing kernel semaphores for synchronization . The Hydra kernel instructions were sampled at random using the hardware monitor. The changes in...thatf r~i~h olvrAt- 1,o;lil armcrl han itf,. own sell of primitive func ions; and c onparinoms acrosns dif fc’rnt opt ratieg ; .emsf is riot possiblc...kcrnel dcsign level is complicated by the fact that each operating system kernel ha. its own set of primitive functions and compari!ons across

  7. Information Factor Color Revolutions and Modern Technology Dismantling of Political Regimes

    Directory of Open Access Journals (Sweden)

    Andrey Victorovich Manoylo

    2014-01-01

    Full Text Available This article analyzes the problems associated with the dismantling of the political regimes in modern states (both authoritarian and democratic type and the role of technology in the process of color revolutions. Problems of dismantling of political regimes and the associated problems of color revolutions acquire extreme urgency and actuality in modern conditions. In the world history always there were problems associated with the dismantling of the political regimes. But formerly the instruments of dismantling included mostly violent methods in the classical sense, applied in armed coups, local armed conflicts, civil wars and military interventions. And the international community managed to develop effective methods to counter these threats and to create effective mechanisms for political control of these processes, even at the international level. Acuteness of the problem associated with the threat of military coups in the various countries of the world does not cease to be actual and not removed from the agenda, but for the whole international community this category of threats is familiar, and the world community knows how to react to it. However, today the world is changing, and technologies of armed coups are replaced by more subtle color revolutions technology that is cleverly disguised as a true revolutionary movement and virtually unopposed from both countries witch fully developed democracy and of the Oriental type, preserved traditional livelihoods. Repetition of the scenario of color revolutions in Ukraine causes legitimate concern (well founded anxiety, since there is growing confidence that Ukraine -not the end point of this scenario, but simply a bargaining chip to the geopolitical game in which the brunt of American directors (producers of color revolutions may be directed to Russia, China and Kazakhstan.

  8. Information Factor Color Revolutions and Modern Technology Dismantling of Political Regimes

    Directory of Open Access Journals (Sweden)

    Andrey Victorovich Manoylo

    2014-01-01

    Full Text Available This article analyzes the problems associated with the dismantling of the political regimes in modern states (both authoritarian and democratic type and the role of technology in the process of color revolutions. Problems of dismantling of political regimes and the associated problems of color revolutions acquire extreme urgency and actuality in modern conditions. In the world history always there were problems associated with the dismantling of the political regimes. But formerly the instruments of dismantling included mostly violent methods in the classical sense, applied in armed coups, local armed conflicts, civil wars and military interventions. And the international community managed to develop effective methods to counter these threats and to create effective mechanisms for political control of these processes, even at the international level. Acuteness of the problem associated with the threat of military coups in the various countries of the world does not cease to be actual and not removed from the agenda, but for the whole international community this category of threats is familiar, and the world community knows how to react to it. However, today the world is changing, and technologies of armed coups are replaced by more subtle color revolutions technology that is cleverly disguised as a true revolutionary movement and virtually unopposed from both- countries witch fully developed democracy and of the Oriental type, preserved traditional livelihoods. Repetition of the scenario of color revolutions in Ukraine causes legitimate concern (well founded anxiety, since there is growing confidence that Ukraine -not the end point of this scenario, but simply a bargaining chip to the geopolitical game in which the brunt of American directors (producers of color revolutions may be directed to Russia, China and Kazakhstan.

  9. Place of the final disposal of short lived dismantling waste; Plats foer slutfoervaring av kortlivat rivningsavfall

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2013-01-15

    This report deals with the short-lived low and intermediate level radioactive waste, which will mainly arise from the dismantling of the Swedish nuclear power plants, but also the dismantling of other nuclear facilities. For these installations to be dismantled, there must be the capacity to receive and dispose of dismantling waste. SKB plans to expand the existing final repository for short-lived radioactive waste (SFR) in Forsmark for this purpose. The legislation requires alternatives to the chosen location. The alternate location for the disposal of decommissioning waste SKB has chosen to compare with is a location in the Simpevarp area outside Oskarshamn. There are currently Oskarshamn nuclear power plant and SKB between stock 'CLAB'. The choice of Simpevarp as alternative location is based on that it's one of the places in the country where data on the bedrock is available to an extent that allows an assessment of the prospects for long-term security, such an assessment is actually showing good potential, and that the location provide realistic opportunities to put into practice the disposal of decommissioning waste. At a comparison between the disposal of short-lived decommissioning waste in an extension of SFR with the option to build a separate repository for short-lived decommissioning waste in Simpevarp, the conclusion is that both options offer potentially good prospects for long-term security. The differences still indicated speaks to the Forsmark advantage. Similar conclusions were obtained when comparing the factors of environment, health and social aspects.

  10. Decommissioning, Dismantling and Disarming: a Unique Information Showroom Inside the G2 Reactor at Marcoule Centre (France) - 12068

    Energy Technology Data Exchange (ETDEWEB)

    Volant, Emmanuelle [CEA DAM, Bruyeres-le-Chatel (France); Garnier, Cedric [CEA DEN, Marcoule (France)

    2012-07-01

    The paper aims at presenting the new information showroom called 'Escom G2' (for 'Espace Communication') inaugurated by the French Atomic Energy and Alternative Energies Commission (CEA) in spring 2011. This showroom is settled directly inside the main building of the G2 nuclear reactor: a facility formerly dedicated to weapon-grade plutonium production since the late 1950's at the Marcoule nuclear centre, in south of France. After its shutdown, and reprocessing of the last spent fuels, a first dismantling step was successfully completed from 1986 to 1996. Unique in France and in Europe, Escom G2 is focused on France dismantling expertise and its action for disarmament. This showroom comprises of a 300-square meters permanent exhibition, organized around four themes: France strategy for disarmament, decommissioning and dismantling technical aspects, uranium and plutonium production cycles. Each of these topics is illustrated with posters, photos, models and technical pieces from the dismantled plants. It is now used to present France's action in disarmament to highly ranked audiences such as: state representatives, diplomats, journalists... The paper explains the background story of this original project. As a matter of fact, in 1996 France was the first nuclear state to decide to shut down and dismantle its fissile material production facilities for nuclear weapons. First, the paper presents the history of the G2 reactor in the early ages of Marcoule site, its operating highlights as well as its main dismantling operations, are presented. In Marcoule, where the three industrial-scale reactors G1, G2 and G3 used to be operated for plutonium production (to be then reprocessed in the nearby UP1 plant), the initial dismantling phase has now been completed (in 1980's for G1 and in 1996 for G2 and G3). The second phase, aimed at completely dismantling these three reactors, will restart in 2020, and is directly linked to the opening of

  11. Treatment for dismantled radioactive solid waste from the TRIGA Mark-2 and 3

    International Nuclear Information System (INIS)

    Park, Seung Kook; Jung, Kyung Hwan

    1999-06-01

    Radioactive wastes are generally classified into 3 type depending on their physical property: liquid, solid and gaseous type. State-of -the art concerning liquid waste treatment has already been published; KAERI/TR-1315/99. Solid wastes classification package and treatment method will be studied to effectively manage them during the practical decommissioning work. All of the spent fuel produced during the operation of the TRIGA Mark-2 and 3 have been transported to the US last year, 1998, according to the spent fuel management strategy set-up by the US government for the non-proliferation of nuclear energy. Solid wastes are mainly all equipment existing inside of the reactors, activated concrete among the bio-shielded concrete, pipes, pimps, resin filter and it's housings, heat-exchangers, liquid waste storage tanks, to radioactive waste storage treatment facilities and so on. Solid wastes are generally low-level. They are classified according to the national regulation and nuclear law and IAEA Safety Standard Series ST-1(1996). Medium level radioactive wastes from reactor structures, mainly stainless steel component from the Rotary Specimen Rack(RSR) will be properly dismantled and stored in a shield container such as TIF(TRIGA Irradiated Fuel) container. While, low-level solid waste will be treated and packed in a ISO container(4m 3 ISO container for example) according to the IAEA recommendation. And combustible solid waste such as cloths, gloves, paper etc. will be packed in a 200 liters drum. This state-of-the art shows a general feature of the solid radioactive waste management which will be produced during the decommissioning of the TRIGA Mark-2 and 3 research reactors. (author). 17 refs., 17 tabs., 2 figs

  12. The Development of the J9: An Operational Level Directorate for Stability and Security Operations for the Military

    National Research Council Canada - National Science Library

    Sheffe, Richard C

    2007-01-01

    .... Many historical case studies suggest that this is a result of not having an ever-present, multi-disciplined staff at the operational level devoted to monitoring and planning for potential SSTR operations...

  13. Efficient operating system level virtualization techniques for cloud resources

    Science.gov (United States)

    Ansu, R.; Samiksha; Anju, S.; Singh, K. John

    2017-11-01

    Cloud computing is an advancing technology which provides the servcies of Infrastructure, Platform and Software. Virtualization and Computer utility are the keys of Cloud computing. The numbers of cloud users are increasing day by day. So it is the need of the hour to make resources available on demand to satisfy user requirements. The technique in which resources namely storage, processing power, memory and network or I/O are abstracted is known as Virtualization. For executing the operating systems various virtualization techniques are available. They are: Full System Virtualization and Para Virtualization. In Full Virtualization, the whole architecture of hardware is duplicated virtually. No modifications are required in Guest OS as the OS deals with the VM hypervisor directly. In Para Virtualization, modifications of OS is required to run in parallel with other OS. For the Guest OS to access the hardware, the host OS must provide a Virtual Machine Interface. OS virtualization has many advantages such as migrating applications transparently, consolidation of server, online maintenance of OS and providing security. This paper briefs both the virtualization techniques and discusses the issues in OS level virtualization.

  14. Using SAFRAN Software to Assess Radiological Hazards from Dismantling of Tammuz-2 Reactor Core at Al-tuwaitha Nuclear Site

    Science.gov (United States)

    Abed Gatea, Mezher; Ahmed, Anwar A.; jundee kadhum, Saad; Ali, Hasan Mohammed; Hussein Muheisn, Abbas

    2018-05-01

    The Safety Assessment Framework (SAFRAN) software has implemented here for radiological safety analysis; to verify that the dose acceptance criteria and safety goals are met with a high degree of confidence for dismantling of Tammuz-2 reactor core at Al-tuwaitha nuclear site. The activities characterizing, dismantling and packaging were practiced to manage the generated radioactive waste. Dose to the worker was considered an endpoint-scenario while dose to the public has neglected due to that Tammuz-2 facility is located in a restricted zone and 30m berm surrounded Al-tuwaitha site. Safety assessment for dismantling worker endpoint-scenario based on maximum external dose at component position level in the reactor pool and internal dose via airborne activity while, for characterizing and packaging worker endpoints scenarios have been done via external dose only because no evidence for airborne radioactivity hazards outside the reactor pool. The in-situ measurements approved that reactor core components are radiologically activated by Co-60 radioisotope. SAFRAN results showed that the maximum received dose for workers are (1.85, 0.64 and 1.3mSv/y) for activities dismantling, characterizing and packaging of reactor core components respectively. Hence, the radiological hazards remain below the low level hazard and within the acceptable annual dose for workers in radiation field

  15. Decommissioning and dismantling of the reprocessing plant Karlsruhe

    International Nuclear Information System (INIS)

    Eiben, K.; Fritz, P.

    1995-01-01

    Reprocessing activities were discontinued in late 1990. The facility was drained and rinsed, and 80 m3 of HLWC have since been stored in special tanks, awaiting vitrification. Decommissioning work is scheduled to proceed in six phases. The reprocessing areas of the facility will be prepared for release from radiological control and dismantled in the first phase. The remaining facilities can be deregulated, and storage tanks dismantled, only after termination of phase 1. The goal of the following phase is clearance from radiological control of all controlled areas, and the last phase is to cover dismantling of all buildings and restoration of a green field site. The overall costs of these activities are estimated to amount to DM 1.657 million. The article explains the contents of the first permits for decommissioning as well as the documents prepared for planning of work and licence application. (orig./HP) [de

  16. Evaluation of worker's dose on a virtual dismantling environment

    International Nuclear Information System (INIS)

    Park, Hee Seong; Kim, Sung Hyun; Park, Byung Suk; Yoon, Ji Sup

    2007-01-01

    The motivation of this study is to provide a basis for a minimization of worker's dose during dismantling activities. In the present study, we proposed methods for identifying an existence of radioactivity which is contained in the dismantling objects and for evaluating a worker's dose under a virtual dismantling environment. To evaluate a worker's external dose, the shape of the exposure room in the KRR 2(Korean Research Reactor TRIGA MARK III) by 3D CAD was created and the radiation dose surrounding the facility by using MCNP- 4C(Monte Carlo N-Particle-4C) was calculated. The radiation field of the exposure room was visualized three dimensionally by using the radiation dose that was obtained by the code

  17. REUSE OF AUTOMOTIVE COMPONENTS FROM DISMANTLED END OF LIFE VEHICLES

    Directory of Open Access Journals (Sweden)

    Piotr NOWAKOWSKI

    2013-12-01

    Full Text Available The problem of recycling end of life automotive vehicles is serious worldwide. It is one of the most important streams of waste in developed countries. It has big importance as recycling potential of raw materials content in automotive vehicles is valuable. Different parts and assemblies after dismantling can also be reused in vehicles where replacement of specific component is necessary. Reuse of the components should be taken into consideration in selecting the vehicles dismantling strategy. It also complies with European Union policy concerning end of life vehicles (ELV. In the paper it is presented systematic approach to dismantling strategies including disassembly oriented on further reuse of components. It is focused on decision making and possible benefits calculation from economic and environmental point of view.

  18. 47 CFR 11.54 - EAS operation during a National Level emergency.

    Science.gov (United States)

    2010-10-01

    ... 47 Telecommunication 1 2010-10-01 2010-10-01 false EAS operation during a National Level emergency... SYSTEM (EAS) Emergency Operations § 11.54 EAS operation during a National Level emergency. (a) The EAS Operating Handbook summarizes the procedures to be followed upon receipt of a National level EAN or EAT...

  19. Operational intervention levels (OILs): a tool to overcome differences in intervention levels?

    International Nuclear Information System (INIS)

    Kirchner, Gerald; Wirth, Erich

    2008-01-01

    The intervention levels for evacuation, sheltering and iodine blockade still differ in many countries, although international organisation like IAEA, NEA or ICRP aspire to harmonise them on an international level. Even if the dose values of the limits are in agreement, they are not necessarily comparable because the type of dose (projected dose, averted dose), the respected exposure pathways (external dose, inhalation, ingestion) or the integration time might differ significantly. The question is raised, how can harmonisation being achieved? International organisations recommend 'operational intervention levels' (OILs) for promptly assessing the results of environmental monitoring and to decide on protective actions. OILs are measurable values derived from dose limits. Best examples are the derived intervention levels for food and feed in the codex alimentarius or by the EC, which limit the ingestion dose to about 5 mSv/a. This paper discusses the properties and potential use of OILs, identifies and derives useful OILs and addresses their benefit in practise both for early and later countermeasures. Furthermore it is discussed whether OILs might be a useful tool to overcome national differences in intervention levels because an OIL value covers a relative wide range of the projected dose due to the uncertainty of the parameters needed for derivation. (author)

  20. Techniques for CAD reconstruction of 'as-built' environments and application to preparing for dismantling of plants

    International Nuclear Information System (INIS)

    Pot, J.; Levesque, P.

    1997-01-01

    Electricite de France is using CAD-generated numeric geometrical models to simulate maintenance operations and enable optimizing maintenance procedures. These models are also used to program the machines or robots for certain servicing procedures. They are used in the operator interfaces for robot control, and provide the operator with virtual cameras or enable generating specific information (such as virtual force feedback). Even more recently, CAD models have been integrated in what is known as 'virtual reality' software, giving the operators a sensation of 'immersion' in a virtual universe. Depending on the need and on the type of results expected from the simulations, one needs more or less precise models of the environment in which work will be performed. EDF is using several techniques to get 'as-built' models of the environments. This article describes the SOISIC system, which is a 3D laser sensor widely used for environment data acquisition, associated with 3Dipsos software, for CAD model reconstruction. These techniques, and the applications subsequently developed formaintenance applications, can be used in preparing and carrying out dismantling operations: 'as-built' CAD modeling of the installation can be used in the preparatory phase, providing plans, simulating the varioussteps, calculating waste volumes, helping in optimization of waste management, etc. These models can also be used during the actual dismantling process, to program the machines or robots used, or in the robot or machinesupervisory system. Some of the presented techniques have been used in a room in the Brennilis plant, which is currently being dismantled. (orig.)

  1. Atomic Energy Commission (CEA) dismantling experience review and perspectives

    International Nuclear Information System (INIS)

    Barre, J.Y.

    1992-01-01

    Reorganization and dismantling have been part of the CEA's facility renewal process for more than twenty years now. Many facilities have already been downrated or will be in the near future. The strategy developed so far is founded on acquired experience, on the basis of which it may be said that: nuclear facilities are reversible in full and strict compliance with safety and security rules; a field of competence has been developed that will help French industries to land on their feet when the time comes on the dismantling market; public opinion has been informed as to the soundness of the energy alternatives chosen

  2. Comparison of thorough decontamination techniques on dismantled pieces of a PWR reactor

    International Nuclear Information System (INIS)

    Klein, M.; Rahier, A.; Mandoki, R.; Ponnet, M.

    1998-01-01

    The decontamination experience gained during the BR3 dismantling project is developed. This started with the full system decontamination of the primary loop and was followed by R and D on thorough decontamination projects. First, a wet abrasive installation has been installed and is now in operation for the thorough cleaning of metallic pieces of simple geometry. Afterwards, the chemical cerium process has been developed. The results of the regeneration with ozone and with electrochemistry are presented in detail. The ozone regeneration process has been selected for the industrial installation of which the construction is foreseen in 1998. (author)

  3. Radiation protection aspects of dismantling and decommissioning of Uranium Mining of Andujar (Spain)

    International Nuclear Information System (INIS)

    Ortiz Ramis, M.T.; Garcia-Bermejo Fernandez, R.; Martin Palomo, N.

    1995-01-01

    This study analyzes the radiation protection aspects during the decommissioning and dismantling of uranium mining in Andujar (Spain). The application during dismantling's mining, the transfer factor of natural radioactive isotopes and the application during the sterile movements are presented

  4. 49 CFR 1242.42 - Administration, repair and maintenance, machinery repair, equipment damaged, dismantling retired...

    Science.gov (United States)

    2010-10-01

    ... repair, equipment damaged, dismantling retired property, fringe benefits, other casualties and insurance, lease rentals, joint facility rents, other rents, depreciation, joint facility, repairs billed to others... maintenance, machinery repair, equipment damaged, dismantling retired property, fringe benefits, other...

  5. Characteristics of organic matter in PM2.5 from an e-waste dismantling area in Taizhou, China.

    Science.gov (United States)

    Gu, Zeping; Feng, Jialiang; Han, Wenliang; Wu, Minghong; Fu, Jiamo; Sheng, Guoying

    2010-08-01

    Solvent extractable organic compounds in PM(2.5) samples collected in Taizhou, a city famous for its electrical and electronic waste (e-waste) recycling industry in Zhejiang province of China, were analyzed to identify the main emission sources based on molecular markers. Two types of plastics which were most frequently contained in the e-wastes, wires/cables and plastic blocks, were burned in the lab and the particles emitted analyzed. The concentrations of PAHs and phthalate esters at the e-waste dismantling area during our sampling periods were about two times of that at the reference urban site, indicating the high pollution level there. The high concentrations of quaterphenyl found at the dismantling area indicated that burning of plastics or polymers was an important emission source of the PAHs in the fine particles. The diagnostic analysis based on the compositions of alkanes, hopanes and other molecular markers showed that engine exhaust, biomass burning and kitchen emissions were also important emission sources at the e-waste dismantling area. Our results suggested that more effort should be paid to control the correlative emission sources such as transportation and kitchen to achieve better air quality at the e-waste dismantling area besides regulating the recycling activities. Copyright 2010 Elsevier Ltd. All rights reserved.

  6. Operational Principle of Water Level Detector for Agricultural and ...

    African Journals Online (AJOL)

    This paper proposes a design to automatically detect the level of water in a reservoir (storage tank) at a preset level and initializes an information to the users in case of low water level. The functionality of this sensor depends basically on the electrical conductivity of water (probes) which varies, depending on the level of its ...

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

    International Nuclear Information System (INIS)

    Baumann, R.; Faber, P.

    2003-01-01

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

  8. Enterprise Level Status and Control of Multi-Satellite Operations

    Data.gov (United States)

    National Aeronautics and Space Administration — Single-satellite mission operation centers are used for nearly all Goddard Space Flight Center (GSFC) mission ground data systems, with a focus on localized data...

  9. High level waste facilities - Continuing operation or orderly shutdown

    International Nuclear Information System (INIS)

    Decker, L.A.

    1998-04-01

    Two options for Environmental Impact Statement No action alternatives describe operation of the radioactive liquid waste facilities at the Idaho Chemical Processing Plant at the Idaho National Engineering and Environmental Laboratory. The first alternative describes continued operation of all facilities as planned and budgeted through 2020. Institutional control for 100 years would follow shutdown of operational facilities. Alternatively, the facilities would be shut down in an orderly fashion without completing planned activities. The facilities and associated operations are described. Remaining sodium bearing liquid waste will be converted to solid calcine in the New Waste Calcining Facility (NWCF) or will be left in the waste tanks. The calcine solids will be stored in the existing Calcine Solids Storage Facilities (CSSF). Regulatory and cost impacts are discussed

  10. Integrating Mission Type Orders into Operational Level Intelligence Collection

    Science.gov (United States)

    2011-05-27

    Techniques, and Procedures U.S. United States UAS Unmanned Aircraft System UAV Unmanned Aerial Vehicle UNICORN Unified Collection Operation Reporting...MTOs. If these suggestions result in doctrinal changes, that will help grow the amount of existing literature pertaining to this topic. Existing...SIUs), Air Force ISR liaison officers (ISRLOs), and operational collection managers began maturing processes and growing techniques for employing MTOs.2

  11. Status and perspectives of the dismantling of nuclear power plants in Germany (Dismantling monitoring 2015); Stand und Perspektiven des Rueckbaus von Kernkraftwerken in Deutschland (''Rueckbau-Monitoring 2015'')

    Energy Technology Data Exchange (ETDEWEB)

    Wealer, Ben; Seidel, Jan Paul [Technische Univ. Berlin (Germany); Gerbaulet, Clemens; Hirschhausen, Christian von [Technische Univ. Berlin (Germany); Deutsches Institut fuer Wirtschaftsforschung, Berlin (Germany)

    2015-11-15

    The dismantling monitoring 2015 covers the nuclear power plants HDR Grosswelzheim, Niederaichbach (KKN), MZFR Karlsruhe, Lingen (KWL), Gundremmingen unit A (KRB-A), VAK Kahl, Muehlheim-Kaerlich (KMK), THTR-300 Hamm-Uentrop, AVR Juelich, Greifswald (KGR 1-5), KNK II Karlsruhe, Rheinsberg (KKR), Wuergassen (KWW), Stade (KKS), Obrigheim (KWO), SNR 300. The post-operational phase activities of other shut-down nuclear power plants and the active companies are summarized.

  12. The further development and evaluation of an automatic dismantler of short staple ring-spun yarns

    CSIR Research Space (South Africa)

    Fassihi, A

    2014-07-01

    Full Text Available Information System (AFIS) single fiber length tests, the fibers from automatically dismantled ring-spun cotton yarns are very similar in their properties to those dismantled by hand (manually). It was also found that, at a speed of 2 m/min, the yarn dismantler...

  13. Modelling the cooling and partial dismantling of the Febex in-situ test

    International Nuclear Information System (INIS)

    Sanchez, M.; Gens, A.; Guimaraes, L.

    2010-01-01

    Document available in extended abstract form only. In many designs for radioactive waste disposal the space between the canister and the cavity surface is filled by an engineered barrier made up of compacted expansive clay. Engineered barrier and adjacent host rock will be submitted to the heating effect of the nuclear waste as well as to associated hydraulic and mechanical phenomena that interact in a complex way. In order to achieve a safe and robust repository design, it is necessary to have a good understanding of the processes that occur in the near field and their evolution over time. To this end, properly instrumented full scale in situ tests provide essential information. The in-situ test operated at full scale and under natural conditions at the underground laboratory managed by NAGRA (Swiss National Cooperative for the Disposal of Radioactive Waste) at the Grimsel test site in Switzerland. Two 4300 W heaters were placed in the axis of the horizontal drift in the natural rock (granite). The heaters were 4.54 m long and 0.90 m in diameter, and were intended to simulate the release of heat by nuclear waste. The space between the rock surface and the heaters was backfilled using blocks of compacted bentonite. The test area was sealed with a 2.7 m long concrete plug. The test was heavily instrumented, including 632 sensors that were installed in the clay barrier and in the rock with measurements of temperatures, relative humidity (equivalent to total suction), pore pressures, displacements, and stresses. The heaters were symmetrically placed in relation to the central section of the test. The power of the heaters was adjusted to maintain a 100 deg. C temperature at the interface between heaters and bentonite barrier. The test was run in this way for five years when one of the heaters was switched off and dismantled. Dismantling data provided extremely valuable information about the state of the barrier at the end of the experiment and a useful benchmark for

  14. Advanced robotic remote handling system for reactor dismantlement

    International Nuclear Information System (INIS)

    Shinohara, Yoshikuni; Usui, Hozumi; Fujii, Yoshio

    1991-01-01

    An advanced robotic remote handling system equipped with a multi-functional amphibious manipulator has been developed and used to dismantle a portion of radioactive reactor internals of an experimental boiling water reactor in the program of reactor decommissioning technology development carried out by the Japan Atomic Energy Research Institute. (author)

  15. Dismantling Racial and Hegemonic Boundaries for an Inclusive ...

    African Journals Online (AJOL)

    ... expressed experiences of hostile institutional cultures, untransformed curricula that are largely based on European traditions and norms and a general atmosphere that is tilted towards white supremacy. The article also gives specifi c attention to the formation of a unifying organisational culture, requisite for dismantling

  16. Pick-N-Pull Auto Dismantlers, Kansas City, LLC Inc.

    Science.gov (United States)

    The EPA is providing notice of a proposed Administrative Penalty Assessment against Pick-N-Pull Auto Dismantlers, Kansas City, LLC, a subsidiary of Schnitzer Steel Industries, Inc., for alleged violations at its facilities at 8012 East Truman Rd., Kansas C

  17. Technicians dismantle the inner section of L3

    CERN Multimedia

    Laurent Guiraud

    2001-01-01

    The technicians are dismantling the forward tracking chamber located at the heart of the L3 detector. This formed part of the hadronic calorimeter, which is used for measuring particle energies. L3 was an experiment at the LEP collider that ran from 1989 to 2000.

  18. Dismantling the silicon microstrip detector on L3

    CERN Multimedia

    Laurent Guiraud

    2001-01-01

    The silicon microstrip detector is located at the heart of the detector and must be kept cool to prevent thermal noise. The work shown here is the removal of the cooling system. L3 was dismantled as part of the closure of the entire LEP accelerator in 2000 to make way for the new LHC.

  19. Chemical Decontamination of Metallic Waste from Uranium Conversion Plant Dismantling

    International Nuclear Information System (INIS)

    Hwang, D. S.; Choi, Y. D.; Hwang, S. T.; Park, J. H.; Byun, J. I.; Jang, N. S.

    2005-01-01

    Korea Atomic Energy Research Institute (KAERI) started a decommissioning program of the uranium conversion plant. Pre-work was carried as follows; installation of the access control facility, installation of a changing room and shower room, designation of an emergency exit way and indicating signs, installation of a radiation management facility, preparation of a storage area for tools and equipments, inspection and load test of crane, distribution and packaging of existing waste, and pre-decontamination of the equipment surface and the interior. First, decommissioning work was performed in kiln room, which will be used for temporary radioactive waste storage room. Kiln room housed hydro fluorination rotary kiln for production of uranium tetra-fluoride. The kiln is about 0.8 m in diameter and 5.5 m long. The total dismantled waste was 6,690 kg, 73 % of which was metallic waste and 27 % the others such as cable, asbestos, concrete, secondary waste, etc. And effluent treatment room and filtration room were dismantled for installation of decontamination equipment and lagoon sludge treatment equipment. There were tanks and square mixer in these rooms. The total dismantled waste was 17,250 kg, 67% of which was metallic waste and 33% the others. These dismantled metallic wastes consist of stainless and carbon steel. In this paper, the stainless steel plate and pipe were decontaminated by the chemical decontamination with ultrasonic

  20. Systemic Operational Design: Bringing Efficacy to the Operational Level of War

    National Research Council Canada - National Science Library

    Bernard, Barrett M

    2007-01-01

    The premise of this monograph is that the Elements of Operational Design are incapable of linking the tactical employment of forces to strategic objectives and that Systemic Operational Design is a viable alternative...

  1. Promising technology for the melting and decontamination of dismantled metal by an induction cold crucible

    International Nuclear Information System (INIS)

    Suzuki, M.; Tsurumaki, K.; Akiyama, T.; Fukumura, N.; Tanaka, T.; Yoshida, M.; Ikenaga, Y.

    1998-01-01

    An induction cold crucible melting is one of the most promising technology for the reuse and decontamination of the radioactively contaminated metallic materials generated during the dismantling of nuclear facilities, because the crucible ensures a long life operation without generating the secondary wastes. Based on the knowledge obtained through the fundamental study using the crucible of 45 mm in diameter, the MERC(Melting and Recycling of Metals by -Cold Crucible) process was designed, manufactured and scaled up to 100-140 mm in diameter. Not only cylindrical sectional crucibles but also rectangular slab sectional crucibles were developed. The maximum power of the high frequency generator is 150 kW and the frequency is 25 kHz. In the MERC, either fragments of stainless steel or tubing and pipings with small section, which were the surrogates of contaminated metallic materials, were continuously supplied together with the flux for the decontamination, followed by melting in the crucible and pulling down by the precise withdrawal system ensuring the melt dome to be kept at a suitable level for the melting. The maximal withdrawal velocity employed was 12 mm/min. The Ingot and slab were cut in every 300 mm length by the mechanical saw. They were automatically transported to the outlet of the equipment by the conveying system. Heat efficiency of the MERC was more than 26%. The ingot surface was smooth and crack free, facilitating the removal of radioactive elements concentrated in a slag stuck on the ingot surface. There was no macro segregation inside. Tracer elements of Sr and Hf transferred to the slag, Cs and Zn to the dust. Co and Mn mostly remained in the ingot. However, up to 10% of Co could transfer to the slag. This work was done under the sponsorship of Science and Technology Agency of Japan. (author)

  2. Standing operating procedures for developing acute exposure guideline levels for hazardous chemicals

    National Research Council Canada - National Science Library

    National Research Council (U.S.). Subcommittee on Acute Exposure Guideline Levels

    2001-01-01

    Standing Operating Procedures for Developing Acute Exposure Guideline Levels for Hazardous Chemicals contains a detailed and comprehensive methodology for developing acute exposure guideline levels (AEGLs...

  3. Better uses for financial reserves. Reserves for decommisioning, dismantling and waste management could be used for changing energy sructures

    International Nuclear Information System (INIS)

    Irrek, W.

    1996-01-01

    The reserves laid back by German operators of nuclear power plants for decommissioning, dismantling and waste management amounted to more than DM 44 billion in 1994, and the sum is still increasing. With this money, the public utilities intend to strengthen their competitive position in other industrial sectrors. The author proposes to transfer this money into public funds instead in order to ensure that it is used in an economically more efficient manner. (orig./RHM) [de

  4. Radiological survey techniques for decontamination and dismantlement applications

    International Nuclear Information System (INIS)

    Ruesink, G.P.; Stempfley, D.H.; Pettit, P.J.; Warner, R.D.

    1997-01-01

    The Department of Energy's Fernald Environmental Management Project (FEMP) is engaged in an aggressive Program to remove all above ground structures as part of the Fernald sites final remediation remedy. Through the complete removal of major facilities such as Plant 7, Plant 4, and Plant 1, the FEMP has developed radiological survey approaches that are effective for the different phases of the Decontamination and Dismantlement (D ampersand D) process. Some of the most pressing challenges facing the FEMP are implementing effective, low cost methods for the D ampersand D of former process buildings while minimizing environmental effects. One of the key components to ensure minimal impact on the environment is the collection of radiological contamination information during the D ampersand D process to facilitate the decision making process. Prior to the final demolition of any structure, radiological surveys of floors, walls, and ceilings must take place. These surveys must demonstrate that contamination levels am below 5000 dpm removable beta/gamma for non-porous surfaces and below 1000 dpm removable-beta/gamma for all porous surfaces. Technique which can perform these activities in a safe, effective, and cost efficient manner are greatly desired. The FEMP has investigated new approaches to address this need. These techniques include sampling approaches using standard baseline methodology as well as innovative approaches to accelerate final radiological clearance processes. To further improve upon this process, the FEMP has investigated several new technologies through the Fernald Plant 1 Large Scale Technology Demonstration Project. One of the most promising of these new technologies, Laser Induced Fluorescence, may significantly improve the radiological clearance survey process. This paper will present real world experiences in applying radiological control limits to D ampersand D projects as well as relate potential productivity and cost improvements with the

  5. The inherent advantages of delayed dismantling of decommissioning nuclear stations

    International Nuclear Information System (INIS)

    Liederman, J.M.; Saroudis, J.I.

    1985-01-01

    Recent studies in Canada pertaining to the decommissioning of the CANDU 600 MW(e) reactor have led to the development of the option of a ''static state'' condition. This alternative is based on judging risk and benefit to society considering the greatly reduced potential radiation exposure to personnel after 30 to 80 years have elapsed, following the final shutdown of the reactor. After approximately 80 to 120 years have elapsed, the decay in all systems and components (with the exception of the reactor assembly) would be such that radiation fields would be at background levels producing an environment that would be acceptable for Stage 3 decommissiong. This philosophy is based on the current engineering judgement that: - All systems, components, and structures which were associated with the nuclear processes and are radioactive, can be put into a static or storage state, and a containment function maintained at low cost for prolonged periods of between 80 to 120 years. - Between 80 to 120 years after shutdown, most of the radioactivity, except for some long lived radionuclides in the reactor vessel itself and its vault, will have naturally decayed to near releasable limits without any external intervention. - There is a lower overall risk to society in this approach, than dismantling and transporting radioactive materials prematurely. This philosophy is developed taking into consideration radiation protection, financial and risk assessment issues. The Canadian concept of dry storage of spent fuel is part of this philosophy and may be of interest to decommissioned nuclear plants of other types. 4 tables, 5 graphs

  6. Main Results of Updated Decommission Conception of NPPs Operating in Ukraine

    International Nuclear Information System (INIS)

    Purtov, Oleg; Masko, Alexander; Vasilchenko, Victor

    2014-01-01

    Results of long-term planning analysis based on consideration of 6 possible scenarios for the nuclear energy development with 15 years and 20 years life time extensions of operation of nuclear power units beyond 30 year provided by original design are presented in the updated decommission conception of NPP's operating in Ukraine. These characteristics of the two main options for NPP decommissioning deferred or immediate dismantling, which is close to the level of acceptability with relative superiority variant of deferred dismantling, are presented. The best option for NPP unit decommissioning as comparative analysis results is the option with deferred dismantling with 30 years endurance time. It can be taken as a basis for optimal strategies for NPP unit decommission design development. Cost estimations for the decommissioning of WWER-440 and WWER-1000 reactor type units are presented in the updated conception. The updated cost assessment for required annual payments with uniform accumulation costs to the Decommission Fund corresponding deferred dismantling variant with 20 years life time extension operation time is 98,2 mln US$ per year. This value is 3.61% of the electricity generated by NPP's in Ukraine and supplied to the wholesale electricity market of Ukraine in 2012 base year. (authors)

  7. Integrating Space Systems Operations at the Marine Expeditionary Force Level

    Science.gov (United States)

    2015-06-01

    Operation ARSST Army Space Support Team BCT Brigade Combat Team BDA Battle Damage Assessment BLOS Beyond Line of Site C2 Command and Control CMCC-CP...accurate imagery of known target locations. Additionally, ISR systems provide a convenient battle damage assessment ( BDA ) option necessary to determine

  8. Safe dismantling of the SVAFO research reactors R2 and R2-0 in Sweden

    International Nuclear Information System (INIS)

    ARNOLD, Hans-Uwe; BROY, Yvonne; Dirk Schneider

    2017-01-01

    The R2 and R2-0 reactors were part of the Swedish government's research program on nuclear power from the early 1960's. Both reactors were shut down in 2005 following a decision by former operator Studsvik Nuclear AB. The decommissioning of the R2 and R2-0 reactors is divided into three phases. The first phase - awarded to AREVA - involved dismantling of the reactors and associated systems in the reactor pool, treatment of the disassembled components as well as draining, cleaning and emptying the pool. In the second phase, the pool structure itself will be dismantled, while removal of remaining reactor systems, treatment and disposal of materials and clean-up will be carried out in the third stage. The entire work is planned to be completed before the end of this decade. The paper describes the several steps of phase 1 - starting with the team building, followed by the dismantling operations and covers challenges encountered and lessons learned as well. The reactors consist of 5.400 kg aluminum, 6.000 kg stainless steel restraint structures as well as, connection elements of the mostly flanged components (1.000 kg). The most demanding - from a radiological point of view - was the R2-0 reactor that was limited to ∼ 1 m"3 construction volumes but with an extremely heterogeneous activation profile. Based on the calculated radiological entrance data and later sampling, nuclide vectors for both reactors depending on the real placement of the single component and on the material (aluminum and stainless steel) were created. Finally, for the highest activated component from R2 reactor, 85 Sv/h were measured. The dismantling principles - adopted on a safety point of view - were the following: The always protected base area of the ponds served as a flexible buffer area for waste components and packaging. Specific protections were also installed on the walls to protect them from mechanical stress which may occur during dismantling work. A specific work platform was

  9. The Japan Power Demonstration Reactor (JPDR) dismantling activities. Dismantling of the reactor enclosure and the auxiliary buildings

    International Nuclear Information System (INIS)

    Seiki, Yoshihiro; Kubo, Takashi.

    1996-01-01

    As the final stage of the JPDR decommissioning program, after the major components were removed from each building of JPDR, the dismantling activities proceeded to the decontamination of contaminated concrete surface and the final radiation survey of buildings. These activities were conducted to verify the developed techniques and the detailed procedures for decontamination, and to allow unrestricted use of the JPDR buildings. Following the decontamination of buildings, the dismantling of each building was started. Before dismantling the buildings, the radiation control designations were changed. The buildings that contaminated embedded pipes were changed from first-class radiation controlled areas to second-class radiation controlled areas. On the other hand, the buildings that had no contaminated pipes were changed to uncontrolled areas. A first-class radiation controlled area allows the use of unsealed sources ; thus, radioactive contamination may exist. A second-class radiation controlled area is one where only sealed sources are allowed. Significant quantities of data and experience were obtained during these activities. The practical procedures for decontamination, the final survey of radioactivity, and the dismantling work of buildings were described in this report. (author)

  10. Topical Session on the Decommissioning and Dismantling Safety Case

    International Nuclear Information System (INIS)

    2002-01-01

    Set up by the Radioactive Waste Management Committee (RWMC), the WPDD brings together senior representatives of national organisations who have a broad overview of Decommissioning and Dismantling (D and D) issues through their work as regulators, implementers, R and D experts or policy makers. These include representatives from regulatory authorities, industrial decommissioners from the NEA Cooperative Programme on Exchange of Scientific and Technical Information on Nuclear Installation Decommissioning Projects (CPD), and cross-representation from the NEA Committee on Nuclear Regulatory Activities, the Committee on Radiation Protection and Public Health, and the RWMC. The EC is a member of the WPDD and the IAEA also participates. This ensures co-ordination amongst activities in these international programmes. Participation from civil society organisations is considered on a case by case basis, and has already taken place through the active involvement of the Group of Municipalities with Nuclear Installations at the first meeting of the WPDD At its second meeting, in Paris, 5-7 December 2001, the WPDD held two topical sessions on the D and D Safety Case and on the Management of Materials from D and D, respectively. This report documents the topical session on the safety case. The topical session was meant to provide an exchange of information and experience on the following issues: What topics should be included in a safety case? Of what should it consist? Is there sufficient and complete guidance nationally and internationally? How do practices differ internationally? Main boundary condition to this session was that it would deal with plants where spent fuel has been removed. Also the topical sessions was kept at a level that makes the most of the varied constituency of the WPDD. Namely, interface issues are important, and issue-identification and discussion was the immediate goal. There was less interest in examining areas where variability amongst national

  11. TSTA loop operation with 100 grams-level of tritium

    International Nuclear Information System (INIS)

    Yoshida, Hiroshi; Fukui, Hiroshi; Hirata, Shingo

    1988-12-01

    A fully integrated loop operation test of Tritium systems Test Assembly (TSTA) with 107 grams of tritium was completed at Los Alamos National Laboratory (LANL) in June, 1988. In this test, a compound cryopump with a charcoal panel was incorporated into the main process loop for the first time. The objectives were (i) to demonstrate the compound cryopump system with different flow rates and impurities, (ii) to demonstrate the regeneration of the compound cryopump system, (iii) to accumulate operating experience with other process systems such as the fuel cleanup system, the isotope separation system, the tritium supply and recovery system, etc. and (iv) to improve the data-base on TSTA safety systems such as the secondary containment system, tritium waste treatment system and tritium monitoring system. This report briefly describes characteristics of the main subsystems observed during the milestone run. (author)

  12. Cyberspace at the Operational Level: Warfighting in All Five Domains

    Science.gov (United States)

    2016-05-13

    Sean Hall 5e. TASK NUMBER Paper Advisor: Prof John Sappenfield 5f. WORK UNIT NUMBER 7. PERFORMING ORGANIZATION NAME(S) AND ADDRESS...decisive, operational objective, center of gravity , planner, commander. 16. SECURITY CLASSIFICATION OF: 17. LIMITATION OF ABSTRACT 18. NUMBER OF...requires much more than doctrinal definitions. History shows how well or poorly nations integrated the sea, air, and space domains in their infancy

  13. L3 experiment dismantling at LEP

    CERN Multimedia

    Laurent Guiraud

    2001-01-01

    The last muon chamber is removed from the L3 experiment at the LEP collider, which was in operation from 1989 to 2000. The large red magnet yoke will be reused by the ALICE experiment when the LHC is constructed.

  14. Operational Bright-Band Snow Level Detection Using Doppler Radar

    Data.gov (United States)

    National Oceanic and Atmospheric Administration, Department of Commerce — A method to detect the bright-band snow level from radar reflectivity and Doppler vertical velocity data collection with an atmospheric profiling Doppler radar. The...

  15. Data analysis on work activities in dismantling of Japan Power Demonstration Reactor (JPDR). Contract research

    International Nuclear Information System (INIS)

    Shiraishi, Kunio; Sukegawa, Takenori; Yanagihara, Satoshi

    1998-03-01

    The safe dismantling of a retired nuclear power plant was demonstrated by completion of dismantling activities for the Japan Power Demonstration Reactor (JPDR), March, 1996, which had been conducted since 1986. This project was a flag ship project for dismantling of nuclear power plants in Japan, aiming at demonstrating an applicability of developed dismantling techniques in actual dismantling work, developing database on work activities as well as dismantling of components and structures. Various data on dismantling activities were therefore systematically collected and these were accumulated on computer files to build the decommissioning database; dismantling activities were characterized by analyzing the data. The data analysis resulted in producing general forms such as unit activity factors, for example, manpower need per unit weight of component to be dismantled, and simple arithmetic forms for forecasting of project management data to be applied to planning another dismantling project through the evaluation for general use of the analyzed data. The results of data analysis could be usefully applied to planning of future decommissioning of commercial nuclear power plants in Japan. This report describes the data collection and analysis on the JPDR dismantling activities. (author)

  16. Calculations of radiation levels during reactor operations for safeguard inspections

    International Nuclear Information System (INIS)

    Sobhy, M.

    1996-01-01

    When an internal core spent fuel storage is used in the shield tank to accommodate a large number of spent fuel baskets, physical calculations are performed to determine the number of these spent fuel elements which can be accommodated and still maintain the gamma activity outside under the permissible limit. The corresponding reactor power level is determined. The radioactivity calculations are performed for this internal storage at different axial levels to avoid the criticality of the reactor core. Transport theory is used in calculations based on collision probability for multi group cell calculations. Diffusion theory is used in three dimensions in the core calculations. The nuclear fuel history is traced and radioactive decay is calculated, since reactor fission products are very sensitive to power level. The radioactivity is calculated with a developed formula based on fuel basket loading integrity. (author)

  17. Blood lead and carboxyhemoglobin levels in chainsaw operators.

    Science.gov (United States)

    van Netten, C; Brubaker, R L; Mackenzie, C J; Godolphin, W J

    1987-06-01

    Fallers in the British Columbia west coast lumber industry often work in climatic and local conditions where little ventilation in their immediate environment is possible. Under these conditions carbon monoxide (CO) and lead fumes from exhaust gases could build up and become a serious occupational hazard. This study monitored the environmental exposure of six fallers to carbon monoxide, nitrogen oxides, and lead under conditions where buildup of these agents would be expected. At the same time blood samples were taken to correlate these environmental concentrations to carboxyhemoglobin (COHb) and blood lead levels. Although there was a highly significant difference between the fallers and the controls regarding the exposure to CO and lead as well as their corresponding COHb and blood lead levels, the environmental and blood concentration of the agents in question did not exceed the maximum allowable concentrations. Temporary short fluctuations in carboxyhemoglobin levels were not monitored in this study and cannot be ruled out as a potential occupational hazard.

  18. Blood lead and carboxyhemoglobin levels in chainsaw operators

    Energy Technology Data Exchange (ETDEWEB)

    van Netten, C.; Brubaker, R.L.; Mackenzie, C.J.; Godolphin, W.J.

    1987-06-01

    Fallers in the British Columbia west coast lumber industry often work in climatic and local conditions where little ventilation in their immediate environment is possible. Under these conditions carbon monoxide (CO) and lead fumes from exhaust gases could build up and become a serious occupational hazard. This study monitored the environmental exposure of six fallers to carbon monoxide, nitrogen oxides, and lead under conditions where buildup of these agents would be expected. At the same time blood samples were taken to correlate these environmental concentrations to carboxyhemoglobin (COHb) and blood lead levels. Although there was a highly significant difference between the fallers and the controls regarding the exposure to CO and lead as well as their corresponding COHb and blood lead levels, the environmental and blood concentration of the agents in question did not exceed the maximum allowable concentrations. Temporary short fluctuations in carboxyhemoglobin levels were not monitored in this study and cannot be ruled out as a potential occupational hazard.

  19. Information Flow Analysis of Level 4 Payload Processing Operations

    Science.gov (United States)

    Danz, Mary E.

    1991-01-01

    The Level 4 Mission Sequence Test (MST) was studied to develop strategies and recommendations to facilitate information flow. Recommendations developed as a result of this study include revised format of the Test and Assembly Procedure (TAP) document and a conceptualized software based system to assist in the management of information flow during the MST.

  20. Radiochemistry Lab Decommissioning and Dismantlement. AECL, Chalk River Labs, Ontario, Canada

    International Nuclear Information System (INIS)

    Kenny, Stephen

    2008-01-01

    Atomic Energy of Canada (AECL) was originally founded in the mid 1940's to perform research in radiation and nuclear areas under the Canadian Defense Department. In the mid 50's The Canadian government embarked on several research and development programs for the development of the Candu Reactor. AECL was initially built as a temporary site and is now faced with many redundant buildings. Prior to 2004 small amounts of Decommissioning work was in progress. Many reasons for deferring decommissioning activities were used with the predominant ones being: 1. Reduction in radiation doses to workers during the final dismantlement, 2. Development of a long-term solution for the management of radioactive wastes in Canada, 3. Financial constraints presented by the number of facilities shutdown that would require decommissioning funds and the absence of an approved funding strategy. This has led to the development of a comprehensive decommissioning plan that is all inclusive of AECL's current and legacy liabilities. Canada does not have a long-term disposal site; therefore waste minimization becomes the driving factor behind decontamination for decommissioning before and during dismantlement. This decommissioning job was a great learning experience for decommissioning and the associated contractors who worked on this project. Throughout the life of the project there was a constant focus on waste minimization. This focus was constantly in conflict with regulatory compliance primarily with respect to fire regulations and protecting the facility along with adjacent facilities during the decommissioning activities. Discrepancies in historical documents forced the project to treat every space as a contaminated space until proven differently. Decommissioning and dismantlement within an operating site adds to the complexity of the tasks especially when it is being conducted in the heart of the plant. This project was very successful with no lost time accidents in over one hundred

  1. Evolution of radiation protection of overall decommissioning and Dismantling of a Nuclear Power Plants

    International Nuclear Information System (INIS)

    Ortiz, M. T.; Ondaro, M.; Irun, I.; Just, J.

    2000-01-01

    From the point of view of Radiological Protection, the overall Decommissioning and Dismantling (D and D) Plan of a Nuclear Power Plant cannot be considered in isolation without considering the evolution of the radiological characteristics of the installation and the site itself from previous, during and final states. This experience of D and D is the first in Spain and in other European countries due to several aspects: 1) the reference reactor technology, 2) total grass power, and 3) management of a great amount of materials to be released. Three decommissioning alternatives were studied: Indefinite maintenance in shutdown state, Stage 1. Stage 2 for the defuelled reactor vessel and contents, with decontamination of most of the rest of the site. Immediate dismantling to Stage 3. Stage 2 was the alternative selected with the release of 80% of the site, keeping the remaining 20% of the site as a regulated area, housing the reactor vessel in a new structure and removing the radioactive waste. The above, along with the fact that this is a specific type of natural uranium-graphite-gas plant (NUGG) and that ownership of the facility has been transferred for dismantling (from HIFRENSA to ENRESA), implies a series of preliminary considerations that, for the purposes of this article, are compiled in the following aspects: a) Preliminary phase prior to transfer, b) Preparatory phase, and c) Dismantling phase. This paper describes aspects under the D and D experiences at CN-V1 NPP, now in progress, from the point of view of the radiological aspects in relation with the continuous updating of the source term. Operative Radiological nuclide vectors, applicable in the Radiation Protection tasks, are also commented to prevent and evaluate several risks during the execution of the works. Finally, there is a description of the results obtained from the work performed to decay the three actual nuclide vectors, to evaluate and obtain activity calculations for the release of the

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

    International Nuclear Information System (INIS)

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

    1999-01-01

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

  3. Dismantling an alpha-contaminated facility

    International Nuclear Information System (INIS)

    Caldwell, R.D.; Harper, R.M.

    1975-01-01

    The difficult task of removing large pieces of highly contaminated equipment from an obsolete plutonium-239 facility was completed in a seven-month operation that included structural alteration of the process building. Detailed job planning, job execution and contamination control were major factors in accomplishing the task

  4. 14 CFR 91.865 - Phased compliance for operators with base level.

    Science.gov (United States)

    2010-01-01

    ... 14 Aeronautics and Space 2 2010-01-01 2010-01-01 false Phased compliance for operators with base... Noise Limits § 91.865 Phased compliance for operators with base level. Except as provided in paragraph... maximum of: (1) After December 31, 1994, 75 percent of the base level held by the operator; (2) After...

  5. Seizing opportunities for change at the operational level.

    Science.gov (United States)

    Restrepo, Diana; Charron-Latour, Julie; Pourmonet, Hugo; Bassetto, Samuel

    2016-04-18

    Purpose - This paper presents a method for handling everyday opportunities for improvement, led by floor staff in healthcare institutions. More than 400,000 incidents and accidents were recorded in Quebec healthcare institutions in 2013. The burden of treatment falls on hospital floor staff. The purpose of this paper is to raise the visibility of this problem and support staff better in their efforts to handle opportunities for improvement. Design/methodology/approach - Based on issues identified in the literature, which have been found to exist in various organizations, the method involved reviewing practices in the field, proposing a solution, and testing it to assess its relevance and limitations. The method was tested in partnership with the Centre Hospitalier de l'Université de Montréal, in the internal medicine unit at Hôtel-Dieu campus. The test lasted three months. Indicators from this test have been compared to results in the literature. Findings - The proposed method presents a 68 per cent increase in ideas generated per person and per week compared to the reference study. The mean time for closing actions was about 41 per cent better (lower) than in the reference case. Research limitations/implications - The test lasted 15 weeks; a longer test is needed to collect more data. Practical implications - The first practical implication of this study was the creation of a method allowing employees to seize opportunities for improvement in their daily work. The application of this method revealed: first, the operational nature of the proposal (empowerment of the work team); second, the operationalization of continuous improvement (71 per cent of ideas were finalized while the initiative was monitored); third, the smooth operation of the mechanism for facilitating continuous improvement (organization of weekly meetings and team participation in these meetings in 90 per cent of cases); and fourth, a shared feeling that intra- and inter-team communication had

  6. Exposure levels to electromagnetic fields in usual operative situations

    International Nuclear Information System (INIS)

    Bemardi, C; Bemardi, T.; Testoni, G.; Zannoli, R.; Tubertini, O

    1997-01-01

    In the last few years, the whole population have been repeatedly solicited from media about the possible negative effects of E.M. Fields involved in all the social activities. This determinate the need of evaluations of the risks in different conditions, supported by accurate measurement protocols. This paper describes the procedures and the results of measurements in four different conditions, which involve the whole population and/or workers of a specific field. Results have been used both to increase the knowledge of the E.M. exposure levels and to evaluate the risks, with respect to the National Rules and Guidelines. (authors)

  7. LEP Dismantling - a first Step into New Era

    CERN Multimedia

    2000-01-01

    The aim of the project is to remove the LEP machine and most of the services from the underground areas in order to install the LHC within the time constraints of its civil engineering and installation programmes The dismantling of LEP will be the first project to be executed under the new INB (Installation Nucléaire de Base) convention for the LHC. This talk will give an overview of the LEP Dismantling project covering traceability, planning, infrastructure and execution. It will explain what it means for our accelerators to be classified as INB's and will introduce the changes in working and safety procedures, which will be enforced from the beginning of October. Note: The presentation will be made in French with the transparencies in English.

  8. Long range manipulator development and experiments with dismantling tools

    International Nuclear Information System (INIS)

    Mueller, K.

    1993-01-01

    An existing handling system (EMIR) was used as a carrier system for various tools for concrete dismantling and radiation protection monitoring. It combined the advantages of long reach and high payload with highly dexterous kinematics. This system was enhanced mechanically to allow the use of different tools. Tool attachment devices for automatic tool exchange were investigated as well as interfaces (electric, hydraulic, compressed air, cooling water and signals). The control system was improved with regard to accuracy and sensor data processing. Programmable logic controller functions for tool control were incorporated. A free field mockup of the EMIR was build that allowed close simulation of dismantling scenarios without radioactive inventory. Aged concrete was provided for the integration tests. The development scheduled included the basic concept investigation; the development of tools and sensors; the EMIR hardware enhancement including a tool exchange; the adaption of tools and mockup and the final evaluation of the system during experiments

  9. Towards a more professional demolition and dismantling industry

    International Nuclear Information System (INIS)

    1988-01-01

    The work of the National Economic Development Office Demolition and Dismantling Group in four areas which are crucial to the economic performance of the demolition and dismantling industry and its safety record is considered. The first concerns the availability and accessibility of information about unconventional structures and details are given of the sort of information often kept for different types of structure. Secondly, the need is stressed for guidelines for the client, particularly on the risks involved and the choice of a competent contractor. Thirdly, basic credentials which it is important for contractors to set out in order to establish a good reputation for the industry are set out. Finally, the particular case of nuclear power station decommissioning is considered with reference to the size of the market, the pioneering knowledge to be gained from the decommissioning of the Windscale Advanced Gas-cooled Reactor, private sector involvement and the special techniques required. (U.K.)

  10. Operational experience with the ALICE High Level Trigger

    Science.gov (United States)

    Szostak, Artur

    2012-12-01

    The ALICE HLT is a dedicated real-time system for online event reconstruction and triggering. Its main goal is to reduce the raw data volume read from the detectors by an order of magnitude, to fit within the available data acquisition bandwidth. This is accomplished by a combination of data compression and triggering. When HLT is enabled, data is recorded only for events selected by HLT. The combination of both approaches allows for flexible data reduction strategies. Event reconstruction places a high computational load on HLT. Thus, a large dedicated computing cluster is required, comprising 248 machines, all interconnected with InfiniBand. Running a large system like HLT in production mode proves to be a challenge. During the 2010 pp and Pb-Pb data-taking period, many problems were experienced that led to a sub-optimal operational efficiency. Lessons were learned and certain crucial changes were made to the architecture and software in preparation for the 2011 Pb-Pb run, in which HLT had a vital role performing data compression for ALICE's largest detector, the TPC. An overview of the status of the HLT and experience from the 2010/2011 production runs are presented. Emphasis is given to the overall performance, showing an improved efficiency and stability in 2011 compared to 2010, attributed to the significant improvements made to the system. Further opportunities for improvement are identified and discussed.

  11. Operational experience with the ALICE High Level Trigger

    International Nuclear Information System (INIS)

    Szostak, Artur

    2012-01-01

    The ALICE HLT is a dedicated real-time system for online event reconstruction and triggering. Its main goal is to reduce the raw data volume read from the detectors by an order of magnitude, to fit within the available data acquisition bandwidth. This is accomplished by a combination of data compression and triggering. When HLT is enabled, data is recorded only for events selected by HLT. The combination of both approaches allows for flexible data reduction strategies. Event reconstruction places a high computational load on HLT. Thus, a large dedicated computing cluster is required, comprising 248 machines, all interconnected with InfiniBand. Running a large system like HLT in production mode proves to be a challenge. During the 2010 pp and Pb-Pb data-taking period, many problems were experienced that led to a sub-optimal operational efficiency. Lessons were learned and certain crucial changes were made to the architecture and software in preparation for the 2011 Pb-Pb run, in which HLT had a vital role performing data compression for ALICE's largest detector, the TPC. An overview of the status of the HLT and experience from the 2010/2011 production runs are presented. Emphasis is given to the overall performance, showing an improved efficiency and stability in 2011 compared to 2010, attributed to the significant improvements made to the system. Further opportunities for improvement are identified and discussed.

  12. Dismantling Experiment of Mock-up Tube Bundle of Steam Generator

    International Nuclear Information System (INIS)

    Kim, Sung Kyun; Lee, Kune Woo

    2010-01-01

    A SG (steam generator) is one of the biggest decommissioning components in nuclear power plants and one has been replaced 2∼6 times during the whole operation of a nuclear power plant. The old SG should be decommissioned for the purpose of the volume reduction of radioactive waste. Among the components of SG, the tube bundle is one of the most difficult items to be dismantled due to the fact that it is very hard to cut since it is made of Inconel 600 which has high resistance of corrosion and abrasion. Moreover, All cutting process should be performed by remotely since radioactive contamination of the internal surface of SG tubes is very high (about 150,000∼300,000 Bq/cm 2 ). Therefore, it is necessary to choose the appropriate cutting methods by the pros and cons analysis for candidate dismantling technologies and to do experiment study for the validation. In this study, the results of cutting experiment for a mock-up bundle by using band saw cutting method are described herein

  13. Process Concepts for Semi-automatic Dismantling of LCD Televisions

    OpenAIRE

    Elo, Kristofer; Sundin, Erik

    2014-01-01

    There is a large variety of electrical and electronic equipment products, for example liquid crystal display television sets (LCD TVs), in the waste stream today. Many LCD TVs contain mercury, which is a challenge to treat at the recycling plants. Two current used processes to recycle LCD TVs are automated shredding and manual disassembly. This paper aims to present concepts for semi-automated dismantling processes for LCD TVs in order to achieve higher productivity and flexibility, and in tu...

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

    International Nuclear Information System (INIS)

    Rose, N.

    1994-01-01

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

  15. Decontamination and dismantlement of Plant 7 at Fernald

    International Nuclear Information System (INIS)

    Albertin, M.; Borgman, T.; Zebick, B.

    1994-01-01

    Decontamination and dismantlement (D ampersand D) tasks have been successfully completed on Plant 7 at the Fernald Environmental Management Project. The seven story facility was radiologically, chemically, and biologically contaminated. The work involved the D ampersand D work beginning with safe shutdown and gross decontamination, and ended with removal of the structural steel. A series of lessons learned were gained which include use of explosives, bidding tactics, safe shutdown, building decontamination and lockdown, use of seam climbers, etc

  16. Robotic dismantlement systems at the CP-5 reactor D and D project

    International Nuclear Information System (INIS)

    Seifert, L. S.

    1998-01-01

    The Chicago Pile 5 (CP-5) Research Reactor Facility is currently undergoing decontamination and decommissioning (D and D) at the Argonne National Laboratory (ANL) Illinois site. CP-5 was the principle nuclear reactor used to produce neutrons for scientific research at Argonne from 1954 to 1979. The CP-5 reactor was a heavy-water cooled and moderated, enriched uranium-fueled reactor with a graphite reflector. The CP-5 D and D project includes the disassembly, segmentation and removal of all the radioactive components, equipment and structures associated with the CP-5 facility. The Department of Energy's Robotics Technology Development Program and the Federal Energy Technology Center, Morgantown Office provided teleoperated, remote systems for use in the dismantlement of the CP-5 reactor assembly for tasks requiring remote dismantlement as part of the EM-50 Large-Scale Demonstration Program (LSDP). The teleoperated systems provided were the Dual Arm Work Platform (DAWP), the Rosie Mobile Teleoperated Robot Work System (ROSIE), and a remotely-operated crane control system with installed swing-reduction control system. Another remotely operated apparatus, a Brokk BM250, was loaned to ANL by the Princeton Plasma Physics Laboratory (PPPL). This machine is not teleoperated and was not part of the LSDP, but deserves some mention in this discussion. The DAWP is a robotic dismantlement system that includes a pair of Schilling Robotic Systems Titan III hydraulic manipulator arms mounted to a specially designed support platform: a hydraulic power unit (HPU) and a remote operator console. The DAWP is designed to be crane-suspended for remote positioning. ROSIE, developed by RedZone Robotics, Inc. is a mobile, electro-hydraulic, omnidirectional platform with a heavy-duty telescoping boom mounted to the platform's deck. The work system includes the mobile platform (locomotor), a power distribution unit (PDU) and a remote operator console. ROSIE moves about the reactor building

  17. Waste Management Strategy for Dismantling Waste to Reduce Costs for Power Plant Decommissioning - 13543

    Energy Technology Data Exchange (ETDEWEB)

    Larsson, Arne; Lidar, Per [Studsvik Nuclear AB, SE-611 82 Nykoeping (Sweden); Bergh, Niklas; Hedin, Gunnar [Westinghouse Electric Sweden AB, Fredholmsgatan 2, SE-721 63, Vaesteraas (Sweden)

    2013-07-01

    Decommissioning of nuclear power plants generates large volumes of radioactive or potentially radioactive waste. The proper management of the dismantling waste plays an important role for the time needed for the dismantling phase and thus is critical to the decommissioning cost. An efficient and thorough process for inventorying, characterization and categorization of the waste provides a sound basis for the planning process. As part of comprehensive decommissioning studies for Nordic NPPs, Westinghouse has developed the decommissioning inventories that have been used for estimations of the duration of specific work packages and the corresponding costs. As part of creating the design basis for a national repository for decommissioning waste, the total production of different categories of waste packages has also been predicted. Studsvik has developed a risk based concept for categorization and handling of the generated waste using six different categories with a span from extremely small risk for radiological contamination to high level waste. The two companies have recently joined their skills in the area of decommissioning on selected market in a consortium named 'ndcon' to further strengthen the proposed process. Depending on the risk for radiological contamination or the radiological properties and other properties of importance for waste management, treatment routes are proposed with well-defined and proven methods for on-site or off-site treatment, activity determination and conditioning. The system is based on a graded approach philosophy aiming for high confidence and sustainability, aiming for re-use and recycling where found applicable. The objective is to establish a process where all dismantled material has a pre-determined treatment route. These routes should through measurements, categorization, treatment, conditioning, intermediate storage and final disposal be designed to provide a steady, un-disturbed flow of material to avoid

  18. Waste Management Strategy for Dismantling Waste to Reduce Costs for Power Plant Decommissioning - 13543

    International Nuclear Information System (INIS)

    Larsson, Arne; Lidar, Per; Bergh, Niklas; Hedin, Gunnar

    2013-01-01

    Decommissioning of nuclear power plants generates large volumes of radioactive or potentially radioactive waste. The proper management of the dismantling waste plays an important role for the time needed for the dismantling phase and thus is critical to the decommissioning cost. An efficient and thorough process for inventorying, characterization and categorization of the waste provides a sound basis for the planning process. As part of comprehensive decommissioning studies for Nordic NPPs, Westinghouse has developed the decommissioning inventories that have been used for estimations of the duration of specific work packages and the corresponding costs. As part of creating the design basis for a national repository for decommissioning waste, the total production of different categories of waste packages has also been predicted. Studsvik has developed a risk based concept for categorization and handling of the generated waste using six different categories with a span from extremely small risk for radiological contamination to high level waste. The two companies have recently joined their skills in the area of decommissioning on selected market in a consortium named 'ndcon' to further strengthen the proposed process. Depending on the risk for radiological contamination or the radiological properties and other properties of importance for waste management, treatment routes are proposed with well-defined and proven methods for on-site or off-site treatment, activity determination and conditioning. The system is based on a graded approach philosophy aiming for high confidence and sustainability, aiming for re-use and recycling where found applicable. The objective is to establish a process where all dismantled material has a pre-determined treatment route. These routes should through measurements, categorization, treatment, conditioning, intermediate storage and final disposal be designed to provide a steady, un-disturbed flow of material to avoid interruptions. Bottle

  19. Operation of low-level radioactive waste incinerator

    International Nuclear Information System (INIS)

    Choi, E.C.; Drolet, T.S.; Stewart, W.B.; Campbell, A.V.

    1979-01-01

    Ontaro Hydro's radioactive waste incinerator designed to reduce the volume of low-level combustible wastes from nuclear generating station's was declared in-service in September 1977. Hiterto about 1500 m 3 of combustible waste have been processed in over 90 separate batches. The process has resulted in 40:1 reduction in the volume and 12.5:1 reduction in the weight of the Type 1 wastes. The ultimate volume reduction factor after storage is 23:1. Airborne emissions has been maintained at the order of 10 -3 to 10 -5 % of the Derived Emission Limits. Incineration of radioactive combustible wastes has been proven feasible, and will remain as one of the most important processes in Ontario Hydro's Radioactive Waste Management Program

  20. Dismantlement and destruction of chemical, nuclear and conventional weapons

    International Nuclear Information System (INIS)

    Schulte, N.T.

    1997-01-01

    The safe destruction and dismantling of chemical, nuclear and conventional weapons is of fundamental importance to the security of all countries represented in this volume. Expertise in the field is not confined to one country or organisation: all can benefit from each other. There is an ever present danger of proliferation of weapons of mass destruction: approximately two dozen countries have ongoing programmes to develop or acquire such weapons, and many are also gaining the capability to build air-surface delivery systems. But much can be done to prevent proliferation by reducing leakage of materials and know-how and by solving the problems of the destruction of surplus weapons systems, which has now come to be a key issue. In 13 sessions of the workshop attention was paid to (1) Dismantlement and Destruction of Chemical, Nuclear and Conventional Weapons; (2) Status of Implementation of Arms Control Treaties and Voluntary Commitments; (3) National Perspectives on Cooperation in Disarmament; (4) Stocktaking of National and Bilateral Disposal/Destruction Programmes: Chemical Weapons; (5) Stocktaking of National and Bilateral Disposal/Destruction Programmes: Nuclear Weapons; (6) Stocktaking of National and Bilateral Disposal/Destruction Programmes: Conventional Weapons. Session; (7) Experience with Currently Employed Chemical Destruction Technologies; (8) Alternative Chemical Destruction Technologies; (9) Deactivation, Dismantlement and Destruction of Delivery Systems and Infrastructure for Nuclear Weapons; (10) Storage, Safeguarding and Disposition of Fissile Materials; (11) Technologies for Conversion and Civil Use of Demilitarized Materials; (12) International Organizations; and (13) Environmental Challenges Posed by Chemical and Nuclear Disarmament

  1. A Study on Dismantling and Verifying North Korea's Nuclear Capabilities

    International Nuclear Information System (INIS)

    Kim, Young Jae; Cheon, Seong Whun

    2007-10-01

    North Korea's nuclear weapon development is a serious threat to South Korea's national security and can become a trigger to change the status quo in the Korean peninsula. Having prevailed security dynamics in Northeast Asia last 20 years, the North Korea's nuclear problem faced a key turning point when Pyongyang tested its first nuclear weapon on October 9, 2006. Despite this test, however, diplomatic efforts to resolve the nuclear issue were never given up, resulting in a so-called, initial agreement signed at the Six-Party Talks in February 2007. With the Six-Party Talks being held more than four years, the six countries have had sufficient time to discuss principal and political matters regarding the dismantlement of North Korea's nuclear weapons. Under the circumstances, this report is going to study practical and detail issues related with dismantling the North's nuclear weapons. Specifically, in light of historical experiences, the report will investigate possible problems to be faced in the course of dismantlement and propose policy measures to overcome these problems

  2. Understanding to requirements for educational level in qualification of reactor operators

    International Nuclear Information System (INIS)

    Zhang Chi; Yang Di; Zhou Limin

    2007-01-01

    Requirements for qualification of reactor operators in nuclear safety regulations were discussed in this paper. The new issue was described in the confirmation of education level of reactor operators. The understanding to the requirements for Educational Level in Qualification of Reactor Operators was provided according to Higher Education Law of the People's Republic of China. It was proposed to improve the confirmation of qualification of reactor operators as soon as possible. (authors)

  3. Development of decommissioning engineering support system for fugen. Development of support system during actual dismantlement works

    International Nuclear Information System (INIS)

    Masanori Izumi; Yukihiro Iguchi; Yoshiki Kannehira

    2005-01-01

    The Advanced Thermal Reactor, Fugen Nuclear Power Station was permanently shut down in March 2003, and is now preparing for decommissioning. We have been developing Decommissioning Engineering Support System (DEXUS) aimed at planning optimal dismantlement process and carrying out dismantlement work safely and precisely. DEXUS consists of 'decommissioning planning support system' and 'dismantling support system'. The dismantling support system is developed aiming at using during actual dismantling work. It consists of three subsystems such as 'Worksite Visualization System', 'Dismantling Data Collection System' and 'Generated Waste Management System'. 'Worksite Visualization System' is a support system designed to provide the necessary information to workers during actual dismantlement works. And this system adopts AR (Augmented Reality) technology, overlapping calculation information into real world. 'Dismantling Data Collection System' is to collect necessary data for improving accuracy of decommissioning planning by evaluating work content and worker equipage, work time for dismantlement works. 'Generated Waste Management system' is a system recording necessary information by attaching the barcode to dismantled wastes or the containers. We can get the information of generated waste by recording generation place, generated time, treatment method and the contents. These subsystems enable to carry out reasonable and safe decommissioning of Fugen. In addition, we expect that those systems will be used for decommissioning of other nuclear facilities in the future. (authors)

  4. Laser cutting equipment for dismantling irradiated PFR fuel sub-assemblies

    International Nuclear Information System (INIS)

    Higginson, P.R.; Campbell, D.A.

    1981-01-01

    Laser cutting was identified as a possible technique for dismantling irradiated Prototype Fast Reactor (P.F.R.) fuel sub-assemblies and initial trials showed that it could be used to make essentially swarf free cuts in P.F.R. wrapper material provided sufficient laser power was available to allow use of an inert cutting gas. A programme of development work has established a technique for inert gas cutting with the reliable, commercially available Ferranti MF 400 laser and equipment for laser cutting of sub-assemblies has been installed in the Irradiated Fuel Cave at P.F.R. Test cuts carried out with this equipment on un-irradiated wrapper sections have shown it to be easy to operate remotely, optically stable and reliable in operation. (author)

  5. Melting of contaminated steel scrap from the dismantling of the CO2 systems of gas cooled, graphite moderated nuclear reactors

    International Nuclear Information System (INIS)

    Feaugas, J.; Jeanjacques, M.; Peulve, J.

    1994-01-01

    G2 and G3 are the natural Uranium cooled reactors Graphite/Gas. The two reactors were designed for both plutonium and electricity production (45 MWe). The dismantling of the reactors at stage 2 has produced more than 4 000 tonnes of contaminated scrap. Because of their large mass and low residual contamination level, the French Atomic Energy Commission (CEA) considered various possibilities for the processing of these metallic products in order to reduce the volume of waste going to be stored. After different studies and tests of several processes and the evaluation of their results, the choice to melt the dismantled pipeworks was taken. It was decided to build the Nuclear Steel Melting Facility known as INFANTE, in cooperation with a steelmaker (AHL). The realization time schedule for the INFANTE lasted 20 months. It included studies, construction and the licensing procedure. (authors). 2 tabs., 3 figs

  6. The advantages and disadvantages of centralized control of air power at operational level

    Science.gov (United States)

    Arisoy, Uǧur

    2014-05-01

    People do not want to see and hear a war. In today's world, if war is inevitable, the use of air power is seen as the preferable means of conducting operations instead of financially burdensome land battles which are more likely to cause heavy loss of life. The use of Air Power has gained importance in NATO operations in the Post-Cold War era. For example, air power has undertaken a decisive role from the beginning to the end of the operation in Libya. From this point of view, the most important issue to consider is how to direct air power more effectively at operational level. NATO's Core JFAC (Joint Force Air Command) was established in 2012 to control joint air power at operational level from a single center. US had experienced JFAC aproach in the Operation Desert Storm in 1991. UK, France, Germany, Italy and Spain are also directing their air power from their JFAC structures. Joint air power can be directed from a single center at operational level by means of JFAC. JFAC aproach provides complex planning progress of Air Power to be controled faster in a single center. An Air Power with a large number of aircrafts, long range missiles of cutting-edge technology may have difficulties in achieving results unless directed effectively. In this article, directing air power more effectively at operational level has been studied in the framework of directing air power from a single center carried out by SWOT analysis technique. "Directing Air Power at operational level from a single center similar to JFAC-like structure" is compared with "Directing Air Power at operational level from two centers similar to AC (Air Command) + CAOC (Combined Air Operations Center) structure" As a result of this study, it is assessed that directing air power at operational level from a single center would bring effectiveness to the air campaign. The study examines directing air power at operational level. Developments at political, strategic and tactical levels have been ignored.

  7. Setting UP a decontamination and dismantling (D and D) scenario - methodology and tools developed leopard

    International Nuclear Information System (INIS)

    Pradoura, F.

    2009-01-01

    At the AREVA NC La Hague site, the former nuclear spent fuel reprocessing plant UP2-400 was shutdown on December 30, 2003. Since then, the cleaning up and dismantling activities have been carried by the DV/PRO project, which is the program management organization settled by AREVA NC, for valorization projects. SGN, part of the AREVA NC Engineering Business Unit, operates as the main contractor of the DV/PRO project and provides project management services related to decommissioning and waste management. Hence, SGN is in charge of building D and D's scenarios for all the facilities of the UP2-400 plant, in compliance with safety, technical and financial requirements. Main outputs are logic diagrams, block flow diagrams, wastes and effluents throughputs. In order to meet with AREVA NC's requirements and expectations, SGN developed specific process and tools methods adapted to the scale and complexity of decommissioning a plant with several facilities, with different kind of processes (chemical, mechanical), some of which are in operation and other being dismantled. Considering the number of technical data and inputs to be managed, this methodology leads to complex outputs such as schedules, throughputs, work packages... The development, the maintenance and the modification of these outputs become more and more difficult with the complexity and the size of the plant considered. To cope with these issues, SGN CDE/DEM UP2-400 project team has developed a dedicated tool to assist and optimize in elaborating D and D scenarios. This tool is named LEOPARD (Logiciel d'Elaboration et d'Optimisation des Programmes d'Assainissement Radiologique et de Demantelement) (Software for the Development and Optimization of Radiological Clean up and Dismantling Programs). The availability of this tool allowed the rapid construction of a test case (demonstrator) that has convinced DV/PRO of its numerous advantages and of the future further development potentials. Presentations of LEOPARD

  8. Status of the Digital Mock-up System for the dismantling of the nuclear facilities

    International Nuclear Information System (INIS)

    Park, Hee Seoung; Kim, S. K.; Lee, K. W.; Oh, W. J.

    2004-12-01

    The database system have already developed is impossible to solve a quantitative evaluation about a various situation from the dismantle activities of the reactor had contaminated with radioactivity. To satisfy the requirements for safety and economical efficiency among a major decommissioning technologies, it need a system that can evaluate and estimate dismantling scheduling, amount of radioactive waste being dismantled, and decommissioning cost. We have review and analyzed status of the digital mock-up system to get a technical guide because we have no experience establishment of one relation to dismantling of research reactor and nuclear power plant

  9. Development of project management data calculation models relating to dismantling of nuclear facilities. Contract research

    Energy Technology Data Exchange (ETDEWEB)

    Sukegawa, Takenori; Ohshima, Soichiro; Shiraishi, Kunio; Yanagihara, Satoshi [Department of Decommissioning and Waste Management, Tokai Research Establishment, Japan Atomic Energy Research Institute, Tokai Ibaraki (Japan)

    1999-02-01

    Labor-hours necessary for dismantling activities are generally estimated based on experience, for example, as a form of unit productivity factors such as the relationship between labor-hours and weight of components dismantled which were obtained by actual dismantling activities. The project management data calculation models together with unit productivity factors for basic dismantling work activities were developed by analyzing the data obtained from the Japan Power Demonstration Reactor (JPDR) dismantling project, which will be applicable to estimation of labor-hours in various dismantling conditions. Typical work breakdown structures were also prepared by categorizing repeatable basic dismantling work activities for effective planning of dismantling activities. The labor-hours for dismantling the JPDR components and structures were calculated by using the code system for management of reactor decommissioning (COSMARD), in which the work breakdown structures and the calculation models were contained. It was confirmed that the labor-hours could be easily estimated by COSMARD through the calculations. This report describes the labor-hour calculation models and application of these models to COSMARD. (author)

  10. Reserves for shutdown/dismantling and disposal in nuclear technology. Theses and recommendations on reform options

    International Nuclear Information System (INIS)

    Meyer, Bettina

    2012-01-01

    The study on reserves for shutdown, dismantling and disposal of nuclear facilities covers the following topics: cost for shutdown, dismantling and disposal and amount and transparency of nuclear reserves, solution by y stock regulated by public law for long-term liabilities, and improvement of the protection in the event of insolvency for the remaining EVU reserves for short- and intermediate-term liabilities. The appendix includes estimations and empirical values for the cost of shutdown and dismantling, estimation of disposal costs, and a summary of Swiss studies on dismantling and disposal and transfer to Germany.

  11. Significance of post-operative changes of serum IL-18 levels in patients with renal transplantation

    International Nuclear Information System (INIS)

    Qi Falian; Xu Jun; Ke Bingshen; Du Xiumin; Yin Qiuxia; Hu Chengjin

    2005-01-01

    Objective: To study the clinical significance of post-operative changes of serum IL-18 levels in patients after renal transplantation. Methods: Serum IL-18 levels were detected with ELISA in 33 patients with renal transplantation before operation and repeated again on d5, d10 and d20 post-operatively as well as in 35 controls. Results: Pre-operatively, serum IL-18 levels in patients for upcoming renal transplantation were significantly higher than those in controls (P<0.01). After operation, the IL-18 levels on d5 and d10 in patients with acute rejection were not significantly changed from those pre-operatively but were markedly increased on d20 (vs pre-operative, d5, d10; all P<0.01). In the patients without rejection, levels in d5 were significantly higher than those pre-operatively, but dropped to approaching pre-operative values on d10 and d20. On d20, levels of serum IL-18 in patients with rejection were very significantly higher than those in stable patients (P<0.01). Conclusion: Serum IL-18 is a useful marker for identifying acute rejection. (authors)

  12. Decontamination and dismantlement of the JANUS Reactor at Argonne National Laboratory-East. Project final report

    International Nuclear Information System (INIS)

    Fellhauer, C.R.; Clark, F.R.

    1997-10-01

    The decontamination and dismantlement of the JANUS Reactor at Argonne National Laboratory-East (ANL-E) was completed in October 1997. Descriptions and evaluations of the activities performed and analyses of the results obtained during the JANUS D and D Project are provided in this Final Report. The following information is included: objective of the JANUS D and D Project; history of the JANUS Reactor facility; description of the ANL-E site and the JANUS Reactor facility; overview of the D and D activities performed; description of the project planning and engineering; description of the D and D operations; summary of the final status of the JANUS Reactor facility based upon the final survey results; description of the health and safety aspects of the project, including personnel exposure and OSHA reporting; summary of the waste minimization techniques utilized and total waste generated by the project; and summary of the final cost and schedule for the JANUS D and D Project

  13. Issues on a tritium measurement system's qualification on a dismantling site

    Energy Technology Data Exchange (ETDEWEB)

    Pigeon, Benoit; Met, Frederic [Waste Treatment and Nuclear Safety Service - SASN, Waste and Measurement Laboratory - LDM, CEA/SASN/LDM, DAM, DIF, Bruyeres Le Chatel, F-91297 Arpajon (France)

    2015-07-01

    In order to choose the suitable outlet, final disposal of radioactive package requires good knowledge of radiological characteristics of the waste. As part of a nuclear facility's dismantling within tritium proceeds, {sup 3}H contamination is evaluated by using wipe tests which are measured by liquid scintillation. The industrialist's choice is a triple coincidence to double coincidence ratio (TDCR) method with a dry counting protocol. The initial protocol had been defined to reduce the quantity of radioactive liquid waste and to perform an automatic quenching correction. A based on TDCR method liquid scintillation analyser was installed on the decommissioning site. It had had to be used by operator non specialized in metrology, This poster presents the laboratory's feedback on the use of the TDCR method on a site: - problems encountered about protocol on a decommissioning site - protocol adjustments and their consequences. (authors)

  14. Evaluation of the secondary radiation impact on personnel during the dismantling of contaminated nuclear equipment

    Directory of Open Access Journals (Sweden)

    Stankunas Gediminas

    2013-01-01

    Full Text Available The article contains a numerical analysis of the secondary radiation contribution to the total radiation affecting the operational personnel during the dismantling activities of the contaminated equipment at a nuclear power plant. This study considers a widely applicable Monte Carlo particle transport code MCNPX and real Ignalina nuclear power plant records. A simplified albedo method is investigated in order to analyze the selected geometrical design cases. Additionally, the impact of the secondary radiation on the personnel dose was analyzed. The numerical MCNPX simulation allowed ascertaining the optimal distance between the source and the wall for the working personnel in closed rooms with contaminated equipment. The developed dose rate maps of the secondary radiation showed cross-sectional distribution of the dose rate inside the enclosed area.

  15. Optimization study and preliminary design for Latina NPP early core retrieval and reactor dismantling

    International Nuclear Information System (INIS)

    Macci, E.; Zirpolo, S.; Imparato, A.; Cacace, A.; Parry, D.; Walkden, P.

    2002-01-01

    In June 2000, an agreement was established between Sogin and BNFL to enable the two companies to co-operate, using their specific experiences in the decommissioning field, for the benefit of projects in Italy, the United Kingdom and for third markets. A decommissioning strategy for the Latina NPP was initially developed in a Phase 1 Study which produced a conceptual design for the decommissioning of the reactor. This study was completed in June 2000. Since then, a second study has been completed, which has further developed the strategy and produced preliminary designs for the early dismantling of the core and reactor building at Latina. The engineering and safety data were produced in order to support Sogin in the preparation of a safety case for plant decommissioning. This safety case was submitted to the Italian Regulator, ANPA, in February 2002. (author)

  16. The molten salt reactor option for beneficial use of fissile material from dismantled weapons

    International Nuclear Information System (INIS)

    Gat, U.; Engel, J.R.

    1991-01-01

    The Molten Salt Reactor (MSR) option for burning fissile fuel from dismantled weapons is examined and is found very suitable for the beneficial use of this fuel. MSRs can utilize any fissile fuel in continuous operation with no special modifications, as demonstrated in the Molten Salt Reactor Experiment. Thus, MSRs are flexible while maintaining their economy. Furthermore, MSRs require only a minimum of special fuel preparation. They can tolerate denaturing and dilution of their fuel. The size of fuel shipments can be determined to optimize safety and security-all of which supports nonproliferation and resists diversion. In addition, MSRs have inherent safety features that make them acceptable and attractive. They can burn fissile material completely or can convert it to other fuels. MSRs also have the potential for burning the actinides and delivering the waste in an optimal form, thus contributing to the solution of one of the major remaining problems in the deployment of nuclear power

  17. Recycling of concrete generated from Nuclear Power Plant dismantling

    International Nuclear Information System (INIS)

    Ogawa, Hideo; Nawa, Toyoharu; Ishikura, Takeshi; Tanaka, Hiroaki

    2013-01-01

    Reactor decommissioning required various technologies such as dismantling of facilities, decontamination, radioactivity measurement and recycling of dismantling wastes. This article discussed recycling of demolished concrete wastes. Dismantling of reactor building of large one unit of nuclear power plants would generate about 500 K tons of concrete wastes, about 98% of which was non-radioactive and could be used as base course material or backfill material after crushed to specified particle size. Since later part of 1990s, high quality recycled aggregate with specified limit of bone-dry density, water absorptivity and amount of fine aggregate had been developed from demolished concrete with 'Heat and rubbing method', 'Eccentric rotor method' and 'Screw grinding method' so as to separate cements attached to aggregate. Recycled aggregates were made from concrete debris with 'Jaw crusher' to particle size less than 40 mm and then particle size control or grinded by various grinding machines. Recycled fine aggregates made from crushing would have fragile site with cracks, air voids and bubbles. The author proposed quality improvement method to selectively separate fragile defects from recycled aggregates using weak grinding force, leaving attached pastes much and preventing fine particle generation as byproducts. This article outlined experiments to improve quality of recycled fine aggregates and their experimental results confirmed improvement of flow ability and compressive strength of mortal using recycled fine aggregates using 'Particle size selector' and 'Ball mill' so as to remove their fragile parts less than 2%. Mortal made from recycled fine aggregate could also prevent permeation of chloride ion. Recycled aggregate could be used for concrete instead of natural aggregate. (T. Tanaka)

  18. Stade. Decommissioning and dismantling of the nuclear power plant - from the nuclear power plant to the green lawn. 3. ed.

    International Nuclear Information System (INIS)

    2008-01-01

    The nuclear power plant Stade (KKS) was shutdown in 2003 and is being dismantled since 2005. The contribution covers the following issues: What means decommissioning and dismantling? What was the reason for decommissioning? What experiences on the dismantling of nuclear power plants are available? What is the dismantling procedure? What challenges for the power plant personal result from dismantling? What happens with the deconstruction material? What happens with the resulting free area (the ''green lawn'')? What is the legal frame work for dismantling?

  19. Organizing to Understand: How to Operate Effectively in the Human Domain

    Science.gov (United States)

    2015-05-21

    was both entering and creating when it overthrew Saddam Hussein and dismantled the Iraqi government and security forces. The research examines the...sponsored initiative to help tactical and operational level commanders understand the human terrain, the “social, ethnographic , cultural, economic, and...as an intelligence function within TRADOC “as the primary and enduring social science-based human domain research , analysis, and training capability

  20. Foam decontamination of large nuclear components before dismantling

    International Nuclear Information System (INIS)

    Costes, J.R.; Sahut, C.

    1998-01-01

    Following some simple theoretical considerations, the authors show that foam compositions can be advantageously circulated them for a few hours in components requiring decontamination before dismantling. The technique is illustrated on six large ferritic steel valves, then on austenitic steel heat exchangers for which the Ce(III)/Ce(IV) redox pair was used to dissolve the chromium; Ce(III) was reoxidized by ozone injection into the foam vector gas. Biodegradable surfactants are sued in the process; tests have shown that the foaming power disappears after a few days, provided the final radioactive liquid waste is adjusted to neutral pH, allowing subsequent coprecipitation of concentration treatment. (author)

  1. Implementing robotics in the Department of Energy Dismantlement Program

    International Nuclear Information System (INIS)

    Jones, A.T.

    1997-01-01

    Since the end of the cold war, as our nuclear stockpile has decreased, the Department of Energy (DOE) has been working rapidly to safely dismantle weapons returned by the military. In order to be retired, weapons must be returned to the Pantex Plant in Amarillo, Texas. There they are reduced to their component parts. Although many of these parts are not hazardous, some, including certain explosive assemblies and radioactive materials, are sufficiently hazardous so that special handling systems are necessary. This paper will describe several of these systems developed by Sandia for Pantex and their technical basis

  2. Cost effective decommissioning and dismantling of nuclear power plants

    International Nuclear Information System (INIS)

    Wasinger, Karl

    2012-01-01

    As for any large and complex project, the basis for cost effective decommissioning and dismantling of nuclear power plants is established with the development of the project. Just as its construction, dismantling of a nuclear power plant is similarly demanding. Daily changing situations due to the progress of construction - in the present case progress of dismantling - result in significant logistical challenges for project managers and site supervisors. This will be aggravated by the fact that a considerable amount of the removed parts are contaminated or even activated. Hence, not only occupational health, safety and environmental protection is to be assured, employees, public and environment are to be adequately protected against the adverse effect of radioactive radiation as well. Work progress and not least expenses involved with the undertaking depend on adherence to the planned course of actions. Probably the most frequent cause of deviation from originally planned durations and costs of a project are disruptions in the flow of work. For being enabled to counteract in a timely and efficient manner, all required activities are to be comprehensively captured with the initial planning. The effect initial activities may have on subsequent works until completion must particularly be investigated. This is the more important the larger and more complex the project actually are. Comprehensive knowledge of all the matters which may affect the progress of the works is required in order to set up a suitable work break-down structure; such work break-down structure being indispensable for successful control and monitoring of the project. In building the related organizational structure of the project, all such stakeholders not being direct part of the project team but which may potentially affect the progress of the project are to be considered as well. Cost effective and lost time injury free dismantling of decommissioned nuclear power plants is based on implementing

  3. Latest expertise investigations in nuclear dismantling and industrial applications

    International Nuclear Information System (INIS)

    Gallozzi Ulmann, Adrien; Chazalet, Julien; Couturier, Pierre; Touzain, Etienne; Amgarou, Khalil; Menaa, Nabil

    2013-06-01

    During the last decades, CANBERRA has developed know-how, expertise and intervention strategies based on its feedback experiences in many countries. This document covers a wide range of applications involving nuclear characterization, for which CANBERRA is able to provide measurement set-up and results, activity characterization and radioactive source localization, as well as to guarantee safety or process thresholds corresponding to the customer's needs. To improve processes best-in-class methodology, know-how and tools have been used in complex examples described in this paper. CANBERRA has demonstrated its ability to better and efficiently prepare for and execute decontamination and dismantling activities. (authors)

  4. Fabrication of mixed oxide fuel using plutonium from dismantled weapons

    International Nuclear Information System (INIS)

    Blair, H.T.; Chidester, K.; Ramsey, K.B.

    1996-01-01

    A very brief summary is presented of experimental studies performed to support the use of plutonium from dismantled weapons in fabricating mixed oxide (MOX) fuel for commercial power reactors. Thermal treatment tests were performed on plutonium dioxide powder to determine if an effective dry gallium removal process could be devised. Fabrication tests were performed to determine the effects of various processing parameters on pellet quality. Thermal tests results showed that the final gallium content is highly dependent on the treatment temperature. Fabrication tests showed that the milling process, sintering parameters, and uranium feed did effect pellet properties. 1 ref., 1 tab

  5. Assessment of Mismatch at Indicated Level of the Upper Side Zone of LZC on abnormal operations

    International Nuclear Information System (INIS)

    Kim, Sung-Min; Park, Joong-Woo; Kho, Dae-Hack; Seo, Hyung-Beom; Han, Bong-Gyun; Moon, Jin-Soo

    2006-01-01

    Liquid Zone Control System of CANDU reactor provides bulk and spatial control. This system has produced abnormal operations with water level increase due to refueling since 1998. The abnormal operations of LZC system at Wolsong 2 can be divided into two periods. One is the sudden drop with continuous operation mode of LZC compressor and the other one is cycling with the on-off operation mode of the LZC compressor. It is identified through the communication with other CANDU reactors that this phenomenon is not unique to Wolsong. Whenever the upper side zone (1,8,6,13) level exceeded 80%, these abnormal operations occurred and mismatch between indicated and actual zone level was found. Counter-plan is prepared to ease these abnormal operations by physicist own efforts at Wolsong 2

  6. A Proof of Factorization Theorem of Drell–Yan Process at Operator Level

    International Nuclear Information System (INIS)

    Zhou Gao-Liang

    2016-01-01

    An alternative proof of factorization theorem for Drell–Yan process that works at operator level is presented in this paper. Contributions of interactions after the hard collision for such inclusive processes are proved to be canceled at operator level according to the unitarity of time evolution operator. After this cancellation, there are no longer leading pinch singular surface in Glauber region in the time evolution of electromagnetic currents. Effects of soft gluons are absorbed into Wilson lines of scalar-polarized gluons. Cancelation of soft gluons is attribute to unitarity of time evolution operator and such Wilson lines. (paper)

  7. 36 CFR 3.15 - What is the maximum noise level for the operation of a vessel?

    Science.gov (United States)

    2010-07-01

    ... level for the operation of a vessel? 3.15 Section 3.15 Parks, Forests, and Public Property NATIONAL PARK... level for the operation of a vessel? (a) A person may not operate a vessel at a noise level exceeding... vessel is being operated in excess of the noise levels established in paragraph (a) of this section may...

  8. The UK's National Programme for IT: Why was it dismantled?

    Science.gov (United States)

    Justinia, Taghreed

    2017-02-01

    This paper discusses the UK's National Programme for IT (NPfIT), which was an ambitious programme launched in 2002 with an initial budget of some £6.2 billion. It attempted to implement a top-down digitization of healthcare in England's National Health Service (NHS). The core aim of the NPfIT was to bring the NHS' use of information technology into the 21st century, through the introduction of an integrated electronic patient record systems, and reforming the way that the NHS uses information, and hence to improve services and the quality of patient care. The initiative was not trusted by doctors and appeared to have no impact on patient safety. The project was marred by resistance due to the inappropriateness of a centralized authority making top-down decisions on behalf of local organizations. The NPfIT was officially dismantled in September 2011. Deemed the world's largest civil IT programme, its failure and ultimate demise sparked a lot of interest as to the reasons why. This paper summarises the underlying causes that lead to dismantling the NPfIT. At the forefront of those circumstances were the lack of adequate end user engagement, the absence of a phased change management approach, and underestimating the scale of the project.

  9. An investigation into soft error detection efficiency at operating system level.

    Science.gov (United States)

    Asghari, Seyyed Amir; Kaynak, Okyay; Taheri, Hassan

    2014-01-01

    Electronic equipment operating in harsh environments such as space is subjected to a range of threats. The most important of these is radiation that gives rise to permanent and transient errors on microelectronic components. The occurrence rate of transient errors is significantly more than permanent errors. The transient errors, or soft errors, emerge in two formats: control flow errors (CFEs) and data errors. Valuable research results have already appeared in literature at hardware and software levels for their alleviation. However, there is the basic assumption behind these works that the operating system is reliable and the focus is on other system levels. In this paper, we investigate the effects of soft errors on the operating system components and compare their vulnerability with that of application level components. Results show that soft errors in operating system components affect both operating system and application level components. Therefore, by providing endurance to operating system level components against soft errors, both operating system and application level components gain tolerance.

  10. An Investigation into Soft Error Detection Efficiency at Operating System Level

    Directory of Open Access Journals (Sweden)

    Seyyed Amir Asghari

    2014-01-01

    Full Text Available Electronic equipment operating in harsh environments such as space is subjected to a range of threats. The most important of these is radiation that gives rise to permanent and transient errors on microelectronic components. The occurrence rate of transient errors is significantly more than permanent errors. The transient errors, or soft errors, emerge in two formats: control flow errors (CFEs and data errors. Valuable research results have already appeared in literature at hardware and software levels for their alleviation. However, there is the basic assumption behind these works that the operating system is reliable and the focus is on other system levels. In this paper, we investigate the effects of soft errors on the operating system components and compare their vulnerability with that of application level components. Results show that soft errors in operating system components affect both operating system and application level components. Therefore, by providing endurance to operating system level components against soft errors, both operating system and application level components gain tolerance.

  11. Remote techniques for the underwater dismantling of reactor internals at the nuclear power plant Gundremmingen unit A

    International Nuclear Information System (INIS)

    Eickelpasch, N.; Steiner, H.; Priesmeyer, U.

    1997-01-01

    Unit A of the nuclear power plant in Gundremmingen (KRB A) is a boiling water reactor with an electrical power of 250 MWe. It was shut down in 1977 after eleven years of operation. The actual decommissioning started in 1983. Since then more than 5200 tons of contaminated components have been dismantled. Special cutting and handling tools were tested, developed and optimized for the purpose of working in radiation fields and under water. Due to the special design of KRB A, which uses a dual-cycle system for additional steam generation, the experience gained is transferable to pressurized water reactors. (Author)

  12. Remote control for the underwater dismantling of reactor internals at the nuclear power plant Gundremmingen unit A

    International Nuclear Information System (INIS)

    Eickelpasch, N.; Steiner, H.; Priesmeyer, U.

    1996-01-01

    The unit A of the nuclear power plant in Gundremmingen (KRB A) is a boiling water reactor with an electrical power of 250 MW e . It was shut down in 1977 after 11 years of operation. The actual decommissioning started in 1983. Meanwhile more than 5200 tons of contaminated components have been dismantled. Special cutting and handling tools were tested, developed and optimized for the purpose of working in radiation fields and under water. Due to the special design of KRB A, using an dual cycle system for additional steam generation, the experience gained is transferable to pressurised water reactors as well. (Author)

  13. Identification and evaluation of factors influencing the timing of dismantling projects; Identifizierung und Bewertung von Einflussfaktoren zur Terminsteuerung bei Rueckbauprojekten

    Energy Technology Data Exchange (ETDEWEB)

    Emami-Far, Hedjeh [Karlsruher Institut fuer Technologie (KIT), Karlsruhe (Germany). Abt. Technologie und Management des Rueckbaus Kerntechnischer Anlagen (TMRK)

    2013-07-01

    The problem of reactor dismantling projects is the amount of overshooting with respect to the planned project time. The question on the origin of this fact is raised together with the possibility of an early problem identification and possible counter measures to fulfill the timing plan. The main issues for the interrogation of personnel, specialists and operators were organization, competence preservation and technology concerning conditioning, storage/disposal and licensing procedures. The contribution includes details on the questions and the evaluation of answers including recommendations for the future approach.

  14. Dismantling of the research reactor RTS-1 Galileo Galilei in Pisa (Italy)

    International Nuclear Information System (INIS)

    Ruiz Martinez, J. t.; Farella, G.; Cimini, E.; Russo, M.

    2014-01-01

    This paper is about the most relevant aspects of the first phase of the dismantling, removal of the water in the pool, prior treatment through evaporation, the dismantling of all the submerged activated elements and other activated or contaminated elements that have been part of the nuclear facility. (Author)

  15. Know History, Know Self: Art Therapists' Responsibility to Dismantle White Supremacy

    Science.gov (United States)

    Hamrick, Cassie; Byma, Christine

    2017-01-01

    In this article, we call on white art therapists to assume responsibility for dismantling white supremacy in the field of art therapy, in personal as well as political-structural arenas. We respond to calls from scholars and writers of color for white people to assume increased responsibility for dismantling white supremacy in white communities…

  16. A treaty more alarming than efficient. The dismantled warheads will not be destroyed. Danger

    International Nuclear Information System (INIS)

    Riche, P.; Despic-Popovic, H.; Nougayrede, N.

    2002-01-01

    This political analysis presents the new treaty of nuclear weapons dismantling between Russia and Usa. In fact the warheads will not be completely dismantling but only stocked, leading to a possible recovery by terrorists. It underlines the real interests of this agreement which are more economic than peaceful. (A.L.B.)

  17. Decontamination and dismantling at the CEA; L'assainissement et le demantelement au CEA

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2006-07-01

    This document presents the dismantling policy at the CEA (French Research Center on the atomic energy), the financing of the decontamination and the dismantling, the regulatory framework, the knowledge and the technology developed at the CEA, the radiation protection, the environment monitoring and the installations. (A.L.B.)

  18. Process for the dismantling of buried equipment, with a contamination risk and eventually irradiating, and intervention enclosure for this process

    International Nuclear Information System (INIS)

    Bodin, F.; Saublet, J.C.

    1991-01-01

    Dismantling of buried equipment, for instance abandoned effluent pipes,is made by unitary sections under mobile enclosure with a self-supporting structure and a floor provided with a long central aperture giving access to the section to dismantle

  19. Cost-benefit analyses for decommissioning and dismantling of nuclear power stations

    International Nuclear Information System (INIS)

    Hock, R.

    1988-01-01

    According to ICRP provisions, radiation doses to the population are to be kept as low as possible, on the basis of a justifiable relationship between additional expense for dose reduction and the radiological benefit. The paper examines whether this optimisation principle requires maximum conceivable limits of personal doses as a result of materials recovery from dismantling ought to be reviewed, and whether clearance levels for materials to be recycled have to be reduced. The cost-benefit assessments presented for various options take into account the cost involved for processing and recycling methods as well as the social burden of dose commitments. A comparison in terms of radiological safety is presented for ultimate disposal of material, or meltdown of material subject to appropriate radiological measurement and surveillance. (DG) [de

  20. Low-level wastewater treatment facility process control operational test report

    International Nuclear Information System (INIS)

    Bergquist, G.G.

    1996-01-01

    This test report documents the results obtained while conducting operational testing of a new TK 102 level controller and total outflow integrator added to the NHCON software that controls the Low-Level Wastewater Treatment Facility (LLWTF). The test was performed with WHC-SD-CP-OTP 154, PFP Low-Level Wastewater Treatment Facility Process Control Operational Test. A complete test copy is included in appendix A. The new TK 102 level controller provides a signal, hereafter referred to its cascade mode, to the treatment train flow controller which enables the water treatment process to run for long periods without continuous operator monitoring. The test successfully demonstrated the functionality of the new controller under standard and abnormal conditions expected from the LLWTF operation. In addition, a flow totalizer is now displayed on the LLWTF outlet MICON screen which tallies the process output in gallons. This feature substantially improves the ability to retrieve daily process volumes for maintaining accurate material balances

  1. Is Systemic Operation Design Capable of Reducing Significantly Bias in Operational Level Planning Caused by Military Organizational Culture?

    Science.gov (United States)

    2006-05-25

    drape shallow ‘rival’ ideas across them. At best this constitutes a waste of time and at worse a new source of poor judgments. Nor is such...quoted in 1 (UK) Armoured Division Draft Future Divisional Headquarters Structure Review ref G3/3800 dated 19 Jul 05. APPENDIX II – Structuring...and divisional level (HQ 1 UK Armoured Division) through to the operational and strategic interface (Project ROBERTS 2).64 Functions in a Deployed

  2. Study on applicability of evaluation model of manpower needs for dismantling of equipments in FUGEN-1. Dismantling process in 3rd/4th feedwater heater room

    International Nuclear Information System (INIS)

    Shibahara, Yuji; Izumi, Masanori; Nanko, Takashi; Tachibana, Mitsuo; Ishigami, Tsutomu

    2010-10-01

    Manpower needs for the dismantling process on the dismantling of equipments in FUGEN 3rd/4th feedwater heater room was calculated with the management data evaluation system (PRODIA Code), and it was inspected whether the conventional evaluation model had applicability for FUGEN or not. It was confirmed that the conventional evaluation model for feedwater heater had no applicability. In comparison of the calculated value with the actual data, we found two difference: 1) the calculated value were significantly larger than the actual data, 2) the actual data for the dismantling of 3rd feedwater heater was twice larger than that of 4th feedwater heater, though these equipments were almost same weight. It was found that these were brought 1) by the difference in the work descriptions of dismantling between JPDR and FUGEN, and 2) by that in the cutting number between 3rd feedwater heater and 4th one. The manpower needs for the dismantling of both feedwater heaters were calculated with a new calculation equation reflecting the descriptions of dismantling, and it was found that these results showed the good agreement with the actual data. (author)

  3. Transparency in nuclear warhead dismantlement -- Limited chain of custody and warhead signatures

    International Nuclear Information System (INIS)

    Kiernan, G.; Percival, M.; Bratcher, L.

    1996-01-01

    The goal of the US Safeguards, Transparency, and Irreversibility (STI) initiative is the development of a series of transparency measures that provide confidence that nuclear warheads are actually being dismantled and that the fissile material being removed from these dismantled weapons is not recycled into new production. A limited chain of custody (LCC) would follow a warhead from the time it is declared excess until it is actually dismantled and the fissile materials are stored. Measurement of warhead signatures is an option in LCC using radiation detection techniques to confirm that a warhead has been dismantled, without intrusive inspections within the dismantlement facility. This paper discusses LCC and warhead signatures as well as indicate first results of laboratory measurements related to warhead signatures

  4. Evaluation methodology of a manipulator actuator for the dismantling process during nuclear decommissioning

    International Nuclear Information System (INIS)

    Park, Jongwon; Kim, Chang-Hoi; Jeong, Kyung-min; Choi, Byung-Seon; Moon, Jeikwon

    2016-01-01

    Highlights: • A methodology to evaluate actuators of a dismantling manipulator. • Evaluation criteria for choosing the most suitable actuator type. • A mathematical evaluation model for evaluation. • The evaluation method is expected to be used for determining other manipulators. - Abstract: This paper presents a methodology to evaluate actuators of a manipulator for dismantling nuclear power plants. Actuators are the most dominant components because a dismantling manipulator relies heavily on the actuator type used. To select the most suitable actuator, evaluation criteria are presented in four categories based on the nuclear dismantling environment. A mathematical model is presented and evaluation results are calculated with weights and scores for each criterion. The proposed evaluation method is expected to be used for determining other aspects of the design of dismantling manipulators.

  5. Education and research when dismantling nuclear plants at the Technical University Dresden; Lehre und Forschung beim Rueckbau kerntechnischer Anlagen an der Technischen Universitaet Dresden

    Energy Technology Data Exchange (ETDEWEB)

    Hurtado, A.; Anthofer, A.; Cloppenborg, T.; Schreier, M. [Technische Univ. Dresden (Germany). Inst. fuer Energietechnik

    2013-08-15

    With the decision by the German government in 2011 to revoke the operating permission from 8 of the existing 17 German nuclear power plants, the responsibility of decommissioning and dismantling these plants has moved back into the focus of public awareness. Under the current legal conditions, the last nuclear plant will be disconnected from the grid on 31.12.2022 and this will create an enormous challenge for all the involved approving authorities, expert organisations, as well as companies involved in dismantling the plants. The development of new and efficient dismantling technologies and strategies is required to perform these highly responsible tasks. On the other hand, the nuclear competence and knowhow, as well as the promotion of young talents in the relevant scientific fields must be preserved. Technological and economic solutions are in demand for the various plants due to the different specifics of nuclear power plants. This will still require e.g. in the field of radiation protection highly qualified and well trained staff in future. The training of these skilled employees will require expanding the subject matter taught at universities, colleges and polytechnics to suit the changed parameters. The chair for hydrogen and nuclear energy technology at the TU Dresden will in future offer lectures as part of a new teaching discipline with the focus on dismantling and disposal. The course 'Dismantling nuclear power plants' took place for the first time in the summer semester 2013. It is organised as a three-day block seminar with an excursion to the company NIS Ingenieurgesellschaft mbH in Alzenau. The company NIS is a subsidiary of the Siempelkamp Nukleartechnik GmbH. This article intends to provide an overview of the contents of the courses and the impressions of the participants. In this way the TU Dresden is making a further contribution to preserving nuclear competence and inter-disciplinary dialogue. (orig.)

  6. Evaluation of noise pollution level in the operating rooms of hospitals: A study in Iran.

    Science.gov (United States)

    Giv, Masoumeh Dorri; Sani, Karim Ghazikhanlou; Alizadeh, Majid; Valinejadi, Ali; Majdabadi, Hesamedin Askari

    2017-06-01

    Noise pollution in the operating rooms is one of the remaining challenges. Both patients and physicians are exposed to different sound levels during the operative cases, many of which can last for hours. This study aims to evaluate the noise pollution in the operating rooms during different surgical procedures. In this cross-sectional study, sound level in the operating rooms of Hamadan University-affiliated hospitals (totally 10) in Iran during different surgical procedures was measured using B&K sound meter. The gathered data were compared with national and international standards. Statistical analysis was performed using descriptive statistics and one-way ANOVA, t -test, and Pearson's correlation test. Noise pollution level at majority of surgical procedures is higher than national and international documented standards. The highest level of noise pollution is related to orthopedic procedures, and the lowest one related to laparoscopic and heart surgery procedures. The highest and lowest registered sound level during the operation was 93 and 55 dB, respectively. Sound level generated by equipments (69 ± 4.1 dB), trolley movement (66 ± 2.3 dB), and personnel conversations (64 ± 3.9 dB) are the main sources of noise. The noise pollution of operating rooms are higher than available standards. The procedure needs to be corrected for achieving the proper conditions.

  7. Integration of remotely operated manipulator systems for the nuclear industry

    International Nuclear Information System (INIS)

    Blight, J.; Cornec, G.

    2003-01-01

    There is no getting away from remotely operated manipulator systems in significant part in dismantling operations, because of the actual radioactive emitting level of installations. However, some main contractors, who have been involved in dismantling projects in the past few years are reluctant to use remotely operated systems because: - equipment characteristics are not suitable for the environment and the work to be performed; - There are some design problems; - Main components do not withstand operation any longer, after some time; - There are deficiencies in the management of quality, for critical equipment problems that degrade the productivity and increase direct and indirect labour cost. As a summary therefore, equipment available on this dismantling market are reputedly unreliable and not 'industrial' (sturdy) enough. However, numerous operations in maintenance in primary loops of nuclear reactors, or in the Offshore sector, are carried out remotely, to the satisfaction of the operators and the investors. In the dismantling sector, a thorough analysis of the difficulties encountered indicates that their origin is mostly due to a lack of methodology - that needs to be addressed -, rather than a technical problem. In that context, CYBERNETIX proposes to be involved in phases upstream and downstream of the equipment supply's. Upstream: Participate in developing/validating the scenarios to be used to optimise the constraints of remote operations/equipment. Downstream: Participate actively in supporting the client on-site, ensuring that equipment are available and maintained by competent and motivated people, and thus, getting experience in order to improve the State-of-the-Art of robotic in that field. Then, the contracting authority and CYBERNETIX jointly define the limits and the content of the involvement of each party, and also define the most appropriate type of 'partnership' between the main contactor and the participating companies, and in order to

  8. 48 CFR 52.249-3 - Termination for Convenience of the Government (Dismantling, Demolition, or Removal of Improvements).

    Science.gov (United States)

    2010-10-01

    ... Convenience of the Government (Dismantling, Demolition, or Removal of Improvements). 52.249-3 Section 52.249-3... Convenience of the Government (Dismantling, Demolition, or Removal of Improvements). As prescribed in 49.502(b)(2), insert the following clause: Termination for Convenience of the Government (Dismantling...

  9. Cost Savings through Innovation in Decontamination, Decommissioning, and Dismantlement

    International Nuclear Information System (INIS)

    Yancey, Neal A.

    2003-01-01

    The United States Department of Energy (DOE) continually seeks safer and more cost effective technologies for the decontamination and decommissioning (D and D) of nuclear facilities. The Deactivation and Decommissioning Focus Area (DDFA) of the DOE's Office of Science and Technology (OST) sponsored large-scale demonstration and deployment projects (LSDDPs) to help bring new technologies into the D and D programs. The Idaho National Engineering and Environmental Laboratory (INEEL) LSDDP generated a list of needs defining specific problems where improved technologies could be incorporated into ongoing D and D tasks. The needs fell into 5 major categories--characterization, dismantlement, safety, material dispositioning, and decontamination. Technologies were carefully selected that provide a large benefit for a small investment. The technologies must provide significant improvements in cost, safety, radiation exposure, waste volume reduction, or schedule savings and widely applicable throughout the DOE complex. The LSDDP project provided training for the new technologies and worked with technology suppliers to resolve any questions that arose. Since 1998, 26 technologies have been demonstrated or deployed through the LSDDP for the D and D program at the INEEL. Of the 26 demonstrated and deployed technologies, 14 were in characterization, 3 were in decontamination, 4 were in dismantlement, 3 were in safety, and 2 were in material dispositioning. To promote the use of these technologies at other sites within the DOE complex, the LSDDP team published fact sheets, videos, technology summary reports, articles in INEEL star newspaper, posters, and maintained an internet home page on the project. As a result, additional deployments have taken place at the Hanford, Mound, Fernald, Oak Ridge, Ashtabula, and West Valley. Eight of the 26 technologies evaluated were developed in foreign countries. The technologies demonstrated have been shown to be faster, less expensive, and

  10. Dismantling of Evaporators by Laser Cutting Measurement of Secondary Emissions

    International Nuclear Information System (INIS)

    Pilot, Guy; Fauvel, Sylvain; Gosse, Xavier; De Dinechin, Guillaume

    2006-01-01

    In order to dismantle the evaporators of an obsolete reprocessing plant in Marcoule, studies were carried out by IRSN (Institut de Radioprotection et de Surete Nucleaire) / DSU/SERAC in cooperation with CEA (power laser group) on the laser cutting of steel structures, on the request of COGEMA (now AREVA NC) /Marcoule (UP1 dismantling project manager) and CEA/UMODD (UP1 dismantling owner). The aim of these studies was: - to quantify and to characterize the secondary emissions produced by Nd-YAG laser cutting of Uranus 65 steel pieces representative of UP1 evaporator elements and to examine the influence of different parameters, - to qualify a pre-filtration technique and particularly an electrostatic precipitator, - to compare the Nd-YAG used with other cutting tools previously studied. The experiments, which took place in a 35 m 3 ventilated cutting cell, allow to underline the following points: for the Uranus 65 steel, the sedimented dross, the deposits on the walls of the cutting cell and the aerosols drawn in the ventilation exhaust duct (∼ 275 m 3 /h), represent respectively between 92% and 99%, between 0.01% and 0.25% and between 1% and 8% of the total collected mass, the attached slag varies much from one configuration to the other and can sometimes amount to a relatively important fraction of the total mass, the kerves vary from 2 mm up to 7 mm for the Uranus 65 steel plates (thickness: 13.8 mm for the single plate and 12.8 + 3.5 mm for the double plate), the exhausted aerosol mass per cut length (g/m) decreases with the cutting speed, varies neither with the stand-off nor with the gas pressure, is dependent upon the gas nature (for the double plate), increases with the laser power, is strongly affected by the nature of the steel (stainless steel or mild steel) and is independent upon the plate position, the size distribution of aerosols is multimodal with a main mode often around 0.45 μm, the electrostatic precipitator has been a satisfactory prefilter

  11. Study Results on Knowledge Requirements for Entry-Level Airport Operations and Management Personnel

    Science.gov (United States)

    Quilty, Stephen M.

    2005-01-01

    This paper identifies important topical knowledge areas required of individuals employed in airport operations and management positions. A total of 116 airport managers and airfield operations personnel responded to a survey that sought to identify the importance of various subject matter for entry level airport operations personnel. The results from this study add to the body of research on aviation management curriculum development and can be used to better develop university curriculum and supplemental training focused on airport management and operations. Recommendations are made for specialized airport courses within aviation management programs. Further, this study identifies for job seekers or individuals employed in entry level positions those knowledge requirements deemed important by airport managers and operations personnel at different sized airports.

  12. Dismantling of the 904 Cell at the HAO/Sud Facility - 13466

    Energy Technology Data Exchange (ETDEWEB)

    Vaudey, C.E.; Crosnier, S. [AREVA Clean-Up BU, 1 route de la Noue 91196 - Gif-sur-Yvette (France); Renouf, M.; Gaspard, N. [AREVA Clean-Up BU, Site de La Hague - BV 35 - 50444 Beaumont Hague (France); Pinot, L. [AREVA D and D BU, Site de La Hague - 50444 Beaumont Hague (France)

    2013-07-01

    La Hague facility, in France, is the spent fuel recycling plant wherein a part of the fuel coming from some of the French, German, Belgian, Swiss, Dutch and Japanese nuclear reactors is reprocessed before being recycled in order to separate certain radioactive elements. The facility has been successively handled by the CEA (1962-1978), Cogema (1978-2006), and AREVA NC (since 2006). La Hague facility is composed of 3 production units: The UP2-400 production unit started to be operated in 1966 for the reprocessing of UNGG metal fuel. In 1976, following the dropout of the graphite-gas technology by EDF, an HAO workshop to reprocess the fuel from the light water reactors is affiliated and then stopped in 2003. - UP2-400 is partially stopped in 2002 and then definitely the 1 January 2004 and is being dismantled - UP2-800, with the same capacity than UP3, started to be operated in 1994 and is still in operation. And UP3 - UP3 was implemented in 1990 with an annual reprocessing capacity of 800 tons of fuel and is still in operation The combined licensed capacity of UP2-800 and UP3 is 1,700 tons of used fuel. (authors)

  13. Varying Levels of Automation on UAS Operator Responses to Traffic Resolution Advisories in Civil Airspace

    Science.gov (United States)

    Kenny, Caitlin; Fern, Lisa

    2012-01-01

    Continuing demand for the use of Unmanned Aircraft Systems (UAS) has put increasing pressure on operations in civil airspace. The need to fly UAS in the National Airspace System (NAS) in order to perform missions vital to national security and defense, emergency management, and science is increasing at a rapid pace. In order to ensure safe operations in the NAS, operators of unmanned aircraft, like those of manned aircraft, may be required to maintain separation assurance and avoid loss of separation with other aircraft while performing their mission tasks. This experiment investigated the effects of varying levels of automation on UAS operator performance and workload while responding to conflict resolution instructions provided by the Tactical Collision Avoidance System II (TCAS II) during a UAS mission in high-density airspace. The purpose of this study was not to investigate the safety of using TCAS II on UAS, but rather to examine the effect of automation on the ability of operators to respond to traffic collision alerts. Six licensed pilots were recruited to act as UAS operators for this study. Operators were instructed to follow a specified mission flight path, while maintaining radio contact with Air Traffic Control and responding to TCAS II resolution advisories. Operators flew four, 45 minute, experimental missions with four different levels of automation: Manual, Knobs, Management by Exception, and Fully Automated. All missions included TCAS II Resolution Advisories (RAs) that required operator attention and rerouting. Operator compliance and reaction time to RAs was measured, and post-run NASA-TLX ratings were collected to measure workload. Results showed significantly higher compliance rates, faster responses to TCAS II alerts, as well as less preemptive operator actions when higher levels of automation are implemented. Physical and Temporal ratings of workload were significantly higher in the Manual condition than in the Management by Exception and

  14. Decontamination before dismantling a fast breeder reactor primary cooling system

    International Nuclear Information System (INIS)

    Costes, J.R.; Antoine, P.; Gauchon, J.P.

    1997-01-01

    The large-scale decontamination of FBR sodium loops is a novel task, as only a limited number of laboratory-scale results are available to date. The principal objective of this work is to develop a suitable decontamination procedure for application to the primary loops of the RAPSODIE fast breeder reactor as part of decommissioning to Stage 2. After disconnecting the piping from the main vessel, the pipes were treated by circulating chemical solutions and the vessels by spraying. The dose rate in the areas to be dismantled was divided by ten. A decontamination factor of about 300 was obtained, and should allow austenitic steel parts to be melted in special furnaces for unrestricted release. (author)

  15. The Dismantling of the Japanese Model in Consumer Electronics

    DEFF Research Database (Denmark)

    Frøslev Christensen, Jens; Holm Olesen, Michael; Kjær, Jonas

    This paper addresses an issue of great importance for the future organization of the consumerelectronics industry: the "battle" of control over component-based digitization. We are now witnessing the dismantling of the Japanese Model that has prevailed in consumer electronicsover the past 30 years....... Specialized and large-scale component suppliers have taken the lead inmost component-based innovations and have obtained increasingly powerful positions in thevalue chain of consumer electronics. This paper provides an in-depth study of the strategic andstructural ramifications of one such component...... technology. Aframework is developed to explain the reluctance of most of the large consumer electronicsgiants in developing/adopting this new technology.Key words: Consumer electronics, Industrial dynamics, Open InnovationJEL Codes: L6, L68, O32...

  16. Method and apparatus for dismantling and disposing of fuel assemblies

    International Nuclear Information System (INIS)

    Meuschke, R.E.; Schulties, J.R.

    1985-01-01

    This invention relates to apparatus and a method for dismantling, shearing, and compacting a fuel assembly frame skeleton. It uses an apparatus capable of hanging or being supported in the transfer canal of the spent fuel pit of the fuel handling building. This apparatus includes a bottom nozzle shear which is held under water to shear off the bottom nozzle and convey it to a scrap transfer bin. Then the remaining portion is brought to a skeleton compactor and shear, also held under water. The compacted skeleton is sheared into a number of smaller portions. After compacting and shearing, the individual portions are fed to the scrap transfer bin. The compacted and sheared skeleton assembly may be placed into a container that is adapted to hold four skeletons for off-site removal

  17. Outsourcing and "dismantling" of steady jobs at hospitals

    Directory of Open Access Journals (Sweden)

    Helton Saragor de Souza

    2016-04-01

    Full Text Available Abstract OBJECTIVE To relate hospitals' organizational structure as the core of a web of outsourced services and flexible employment bonds among healthcare professionals in the context of finance capitalism, analyzing work arrangements based mainly on the type of employment bond. METHOD Qualitative research through ethnography, interviews, data analysis, and case studies. The case studies were concentrated in 3 hospitals located in the São Paulo metropolitan region under different management types: public administration; outsourced administration via a healthcare social organization (HSO; and private administration. RESULTS This study highlights a trend in outsourcing, dismantling of steady jobs, and shaping working relations asymmetrically in terms of healthcare professions. CONCLUSION These aspects are characteristic of contemporary capitalism and post-Fordist work organization. In this context, the state under sponsorship cripples the very existence of an effective human resources policy, creating a favorable environment for outsourcing and flexibility of employment bonds among healthcare workers.

  18. Mock-up-CZ: dismantling of the experiment - Geotechnical results

    International Nuclear Information System (INIS)

    Svoboda, J.; Vasicek, R.

    2010-01-01

    Document available in extended abstract form only. The issue of the disposal of radioactive waste is one of the most pressing challenges of our age, for which, in most countries, the deep repository concept is generally considered to be the most suitable final solution. In order to make such a repository both safe and reliable, intensive research is underway worldwide. The construction of physical models is one approach to the study of the engineered barriers for deep geological repositories; one such experiment, Mock-Up-CZ, has been performed at the Centre of Experimental Geotechnics, CTU in Prague. The Mock-Up-CZ experiment simulated the vertical placement of a container with radioactive waste, an approach that is in line with the Swedish KBS-3 system. The physical model consisted of a barrier made up of bentonite blocks, powdered bentonite backfill, a heater and hydration and monitoring systems. The whole experiment was enclosed in a cylindrical box, whose construction was able to withstand high pressure due to bentonite swelling. A number of sensors (monitoring changes in temperature, pressure and moisture) were placed inside the bentonite barrier. The basic material used in the experiment consisted of a mixture of Czech bentonite from the Rokle deposit (85%), quartz sand (10%) and graphite (5%). The first phase of the experiment commenced on 7 May 2002, during which the heater was switched on, with no water input. After 6 months the second phase commenced in which water was introduced through the hydration system. This phase ended on 2nd January 2006 when the heater was switched off. After allowing time for cooling, the dismantling phase commenced (30 January 2006). After a further one and a half months (17 March 2006) the dismantling of the experimental vessel was completed. Post-decommissioning analysis continued until the end of 2007. Dismantling and post-decommissioning analysis were carried out according to a very detailed plan which included not only

  19. Chronic subdural hematoma with sedimentation level on CT: correlation with clinical and operative findings

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Sung Hee; Lee, Hyeon Kyeong; Lee, Won Jae [College of Medicine, Dongguk University, Kyungju (Korea, Republic of)] (and others)

    1994-03-15

    The purpose of this study is to correlate CT findings of the patients with chronic subdural hematoma(SDH) showing a sedimentation level with their clinical and operative findings. We selected 9 patients who showed a sedimentation level within the hematoma after reviewing the CT findings of 55 patients with SDH. We also analyzed their age, initial symptoms, cause of head injury, latent period, the level of consciousness on admission, CT findings, and operative findings. All of the 9 patients were aged persons(over 52 years). They had a history of acute exacerbation of neurologic symptoms. Five of them had an apparent history of head trauma more than one month before the exacerbation. The CT scans showed unilateral, crescent-shaped subdural fluid collection with a sedimentation level except a case of bilateral SDH and 2 cases of planoconvex-shaped SDH. The interface of the sedimentation level was sharp in 3 cases and indistinct in 6 cases. None had bleeding tendency and the hemoglobin level was slightly decreased in 2 patients. All patients revealed membrane of the hematoma during operation. The upper portion of the sedimentation was liquefied blood and the lower portion was fresh blood clots. We could observe fresh RBC's in the hematoma microscopically. A sedimentation level in chronic SDH was operatively proved to represent rebleeding, and was clinically manifested as an acute exacerbation of symptoms.

  20. Systems analysis of radiation safety during dismantling of power-plant equipment at a nuclear power station

    International Nuclear Information System (INIS)

    Bylkin, B.K.; Shpitser, V.Ya.

    1993-01-01

    A systems analysis of the radiation safety makes possible an ad hoc determination of the elements forming the system, as well as the establishment of the characteristics of their interaction with radiation-effect factors. Here the authors will present part of the hierarchical analysis procedure, consisting in general of four separate procedures. The purpose is to investigate and analyze the mean and stable (on the average) indices of radiation safety, within the framework of alternative mathematical models of dismantling the power-plant equipment of a nuclear power station. The following three of the four procedures are discussed: (1) simulated projection, of the processing of radioactive waste; (2) analysis of the redistribution of radionuclides during the industrial cycle of waste treatment; (3) planning the collective dose load during the dismantling operation. Within the framework of the first of these procedures, the solutions to the problem of simulating a waste-treatment operation of maximum efficiency are analyzed. This analysis is based on the use of a data base for the parameters of the installations, assemblies, and equipment, enabling the integration of these in a simulation of a complex automated facility. The results were visualized in an AUTOCAD-10 medium using a graphical data base containing an explanation of the rooms

  1. For a public management of funds dedicated to nuclear dismantling: the TESEN (fund for the Energy transition and a fair phasing out nuclear), and its assignment to the financing of energy transition

    International Nuclear Information System (INIS)

    Autissier, Isabelle; Germa, Philippe

    2013-01-01

    The report outlines that the cost of nuclear energy in France is largely under-assessed because of the under-evaluation of the future dismantling of nuclear installations and of the management of radioactive wastes. It outlines that provisions made for this dismantling are insufficient, opaque and very risky. This report proposes the creation of a fund independent from nuclear operators to make pay the actual cost of nuclear energy and reduce the French electrical dependence on this energy, to secure long-term financing to finance the dismantling, to bring the financing for the decades to come to finance energy transition, to finance energy transition at reasonable rates, and to clarify the governance for phasing out nuclear

  2. Effects of PCBs and PBDEs on thyroid hormone, lymphocyte proliferation, hematology and kidney injury markers in residents of an e-waste dismantling area in Zhejiang, China

    Energy Technology Data Exchange (ETDEWEB)

    Xu, Peiwei, E-mail: pwxu@cdc.zj.cn; Lou, Xiaoming; Ding, Gangqiang, E-mail: gqding@cdc.zj.cn; Shen, Haitao; Wu, Lizhi; Chen, Zhijian; Han, Jianlong; Wang, Xiaofeng, E-mail: zjcdcwxf@gmail.com

    2015-12-01

    Polychlorinated biphenyls (PCBs) and polybrominated diphenyl ethers (PBDEs) are two typical categories of contaminants released from e-waste dismantling environments. In China, the body burdens of PCBs and PBDEs are associated with abnormal thyroid hormones in populations from e-waste dismantling sites, but the results are limited and contradictory. In this study, we measured the serum levels of PCBs and PBDEs and the thyroid hormone free triiodothyronine (FT3), free thyroxine (FT4) and thyroid-stimulating hormone (TSH) in 40 residents in an e-waste dismantling area and in 15 residents in a control area. Additionally, we also measured some lymphocyte proliferation indexes, hematologic parameters and kidney injury markers, including white blood cells, neutrophils, monocytes, lymphocytes, hemoglobin, platelets, serum creatinine and beta 2-microglobulin (β{sub 2}-MG). The results indicated that the mean level of ΣPCBs in the exposure group was significantly higher than that in the control group (964.39 and 67.98 ng g{sup −1}, p < 0.0001), but the mean level of ΣPBDEs in the exposure group was not significantly higher than that in the controls (139.32 vs. 75.74 ng g{sup −1}, p > 0.05). We determined that serum levels of FT3, FT4, monocytes and lymphocytes were significantly lower, whereas the levels of neutrophils, hemoglobin, platelets and serum creatinine were significantly higher in the exposed group (p < 0.05). The mean level of ΣPCBs was negatively correlated with levels of FT3, FT4, monocytes and lymphocytes (p < 0.05) and positively correlated with levels of neutrophils, hemoglobin, serum creatinine and β{sub 2}-MG (p < 0.05). Additionally, the mean level of ΣPBDEs was positively correlated with levels of white blood cells, hemoglobin and platelets (p < 0.05). Our data suggest that exposure to an e-waste dismantling environment may increase the body burdens of PCBs and the specific PBDEs congeners in native residents and that the contaminants released

  3. The application of assessment principles to an operational low level waste disposal site in England

    International Nuclear Information System (INIS)

    McHugh, J.O.; Newstead, S.; Weedon, C.J.

    1988-01-01

    This paper reviews the current assessment principles utilized in England and discusses their application to the Drigg low-level Radioactive Waste Disposal Site. The Drigg Site was established in 1959 and the assessment principles were published in 1985; therefore, although the Drigg Site has operated successfully, the application of the assessment principles has caused changes in operations and the establishment of further site research by the Department of the Environment

  4. Low-level radioactive waste disposal operations at Los Alamos National Laboratory

    International Nuclear Information System (INIS)

    Stanford, A.R.

    1997-01-01

    Los Alamos National Laboratory (LANL) generates Low-Level Radioactive Waste (LLW) from various activities: research and development, sampling and storage of TRU wastes, decommissioning and decontamination of facilities, and from LANL's major role in stockpile stewardship. The Laboratory has its own active LLW disposal facility located at Technical Area 54, Area G. This paper will identify the current operations of the facility and the issues pertaining to operating a disposal facility in today's compliance and cost-effective environment

  5. Optimized phases for reactor dismantling – an efficient and sustainable concept

    International Nuclear Information System (INIS)

    Krüger, S.; Winter, J.

    2013-01-01

    D&D projects are driven by costs, to implement an optimization process from the very beginning is key. Optimized strategy and sequencing of the dismantling (hot to cold) will provide serious economical savings . Larger dismantling packages will reduce interfaces and ease the coordination efforts on site. Early usage of mobile systems will ease the large-scale release for dismantling Social transition has to be addressed with priority and to be planned at an early phase in the D&D planning Concept, Planning & Project Management will influence the success of the project much more than the used technique

  6. Operating cost guidelines for benchmarking DOE thermal treatment systems for low-level mixed waste

    International Nuclear Information System (INIS)

    Salmon, R.; Loghry, S.L.; Hermes, W.H.

    1994-11-01

    This report presents guidelines for estimating operating costs for use in benchmarking US Department of Energy (DOE) low-level mixed waste thermal treatment systems. The guidelines are based on operating cost experience at the DOE Toxic Substances Control Act (TSCA) mixed waste incinerator at the K-25 Site at Oak Ridge. In presenting these guidelines, it should be made clear at the outset that it is not the intention of this report to present operating cost estimates for new technologies, but only guidelines for estimating such costs

  7. Comparing the subjective task difficulty of human operators with task description levels

    International Nuclear Information System (INIS)

    Park, Jin Kyun; Jung, Won Dea; Yang, Joon Eon

    2011-01-01

    Without the loss of generality, it is reasonable to say that an operating procedure consists of many steps including detailed descriptions that provide necessary information in conducting the required tasks safely and effectively. In this regard, since it is widely perceived that procedures are effective for reducing the occurrence of human performance related problems, the use of procedures is very popular in large process control systems including nuclear power plants (NPPs), commercial airplanes and railway systems. However, the secure of an operational safety by using an operating procedure can be accomplished only if human operators are able to effectively obtain necessary information from it. In other words, it is hard to expect the reduction of human performance related problems, if task descriptions are so ambiguous or incomplete that human operators feel an undue difficulty in identifying 'what have to be done' and 'how to do it' from procedures. Unfortunately, it seems that a systematic method that can be used to distinguish the proper level of task descriptions is rare. For this reason, Park et al. developed a decision chart that could be helpful for characterizing the level of task descriptions. In this study, in order to ensure the appropriateness of the suggested decision chart, more detailed investigations were conducted with the support of human operators who are working as the operating personnel of NPPs

  8. Operator dependency of the radiation exposure in cardiac interventions: feasibility of ultra low dose levels

    International Nuclear Information System (INIS)

    Emre Ozpelit, Mehmet; Ercan, Ertugrul; Pekel, Nihat; Tengiz, Istemihan; Yilmaz, Akar; Ozpelit, Ebru; Ozyurtlu, Ferhat

    2017-01-01

    Introduction: Mean radiation exposure in invasive cardiology varies greatly between different centres and interventionists. The International Commission on Radiological Protection and the EURATOM Council stipulate that, despite reference values, 'All medical exposure for radiodiagnostic purposes shall be kept as low as reasonably achievable' (ALARA). The purpose of this study is to establish the effects of the routine application of ALARA principles and to determine operator and procedure impact on radiation exposure in interventional cardiology. Materials and methods: A total of 240 consecutive cardiac interventional procedures were analysed. Five operators performed the procedures, two of whom were working in accordance with ALARA principles (Group 1 operators) with the remaining three working in a standard manner (Group 2 operators). Radiation exposure levels of these two groups were compared. Results: Total fluoroscopy time and the number of radiographic runs were similar between groups. However, dose area product and cumulative dose were significantly lower in Group 1 when compared with Group 2. Radiation levels of Group 1 were far below even the reference levels in the literature, thus representing an ultra-low-dose radiation exposure in interventional cardiology. Conclusion: By use of simple radiation reducing techniques, ultra-low-dose radiation exposure is feasible in interventional cardiology. Achievability of such levels depends greatly on operator awareness, desire, knowledge and experience of radiation protection. (authors)

  9. Present status of refining and conversion facility dismantling. Progress in 2008 first half of the fiscal year

    International Nuclear Information System (INIS)

    Kado, Kazumi; Sugitsue, Noritake; Morimoto, Yasuyuki; Ikegami, Sohei; Takahashi, Nobuo; Tokuyasu, Takashi

    2009-06-01

    The Refining and Conversion Facility located in the Ningyo-toge Environmental Engineering Center. Process of natural uranium conversion facility (PNC Process) and reprocessed uranium conversion facility (two-stage dry fluorination system) is in a Refining and Conversion Facility. This building started construction in 1979 and was completed in October 1981. The PNC process operated from March 1982 to March 1991. As a result, uranium hexafluoride of about 385 tonU was manufactured. Also, the reprocessed uranium conversion process operated from December 1982 to July 1999. As a result, uranium hexafluoride of about 338 tonU was manufactured. The demonstration of the demolition method was done using the PNC process after the end of operation. The schedule which will finish dismantling of all equipment in a radiation controlled area is by the 2011 fiscal year. This report summarized the present situation by the first half of the 2008 fiscal year of a Refining and Conversion Facility decommissioning. (author)

  10. Utilization of External Capacities as an Integral Component of Concepts for Residues and Dismantling Using the Example of the CARLA Plant. National and International Experiences in Recycling

    International Nuclear Information System (INIS)

    Kluth, Thomas

    2014-01-01

    -room. Here, a suspension track blasting equipment was installed along with an inside tube blasting equipment. With this equipment, all tubes starting from a diameter of 20 mm can be decontaminated. Further steps of upgrading are in planning stage. For metals having been processed by melting and for nearly all process wastes licensed release procedures according to paragraph 29 StrlSchV (radiation protection ordinance) are available including established disposal paths. Taking into account several marginal conditions, a decay storage of up to 20 years can be effected for metal ingots at our premises at Krefeld. This, too, is an important contribution to more flexibility and higher efficiency. The CARLA plant fulfills all requirements which are indispensable for a good concept to treat residues. It avoids waste, reduces the waste volume and provides for subsequent recycling of the residues. The licensed capacity of the plant is sufficient to make up for any peak of demand resulting from the present situation. Thus the operators are able to design their dismantling strategies in the plants much more freely. Disassembly works, for example, can be predated into the post-closure phase. Different project steps can be processed parallelly and the whole material logistics in the plant can be optimized. By increased involvement of external capacities like CARLA the challenges of the national dismantling activities over the coming years can be mastered successfully to a large extent. The same applies to the international sector where, however, the sometimes strongly differing framework requirements regarding the situation of the final repository or release options may lead to different key aspects for involving CARLA into the individual projects. In international technological comparison, German dismantling projects doubtlessly take a leading position, however, regarding efficiency there is still room for optimization. An early involvement of qualified service suppliers can help to

  11. Overview of recycling technologies for decommissioned materials. Lessons learned during the dismantling of a small PWR reactor

    International Nuclear Information System (INIS)

    Klein, M.; Emond, O.; Ponnet, M.

    2001-01-01

    Full text: SCK CEN is dismantling its 11 MWe PWR reactor. The reactor was shutdown in 1987 after 25 years of operation and the dismantling started in 1990. For the management of the low radioactive materials, we apply a strategy promoting the minimisation of the production of radioactive waste and hence the maximisation of the production of recycled materials while keeping the costs as low as possible. The recycled materials are either reused in the non- nuclear industry as raw materials (metal scrap industry or building industry for the concrete) or recycled in the nuclear industry for specific applications (reuse of metals for fabrication of shielding, potential reuse of concrete for production of 'radioactive mortar'). The clearance of radioactive materials and their reuse require the strict respect of procedures and specifications. In our case, the Health Physics department under supervision of the Competent Authority establishes the procedures. This procedure is still a case by case practice but the legislation in Belgium is progressively put in place. For the recycling in the nuclear industry, we must respect the specifications of the end-user. Up to now, we have recycled low radioactive metals for the fabrication of shielding in the USA, so we had to respect the specifications of the melting facility and to obtain the authorisations for the transport abroad and for the transfer of property. Besides the radioactive waste route, we are using several evacuation routes for the dismantled materials: Evacuation of the cleared metals (iron, stainless steel, copper, electric motors...) to a local scrap dealer; Evacuation of metals to the Studsvik melting facility situated in Sweden: after clearance by the Swedish Authority, the non radioactive materials are sent to a local scrap dealer and the secondary radioactive waste is sent back to Belgium and conditioned by Belgoprocess. This technology further decontaminates the metals and allows performing an accurate

  12. Digital Autoradiography as a novel complementary technique for the investigation of radioactive contamination in nuclear facilities under dismantlement

    International Nuclear Information System (INIS)

    Haudebourg, Raphael; Fichet, Pascal; Goutelard, Florence

    2015-01-01

    The detection (location and quantification) of nuclear facilities to be dismantled possible contamination with low-range particles emitters ( 3 H, other low-energy β emitters, a emitters) remains a tedious and expensive task. Indeed, usual remote counters show a too low sensitivity to these non-penetrating radiations, while conventional wipe tests are irrelevant for fixed radioactivity evaluation. The only method to accurately measure activity levels consists in sampling and running advanced laboratory analyses (spectroscopy, liquid scintillation counting, pyrolysis...). Such measurements generally induce sample preparation, waste production (destructive analyses, solvents), nuclear material transportation, long durations, and significant labor mobilization. Therefore, the search for the limitation of their number and cost easily conflicts with the necessity to perform a dense screening for sampling (to maximize the representativeness of the samples), in installations of thousands of square meters (floors, wells, ceilings), plus furniture, pipes, and other wastes. To overcome this contradiction, Digital Autoradiography (D. A.) was re-routed from bio molecular research to radiological mapping of nuclear installations under dismantling and to waste and sample analysis. After in-situ exposure to the possibly-contaminated areas to investigate, commercial reusable radiosensitive phosphor screens (of a few 100 cm 2 ) were scanned in the proper laboratory device and sharp quantitative images of the radioactivity could be obtained. The implementation of geostatistical tools in the data processing software enabled the exhaustive characterization of concrete floors at a rate of 2 weeks / 100 m 2 , at lowest costs. Various samples such as drilled cores, or tank and wood pieces, were also successfully evaluated with this method, for decisive results. Thanks to the accurate location of potential contamination spots, this approach ensures relevant and representative sampling

  13. Maintaining reduced noise levels in a resource-constrained neonatal intensive care unit by operant conditioning.

    Science.gov (United States)

    Ramesh, A; Denzil, S B; Linda, R; Josephine, P K; Nagapoornima, M; Suman Rao, P N; Swarna Rekha, A

    2013-03-01

    To evaluate the efficacy of operant conditioning in sustaining reduced noise levels in the neonatal intensive care unit (NICU). Quasi-experimental study on quality of care. Level III NICU of a teaching hospital in south India. 26 staff employed in the NICU. (7 Doctors, 13 Nursing staff and 6 Nursing assistants). Operant conditioning of staff activity for 6 months. This method involves positive and negative reinforcement to condition the staff to modify noise generating activities. Comparing noise levels in decibel: A weighted [dB (A)] before conditioning with levels at 18 and 24 months after conditioning. Decibel: A weighted accounts for noise that is audible to human ears. Operant conditioning for 6 months sustains the reduced noise levels to within 62 dB in ventilator room 95% CI: 60.4 - 62.2 and isolation room (95% CI: 55.8 - 61.5). In the preterm room, noise can be maintained within 52 dB (95% CI: 50.8 - 52.6). This effect is statistically significant in all the rooms at 18 months (P = 0.001). At 24 months post conditioning there is a significant rebound of noise levels by 8.6, 6.7 and 9.9 dB in the ventilator, isolation and preterm room, respectively (P =0.001). Operant conditioning for 6 months was effective in sustaining reduced noise levels. At 18 months post conditioning, the noise levels were maintained within 62 dB (A), 60 dB (A) and 52 dB (A) in the ventilator, isolation and pre-term room, respectively. Conditioning needs to be repeated at 12 months in the ventilator room and at 18 months in the other rooms.

  14. An Analysis of United States Marine Corps Enlisted Entry-Level Training Using Supply Chain and Operations Management

    Science.gov (United States)

    2010-12-01

    An Analysis of United States Marine Corps Enlisted Entry-Level Training Using Supply Chain and Operations Management ______________________________________ By...Report 4. TITLE AND SUBTITLE: An Analysis of United States Marine Corps Enlisted Entry-Level Training Using Supply Chain and Operations Management 6...Level Training; United States Marine Corps; Operations Management ; Supply Chain Management; Process Analysis 16. PRICE CODE 17. SECURITY

  15. Human reliability analysis in support of a level 1 PRA for Surry during midloop operations

    International Nuclear Information System (INIS)

    Lin, J.C.; Bley, D.C.; Chu, T.-L.

    2004-01-01

    The objectives of this Level 1 probabilistic risk assessment (PRA) are to evaluate the important accident sequences initiated during midloop operations and to compare the qualitative and quantitative results with those for accidents initiated during power operations. The primary types of human actions analyzed in this study involve the dynamic operator actions and recovery actions that take place during the accident sequence following an initiating event. Two parts of the human actions were analyzed: failure to diagnose and failure to perform the action. The scope of the Level 1 PRA for Surry during midloop operations includes internal, fire, and flood initiating events. The major categories of dynamic operator actions taken during the accident sequence following an initiating event are: providing makeup to the reactor coolant system (RCS), restoring residual heat removal (RHR) cooling, establishing steam generator reflux cooling, establishing primary feed and spill, establishing gravity feed from refueling water storage tank (RWST), establishing high pressure recirculation, establishing recirculation spray, and cross-connecting RWSTs. All categories are not applicable to all initiating events and all plant operating states (POS). (author)

  16. Integration of emergency action levels with Combustion Engineering Emergency Operating Procedures

    International Nuclear Information System (INIS)

    Faletti, D.W.; Jamison, J.D.

    1985-09-01

    This report documents the development of a method for integrating Emergency Action Levels (EALs) with plant-specific Emergency Operating Procedures (EOPs) using the Combustion Engineering Owners' Group Emergency Operating Procedure Technical Guidelines (CEOG EOPTFs). EALs are discrete conditions or values of plant operating parameters which, if exceeded, require declaration of an appropriate level of emergency. At most operating plants, the EALs and event classification procedures are totally separate from the Emergency Operating Procedures used by the plant staff to control the plant during abnormal conditions. Control room personnel using the EOPs to deal with abnormal plant conditions must recognize when plant safety is sufficiently degraded that an emergency declaration may be warranted, and then enter a separate classification procedure containing EALs for a number of plant conditions and parameters. The operator then compares the existing plant conditions to the EALs and makes an emergency declaration accordingly. Using the Combustion Engineering Owners' Group Technical Guidelines document, a set of emergency class definitions and criteria were developed based on the status of the three main fission product barriers (fuel cladding, primary coolant system and containment). The EOPTGs were then annotated with suggested guidance to a procedure writer. The proposed method was tested by applying it to the reactor accident sequences that were shown in the reactor safety study to dominate accident risk. The object of the test was to determine if an EAL set linked to the EOP annotations would produce timely and accurate classification of the risk-dominant sequences. 6 refs., 13 figs., 31 tabs

  17. A process for separating aggregate from concrete waste during the dismantlement of nuclear power plants

    International Nuclear Information System (INIS)

    Koga, Yasuo; Inoue, Toshikatsu; Tateyashiki, Hisashi; Sukekiyo, Mitsuaki; Okamoto, Masamichi; Asano, Touichi.

    1997-01-01

    The decommissioning and dismantling of nuclear power plants will produce a large quantity of non-active waste concrete. From the viewpoint of recycling of this waste concrete the recovery of aggregate contained in concrete at 80% and reuse of it into a new plant construction are envisioned. For these purposes we have studied the recovery process of aggregate from concrete composed of a heating step followed by a milling step onto waste concrete blocks. We have found that higher operation temperature brings a better effect for the separation of aggregate from a concrete body, however too high temperature may reversely degrade a quality of recovered aggregate itself. The most effective heating temperature which is considered not to give the damage to a quality of aggregate stays between 200-500degC. The effect of a duration at such temperature zone is relatively small. As a conclusion we have found that 300degC of heating temperature and 30-120 minutes of a duration in a rod mill with high efficiency of rubbing work for getting coarse aggregate and an agitate mill for fine aggregate might be proper operating conditions under which we can recover both coarse and fine aggregate with the quality within JASS 5N standard. (author)

  18. Design and Assessment of an Associate Degree-Level Plant Operations Technical Education Program

    Science.gov (United States)

    Selwitz, Jason Lawrence

    2017-01-01

    Research was undertaken to develop and evaluate an associate degree-level technical education program in Plant Operations oriented towards training students in applied science, technology, engineering, and mathematics (STEM) skills and knowledge relevant to a spectrum of processing industries. This work focuses on four aspects of the curriculum…

  19. Analyzing the Required Professional Qualification for Agricultural Extension Experts in Operational Level in the Mazandaran Province

    Directory of Open Access Journals (Sweden)

    Amir Ahmadpour

    2015-08-01

    Full Text Available Extension experts who play an active role at the operational level are required to have some indispensable competencies to enable them to provide the rural community with some high quality, ­applicable and important educational programs. Accordingly, the study sought to analyze the components of professional qualifications for agricultural extension experts’ operational level. This study is a descriptive and survey research. The statistical population (Agricultural Extension Experts in Operational Levels was comprised of 290 persons. And the proportional stratified sampling using Krejcie-Morgan Table was applied and 165 subjects were selected. The data collection tool was a researcher-made questionnaire, and its content validity was approved by agricultural extension experts and by using KMO coefficient and Bartlett’s Test giving a reliability of KMO=0.737(. The data analysis results showed that seven extracted factors of (research factors, technical-professional factors, teaching factors, managerial factors, personality factors, communication factors and virtual technology factors explain 63.691% of the total variance of the professional competencies for agriculture extension experts’ operational levels in the province. The  findings indicate that based on scientific methods of research,  assessment of needs, planning and assessment, and in-service training workshops implementation for experts seem to be necessary. Distinctive attention should be practiced by Agriculture Organization to improve agents’ skills in a variety of crops cultivation and in working with software and agricultural applications.

  20. Elimination of zero sequence circulating current between parallel operating three-level inverters

    DEFF Research Database (Denmark)

    Li, Kai; Wang, Xiaodong; Dong, Zhenhua

    2016-01-01

    In order to suppress the zero sequence circulating currents (ZSCCs) between parallel operating three level voltage source inverters with common AC and DC buses, a common mode voltage reduction PWM (CMVR-PWM) technique and neural point potentials (NPPs) control based method is proposed in this paper...

  1. Installation and operation manual on sea level gauge (Model: NIO_Ghana_2004)

    Digital Repository Service at National Institute of Oceanography (India)

    Joseph, A; Pereira, A; VijayKumar, K.; Prabhudesai, S.; Methar, A; Dias, M.

    NIO sea level gauge is a pressure-based gauge that operates on 12 volts battery. The pressure-sensing element used in this gauge is a piezo-resistive programmable semiconductor transducer that provides pressure samples in RS-485 format...

  2. Designing vertical shafts for mines with deepening and outlet of rock to the operating level

    Energy Technology Data Exchange (ETDEWEB)

    Durov, Ye.M.

    1983-01-01

    Requirements for designing the cross sections of central shafts are examined, as well as those for determining the productivity of lifts and equipment of the shafts with a condition of use in a subsequent technological layout of their deepening with outlet of the rock to the operating level. Typical cross sections of skip and cellular shafts are given.

  3. Present status of refining and conversion facility dismantling. Progress in latter half of 2010FY

    International Nuclear Information System (INIS)

    Kado, Kazumi; Sugitsue, Noritake; Morimoto, Yasuyuki; Ikegami, Sohei; Tanaka, Yoshio; Takahashi, Nobuo; Tokuyasu, Takashi

    2011-09-01

    The Refining and Conversion Facility located in the Ningyo-toge Environmental Engineering Center had the natural uranium conversion process and reprocessed uranium conversion process. The construction of this facility was started in 1979 and completed in October 1981. Dismantling of equipments in radiation controlled area of this facility was started from 2008. Equipments in radiation controlled area (excluding ventilating equipment and liquid waste treatment equipment) will be dismantled by the 2011 fiscal year, and ventilating equipment and liquid waste treatment equipment will be dismantled by the 2014 fiscal year. This report describes the master plan of this decommissioning and shows as the progress in latter half year of 2010FY, the actual time schedule, the method of decommissioning, the decommissioning progress appearance with photographs, work rates of each room / each worker class, and the quantity of dismantled materials and secondary wastes. (author)

  4. LEAR, shown here dismantled, will live to see another golden era as LEIR starting in 2005.

    CERN Multimedia

    Maximilien Brice

    2004-01-01

    The LEAR (Low Energy Antiproton Ring) experiment has now been dismantled. Only the dipoles remain for use in the future LEIR (Low Energy Ion Ring) experiment, the new ring which will supply lead ions to the LHC experiments.

  5. Deliberated opinion of the Environment Authority concerning the dismantling of the Ulysse reactor (CEA Saclay)

    International Nuclear Information System (INIS)

    2010-01-01

    As the Ulysse reactor of Saclay is about to be dismantled, this report discusses the content of a request made by the CEA to definitely stop and dismantle this reactor. After having recalled the origin of this dismantling project and its regulatory framework, it describes the actual works which are planned, and outlines the main challenges to be faced. It discusses the content of the environmental report or impact study, notably the analysis of the initial condition, the analysis of direct and indirect effects of the project on the environment and health, and of the envisaged measures (waste management, liquid and gaseous effluent management, risk management, radiological exposure of workers in charge of this dismantling, and transports). Recommendations are formulated for a rewriting of the provided documents

  6. Operational Strategies for Low-Level Radioactive Waste Disposal Site in Egypt - 13513

    International Nuclear Information System (INIS)

    Mohamed, Yasser T.

    2013-01-01

    The ultimate aims of treatment and conditioning is to prepare waste for disposal by ensuring that the waste will meet the waste acceptance criteria of a disposal facility. Hence the purpose of low-level waste disposal is to isolate the waste from both people and the environment. The radioactive particles in low-level waste emit the same types of radiation that everyone receives from nature. Most low-level waste fades away to natural background levels of radioactivity in months or years. Virtually all of it diminishes to natural levels in less than 300 years. In Egypt, The Hot Laboratories and Waste Management Center has been established since 1983, as a waste management facility for LLW and ILW and the disposal site licensed for preoperational in 2005. The site accepts the low level waste generated on site and off site and unwanted radioactive sealed sources with half-life less than 30 years for disposal and all types of sources for interim storage prior to the final disposal. Operational requirements at the low-level (LLRW) disposal site are listed in the National Center for Nuclear Safety and Radiation Control NCNSRC guidelines. Additional procedures are listed in the Low-Level Radioactive Waste Disposal Facility Standards Manual. The following describes the current operations at the LLRW disposal site. (authors)

  7. Multiparameter optimisation of dismantling activities and waste management at a research centre

    International Nuclear Information System (INIS)

    Andres, Roger

    2001-01-01

    Full text: The Paul Scherrer Institute (PSI) is a multi-disciplinary research centre for natural sciences and technology. The institute is active in solid-state physics, materials sciences, elementary particle physics, life sciences, nuclear and non-nuclear energy research, and energy-related ecology. PSI develops and operates complex research installations such as nuclear reactors and particle accelerators. These produce ionising radiation and major quantities of radioactive materials. The optimal handling of decommissioning and dismantling projects and radioactive waste treatment at PSI represents a complex management task, and is determined by many parameters that are only partially identical to those in the energy producing industry. Some of the major issues are addressed below. Management: The research community often requires rapid changes of experimental equipment. This necessitates that the four steps of decommissioning, removal, dismantling and conditioning of waste are spatially and temporally separated. The availability of a great scientific knowledge pool is instrumental for innovative solutions for the complex problems encountered. The accessibility of a modem hardware park (instruments, workshops etc.), sophisticated computer systems and modelling know how can facilitate the work considerably. The lack of a dedicated pool of decommissioning funds and the need for rapid response (see above) necessitate flexibility of the decommissioning crew and constant coordination and optimisation of the work packages with the institute's top management. The product of a research centre in general is not a tradable commodity and does not result in a direct return of money. Financial mechanisms such as the accumulation of funds for future liabilities are not an option. Since PSI - as probably most research institutes - is funded on a yearly basis, long term cost optimisations processes are in competition with legitimate short-term research needs. The benefits of

  8. Directions in low-level radioactive waste management. Low level-radioactive waste disposal: currently operating commercial facilities

    International Nuclear Information System (INIS)

    1983-09-01

    This publication discusses three commercial facilities that receive and dispose of low-level radioactive waste. The facilities are located in Barnwell, South Carolina; Beatty, Nevada; and Richland, Washington. All three facilities initiated operations in the 1960s. The three facilities have operated without such major problems as those which led to the closure of three other commercial disposal facilities located in the United States. The Beatty site could be closed in 1983 as a result of a Nevada Board of Health ruling that renewal of the site license would be inimical to public health and safety. The site remains open pending federal and state court hearings, which began in January 1983, to resolve the Board of Health ruling. The three sites may also be affected by NRC's 10 CFR Part 61 regulations, but the impact of those regulations, issued in December 1982, has not yet been assessed. This document provides detailed information on the history and current status of each facility. This information is intended, primarily, to assist state officials - executive, legislative, and agency - in planning for, establishing, and managing low-level waste disposal facilities. 12 references

  9. Sites with nuclear facilities in the state of dismantling and their future from the public perspective

    International Nuclear Information System (INIS)

    Kretz, Simon Philipp

    2015-01-01

    The thesis on the public perspective at sites of nuclear facility dismantling covers the following issues: the change of German energy landscapes under social and political points of view, theoretical frame of the work, combination of empirical studies and the theoretical approaches in a space concept, action model and hypotheses on the situation and development in communities with nuclear facilities in the state of dismantling, description of the interviewees, and the empirical results of the interviews.

  10. Management system information of characterization of the dismantling project of Jose Cabrera

    International Nuclear Information System (INIS)

    Gimeno Blesa, M. E.; Martin Palomo, N.; Gomez Rodriguez, C. A.

    2011-01-01

    In the proposed dismantling and decommissioning of the Jose Cabrera NPP is designed and implemented a database of physical and radiological inventory, which provides a powerful tool to optimize the storage, monitoring and control of the characterization data. The database is a useful and reliable management system characterization information that facilitates access and information processing, and ensures their integrity and traceability along of the dismantling project.

  11. An ergonomics study of computerized emergency operating procedures: Presentation style, task complexity, and training level

    International Nuclear Information System (INIS)

    Xu Song; Song Fei; Li Zhizhong; Zhao Qianyi; Luo Wei; He Xuhong; Salvendy, Gavriel

    2008-01-01

    Emergency operating procedures (EOPs) are widely used in nuclear power plants (NPPs). With the development of information technology, computerized EOPs are taking the place of paper-based ones. Unlike paper-based EOPs, the industrial practice of computerized EOPs is still quite limited. Ergonomics issues of computerized EOPs have not been studied adequately. This study focuses on the effects of EOP presentation style, task complexity, and training level on the performance of the operators in the execution of computerized EOPs. One simulated computerized EOP system was developed to present two EOPs, each with different task complexity levels, by two presentation styles (Style A: one- and two-dimensional flowcharts combination; Style B: two-dimensional flowchart and success logic tree combination). Forty subjects participated in the experiment of EOP execution using the simulated system. Statistical analysis of the experimental results indicates that: (1) complexity, presentation style, and training level all can significantly influence the error rate. High-complexity tasks and lack of sufficient training may lead to a higher error rate. Style B caused a significantly higher error rate than style A did in the skilled phase. So the designers of computerized procedures should take the presentation styles of EOPs into account. (2) Task complexity and training level can significantly influence operation time. No significant difference was found in operation time between the two presentation styles. (3) Training level can also significantly influence the subjective workload of EOPs operations. This implies that adequate training is very important for the performance of computerized EOPs even if emergency responses with computerized EOPs are much more simple and easy than that with paper-based EOPs

  12. An ergonomics study of computerized emergency operating procedures: Presentation style, task complexity, and training level

    Energy Technology Data Exchange (ETDEWEB)

    Xu Song; Song Fei [Department of Industrial Engineering, Tsinghua University, Beijing 100084 (China); Li Zhizhong [Department of Industrial Engineering, Tsinghua University, Beijing 100084 (China)], E-mail: zzli@tsinghua.edu.cn; Zhao Qianyi; Luo Wei [Department of Industrial Engineering, Tsinghua University, Beijing 100084 (China); He Xuhong [Scanpower Risk Management China Inc., Towercrest International Plaza, No. 3 Maizidian West Road, Chaoyang District, Beijing 100016 (China); Salvendy, Gavriel [Department of Industrial Engineering, Tsinghua University, Beijing 100084 (China)

    2008-10-15

    Emergency operating procedures (EOPs) are widely used in nuclear power plants (NPPs). With the development of information technology, computerized EOPs are taking the place of paper-based ones. Unlike paper-based EOPs, the industrial practice of computerized EOPs is still quite limited. Ergonomics issues of computerized EOPs have not been studied adequately. This study focuses on the effects of EOP presentation style, task complexity, and training level on the performance of the operators in the execution of computerized EOPs. One simulated computerized EOP system was developed to present two EOPs, each with different task complexity levels, by two presentation styles (Style A: one- and two-dimensional flowcharts combination; Style B: two-dimensional flowchart and success logic tree combination). Forty subjects participated in the experiment of EOP execution using the simulated system. Statistical analysis of the experimental results indicates that: (1) complexity, presentation style, and training level all can significantly influence the error rate. High-complexity tasks and lack of sufficient training may lead to a higher error rate. Style B caused a significantly higher error rate than style A did in the skilled phase. So the designers of computerized procedures should take the presentation styles of EOPs into account. (2) Task complexity and training level can significantly influence operation time. No significant difference was found in operation time between the two presentation styles. (3) Training level can also significantly influence the subjective workload of EOPs operations. This implies that adequate training is very important for the performance of computerized EOPs even if emergency responses with computerized EOPs are much more simple and easy than that with paper-based EOPs.

  13. The ATLAS Level-1 Topological Trigger Design and Operation in Run-2

    CERN Document Server

    Igonkina, Olga; The ATLAS collaboration

    2018-01-01

    The ATLAS Level-1 Trigger system performs initial event selection using data from calorimeters and the muon spectrometer to reduce the LHC collision event rate down to about 100 kHz. Trigger decisions from the different sub-systems are combined in the Central Trigger Processor for the final Level-1 decision. A new FPGAs-based AdvancedTCA sub-system was introduced to calculate in real time complex kinematic observables: the Topological Processor System. It was installed during the shutdown and commissioning started in 2015 and continued during 2016. The design and operation of the Level-1 Topological Trigger in Run-2 will be illustrated.

  14. Correlation between defect transition levels and thermoelectric operational temperature of doped CrSi2

    Science.gov (United States)

    Singh, Abhishek; Pandey, Tribhuwan

    2014-03-01

    The performance of a thermoelectric material is quantified by figure of merit ZT. The challenge in achieving high ZT value requires simultaneously high thermopower, high electrical conductivity and low thermal conductivity at optimal carrier concentration. So far doping is the most versatile approach used for modifying thermoelectric properties. Previous studies have shown that doping can significantly improve the thermoelectric performance, however the tuning the operating temperature of a thermoelectric device is a main issue. Using first principles density functional theory, we report for CrSi2, a linear relationship between thermodynamic charge state transition levels of defects and temperature at which thermopower peaks. We show for doped CrSi2 that the peak of thermopower occurs at the temperature Tm, which corresponds to the position of defect transition level. Therefore, by modifying the defect transition level, a thermoelectric material with a given operational temperature can be designed. The authors thankfully acknowledge support from ADA under NpMASS.

  15. Derivation methods for clearance levels applied to reactors

    International Nuclear Information System (INIS)

    Okoshi, Minoru; Seki, Takeo

    2001-01-01

    In order to support the discussion by the Nuclear Safety Commission, JAERI derived the unconditional clearance levels for concrete and metal arising from the operation and dismantling of nuclear reactors. The clearance levels of 20 radionuclides were derived from 10 μSv/y of individual doses by deterministic approach. In this approach, calculation models were established to assess individual doses resulting from 73 exposure pathways related to disposal and recycle/reuse, and realistic parameter values were selected considering Japanese natural and social conditions. The appropriateness of selected parameter values was confirmed by stochastic analyses. (author)

  16. Evaluation of decontamination during dismantling of plutonium-contaminated glove boxes

    International Nuclear Information System (INIS)

    Kinugasa, Manabu; Taguchi, Seigi; Ohzeki, Satoru; Inoue, Yoshiaki; Kashima, Sadamitsu

    1981-01-01

    The dismantling work of plutonium-contaminated glove boxes was carried out. These glove boxes had been used for the R and D of plutonium-uranium mixed oxide fuel for 15 years. The work was carried out in a pressure-controlled greenhouse, and the contamination of air in the greenhouse was monitored continuously. In order to reduce the contamination of air during dismantling, the decontamination and fixation of loose contaminants on the surfaces of glove boxes were very important. The correlation between decontamination and the contamination of air regarding dismantling is reported in this paper. The surface contamination density of the glove boxes was measured utilizing the smear method before and after the decontamination, and the decontamination effects were estimated. The contamination of air during dismantling was continuously measured with a plutonium dust monitor. It was found that loose contamination exponentially decreased by the decontamination process. When the so-called wet glove boxes, which contained wet recovery and waste disposal apparatus, were dismantled, the contamination of air did not exceed 500 (MPC) a. However, the contamination of air exceeded 500 (MPC) a several times in the present work of dismantling the so-called dry glove boxes which had been used for the fabrication of plutonium-uranium mixed oxide pellets. (Kato, T.)

  17. DIRECT DISMANTLING OF REPROCESSING PLANT CELLS THE EUREX PLANT EXPERIENCEe2d12c

    International Nuclear Information System (INIS)

    Gili, M.; Troiani, F.; Risoluti, P.

    2003-01-01

    After finishing the reprocessing campaigns in 1970-1983, the EUREX pilot reprocessing plant of ENEA Saluggia Research Center started into a new phase, aiming to materials and irradiated fuel systemation and radioactive wastes conditioning. In 1997 the project ''CORA'' for a vitrification plant for the high and intermediate liquid radioactive wastes started. The ''CORA'' plant will be hosted in some dismantled cells of the EUREX plant, reusing many of the EUREX plant auxiliary systems, duly refurbished, saving money and construction time and avoiding a new nuclear building in the site. Two of the cells that will be reused were part of the EUREX chemical process (solvent recovery and 2nd extraction cycle) and the components were obviously internally contaminated. In 2000 the direct (hands-on) dismantling of one of them started and has been completed in summer 2002; the second one will be dismantled in the next year and then the ''CORA'' plant will be assembled inside the cells. Special care w as taken to avoid spread of contamination in the cells, where ''CORA'' installation activities will start in the next years, during the dismantling process The analysis of data and results collected during the dismantling of the first cell shows that direct dismantling can be achieved with careful choice of tools, procedures and techniques, to reduce volumes of wastes to be disposed and radiological burden

  18. The Blue Lady Case and the International Issue of Ship Dismantling - Comment

    Directory of Open Access Journals (Sweden)

    Florent Pelsy

    2008-09-01

    Full Text Available This paper focuses on the decision of the Supreme Court of India to allow the dismantling of the Blue Lady (ex France in Alang. The first part underlines that the Supreme Court of India is prioritising the commercial interest of the dismantling companies over the social and environmental concerns of the workers and the communities living in Alang. It argues that such decision goes against its 2003 judgement on ship-dismantling. It then demonstrates that the Supreme Court of India is distorting the concept of sustainable development. The second part analyses the Blue Lady case from an international perspective since most of the ships that are dismantled in India come from developed countries. It provides an overview of the Basel Convention on ship dismantling issues and a study of the Clemenceau case before the French Conseil d'Etat. It then concludes that a better control of end-of-life ships in OECD countries and a new international convention on ship-dismantling would be necessary in order to prevent environmental and social disasters in Alang.

  19. Plutonium active operation of the Winfrith modular containment system

    International Nuclear Information System (INIS)

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

    1985-01-01

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

  20. Nitrous oxide levels in operating and recovery rooms of Iranian hospitals.

    Science.gov (United States)

    Maroufi, Sh Sadigh; Gharavi, Mj; Behnam, M; Samadikuchaksaraei, A

    2011-01-01

    Nitrous oxide (N(2)O) is the oldest anesthetic in routine clinical use and its occupational exposure is under regulation by many countries. As studies are lacking to demonstrate the status of nitrous oxide levels in operating and recovery rooms of Iranian hospitals, we aimed to study its level in teaching hospitals of Tehran University of Medical Sciences. During a 6-month period, we have measured the shift-long time weighted average concentration of N(2)O in 43 operating and 12 recovery rooms of teaching hospitals of Tehran University of Medical Sciences. The results show that the level of nitrous oxide in all hospitals is higher than the limits set by different countries and anesthetists are at higher risk of exposure. In addition, it was shown that installation of air ventilation could reduce not only the overall exposure level, but also the level of exposure of anesthetists in comparison with other personnel. The high nitrous oxide level in Iranian hospitals necessitates improvement of waste gas evacuation systems and regular monitoring to bring the concentration of this gas into the safe level.

  1. Gaukang and White Coup: Dismantling of Traditional Power

    Directory of Open Access Journals (Sweden)

    Nila Sastrawati

    2017-12-01

    Full Text Available This paper discusses the concept of power adhered to by the South Sulawesi community and explains the power struggle which had occurred both in the past and present. The South Sulawesi community’s conceptiontraditional power on power signifies a strong, transcendental relationship between themselves and supernatural powers, wherein all objects possessing certain peculiarities are inseparable from the stable and unchanging cosmic world. Thus, gaukang holds a significant position in the life of the South Sulawesi community, particularly pertaining to matters of power struggle. The waxing and waning of traditional power in South Sulawesi is determined by at least three factors: firstly, a change in power patterns with the emergence of new elites having a commoner background; secondly, incessant resistance to feudalistic rule; and lastly, the application of modern bureaucratic model. The general conclusion of this paper emphasizes the position of gaukang as a central point affecting the various power struggles that occurred throughout the history of the South Sulawesi community. The enactment of Regional Regulation (Perda No. 5 year 2016 on the Organization of Gowa Regency Local Cultural and Customary Institution provides a peek at how bureaucratic power had dismantled traditional power in Gowa Regency, which included, consequently, the transfer of authority over the royal heirlooms or gaukang of the Gowa Kingdom.

  2. From dismantling to current scenario in Galician mano commun mountains

    Directory of Open Access Journals (Sweden)

    Francisco García Quiroga

    2013-03-01

    Full Text Available Common mountains are, like seeds, folklore or free software, good examples of commons. They all count on a community to autonomously manage a good in a collaborative manner by establishing rules to guarantee its sustainability. Common mountains in Galicia represent a property modality and goods management breaking the classic dichotomy of pubic against private, by introducing a collective property alternative. The specificity of these mountains is determined by the fact that the holders of the property right are the regular inhabitants of the land; besides, it is important to stress how these communities have been able to create the rules to guarantee the sustainability of this good. Despite the inherent importance of this modality of commons, a process of dismantling has taken place for a long time with the goal of privatizing these goals. This process was reflected in the shortening of the area of these 18.000 mountains from between 1.8 and 2 millions of hectares in Galicia to the current 640.000 hectares. With the analysis of the commons we can understand how communities can assume co responsibility in the sustainability of goods and how this modality is perfectly viable. The study of these goods brings us closer to the idea of new models in social relations and mutual support networks are possible.

  3. Dismantling method for reactor pressure vessel and system therefor

    International Nuclear Information System (INIS)

    Hayashi, Makoto; Enomoto, Kunio; Kurosawa, Koichi; Saito, Hideyo.

    1994-01-01

    Upon dismantling of a reactor pressure vessel, a containment building made of concretes is disposed underground and a spent pressure vessel is contained therein, and incore structures are contained in the spent pressure vessel. Further, a plasma-welder and a pressing machine are disposed to a pool for provisionally placing reactor equipments in the reactor building for devoluming the incore structures by welding and compression. An overhead-running crane and rails therefor are disposed on the roof and the outer side of the reactor building for transporting the pressure vessel from the reactor building to the containment building. They may be contained in the containment building after incorporation of the incore structures into the pressure vessel at the outside of the reactor building. For the devoluming treatment, a combination of cutting, welding, pressing and the like are optically conducted. A nuclear power plant can be installed by using a newly manufactured nuclear reactor, with no requirement for a new site and it is unnecessary to provide a new radioactive waste containing facility. (N.H.)

  4. Management of wastes from dismantled nuclear power plants

    International Nuclear Information System (INIS)

    1979-01-01

    The problems associated with the management of radioactive wastes encountered in the dismantling of a 1200MWe PWR reactor are considered. It is possible to extend all the conclusions reached in these studies to BWR's or other reactors of the same type using light water as a coolant and moderator. The studies performed established the specific characteristics of these wastes: a gamma activity due essentially to 60 Co (after some fifty years this radioisotope will have decayed sufficiently to enable it to be stored without shielding); the presence of 63 Ni and 59 Ni (these long half-life beta emitting radioisotopes need to be stored over a long or even indefinite period of time); contaminated components (60% of the overall wastes), the reselling of these components involving costly decontamination processes. Extensive studies have been conducted on the management and handling of these wastes: packaging, transport, processing, storage and a great many techniques have been developed. However, further developments in concentration methods (fusion, crushing, cryogenics etc) and the selection of storage sites for this type of waste are necessary. Depending on the solutions chosen, the global cost of the wastes coming from a 1200 MW PWR reactor can vary between 10 and 20 million BFR

  5. A three-level support method for smooth switching of the micro-grid operation model

    Science.gov (United States)

    Zong, Yuanyang; Gong, Dongliang; Zhang, Jianzhou; Liu, Bin; Wang, Yun

    2018-01-01

    Smooth switching of micro-grid between the grid-connected operation mode and off-grid operation mode is one of the key technologies to ensure it runs flexible and efficiently. The basic control strategy and the switching principle of micro-grid are analyzed in this paper. The reasons for the fluctuations of the voltage and the frequency in the switching process are analyzed from views of power balance and control strategy, and the operation mode switching strategy has been improved targeted. From the three aspects of controller’s current inner loop reference signal, voltage outer loop control strategy optimization and micro-grid energy balance management, a three-level security strategy for smooth switching of micro-grid operation mode is proposed. From the three aspects of controller’s current inner loop reference signal tracking, voltage outer loop control strategy optimization and micro-grid energy balance management, a three-level strategy for smooth switching of micro-grid operation mode is proposed. At last, it is proved by simulation that the proposed control strategy can make the switching process smooth and stable, the fluctuation problem of the voltage and frequency has been effectively improved.

  6. Level 1 shutdown and low power operation of Mochovce NPP, Unit 1, Slovakia

    International Nuclear Information System (INIS)

    Halada, P.; Cillik, I.; Stojka, T.; Kuzma, M.; Prochaska, J.; Vrtik, L.

    2004-01-01

    The paper presents general approach, used methods and form of documentation of the results that have been applied within the shutdown and low power PSA (SPSA) study for Mochovce NPP, Unit 1, Slovakia. The SPSA project was realized by VUJE Trnava Inc., Slovakia in 2001-2002 years. The Level 1 SPSA study for Mochovce NPP Unit 1 covers internal events as well as internal (fires, floods and heavy load drop) and external (aircraft crash, extreme meteorological conditions, seismic event and influence of surrounding industry) hazards. Mochovce NPP consists of two operating units equipped with VVER 440/V213 reactors safety upgraded before construction finishing and operation start. 87 safety measures based on VVER 440 operational experience and international mission insights were implemented to enhance its operational and nuclear safety. The SPSA relates to full power PSA (FPSA) as a continuation of the effort to create a harmonized level 1 PSA model for all operational modes of the plant with the goal to use it for further purposes as follows: Real Time Risk Monitor, Maintenance Optimization, Technical Specifications Optimization, Living PSA. (author)

  7. Cernavoda NPP Unit 1: Operating experience program and plant specific performance indicators (level 2)

    International Nuclear Information System (INIS)

    Teodor, Vasile; Popa, Viorel

    1998-01-01

    The basis for the Operating Experience Program was set in place since early stages of the commissioning phase (1993), when a system based on the Canadian approach was implemented for reporting, reviewing, assessing and establishing of the necessary corrective action for unplanned events. This system provided excellent opportunity to train staff in unplanned event assessment methodology, and prepare the station for the formal reporting process following criticality in accordance with the licensing requirements. The formal process, set in place after criticality is described in Station Instruction Procedure SI-01365-P13 'Unplanned Event Report' and was developed under the supervision of Safety and Compliance Department. In parallel, a program for information exchange and trending of performance indicators was developed by Technical Services Department. The WANO recommendations following August 1997 Peer Review provided the opportunity for a better understanding and reconsideration of the Operating Experience Program. As a result, all the activities related to this topic were assigned to a new structure, within Safety and Compliance Department. As such an Operating Experience Group was created and a new program is now being developed in an integrated and centralized manner. The content of the paper is the following: - Overview; - Operating Experience Program; - Event Analysis (Unplanned Events Assessment System - UEIR Process- and Systematic Analysis of Operational Events - ACR Process); - Information Exchange Program; - Monitoring of Operating Experience - Plant Specific Performance Indicators; - Purpose; - Level 2 Performance Indicators. Four appendices are added containing: - A. Station performance indicators/targets (Level 2); - B. SPI (Station Performance Indicators - Level 2) - Graphics; - C. UEIR, LRS (Safety and Licensing Review Sheet), UEFR (Unplanned Event Follow-up Report), ACR and OPEX forms. (authors)

  8. Developing operating procedures for a low-level radioactive waste disposal facility

    International Nuclear Information System (INIS)

    Sutherland, A.A.; Miner, G.L.; Grahn, K.F.; Pollard, C.G.

    1993-10-01

    This document is intended to assist persons who are developing operating and emergency procedures for a low-level radioactive waste disposal facility. It provides 25 procedures that are considered to be relatively independent of the characteristics of a disposal facility site, the facility design, and operations at the facility. These generic procedures should form a good starting point for final procedures on their subjects for the disposal facility. In addition, this document provides 55 annotated outlines of other procedures that are common to disposal facilities. The annotated outlines are meant as checklists to assist the developer of new procedures

  9. Developing operating procedures for a low-level radioactive waste disposal facility

    Energy Technology Data Exchange (ETDEWEB)

    Sutherland, A.A.; Miner, G.L.; Grahn, K.F.; Pollard, C.G. [Rogers and Associates Engineering Corp., Salt Lake City, UT (United States)

    1993-10-01

    This document is intended to assist persons who are developing operating and emergency procedures for a low-level radioactive waste disposal facility. It provides 25 procedures that are considered to be relatively independent of the characteristics of a disposal facility site, the facility design, and operations at the facility. These generic procedures should form a good starting point for final procedures on their subjects for the disposal facility. In addition, this document provides 55 annotated outlines of other procedures that are common to disposal facilities. The annotated outlines are meant as checklists to assist the developer of new procedures.

  10. Noise levels of a track-laying tractor during field operations in the vineyard

    Directory of Open Access Journals (Sweden)

    Pietro Catania

    2013-09-01

    Full Text Available Noise in agriculture is one of the risk factors to be taken into account in the assessment of the health and safety of workers; in particular, it is known that the tractor is a source of high noise. The Italian Low Decree 81/2008 defined the requirements for assessing and managing noise risk identifying a number of procedures to be adopted at different noise levels to limit workers exposure. This paper concerns the analysis of the noise risk arising from the use of a tracklaying tractor during field operations carried out in the vineyard. The objective of this study was to evaluate the noise level that comes close to the ear of the operator driving the tractor measuring the values of equivalent sound level (Leq(A and peak sound pressure (LCpk. We considered four options related to the same tractor coupled with the following tools to perform some farming operations: rototilling, chisel plough, flail mowers and vibro farmer. We considered three test conditions: T1 in flat (slope 0%, T2 uphill and T3 downhill (both 30% slope. The instrument used for the measurements is a precision integrating portable sound level meter, class 1, model HD2110L by Delta OHM, Italy. Each survey lasted 2 minutes, with an interval of measurement equal to 0.5 s. The tests were performed in compliance with the standards ISO 9612 and ISO 9432. The results show that the measured sound levels exceed the limits allowed by the regulations in almost all the test conditions; values exceeding the threshold limit of 80 dB(A were recorded coming up to a maximum value of 92.8 dB(A for flail mowers in test T1. When limits imposed by the regulations are exceeded, the operator is obliged to wear the appropriate Personal Protective Equipment.

  11. The management of intermediate-level radioactive wastes arising from reprocessing operations

    International Nuclear Information System (INIS)

    Elsden, A.D.

    1984-01-01

    The reprocessing of spent nuclear fuel results in the generation of radioactive wastes in the form of liquids, gases and solids. This paper outlines the principles and major elements of the waste management systems currently in use or under development for the category of waste known as intermediate-level wastes. To enable implementation of an optimized waste management system, engineering process evaluations, development and design in the following areas are required: The definition of cost effective options taking account of constraints which may arise from other operations in the overall system, e.g. from transport requirements or from criteria derived from environmental impact assessments of alternative disposal routes; Plant and equipment development to enable acceptable system and active plant operations on an industrial scale; Safety and reliability studies to ensure adequate protection of both the general public and plant operators during all stages of the waste management system including disposal

  12. Operator interface for the PEP-II low level RF control system

    International Nuclear Information System (INIS)

    Allison, S.; Claus, R.

    1997-05-01

    This paper focuses on the operational aspects of the low level RF control system being built for the PEP-II storage rings at SLAC. Subsystems requiring major operational considerations include displays for monitor and control from UNIX workstations, slow feedback loops and control sequences residing on microprocessors, and various client applications in the existing SLAC Linear Collider (SLC) control system. Since commissioning of PEP-II RF is currently in-progress, only those parts of the control system used during this phase are discussed in detail. Based on past experience with the SLC control system, it is expected that effort expended during commissioning on a solid user interface will result in smoother transition to full reliable 24-hour-a-day operation

  13. Operating experience during high-level waste vitrification at the West Valley Demonstration Project

    International Nuclear Information System (INIS)

    Valenti, P.J.; Elliott, D.I.

    1999-01-01

    This report provides a summary of operational experiences, component and system performance, and lessons learned associated with the operation of the Vitrification Facility (VF) at the West Valley Demonstration Project (WVDP). The VF was designed to convert stored high-level radioactive waste (HLW) into a stable waste form (borosilicate glass) suitable for disposal in a federal repository. Following successful completion on nonradioactive test, HLW processing began in July 1995. Completion of Phase 1 of HLW processing was reached on 10 June 1998 and represented the processing of 9.32 million curies of cesium-137 (Cs-137) and strontium-90 (Sr-90) to fill 211 canisters with over 436,000 kilograms of glass. With approximately 85% of the total estimated curie content removed from underground waste storage tanks during Phase 1, subsequent operations will focus on removal of tank heel wastes

  14. CVISN operational and architectural compatibility handbook (COACH). Part 1, Operational concept and top-level design checklists

    Science.gov (United States)

    1999-04-22

    The CVISN Operational and Architectural Compatibility Handbook (COACH) provides a comprehensive checklist of what is required to conform with the Commercial Vehicle Information Systems and Networks (CVISN) operational concepts and architecture. It is...

  15. Proceedings of the workshop on transite decontamination dismantlement and recycle/disposal

    International Nuclear Information System (INIS)

    1993-01-01

    On February 3--4, 1993, a workshop was conducted to examine issues associated with the decontamination, dismantlement, and recycle/disposal of transite located at the US Department of Energy Fernald site near Cincinnati, OH. The Fernald Environmental Management Project (FEMP) is a Superfund Site currently undergoing remediation. A major objective of the workshop was to assess the state-of-the-art of transite remediation, and generate concepts that could be useful to the Fernald Environmental Restoration Management Co. (FERMCO) for remediation of transite. Transite is a building material consisting of asbestos fiber and cement and may be radioactively contaminated as a result of past uranium processing operations at the FEMP. Many of the 100 buildings within the former uranium production area were constructed of transite siding and roofing and consequently, over 180,000 m 2 of transite must be disposed or recycled. Thirty-six participants representing industry, academia, and government institutions such as the EPA and DOE assembled at the workshop to present their experience with transite, describe work in progress, and address the issues involved in remediating transite

  16. Study of large size fiber reinforced cement containers for solid wastes from dismantling

    International Nuclear Information System (INIS)

    Jaouen, C.

    1990-01-01

    The production of large-sized metallic waste by dismantling operations, and the evolution of the specifications of the waste to be stored in the different European countries will create a need for large standard containers for the transport and final disposal of the corresponding waste. The research conducted during the 1984-1988 programme, supported by the Commission of European Communities, and based on a comparative study of high-grade concrete materials, reinforced with organic or metallic fibres, led to the development of a high performance container meeting international transport recommendations as well as French requirements for shallow-ground disposal. The material selected, consisting of high-performance mortar with metal fibre reinforcement, was the subject of an intensive programme of characterization tests conducted in close cooperation with LAFARGE Company, demonstrating the achievement of mechanical and physical properties comfortably above the regulatory requirements. The construction of an industrial prototype and the subsequent economic analysis served to guarantee the industrial feasibility and cost of this system, in which attempts were made to optimize the finished package product, including its closure system

  17. Expanding to teleoperation of a tight modular workshop for dismantling radioactive components

    International Nuclear Information System (INIS)

    Gasc, B.

    1990-01-01

    The CEA (French Nuclear Energy Commission) in connection with TECHNICATOME developed a tight modular workshop for the dismantling of AT1 plant facilities in LA HAGUE. This workshop constructed of reusable stainless steel panels assembled by bolting provides a tight and decontaminable working zone compatible with any building configuration. This being the case, the operators bearing ventilated suits may work under the best safety conditions on alpha-contaminated materials. For the purpose of expanding the working capacities of this workshop it was decided to develop special components for teleoperation from the outside as in a conventional cell. To meet this objective which is within the scope of the contract signed with the CEC, the following components were developed and constructed: - manipulator holder panel, - swivelling hatch panel, - wall equipment sealed transfer device and, - modular biological protection. The design, construction and tests of these new components led to their qualification and further incorporation in the list of components of the modular workshop liable to be used for teleoperation procedures

  18. Operation and management plan of Rokkasho Low Level Radioactive Waste Disposal Center

    Energy Technology Data Exchange (ETDEWEB)

    Nakanishi, Z.; Tomozawa, T.; Mahara, Y.; Iimura, H. [Japan Nuclear Fuel Ltd., Tokyo (Japan). Radioactive Waste Management Dept.

    1993-12-31

    Japan Nuclear Fuel Limited (JNFL) started the operation of the Rokkasho Low-Level Radioactive Waste Disposal Center in December, 1992. This center is located at Rokkasho Village in Aomori Prefecture. The facility in this center will provide for the disposal of 40,000 m{sup 3} of the low-level radioactive waste (LLW) produced from domestic nuclear power stations. The facility will receive between 5,000 m{sup 3} and 10,000 m{sup 3} of waste every year. Strict and efficient institutional controls, such as the monitoring of the environment and management of the site, is required for about 300 years. This paper provides an outline of the LLW burial operation and management program at the disposal facility. The facility is located 14--19 meters below the ground surface in the hollowed out Takahoko Formation.

  19. Operation and management plan of Rokkasho Low Level Radioactive Waste Disposal Center

    International Nuclear Information System (INIS)

    Nakanishi, Z.; Tomozawa, T.; Mahara, Y.; Iimura, H.

    1993-01-01

    Japan Nuclear Fuel Limited (JNFL) started the operation of the Rokkasho Low-Level Radioactive Waste Disposal Center in December, 1992. This center is located at Rokkasho Village in Aomori Prefecture. The facility in this center will provide for the disposal of 40,000 m 3 of the low-level radioactive waste (LLW) produced from domestic nuclear power stations. The facility will receive between 5,000 m 3 and 10,000 m 3 of waste every year. Strict and efficient institutional controls, such as the monitoring of the environment and management of the site, is required for about 300 years. This paper provides an outline of the LLW burial operation and management program at the disposal facility. The facility is located 14--19 meters below the ground surface in the hollowed out Takahoko Formation

  20. Evaluation of scheduling problems for the project planning of large-scale projects using the example of nuclear facility dismantling; Evaluation von Schedulingproblemen fuer die Projektplanung von Grossprojekten am Beispiel des kerntechnischen Rueckbaus

    Energy Technology Data Exchange (ETDEWEB)

    Huebner, Felix; Schellenbaum, Uli; Stuerck, Christian; Gerhards, Patrick; Schultmann, Frank

    2017-05-15

    The magnitude of widespread nuclear decommissioning and dismantling, regarding deconstruction costs and project duration, exceeds even most of the prominent large-scale projects. The deconstruction costs of one reactor are estimated at several hundred million Euros and the dismantling period for more than a decade. The nuclear power plants built in the 1970s are coming closer to the end of their planned operating lifespan. Therefore, the decommissioning and dismantling of nuclear facilities, which is posing a multitude of challenges to planning and implementation, is becoming more and more relevant. This study describes planning methods for large-scale projects. The goal of this paper is to formulate a project planning problem that appropriately copes with the specific challenges of nuclear deconstruction projects. For this purpose, the requirements for appropriate scheduling methods are presented. Furthermore, a variety of possible scheduling problems are introduced and compared by their specifications and their behaviour. A set of particular scheduling problems including possible extensions and generalisations is assessed in detail. Based on the introduced problems and extensions, a Multi-mode Resource Investment Problem with Tardiness Penalty is chosen to fit the requirements of nuclear facility dismantling. This scheduling problem is then customised and adjusted according to the specific challenges of nuclear deconstruction projects. It can be called a Multi-mode Resource Investment Problem under the consideration of generalized precedence constraints and post-operational costs.

  1. Six-year experiences in the operation of a low level liquid waste treatment plant

    International Nuclear Information System (INIS)

    Wen, S.-J.; Hwang, S.-L.; Tsai, C.-M.

    1980-01-01

    The operation of a low level liquid waste treatment plant is described. The plant is designed for the disposal of liquid waste produced primarily by a 40 MW Taiwan Research Reactor as well as a fuel fabrication plant for the CANDU type reactor and a radioisotopes production laboratory. The monthly volume treated is about 600-2500 ton of low level liquid waste. The activity levels are in the range of 10 -5 -10 -3 μCi/cm 3 . The continuous treatment system of the low level liquid waste treatment plant and the treatment data collected since 1973 are discussed. The advantages and disadvantages of continuous and batch processes are compared. In the continuous process, the efficiency of sludge treatment, vermiculite ion exchange and the adsorption of peat are investigated for further improvement. (H.K.)

  2. Mass Communication, Advertising, and Marketing Research at the Strategic and Operational Levels of War

    Science.gov (United States)

    2013-05-05

    EBSCOhost (accessed November 4, 2012): 157. 43 Ibid., 156. 44 Ibid., 163. 45 Chang, Chun-Tuan. 2011. “Guilt appeals in cause-related marketing ...Mass Communication, Advertising, and Marketing Research at the Strategic and Operational Levels of War by Colonel Ralph...Education of the Middle States Association of Colleges and Schools, 3624 Market Street, Philadelphia, PA 19104, (215) 662-5606. The Commission on

  3. Design and operation of a low-level solid-waste disposal site at Los Alamos

    International Nuclear Information System (INIS)

    Balo, K.A.; Wilson, N.E.; Warren, J.L.

    1982-01-01

    Since the mid-1940's, approximately 185000 m 3 of low-level and transuranic radioactive solid waste, generated in operations at the Los Alamos National Laboratory, have been disposed of by on-site shallow land burial. Procedures and facilities have been designed and evaluated in the areas of waste acceptance, treatment and storage, disposal, traffic control, and support systems. The methodologies assuring the proper management and disposal of radioactive solid waste are summarized

  4. Design and Assessment of an Associate Degree-Level Plant Operations Technical Education Program

    Science.gov (United States)

    Selwitz, Jason Lawrence

    Research was undertaken to develop and evaluate an associate degree-level technical education program in Plant Operations oriented towards training students in applied science, technology, engineering, and mathematics (STEM) skills and knowledge relevant to a spectrum of processing industries. This work focuses on four aspects of the curriculum and course development and evaluation research. First, the context of, and impetus for, what was formerly called vocational education, now referred to as technical or workforce education, is provided. Second, the research that was undertaken to design and evaluate an associate degree-level STEM workforce education program is described. Third, the adaptation of a student self-assessment of learning gains instrument is reviewed, and an analysis of the resulting data using an adapted logic model is provided, to evaluate the extent to which instructional approaches, in two process control/improvement-focused courses, were effective in meeting course-level intended learning outcomes. Finally, eight integrative multiscale exercises were designed from two example process systems, wastewater treatment and fast pyrolysis. The integrative exercises are intended for use as tools to accelerate the formation of an operator-technician's multiscale vision of systems, unit operations, underlying processes, and fundamental reactions relevant to multiple industries. Community and technical colleges serve a vital function in STEM education by training workers for medium- and high-skilled technical careers and providing employers the labor necessary to operate and maintain thriving business ventures. Through development of the curricular, course, and assessment-related instruments and tools, this research helps ensure associate degree-level technical education programs can engage in a continual process of program evaluation and improvement.

  5. [Influence of different lighting levels at workstations with video display terminals on operators' work efficiency].

    Science.gov (United States)

    Janosik, Elzbieta; Grzesik, Jan

    2003-01-01

    The aim of this work was to evaluate the influence of different lighting levels at workstations with video display terminals (VDTs) on the course of the operators' visual work, and to determine the optimal levels of lighting at VDT workstations. For two kinds of job (entry of figures from a typescript and edition of the text displayed on the screen), the work capacity, the degree of the visual strain and the operators' subjective symptoms were determined for four lighting levels (200, 300, 500 and 750 lx). It was found that the work at VDT workstations may overload the visual system and cause eyes complaints as well as the reduction of accommodation or convergence strength. It was also noted that the edition of the text displayed on the screen is more burdening for operators than the entry of figures from a typescript. Moreover, the examination results showed that the lighting at VDT workstations should be higher than 200 lx and that 300 lx makes the work conditions most comfortable during the entry of figures from a typescript, and 500 lx during the edition of the text displayed on the screen.

  6. Deterministic Assessment of Future Costs for Dismantling (FA)

    Energy Technology Data Exchange (ETDEWEB)

    Vasko, Marek [DECOM, Trnava (Slovakia)

    2012-11-01

    The main objective of the report is to provide an re-evaluation of cost calculations by OMEGA code for the Intermediate Storage for Spent Fuel in Studsvik (FA facility) using up-to-date Swedish labour cost unit factors and available up-to-date Swedish (or international) cost unit factors for consumables, materials and substances. Furthermore, evolution of other OMEGA database parameters concerning cost calculations e.g. manpower unit factors and workgroups parameters are taken into account. This report follows up former project which introduced tentative calculations of main decommissioning parameters such as costs, manpower and exposure of personnel for activities of older nuclear facility decommissioning in Sweden represented by FA Facility in Studsvik by means of calculation code OMEGA. The project demonstrated an implementation of advanced costing methodology based on PSL structure format to achieve transparent, traceable and comparable estimates even for older nuclear facilities like FA Facility in Studsvik. This former project used Slovak origin labour costs unit factors and other cost unit factors. After successful completion of this project, there was an intent of SSM to reevaluate calculations using an up-to-date Swedish labour cost data and also available Swedish consumables and materials cost data if available. Within this report re-calculations of main decommissioning parameters using available Swedish data are presented in structure according to Proposed Standardized List of Items for Costing Purposes. Calculations are made for decommissioning scenario with post-dismantling decontamination and steel radwaste melting technologies available at the site. All parameters are documented and summed up in both table and graphic forms in text and Annexes. Further, comparison of calculated results with previous calculations together with discussion is provided.

  7. Deterministic Assessment of Future Costs for Dismantling (FA)

    International Nuclear Information System (INIS)

    Vasko, Marek

    2012-03-01

    The main objective of the report is to provide an re-evaluation of cost calculations by OMEGA code for the Intermediate Storage for Spent Fuel in Studsvik (FA facility) using up-to-date Swedish labour cost unit factors and available up-to-date Swedish (or international) cost unit factors for consumables, materials and substances. Furthermore, evolution of other OMEGA database parameters concerning cost calculations e.g. manpower unit factors and workgroups parameters are taken into account. This report follows up former project which introduced tentative calculations of main decommissioning parameters such as costs, manpower and exposure of personnel for activities of older nuclear facility decommissioning in Sweden represented by FA Facility in Studsvik by means of calculation code OMEGA. The project demonstrated an implementation of advanced costing methodology based on PSL structure format to achieve transparent, traceable and comparable estimates even for older nuclear facilities like FA Facility in Studsvik. This former project used Slovak origin labour costs unit factors and other cost unit factors. After successful completion of this project, there was an intent of SSM to reevaluate calculations using an up-to-date Swedish labour cost data and also available Swedish consumables and materials cost data if available. Within this report re-calculations of main decommissioning parameters using available Swedish data are presented in structure according to Proposed Standardized List of Items for Costing Purposes. Calculations are made for decommissioning scenario with post-dismantling decontamination and steel radwaste melting technologies available at the site. All parameters are documented and summed up in both table and graphic forms in text and Annexes. Further, comparison of calculated results with previous calculations together with discussion is provided

  8. Recycling of concrete waste generated from nuclear power plant dismantling

    International Nuclear Information System (INIS)

    Ogawa, Hideo; Nagase, Takahiro; Tanaka, Hiroaki; Nawa, Toyoharu

    2012-01-01

    Non-radioactive concrete waste generated from dismantling of a standard large nuclear power plant is estimated to be about 500,000 tons in weight. Using such waste as recycled aggregate within the enclosure of the plant requires a new manufacturing technology that generates a minimal amount of by-product powder. Recycled aggregate has brittle parts with defects such as cracks, pores, and voids in residual paste from original concrete. This study presents a method of selectively removing the defective parts during manufacture to improve the quality of the recycled fine aggregate. With this selective removal method used, the amount of by-product powder can be reduced by half as compared to that by a conventional method. The influences of the characteristics of the recycled fine aggregate on the flowability and strength of the mortar using recycled fine aggregate were evaluated by multiple linear regression analysis. The results clearly showed that the flowability was primarily affected by the filling fraction of recycled fine aggregate, while the compressive strength of mortar was primarily affected by the fraction of defects in the aggregate. It was also found that grains produced by a granulator have more irregularities in the surfaces than those produced by a ball mill, providing an increased mortar strength. Using these findings from this study, efforts are also being made to develop a mechanical technology that enables simultaneous processing of decontamination and recycling. The granulator under consideration is capable of grinding the surfaces of irregularly shaped particles and may be used successfully, under optimal conditions, for the surface decontamination of concrete waste contaminated with radioactive materials. (author)

  9. Improving Interagency Planning and Execution at the Operational Level: Creating a Stability and Reconstruction Component Within a Joint Task Force

    National Research Council Canada - National Science Library

    Dombrowski, Michael P

    2006-01-01

    ...?s attempts at winning the peace. Recent operations in Afghanistan and Iraq illustrate the lack of interagency unity of effort at the operational level and cry out for an enduring solution similar to Goldwater-Nichols...

  10. Preliminary dismantling for the decommissioning of nuclear licensed facilities at the CEA Centre in Fontenay aux Roses

    International Nuclear Information System (INIS)

    Estivie, D.; Bohar, M.P.; Jeanjacques, M.; Binet, C.

    2008-01-01

    Under the perimeter modification programme for the Nuclear Licensed Facilities (NLFs) of the French Atomic Energy Commission centre at Fontenay aux Roses (CEN-FAR), preliminary dismantling work proved necessary to decommission the buildings outside the nuclear perimeter and create interim storage areas for waste packages. This summary describes the dismantling of Buildings 07, 53 and 91/54, which are the most representative of the preliminary dismantling work. (author)

  11. Project Guarantee 1985. Repository for high-level radioactive waste: construction and operation

    International Nuclear Information System (INIS)

    Anon.

    1985-01-01

    An engineering project study aimed at demonstrating the feasibility of constructing a deep repository for high-level waste (Type C repository) has been carried out; the study is based on a model data-set representing typical geological and rock mechanical conditions as found outside the so-called Permocarboniferous basin in the regions under investigation by Nagra in Cantons Aargau, Schaffhausen, Solothurn and Zuerich. The repository is intended for disposal of high-level waste and any intermediate-level waste from re-processing in which the concentration of long-lived alpha-emitters exceeds the permissible limits set for a Type B repository. Final disposal of high-level waste is in subterranean, horizontally mined tunnels and of intermediate-level waste in underground vertical silos. The repository is intended to accomodate a total of around 6'000 HWL-cylinders (gross volume of around 1'200 m3) and around 10'000 m3 of intermediate-level waste. The total excavated volume is around 1'100'000 m3 and a construction time for the whole repository (up to the beginning of emplacement) of around 15 years is expected. For the estimated 50-year emplacement operations, a working team of around 60 people will be needed and a team of around 160 for the simultaneous tunnelling operations and auxiliary work. The project described in the present report permits the conclusion that construction of a repository for high-level radioactive waste and, if necessary, spent fuel-rods is feasible with present-day technology

  12. SYSTEM OF STANDARTIZATION OF CONSTRUCTION OPERATIONS ARRANGEMENT

    Directory of Open Access Journals (Sweden)

    Oleynik Pavel Pavlovich

    2012-10-01

    Full Text Available In the proposed article, management of construction operations is represented as a multi-level system; it is considered with the framework of projects including new construction, restructuring and overhaul of buildings and structures. The system of management of construction operations is to be composed of the following three constituent parts. They include a construction and assembling entity, project and operations, and a procurement base. Such matters as the quality of construction products, purchase (lease of building machinery and vehicles are incorporated into the level of the construction and assembling entity. The project level comprises such components of construction operations management as pre-construction preparation of a project, methods and forms of construction management, preparatory works, management of construction activities, real-time operations control, construction quality control, etc. The level of operations and the procurement base covers the needs for materials and equipment, their purchase and procurement, as well as the warehouse management. The main elements of the standardization system are identified. Standards of construction operations management are explained, including 1. General Provisions; 2. Preparation and performance of construction and assembling works; 3. New construction. Building site organization; 4. Demolition (dismantling of buildings and structures; 5. Rules of preparation for acceptance and commissioning of completed residential buildings. The prospects for the further development of the system of standardization of construction operations management are outlined

  13. Design and operation of high level waste vitrification and storage facilities

    International Nuclear Information System (INIS)

    1992-01-01

    The conversion of high level wastes (HLW) into solids has been studied for the past 30 years, primarily in those countries engaged in the reprocessing of nuclear fuels. Production and demonstration calcination and solidification plants have been operated by using waste solutions from fuels irradiated at various burnup rates, depending on the reactor type. Construction of more advanced solidification processes is now in progress in several countries to permit the handling of high burnup power reactor fuel wastes. The object of this report is to provide detailed information and references for those vitrification systems in advanced stages of implementation. Some less detailed information will be provided for previously developed immobilization systems. The report will examine the HLLW arising from the various locations, the features of each process as well as the stage of development, scale-up potential and flexibility of the processes. Since the publication of IAEA Technical Reports Series No. 176, Techniques for the Solidification of High-Level Wastes great progress on this subject has been made. The AVM in France has been operated successfully for 11 years and France has completed construction at La Hague of two vitrification plants that are based on the AVM rotary calciner/metallic melter process. A similar plant is under construction at Sellafield. The ceramic melter process has been chosen by several countries. Germany has successfully operated the PAMELA vitrification plant. Since 1986, Belgoprocess has continued to operate this facility. The former USSR operated the EP-500 plant from 1986 to 1988. In addition, two ceramic melter vitrification plants are nearing completion in the USA at Savannah River and West Valley and plans are being made to use this technology at Hanford as well as in Japan, Germany and India. This major progress attests to the maturity of these technologies for vitrifying HLLW to make a borosilicate glass for disposal of the waste. 67

  14. Spatially-varying surface roughness and ground-level air quality in an operational dispersion model

    International Nuclear Information System (INIS)

    Barnes, M.J.; Brade, T.K.; MacKenzie, A.R.; Whyatt, J.D.; Carruthers, D.J.; Stocker, J.; Cai, X.; Hewitt, C.N.

    2014-01-01

    Urban form controls the overall aerodynamic roughness of a city, and hence plays a significant role in how air flow interacts with the urban landscape. This paper reports improved model performance resulting from the introduction of variable surface roughness in the operational air-quality model ADMS-Urban (v3.1). We then assess to what extent pollutant concentrations can be reduced solely through local reductions in roughness. The model results suggest that reducing surface roughness in a city centre can increase ground-level pollutant concentrations, both locally in the area of reduced roughness and downwind of that area. The unexpected simulation of increased ground-level pollutant concentrations implies that this type of modelling should be used with caution for urban planning and design studies looking at ventilation of pollution. We expect the results from this study to be relevant for all atmospheric dispersion models with urban-surface parameterisations based on roughness. -- Highlights: • Spatially variable roughness improved performance of an operational model. • Scenario modelling explored effect of reduced roughness on air pollution. • Reducing surface roughness can increase modelled ground-level pollution. • Damped vertical mixing outweighs increased horizontal advection in model study. • Result should hold for any model with a land-surface coupling based on roughness. -- Spatially varying roughness improves model simulations of urban air pollutant dispersion. Reducing roughness does not always decrease ground-level pollution concentrations

  15. Intrahepatic cholangiocarcinoma prognostic determination using pre-operative serum C-reactive protein levels

    International Nuclear Information System (INIS)

    Lin, Zi-Ying; Liang, Zhen-Xing; Zhuang, Pei-Lin; Chen, Jie-Wei; Cao, Yun; Yan, Li-Xu; Yun, Jing-Ping; Xie, Dan; Cai, Mu-Yan

    2016-01-01

    Serum C-reactive protein (CRP), an acute inflammatory response biomarker, has been recognized as an indicator of malignant disease progression. However, the prognostic significance of CRP levels collected before tumor removal in intrahepatic cholangiocarcinoma requires further investigation. We sampled the CRP levels in 140 patients with intrahepatic cholangiocarcinoma who underwent hepatectomies with regional lymphadenectomies between 2006 and 2013. A retrospective analysis of the clinicopathological data was performed. We focused on the impact of serum CRP on the patients’ cancer-specific survival and recurrence-free survival rates. High levels of preoperative serum CRP were significantly associated with well-established clinicopathologic features, including gender, advanced tumor stage, and elevated carcinoembryonic antigen and carbohydrate antigen 19-9 levels (P < 0.05). Univariate analysis demonstrated a significant association between high levels of serum CRP and adverse cancer-specific survival (P = 0.001) and recurrence-free survival (P < 0.001). In patients with stage I/II intrahepatic cholangiocarcinoma, the serum CRP level was a prognostic indicator for cancer-specific survival. In patients with stage I/II or stage III/IV, the serum CRP level was a prognostic indicator for recurrence-free survival (P < 0.05). Additionally, multivariate analysis identified serum CRP level in intrahepatic cholangiocarcinoma as an independent prognostic factor (P < 0.05). We confirmed a significant association of elevated pre-operative CRP levels with poor clinical outcomes for the tested patients with intrahepatic cholangiocarcinoma. Our results indicate that the serum CRP level may represent a useful factor for patient stratification in intrahepatic cholangiocarcinoma management

  16. Expertise of the Oeko-Institute on the application to obtain permission to partially dismantle the Niederaichbach nuclear power plant

    International Nuclear Information System (INIS)

    1985-01-01

    This expertise gives an overview on the problems associated with the decommissioning and dismantling of the Niederaichbach nuclear power plant, considering technical and legal aspects. It wants to prove that the dismantling of this reactor cannot serve as evidence to prove the general feasibility of reactor dismantling. Much space is dedicated to the discussion about where the borderline should be drawn between radioactive and non-radioactive materials according to the ordinance on radiation protection. The reasons for rejecting the partial dismantling application are given. (DG) [de

  17. State of dismantling of reactor facilities (JPDR) in Tokai Research Establishment, Japan Atomic Energy Research Institute (fiscal year 1986)

    International Nuclear Information System (INIS)

    1987-01-01

    As to this dismantling work, the contents of the notice on the dismantling and the policy of administration offices to deal with it were reported to the Nuclear Safety Commission beforehand, and after the approval was obtained, it has been executed. Based on the talk of the chairman of Nuclear Safety Commission on January 6, 1983, the state of dismantling is reported. In fiscal year 1986, the second stage dismantling was begun in December, and it was confirmed that the works were carried out safety. In order to ensure the place required for dismantling and removing in-core structures and the pressure vessel, the pressure vessel upper cover and its heat insulator were removed from the third story of the containment vessel. A part of the facilities installed on the second and third stories of the containment vessel was also dismantled and removed. In order to utilize as the place for the temporary preservation and decontamination of dismantled things, a part of the facilities installed in the dump condenser building was dismantled and removed. The control building was reconstructed for smoothly carrying out the entrance control of workers. 36 spent fuel assemblies were carried away for reprocessing. The exposure dose of workers was below the detectable limit of film badges. The dismantled wastes were about 171 t of metals and 34 t of concrete. (Kako, I.)

  18. Formulation of special glass frit and its use for decontamination of Joule melter employed for vitrification of high level and radioactive liquid waste

    International Nuclear Information System (INIS)

    Valsala, T.P.; Mishra, P.K.; Thakur, D.A.; Ghongane, D.E.; Jayan, R.V.; Dani, U.; Sonavane, M.S.; Kulkarni, Y.

    2012-01-01

    Advanced vitrification system at TWMP Tarapur was used for successful vitrification of large volume of HLW stored in waste tank farm. After completion of the operational life of the joule melter, dismantling was planned. Prior to the dismantling, the hold up inventory of active glass product from the melter was flushed out using specially formulated inactive glass frit to reduce the air activity buildup in the cell during dismantling operations. The properties of the special glass frit prepared are comparable with that of the regular product glass. More than 94% of holdup activity was flushed out from the joule melter prior to the dismantling of the melter. (author)

  19. Decree no. 2005-78 from January 26, 2005, authorizing the Atomic Energy Commission to proceed to the definitive shutdown and dismantling operations of the nuclear facility no.20, named Siloe reactor, in the Grenoble city territory (Isere); Decret no. 2005-78 du 26 janvier 2005, autorisant le Commissariat a l'energie atomique a proceder aux operations de mise a l'arret definitif et de demantelement de l'installation nucleaire de base no.20 denommee reacteur Siloe sur le territoire de la commune de Grenoble (Isere)

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2005-02-15

    On March 19, 2003, the French atomic energy commission (CEA) addressed an authorization demand for the definitive shutdown and dismantling of the Siloe reactor. After a technical and administrative instruction of this demand by the French nuclear safety authority (ASN), a project of decree has been presented on July 6, 2004 at the permanent section of the inter-ministry commission of basic nuclear facilities. The commission gave its favourable judgment which is the object of this decree. (J.S.)

  20. Decree no. 2005-79 from January 26, 2005, authorizing the Atomic Energy Commission to proceed to the definitive shutdown and dismantling operations of the nuclear facility no.21, named Siloette research reactor, in the Grenoble city territory (Isere); Decret no. 2005-79 du 26 janvier 2005, autorisant le Commissariat a l'Energie Atomique a proceder aux operations de mise a l'arret definitif et de demantelement de l'installation nucleaire de base no.21 denommee reacteur de recherche Siloette sur le territoire de la commune de Grenoble (Isere)

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2005-02-15

    On May 26, 2003, the French atomic energy commission (CEA) addressed an authorization demand for the definitive shutdown and dismantling of the Siloette research reactor. After a technical and administrative instruction of this demand by the French nuclear safety authority (ASN), a project of decree has been presented on July 6, 2004 at the permanent section of the inter-ministry commission of basic nuclear facilities. The commission gave its favourable judgment which is the object of this decree. (J.S.)