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Sample records for cadarache dismantling projects

  1. Intensive post operation clean out (Poco) in AREVA NC Cadarache dismantling projects: economic value and sustainable development

    International Nuclear Information System (INIS)

    After fabricating plutonium fuels for 40 years (Fast Breeder Reactor, MOX), commercial operations at the AREVA NC Cadarache plant ended in 2003 and post operation clean out of its production buildings and laboratory started. AREVA objective is to achieve IAEA level 2 cleanup of the process facilities and transfer them to their owner, the French Atomic Energy Commission (CEA). There are two main opposite dismantling scenarios: very limited cleanup to optimize man power, or intensive cleanup of the facilities to optimize the quantity of long lived level waste as much as possible. Economic and environmental considerations lead the choice between these two options. (author)

  2. ITER at Cadarache; ITER a Cadarache

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2005-06-15

    This public information document presents the ITER project (International Thermonuclear Experimental Reactor), the definition of the fusion, the international cooperation and the advantages of the project. It presents also the site of Cadarache, an appropriate scientifical and economical environment. The last part of the documentation recalls the historical aspect of the project and the today mobilization of all partners. (A.L.B.)

  3. 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...

  4. Project management for the decommissioning and dismantling of nuclear facilities

    International Nuclear Information System (INIS)

    The decommissioning of nuclear power plants is executed in a classic project manner as it is known from other construction projects. It is obvious to use the known portfolio of project management tools. The complexity that is created by the large size of the project in combination with safety requirements of the nuclear industry has to be handled. Complexity can only be managed addressing two main drivers: Prioritization and speed (agility) in project execution. Prioritization can be realized by applying tools like Earned Value Management. A high speed of project execution is established by applying Agile Management like SCRUM-methods. This method is adopted in the context of the cooperation ''Complex Projects'' to the needs of nuclear industry.

  5. CULTURAL ISSUES IN FINNISH AND CHINESE PRACTICAL BUSINESS TRANSACTIONS : Case: Varkaus Paper Machine Dismantling Project

    OpenAIRE

    Chen, Yuanyuan

    2012-01-01

    This thesis report is compiled to investigate the cultural issues in modern Finnish and Chinese practical business transactions and aims to figure out some viable suggestions for the business people involved in or thinking about Finnish-Chinese business. In order to do so, business culture theories were carefully studied and a case study, called the Varkaus Dismantling Project, which was an intercultural cooperation between Umacon Oy and Nine Dragons Industries Co., Ltd., was observed. ...

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

    Energy Technology Data Exchange (ETDEWEB)

    Fellhauer, C.R.; Clark, F.R. [Argonne National Lab., IL (United States). Technology Development Div.; Garlock, G.A. [MOTA Corp., Cayce, SC (United States)

    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.

  7. Licensing documentation and licensing process for dismantling and decontamination projects in Lithuania

    Energy Technology Data Exchange (ETDEWEB)

    Uspuras, Eugenijus; Rimkevicius, Sigitas; Babilas, Egidijus [Lithuanian Energy Institute (LEI), Kaunas (Lithuania)

    2013-07-01

    One of the main tasks of any decommissioning project is the licensing process which allows implementation of developed strategies in real NPP. The Lithuanian laws on nuclear energy and on radioactive waste management require that the dismantling and decontamination (D and D) projects shall be licensed by the Lithuanian State Nuclear Power Safety Inspectorate (VATESI) and other Authorities. Licensing is an inseparable part of the Lithuania regulatory and supervisory system for safety of nuclear facilities. The licensing process starts when NPP submits the first licensing document(s) to the Authorities. It is completed when all the licensing documents are approved by the Authorities and authorization to start D and D works is received by NPP. Current paper will discuss one of the main steps in D and D projects implementation process - Licensing and will provide information about D and D licensing approach used in Lithuania. (orig.)

  8. Licensing documentation and licensing process for dismantling and decontamination projects in Lithuania

    International Nuclear Information System (INIS)

    One of the main tasks of any decommissioning project is the licensing process which allows implementation of developed strategies in real NPP. The Lithuanian laws on nuclear energy and on radioactive waste management require that the dismantling and decontamination (D and D) projects shall be licensed by the Lithuanian State Nuclear Power Safety Inspectorate (VATESI) and other Authorities. Licensing is an inseparable part of the Lithuania regulatory and supervisory system for safety of nuclear facilities. The licensing process starts when NPP submits the first licensing document(s) to the Authorities. It is completed when all the licensing documents are approved by the Authorities and authorization to start D and D works is received by NPP. Current paper will discuss one of the main steps in D and D projects implementation process - Licensing and will provide information about D and D licensing approach used in Lithuania. (orig.)

  9. Network dismantling

    CERN Document Server

    Braunstein, Alfredo; Semerjian, Guilhem; Zdeborová, Lenka

    2016-01-01

    We study the problem of network dismantling, that is of finding a minimal set of vertices whose removal leaves the network broken in connected components of sub-extensive size. For a large class of random graphs this problem is tightly connected to the decycling problem (the removal of vertices leaving the graph acyclic). Exploiting this connection and recent works on epidemic spreading we present precise predictions for the minimal size of a dismantling set in a large random graph with a prescribed (light-tailed) degree distribution. Building on the statistical mechanics perspective we propose a three-stage Min-Sum algorithm for efficiently dismantling networks, including heavy-tailed ones for which the dismantling and decycling problems are not equivalent. We also provide insight into the dismantling problem concluding that it is an intrinsically collective problem and optimal dismantling sets cannot be viewed as a collection of individually well performing nodes.

  10. Processing of radioactive effluents in Cadarache research centre

    International Nuclear Information System (INIS)

    French Atomic Energy Commission (Commissariat a l'Energie Atomique - CEA) is studying the design of a new plant for processing liquid aqueous radioactive effluents produced on Cadarache Research Centre. Effluents to be processed are low and medium activity effluents, with, for some of them, important concentrations of actinides, and which lead to the production of A and B category solid wastes, according to the French legislation, and suitable for final disposal. The objectives in terms of minimization of discharge's activity level and solid waste production have guided a selection of processes and their arrangement, in order to optimise decontamination and volume concentration factors. Seeded-ultrafiltration and vitrification with cold crucible melter are part of the selected processes for which developments are in progress in CEA for application to the characteristics of the project. (authors)

  11. Report transparency and nuclear safety 2007 CEA Cadarache; Rapport transparence et securite nucleaire 2007 CEA Cadarache

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2007-07-01

    This report presents the activities of the CEA Center of Cadarache for the year 2007. The actions concerning the safety, the radiation protection, the significant events, the release control and the environmental impacts and the wastes stored on the center are discussed. More especially the report discusses the beginning of the RJH reactor construction, the fourth generation reactors research programs, the implementing of la Rotonde the new radioactive wastes management installation, the renovation of the LECA. (A.L.B.)

  12. TJ-II operation tracking from Cadarache

    International Nuclear Information System (INIS)

    The TJ-II remote participation system was designed to follow the TJ-II discharge production, even allowing the physicist in charge of operation to be in a remote location. The system has been based on both web servers and Java technology. These elements were chosen due to its open character, security properties, platform independence and technological maturity. Web pages and Java applications permit users to access experimental systems, data servers and the operation logbook. Security resources are provided by the PAPI system, a distributed authentication and authorization system. The TJ-II remote participation tools have allowed us to command and follow the stellarator operation from Cadarache. Over 1,000 digitizer channels and more than 20 diagnostic control systems were remotely available from web pages for monitoring/programming purposes. One Java application provided on-line information about the acquisition status of channels and acquisition cards. A second Java application showed temporal evolution signals that were refreshed in an automated way on the screen after each shot. A third Java application provided access to the operation logbook. In addition to these tools, we used the VRVS video conferencing system (FUSION community, X-Point room) and the EFDA Messenger Service for instant messaging (Jabber client). (Author)

  13. TJ-II operation tracking from Cadarache

    International Nuclear Information System (INIS)

    The TJ-II remote participation system was designed to follow the TJ-II discharge production, even allowing the physicist in charge of operation to be in a remote location. The system has been based on both web servers and Java technology. These elements were chosen due to its open character, security properties, platform independency and technological maturity. Web pages and Java applications permit users to access experimental systems, data servers and the operation logbook. Security resources are provided by the PAPI system, a distributed authentication and authorization system. The TJ-II remote participation tools have allowed us to command and follow the stellarator operation from Cadarache. Over 1,000 digitizer channels and more than 20 diagnostic control systems were remotely available from web pages for monitoring/programming purposes. One Java application provided on-line information about the acquisition status of channels and acquisition cards. A second Java application showed temporal evolution signals that were refreshed in an automated way on the screen after each shot. A third Java application provided access to the operation logbook. In addition to these tools, we used the VRVS videoconferencing system (FUSION community, X-Point room) and the EFDA Messenger Service for instant messaging (Jabber client). (author)

  14. Robots in dismantling

    International Nuclear Information System (INIS)

    Because of personnel radiologic hazards, dismantling of most nuclear installations cannot be considered without robots use. Robot solutions have been used for fifteen years by the Nuclear Installation Dismantling Unit of the CEA to carry out projects of level 3 (i.e. removal of all radioactivity from the installations). PIADE and ATENA carriers and MA23 and RD500 manipulators have largely contributed to the success of ELAN IIB and AT1 projects. The experience benefits of these projects has led the CEA to propose new research programs to test a new hydraulic arm and more changeable and lighter carriers. In future projects, the use of computerized simulation and more powerful remote viewing equipments for tool control and irradiation points locating will improve the training and comfort of operators. The use of modeling in connection with new control systems, such as TAO2000, will allow more complete automatic cutting and handling operations. (J.S.). 7 figs., 1 tab

  15. The challenges of dismantling

    International Nuclear Information System (INIS)

    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)

  16. Radioactivity and radioprotection: the every day life in a nuclear installation. Press tour at CEA/GRENOBLE 18 november 1999; Radioactivite et radioprotection: la vie quotidienne dans une installation nucleaire. Voyage de presse au Centre CEA/CADARACHE 18 novembre 1999

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-11-01

    In the framework of the public information, this paper gives a general information on the radioactivity and the radioprotection at the CEA/Cadarache center. A first part is devoted to a presentation of the radioactivity with definitions and radiation effects on the human being and the environment. An other part presents the radioprotection activities and regulations. The last part deals with specific activities of the CEA/Cadarache: the CASCAD installations for spent fuels storage, the LECA Laboratory for the Examination of Active Fuels and a dismantling installation for big irradiated objects. Historical aspects of the CEA/Cadarache are also provided. (A.L.B.)

  17. Management system information of characterization of the dismantling project of Jose Cabrera; Sistema de Gestion de la informacion de caracterizacion del proyecto de desmantelamiento de la CN Jose Cabrera

    Energy Technology Data Exchange (ETDEWEB)

    Gimeno Blesa, M. E.; Martin Palomo, N.; Gomez Rodriguez, C. A.

    2011-07-01

    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.

  18. Report transparency and nuclear safety 2007 CEA Cadarache

    International Nuclear Information System (INIS)

    This report presents the activities of the CEA Center of Cadarache for the year 2007. The actions concerning the safety, the radiation protection, the significant events, the release control and the environmental impacts and the wastes stored on the center are discussed. More especially the report discusses the beginning of the RJH reactor construction, the fourth generation reactors research programs, the implementing of la Rotonde the new radioactive wastes management installation, the renovation of the LECA. (A.L.B.)

  19. Dismantling of nuclear facilities

    International Nuclear Information System (INIS)

    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.)

  20. Melter Dismantlement

    Energy Technology Data Exchange (ETDEWEB)

    Richardson, BS

    2000-10-01

    The U.S. Department of Energy (DOE) has been utilizing vitrification processes to convert high-level radioactive waste forms into a stable glass for disposal in waste repositories. Vitrification facilities at the Savannah River Site (SRS) and at the West Valley Demonstration Project (WVDP) are converting liquid high level waste (HLW) by combining it with a glass-forming media to form a borosilicate glass, which will ensure safe long-term storage. Large, slurry fed melters, which are utilized for this process, were anticipated to have a finite life, on the order of two to three years, at which time they would have to be replaced using remote methods, due to the high radiation fields. In actuality the melters useable life span has, to date, have exceeded original life span estimates. Initial plans called for the removal of failed melters by placing the melter assembly into a container and storing in a concrete vault on the vitrification plant site pending size reduction, segregation, containerization, and shipment to appropriate storage facilities. Separate facilities for the processing of the failed melters currently do not exist. Options for handling these melters include (1) locating a facility to conduct the size reduction, characterization, and containerization as originally planned; (2) long-term storage or disposal of the complete melter assembly; and (3) attempting to refurbish the melter and to reuse the melter assembly. The focus of this report is to look at methods and issues pertinent to size reduction and/or melter refurbishment. In particular, removal of glass as a part of a refurbishment or for the purposes of reducing contamination levels (allowing for disposal of a greater proportion of the melter as low level waste) will be addressed.

  1. Challenges of dismantling

    International Nuclear Information System (INIS)

    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.)

  2. Report on transparency and nuclear safety 2014 - Cadarache CEA centre

    International Nuclear Information System (INIS)

    This document proposes, first, a presentation of the Cadarache CEA centre, of its activities and installations, gives a rather detailed overview of measures related to safety and to radiation protection within these activities and installations. Then it reports significant events related to safety and to radiation protection which occurred in 2014 and have been declared to the ASN. Next, it discusses the results of release measurements (liquid and gaseous effluents, radiological assessment, and chemical assessment for various installations) and the control of the chemical and radiological impact of these gaseous and liquid effluents on the environment. Finally, it addresses the issue of radioactive wastes which are stored in the different nuclear base installations of the Centre, indicates the different measures aimed at limiting the volume of these warehoused wastes and addresses their impact on health and on the environment. Nature and quantities of warehoused wastes are specified. Remarks and recommendations of the CHSCT are given

  3. Advanced systems for dismantling

    International Nuclear Information System (INIS)

    In this paper the author shows the approach used by the UDIN (Unite Centrale de Declassement des Installations Nucleaires) for dismantling. With respect of costs for dismantling, it is necessary to take in account the specificity of dismantling work site and to protect the environment and the workers. Some examples show these points. The protections are made by a good study of the work site, by a preliminary decontamination if possible by containment of contamination and by utilization of robots and technics to reduce radioactive wastes

  4. Innovations in dismantling robotics

    International Nuclear Information System (INIS)

    Since the beginning of the 1970s, CEA has developed innovative systems for remote operation in nuclear fields. This paper presents the main developments achieved for dismantling applications of robotic systems (manipulators, carriers, controllers, simulation). (orig.)

  5. The direct-Mat Project: Dismantling and Recycling Techniques for road Materials. Sharing Knowledge and Practices; El proyecto DIRECT-MAT: Tecnicas de demolicion y reciclado de materiales para la carretera-Compartiendo conocimientos y practicas

    Energy Technology Data Exchange (ETDEWEB)

    Sinis Fernandez, F.; Rubio guzman, B.; Gonzalez Abadias, A. I.

    2011-07-01

    This article describes the content of the DIRECT-MAT (Dismantling and Recycling for road Materials) project. the DIRECT MAT project objectives consist of sharing and disseminating, at the European scale, national knowledge and field practices regarding the dismantling and recycling of road and road related materials, for the benefit of all European countries. Road material recycling processes have previously been studied in national research projects in the last years; unfortunately, the results of those projects almost never benefit other European countries. This is especially true for the newer Member States. The DIRECT-MAT project, within 7{sup t}h Framework Programme, is a three year project starting in 2009, and is comparised of 20 partners from 15 participating countries. to reach the aims of the project, a WEB database will be created to compile and display the extensive and already validated research and job site data and a set of Best Practices Guides on dismantling and recycling of different types of materials will be issued. Finally, guidelines will be proposed to ensure database updating, including the results of future researches. (Author) 6 refs.

  6. Report on transparency and nuclear safety - Cadarache CEA centre - 2012

    International Nuclear Information System (INIS)

    A first volume proposes a presentation of the Cadarache CEA centre, of its activities and installations, gives a rather detailed overview of measures related to safety and to radiation protection within these activities and installations. It also reports significant events related to safety and to radiation protection which occurred in 2012 and have been declared to the ASN. It discusses the results of release measurements (liquid and gaseous effluents, radiological assessment, and chemical assessment for various installations) and the control of the chemical and radiological impact of these gaseous and liquid effluents on the environment. It addresses the issue of radioactive wastes which are stored in the different nuclear base installations of the Centre, indicates the different measures aimed at limiting the volume of these warehoused wastes and addresses their impact on health and on the environment. Nature and quantities of warehoused wastes are specified. The second volume concerns some specific installations (INB 32 or ATPu, and INB 54 or LPC) which belong to AREVA NC. The same topics are addressed: presentation of the facilities, arrangements regarding safety and radiation protection, significant events related to safety and radiation protection, measurements of effluents and their impact on the environment, warehoused wastes. Remarks and recommendations of the CHSCT are given

  7. Elk River Reactor dismantling

    International Nuclear Information System (INIS)

    The dismantling program was carried out in three overlapping phases: the planning phase which included the preliminary planning and selection of the dismantling approach, the dismantling phase which included all work performed to remove the reactor facility and restore the site to its pre-reactor condition, and the closeout phase which included the final site survey and efforts necessary to terminate the AEC license and contract. Of particular interest was the use of a remotely operated plasma cutting torch to section the pressure vessel internals, the pressure vessel and the outer thermal shield, the use of explosives in removal of the biological shield and the method of establishment of the criteria for material disposal

  8. Project management for the decommissioning and dismantling of nuclear facilities; Projektmanagement fuer Stilllegung und Rueckbau kerntechnischer Anlagen

    Energy Technology Data Exchange (ETDEWEB)

    Klasen, Joerg; Wilhelm, Oliver [ENBW Kernkraft GmbH, Neckarwestheim (Germany); Seizer, Burkhard; Schuetz, Tobias [Drees und Sommer, Stuttgart (Germany)

    2015-12-15

    The decommissioning of nuclear power plants is executed in a classic project manner as it is known from other construction projects. It is obvious to use the known portfolio of project management tools. The complexity that is created by the large size of the project in combination with safety requirements of the nuclear industry has to be handled. Complexity can only be managed addressing two main drivers: Prioritization and speed (agility) in project execution. Prioritization can be realized by applying tools like Earned Value Management. A high speed of project execution is established by applying Agile Management like SCRUM-methods. This method is adopted in the context of the cooperation ''Complex Projects'' to the needs of nuclear industry.

  9. A close-up of the ALEPH Time Projection Chamber (TPC) after the detector was dismantled, with a slice removed for the exhibition at the Musée International d'Horlogerie.

    CERN Multimedia

    2004-01-01

    On the occasion of CERN's 50th anniversary, starting 2 December at the Musée International d'Horlogerie in La Chaux-de-Fonds, Switzerland, a new exhibition will pay tribute to physics, from the cosmic to the subatomic scales. The exhibition, which run for several years, includes a slice of the Time Projection Chamber (TPC) from ALEPH, one of the LEP detectors, which CERN donated to the museum when the detector was dismantled.

  10. 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...

  11. Decontamination and dismantlement of the building 594 waste ion exchange facility at Argonne National Laboratory-East project final report.

    Energy Technology Data Exchange (ETDEWEB)

    Wiese, E. C.

    1998-11-23

    The Building 594 D&D Project was directed toward the following goals: Removal of any radioactive and hazardous materials associated with the Waste Ion Exchange Facility; Decontamination of the Waste Ion Exchange Facility to unrestricted use levels; Demolition of Building 594; and Documentation of all project activities affecting quality (i.e., waste packaging, instrument calibration, audit results, and personnel exposure) These goals had been set in order to eliminate the radiological and hazardous safety concerns inherent in the Waste Ion Exchange Facility and to allow, upon completion of the project, unescorted and unmonitored access to the area. The ion exchange system and the resin contained in the system were the primary areas of concern, while the condition of the building which housed the system was of secondary concern. ANL-E health physics technicians characterized the Building 594 Waste Ion Exchange Facility in September 1996. The characterization identified a total of three radionuclides present in the Waste Ion Exchange Facility with a total activity of less than 5 {micro}Ci (175 kBq). The radionuclides of concern were Co{sup 60}, Cs{sup 137}, and Am{sup 241}. The highest dose rates observed during the project were associated with the resin in the exchange vessels. DOE Order 5480.2A establishes the maximum whole body exposure for occupational workers at 5 rem (50 mSv)/yr; the administrative limit at ANL-E is 1 rem/yr (10 mSv/yr).

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

    International Nuclear Information System (INIS)

    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.)

  13. Dismantling cost and strategy

    International Nuclear Information System (INIS)

    In the shutdown of nuclear facilities the strategie includes decontamination and dismantling steps. Those steps are well established in a theoretical level and by the responsible international organizations. The deployment of such a strategy at national level for radiochemical facilities is just beginning. An example of such kind of operation is presented. The shutdown of the waste processing plant, in 1974, was performed by the Eurochemic Society

  14. Seismic risk and safety of nuclear installations. A look at the Cadarache Centre; Risque sismique et surete des installations nucleaires. Regards sur le Centre de Cadarache

    Energy Technology Data Exchange (ETDEWEB)

    Verrhiest-Leblanc, G.; Chevallier, A. [Autorite de Surete Nucleaire 75 - Paris (France)

    2010-11-15

    After a brief recall of some important seismic events which occurred in the past in the south-eastern part of France, the authors indicate the nuclear installations present in this region. They outline the difference between requirements for a usual building and for basic nuclear installations. They indicate laws and regulations which are to be applied to these installations like to any hazardous industrial installation. They describe the seismic risk as it has been determined for the Cadarache area, and evoke the para-seismic design of new nuclear installations which are to be built in Cadarache and actions for a para-seismic reinforcement of existing constructions. Finally, they evoke organisational aspects (emergency plans) and the approach for a better information and transparency about the seismic risk

  15. 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!

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

    International Nuclear Information System (INIS)

    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

  17. Conclusions of the DIRECT-MAT project: Dismantling and recycling techniques for road materials; Conclusiones del proyecto DIRECT-MAT: Tecnicas de demolicion y reciclado de materiales para la carretera

    Energy Technology Data Exchange (ETDEWEB)

    Gonzalez Abadias, A. I.; Ruiz-Aucar Berlinches, E.; Sinis Fernandez, F.

    2012-07-01

    DIRECT-MAT (Dismantling and Recycling Techniques for road Materials) is a research project included in the 7{sup t}h Framework Programme of the EU, which counted with the participation of 20 partners from 15 different European countries. The Transport Research Centre of CEDEX (Spain) has been part of this project that began in January 2009. The aim of the DIRECT-MAT project has been to enable that national experience in the field of demolition and recycling of materials related to roads can be shared and disseminated among European countries for the benefit of all of them. In 2011 the paper the Direct-Mat Project: Dismantling and recycling techniques for road materials. Sharing knowledge and practices was published in the number 161 of Ingenieria Civil magazine. That paper consisted of an extensive description of the project, explaining in detail its structure, the status of the work in early 2011 and the conclusions drawn from the milestones (review of existing national documents). This paper is a continuation of the one previously published. This this article describes the work carried out since then and the collisions of the project. During this time, the main activities have been the compilation of several case studies and the developing of best practice guides. Regarding the results of the project, it is important to mention the database in which all the information gathered during the project is being uploads. Soon, it will have free online access. This database in perhaps the most remarkable results of the project, as it represents an invaluable reference tool for all the stake holders interested in the wide variety of recycling techniques that are being carried out today in Europe. (Author) 8 refs.

  18. TRIGA Mark-III reactor dismantling program

    International Nuclear Information System (INIS)

    The activation assessment of the main parts of the TRIGA Mark-III (KRR-2) was estimated to effectively dismantle the activated and contaminated areas. All of the method and the order for decommissioning the KRR-2 have been chosen as a result of the examination of the physical structure and radiological conditions of the reactor component. These decommissioning methods and orders were reviewed as part of the Hazard and Operability (HAZOP) studies for the project. Radiological assessment is also done to protect the workers and the environment from the dismantling work. License documents were submitted to the Ministry of Science and Technology (MOST) at the end of 1998. Practical work of the D and D will start at the end of 1999 once the government issues the license. Radiation protection plan was also set up to control the workers and environment. This paper summarized the main lines of those studies. (author)

  19. 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...

  20. Continuously tritium monitoring of the pipe of liquid effluents at the Cea Cadarache; Controle en continu du tritium de la conduite des effluents liquides du CEA Cadarache

    Energy Technology Data Exchange (ETDEWEB)

    Pira, Y

    2004-07-01

    This report is oriented toward the radiation protection of environment that is an essential component of radiation protection. It is necessary to detect any solid, liquid or gaseous abnormal release and to find its origin. The present study bears on a detection instrument in continuously to find tritium in liquid effluents of the Cea Cadarache. After having study the functioning principle of this device, an evaluation of its performances has been realised ( back noise, yield, detection limit) and to a checking in real conditions of utilization. (N.C.)

  1. Remote tool development for nuclear dismantling operations

    International Nuclear Information System (INIS)

    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)

  2. The good wealth of dismantlement

    International Nuclear Information System (INIS)

    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.)

  3. LEP dismantling : Expérience ALEPH

    CERN Multimedia

    Patrice Loïez

    2001-01-01

    Photo 01 : Cabling team Photo 02 : Electronic assistant Photo 03 : Team of ALEPH dismantling Photo 04 : Radio protection team Photo 05 : Radio protection team Photo 06 : Technical team Photo 07 : Technical team Photo 08 : Transport team Photo 09 . Team of ALEPH dismantling Photo 10 : Team of ALEPH dismantling Photo 11 : Gas team

  4. Influence of high permeability disks in an axisymmetric model of the Cadarache dynamo experiment

    CERN Document Server

    Giesecke, A; Stefani, F; Gerbeth, G; Léorat, J; Herreman, W; Luddens, F; Guermond, J -L

    2011-01-01

    Numerical simulations of the kinematic induction equation are performed on a model configuration of the Cadarache von-K\\'arm\\'an-Sodium dynamo experiment. The effect of a localized axisymmetric distribution of relative permeability {\\mu} that represents soft iron material within the conducting fluid flow is investigated. The critical magnetic Reynolds number Rm^c for dynamo action of the first non-axisymmetric mode roughly scales like Rm^c({\\mu})-Rm^c({\\mu}->infinity) ~ {\\mu}^(-1/2) i.e. the threshold decreases as {\\mu} increases. This scaling law suggests a skin effect mechanism in the soft iron disks. More important with regard to the Cadarache dynamo experiment, we observe a purely toroidal axisymmetric mode localized in the high permeability disks which becomes dominant for large {\\mu}. In this limit, the toroidal mode is close to the onset of dynamo action with a (negative) growth-rate that is rather independent of the magnetic Reynolds number. We qualitatively explain this effect by paramagnetic pumping...

  5. NOCHAR Polymers: An Aqueous and Organic Liquid Solidification Process for Cadarache LOR (Liquides Organiques Radioactifs) - 13195

    International Nuclear Information System (INIS)

    To handle the Very Low Level Waste (VLLW) and the Low Level Waste (LLW) in France, two options can be considered: the incineration at CENTRACO facility and the disposal facility on ANDRA sites. The waste acceptance in these radwaste routes is dependent upon the adequacy between the waste characteristics (physical chemistry and radiological) and the radwaste route specifications. If the waste characteristics are incompatible with the radwaste route specifications (presence of significant quantities of chlorine, fluorine, organic component etc or/and high activity limits), it is necessary to find an alternative solution that consists of a waste pre-treatment process. In the context of the problematic Cadarache LOR (Liquides Organiques Radioactifs) waste streams, two radioactive scintillation cocktails have to be treated. The first one is composed of organic liquids at 13.1 % (diphenyloxazol, mesitylene, TBP, xylene) and water at 86.9 %. The second one is composed of TBP at 8.6 % and water at 91.4 %. They contain chlorine, fluorine and sulphate and have got alpha/beta/gamma spectra with mass activities equal to some kBq.g-1. Therefore, tritium is present and creates the second problematic waste stream. As a consequence, in order for disposal acceptance at the ANDRA site, it is necessary to pre-treat the waste. The NOCHAR polymers as an aqueous and organic liquid solidification process seem to be an adequate solution. Indeed, these polymers constitute an important variety of products applied to the treatment of radioactive aqueous and organic liquids (solvent, oil, solvent/oil mixing etc) and sludge through a mechanical and chemical solidification process. For Cadarache LOR, N910 and N960 respectively dedicated to the organic and aqueous liquids solidification are considered. With the N910, the organic waste solidification occurs in two steps. As the organic liquid travels moves through the polymer strands, the strands swell and immobilise the liquid. Then as the

  6. 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

  7. Decontamination and dismantling at the CEA

    International Nuclear Information System (INIS)

    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.)

  8. Decontamination and dismantlement of the building 200/205 pneumatic transfer tube at Argonne National Laboratory-East project final report.

    Energy Technology Data Exchange (ETDEWEB)

    Wiese, E. C.

    1998-12-11

    The Building 200/205 Pneumatic Transfer Tube D&D Project was directed toward the following goals: Remove any radioactive and hazardous materials associated with the transfer tube; Survey the transfer tube to identify any external contamination; Remove the transfer tube and package for disposal; Survey the soil and sand surrounding the transfer tube for any contamination; and Backfill the trench in which the tube sat and restore the area to its original condition. These goals had been set in order to eliminate the radiological and hazardous safety concerns inherent in the buried transfer tube and to allow, upon completion of the project, the removal of this project from the ANL-E action item list. The physical condition of the transfer tube and possible nuclear fuel samples lost in the tube were the primary areas of concern, while the exact location of the transfer tube was of secondary concern. ANL-E health physics technicians collected characterization data from the ends of the Building 200/205 pneumatic transfer tube in January 1998. The characterization surveys identified contamination to a level of 67,000 dpm (1,117 Bq) ({beta}/{gamma}) and 20,000 dpm (333 Bq) {alpha} smearable at the opening.

  9. KROTOS FCI experimental programme at CEA Cadarache: new features and status

    Energy Technology Data Exchange (ETDEWEB)

    Bonnet, J.M.; Bullado, Y.; Journeau, C.; Fouquart, P.; Piluso, P.; Sergeant, C.; Magallon, D. [CEA-Cadarache, DTN/STRI/LMA, Bat 708, BP1, 13108 Saint Paul lez Durance cedex (France)

    2005-07-01

    Full text of publication follows: KROTOS facility has been operated by the European Commission at JRC-Ispra for many years until 1999 as part of the FARO/KROTOS programme. The programme had to be stopped at JRC due to new EC priorities, and an agreement was concluded with CEA to transfer the KROTOS facility and know-how to Cadarache to continue investigating the pending FCI issues. By this agreement, CEA became owner of the facility. The main objective of the KROTOS programme at CEA Cadarache is understanding the role of melt properties in steam explosion propagation and energetics and, in particular, steam explosion behaviour of prototypical corium melts. Possible influence of physicochemical processes on explosiveness will also be explored. Actually, analysis of alumina debris produced at Ispra have shown that formation of metastable phases and chemical reaction with water at high temperature may play a significant role in enhancing heat transfer to water in the explosion phase. In order to reach the objective, steam explosion experiments are performed in well characterised conditions for a large spectrum of conditions and melt compositions of interest for both in- and ex-vessel situations. A trigger is applied as a rule. Advanced technology and instrumentation is used to reduce uncertainties on initial conditions and characterise the various phases of an explosion, with emphasis on high energy X-ray cinematography to qualify pre-mixing. This advanced instrumentation will enable the measurement of detailed variables to consolidate the qualification of the FCI codes. The use of high energy X-rays made it necessary to construct a new building to house the facility and its components. The facility should newly become operative early 2005. Main improvements with respect to Ispra concern melt delivery, hydrogen measurement and X-ray imaging. Preliminary studies have demonstrated that identification of the pre-mixture-water interface and coherent melt jet core, and

  10. Restoration of contaminated sites in the project PIMIC dismantling. The case of lentil; Restauracion de terrenos contaminados en el Proyecto PIMIC desmantelamiento. El caso de la lenteja

    Energy Technology Data Exchange (ETDEWEB)

    Medinilla, G.; Naranjo, V.; Vidaechea, S.

    2011-07-01

    The contaminated ground area called Lenteja (lentil), located in Ciemat and caused by a liquid leakage in 1970, is being decontaminated within PIMIC decommissioning project. Most remarkable aspects of this task are: -Initial radiological characterization (25 boreholes, 277 sample analyses). -Management of more than 2000 m{sup 3} of materials. Pile walls for excavation, and ventilated tent confinement. -Excavation of more than 6 m depth in an area of approx. 120 m{sup 2}. -Development of Sr-90 in field measuring techniques for soil pre classification. (Author)

  11. Flow modelling in fractured aquifers, development of multi-continua model (direct and inverse problems) and application to the CEA/Cadarache site

    International Nuclear Information System (INIS)

    This research thesis concerns the modelling of aquifer flows under the CEA/Cadarache site. The author reports the implementation of a numerical simulation tool adapted to large scale flows in fractured media, and its application to the Cadarache nuclear site. After a description of the site geological and hydrogeological characteristics, the author presents the conceptual model on which the modelling is based, presents the inverse model which allows a better definition of parameters, reports the validation of the inverse approach by means of synthetic and semi-synthetic cases. Then, he reports experiments and simulation of the Cadarache site

  12. Fuel racks dismantling workshop at Centraco facility - 59365

    International Nuclear Information System (INIS)

    Document available in abstract form only. Full text of publication follows: - Initial context: EDF aims to replace all the ancient storage racks to gain place in the fuel ponds. This project represents about 450 units up to 4 m x 4, 4 m x 2, 9 m, weight 6,4 te to dismantle, during 5 years The average density of the racks is very low (∼ 0.15). Due to this low density, final repository route is not adapted. By its knowledge and capabilities, CENTRACO route was chosen to reduce volume, restore density, decontaminate and secure the elimination of the racks. With those data, CENTRACO has defined the ATG workshop to dismantle racks but also wide components as steam generators. It was designed with as much automated devices and skills as possible, in order to avoid dose rate and contamination and to save time. It is currently under construction and will be put in operation in the early 2012. (authors)

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

    International Nuclear Information System (INIS)

    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

  14. Dismantling of Biological Agricultural Reactor Netherlands (BARN)

    International Nuclear Information System (INIS)

    The Biological Agricultural Reactor (BARN) was built in 1962 by government order through the Institute for Atomic Science in Agriculture (ITAL) in the Netherlands. The idea to build this nuclear reactor especially for biological research purposes was grown out of the first international conference about peaceful application of atomic energy hold in 1955. The construction composed of a basin reactor with light water as moderator and cooling medium. Up to 90% enriched Uranium was used as fuel. The maximal power was 100 kW. The reactor was used for research in the field of plant reproduction and other biological research. Mainly because of disappointing scientific results in 1978, 15 years after the start, the decision was made to terminate the reactor process following by dismantling. Alternative techniques proved to give comparative results at lower costs. In the decision making process political considerations played an important role. Prior to dismantling the reactor the 26 fuel elements were removed. Beside the uranium-235 each element contains about 1.3 TBq of fission and activation products. In 1982 the elements were shipped tot the Savannah River Plant in United States. An extensive analyze was carried out to map out the activation products on basis of neutron flux data, radiation history and composition of the materials. Results of this study was used to predict the dose rate of the different activated items and consequently to reduce risks of handling the items. For several reasons (e.g. control of building, knowledge of the plant) in 1996 a project has been initiated to remove all the active materials form the building and to recover the place to the original state, i.e. forest. High radioactive items with large dimensions were transferred to the so-called 'hot cells' of the ECN and were cut into small pieces. Finally all the activated material was brought to the COVRA for end storage. Parts of the basin construction were highly activated and were removed

  15. The use of non-destructive passive neutron measurement methods in dismantling and radioactive waste characterization

    International Nuclear Information System (INIS)

    The cleaning up and dismantling of nuclear facilities lead to a great volume of technological radioactive wastes which need to be characterized in order to be sent to the adequate final disposal or interim storage. The control and characterization can be performed with non-destructive nuclear measurements such as gamma-ray spectrometry. Passive neutron counting is an alternative when the alpha-gamma emitters cannot be detected due to the presence of a high gamma emission resulting from fission or activation products, or when the waste matrix is too absorbing for the gamma rays of interest (too dense and/or made of high atomic number elements). It can also be a complement to gamma-ray spectrometry when two measurement results must be confronted to improve the confidence in the activity assessment. Passive neutron assays involve the detection of spontaneous fission neutrons emitted by even nuclides (238Pu, 240Pu, 242Pu, 242Cm, 244Cm...) and neutrons resulting from (α, n) reactions with light nuclides (O, F, Be...). The latter is conditioned by the presence of high α-activity radionuclides (234U, 238Pu, 240Pu, 241Am...) and low-Z elements, which depends on the chemical form (metallic, oxide or fluorine) of the plutonium or uranium contaminant. This paper presents the recent application of passive neutron methods to the cleaning up of a nuclear facility located at CEA Cadarache (France), which concerns the Pu mass assessment of 2714 historic, 100 litre radioactive waste drums produced between 1980 and 1997. Another application is the dismantling and decommissioning of an uranium enrichment facility for military purposes, which involves the 235U and total uranium quantifications in about a thousand, large compressors employed in the gaseous diffusion enrichment process. (authors)

  16. Rapport d'étude : La perception des risques majeurs par les riverains du CEA de Cadarache

    OpenAIRE

    Lopez, Alexia; Régner, Isabelle; Schleyer-Lindenmann, Alexandra

    2015-01-01

    Ce rapport d'étude vient répondre aux interrogations de son commanditaire, la CLI (Commission Local d'Information) du CEA (Commissariat à l'énergie Atomique) de Cadarache. Il s'organise en trois partie : une première partie établit un état des lieux des connaissances des risques majeurs par les habitants. Les risques majeurs officiellement recensés sont : le risque feu de forêt, le risque inondation, le risque sismique, le risque de mouvement de terrain, le risque de rupture de barrage, et le...

  17. Report on transparency and nuclear safety, Cadarache 2011, Volume 1 + Volume 2 INB 32 and 54 Areva NC

    International Nuclear Information System (INIS)

    For respectively different sites all situated in Cadarache, the CEA Centre on the one hand, and the AREVA nuclear base installation INB 32 and 54 on the other hand, these volumes propose a presentation of their activities and installations, a description of measures regarding safety and radiation protection, a description of significant events regarding nuclear safety and radiation protection, a presentation and discussion of results of measurements of releases and of their impact on the environment, and a description of the different radioactive wastes stored on the concerned site

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

    International Nuclear Information System (INIS)

    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

  19. Nuclear reactor dismantling method and device

    International Nuclear Information System (INIS)

    The reactor dismantling device according to the present invention comprises an elevator lift extending from the lower portion in a biological-shielding walls of the reactor to an operation floor thereabove and a scaffolding for cutting operation vertically disposed at the periphery thereof. The scaffolding is rotated around a cutting mast by remote control to displace a cutting position for a drilling device. Then, pieces of the biological-shielding walls are cut out and automatically transported from the inside of the biological-shielding walls to an operation chamber by a recovery device, a truck and an elevator lift. This makes the dismantling operation highly efficient, to shorten the term of works. Further, operators' exposure dose can be mitigated, thereby enabling to improve safety of the dismantling operation. (T.M.)

  20. Transport and the dismantling of nuclear facilities

    International Nuclear Information System (INIS)

    Transport is not a real limiting constraint for the dismantling of nuclear facility if transport is taking into account very early in the dismantling process since numerous packages in various sizes already exist. For instance the TN-Gemini package allows the constitution of B-type packages for high radioactive level wastes, its volume capacity of about 16 m3 can store up to 5.8 tones of wastes, its external dimensions make it look like a sea container. One difficulty would be to find the adequate waste classification for a package containing heterogeneous wastes. (A.C.)

  1. DECISION ANALYSIS SCIENCE MODELING FOR APPLICATION AND FIELDING SELECTION APPLIED TO EQUIPMENT DISMANTLEMENT TECHNOLOGIES

    Energy Technology Data Exchange (ETDEWEB)

    M.A. Ebadian, Ph.D.

    1999-01-01

    The dismantlement of radioactively contaminated process equipment is a major concern during the D&D process. There are an estimated 1,200 buildings in the DOE-EM complex that will require the dismantlement of equipment and various metal structures. As buildings undergo the D&D process, this metallic equipment contaminated with radionuclides such as uranium and plutonium must be size-reduced before final disposal. A single information source comparing dismantlement technologies in the areas of safety, cost, and performance is needed by DOE managers and is not currently available. 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&D project costs. The purpose of this investigation was to evaluate commercially available and innovative technologies for equipment dismantlement and provide a comprehensive source of information to the D&D community in the areas of technology performance, cost, and health and safety.

  2. Web software for the control and management of radiation protection devices in the Cadarache site; Application WEB pour le controle et la gestion des appareils de radioprotection sur le centre de Cadarache

    Energy Technology Data Exchange (ETDEWEB)

    Beltritti, F. [CEA Cadarache 13108 St Paul lez Durance Cedex (France)

    2010-07-01

    This series of slides presents how to use a new software dedicated to the management of the periodical controls that have to be performed on the equipment involved in radiation protection. This software is ready to be dispatched on the CEA site of Cadarache. This software gives information on: the device to be controlled, the controls that have to be performed, the procedures to follow to make the test, the equipment necessary for the test particularly the need for radioactive sources, the maintenance of the device, the previous measurements and in the end the device's conformity. An evaluation of the conformity of all the devices present in a building or an area or of a particular type can be easily obtained. (A.C.)

  3. Glovebox dismantling activities and decommissioning plan for plutonium fuel fabrication facility

    International Nuclear Information System (INIS)

    The gloveboxes and process equipment used at plutonium fuel handling facilities have had to be replaced due to deterioration or the need to make changes. So far, their removal and replacement has taken place more than 30 times in Plutonium Fuel Center, Japan Nuclear Cycle Development Institute (JNC). In most recent dismantling activities, we removed four giant gloveboxes (total size, 110 cubic meters) which possessed equipment to recover plutonium from mixed oxide (MOX) fuel scraps. We have implemented a number of procedural improvements in dismantling activities and collected various kinds of data, including type and amount of primary and secondary waste from dismantling, relation between waste volume and work force, etc. Plutonium Fuel Fabricating Facility (PFFF) is one of the three plutonium fuel handling facilities in Plutonium Fuel Center, JNC. Its final mission to produce MOX fuels for the advanced thermal reactor 'Fugen' Nuclear Power Station was successfully finished in 2002. Then, we started preparatory activities to draw up a Deactivation and Decommissioning (DD) plan for this facility and to construct a database with the experimental data of glovebox dismantling activities acquired in the past thirty years. The DD schedule for this facility can be broken down into three phases. Phase 1 (to 2010): Stabilization of all the special nuclear materials in the facility and remove them from the facility. Establish new and effective decontamination and volume reduction technologies in order to improve existing methods. Phase 2 (2010-2015): Applying the above-mentioned technologies to some of the glovebox dismantling activities and confirm their adaptability for the project. Draw up a detailed DD plan which meets to various regulations. Phase 3 (2015-2020): Dismantling of all the remaining gloveboxes in the facility and promote research and development of DD technologies for future projects. Decontamination of inner surfaces of the building in order to reuse the

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

    International Nuclear Information System (INIS)

    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

  5. Dismantling operations by SGN : the WAGR and PIVER examples

    Energy Technology Data Exchange (ETDEWEB)

    Destrait, Laurent [D and D Programme Manager, SGN (France)

    1999-07-01

    By around september next year decommissioning work at WAGR should be getting into its stride. Among the most difficult operations, the dismantling of the pressure vessel and insulation will be carried out by ENTECH : a consortium of Strachan and Henshaw and SGN. The three year contract, recognised as one of the project's most technically demanding, is : 1. to primarily provide methodology and manufacture of tooling to dismantle the pressure vessel and to package it together with the debris arising, safely and effectively for disposal, 2. To provide operator training and support to the dismantling operations. The vessel is 13.1-m high, 6.5-m diameter and, clad with insulation, results in total weight of 118te. It consists of a rather combination asbestos, cement, metadextramite, chicken wire and aluminium sheeting mounted onto a carbon steel and mild steel. Based on the respective advantages and weaknesses of all of the existing cutting methods and the criteria as : risk, safety, robustness, efficiency, speed and optional use of the remote dismantling machine (already in ;lace), the final method chosen was oriented toward the process combining mechanical and thermal cutting. The dismantling of the reactor pressure vessel will be carried out using the existing RDM and a combination of a disc cutter for the insulation on the outside and an Oxy/propane flame cutting torch for the steel from the inside. The pressure vessel and insulation will be cut in five stages to a size which can be carried from the reactor vault to the sentencing cell for processing into baskets before being transferred into boxes in the waste packaging building and dispatched as ILW or LLW. The decision to decommission PIVER(Pilot Vitrification facility) was made in 1984, after some 5 million curies had been vitrified. The objective was to thoroughly clean up the process cell in order to allow installation of a new research and development facility. The decommissioning program lasted from

  6. Dismantling operations by SGN : the WAGR and PIVER examples

    International Nuclear Information System (INIS)

    By around september next year decommissioning work at WAGR should be getting into its stride. Among the most difficult operations, the dismantling of the pressure vessel and insulation will be carried out by ENTECH : a consortium of Strachan and Henshaw and SGN. The three year contract, recognised as one of the project's most technically demanding, is : 1. to primarily provide methodology and manufacture of tooling to dismantle the pressure vessel and to package it together with the debris arising, safely and effectively for disposal, 2. To provide operator training and support to the dismantling operations. The vessel is 13.1-m high, 6.5-m diameter and, clad with insulation, results in total weight of 118te. It consists of a rather combination asbestos, cement, metadextramite, chicken wire and aluminium sheeting mounted onto a carbon steel and mild steel. Based on the respective advantages and weaknesses of all of the existing cutting methods and the criteria as : risk, safety, robustness, efficiency, speed and optional use of the remote dismantling machine (already in ;lace), the final method chosen was oriented toward the process combining mechanical and thermal cutting. The dismantling of the reactor pressure vessel will be carried out using the existing RDM and a combination of a disc cutter for the insulation on the outside and an Oxy/propane flame cutting torch for the steel from the inside. The pressure vessel and insulation will be cut in five stages to a size which can be carried from the reactor vault to the sentencing cell for processing into baskets before being transferred into boxes in the waste packaging building and dispatched as ILW or LLW. The decision to decommission PIVER(Pilot Vitrification facility) was made in 1984, after some 5 million curies had been vitrified. The objective was to thoroughly clean up the process cell in order to allow installation of a new research and development facility. The decommissioning program lasted from 1984 to

  7. A Study on Dismantling of Westinghouse Type Nuclear Reactor

    Energy Technology Data Exchange (ETDEWEB)

    Jeong, Woo-Tae; Lee, Sang-Guk [KHNP-CRI, Daejeon (Korea, Republic of)

    2014-10-15

    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.

  8. NPP bulk equipment dismantling problems and experience

    International Nuclear Information System (INIS)

    NPP bulk equipment dismantling problems and experience are summarized. 'ECOMET-S' JSC is shown as one of the companies which are able to make NPPs industrial sites free from stored bulk equipment with its further utilization. 'ECOMET-S' JSC is the Russian Federation sole specialized metallic LLW (MLLW) treatment and utilization facility. Company's main objectives are waste predisposal volume reduction and treatment for the unrestricted release as a scrap. Leningrad NPP decommissioned main pumps and moisture separators/steam super heaters dismantling results are presented. Prospective fragmentation technologies (diamond and electro-erosive cutting) testing results are described. The electro-erosive cutting machine designed by 'ECOMET-S' JSC is presented. The fragmentation technologies implementation plans for nuclear industry are presented too. (author)

  9. Brennilis - first deployment of industrial robots for the dismantling of a french nuclear power plant

    International Nuclear Information System (INIS)

    Since its founding in 1960, NUKEM Technologies has developed into one of Europe's leading engineering design and plant construction companies in the nuclear sector. For more than 25 years NUKEM has also been a specialist in the fields of RAW management and decommissioning consultancy. Today, we are proud on showing our extensive international track-record, to the growing needs for RAW facilities and decommissioning around the world. Together with our shareholder Atomstroyexport, NUKEM is embedded in a strong and strategically oriented group. NUKEM is now applying its skills and experience to the dismantling projects of French's 'First Generation' nuclear reactors, which are currently underway and have a pilot nature in terms of the entire future French dismantling program. In particular, one of these projects, the dismantling of EDF's CO2-cooled heavy-water reactor (EL 4) at BRENNILIS in Brittany is being performed by a Franco-German consortium, consisting of ONET Technologies Grands Projects (France) and NUKEM Technologies (Germany). The chosen dismantling strategy is based on the use of standard industrial (remote-controlled) robot systems, which not only carry out the dismantling activities, but also perform step-by-step the construction of their own infrastructure in the reactor core, as dismantling progresses. These standard robots, are of course enhanced by NUKEM in the BRENNILIS project with adaptations for the radiological environment, adjustments to the geometric requirements regarding compactness of the robots, whilst maximising the necessary reach distance and load-bearing capability. The biggest advantage of the chosen concept is that it allows for a combination of individual joy-stick-control and installed base program as well as a high level of flexibility of use and high handling speed. An integrated accident control system ensures in parallel, that no human error can lead to damage of the robot systems. The equipment and process design and the sum

  10. Testing and Commissioning of a Multifunctional Tool for the Dismantling of the Activated Internals of the KNK Reactor Shaft - 13524

    International Nuclear Information System (INIS)

    The Compact Sodium Cooled Reactor Facility Karlsruhe (KNK), a prototype reactor to demonstrate the Fast Breeder Reactor Technology in Germany, was in operation from 1971 to 1991. The dismantling activities started in 1991. The project aim is the green field in 2020. Most of the reactor internals as well as the primary and secondary cooling loops are already dismantled. The total contaminated sodium inventory has already been disposed of. Only the high activated reactor vessel shielding structures are remaining. Due to the high dose rates these structures must be dismantled remotely. For the dismantling of the primary shielding of the reactor vessel, 12 stacked cast iron blocks with a total mass of 90 Mg and single masses up to 15.5 Mg, a remote-controlled multifunctional dismantling device (HWZ) was designed, manufactured and tested in a mock-up. After successful approval of the test sequences by the authorities, the HWZ was implemented into the reactor building containment for final assembling of the auxiliary equipment and subsequent hot commissioning in 2012. Dismantling of the primary shielding blocks is scheduled for early 2013. (authors)

  11. Testing and Commissioning of a Multifunctional Tool for the Dismantling of the Activated Internals of the KNK Reactor Shaft - 13524

    Energy Technology Data Exchange (ETDEWEB)

    Rothschmitt, Stefan; Graf, Anja [WAK Rueckbau- und Entsorgungs- GmbH, P.O.Box 12 63, 76339 Eggenstein-Leopoldshafen (Germany); Bauer, Stefan; Klute, Stefan; Koselowski, Eiko [Siempelkamp Nukleartechnik GmbH, Am Taubenfeld 25/1, 69123 Heidelberg (Germany); Hendrich, Klaus [Ingenieurbuero Hendrich, Moerikeweg 14, 75015 Bretten (Germany)

    2013-07-01

    The Compact Sodium Cooled Reactor Facility Karlsruhe (KNK), a prototype reactor to demonstrate the Fast Breeder Reactor Technology in Germany, was in operation from 1971 to 1991. The dismantling activities started in 1991. The project aim is the green field in 2020. Most of the reactor internals as well as the primary and secondary cooling loops are already dismantled. The total contaminated sodium inventory has already been disposed of. Only the high activated reactor vessel shielding structures are remaining. Due to the high dose rates these structures must be dismantled remotely. For the dismantling of the primary shielding of the reactor vessel, 12 stacked cast iron blocks with a total mass of 90 Mg and single masses up to 15.5 Mg, a remote-controlled multifunctional dismantling device (HWZ) was designed, manufactured and tested in a mock-up. After successful approval of the test sequences by the authorities, the HWZ was implemented into the reactor building containment for final assembling of the auxiliary equipment and subsequent hot commissioning in 2012. Dismantling of the primary shielding blocks is scheduled for early 2013. (authors)

  12. Safety Assessment of Low-Contaminated Equipment Dismantling at Nuclear Power Plants

    Directory of Open Access Journals (Sweden)

    Egidijus Babilas

    2015-01-01

    Full Text Available The decommissioning of nuclear facilities requires adequate planning and demonstration that dismantling and decontamination activities can be conducted safely. Existing safety standards require that an appropriate safety assessment be performed to support the decommissioning plan for each facility (International Atomic Energy Agency, 2006. This paper presents safety assessment approach used in Lithuania during the development of the first dismantling and decontamination project for Ignalina NPP. The paper will mainly focus on the identification and assessment of the hazards raised due to dismantling and decontamination activities at Ignalina Nuclear Power Plant and on the assessment of the nonradiological and radiological consequences of the indicated most dangerous initiating event. The drop of heavy item was indicated as one of most dangerous initiating events for the discussed Ignalina Nuclear Power Plant dismantling and decontamination project. For the analysis of the nonradiological impact the finite element model for the load drop force calculation was developed. The radiological impact was evaluated in those accident cases which would lead to the worst radiological consequences. The assessments results show that structural integrity of the building and supporting columns of building structures will be maintained and radiological consequences are lower than the annual regulatory operator dose limit.

  13. Advanced robotics for decontamination and dismantlement

    International Nuclear Information System (INIS)

    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

  14. Melter Glass Removal and Dismantlement

    Energy Technology Data Exchange (ETDEWEB)

    Richardson, BS

    2000-10-31

    The U.S. Department of Energy (DOE) has been using vitrification processes to convert high-level radioactive waste forms into a stable glass for disposal in waste repositories. Vitrification facilities at the Savannah River Site (SRS) and at the West Valley Demonstration Project (WVDP) are converting liquid high-level waste (HLW) by combining it with a glass-forming media to form a borosilicate glass, which will ensure safe long-term storage. Large, slurry fed melters, which are used for this process, were anticipated to have a finite life (on the order of two to three years) at which time they would have to be replaced using remote methods because of the high radiation fields. In actuality the melters useable life spans have, to date, exceeded original life-span estimates. Initial plans called for the removal of failed melters by placing the melter assembly into a container and storing the assembly in a concrete vault on the vitrification plant site pending size-reduction, segregation, containerization, and shipment to appropriate storage facilities. Separate facilities for the processing of the failed melters currently do not exist. Options for handling these melters include (1) locating a facility to conduct the size-reduction, characterization, and containerization as originally planned; (2) long-term storing or disposing of the complete melter assembly; and (3) attempting to refurbish the melter and to reuse the melter assembly. The focus of this report is to look at methods and issues pertinent to size-reduction and/or melter refurbishment in particular, removing the glass as a part of a refurbishment or to reduce contamination levels (thus allowing for disposal of a greater proportion of the melter as low level waste).

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

    International Nuclear Information System (INIS)

    A description is given of the partial dismantling of the dissolver used for fuel elements of up to 1.6 wt % 235U 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)

  16. Achievements and prospects of robotics in dismantling operations

    International Nuclear Information System (INIS)

    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

  17. Capacitive tool standoff sensor for dismantlement tasks

    Energy Technology Data Exchange (ETDEWEB)

    Schmitt, D.J.; Weber, T.M. [Sandia National Labs., Albuquerque, NM (United States); Liu, J.C. [Univ. of Illinois, Urbana, IL (United States)

    1996-12-31

    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.

  18. Capacitive tool standoff sensor for dismantlement tasks

    International Nuclear Information System (INIS)

    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. Dismantling of Highly Contaminated Process Installations of the German Reprocessing Facility (WAK) - Status of New Remote Handling Technology - 13287

    International Nuclear Information System (INIS)

    Decommissioning and dismantling of the former German Pilot Reprocessing Plant Karlsruhe (WAK) including the Vitrification Facility (VEK) is being executed in different Project steps related to the reprocessing, HLLW storage and vitrification complexes /1/. While inside the reprocessing building the total inventory of process equipment has already been dismantled and disposed of, the HLLW storage and vitrification complex has been placed out of operation since vitrification and tank rinsing procedures where finalized in year 2010. This paper describes the progress made in dismantling of the shielded boxes of the highly contaminated laboratory as a precondition to get access to the hot cells of the HLLW storage. The major challenges of the dismantling of this laboratory were the high dose rates up to 700 mSv/h and the locking technology for the removal of the hot cell installations. In parallel extensive prototype testing of different carrier systems and power manipulators to be applied to dismantle the HLLW-tanks and other hot cell equipment is ongoing. First experiences with the new manipulator carrier system and a new master slave manipulator with force reflection will be reported. (authors)

  20. Dismantling of Highly Contaminated Process Installations of the German Reprocessing Facility (WAK) - Status of New Remote Handling Technology - 13287

    Energy Technology Data Exchange (ETDEWEB)

    Dux, Joachim; Friedrich, Daniel; Lutz, Werner; Ripholz, Martina [WAK Rueckbau- und Entsorgungs- GmbH, P.O. Box 12 63, 76339 Eggenstein-Leopoldshafen (Germany)

    2013-07-01

    Decommissioning and dismantling of the former German Pilot Reprocessing Plant Karlsruhe (WAK) including the Vitrification Facility (VEK) is being executed in different Project steps related to the reprocessing, HLLW storage and vitrification complexes /1/. While inside the reprocessing building the total inventory of process equipment has already been dismantled and disposed of, the HLLW storage and vitrification complex has been placed out of operation since vitrification and tank rinsing procedures where finalized in year 2010. This paper describes the progress made in dismantling of the shielded boxes of the highly contaminated laboratory as a precondition to get access to the hot cells of the HLLW storage. The major challenges of the dismantling of this laboratory were the high dose rates up to 700 mSv/h and the locking technology for the removal of the hot cell installations. In parallel extensive prototype testing of different carrier systems and power manipulators to be applied to dismantle the HLLW-tanks and other hot cell equipment is ongoing. First experiences with the new manipulator carrier system and a new master slave manipulator with force reflection will be reported. (authors)

  1. The radioprotection challenges associated with the dismantling of nuclear facilities; Les enjeux de radioprotection associes au demantelement des installations nucleaires

    Energy Technology Data Exchange (ETDEWEB)

    Anon.

    2011-01-15

    This document proposes an overview of the different studies performed by the CEPN (the French Centre of investigation on protection assessment in the nuclear sector) to develop principles and good practices in the field of radiation protection in the case of dismantling activities. These issues are addressed with respect to the characteristics of these dismantling activities, i.e. the evolution of radiological conditions under which workers are intervening, the production and handling of very important volumes of radioactive and conventional wastes, and the possible existence of a site rehabilitation project

  2. I.Care.fire. EDP-supported dynamic fire-protection concept adaptation in the course of dismantling nuclear facilities

    International Nuclear Information System (INIS)

    Through the political resolution to terminate the use of nuclear energy, the number of dismantling projects in the nuclear area will significantly increase in the years to come. In the course of dismantling, the buildings and plant measures for fire protection will change constantly, this means that the existing fire-protection concept of the plant must be subjected to ongoing adaptation. This adaptation is based on preparation of fire load lists and execution of safety analyses. Previously this adaptation was executed manually, this was both time-intensive and personnel-intensive. The transition to EDP-supported fire protection should occur with the aid of adaptive fire-protection design to optimise adaptation of the fire protection. This adaptive fire protection design, with the aid of a software tool, enables electronic recording of the fire load lists, automatic execution of safety analyses and facilitation of dismantling steps relative to fire protection.

  3. The application of mechanical and thermal cutting tools for the dismantling of activated internals of the reactor pressure vessels in the Versuchsatomkraftwerk, Kahl and the Gundremmingen Unit A

    Energy Technology Data Exchange (ETDEWEB)

    Eickelpasch, N. [Versuchsatomkraftwerk GmbH, Kahl am Main (Germany); Kalwa, H. [Versuchsatomkraftwerk GmbH, Kahl am Main (Germany); Steiner, H. [Kernkraftwerke Gundremmingen Betriebsgesellschaft mbH, D-89355 Gundremmingen (Germany); Priesmeyer, U. [Kernkraftwerke Gundremmingen Betriebsgesellschaft mbH, D-89355 Gundremmingen (Germany)

    1997-07-01

    The Gundremmingen Unit A plant (KRB A) and the Versuchsatomkraftwerk Kahl (VAK) plant represent the first generation of nuclear reactors in Germany. The 250 MW{sub e} reactor KRB A was the first commercial reactor in Germany and the 16 MW{sub e} reactor VAK was the pilot nuclear power plant, which had to serve mainly scientific purposes. KRB A is under dismantling since 1983, VAK since 1988. Although they are both of the boiling water type, they are rather different to each other, referring to their size and construction. The actual work is the dismantling of high contaminated components inside the reactor buildings and the underwater cutting of activated internals of the reactor pressure vessels. Several cutting techniques have been developed, tested and applied to respective dismantling tasks in the meantime. The experiences made in both projects are not limited to dismantling work only, but also include know-how on effective decontamination and scrap recycling. (orig.)

  4. Prefiltration of gaseous effluents in plant dismantling

    International Nuclear Information System (INIS)

    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

  5. Determining the cost of nuclear technology dismantling - software to quantify the costs of clean dismantling of nuclear installations

    International Nuclear Information System (INIS)

    Division ENERGOPROJEKT PRAHA processes within the group UJV Rez, a.s. complex pre-project and project preparation works in the nuclear field. Division prepares studies and documentation necessary for the customer's decision making (feasibility studies, business plans, building plans, etc.), preparatory, conceptual and project documentation), including related engineering services. Further safety documentation processes at all levels and documentation of the evaluation of environmental impact (EIA). In the area of a decommissioning process complete alternate design studies and design documentations of a decommissioning of NPPs in order to choose suitable variant of solution. An important area is the financing of the decommissioning process, creation of financial reserves, the input data to create a cost estimate and methodology for cost estimate. Quantifying the cost demands of the decommissioning process throughout the life cycle is composed of individual cost items for individual decommissioning activities. These also include determining the amount of costs necessary for removing uncontaminated or decontaminated process equipment. In the division ENERGOPROJEKT PRAHA was created software DEMONDEC for the estimation of these costs, which is based on the assumption that the costs to be incurred for dismantling of the above technological nuclear installation, it can be derived from the performance indicators when removing analogue equipment and systems that are part of common industrial buildings. (authors)

  6. Dismantlement and Radioactive Waste Management of DPRK Nuclear Facilities

    International Nuclear Information System (INIS)

    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

  7. 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

  8. 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.

  9. Environmental Assessment for decontamination and dismantlement, Pinellas Plant

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    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).

  10. Environmental Assessment for decontamination and dismantlement, Pinellas Plant

    International Nuclear Information System (INIS)

    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)

  11. Recent developments in post-irradiation examination techniques for water reactor fuel. Proceedings of a technical committee meeting held in Cadarache, France, 17-21 October 1994

    International Nuclear Information System (INIS)

    At the invitation of the Government of France, following a proposal of the International Working Group on Water Reactor Fuel Performance and Technology (IWGFPT) the IAEA convened a Technical Committee meeting from 14 to 21 October 1994 in Cadarache to discuss recent technical advances and improvements in the field of post-irradiation examination (PIE) of fuel used in nuclear power plants. Fifty participants representing 14 countries attended the meeting and 30 papers were presented and discussed during five technical sessions. Working Groups composed of the session chairmen and authors of papers prepared summaries of each session including conclusions and recommendations for future work. Refs, figs and tabs

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

    International Nuclear Information System (INIS)

    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.)

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

    International Nuclear Information System (INIS)

    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

  14. Experience Review on Dismantling Procedure for American Decommissioned NPPs

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Hyosub; Son, Daesun; Lee, Jaeyong; Kim, Kyungmin; Kim, Yong-soo [Hanyang University, Seoul (Korea, Republic of)

    2015-05-15

    According to IAEA, the number of shutdown NPPs is totally 150 globally. In Korea, there are 23 operating NPPs and 5 NPPs under construction. But Korea has no shutdown NPP and has no experience on decommissioning commercial reactor so far except for decommissioning research reactor, TRIGA MARK-3. Based on the NPP lifetime as a 45 years, it is expected that 440 NPPs in the world and 16 NPPs in Korea will come to an end of their lifetime until 2060. In this study, decontamination and decommissioning (D and D) procedure of shutdown NPPs in US concentrated on dismantling of reactor vessel and its internals is investigated. Detailed activation analysis on primary system should be followed for safe D and D activities. However many US decommissioning projects encountered that collection and removal of irradiated small and scattered debris from segmentation were challenging issues. That's why cutting enclosure was implemented to restrict the spread of debris to other area of refueling cavity. Furthermore lifting of total weight (apx. 1,000,000 kg) on primary system including RPV, RVI and interior low-density concrete was extremely heavy.

  15. Mobile worksystems for decontamination and dismantlement

    International Nuclear Information System (INIS)

    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

  16. 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.

  17. Implementation of the environmental management plan for the dismantling of nuclear powered submarines at Zvezdochka Shipyard, Russia

    International Nuclear Information System (INIS)

    Department of Foreign Affairs and International Trade Canada is funding the dismantling of twelve nuclear powered submarines (NPS) from the Russian Federation's Northern Fleet as part of the Global Partnership Initiative against weapons and materials of mass destruction. In this paper, work performed by Nuclear Safety Solutions Ltd. and its collaborators in support of these activities is described. First, an environmental impact assessment of towing and dismantling NPS in the Kola Peninsula, and the Barents and White Seas was performed. The assessed activities included: towing of NPS from Naval Bases in Murmansk Region to the Zvezdochka shipyard (Severodvinsk); defuelling of onboard reactors; dismantling of NPS at Zvezdochka; and waste management. The assessment helped identify mitigation measures that could prevent the occurrence of adverse effects. Next, the project team defined and implemented an environmental management plan (EMP) based on the shipyard's existing environmental policy and the mitigating measures identified during the environmental assessment. Specific targets were defined to track the progress of the EMP implementation, and are described in this paper. During the study period, three Victor Class NPS were dismantled at Zvezdochka. The major benefits realized include: removal and spent nuclear fuel assemblies; treatment/decontamination of liquid and solid radioactive waste; and the cultivation of collaboration between Russian and Western expertise. (author)

  18. Implementation of the environmental management plan for the dismantling of nuclear powered submarines at Zvezdochka shipyard, Russia

    International Nuclear Information System (INIS)

    Department of Foreign Affairs and International Trade Canada is funding the dismantling of twelve nuclear powered submarines (NPS) from the Russian Federation's Northern Fleet as part of the Global Partnership Initiative against weapons and materials of mass destruction. In this paper, work performed by Nuclear Safety Solutions Ltd. and its collaborators in support of these activities is described. First, an environmental impact assessment of towing and dismantling NPS in the Kola Peninsula, and the Barents and White Seas was performed. The assessed activities included: towing of NPS from Naval Bases in Murmansk Region to the Zvezdochka shipyard (Severodvinsk); defuelling of onboard reactors; dismantling of NPS at Zvezdochka; and waste management. The assessment helped identify mitigation measures that could prevent the occurrence of adverse effects. Next, the project team defined and implemented an environmental management plan (EMP) based on the shipyard's existing environmental policy and the mitigating measures identified during the environmental assessment. Specific targets were defined to track the progress of the EMP implementation, and are described in this paper. During the study period, three Victor Class NPS were dismantled at Zvezdochka. The major benefits realized include: removal of spent nuclear fuel assemblies; treatment/ decontamination of liquid and solid radioactive waste; and the cultivation of collaboration between Russian and Western expertise. (author)

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

    International Nuclear Information System (INIS)

    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 a future national storage facility

  20. 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

  1. 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.

  2. Topical Session on the Decommissioning and Dismantling Safety Case

    International Nuclear Information System (INIS)

    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

  3. 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

    interruptions. Bottle-necks in the process causes increased space requirements and will have negative impact on the project schedule, which increases not only the cost but also the dose exposure to personnel. For these reasons it is critical to create a process that transfers material into conditioned waste ready for disposal as quickly as possible. To a certain extent the decommissioning program should be led by the waste management process. With the objective to reduce time for handling of dismantled material at site and to efficiently and environmental-friendly use waste management methods (clearance for re-use followed by clearance for recycling), the costs for the plant decommissioning could be reduced as well as time needed for performing the decommissioning project. Also, risks for delays would be reduced with a well-defined handling scheme which limits surprises. Delays are a major cost driver for decommissioning projects. (authors)

  4. Decommissioning of the ASTRA research reactor: Dismantling the auxiliary systems and clearance and reuse of the buildings

    Directory of Open Access Journals (Sweden)

    Meyer Franz

    2008-01-01

    Full Text Available The paper presents work performed in the last phase of the decommissioning of the ASTRA research reactor at the Austrian Research Centers Seibersdorf. Dismantling the pump room installations and the ventilation system, as well as the clearance of the buildings is described. Some conclusions and summary data regarding the timetable, material management, and the cost of the entire project are also presented.

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

    International Nuclear Information System (INIS)

    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

  6. 49 CFR 1242.42 - Administration, repair and maintenance, machinery repair, equipment damaged, dismantling retired...

    Science.gov (United States)

    2010-10-01

    ... 49 Transportation 9 2010-10-01 2010-10-01 false Administration, repair and maintenance, machinery repair, equipment damaged, dismantling retired property, fringe benefits, other casualties and insurance... maintenance, machinery repair, equipment damaged, dismantling retired property, fringe benefits,...

  7. The CEA Cadarache site. Additional safety assessment with respect to the accident which occurred in the Fukushima-Daiichi nuclear power station

    International Nuclear Information System (INIS)

    After a presentation of some characteristics of the CEA Cadarache site (internal and external industrial environment, crisis management organization at the CEA level and at the local level), this document reports the identification of structures and equipment concerned by crisis management (site support functions, critical structures and equipment concerned by additional safety assessments). Then, it addresses the different risks: earthquake (sizing of critical structures and equipment, margin assessment), flooding (possible origins, alarm measures), other extreme natural events (extreme meteorological conditions, extreme earthquake with induced flooding, forest fire), and loss of electric supplies and of cooling systems. The last parts address the organization of accident management in situation typically related to additional safety management), and subcontracting conditions and practices

  8. Place of the final disposal of short lived dismantling waste

    International Nuclear Information System (INIS)

    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

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

    International Nuclear Information System (INIS)

    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 CO2 blasting tests on non active samples

  10. A system for automated, dismantlement of plutonium weapons components

    International Nuclear Information System (INIS)

    The development of advanced dismantlement technologies will play an integral part on the changing role of the DOE. As an important component to this effort, the ARIES (Automated Retirement and Integrated Extraction System) System is designed to provide a test bed for the development of technology for the dismantlement of the primaries of nuclear weapons (pits). The ARIES system will integrate and automate the processes of pit disassembly, plutonium, plutonium removal, preparation of oxide from plutonium metal, decontamination of non-plutonium parts, and in-line measurement of the products and wastes by state-of-the-art non-destructive assay (NDA) methods. No integrated method now exists for the dismantlement and recovery of nuclear material from many weapons designs. Even those assemblies for which recovery techniques have been established require extensive manual handling (with associated personnel exposure to radiation) and result in considerable waste generation during dismantlement. The disposition of excess plutonium will require a facility to disassemble and remove plutonium from the pits. ARIES will provide the methods to satisfy this goal while at the same time reducing waste generation, lowering personnel radiation exposures, and operating to the highest standards of safety and security. A description of the ARIES system is given

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

    International Nuclear Information System (INIS)

    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

  12. Log of refining and conversion facility dismantling. Progress in 2009FY

    International Nuclear Information System (INIS)

    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, and all equipments in radiation controlled area will be dismantled by 2011 fiscal year. This report is a record of the dismantlement situation of the Refining and Conversion Facility in 2009 fiscal years. Concretely, dismantlement logs, dismantlement material, and secondary waste are published. (author)

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

    International Nuclear Information System (INIS)

    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

  14. Hot-cell for dismantling of nuclear gauges

    CERN Document Server

    Reis, L C A

    2000-01-01

    This work objectives the design of a hot-cell that will be used for dismantling of nuclear gauges. In the hot-cell, nuclear gauges received as radioactive waste at the Centro de Desenvolvimento da Tecnologia Nuclear - CDTN will be dismantled, in order to decrease the volume of radioactive waste to be stored at the Center. Sources originally conditioned as special form radioactive material will be tested and in case do not present leakage, the respective gauges will be disposable for reusing by radioisotope users. The remaining sources will be taken off the original shielding and conditioned in special packages adequate for storage and disposal. All steps of work, the hot-cell design and methodology for conditioning are also described.

  15. The development of thermal and mechanical cutting technology for the dismantlement of the internal core of Fukushima Daiichi NPS

    International Nuclear Information System (INIS)

    The cutting technologies for removing the fuel debris and the internal core structure in Fukushima Daiichi Nuclear Power Plant are needed in consideration of the situation in the core and so on. On the other hand, Japan Atomic Energy Agency (JAEA), which has been carrying out the decommissioning of the nuclear facilities ending the R and D, has several technologies and knowledge to dismantle the nuclear facilities. In particular, the cutting technologies of the plasma arc, the laser, and the abrasive water jet (AWJ) – which are used for dismantling the reactor of N.P.S. (FUGEN), a heavy water-moderated, light water cooled, pressure-tube-type reactor – and the plasma jet for dismantling the nuclear fuel facilities have been developed. Therefore, based on the above, JAEA has carried out the cutting test for investigating the applicability of those cutting technologies to propose the method for removing the fuel debris and the internal core structure to the national project. This paper outlines the test results of the plasma arc and the AWJ cutting technologies, and the future plan of the test of those technologies and the plasma jet cutting technology. (author)

  16. 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...

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

    International Nuclear Information System (INIS)

    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)

  18. Pilot study dismantlement of 20 lead-lined shipping casks

    International Nuclear Information System (INIS)

    This report describes a pilot study conducted at the INEL to dismantle lead-lined casks and shielding devices, separate the radiologically contaminated and hazardous materials, and recycle resultant scrap lead. The facility areas where the work was performed, dismantlement methods, and process equipment are described. Issues and results associated with recycling the lead as a free-released scrap metal are presented and discussed. Data and results from the pilot study are summarized and presented. The study concluded that cask dismantlement at the INEL can be performed as a legitimate recycling activity for scrap lead. Ninety-one percent of the lead recovered passed free-release criteria. The value of the 50,375 lb of recovered lead is approximately $0.45/lb. Resultant waste streams can be satisfactorily treated and disposed. Only very low levels of bulk radiological contamination (47 picocuries/gram of 137 Cs and 3.2 picocuries/gram of 6OCo) were detected in the lead rejected for free release

  19. GLOVEBOX DISMANTLEMENT AND EQUIPMENT PROTECTION IN CONTAMINATED ENVIRONMENTS

    Energy Technology Data Exchange (ETDEWEB)

    Kitamura, Akihiro; Stallings, Ellen; Wilburn, Dianne W.

    2003-02-27

    It has been revealed from the experiences of Decontamination and Decommissioning (D&D) activities that even a small improvement in performance can result in significant risk reduction and cost savings. For example, Race Scan Ear Mic System, which was originally developed for communications between racecar drivers and crews in loud environments, has been successfully applied to D&D work and proved to enhance worker safety and communications. Glovebox dismantlement is an important and costly process in D&D activities of nuclear facilities. Adequate decontamination and size reduction of the gloveboxes are especially important in this activity because they have the potential to reduce risks and costs significantly. This paper presents some simple approaches to support D&D tasks and discusses their potential advantages. Examples discussed include: Repeated shear wiping of large pipes and ducts; Application of thin layers on radiological counters for uninterrupted use; and Partial use of robotics for glovebox dismantling. The paper also discusses schematics for protecting equipment interiors and/or glovebox inner surfaces from contamination, which may result in significant savings and waste minimization upon future dismantlement. Examples discussed include: Smart coating for contamination prevention; and Protecting equipment by geometrically simple cover.

  20. Nuclear Resonance Fluorescence for Material Verification in Dismantlement

    International Nuclear Information System (INIS)

    Nuclear resonance fluorescence (NRF) is a well-established physical process that provides an isotope-specific signature that can be exploited for isotopic detection and characterization of samples. Pacific Northwest National Laboratory has been investigating possible applications of NRF for national security. Of the investigated applications, the verification of material in the dismantlement process is the most promising. Through a combination of benchmarking measurements and radiation transport modeling, we have shown that NRF techniques with existing bremsstrahlung photon sources and a modest detection system can be used to detect highly enriched uranium in the quantities and time limits relevant to the dismantlement process. Issues such as orientation, placement and material geometry do not significantly impact the sensitivity of the technique. We have also investigated how shielding of the uranium would be observed through non-NRF processes to enable the accurate assay of the material. This paper will discuss our findings on how NRF and photon-interrogation techniques may be applied to the material verification in the dismantlement process.

  1. Report on transparency and nuclear safety 2013 - Cadarache CEA centre - Tome 1. INB 32 (ATPu) et 54 (LCP) AREVA NC - Tome 2

    International Nuclear Information System (INIS)

    A first volume proposes a presentation of the Cadarache CEA centre, of its activities and installations, gives a rather detailed overview of measures related to safety and to radiation protection within these activities and installations. It also reports significant events related to safety and to radiation protection which occurred in 2013 and have been declared to the ASN. It discusses the results of release measurements (liquid and gaseous effluents, radiological assessment, and chemical assessment for various installations) and the control of the chemical and radiological impact of these gaseous and liquid effluents on the environment. It addresses the issue of radioactive wastes which are stored in the different nuclear base installations of the Centre, indicates the different measures aimed at limiting the volume of these warehoused wastes and addresses their impact on health and on the environment. Nature and quantities of warehoused wastes are specified. The second volume concerns some specific installations (INB 32 or ATPu, and INB 54 or LPC) which belong to AREVA NC. The same topics are addressed: presentation of the facilities, arrangements regarding safety and radiation protection, significant events related to safety and radiation protection, measurements of effluents and their impact on the environment, warehoused wastes. Remarks and recommendations of the CHSCT are given

  2. 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

  3. Data Assimilation and Dismantling Waste: A Methodology Customised for Radioactive Inventory Assessment Purposes

    International Nuclear Information System (INIS)

    Data assimilation is a versatile methodology which is widely used nowadays for estimating complex system variables. The estimation of a given quantity by data assimilation involves taking into account both the observational data and the underlying physical principles governing the system under observation. Let us consider two assumptions, (1) the observational information consists of radioactivity measurements of numerous samples of graphite (or other material) from known points and (2) the physical principles are those of activation under neutron flux during nuclear power plant operation. With these two assumptions, a data-assimilation-like methodology is ready to be applied to radioactive inventory computation for dismantling graphite (or other material). The paper is written for a planned graphite disposal project in France, for the purposes of its inventory forecasting. It introduces specific concepts for activation laws, presents the beginning of the application to Bugey 1 plant pile and proposes an original method for overall error quantification. (authors)

  4. The Blue Lady Case and the International Issue of Ship Dismantling - Comment

    OpenAIRE

    Florent Pelsy

    2008-01-01

    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 distorti...

  5. Assessing the economics of processing end-of-life vehicles through manual dismantling.

    Science.gov (United States)

    Tian, Jin; Chen, Ming

    2016-10-01

    Most dismantling enterprises in a number of developing countries, such as China, usually adopt the "manual+mechanical" dismantling approach to process end-of-life vehicles. However, the automobile industry does not have a clear indicator to reasonably and effectively determine the manual dismantling degree for end-of-life vehicles. In this study, five different dismantling scenarios and an economic system for end-of-life vehicles were developed based on the actual situation of end-of-life vehicles. The fuzzy analytic hierarchy process was applied to set the weights of direct costs, indirect costs, and sales and to obtain an optimal manual dismantling scenario. Results showed that although the traditional method of "dismantling to the end" can guarantee the highest recycling rate, this method is not the best among all the scenarios. The profit gained in the optimal scenario is 100.6% higher than that in the traditional scenario. The optimal manual dismantling scenario showed that enterprises are required to select suitable parts to process through manual dismantling. Selecting suitable parts maximizes economic profit and improves dismantling speed.

  6. Radiation environment account before dismantling the conversion facilities. Evaluation of the uranium inventory and air dose rate in the dismantling facilities 2

    International Nuclear Information System (INIS)

    At the reprocessed uranium conversion facilities, Hydration and Conversion room-1,2,3, Dehydration and Conversion room-1,2, Dry process filter room have been dismantled according to the schedule, in 2009 fiscal year. The gamma-ray measurement had been carried out before dismantlement to evaluate the radioactivity inventory. As a result, the uranium recovery work was forecasted for reasonable dismantlement. In addition, the feature nuclide affecting the results of the measurement on the air dose was evaluated. Additionally, as the waste data, gamma-ray analysis results are shown. (author)

  7. Recycling of concrete generated from Nuclear Power Plant dismantling

    International Nuclear Information System (INIS)

    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)

  8. Implementing robotics in the Department of Energy Dismantlement Program

    International Nuclear Information System (INIS)

    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

  9. Evaluating and planning the radioactive waste options for dismantling the Tokamak Fusion Test Reactor

    Energy Technology Data Exchange (ETDEWEB)

    Rule, K.; Scott, J.; Larson, S. [Princeton Plasma Physics Lab., NJ (United States)] [and others

    1995-12-31

    The Tokamak Fusion Test Reactor (TFTR) is a one-of-a kind tritium fusion research reactor, and is planned to be decommissioned within the next several years. This is the largest fusion reactor in the world and as a result of deuterium-tritum reactions is tritium contaminated and activated from 14 Mev neutrons. This presents many unusual challenges when dismantling, packaging and disposing its components and ancillary systems. Special containers are being designed to accommodate the vacuum vessel, neutral beams, and tritium delivery and processing systems. A team of experienced professionals performed a detailed field study to evaluate the requirements and appropriate methods for packaging the radioactive materials. This team focused on several current and innovative methods for waste minimization that provides the oppurtunmost cost effective manner to package and dispose of the waste. This study also produces a functional time-phased schedule which conjoins the waste volume, weight, costs and container requirements with the detailed project activity schedule for the entire project scope. This study and project will be the first demonstration of the decommissioning of a tritium fusion test reactor. The radioactive waste disposal aspects of this project are instrumental in demonstrating the viability of a fusion power reactor with regard to its environmental impact and ultimate success.

  10. Conceptual Study on Dismantling of CANDU Nuclear Reactor

    Energy Technology Data Exchange (ETDEWEB)

    Jeong, Woo-Tae; Lee, Sang-Guk [KHNP-CRI, Daejeon (Korea, Republic of)

    2014-10-15

    In this paper, we reviewed 3D design model of the CANDU type reactor and suggested feasible cutting scheme. The structure of CANDU nuclear reactor, the calandria assembly was reviewed using 3-D CAD model for future decommissioning. Through the schematic diagram of CANDU nuclear power plant, we identified the differences between PWR and CANDU reactor assembly. Method of dismantling the fuel channels from the calandria assembly was suggested. Custom made cutter is recommended to cut all the fuel channels. The calandria vessel is recommended to be cut by band saw or plasma torch. After removal of the fuel channels, it was assumed that radiation level near the calandria vessel is not very high. For cutting of the end shields, various methods such as band saw, plasma torch, CAMC could be used. The choice of a specific method is largely dependent on radiological environment. Finally, method of cutting the embedment rings is considered. As we assume that operators could cut the rings without much radiation exposure, various industrial cutting methods are suggested to be applied. From the above reviews, we could conclude that decommissioning of CANDU reactor is relatively easy compared to that of PWR reactor. Technologies developed from PWR reactor decommissioning could be applied to CANDU reactor dismantling.

  11. Decontamination of dismantled parts from phosphate rock fertilizer plant decommissioning

    International Nuclear Information System (INIS)

    Decommissioning of the Uranium Recovery Section at the Phosphate Rock Fertilizer Plant in Gresik, East Java, Indonesia requires decontamination activity be applied to dismantled parts. The decontamination study has categorized the dismantled parts into three types, type A, type B and type C parts. Type A parts were the equipment having very low surface activity or below the clearance level. Type B parts were the equipment having surface activity beyond the clearance level, containing radioactive scale, which is easily removed by in situ decontamination to become parts that are useable unrestrictedly. Type C parts were the equipment having surface activity beyond the clearance level whose nature is very difficult to remove. In situ decontamination of the type B parts have been studied. Mechanical surface cleaning methods and strippable coating methods can be applied for in situ decontamination. The application of strippable coating methods with a composition of 10.0% phosphoric acid, 1.0% HEDPA, 3.0% tartaric acid, 12.0% polyvinyl alcohol and 4.3% absorbent clynoptilolyte was considered to be very effective. (author)

  12. 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.)

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

    International Nuclear Information System (INIS)

    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)

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

    International Nuclear Information System (INIS)

    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.)

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

    International Nuclear Information System (INIS)

    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)

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

    International Nuclear Information System (INIS)

    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

  17. Remote laser machining for nuclear site under dismantling (ROLD Program)

    International Nuclear Information System (INIS)

    This report describes the design, development and manufacturing of a power laser cutting tool remotely-operated, adapted to nuclear installations dismantling. The technological choices adopted for the conception of the laser robot ROLD are presented, as well as the coupling to a power laser in a real but not radioactive environment. A series of tests on sample cutting performances are presented. A complementary working program with respect to the initial one was intended for the development of an automatic cutting trajectory teaching system. A three dimensional laser camera, assisted by a proximity sensor by optical triangulation would allow to create a picture of the cutting scene which would have been used for the trajectory calculation. The trials have not yet been successful, but the results are presented in the report

  18. Method and jig for dismantling nuclear fuel assembly

    Energy Technology Data Exchange (ETDEWEB)

    Urata, Megumi; Watahiki, Minoru.

    1989-08-30

    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.).

  19. 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......-based innovation, the current transformation ofsound amplification from conventional to digital amplifiers. We study the early formation of thisnew technology as especially reflected in the particularly dynamic cluster of innovation inDenmark and extend the analysis to the global strategizing around this new...

  20. Fast and simple decycling and dismantling of networks

    CERN Document Server

    Zdeborová, Lenka; Zhou, Hai-Jun

    2016-01-01

    Decycling and dismantling of complex networks are underlying many important applications in network science. Recently these two closely related problems were tackled by several heuristic algorithms, simple and considerably sub-optimal, on the one hand, and time-consuming message-passing ones that evaluate single-node marginal probabilities, on the other hand. In this paper we propose a simple and extremely fast algorithm, CoreHD, which recursively removes nodes of the highest degree from the $2$-core of the network. CoreHD performs much better than all existing simple algorithms. When applied on real-world networks, it achieves equally good solutions as those obtained by the state-of-art iterative message-passing algorithms at greatly reduced computational cost, suggesting that CoreHD should be the algorithm of choice for many practical purposes.

  1. 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.

  2. NucLab Marcoule: A dedicated waste management and dismantling support laboratory

    International Nuclear Information System (INIS)

    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.

  3. Multiparameter optimisation of dismantling activities and waste management at a research centre

    International Nuclear Information System (INIS)

    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

  4. Systems analysis of radiation safety during dismantling of power-plant equipment at a nuclear power station

    International Nuclear Information System (INIS)

    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

  5. Adapting Dismantling and Decommissioning Strategies to a Variety of Nuclear Fuel Cycle Facilities - 12237

    International Nuclear Information System (INIS)

    AREVA has accumulated over 20 years of experience in managing and operating fuel cycle facilities Decontamination and Decommissioning (D and D) projects of many different types and a variety of scales, both as facility owner (at La Hague for example) and as prime contractor to external customers such as the French Atomic Energy Commission (at Marcoule). A specific Business Unit was created in 2008 to capitalize on this experience and to concentrate - in one division - the specific skills required to be successful and cost effective in decommissioning projects. Indeed one of the key lessons learned in the past decades is that decommissioning is a significantly different business as compared to normal operations of a nuclear facility. Almost all the functions of a project need to be viewed from a different angle, challenged and adapted consequently in order to optimize costs and schedule. Three examples follow to illustrate the point: Safety management needs to take into account the ever changing configuration of a plant under D and D (a quite new situation for the authorities). Production of waste is significantly different in term of volume, activities, conditioning and disposal path. Technology is important but technical issues are often less critical than good management and planning. Further examples and lessons learned are developed through reviewing the projects experience basis. AREVA has a long and vast experience in the cleanup and dismantling of a number of very large and complex nuclear facilities. This effort focused initially on AREVA's own plants and is expanding now to other customers. The setup of a specific Business Unit in 2008 to takeover this business allowed concentration of the skills and the lessons learned in a dedicated division so as to provide the best means to optimize safety, performance, costs and schedules. Indeed transitioning from operations to D and D of a nuclear facility is a quantum leap. The assistance from specialized teams can

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

    International Nuclear Information System (INIS)

    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

  7. 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.

  8. Design and trial fabrication of a dismantling apparatus for irradiation capsules of solid tritium breeder materials

    Energy Technology Data Exchange (ETDEWEB)

    Hayashi, K. [Japan Atomic Energy Agency, Blanket Irradiation and Analysis Group, Fusion Research and Development Directorate, 4002 Narita-cho, Oarai-machi, Ibaraki-ken 311-1393 (Japan)], E-mail: hayashi.kimio@jaea.go.jp; Nakagawa, T.; Onose, S.; Ishida, T.; Nakamichi, M. [Japan Atomic Energy Agency, Blanket Irradiation and Analysis Group, Fusion Research and Development Directorate, 4002 Narita-cho, Oarai-machi, Ibaraki-ken 311-1393 (Japan); Takatsu, H. [Fusion Energy and Development Directorate, Japan Atomic Energy Agency, 801-1 Mukouyama, Naka-shi, Ibaraki-ken 311-0193 (Japan); Nakamura, M.; Noguchi, T. [Kaken, Inc., 873-3 Shikada, Hokota-shi, Ibaraki-ken, 311-1416 (Japan)

    2009-04-30

    Irradiation experiments of solid breeder materials including Li{sub 2}TiO{sub 3} have been being carried out in preparation for a test blanket module (TBM) of the International Thermonuclear Experimental Reactor (ITER). The present paper deals with design and trial-fabrication works for developing a dismantling apparatus for the irradiation capsules. The dismantling process leads to release of tritium which is left in free volumes of the capsule or in the breeder specimens. In the design of the dismantling apparatus, the released tritium is recovered safely by a purge-gas system during the cutting of the irradiation capsule by a band saw, and then the tritium is consolidated into a radioactive waste. Furthermore, an inner-box enclosing the dismantling apparatus works as a countermeasure of possible release of tritium in accidental events. Good performance of a trial fabrication model of the dismantling apparatus has been demonstrated by preliminary cutting runs using some mockups simulating the irradiation capsules. Thus, the present design of the apparatus, together with the trial mock-up runs, will contribute to the design of the TBM structure and to the planning of the dismantling process of the TBM.

  9. Design and trial fabrication of a dismantling apparatus for irradiation capsules of solid tritium breeder materials

    International Nuclear Information System (INIS)

    Irradiation experiments of solid breeder materials including Li2TiO3 have been being carried out in preparation for a test blanket module (TBM) of the International Thermonuclear Experimental Reactor (ITER). The present paper deals with design and trial-fabrication works for developing a dismantling apparatus for the irradiation capsules. The dismantling process leads to release of tritium which is left in free volumes of the capsule or in the breeder specimens. In the design of the dismantling apparatus, the released tritium is recovered safely by a purge-gas system during the cutting of the irradiation capsule by a band saw, and then the tritium is consolidated into a radioactive waste. Furthermore, an inner-box enclosing the dismantling apparatus works as a countermeasure of possible release of tritium in accidental events. Good performance of a trial fabrication model of the dismantling apparatus has been demonstrated by preliminary cutting runs using some mockups simulating the irradiation capsules. Thus, the present design of the apparatus, together with the trial mock-up runs, will contribute to the design of the TBM structure and to the planning of the dismantling process of the TBM.

  10. 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.

  11. Proceedings of the workshop on transite decontamination dismantlement and recycle/disposal

    International Nuclear Information System (INIS)

    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 m2 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

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

    International Nuclear Information System (INIS)

    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

  13. Management of wastes from dismantled nuclear power plants

    International Nuclear Information System (INIS)

    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 60Co (after some fifty years this radioisotope will have decayed sufficiently to enable it to be stored without shielding); the presence of 63Ni and 59Ni (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

  14. 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

    dismantling project (FEBEX-DP) are: - Characterization of the key physical properties (e.g., density, water content) of the barrier and their distribution, - Characterization of corrosion and microbiological processes on instruments and coupons resulting from evolving redox conditions and saturation states, including gas analysis, - Characterization macro- and micro level studies of mineralogical interactions at material interfaces (e.g., cement-bentonite or iron-bentonite, rock-bentonite), - Assessment of sensor performance, - Further increasing understanding of the thermo-hydro-mechanical (THM) and thermo-hydro-chemical (THC) processes through integration of monitoring and dismantling results. An intensive laboratory program will be conducted in 2015/2016 in order to achieve the outlined main objectives. It includes extensive mineralogical, chemical and biological investigations of the buffer and the related interfaces. It will be accompanied by pre- and post dismantling modeling efforts. Unique data are expected after completing one of the longest running 1:1 in-situ EBS experiment under continued heating and natural saturation conditions. It will further consolidate the EBS knowledge and will act as a benchmark for major coupled modeling codes. The dismantling project is set-up as an international project with partners from Europe, Asia and North America. Further information can are under http://www.grimsel.com/gts-phase-vi/febex-dp/febex-dp-introduction.

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

    International Nuclear Information System (INIS)

    dismantling project (FEBEX-DP) are: - Characterization of the key physical properties (e.g., density, water content) of the barrier and their distribution, - Characterization of corrosion and microbiological processes on instruments and coupons resulting from evolving redox conditions and saturation states, including gas analysis, - Characterization macro- and micro level studies of mineralogical interactions at material interfaces (e.g., cement-bentonite or iron-bentonite, rock-bentonite), - Assessment of sensor performance, - Further increasing understanding of the thermo-hydro-mechanical (THM) and thermo-hydro-chemical (THC) processes through integration of monitoring and dismantling results. An intensive laboratory program will be conducted in 2015/2016 in order to achieve the outlined main objectives. It includes extensive mineralogical, chemical and biological investigations of the buffer and the related interfaces. It will be accompanied by pre- and post dismantling modeling efforts. Unique data are expected after completing one of the longest running 1:1 in-situ EBS experiment under continued heating and natural saturation conditions. It will further consolidate the EBS knowledge and will act as a benchmark for major coupled modeling codes. The dismantling project is set-up as an international project with partners from Europe, Asia and North America. Further information can are under http://www.grimsel.com/gts-phase-vi/febex-dp/febex-dp-introduction.

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    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.

  17. Analysis of radwaste management alternatives during dismantling of Ignalina NPP systems with low level contamination

    Energy Technology Data Exchange (ETDEWEB)

    Poskas, Gintautas [Lithuanian Energy Institute, Kaunas (Lithuania). Nuclear Engineering Lab.; Kaunas Univ. of Technology (Lithuania); Poskas, Povilas; Simonis, Audrius [Lithuanian Energy Institute, Kaunas (Lithuania). Nuclear Engineering Lab.

    2013-12-15

    Ignalina NPP was operating two RBMK-1500 reactors which are under decommissioning now. In this paper, analysis on radwaste management alternatives during the dismantling of systems with low level contamination and different types of components in buildings 117/1 and V1 are presented. After situation analysis and collection of the primary information related to components' physical and radiological characteristics, location and other data, two alternatives for radwaste management during the dismantling were formulated and evaluated: the first one (A1) when the decontamination of the dismantled components is performed (if it is reasonable), and the second one (A2) when no decontamination of the dismantled components is performed and after the dismantling, the components are routed to appropriate waste storage or disposal sites. To select the preferable alternative, MCDA method - AHP (Analytic Hierarchy Process) is applied. Hierarchical lists of decision criteria, necessary for assessment of alternatives performance, are formulated. Quantitative decision criteria values for these alternatives are calculated using software DECRAD, which was developed by Lithuanian Energy Institute Nuclear Engineering Laboratory. Qualitative decision criteria are evaluated using expert judgment. Analysis results show that alternative A1 has a preference against alternative A2. (orig.)

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

    International Nuclear Information System (INIS)

    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.)

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

    International Nuclear Information System (INIS)

    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

  20. Rockwell International Hot Laboratory decontamination and dismantlement interim progress report 1987-1996

    Energy Technology Data Exchange (ETDEWEB)

    None

    1997-05-06

    OAK A271 Rockwell International Hot Laboratory decontamination and dismantlement interim progress report 1987-1996. The Rockwell International Hot Laboratory (RIHL) is one of a number of former nuclear facilities undergoing decontamination and decommissioning (D&D) at the Santa Susana Field Laboratory (SSFL). The RIHL facility is in the later stages of dismantlement, with the final objective of returning the site location to its original natural state. This report documents the decontamination and dismantlement activities performed at the facility over the time period 1988 through 1996. At this time, the support buildings, all equipment associated with the facility, and the entire above-ground structure of the primary facility building (Building 020) have been removed. The basement portion of this building and the outside yard areas (primarily asphalt and soil) are scheduled for D&D activities beginning in 1997.

  1. Decommissioning: dismantling of thickwalled steel structures using the contact-arc-metal-drilling technique. Final report

    International Nuclear Information System (INIS)

    1. Status of the technology: Today austenitic steel components with a material thickness of more than 200 mm cannot be cut surely by using conventional thermal cutting techniques. A reduction of the wall thickness, by using an effective cutting technique with low restoring forces, is necessary but not available, now. 2. Objectives: Target of the project was the qualification of the thermal contact-arc-metal-drilling technique, based on the contact-arc-metal-cutting technique for the reduction of the wall thickness of steel components in preparation for other cutting techniques to finish the dismantling task if necessary. 3. Methode: Development of the contact-arc-metal-drilling technique for the production of deep (>200 mm) blind holes with non-circular cross sections. Optimization of the drilling parameters and quantification of the released emissions under a radiological aspect. Development of a monitoring system for the electrode wear and a device for changing weared electrodes automatically. 4. Result: The contact-arc-metal-drilling technique was qualified by producing blind holes with a depth of 230 mm. The aerosols, hydrosols and gas emissions of the process were quantified and various monitoring techniques for the wear of the electrode were tested. A pneumatically aided clamping and changing device for electrodes was designed and tested. 5. Applications: The designed clamping device with its integrated pneumatically aided electrode release can be adapted directly to a tool guiding machine. Using this cutting technique steel components with a material thickness of 230 mm can be reduced to a remaining wall thickness and the released emissions can be estimated. (orig.)

  2. Polychlorinated biphenyls (PCBs) in the frame of the dismantling of nuclear facilities

    International Nuclear Information System (INIS)

    During construction and maintenance of nuclear facilities PCB (polychlorinated biphenyls) containing paints were used in a large extent in the past. The WAK dismantling and disposal Company has dismantles such facilities and identified the PCB in the buildings. Besides the radionuclides the conventional hazardous material group of the PCBs has also to be disposed. The respective legal regulations have to be considered. In the frame of the contribution the radiological release of building structures with respect to re-use or demolition and residual PCB containing materials is discussed. The radiological disposal in final repositories and the conventional disposal regulations for releasable residual wastes are reported.

  3. Transport and the dismantling of nuclear facilities; Les transports lies a la deconstruction des installations nucleaires

    Energy Technology Data Exchange (ETDEWEB)

    Hartenstein, M.

    2011-11-15

    Transport is not a real limiting constraint for the dismantling of nuclear facility if transport is taking into account very early in the dismantling process since numerous packages in various sizes already exist. For instance the TN-Gemini package allows the constitution of B-type packages for high radioactive level wastes, its volume capacity of about 16 m{sup 3} can store up to 5.8 tones of wastes, its external dimensions make it look like a sea container. One difficulty would be to find the adequate waste classification for a package containing heterogeneous wastes. (A.C.)

  4. Health and Safety Considerations Associated with Sodium-Cooled Experimental Nuclear Fuel Dismantlement

    Energy Technology Data Exchange (ETDEWEB)

    Carvo, Alan E. [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2015-04-01

    Between the mid-1970s and the mid-1980s Sandia National Laboratory constructed eleven experimental assemblies to simulate debris beds formed in a sodium-cooled fast breeder reactor. All but one of the assemblies were irradiated. The experimental assemblies were transferred to the Idaho National Laboratory (INL) in 2007 and 2008 for storage, dismantlement, recovery of the uranium for reuse in the nuclear fuel cycle, and disposal of unneeded materials. This paper addresses the effort to dismantle the assemblies down to the primary containment vessel and repackage them for temporary storage until such time as equipment necessary for sodium separation is in place.

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

    International Nuclear Information System (INIS)

    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 m2 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.)

  6. Days of dismantling activities of installations and rehabilitation of contaminated sites in France

    International Nuclear Information System (INIS)

    The objective of these days, organized by the section environment of the French society of radiation protection, is to present a panorama of the activities of nuclear installations dismantling and contaminated sites rehabilitation in France, by leaning in the same time on practical cases and by stating the French rule and the national and international recommendations on the subject. These days have also for object to approach the stakes associated with the sectors of waste management and the materials generated by these activities and in a more general way, the stakes to come for the different actors of the dismantling and the rehabilitation. (N.C.)

  7. 49 CFR 1242.37 - Dismantling retired property and depreciation (accounts XX-26-39 and 62-26-00).

    Science.gov (United States)

    2010-10-01

    ... 49 Transportation 9 2010-10-01 2010-10-01 false Dismantling retired property and depreciation (accounts XX-26-39 and 62-26-00). 1242.37 Section 1242.37 Transportation Other Regulations Relating to... FOR RAILROADS 1 Operating Expenses-Equipment § 1242.37 Dismantling retired property and...

  8. 49 CFR 1242.51 - Dismantling retired property and depreciation (accounts XX-27-39 and 62-27-00).

    Science.gov (United States)

    2010-10-01

    ... 49 Transportation 9 2010-10-01 2010-10-01 false Dismantling retired property and depreciation (accounts XX-27-39 and 62-27-00). 1242.51 Section 1242.51 Transportation Other Regulations Relating to... FOR RAILROADS 1 Operating Expenses-Equipment § 1242.51 Dismantling retired property and...

  9. The PCR (Prévessin Control Room), scene of some of the greatest moments in CERN's history, is being dismantled to prepare for a complete overhaul.

    CERN Multimedia

    Maximilien Brice

    2004-01-01

    Removal manager Claes Frisk (right on picture 02) in the almost entirely dismantled PCR, together with René Ballet, who installed the racks in the 1970s and today is responsible for dismantling them.

  10. Investigation and design of the dismantling process of irradiation capsules containing tritium. 2. Detailed design and trial fabrication of capsule dismantling apparatus and investigation of glove box facility

    International Nuclear Information System (INIS)

    In-pile functional tests of breeding blankets have been planned by Japan Atomic Energy Agency (JAEA), using a test blanket module (TBM) which will be loaded in the International Thermonuclear Experimental Reactor (ITER). In preparation for the in-pile functional tests, JAEA has been performing irradiation experiments of lithium titanate (Li2TiO3), which is the first candidate of solid breeder materials for the blanket of the demonstration reactor (DEMO) under designing in Japan. The present report describes 1) results of a detailed design and trial fabrication tests of a dismantling apparatus for irradiation capsules which were used in irradiation experiments by the Japan Materials Testing Reactor (JMTR) of JAEA, and 2) results of a preliminary investigation of a glove box facility for post-irradiation examinations (PIEs). In the detailed design of the dismantling apparatus, detailed specifications and the installation methods were examined, based on results of a conceptual design and basic design which were carried out before the present work. In the trial fabrication, cutting tests were curried out by making a mockup of a cutting component, which is a key component of the dismantling apparatus, as well as some simulated JMTR irradiation capsules. Good cutting performance was attained by optimizing the cutting speed, through repeated reviews of the results of the trial fabrication tests. In addition, improvement of the capsule clamping mechanism brought a prospect for feasibility of the apparatus in terms of operational convenience such as setting and removal, respectively, of the capsule before and after the cutting. Furthermore, a preliminary investigation of a glove box facility was carried out in order to secure a facility for PIE work after the capsule dismantling, which revealed a technical feasibility. (author)

  11. A state-of-the art on the dismantling techniques for the KRR-1 and 2 decommissioning

    International Nuclear Information System (INIS)

    The status of the dismantling technology of such countries with decommissioning experience as Germany, Japan, USA and Belgium, was investigated on the appropriate selection for the dismantling method on the Korean Research Reactors 1 and 2(KRR- 1 and 2) decommissioning program. Especially, the cutting technology and its application were inspected for effective dismantling of the metal and concrete in the nuclear facilities. The cutting technology was largely divided into thermal, mechanical and electrical method and the status of its development was studied by each nations. And the status of the remote controlled dismantling technology by using a robot manipulation system in USA was investigated, and this technology also was compared with the manual work about the effect on the reduction of the worker exposure and saving the cost. In addition, the applicability of the dismantling technology to Korean Research Reactor 1 and 2

  12. The radiological consequences of delaying the final dismantling of a Magnox nuclear power station

    International Nuclear Information System (INIS)

    The timing of the final dismantling process after shutdown and decommissioning of Magnox power stations will depend on balancing the need to reuse the site against the advantages of allowing residual radioactivity to decay. A delay of 130 years would reduce the dose commitment to dismantling staff as far as practicable and remove the need to depend on robotic systems. This in turn would lead to cost savings of about Pound 800M, at 1986 prices, totalled over all the CEGB's Magnox power. If final dismantling were to be delayed, it is intended that the residual reactor building would be maintained in a sealed, weathertight condition, and it is confidently expected that this will be achieved. This report investigates the consequences of any failure in this containment using, as a demonstration of the robustness of the radiological case for delay, some extreme scenarios in which the nuclear island is presumed to have collapsed. To demonstrate the robustness of the case for delay, the radiological consequences over a time period, which is roughly one order of magnitude both greater and smaller than the 130 y optimum are considered. The radiological consequences which might result, over a 1500 year period, from the leakage of radioactive materials from the reactor structure in the event that final dismantling were to be delayed are determined. Any engineering constraints which these radiological consequences might impose are discussed. (author)

  13. Dismantling of nuclear power plants: the audit office calls EdF to order

    International Nuclear Information System (INIS)

    The audit office has questioned Electricite de France (EdF) about its capacity to finance the dismantling operation of its nuclear power plants and the long-term management of radioactive wastes. The French government, who is the last responsible parties, must clarify this situation in particular in the prospect of a partial privatization of EdF. Short paper. (J.S.)

  14. Value estimation of end of life vehicles as a source of competitive advantage for dismantling station

    Directory of Open Access Journals (Sweden)

    Monika Kosacka

    2016-03-01

    Full Text Available   Background: End of Life vehicles become an emerging problem because of the type of waste which they are. Each country is creating own recycling network where ELVs are well secured and recycled. Poland is a country where the system is not working correct because of a high absorption of ELVs by illegal dismantling entities which are more competitive than legal elements of recycling network. The problem is well known but there is still lack of solution. The purpose of this article is to present the concept of tools for the valuation of ELVs in order to improve the competitiveness of disassembly stations. Methods: The research methodology consists of a literature review as well as observations, surveys, BPMN and UML diagrams. On the basis of literature review and observations the problem was identified. The surveys were elaborated in order to identify requirements for the concept of the tool. BPMN and UML diagrams were used to model the processes in dismantling station and the information flow between the user and the tool. Results: There was established a concept of the tool - ELV's Calculator which support decisions of ELV's value estimation. Conclusions: Improving competitiveness of legal dismantling station is extremely important issue in order to provide safe for Environment and People and economically justified ELVs' management. Legal entities have to follow the law what makes their business cost higher. This paper provides a solution of encouraging people to return ELVs to legal dismantlers by offering them price adequate to market demand.    

  15. Exploring the Development and Dismantling of Equivalence Classes Involving Terrorist Stimuli

    Science.gov (United States)

    Dixon, Mark R.; Rehfeldt, Ruth Anne; Zlomke, Kimberly R.; Robinson, Ashton

    2006-01-01

    The present paper describes 2 studies that present a conceptual interpretation and experimental findings involving the developing and dismantling of equivalence classes consisting of terrorist stimuli. In the first study, 8 United States citizen participants were trained to match nonterrorist stimuli to American and terrorist images. Afterwards,…

  16. Sustainable design for automotive products: dismantling and recycling of end-of-life vehicles.

    Science.gov (United States)

    Tian, Jin; Chen, Ming

    2014-02-01

    The growth in automotive production has increased the number of end-of-life vehicles (ELVs) annually. The traditional approach ELV processing involves dismantling, shredding, and landfill disposal. The "3R" (i.e., reduce, reuse, and recycle) principle has been increasingly employed in processing ELVs, particularly ELV parts, to promote sustainable development. The first step in processing ELVs is dismantling. However, certain parts of the vehicle are difficult to disassemble and use in practice. The extended producer responsibility policy requires carmakers to contribute in the processing of scrap cars either for their own developmental needs or for social responsibility. The design for dismantling approach can be an effective solution to the existing difficulties in dismantling ELVs. This approach can also provide guidelines in the design of automotive products. This paper illustrates the difficulty of handling polymers in dashboards. The physical properties of polymers prevent easy separation and recycling by using mechanical methods. Thus, dealers have to rely on chemical methods such as pyrolysis. Therefore, car designers should use a single material to benefit dealers. The use of materials for effective end-of-life processing without sacrificing the original performance requirements of the vehicle should be explored. PMID:24326159

  17. Design approach of irradiated sample/capsule dismantling machine for use in hot cell

    International Nuclear Information System (INIS)

    The main job of designing a machine for purpose boils down to a selection process from the available tools/techniques satisfactory to the five issues noted above. The paper deals with the dismantling of a typical irradiated capsule of 50R/hr

  18. Deny, Distance, or Dismantle? How White Americans Manage a Privileged Identity.

    Science.gov (United States)

    Knowles, Eric D; Lowery, Brian S; Chow, Rosalind M; Unzueta, Miguel M

    2014-11-01

    Social scientists have traditionally argued that whiteness-the attribute of being recognized and treated as a White person in society-is powerful because it is invisible. On this view, members of the racially dominant group have the unique luxury of rarely noticing their race or the privileges it confers. This article challenges this "invisibility thesis," arguing that Whites frequently regard themselves as racial actors. We further argue that whiteness defines a problematic social identity that confronts Whites with 2 psychological threats: the possibility that their accomplishments in life were not fully earned (meritocratic threat) and the association with a group that benefits from unfair social advantages (group-image threat). We theorize that Whites manage their racial identity to dispel these threats. According to our deny, distance, or dismantle (3D) model of White identity management, dominant-group members have three strategies at their disposal: deny the existence of privilege, distance their own self-concepts from the White category, or strive to dismantle systems of privilege. Whereas denial and distancing promote insensitivity and inaction with respect to racial inequality, dismantling reduces threat by relinquishing privileges. We suggest that interventions aimed at reducing inequality should attempt to leverage dismantling as a strategy of White identity management. PMID:26186110

  19. Adaptation of high pressure water jets with abrasives for nuclear installations dismantling

    International Nuclear Information System (INIS)

    This report presents the work realized for adjust the cutting technology with high pressure water jet with abrasives for nuclear installation dismantling. It has necessited the conception and the adjustement of a remote tool and the realization of cutting tests with waste produce analysis. This technic can be ameliorated with better viewing systems and better fog suction systems

  20. Process for dismantling of burnt-up nuclear reactor fuel rods

    International Nuclear Information System (INIS)

    In order to dismantle burnt-up fuel elements made from zirconium alloys, these are hydrated in a hydrogen atmosphere at 300-4000C and after cooling are broken up in a breaking machine, making use of their brittleness. This scrap is then taken for reprocessing. (orig.)

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

    International Nuclear Information System (INIS)

    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.)

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

    International Nuclear Information System (INIS)

    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

  3. A study of a decommissioning activities classification structure for decommissioning of the project management of a nuclear power plant

    International Nuclear Information System (INIS)

    Decommissioning activities and requirements that was established in the planning stage should be organized systematically in the course of dismantling the NPP. The work breakdown structure is essential to ensuring that all the project scope is identified, estimated and executed. The project manager needs to ensure that a WBS is established early in the project and maintained throughout the project life cycle. A project management system is ongoing under the circumstance of having no experience dismantling the NPP. The system related to the NPP decommissioning should have technical criteria as well as regulatory requirements in the full scale of decommissioning stage. In the dismantling stage, decommissioning plan document should include the results of radiation/radioactivity characterization, evaluation of the amount of dismantled waste, calculation of the expose dose rate, evaluation of decommissioning cost and schedule after shutdown

  4. D and D projects trends

    International Nuclear Information System (INIS)

    This series of slides presents: 1 - the Various types of needs and types of operations in any D and D project, 2 - the strong variety of nuclear units to dismantle, 3 - the D and D dependence on nuclear operators' strategy (Immediate/Deferred dismantling), 4 - the demand for D and D services with respect to the ageing of the nuclear fleet, 5 - the impacts to come on the D and D environment due to the Fukushima accident, 6 - the geographical dependence of D and D demands, 7 - the different D and D choices from nuclear operators in the supply chain management, 8 - the key levers in a D and D project performance, 9 - Some key competencies in D and D, 10 - Risk management for both clients and suppliers in a D and D project, 11 - AREVA involvement in Fukushima project as a key demonstration of a critical D and D project management

  5. Discussions on JNC roles and issues on management and disposition of surplus plutonium from the dismantlement of nuclear warhead

    International Nuclear Information System (INIS)

    Japan Nuclear Cycle Development Institute (JNC) and Russian Federation are now promoting the collaborative project to use the fast breeder reactor of BN-600 for the Russian surplus plutonium under the framework of the bilateral agreement on peaceful use of atomic energy. Based upon this background, JNC organized a study group to survey the world aspect on surplus plutonium resulting in START (Strategic Arms Reduction Treaty). The study group, including technical experts and also experts on international affairs, made a report after their survey and gave wide range discussion on various issues. The surplus plutonium of Russian Federation was estimated to be 102 - 136 tones. There were shortages of back end technologies in Russian infrastructures for dismantling, reprocessing and disposition of the surplus plutonium. A supporting leadership of USA to Russian Federation met some difficulties due to the strategic gap between both countries. One of the examples is the temporal evolution of USA attitude toward the CANDU (thermal power reactors of Canadian design characterized by heavy water moderator, pressure tube construction, and on-power refuelling) option to use surplus plutonium as MOX (Mixed OXide) fuels. Additional supports from the G8 (Group of eight) countries except USA and Russian Federation came up to their expectation. For examples, the joint group of French, German and Russian is promoting DEMOX (Demonstration of MOX fuel) project but is on the way to discussion depending on various thoughts about mutual benefits. Many issues remained in joint project with CIS (Commonwealth of Independent States), such as safeguard, nonproliferation, energy supply and demand, and environmental impacts. In addition, public opinions will give some impacts to policy makers, especially in USA. This report had analyzed many viewpoints for technical and political issues on surplus plutonium in the world, and pointed out consequences, merits and demerits after possible many

  6. Laser dismantling of PHWR spent fuel bundles and decladding of fuel pins in the highly radioactive hot cells

    International Nuclear Information System (INIS)

    Full text: For reprocessing of PHWR fuel, fuel bundles are at present chopped mechanically into small pieces of pins using high tonnage mechanical press before dissolution. The existing method of bundle dismantling is purely mechanical using very high force for chopping. A laser based automated bundle dismantling system is developed. In the system, end-plates of bundle, which holds the fuel pins together, are cut using Nd-YAG laser to separate the bundles into pins. In addition to pin separation, the pins are to be chopped into small pieces using a small mechanical chopper. Since the spent fuel is highly radioactive, all these operations are performed remotely in hot cells. Post irradiation examination also requires dismantling of bundles into pins so that they can select the pins for the further examinations. In both these applications laser dismantling remains the most. important step and this system has been developed and tested. This paper describes the experience gained during the development efforts

  7. Radiation protection aspects of established dismantling and decontamination technologies. Information and experiences from the decommissioning of nuclear facilities; Strahlenschutzaspekte gaengiger Abbau- und Dekontaminationstechniken. Informationen und Erfahrungen aus der Stilllegung kerntechnischer Anlagen

    Energy Technology Data Exchange (ETDEWEB)

    Kaulard, Joerg; Brendebach, Boris; Strub, Erik

    2010-12-15

    The report covers the following topics: the concept of an idealized dismantling technology selection process, examples on aspects of the dismantling strategy,features of dismantling and decontamination technologies in the frame of radiation protection aspects, examples of dismantling technologies based on the features of the German decommissioning practice (NPPs Greifswald, Wuergassen, Stade, Gundremmingen, research reactors Kahl, KNK and MZFR) experiences on radiation protection aspects with decontamination and dismantling technologies.

  8. Radiation monitoring during the last stage of the dismantling of the system in the CIEMAT-04

    International Nuclear Information System (INIS)

    Various operations which include the removal of irradiated fuel storage ten wells have been during this final stage. The SPR has established since the start of these operations a radiological surveillance program of workers that includes the use of official external dosimetry and direct-reading, and the control of internal contamination (direct and indirect measurements), in addition to daily monitoring of environmental pollution and external contamination. After decontamination and dismantling operations, there are plans to tackle the final characterisation of the installation and the declassification of the material generated as declassificable. As stage one of these processes has been developed an isotope-type from the analytical results of samples operational s taken from the Home of this last stage of dismantling. (Author)

  9. Back to the green field - Niederaichbach nuclear power plant faces total dismantling

    International Nuclear Information System (INIS)

    Following its shut-down in 1974, the Niederaichbach 100 MW nuclear power plant was placed in a state of 'Safe Containment'. Continuation of this heavy-water plant in this state was licensed by authorities in 1981. Safe containment as the first decommissioning step was effected with a view to cost minimization in order to maintain the plant in the licensed state as well as to have sufficient time for planning its complete dismantling and removal. Planning activities were concluded by now. Dismantling license may be expected to be issued at the beginning of 1986. Complete disassembly of the plant will furnish proof for safe technical control of nuclear power plants from 'the cradle to the grave'. (orig.)

  10. Decommissioning and dismantling of nuclear reactors and nuclear spent fuel interim storage in Germany

    International Nuclear Information System (INIS)

    The authors visited Germany in April 2013 to investigate state of reactor decommissioning and dismantling and interim storage of spent fuels reflecting nuclear power phaseout policy after the Fukushima accident. They visited interim storage facilities of radioactive wastes (ZLN, Zwischenlanger Nord) and central active workshop (ZAW, Zentrale Aktive Werkstatt) at Greifswald, and interim storage facilities of spent fuels at Philippsburg. CASTOR (Cask for Storage and Transport of Radioactive Material) was used for interim storage of spent fuels and high-level wastes for 40 years. Amount of wastes produced by decommissioning and dismantling was estimated 1800 ktons consisting of 1200 ktons non-radioactive and 600 ktons radioactive wastes, 500 ktons of which could be decontaminated less than clearance level and 100 ktons of which were obliged to be stored as radioactive wastes. New geological repository site for high level radioactive wastes should be found and developed. (T. Tanaka)

  11. A working class critique to the bourgeois policies of dismantling the full tenure and perpetuating renewable contracts affecting library workers

    OpenAIRE

    Muela-Meza, Zapopan Martín

    2014-01-01

    This paper, “A working class critique to the bourgeois policies of dismantling the full tenure and perpetuating renewable contracts affecting library workers” analyses this research problem: What are some of the most adverse effects of the burgeois policies of their labor flexibility and precariousness by dismantling the lack of labor tenure and promotion, and by perpetuating the renewal of contracts affecting social and labor stability and thus their humane living conditions, health, and hap...

  12. Mobile Work Platform - A Fluor Fernald innovative dismantlement technology

    International Nuclear Information System (INIS)

    The Department of Energy's (DOE) Office of Science and Technology Decontamination and Decommissioning (D andD) Focus Area, led by the National Energy Technology Laboratory, has been charged with finding new and innovative D and D technologies and then validating through field demonstration that the technologies are safer, faster and/or more cost-effective. The D and D Focus Area's approach to verifying the benefits of the improved D and D technologies is to use them at DOE sites in large-scale demonstration and deployment (LSDD) projects. The DOE's Fernald Environmental Management Project (FEMP), near Cincinnati Ohio, was host for a LSDD Project overseen by the D and D Focus Area. The FEMP was formerly engaged in the production of high quality uranium metal; and is now currently undergoing active environmental restoration, including removal of major process facilities. As observed during the D and D of Fernald's Plant 1, the baseline method for removing piping required laborers to work above the floor on ladders, scaffolding, ardor man-lifts with hand-held power tools. The pipe must first be rigged to prevent falling when cut. After cutting, the pipe is manually lowered to the ground and placed in a storage/disposal container. The Mobile Work Platform (MWP) consists of a mobile chassis, telescoping arm and a dual crimper/shear ''end-effecter''. It has the capability to grab and hold a pipe, crimp and shear the pipe (up to a ten-foot section) on either side of where it is being held and then lower and place the pipe section into a storage/disposal container. The MWP can crimp/shear up to a 6-inch diameter, schedule 401, carbon steel pipe. A single operator using a radio remote control operates the MWP. The paper will describe the results (productivity, safety advantages and lessons learned) during the Mobile Work Platform demonstration at Fernald

  13. Project Feedback Experience

    International Nuclear Information System (INIS)

    In the financial responsibility of the Karlsruhe Research Center 5 reactors and 1 reprocessing plant are being decommissioned with these activities reaching a total volume of 2 billion Euros. Three reactor projects have already been completed: The FR 2 research reactor is in the state of safe enclosure i.e., only the reactor pressure vessel and its internals are in place. Apart from that the reactor building is empty. The reactors KKN and HDR have been dismantled completely and the sites have been re-cultivated (green field) again. The state of the other projects are as follows: - Multi Purpose Research Reactor (MZFR): remote controlled dismantling of the reactor vessel and internals; - Compact Sodium Cooled Reactor (KNK): installation of the equipment for the remote controlled dismantling of the reactor tank and its internals; - Karlsruhe Reprocessing Plant (WAK): decontamination of the process cells, construction of a vitrification facility for the treatment of the high-active waste concentrate (HAWC) and commission of the equipment for the segmentation of the HAWC storage tanks. The experience gained so far with regard to the technology applied and the licensing procedure will be described and discussed in the paper. The decommissioning progress is decisively determined by the direct treatment and disposal of the generated radioactive wastes. The FZK facilities and processing units available for this purpose will be also presented. Furthermore, the consequences of establishing specific organizational units as well as of a consistent project management will be outlined. (author)

  14. 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.

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

    International Nuclear Information System (INIS)

    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

  16. 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.

  17. Further retardation could lead to a hold-up of nuclear reactor dismantling

    International Nuclear Information System (INIS)

    The following issues concerning the consequences of the German nuclear power phaseout are discussed: the cost of reactor dismantling could increase; the complete deconstruction of a nuclear power plant including environmental revitalization take a time of 10-15 years; the largest challenge is the still unsolved problem of final disposal; further retardations could trigger a complete deadlock of the deconstruction due to completely filled interim storage facilities. A further problem is the knowledge preservation due to the lack of students.

  18. 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)

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

    International Nuclear Information System (INIS)

    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)

  20. Study on Evaluation of Project Management Data for Decommissioning of Uranium Refining and Conversion Plant - 12234

    Energy Technology Data Exchange (ETDEWEB)

    Usui, Hideo; Izumo, Sari; Tachibana, Mitsuo [Japan Atomic Energy Agency, Tokai-mura, Naka-gun, Ibaraki, 319-1195 (Japan); Shibahara, Yuji [Japan Atomic Energy Agency, Tokai-mura, Naka-gun, Ibaraki, 319-1195 (Japan); University of Fukui, Fukui-shi, Fukui, 910-8507 (Japan); Morimoto, Yasuyuki; Tokuyasu, Takashi; Takahashi, Nobuo; Tanaka, Yoshio; Sugitsue, Noritake [Japan Atomic Energy Agency, Kagamino-cho, Tomata-gun, Okayama, 708-0698 (Japan)

    2012-07-01

    Some of nuclear facilities that would no longer be required have been decommissioned in JAEA (Japan Atomic Energy Agency). A lot of nuclear facilities have to be decommissioned in JAEA in near future. To implement decommissioning of nuclear facilities, it was important to make a rational decommissioning plan. Therefore, project management data evaluation system for dismantling activities (PRODIA code) has been developed, and will be useful for making a detailed decommissioning plan for an object facility. Dismantling of dry conversion facility in the uranium refining and conversion plant (URCP) at Ningyo-toge began in 2008. During dismantling activities, project management data such as manpower and amount of waste generation have been collected. Such collected project management data has been evaluated and used to establish a calculation formula to calculate manpower for dismantling equipment of chemical process and calculate manpower for using a green house (GH) which was a temporary structure for preventing the spread of contaminants during dismantling. In the calculation formula to calculate project management data related to dismantling of equipment, the relation of dismantling manpower to each piece of equipment was evaluated. Furthermore, the relation of dismantling manpower to each chemical process was evaluated. The results showed promise for evaluating dismantling manpower with respect to each chemical process. In the calculation formula to calculate project management data related to use of the GH, relations of GH installation manpower and removal manpower to GH footprint were evaluated. Furthermore, the calculation formula for secondary waste generation was established. In this study, project management data related to dismantling of equipment and use of the GH were evaluated and analyzed. The project management data, manpower for dismantling of equipment, manpower for installation and removal of GH, and secondary waste generation from GH were considered

  1. Plant Decontamination as a Precondition of the Remote Dismantling Concept of the Karlsruhe Vitrification Plant VEK - 12206

    International Nuclear Information System (INIS)

    Vitrification of the high-active liquid waste concentrates (HAWC) was a major milestone in the WAK decommissioning project (StiWAK). From September 2009 to June 2010, about 56 m3 of HAWC were vitrified at the Karlsruhe vitrification facility (VEK) and filled into 123 canisters. HAWC vitrification was followed by an extensive rinsing and shutdown program, in the course of which both the VEK process installations and the facilities for the storage and evaporation of high-active fission product solutions (LAVA) are prepared specifically for dismantling. Finally the rinsing programme leads to an overall reduction of the remaining contamination in the installations by a factor of approx. 5 - 10. The amount of liquids arisen from this program has been vitrified and another 17 canisters have been filled. In total, 140 canisters were packed into 5 CASTOR casks that were already transported to the Zwischenlager Nord (interim store North) of EWN GmbH (ZLN) in the mid of February 2011. The melter of the VEK was already shut down in the late November 2010. (authors)

  2. Cost calculations for decommissioning and dismantling of nuclear research facilities

    Energy Technology Data Exchange (ETDEWEB)

    Andersson, I. (Studsvik Nuclear AB (Sweden)); Backe, S. (Institute for Energy Technology (Norway)); Cato, A.; Lindskog, S. (Swedish Nuclear Power Inspectorate (Sweden)); Efraimsson, H. (Swedish Radiation Protection Authority (Sweden)); Iversen, Klaus (Danish Decommissioning (Denmark)); Salmenhaara, S. (VTT Technical Research Centre of Finland (Finland)); Sjoeblom, R. (Tekedo AB, (Sweden))

    2008-07-15

    . Examples are provided for each of the countries of relevant projects. They are as follows: 5) Research reactor DR1 in Denmark 6) The TRIGA research reactor in Finland 7) The uranium reprocessing plant in Norway 8) Research reactor R1 in Sweden The following conclusions were made: 9) IAEA and OECD/NEA documents provide invaluable advice for pertinent approaches. 10) Adequate radiological surveying is needed before precise cost calculations can be made. 11) The same can be said about technical planning including selection of techniques to be used. 12) It is proposed that separate analyses be made regarding the probabilities for conceivable features and events which could lead to significantly higher costs than expected. 13) It is expected that the need for precise cost estimates will dictate the pace of the radiological surveying and technical planning, at least in the early stages. 14) It is important that the validity structure for early cost estimates with regard to type of facility be fully appreciated. E g, the precision is usually less for research facilities. 15) The summation method is treacherous and leads to systematical underestimations in early stages unless compensation is made for the fact that not all items are included. 16) Comparison between different facilities can be made when there is access to information from plants at different stages of planning and when accommodation can be made with regard to differences in features. 17) A simple approach is presented for 'calibration' of a cost estimate against one or more completed projects. 18) Information exchange and co-operations between different plant owners is highly desirable. (au)

  3. Cost calculations for decommissioning and dismantling of nuclear research facilities

    International Nuclear Information System (INIS)

    . Examples are provided for each of the countries of relevant projects. They are as follows: 5) Research reactor DR1 in Denmark 6) The TRIGA research reactor in Finland 7) The uranium reprocessing plant in Norway 8) Research reactor R1 in Sweden The following conclusions were made: 9) IAEA and OECD/NEA documents provide invaluable advice for pertinent approaches. 10) Adequate radiological surveying is needed before precise cost calculations can be made. 11) The same can be said about technical planning including selection of techniques to be used. 12) It is proposed that separate analyses be made regarding the probabilities for conceivable features and events which could lead to significantly higher costs than expected. 13) It is expected that the need for precise cost estimates will dictate the pace of the radiological surveying and technical planning, at least in the early stages. 14) It is important that the validity structure for early cost estimates with regard to type of facility be fully appreciated. E g, the precision is usually less for research facilities. 15) The summation method is treacherous and leads to systematical underestimations in early stages unless compensation is made for the fact that not all items are included. 16) Comparison between different facilities can be made when there is access to information from plants at different stages of planning and when accommodation can be made with regard to differences in features. 17) A simple approach is presented for 'calibration' of a cost estimate against one or more completed projects. 18) Information exchange and co-operations between different plant owners is highly desirable. (au)

  4. 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.)

  5. The dismantling of nuclear installations and the radioactive wastes management. Report of the President of the Republic followed by the answers of concerned administrations and organisms

    International Nuclear Information System (INIS)

    The discussed subjects concerns the situation and the challenges of the nuclear installations dismantling and the radioactive wastes management (main intervenors, panorama of the situation, rules applied to the dismantling and the radioactive wastes), the first experiences of dismantling and radioactive wastes disposal (experiences at the CEA and EDF, implementing of solutions for the disposal), interrogations and certainties (provision for future expenses, public information). (A.L.B.)

  6. New neutron detector based on Micromegas technology for ADS projects

    CERN Document Server

    Andriamonje, Samuel A; Aune, Stephan; Ban, Gilles; Breaud, Stephane; Blandin, Christophe; Ferrer, Esther; Geslot, Benoit; Giganon, Arnaud; Giomataris, Ioannis; Jammes, Christian; Kadi, Yacine; Laborie, Philippe; Lecolley, Jean Francois; Pancin, Julien; Riallot, Marc; Rosa, Roberto; Sarchiapone, Lucia; Steckmeyer, Jean Claude; Tillier, Joel

    2006-01-01

    A new neutron detector based on Micromegas technology has been developed for the measurement of the simulated neutron spectrum in the ADS project. After the presentation of simulated neutron spectra obtained in the interaction of 140 MeV protons with the spallation target inside the TRIGA core, a full description of the new detector configuration is given. The advantage of this detector compared to conventional neutron flux detectors and the results obtained with the first prototype at the CELINA 14 MeV neutron source facility at CEA-Cadarache are presented. The future developments of operational Piccolo-Micromegas for fast neutron reactors are also described.

  7. Stade. Decommissioning and dismantling of the nuclear power plant - from the nuclear power plant to the green lawn. 3. ed.; Stade. Stilllegung und Rueckbau des Kernkraftwerks - vom Kernkraftwerk zur ''Gruenen Wiese''

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2008-07-01

    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?.

  8. Modeling of the Radiation Doses during Dismantling of RBMK-1500 Reactor Pressurized Tanks from Emergency Core Cooling System

    Directory of Open Access Journals (Sweden)

    A. Simonis

    2013-01-01

    Full Text Available Decommissioning of the Ignalina Nuclear Power Plant involves multiple problems. One of them is personnel radiation safety during the performance of dismantling activities. In this paper, modeling results of radiation doses during the dismantling of the pressurized tank from the emergency core cooling system (ECCS PT of RBMK-1500 reactor are presented. The radiological surveys indicate that the inner surface of the ECCS PT is contaminated with radioactive products of corrosion and sediments due to the radioactive water. The effective doses to the workers have been modeled for different strategies of ECCS PT dismantling. In order to select the optimal personnel radiation safety, the modeling has been performed by the means of computer code “VISIPLAN 3D ALARA Planning tool” developed by SCK CEN (Belgium. The impacts of dismantling tools, shielding types, and extract ventilation flow rate on effective doses during the dismantling of ECCS PT have been analyzed. The total effective personnel doses have been obtained by summarizing the effective personnel doses from various sources of exposure, that is, direct radiation from radioactive equipment, internal radiation due to inhalation of radioactive aerosols, and direct radiation from radioactive aerosols arising during hot cutting in premises. The uncertainty of the collective doses is also presented in this paper.

  9. Investigation of specific applications of laser cutting for dismantling of nuclear power plants

    International Nuclear Information System (INIS)

    The aim of this work, performed on an experimental basis in a frame of strict collaboration between industry (Fiat-CIEI and Fiat-CRF in Turin) and public research laboratories (ENEA-PAS-FIBI in Bologna, ENEA-PAS-ISP and ENEA-TIB-TECNLAS in Rome) and supported by a CEC contract, was to bring out the items for better evaluation of the laser beam application possibilities in dismantling nuclear power plants. The main topics of the research have been: (i) study and definition of the relevant basic parameters ruling the aerosol generation rate and behaviour in terms of physical and chemical characteristics. This work has been performed in a facility specifically designed for aerosol measurements and equipped with a 2kW laser source; (ii) study of the feasibility of local abatement of the aerosols produced and of the pressure drop in the HEPA filters; (iii) study of long-distance transmission of the laser beam power performed with a 5KW laser source with an evaluation of the power loss and beam characteristic modifications; (iv) study of laser beam technique application for dismantling the Garigliano power plant steam drum in order to better demonstrate the feasibility of the use of this technique. The research resulted in the conclusion that the laser beam is actually appropriate for long-distance dismantling of metal components. Although the main aspects of the laser cutting process have been examined, some problems remain to be investigated. This could be performed, after proper cost-benefit evaluation, during a future decommissioning programme

  10. System decontamination in the Stade nuclear power plant prior to dismantling

    Energy Technology Data Exchange (ETDEWEB)

    Stiepani, C. [AREVA NP GmbH, Erlangen (Germany); Seidelmann, K. [Kernkraftwerk Stade (Germany)

    2006-07-01

    The Stade nuclear plant (KKS) was permanently shut down in November 2003. The primary system and the most important auxiliary systems (emergency cooling system, residual heat removal system, coolant purification system and volume control system) were chemically decontaminated. The paper describes the applied decontamination process HP/CORD {sup registered} UV and the results obtained during full system decontamination. This paper explains in detail the advantages of a full system decontamination as a central measure prior to dismantling as well as the excellent decontamination results. The potential for dose rate reduction in operational power plant is also pointed out. (orig.)

  11. The Best-of-2-Worlds philosophy: developing local dismantling and global infrastructure network for sustainable e-waste treatment in emerging economies.

    Science.gov (United States)

    Wang, Feng; Huisman, Jaco; Meskers, Christina E M; Schluep, Mathias; Stevels, Ab; Hagelüken, Christian

    2012-11-01

    E-waste is a complex waste category containing both hazardous and valuable substances. It demands for a cost-efficient treatment system which simultaneously liberates and refines target fractions in an environmentally sound way. In most developing countries there is a lack of systems covering all steps from disposal until final processing due to limited infrastructure and access to technologies and investment. This paper introduces the 'Best-of-2-Worlds' philosophy (Bo2W), which provides a network and pragmatic solution for e-waste treatment in emerging economies. It seeks technical and logistic integration of 'best' pre-processing in developing countries to manually dismantle e-waste and 'best' end-processing to treat hazardous and complex fractions in international state-of-the-art end-processing facilities. A series of dismantling trials was conducted on waste desktop computers, IT equipment, large and small household appliances, in order to compare the environmental and economic performances of the Bo2W philosophy with other conventional recycling scenarios. The assessment showed that the performance of the Bo2W scenario is more eco-efficient than mechanical separation scenarios and other local treatment solutions. For equipment containing substantial hazardous substances, it demands the assistance from domestic legislation for mandatory removal and safe handling of such fractions together with proper financing to cover the costs. Experience from Bo2W pilot projects in China and India highlighted key societal factors influencing successful implementation. These include market size, informal competitors, availability of national e-waste legislation, formal take-back systems, financing and trust between industrial players. The Bo2W philosophy can serve as a pragmatic and environmentally responsible transition before establishment of end-processing facilities in developing countries is made feasible. The executive models of Bo2W should be flexibly differentiated

  12. Project: Decommissioning and Reuse of Licensed Nuclear Facilities at the CEA Centre, Fontenay-aux-Roses, (CEA-FAR) France. Annex A.I-3

    International Nuclear Information System (INIS)

    installations NLF 58 and 59. The glove boxes in NLF 58 and 59 were transferred to another facility at the CEA Centre at Cadarache or dismantled in the CEA's waste treatment installations on-site. Following removal of the equipment, the interiors of the buildings were cleaned up and the premises thus became reusable as offices for conventional work. NLF 59 (RM1 and RM2) underwent phased dismantling. After cleanup, the RM1 premises were reused as offices, a conference facility, a lecture room and an amphitheatre

  13. Interim storage of dismantled nuclear weapon components at the U.S. Department of Energy Pantex Plant

    International Nuclear Information System (INIS)

    Following the events of 1989 and the subsequent cessation of production of new nuclear weapons by the US, the mission of the Department of Energy (DOE) Nuclear Weapons Complex has shifted from production to dismantlement of retired weapons. The sole site in the US for accomplishing the dismantlement mission is the DOE Pantex Plant near Amarillo, Texas. Pending a national decision on the ultimate storage and disposition of nuclear components form the dismantled weapons, the storage magazines within the Pantex Plant are serving as the interim storage site for pits--the weapon plutonium-bearing component. The DOE has stipulated that Pantex will provide storage for up to 12,000 pits pending a Record of Decision on a comprehensive site-wide Environmental Impact Statement in November 1996

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

    International Nuclear Information System (INIS)

    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

  15. Dismantling reactor pressure vessel internals at the Stade nuclear power station. Another milestone reached on the way to green field conditions; Rueckbau der Reaktordruckbehaelter-Einbauten im Kernkraftwerk Stade. Ein weiterer Meilenstein auf dem Weg zur gruenen Wiese ist realisiert

    Energy Technology Data Exchange (ETDEWEB)

    Schmitz, Annette [AREVA NP GmbH, Erlangen (Germany); Knoll, Peter [Kernkraftwerk Stade GmbH und Co. oHG, Stade (Germany)

    2009-08-15

    In November 2003, the Stade nuclear power station (KKS) of E.ON Kernkraft GmbH was shut down for economic reasons. In its history of 31 years of operation up to that point in time KKS generated 152,460,660 MWh (gross) of electricity. From 1984 on, the reactor in addition supplied district heat to an adjacent saltworks. In early 2007 E.ON Kernkraftwerk GmbH, in the course of dismantling phase III, commissioned Areva NP to disassemble and package the reactor pressure vessel (RPV) internals. Within 17 months Areva did the entire engineering for this project, which was demanding in many respects. Over that period of time, detailed planning, drafting and licensing of the documents, design and manufacturing of the machines and facilities as well as their qualification, and personnel training were completed. Activities on site began in May 2008. Twelve months later, the RPV internals had been dismantled. This contractual milestone was reached even ahead of time. The shielding measures taken, ongoing optimization throughout the project phase, and the possibility to do without a containment allowed the estimated collective dose for these activities to be clearly underrun. The whole project was completed in late August 2009, and disassembly and packaging ready for repository storage of the RPV internals were carried out in a minimum of time. (orig.)

  16. Investigation and design of the dismantling process for irradiation capsules containing tritium. 1. Conceptual investigation and basic design

    International Nuclear Information System (INIS)

    In-pile functional tests of tritium breeding blankets for fusion reactors have been planned by Japan Atomic Energy Agency (JAEA), using a test blanket module (TBM) which will be loaded in ITER. In preparation for the in-pile functional tests, JAEA has been being performed irradiation experiments of solid breeder materials including Li2TiO3, which is the first candidate of tritium breeder materials for the blanket of the demonstration reactor (DEMO) in a water-cooled solid-breeder design concept in Japan. The present report describes conceptual investigation and basic design of the dismantling process for irradiation capsules which were used in irradiation experiments by the Japan Materials Testing Reactor (JMTR) of JAEA. An irradiation capsule to be dismantled is comprised of a cylindrical outer-container (65mm in outer diameter) and an inner-container which is loaded with Li2TiO3 pebbles. In the present design, the irradiation capsule is cut by a band saw; the released tritium is recovered safely by a purge-gas system, and is consolidated into a radioactive waste form. Furthermore, an inner-box enclosing the dismantling apparatus has been designed as a safety countermeasure of possible tritium release from the dismantling apparatus in accidental events. The adoption of the inner-box has brought a prospect to be able to utilize an existing hot cell (β γ cell) equipped with usual wall material permeable to tritium, without extensive refurbishing of the cell. Thus, the present study has indicated the feasibility of the dismantling process for the irradiated JMTR capsules containing tritium. The results of the present investigation and design will contribute to the design of the TBM structure and to the planning of the dismantling process of the TBM. (author)

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

    International Nuclear Information System (INIS)

    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

  18. Life cycle assessment of hybrid vehicles recycling: Comparison of three business lines of dismantling.

    Science.gov (United States)

    Belboom, Sandra; Lewis, Grégory; Bareel, Pierre-François; Léonard, Angélique

    2016-04-01

    This paper undertakes an environmental evaluation of hybrid vehicles recycling, using industrial data from Comet Traitement SA in Belgium. Three business lines have been modelled and analysed. The first one is relative to the business as usual with a dismantling to recover batteries and engines followed by shredding and post shredding treatments. The second one considers, in addition, the removal of electronic control units (ECU) before shredding followed by same steps than in the first line and the last one is relative to the additional removal of big plastic parts before shredding and business as usual post shredding treatments. Results show non-significant environmental benefits when ECU or large parts of plastics are recovered before shredding. Improvements in terms of environmental benefits are lower than the uncertainty of the results. Indeed, the performing usual process for end-of-life vehicles (ELV) treatment reaches 97% of the ELV which is valorised in terms of metal and energy recoveries. Post shredding treatment units include metals, plastics and energy recovery of residues. Comet business as usual route for ELV valorisation is in accordance with the requirements of the European directive and recommendations for further improvement with dismantling of other parts (ECU or plastics) before shredding are non-relevant in this case.

  19. Electrolytic decontamination of the dismantled metallic wastes contaminated with uranium compounds in neutral salt solutions

    International Nuclear Information System (INIS)

    Electrolytic dissolution study was carried out to evaluate the applicability of electrochemical decontamination process using a neutral salt electrolyte as a decontamination technology for the recycle or self disposal with authorization of large amount of metallic wastes contaminated with uranium compounds generated by dismantling a retired uranium conversion plant using SUS-304 and Inconel-600 specimen as the main materials of internal system components of the plant. The effects of type of neutral salt as an electrolyte, current density, and concentration of electrolyte on the dissolution of the materials were evaluated. On the basis of the results obtained through the basic inactive experiments, electrochemical decontamination tests using the specimens contaminated with uranium compounds such as UO2, AUC (ammonium uranyl carbonate) and ADU (ammonium diuranate) taken from an uranium conversion plant were performed in Na2SO4 and NaNO3 solution. It was verified that the electrochemical decontamination of the dismantled metallic wastes was quite successful in Na2SO4 and NaNO3 neutral salt electrolyte by reducing β radioactivities below the level of self disposal with authorization within 10 minutes regardless of the type of contaminants and the degree of contamination

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

    International Nuclear Information System (INIS)

    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)

  1. DISMANTLING OF THE UPPER RPV COMPONENTS OF THE KARLSRUHE MULTI-PURPOSE RESEARCH REACTOR (MZFR), GERMANY

    Energy Technology Data Exchange (ETDEWEB)

    Prechtl, E.; Suessdorf, W.

    2003-02-27

    The Multi-purpose Research Reactor was a pressurized-water reactor cooled and moderated with heavy water. It was built from 1961 to 1966 and went critical for the first time on 29 September 1965. After nineteen years of successful operation, the reactor was de-activated on 3 May 1984. The reactor had a thermal output of 200 MW and an electrical output of 50 MW. The MZFR not only served to supply electrical power, but also as a test bed for: - research into various materials for reactor building (e. g. zirkaloy), - the manufacturing and operating industry to gain experience in erection and operation, - training scientific and technical reactor staff, and - power supply (first nuclear combined-heat-and-power system, 1979-1984). The experience gained in operating the MZFR was very helpful for the development and operation of power reactors. At first, safe containment and enclosure of the plant was planned, but then it was decided to dismantle the plant completely, step by step, in view o f the clear advantages of this approach. The decommissioning concept for the complete elimination of the plant down to a green-field site provides for eight steps. A separate decommissioning license is required for each step. As part of the dismantling, about 72,000 Mg [metric tons] of concrete and 7,200 Mg of metal (400 Mg RPV) must be removed. About 700 Mg of concrete (500 Mg biological shield) and 1300 Mg of metal must be classified as radioactive waste.

  2. Life cycle assessment of hybrid vehicles recycling: Comparison of three business lines of dismantling.

    Science.gov (United States)

    Belboom, Sandra; Lewis, Grégory; Bareel, Pierre-François; Léonard, Angélique

    2016-04-01

    This paper undertakes an environmental evaluation of hybrid vehicles recycling, using industrial data from Comet Traitement SA in Belgium. Three business lines have been modelled and analysed. The first one is relative to the business as usual with a dismantling to recover batteries and engines followed by shredding and post shredding treatments. The second one considers, in addition, the removal of electronic control units (ECU) before shredding followed by same steps than in the first line and the last one is relative to the additional removal of big plastic parts before shredding and business as usual post shredding treatments. Results show non-significant environmental benefits when ECU or large parts of plastics are recovered before shredding. Improvements in terms of environmental benefits are lower than the uncertainty of the results. Indeed, the performing usual process for end-of-life vehicles (ELV) treatment reaches 97% of the ELV which is valorised in terms of metal and energy recoveries. Post shredding treatment units include metals, plastics and energy recovery of residues. Comet business as usual route for ELV valorisation is in accordance with the requirements of the European directive and recommendations for further improvement with dismantling of other parts (ECU or plastics) before shredding are non-relevant in this case. PMID:26898478

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

    International Nuclear Information System (INIS)

    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

  4. High pressure water abrasive suspension JET cutting - An innovative cutting technology for the dismantling of reactor core components

    Energy Technology Data Exchange (ETDEWEB)

    Kalwa, H. [VAK, Kahl (Germany); Schwarz, T. [RWE NUKEM Limited, B7 Windscale, Seascale, Cumbria CA20 1PF (United Kingdom)

    2003-07-01

    In the frame of decommissioning of nuclear facilities the dismantling of reactor pressure vessels and their internals represent one special challenge. Due to their high activation, associated high dose rate levels, and to some extent the complex geometry and high material thickness of the components, there are particular demands for dismantling techniques. The task is to safely and economically work in every respect and therefore employ techniques with a wide area of application. As a proven technique, RWE NUKEM offers High Pressure Water Abrasive Suspension Jet Cutting. High pressure Water Abrasive Suspension Jet cutting (WASJ), well established in non-nuclear applications, has now been upgraded to meet the demands of decommissioning in the nuclear industry. The application at the Nuclear Power Plant in Kahl (VAK) was one of the first industrial scale applications. Based on several tests and parametric studies, High Water Abrasive Suspension Jet Cutting was tested against other cutting technologies. Because the overall performance in terms of fast and easy cutting operations, ability for remote handling, production of secondary waste WASJ was chosen at VAK Kahl for the dismantling of the lower core shroud and the reactor pressure vessel itself. The dismantling of the core shroud and the reactor vessel took place in-situ (component in its built-in position) using the WASJ technology. As example of application the core shroud of VAK is given. The total mass of the VAK lower shroud was about 3 tons and the wall thickness varied from 30 to 135 mm. The shroud was cut into segments in its in-vessel position, each segment being 500 x 900 mm and having a mass of about 0.25 tons. Cutting was performed in such a way that the separated pieces could be loaded directly into standard waste containers. All secondary waste (abrasives and dross) was collected in two 200 liter drums and, after drying, the drums were sent directly to waste storage. Reactor Pressure Vessel of VAK

  5. Dismantling of the research reactor RTS-1 Galileo Galilei in Pisa (Italy); Desmantelamiento del reactor de investigacion RTS-1 Galileo Galilei en Pisa (Italia)

    Energy Technology Data Exchange (ETDEWEB)

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

    2014-07-01

    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)

  6. Control of radioactive waste in dismantling of a nuclear facility; Control de residuos radiactivos en desmantelamiento de una instalacion nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Campayo, E.

    2014-07-01

    In the dismantling of a nuclear facility are generated radioactive waste that must be suitably processed. The overall process, in a simplified manner, contemplates the characterization in origin, their segregation on the basis of physical, mechanical, and radiological characteristics and their packaging. (Author)

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

    Energy Technology Data Exchange (ETDEWEB)

    Van Lauwe, Aymeric; Ridikas, Danas; Damoy, Francois; Blideanu, Valentin; Fajardo, Christophe [CEA Saclay, DSM/DAPNIA, F-91191 Gif-sur-Yvette (France); Aubert, Marie-Cecile [CEA Saclay, DSM/SAC/CQSE, F-91191 Gif-sur-Yvette (France); Foulon, Francois [CEA Saclay, INSTN, F-91191 Gif-sur-Yvette (France)

    2006-07-01

    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)

  8. Skills management medical labor in the plan of dismantling and decommissioning of the nuclear power plant Jose Cabrera

    International Nuclear Information System (INIS)

    The model adopted for managing the skills of workers in the various contracts present in the dismantling in order to minimize, on the one hand, workplace accidents attributable to previous health status of the worker and the other the effects on the health could have a possible exposure to ionizing radiation. This model is based on the close coordination between the departments directly involved.

  9. Dose reduction through automation of nuclear weapons dismantlement and storage procedures at the Department of Energy's Pantex Facility

    International Nuclear Information System (INIS)

    With the end of the Cold War and the subsequent break up of the Soviet Union, the number of weapons in the nuclear stockpile now greatly exceeds any foreseeable future need. To compensate for this excess an estimated 20,000 nuclear warheads have been earmarked for dismantlement and storage at the Department of Energy's Pantex Plant near Amarillo, Texas. It is anticipated that the majority of these warheads will arrive at the Pantex facility by the year 2000. At that time, it is estimated that current dismantlement and inventory procedures will not be adequate to control worker radiation exposure within administrative and federal dose limits. To control these exposures alternate approaches to dismantlement and inventory must be developed. One attractive approach is to automate as many activities as possible, thus reducing worker exposure. To facilitate automation of dismantlement and storage procedures, current procedures were investigated in terms of collective dose to workers, time to completion, ease of completion, and cost of automation for each task. A cost-benefit comparison was then performed in order to determine which procedures would be most cost-effective to automate

  10. Flow analysis of heavy metals in a pilot-scale incinerator for residues from waste electrical and electronic equipment dismantling

    Energy Technology Data Exchange (ETDEWEB)

    Long, Yu-Yang; Feng, Yi-Jian; Cai, Si-Shi; Ding, Wei-Xu; Shen, Dong-Sheng, E-mail: shends@zju.edu.cn

    2013-10-15

    Highlights: • Cu, Zn, Pb, and Ni are enriched in bottom ash from WEEE dismantling residues. • The heavy metal residual fraction restricts transfer in the incinerator. • Pre-treatment to remove heavy metals from WEEE residues would reduce emissions. -- Abstract: The large amount of residues generated from dismantling waste electrical and electronic equipment (WEEE) results in a considerable environmental burden. We used material flow analysis to investigate heavy metal behavior in an incineration plant in China used exclusively to incinerate residues from WEEE dismantling. The heavy metals tested were enriched in the bottom and fly ashes after incineration. However, the contents of heavy metals in the bottom ash, fly ash and exhaust gas do not have a significant correlation with that of the input waste. The evaporation and recondensation behavior of heavy metals caused their contents to differ with air pollution control equipment because of the temperature difference during gas venting. Among the heavy metals tested, Cd had the strongest tendency to transfer during incineration (T{sub Cd} = 69.5%) because it had the lowest melting point, followed by Cu, Ni, Pb and Zn. The exchangeable and residual fractions of heavy metals increased substantially in the incineration products compared with that of the input residues. Although the mass of residues from WEEE dismantling can be reduced by 70% by incineration, the safe disposal of the metal-enriched bottom and fly ashes is still required.

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

    International Nuclear Information System (INIS)

    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

  12. Decommissioning of the ASTRA research reactor: Dismantling of the biological shield

    Directory of Open Access Journals (Sweden)

    Meyer Franz

    2006-01-01

    Full Text Available The paper describes the dismantling of the inactive and activated areas of the biological shield of the ASTRA research reactor at the Austrian Research Center in Seibersdorf. The calculation of the parameters determining the activated areas at the shield (reference nuclide, nuclide vector in the barite concrete and horizontal and vertical reduction behaviors of activity concentration and the activation profiles within the biological shield for unrestricted release, release restricted to permanent deposit and radioactive waste are presented. Considerations of located activation anomalies in the shield, e.g. in the vicinities of the beam-tubes, were made according to the reactor's operational history. Finally, an overview of the materials removed from the biological shield is given.

  13. The dismantling of the Tokai 1 Steam Raising Units using remotely controlled techniques

    Energy Technology Data Exchange (ETDEWEB)

    Blight, J. [Business Development Manager Nuclear Business Unit Cybernetix SA, 13 - Marseille (France); Satoh, T. [General Manager Decommissioning Project Dept Japan Power Corporation, 13 - Marseille (France); Sawamoto, M. [General Manager Project Development Dept e-Energy Corp, SOJIZT Group, 13 - Marseille (France)

    2008-07-01

    The Tokai 1 gas cooled reactor 166 MW(e) reactor went into service in 1966 and was shut down in 1998. Since that date the Japan Atomic Power Company, the owner of the plant has been planning and implementing an ambitious programme which will lead to the first Level 3 decommissioning of a commercial power reactor in Japan. JPC's basic strategy is to manage and perform the decommissioning work with in-house resources, calling on the support of specialist companies as and when required. This paper describes the JPC programme and in particular the dismantling of the 4 steam raising units (SRU) which is to be performed using remotely controlled equipment. (authors)

  14. Decommissioning of the ASTRA research reactor - dismantling of the biological shield

    International Nuclear Information System (INIS)

    The paper describes the dismantling of the inactive and activated areas of the biological shield of the ASTRA research reactor at the Austrian Research Center in Seibersdorf. The calculation of the parameters determining the activated areas at the shield (reference nuclide, nuclide vector in the barite concrete and horizontal and vertical reduction behaviors of activity concentration) and the activation profiles within the biological shield for unrestricted release, release restricted to permanent deposit and radioactive waste are presented. Considerations of located activation anomalies in the shield, e. g. in the vicinities of the beam-tubes, were made according to the reactor's operational history. Finally, an overview of the materials removed from the biological shield is given. (author)

  15. 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.

  16. Taking samples from the reactor components in preparation for dismantling the TRIGA reactor at the Medical University of Hannover

    International Nuclear Information System (INIS)

    After shutting down the facility at the end of 1996 the spent TRIGA fuel elements from the research reactor at the Medical University of Hanover (MHH) were returned to the United States in the summer of 1999 and thus disposed of for the MHH. Consequently one of the main prerequisites for dismantling the TRIGA reactor as planned has been fulfilled. In preparation for dismantling the facility a number of samples were taken from the various reactor components in 2000. The aim of the samples being taken was to establish the radiological condition of the facility in more detail, in particular the condition of the activated components in the reactor tank and the biological shield in the core area. Up to now the calculated estimates for these components had been based mainly on the details provided in the facility documentation when operation started at the beginning of the 1970s, showing that the evaluation of the activity and dose rates was too high. This was confirmed in 1998 in the course of measuring contamination and dose rates when samples were taken from some reactor components before the fuel elements were removed. For example, drill samples were taken from the bottom part of a graphite blind element and from the central radiation beam tube in the core area and then analyzed by the U.R.A. Laboratory of the University of Regensburg. As it is planned to dismantle the reactor facility completely by hand, it is necessary to have realistic radiological data in order to prepare for the dismantling procedure. Furthermore, both the release of radioactive materials into the environment and the costs for external disposal of the radioactive waste from the dismantling of the reactor are to be kept to a minimum. (orig.)

  17. ICP0 dismantles microtubule networks in herpes simplex virus-infected cells.

    Directory of Open Access Journals (Sweden)

    Mingyu Liu

    Full Text Available Infected-cell protein 0 (ICP0 is a RING finger E3 ligase that regulates herpes simplex virus (HSV mRNA synthesis, and strongly influences the balance between latency and replication of HSV. For 25 years, the nuclear functions of ICP0 have been the subject of intense scrutiny. To obtain new clues about ICP0's mechanism of action, we constructed HSV-1 viruses that expressed GFP-tagged ICP0. To our surprise, both GFP-tagged and wild-type ICP0 were predominantly observed in the cytoplasm of HSV-infected cells. Although ICP0 is exclusively nuclear during the immediate-early phase of HSV infection, further analysis revealed that ICP0 translocated to the cytoplasm during the early phase where it triggered a previously unrecognized process; ICP0 dismantled the microtubule network of the host cell. A RING finger mutant of ICP0 efficiently bundled microtubules, but failed to disperse microtubule bundles. Synthesis of ICP0 proved to be necessary and sufficient to disrupt microtubule networks in HSV-infected and transfected cells. Plant and animal viruses encode many proteins that reorganize microtubules. However, this is the first report of a viral E3 ligase that regulates microtubule stability. Intriguingly, several cellular E3 ligases orchestrate microtubule disassembly and reassembly during mitosis. Our results suggest that ICP0 serves a dual role in the HSV life cycle, acting first as a nuclear regulator of viral mRNA synthesis and acting later, in the cytoplasm, to dismantle the host cell's microtubule network in preparation for virion synthesis and/or egress.

  18. The 'Room within a Room' Concept for Monitored Warhead Dismantlement

    Energy Technology Data Exchange (ETDEWEB)

    Tanner, Jennifer E.; Benz, Jacob M.; White, Helen; McOmish, Sarah; Allen, Keir; Tolk, Keith; Weeks, George E.

    2014-12-01

    Over the past 10 years, US and UK experts have engaged in a technical collaboration with the aim of improving scientific and technological abilities in support of potential future nuclear arms control and non-proliferation agreements. In 2011 a monitored dismantlement exercise provided an opportunity to develop and test potential monitoring technologies and approaches. The exercise followed a simulated nuclear object through a dismantlement process and looked to explore, with a level of realism, issues surrounding device and material monitoring, chain of custody, authentication and certification of equipment, data management and managed access. This paper focuses on the development and deployment of the ‘room-within-a-room’ system, which was designed to maintain chain of custody during disassembly operations. A key challenge for any verification regime operating within a nuclear weapon complex is to provide the monitoring party with the opportunity to gather sufficient evidence, whilst protecting sensitive or proliferative information held by the host. The requirement to address both monitoring and host party concerns led to a dual function design which: • Created a controlled boundary around the disassembly process area which could provide evidence of unauthorised diversion activities. • Shielded sensitive disassembly operations from monitoring party observation. The deployed room-within-a-room was an integrated system which combined a number of chain of custody technologies (i.e. cameras, tamper indicating panels and enclosures, seals, unique identifiers and radiation portals) and supporting deployment procedures. This paper discusses the bounding aims and constraints identified by the monitoring and host parties with respect to the disassembly phase, the design of the room-within-a-room system, lessons learned during deployment, conclusions and potential areas of future work. Overall it was agreed that the room-within-a-room approach was effective but

  19. Decontamination and decommissioning project for the nuclear facilities

    International Nuclear Information System (INIS)

    In 2004, the dismantling of the reactor pool, including the equipment in the pool, was started. The radioactivity of the equipment, caused by activation was much higher than the expected activity and 7 remotely operated devices were developed to dismantle them. Project management including man power control, quality control was carried out and radiation protection programs and environmental surveillance was also conducted. The waste from dismantling sites was classified according to the physco-chemical properties and radioactivity level, each was further treated or stored according to the relevant procedures. The issues from the safety evaluation by KINS was analyzed and answered. Some preparative works, such as a supply of new electric source and installation of a new ventilation system, were conducted. A process for the treatment of the sludge waste in lagoon was developed and the basic requirements for the process were established

  20. Decontamination and Decommissioning Project for the Nuclear Facilities

    International Nuclear Information System (INIS)

    The final goal of this project is to complete safely and successfully the decommissioning of the Korean Research Reactor no.1 (KRR-1) and the Korean Research Reactor no.2 (KRR-2), and uranium conversion plant (UCP). The dismantling of the reactor hall of the KRR-2 was planned to complete till the end of 2004, but it was delayed because of a few unexpected factors such as the development of a remotely operated equipment for dismantling of the highly radioactive parts of the beam port tubes. In 2005, the dismantling of the bio-shielding concrete structure of the KRR-2 was finished and the hall can be used as a temporary storage space for the radioactive waste generated during the decommissioning of the KRR-1 and KRR-2. The cutting experience of the shielding concrete by diamond wire saw and the drilling experience by a core boring machine will be applied to another nuclear facility dismantling. An effective management tool of the decommissioning projects, named DECOMIS, was developed and the data from the decommissioning projects were gathered. This system provided many information on the daily D and D works, waste generation, radiation dose, etc., so an effective management of the decommissioning projects is expected from next year. The operation experience of the uranium conversion plant as a nuclear fuel cycle facility was much contributed to the localization of nuclear fuels for both HWR and PWR. It was shut down in 1993 and a program for its decontamination and dismantling was launched in 2001 to remove all the contaminated equipment and to achieve the environment restoration. The decommissioning project is expected to contribute to the development of the D and D technologies for the other domestic fuel cycle facilities and the settlement of the new criteria for decommissioning of the fuel cycle related facilities

  1. 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)

    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)

  2. 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

  3. Long term dismantling of a basaltic volcano (Piton des Neiges, La Réunion hotspot).

    Science.gov (United States)

    Chaput, Marie; Famin, Vincent; Michon, Laurent; Catry, Thibault

    2010-05-01

    We present a structural investigation of destabilization processes at the Piton des Neiges, the extinct volcano of La Reunion Island. We focus on the Cirque of Cilaos (a large erosional depression south of the volcano summit), where the exposed internal structure of Piton des Neiges is made of pahoehoe lava flows of the shield building stage (unknown thickness) and breccias (~1 km thick), covered by volcanic products of the differentiated stage (~1 km thick). The breccias contain only basic elements and consist in debris flows and debris avalanches deposits. Beddings in the debris flows and shear structures in the avalanche deposits indicate a runout in the direction 300°. We suggest that these breccias may represent the upper part of the Cap La Houssaye mass wasting events observed onshore and offshore on the western side of la Réunion (Bachèlery et al., 2003). The breccias display many indicators of brittle deformation, such as faults (normal and strike slip) and intrusions (dykes and sills). Fault data inversion allows to recognize two episodes of deformation. The first, older step of deformation is consistent with a minimum principal stress oriented N120. Intrusions related to this deformation are basic magmas of the shield building stage. The second, later stage of extension oriented N-S crosscuts the N120 deformation with intrusion compositions of the differentiated stage. These results show that the dismantling of Piton des Neiges proceeded in two ways: catastrophic episodic destabilization and slow internal deformation. During the shield-building stage, slow and rapid dismantling was occurring in the 300° direction in the studied area, whereas it evolved toward a N-S slow collapse during the differentiated stage of magmatic activity. This result fully agrees with a recent study carried out within debris avalanches deposits in the cirque of Salazie (north of Piton des Neiges summit) which attests that the northern flank of the Piton des Neiges has also

  4. Design of the Iris reactor to simplify dismantling of concrete structures during decommissioning

    International Nuclear Information System (INIS)

    IRIS is an advanced PWR of integral type and 335 MWe power. Its compact containment (spherical, 25 m diameter) enables integrating it inside the reactor/auxiliary building to improve safety, security and economics. Moreover, IRIS has instituted aggressive radiation reduction objectives. One of them is related to decommissioning and dismantling of concrete structures. Specifically, the concrete wall of the reactor vessel cavity in loop PWRs becomes activated. Hence, when the time for decommissioning comes, it must be dismantled/cut with all the necessary precautions, and then disposed of as radioactive waste (even if low-level), at high cost. The IRIS objective is that after 100 years of operation the reactor cavity structure (concrete walls) would remain below the free release level, i.e., would not be treated as radioactive waste. That would significantly simplify returning the site to green field status and reduce the cost of decommissioning. A coordinated analysis was performed by several groups within the IRIS team; this paper describes the analysis performed by Georgia Institute of Technology using the SCALE6/MAVRIC methodology. The activation of the concrete in the reactor vessel cavity wall is driven by its impurities, primarily cobalt and europium. The neutron flux reaching the walls is significantly attenuated (more than ten orders of magnitude) in IRIS due to the inherent shielding provided by the wide downcomer, but the free release limit based on the IAEA guidelines is relatively low for the considered isotopes, 0.1 Bq/g. As a result, activation in the baseline case (reference design) exceeds the limit over the surface layer of a significant portion of the cavity wall. A design solution was developed in which the concrete wall is borated. This modified design reduced the activation anywhere in the cavity concrete wall to below the clearance limit. Thus, after removing the reactor vessel, decommissioning could proceed as with any other industrial

  5. Melting of the metallic wastes generated by dismantling retired nuclear research facilities

    International Nuclear Information System (INIS)

    The decommissioning of nuclear installations results in considerably large amounts of radioactive metallic wastes such as stainless steel, carbon steel, aluminum, copper etc. It is known that the reference 1,000 MWe PWR and 881 MWe PHWR will generate metal wastes of 24,800 ton and 26,500 ton, respectively. In Korea, the D and D of KRR-2 and a UCP at KAERI have been performed. The amount of metallic wastes from the KRR-1 and UCP was about 160 ton and 45 ton, respectively, up to now. These radioactive metallic wastes will induce problems of handling and storing these materials from environmental and economical aspects. For this reason, prompt countermeasures should be taken to deal with the metal wastes generated by dismantling retired nuclear facilities. The most interesting materials among the radioactive metal wastes are stainless steel (SUS), carbon steel (CS) and aluminum wastes because they are the largest portions of the metallic wastes generated by dismantling retired nuclear research facilities. As most of these steels are slightly contaminated, if they are properly treated they are able to be recycled and reused in the nuclear field. In general, the technology of a metal melting is regarded as one of the most effective methods to treat metallic wastes from nuclear facilities. In conclusion: The melting of metal wastes (Al, SUS, carbon steel) from a decommissioning of research reactor facilities was carried out with the use of a radioisotope such as cobalt and cesium in an electric arc furnace. In the aluminum melting tests, the cobalt was captured at up to 75% into the slag phase. Most of the cesium was completely eliminated from the aluminum ingot phase and moved into the slag and dust phases. In the melting of the stainless steel wastes, the 60Co could almost be retained uniformly in the ingot phase. However, we found that significant amounts of 60Co remained in the slag at up to 15%. However the removal of the cobalt from the ingot phase was improved by

  6. Pollution characterization and diurnal variation of PBDEs in the atmosphere of an E-waste dismantling region

    Energy Technology Data Exchange (ETDEWEB)

    Chen Duohong [State Key Laboratory of Organic Geochemistry, Guangdong Key Laboratory of Environment and Resources, Guangzhou Institute of Geochemistry, Chinese Academy of Sciences, Guangzhou 510640, Guangdong Province (China); Graduate School of Chinese Academy of Sciences, 100049 Beijing (China); Bi, Xinhui [State Key Laboratory of Organic Geochemistry, Guangdong Key Laboratory of Environment and Resources, Guangzhou Institute of Geochemistry, Chinese Academy of Sciences, Guangzhou 510640, Guangdong Province (China)], E-mail: bixh@gig.ac.cn; Zhao Jinping; Chen Laiguo; Tan Jihua [State Key Laboratory of Organic Geochemistry, Guangdong Key Laboratory of Environment and Resources, Guangzhou Institute of Geochemistry, Chinese Academy of Sciences, Guangzhou 510640, Guangdong Province (China); Graduate School of Chinese Academy of Sciences, 100049 Beijing (China); Mai Bixian [State Key Laboratory of Organic Geochemistry, Guangdong Key Laboratory of Environment and Resources, Guangzhou Institute of Geochemistry, Chinese Academy of Sciences, Guangzhou 510640, Guangdong Province (China); Sheng Guoying; Fu Jiamo [State Key Laboratory of Organic Geochemistry, Guangdong Key Laboratory of Environment and Resources, Guangzhou Institute of Geochemistry, Chinese Academy of Sciences, Guangzhou 510640, Guangdong Province (China); Institute of Environmental Pollution and Health, School of Environmental and Chemical Engineering, Shanghai University, 200072 Shanghai (China); Wong Minghung [Croucher Institute for Environmental Sciences Hong Kong Baptist University, Kowloon, Hong Kong (China); Department of Biology, Hong Kong Baptist University, Kowloon, Hong Kong (China)

    2009-03-15

    Diurnal air samples were collected from the E-waste dismantling region Guiyu and the underwear industry region Chendian. This was the first report to present the diurnal variation of PBDEs in the atmosphere. The average concentrations of 11 PBDE congeners were 11,742 pg m{sup -3} in the daytime, and 4830 pg m{sup -3} at night in Guiyu, while the concentrations were lower in Chendian with 376 pg m{sup -3} in the daytime, and 237 pg m{sup -3} at night. BDE-209 accounted for 22% and 31.3% of the total PBDEs in Guiyu and Chendian, respectively. The diurnal variation trends of BDE-47, -99, -153, -183, and -209 were also analyzed in detail in the two regions. - A survey of atmospheric PBDE concentrations at day and night will help identify the short time variability of PBDEs in an E-waste dismantling region of South China.

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

    International Nuclear Information System (INIS)

    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

  8. Pilot tests for dismantling by blasting of the biological shield of a shut down nuclear power station

    International Nuclear Information System (INIS)

    Following free-field tests on concrete blocks the feasibility of explosive dismantling of the biological shield of nuclear power stations has been succesfully tested at the former hotsteam reaction in Karlstein/Main Germany. For this purpose a model shield of scale 1:2 was embedded into the reactor structure at which bore-hole blasting tests employing up to about 15 kg of explosive were performed. An elaborate measurement system allowed to receive detailed information on the blast side-effects: Special emphasis was focussed on the quantitative registration of the dynamic blast loads; data for the transfer of the dismantling method to the removal of real ractor structures were obtained. (orig.)

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

    International Nuclear Information System (INIS)

    In the Uranium Powder Manufacturing Plant at CAC, U3O8 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)

  10. 49 CFR 1242.30 - Dismantling retired road property and depreciation (accounts XX-17-39, XX-18-39, XX-19-39, 62-17...

    Science.gov (United States)

    2010-10-01

    ... 49 Transportation 9 2010-10-01 2010-10-01 false Dismantling retired road property and depreciation (accounts XX-17-39, XX-18-39, XX-19-39, 62-17-00, 62-18-00, and 62-19-00). 1242.30 Section 1242.30....30 Dismantling retired road property and depreciation (accounts XX-17-39, XX-18-39, XX-19-39,...

  11. DISMANTLEMENT TECHNIQUE OF ROOF TRUSS OF SHOUGANG GROUP'S MAIN BUILDING FOR HIGH-STRENGTH MACHINE STEEL PRODUCTION LINE%首钢高强度机械制造用钢生产线主厂房屋面网架拆除施工技术

    Institute of Scientific and Technical Information of China (English)

    阮新伟

    2012-01-01

    首钢高强度机械制造用钢生产线主厂房屋面网架需进行拆除,拆除量之大在国内目前尚属罕见.通过详细策划,采取利用厂房原有的双梁天车,在其主梁能搭设脚手架作为可移动的施工作业平台,进行空中屋面网架散拆的施工方案,取得了良好的施工效果.%The roof truss of Shougang Group's main building for high-strength machine steel production line needs to be dismantled and this project witnesses the biggest dismantlement workload in China. After careful planning, scaffold is erected as a mobile construction platform on the main beam of the existing double-beam crown block to dismantle the truss in the air. Favorable construction effects are obtained.

  12. [Pollution Characteristics and Ecological Risk of PBDEs in Water and Sediment from an Electronic Waste Dismantling Area in Taizhou].

    Science.gov (United States)

    Chen, Xiang-ping; Peng, Bao-qi; Lü, Su-ping; Chen, Qiang; Zhang, Yong; Huang, Chang-jiang; Dong, Qiao-xiang

    2016-05-15

    An e-waste dismantling industrial park of Taizhou was selected as the sampling center, within a radius of 16 km, and a total of 30 sampling sites were designed in three circles as follows: C (3 km), S (5-10 km) and R (10-16 km). Pollution characteristics and ecological risk of polybrominated diphenyl ethers (PBDEs) in water and sediments were investigated. The concentrations of PBDEs in water ranged from 9.4 to 57.2 ng · L⁻¹, with a mean value of 25.9 ng · L⁻¹; and 3.7 to 38,775 ng · g⁻¹, with an average of 2 779 ng · g⁻¹ in sediments. BDE-209 was the predominant congener. The spatial distribution patterns of PBDE levels in water and sediment were both in the following order: C > S > R. Furthermore, the concentrations of PBDEs in sediments showed significant negative correlation against the distance from the industrial park (P world, the PBDEs contamination was more serious in the area, which indicated that e-waste dismantling activity was one of the significant sources for PBDEs pollution. It was estimated that a total of 30. 7 t PBDEs (including 28. 9 t BDE- 209) was discharged into surrounding environment as a result of dismantling industrial activities in last 40 years. A preliminary ecological risk assessment for PBDEs in water and sediments was conducted by hazard quotient method. The results demonstrated that the Penta-BDEs in the center of e-waste dismantling area ( a radius of 1.5 km) was at particularly high risk level and could cause serious influence on the ecological safety and human health. PMID:27506030

  13. Reintegration of areas of the IPEN's dismantled nuclear fuel cycle pilot plants as new laboratories of the CQMA

    International Nuclear Information System (INIS)

    IPEN has faced the problem of the dismantling of their Nuclear Fuel Cycle old facilities. Those facilities already played their roles of technological development and personnel's training, with transfer of the technology for institutions entrusted of the 'scale up' of the units. Most of the pilot plants interrupted the activities more than ten years ago, due to the lack of resources for the continuity of the research. The appropriate facilities maintenance has been also harmed by the lack of resources, with evident signs of deterioration in structures and equipment. The existence of these facilities also implicates in the need of constant surveillance, representing additional obligations, costs and problems. The reasons to promote as soon as possible the dismantling of the IPEN's Nuclear Fuel Cycle Pilot Plants elapse mainly from the need of physical space for new activities, since the R and D in the nuclear fuel cycle area were interrupted and from the loss of personnel that set up and operated the referred units, one of the most concerning aspects in case of the postponement of the dismantling process. One of these new activities is the IPEN's Environmental Program. In the building where there was the Uranium Dissolution and Purification Pilot Plant, already dismantled, it was decided to settle the Laboratory of Chemical and Environmental Analyses, being necessary its total liberation from the point of view of radioactive contamination. This paper describes the procedures, problems faced and results related to the reintegration of the former pilot plant areas as new laboratories of the Chemical and Environmental Technology Center - CQMA - of the IPEN. (author)

  14. The Harper Government's New Right Neoliberal Agenda and the Dismantling of Status of Women Canada and the Family Violence Initiative

    OpenAIRE

    Ruth M Mann

    2016-01-01

    This paper situates the Harper government’s 2006 restructuring and effective dismantling of Status of Women Canada and its 2011 take down of the approximate 12,000 volume online library of the federal Family Violence Initiative in relation to two developments. These are the ascendant influence of men’s rights and other antifeminist activism in Canada and globally; and the concurrent rise of a Hayekian-animated New Right neoliberal agenda intent on subordinating civil society and democratic ru...

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

    International Nuclear Information System (INIS)

    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)

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

    International Nuclear Information System (INIS)

    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.)

  17. Decommissioning optimization of the Loviisa nuclear power station dismantling the pressure vessel and decontamination of primary circuit

    International Nuclear Information System (INIS)

    The report describes radioactivities and radiation levels in decommissioning situation at the Loviisa Nuclear Power Station and optimization of plant decommissioning in view of costs and radiation doses. In calculation of the activity inventory, the existing activity calculations, the literature data and the measuring results and experiences gained at the Loviisa plant have been used as basic data. The radiation levels have been calculated with a computer program based on the point kernel method. A technique for dismantling the reactor pressure vessel and internals as large parts has been developed. As compared with segmenting into small parts, the developed dismantling technique saves FIM 12.3 million of immediate costs and 0.7 manSv of collective radiation doses, if the plant is decommissioned two years after the final reactor shutdown. Saving in total decommissioning costs and doses is 3-4%. Costs of primary circuit chemical decontamination of one plant unit are FIM 1.7 million. Major part of the costs is caused by solidification and final disposal of active waste produced in decontamination. The primary circuit decontamination saves 0.36 manSv in collective radiation doses caused by dismantling operations, if the plant is decommissioned two years after the final reactor shutdown. Price of a saved manSv is FIM 4.8 million. (author)

  18. Y-12 Plant decontamination and decommissioning technology logic diagram for Building 9201-4. Volume 3: Technology evaluation data sheets; Part A: Characterization, dismantlement

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1994-09-01

    The Y-12 Plant Decontamination and Decommissioning Technology Logic Diagram for Building 9201-4 (TLD) was developed to provide a decision-support tool that relates decontamination and decommissioning (D and D) problems at Bldg. 9201-4 to potential technologies that can remediate these problems. The TLD uses information from the Strategic Roadmap for the Oak Ridge Reservation, the Oak Ridge K-25 Site Technology Logic Diagram, the Oak Ridge National Laboratory Technology Logic Diagram, and a previous Hanford logic diagram. This TLD identifies the research, development, demonstration, testing, and evaluation needed for sufficient development of these technologies to allow for technology transfer and application to D and D and waste management (WM) activities. It is essential that follow-on engineering studies be conducted to build on the output of this project. These studies will begin by selecting the most promising technologies identified in the TLD and by finding an optimum mix of technologies that will provide a socially acceptable balance between cost and risk. This report consists of the characterization and dismantlement data sheets.

  19. Y-12 Plant decontamination and decommissioning technology logic diagram for Building 9201-4. Volume 3: Technology evaluation data sheets; Part A: Characterization, dismantlement

    International Nuclear Information System (INIS)

    The Y-12 Plant Decontamination and Decommissioning Technology Logic Diagram for Building 9201-4 (TLD) was developed to provide a decision-support tool that relates decontamination and decommissioning (D and D) problems at Bldg. 9201-4 to potential technologies that can remediate these problems. The TLD uses information from the Strategic Roadmap for the Oak Ridge Reservation, the Oak Ridge K-25 Site Technology Logic Diagram, the Oak Ridge National Laboratory Technology Logic Diagram, and a previous Hanford logic diagram. This TLD identifies the research, development, demonstration, testing, and evaluation needed for sufficient development of these technologies to allow for technology transfer and application to D and D and waste management (WM) activities. It is essential that follow-on engineering studies be conducted to build on the output of this project. These studies will begin by selecting the most promising technologies identified in the TLD and by finding an optimum mix of technologies that will provide a socially acceptable balance between cost and risk. This report consists of the characterization and dismantlement data sheets

  20. Venezuelan Experience and Challenges on Partial Dismantling and Conversion of the Venezuelan RV-1 Nuclear Research Reactor into an Industrial Irradiation Plant

    International Nuclear Information System (INIS)

    The RV-1 nuclear research reactor of the Venezuelan Institute for Scientific Research is a pool type reactor of 3 MW of thermal power that was operated from 1961 to 1991 despite having a high level of obsolescence. Since 1991, IVIC has studied different options in spite of its obsolescence to upgrade, decommission or convert the reactor facility into an industrial irradiation plant. The option to convert the RV-1 into an industrial irradiation plant prevailed politically. In December 2003, the reactor conversion activities had been completed at a cost of US $3 million. The RV-1 conversion project consisted mainly of the characterization of the radioactive contamination of structures, systems and equipment in preparation of their dismantling and removal from the reactor building, waste classification and disposal. Structural modifications were made, e.g. new ventilation and water systems for treatment of the reactor pool and the 60Co source pool, concluding finally with the installation and commissioning of a new irradiator with a maximum rack capacity of 1 MCi. Currently, the RV-1 remains permanently shutdown, and the industrial irradiation plant is operating 22.5 hours per day, 365 days a year. All of these activities carried out have represented a challenge for our country. (author)

  1. 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)

  2. An analysis of influence of input parameters on the external exposure during dismantling of steam generator

    International Nuclear Information System (INIS)

    The decommissioning of nuclear installations represents an essential phase of facility's lifecycle. The main goal of this process is to achieve partial or complete release from radiation control. This can be successfully done only when all activities are planned and optimized according to the ALARA principle. The presence of radioactivity (whether induced activity or contamination) makes the process of dismantling of large components more difficult, because beside their large dimensions and masses, also the level of activity (several orders higher than natural background) has to be taken into account. The subject of analysis is steam generator used in NPPs with VVER 440 type reactor after about 30 years of standard operation. The results of calculation show the big influence of studied input parameters on the external exposure. After comparison of scenarios it is obvious that the decontamination with decontamination factor of 100 causes about 50-times greater decrease of the dose load than the decay time of 5 years (related to the Scenario 0). The more detailed description of model of steam generator, tasks, scenarios and results analysis will be given in the full paper. (authors)

  3. Chemical oxygen-iodine laser for decommissioning and dismantlement of nuclear facilities

    Science.gov (United States)

    Tei, Kazuyoku; Sugimoto, Daichi; Endo, Masamori; Takeda, Shuzaburo; Fujioka, Tomoo

    2000-01-01

    Conceptual designs of a chemical oxygen-iodine laser (COIL) facility for decommissioning and dismantlement (DD) of nuclear facility is proposed. The requisite output power and beam quality was determined base don our preliminary experiments of nonmetal material processing. Assuming the laser power of 30kW, it is derived that the beam quality of M2 equals 36 required to cut a biological shield wall of a nuclear power plant at a cutting speed of 10mm/min. Then the requisite specification of an optical fiber to deliver the laser is calculated. It turned to be quite extreme, core diameter of 1.7mm and NA equals 0.018. The mass flow and heat balance of proposed facility is calculated based on our recent COIL studies. With the high-pressure subsonic mode, the vacuum pump size is minimized compared to the supersonic operation. Finally, the size of the facility is estimated assuming tow-hour continuous operation. It is revealed that such a system can be packed in five railway containers.

  4. Expanding to teleoperation of a tight modular workshop for dismantling radioactive components

    International Nuclear Information System (INIS)

    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

  5. Explosive cutting techniques for dismantling of concrete structures in a nuclear power station following decommissioning

    International Nuclear Information System (INIS)

    This report describes the work that has been jointly carried out, based on a common and complementary research programme, by the Battelle Institut e.V., Frankfurt and Taylor Woodrow Construction Ltd., Southall, on the controlled use of explosives for the cutting and safe removal of activated and contaminated parts of nuclear facilities without impairing the overall structural integrity. Previous work had demonstrated the feasibility of using explosive techniques for the stripping off of an equivalent thickness of concrete, for radiation protection, from the inside walls of nuclear facilities. The present research work aims at complementing, improving and optimizing the foregoing work. Extensive investigations have been executed on the adjustment of blasting parameters, material and structural effects, drilling techniques, particle distribution and on procedures for remote handling. The report presents the results obtained from field trials and theoretical analysis undertaken to augment the development programme. It concludes that the controlled use of explosives offers a safe and favourable dismantling technique for the decommissioning of nuclear facilities

  6. Dismantling and decontamination of the tube bundle of a feedwater preheater of the Garigliano BWR

    International Nuclear Information System (INIS)

    The report deals with dismantling and decontamination of the tube bundle of a feedwater preheater of Garigliano-BWR. Decontamination is a common practice in decommissioning works and it can be used both for reducing radiation exposures, in order to save manrem, and for the unrestricted release of materials. In this latter field the decontamination of tube bundle is a particular case because of their large contaminated surfaces and relatively low weight; at the moment no decon technique was available on the market to decontaminate up to the unrestricted release the materials of tube bundles. In this context an innovative decon technique using aggressive chemicals together with ultrasounds in a tank, was developed by several laboratories and assessed with in-scale testings. A decon procedure considering two phases: first with ultrasounds applied in water at 600C, and second with ultrasounds applied in a solution of HF/HNO3 acids at 60-700C, was qualified. The demonstration of the performances of the new technique under real conditions was made by performing ten full-scale demo tests, each one on an assembly of 100 straight tubes, 1 m long each, for a total of 1000 meters

  7. Local information committee and social repercussions of the closure and dismantling of Vandellos-I

    International Nuclear Information System (INIS)

    Vandellos-I is a 497 MW gas graphite type nuclear power plant located in the Province of Tarragona. Its construction began in 1967 and it started operating in 1972. Its design was very similar to the French plant at St. Laurent des Eaux. In 1989 a fire in the turbine house led to the final shutdown of the reactor in 1990 by Ministerial Order. Responsibility for the site was transferred from the utility to ENRESA in February 1998. Since then, main decommissioning activities of Vandellos-I have been undertaken, following post operational clean out, conditioning of spent fuel and treatment of operational wastes including the graphite components from fuel elements. Stage 2 decommissioning activities have been extended up to 2003. As it is known, when a new nuclear installation is commissioned, exists a change in the Socioeconomic activity in the local area. This new activity usually begins with an increase of employment and population until the finalization of the commissioning contracts when the NPP starts up. At tile same time during the operational stage, municipal incomes are increased. During the decommissioning of a nuclear installation, some socio-economic impacts in the surrounded area are produced, strongly dependent on the activity of the decommissioned facility. For a complete evaluation of the impact of the dismantling phase, the overall process of decommissioning of a nuclear installation should be considered, including the following three phases: - permanent shutdown; - decommissioning period; - post-closure. (author)

  8. Characterisation and materials flow management for waste electrical and electronic equipment plastics from German dismantling centres.

    Science.gov (United States)

    Arends, Dagmar; Schlummer, Martin; Mäurer, Andreas; Markowski, Jens; Wagenknecht, Udo

    2015-09-01

    Waste electrical and electronic equipment is a complex waste stream and treatment options that work for one waste category or product may not be appropriate for others. A comprehensive case study has been performed for plastic-rich fractions that are treated in German dismantling centres. Plastics from TVs, monitors and printers and small household appliances have been characterised extensively. Based on the characterisation results, state-of-the-art treatment technologies have been combined to design an optimised recycling and upgrade process for each input fraction. High-impact polystyrene from TV casings that complies with the European directive on the restriction of hazardous substances (RoHS) was produced by applying continuous density separation with yields of about 60%. Valuable acrylonitrile butadiene styrene/polycarbonate can be extracted from monitor and printer casings by near-infrared-based sorting. Polyolefins and/or a halogen-free fraction of mixed styrenics can be sorted out by density separation from monitors and printers and small household appliances. Emerging separation technologies are discussed to improve recycling results.

  9. Decontamination and dismantling of Cendrillon transfer systems for radioactive liquid solutions - 59336

    International Nuclear Information System (INIS)

    Document available in abstract form only. Full text of publication follows: The CENDRILLON system was studied and developed by the CEA at the end of the 1950's and early of the 1960's to transfer and transport the radioactive liquid solutions to waste treatment facilities. This system has been manufactured in several versions in three different sizes and for each different volumes of capacity. For each size, the biological shielding thickness is based on the volume capacity. Whatever the size and volume, the CENDRILLON connection system remains identical. All liquid transfers, filling and sucking out, of the CENDRILLON are carried under vacuum. The CENDRILLON D and D works are carried out during the facilities POCO (post clean out operations) and decommissioning or into a dedicated waste treatment plant. The parer will show CEA's procedure to carry out these CENDRILLON D and D works. It consists of tasks sequences: CENDRILLON emptiness assessment, capacity flushing and decontamination, pumping out, drying and finally CENDRILLON dismantling by mechanical disassembly (taking apart) and the capacity cutting. Control of nuclear risk is essential for all these tasks: radiolysis, contamination and irradiation. (authors)

  10. Characterisation and materials flow management for waste electrical and electronic equipment plastics from German dismantling centres.

    Science.gov (United States)

    Arends, Dagmar; Schlummer, Martin; Mäurer, Andreas; Markowski, Jens; Wagenknecht, Udo

    2015-09-01

    Waste electrical and electronic equipment is a complex waste stream and treatment options that work for one waste category or product may not be appropriate for others. A comprehensive case study has been performed for plastic-rich fractions that are treated in German dismantling centres. Plastics from TVs, monitors and printers and small household appliances have been characterised extensively. Based on the characterisation results, state-of-the-art treatment technologies have been combined to design an optimised recycling and upgrade process for each input fraction. High-impact polystyrene from TV casings that complies with the European directive on the restriction of hazardous substances (RoHS) was produced by applying continuous density separation with yields of about 60%. Valuable acrylonitrile butadiene styrene/polycarbonate can be extracted from monitor and printer casings by near-infrared-based sorting. Polyolefins and/or a halogen-free fraction of mixed styrenics can be sorted out by density separation from monitors and printers and small household appliances. Emerging separation technologies are discussed to improve recycling results. PMID:26111535

  11. Post-decontamination and dismantlement (D ampersand D) characterization report for CFA-669 site

    International Nuclear Information System (INIS)

    This report presents results of post-decontamination and dismantling (D ampersand D) characterization surveys performed by EG ampersand G Idaho, Inc. (EG ampersand G Idaho), at Central Facilities Area (CFA)-669, which was the Hot Laundry Facility. The site was characterized to determine and document the radiological and chemical conditions of the site following D ampersand D and to determine if the site satisfies the release criteria. Constructed in 1950, CFA-669 served as the ''hot'' and ''cold'' laundry for Idaho National Engineering Laboratory site contractors until the boiler exploded in 1981. The building was shut down at that time. Before D ampersand D activities began in 1992, the facility was characterized and the results documented. D ampersand D activities were completed in July 1994. The post-D ampersand D radiological characterization consisted of radiation measurements and analyses of soil samples to identify man-made radionuclides and determine the specific activity of each sample. The chemical characterization consisted of toxicity characterization leaching procedure (TCLP) analysis for metals and for volatile and semivolatile organic contamination

  12. ITER project starring - new step of R and D of fusion researches in Japan

    International Nuclear Information System (INIS)

    ITER is an international tokamak research/engineering proposal which intended to be an experimental project between today's studies of plasma physics and future electricity-producing fusion power plants. The seven participants (EU, USA, Russia, Japan, Korea, China and India) formally agreed to fund the project in November, 2006. It is based in Cadarache, France. This feature articles consist of six reports such as ITER system starting-hope for Japanese leadership by Kaname IKEDA, outline of ITER and BA project and realization of fusion power by Hiroki MATSUO, hope for development of fusion by Humitaka SATO, ITER projects details by Masahiro MORI, broader approach (BA) projects details by Takeo NISHITANI, and trends of development by each country by Hidetoshi YOSHIDA. (S.Y.)

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

    Energy Technology Data Exchange (ETDEWEB)

    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{sup 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.

  14. A microstructural analysis of solder joints from the electronic assemblies of dismantled nuclear weapons

    Energy Technology Data Exchange (ETDEWEB)

    Vianco, P.T.; Rejent, J.A. [Sandia National Labs., Albuquerque, NM (United States). Materials Joining Dept.

    1997-05-01

    MC1814 Interconnection Boxes from dismantled B57 bombs, and MC2839 firing Sets from retired W70-1 warheads were obtained from the Pantex facility. Printed circuit boards were selected from these components for microstructural analysis of their solder joints. The analysis included a qualitative examination of the solder joints and quantitative assessments of (1) the thickness of the intermetallic compound layer that formed between the solder and circuit board Cu features, and (2) the Pb-rich phase particle distribution within the solder joint microstructure. The MC2839 solder joints had very good workmanship qualities. The intermetallic compound layer stoichiometry was determined to be that of Cu6Sn5. The mean intermetallic compound layer thickness for all solder joints was 0.885 mm. The magnitude of these values did not indicate significant growth over the weapon lifetime. The size distribution of the Pb-rich phase particles for each of the joints were represented by the mean of 9.85 {times} 10{sup {minus}6} mm{sup 2}. Assuming a spherical geometry, the mean particle diameter would be 3.54 mm. The joint-to-joint difference of intermetallic compound layer thickness and Pb-rich particle size distribution was not caused by varying thermal environments, but rather, was a result of natural variations in the joint microstructure that probably existed at the time of manufacture. The microstructural evaluation of the through-hole solder joints form the MC2839 and MC1814 components indicated that the environmental conditions to which these electronic units were exposed in the stockpile, were benign regarding solder joint aging. There was an absence of thermal fatigue damage in MC2839 circuit board, through-hole solder joints. The damage to the eyelet solder joints of the MC1814 more likely represented infant mortality failures at or very near the time of manufacture, resulting from a marginal design status of this type of solder joint design.

  15. Reserves for shutdown/dismantling and disposal in nuclear technology. Theses and recommendations on reform options; Rueckstellungen fuer Stilllegung/Rueckbau und Entsorgung im Atombereich. Thesen und Empfehlungen zu Reformoptionen

    Energy Technology Data Exchange (ETDEWEB)

    Meyer, Bettina [Forum Oekologisch-Soziale Marktwirtschaft e.V. (FOeS), Berlin (Germany). Green Budget Germany (GBG)

    2012-04-11

    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.

  16. DOWNSIZING TO CORPORATE ANOREXIA WHILE DISMANTLING THE MIDDLE CLASS: ARE WE IN DANGER OF RECREATING THE 1920S?

    Directory of Open Access Journals (Sweden)

    Thomas R. Winpenny

    1999-01-01

    Full Text Available Corporate downsizing has run rampant on the American scene during the 1990s. Indeed, Business Week claimed it had become a fad. Ironically, the new “lean and mean” look did not apply to CEO compensation packages. More critically, corporate downsizing hurt middle class purchasing power. The Big Lie that emerged from this was that America could dismantle the middle class and have a booming economy. Much of this reasoning sounds, sadly enough, like the thinking so prevalent in the 1920s.

  17. Decommissioning and dismantling of the Rossendorf Isotope Production; Stilllegung und Rueckbau der Rossendorfer Isotopenproduktion. T. 1. Betriebshistorie, Genehmigungsverfahren und Planungskonzept

    Energy Technology Data Exchange (ETDEWEB)

    Grahnert, Thomas [VKTA - Strahlenschutz Analytik und Entsorgung Rossendorf e.V., Dresden (Germany). Reststoffbehandlung und Qualitaetswesen; Jansen, Sven [VKTA - Strahlenschutz Analytik und Entsorgung Rossendorf e.V., Dresden (Germany). Betrieblicher Strahlenschutz; Boessert, Wolfgang [VKTA - Strahlenschutz Analytik und Entsorgung Rossendorf e.V., Dresden (Germany). Bereich Rueckbau und Entsorgung; Kniest, Steffen [Siempelkamp NIS Ingenieurgesellschaft mbH, Dresden (Germany)

    2016-05-15

    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.

  18. Provision of capital for shutdown, dismantling and disposal. Cost risks and proposals for reform for a responsibility related financing

    International Nuclear Information System (INIS)

    In Germany the latest discussion on the cost of nuclear phase-out, dismantling and waste disposal has shown that the provision of capital by the concerned companies for these challenges and the actual regulations are not sufficient for a long-term financing security. The study presents a reform concept including the need of improved transparency on the provision of capital, a differentiated financial statement, the introduction of a stock under public law for insolvency protection including a financing responsibility for the companies and subsequent payments in case of cost increase, and an increase of protection in case of insolvency.

  19. Decommissioning and dismantling of nuclear facilities. An assessment of the current legal situation relating to standard setting and licensing

    International Nuclear Information System (INIS)

    The introductory survey presents the framework conditions set by the nuclear technical codes, the law, and the nuclear licensing provisions. The first contribution (by A.Kurz) analyses the legal position referring to the points of law and to the problems encountered in connection with activities for the decommissioning and dismantling of nuclear facilities. The second contribution (by W.H. Junker) shows the regulatory situation by presenting a synopsis of licences, discussing their legal background and in particular their effects in practice. (HP)

  20. Analysis of Alternatives for Dismantling of the Equipment in Building 117/1 at Ignalina NPP - 13278

    Energy Technology Data Exchange (ETDEWEB)

    Poskas, Povilas; Simonis, Audrius [Lithuanian Energy Institute, Kaunas (Lithuania); Poskas, Gintautas [Lithuanian Energy Institute, Kaunas (Lithuania); Kaunas University of Technology, Kaunas (Lithuania)

    2013-07-01

    Ignalina NPP was operating two RBMK-1500 reactors which are under decommissioning now. In this paper dismantling alternatives of the equipment in Building 117/1 are analyzed. After situation analysis and collection of the primary information related to components' physical and radiological characteristics, location and other data, two different alternatives for dismantling of the equipment are formulated - the first (A1), when major components (vessels and pipes of Emergency Core Cooling System - ECCS) are segmented/halved in situ using flame cutting (oxy-acetylene) and the second one (A2), when these components are segmented/halved at the workshop using CAMC (Contact Arc Metal Cutting) technique. To select the preferable alternative MCDA method - AHP (Analytic Hierarchy Process) is applied. Hierarchical list of decision criteria, necessary for assessment of alternatives performance, are formulated. Quantitative decision criteria values for these alternatives are calculated using software DECRAD, which was developed by Lithuanian Energy Institute Nuclear engineering laboratory. While qualitative decision criteria are evaluated using expert judgment. Analysis results show that alternative A1 is better than alternative A2. (authors)

  1. Days of dismantling activities of installations and rehabilitation of contaminated sites in France; Demantelement des installations et rehabilitation de sites contamines

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2008-07-01

    The objective of these days, organized by the section environment of the French society of radiation protection, is to present a panorama of the activities of nuclear installations dismantling and contaminated sites rehabilitation in France, by leaning in the same time on practical cases and by stating the French rule and the national and international recommendations on the subject. These days have also for object to approach the stakes associated with the sectors of waste management and the materials generated by these activities and in a more general way, the stakes to come for the different actors of the dismantling and the rehabilitation. (N.C.)

  2. A treaty more alarming than efficient. The dismantled warheads will not be destroyed. Danger; Un traite plus inquietant qu'efficace. Les ogives demantelees ne seront pas detruites. Risque

    Energy Technology Data Exchange (ETDEWEB)

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

    2002-07-01

    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.)

  3. Human and organisational factors as key levers of performance in D and D project management - 59323

    International Nuclear Information System (INIS)

    Document available in abstract form only. Full text of publication follows: In a number pf D and D projects, the type of installations to be dismantled and the variety of their equipments (glove-boxes, tanks..) and the products present on site (plutonium, uranium) in the form of powder are making many operations manual ones. Key phases in HR and organisation management: - The first D and D experience, the learning curve ramp-up - To begin any project, you usually try to benefit from benchmark of similar projects to be able to build up the first scenario, by using the best practices. The first experimental team consisted of operators who already had experienced dismantling at least once in the course of their career. This first dismantling operation is preferably to be conducted on an installation relatively poorly contaminated. This was to implement the correct techniques thus reducing the consequences of a possible unforeseen event. The capitalisation on the return on experience The success of this first dismantling site operation allowed us to implement a process of experience feedback to build the scenarios and the operating procedures of the following sites. In particular, targeted safety-security stop points are positioned for validation on the operations by people responsible for safety and security

  4. Development of the graphic design and control system based on a graphic simulator for the spent fuel dismantling equipment

    International Nuclear Information System (INIS)

    In this study, the graphic design system is developed for designing the spent fuel rod consolidation and the dismantling processes. This system is used throughout the design stages from the conceptual design to the motion analysis. Also, the real-time control system of the rod extracting equipment is developed. This system utilizes the graphic simulator which simulates the motion of the equipment in real time by synchronously connecting the control PC with the graphic server through the TCP/IP network. The developed system is expected to be used as an effective tool in designing the process equipment for the spent fuel management. And the real-time graphic control system can be effectively used to enhance the reliability and safety of the spent fuel handling process by providing the remote monitoring function of the process

  5. Development of the graphic design and control system based on a graphic simulator for the spent fuel dismantling equipment

    Energy Technology Data Exchange (ETDEWEB)

    Lee, J. Y.; Kim, S. H.; Song, T. G.; Yoon, J. S

    2000-06-01

    In this study, the graphic design system is developed for designing the spent fuel rod consolidation and the dismantling processes. This system is used throughout the design stages from the conceptual design to the motion analysis. Also, the real-time control system of the rod extracting equipment is developed. This system utilizes the graphic simulator which simulates the motion of the equipment in real time by synchronously connecting the control PC with the graphic server through the TCP/IP network. The developed system is expected to be used as an effective tool in designing the process equipment for the spent fuel management. And the real-time graphic control system can be effectively used to enhance the reliability and safety of the spent fuel handling process by providing the remote monitoring function of the process.

  6. Oak Ridge K-25 Site Technology Logic Diagram. Volume 3, Technology evaluation data sheets; Part A, Characterization, decontamination, dismantlement

    Energy Technology Data Exchange (ETDEWEB)

    Fellows, R.L. [ed.

    1993-02-26

    The Oak Ridge K-25 Technology Logic Diagram (TLD), a decision support tool for the K-25 Site, was developed to provide a planning document that relates environmental restoration and waste management problems at the Oak Ridge K-25 Site to potential technologies that can remediate these problems. The TLD technique identifies the research necessary to develop these technologies to a state that allows for technology transfer and application to waste management, remedial action, and decontamination and decommissioning activities. The TLD consists of four separate volumes-Vol. 1, Vol. 2, Vol. 3A, and Vol. 3B. Volume 1 provides introductory and overview information about the TLD. Volume 2 contains logic diagrams. Volume 3 has been divided into two separate volumes to facilitate handling and use. This report is part A of Volume 3 concerning characterization, decontamination, and dismantlement.

  7. Analysis of results obtained with different cutting techniques and associated filtration systems for the dismantling of radioactive metallic components

    International Nuclear Information System (INIS)

    The present joint study performed by the Commissariat a l'energie atomique and the Universitaet Hannover and coordinated by the Commission of the European Communities was intended to analyse the results generated in a number of research contracts concerned with cutting tests in air and underwater, with consideration of the prevailing working conditions. The analysis has led to a large database, giving broadly-assessed information for the dismantling of radioactive components. The range of study was enlarged, where possible, to include recently obtained results outside the present research programme, consideration also being given to supplementary cutting tools and filtration systems not covered by the present programme. Data was concentrated in structured information packages on practical experience available for a series of cutting tools and filters. These were introduced into a computerized user-friendly databank, to be considered as a first-stage development, which should be continuously updated and possibly oriented in the future to an expert system

  8. The Harper Government's New Right Neoliberal Agenda and the Dismantling of Status of Women Canada and the Family Violence Initiative

    Directory of Open Access Journals (Sweden)

    Ruth M Mann

    2016-06-01

    Full Text Available This paper situates the Harper government’s 2006 restructuring and effective dismantling of Status of Women Canada and its 2011 take down of the approximate 12,000 volume online library of the federal Family Violence Initiative in relation to two developments. These are the ascendant influence of men’s rights and other antifeminist activism in Canada and globally; and the concurrent rise of a Hayekian-animated New Right neoliberal agenda intent on subordinating civil society and democratic rule to the forces of twenty-first century global capitalism. The paper contends that anti-feminism is among a host of neoconservative forces that the New Right instrumentalizes to augment and advance and its neoliberal agenda. For the New Right, however, the enemy is not gender equality or feminism per se but rather the market inhibiting commitment to social justice that feminism participates in and advances.

  9. 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.)

  10. 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.

  11. Application of abrasive water suspension jets for dismantling of metallic structural components; Anwendung von Wasserabrasivsuspensionsstrahlen zur Zerlegung metallischer Komponenten

    Energy Technology Data Exchange (ETDEWEB)

    Brandt, C.

    1999-07-01

    Abrasive water suspension jets continue to open up new applications in the dismantling of nuclear installations because of their specific cutting capabilities and other advantages. The progress report in hand examines possibilities for drastic reduction of the volume of required liquids, accompanied by an enhancement of the cutting performance. This was achieved especially by increasing the operational pressure to 200 MPa. Based on experimentally derived data, a tool for optimization of the cutting performance was developed. This tool enables cutting work optimization by an assessment of optimal cutting parameters, also taking into account the specific boundary conditions. On the basis of the results achieved and reported in this publication, the WASS method could be applied on site for the first time in December 1997, for dismantling of the bottom part of the core shroud of the VAK experimental reactor facility at Kahl. (orig./CB) [German] Wasserabrasivsuspensionsstrahlen besitzen aufgrund ihrer verfahrensspezifischen Vorteile ein grosses Potential beim Rueckbau kerntechnischer Anlagen. Bisher scheiterte ein Einsatz des Verfahrens an der Menge des sekundaeren Abfalls. Im Rahmen der Arbeit werden Moeglichkeiten zur drastischen Reduzierung der eingesetzten Volumenstroeme bei gleichzeitiger Steigerung der Schnittleistung aufgezeigt. Dies wird insbesondere durch die Anhebung des Betriebsdruckes auf 200 MPa erreicht. Auf Basis experimentell ermittelter Daten ist ein Werkzeug zur Optimierung der Schnittleistung entwickelt worden. Dieses Werkzeug ermoeglicht die Abschaetzung optimaler Schneidparameter unter Beruecksichtigung der spezifischen Randbedingungen. Basierend auf den im Rahmen der vorliegenden Arbeit erzielten Ergebnisse konnte das WASS-Verfahren im Dezember 1997 erstmals unter realen Bedingungen im Versuchsatomkraftwerk, Kahl (VAK) zur Zerlegung des Kernmantelunterteils eingesetzt werden. (orig.)

  12. Monitoring indicators in a dismantling; Seguimiento de indicadores en un desmantelamiento. Conocerse a si mismo

    Energy Technology Data Exchange (ETDEWEB)

    Soto Lanuza, A.

    2013-07-01

    Knowing yourself know the processes (Manual process), knows as the more quantitative possible, as are things (table of indicators), document and manage incidents and finds (integrated system of improvements), will allow us to carry to term two important tasks: the tracking and the continuous improvement of the project.

  13. Dismantling the Pink Door in the Apartheid Wall: Towards a Decolonized Palestinian Queer Politics

    NARCIS (Netherlands)

    H. Maikey; M. Stelder

    2015-01-01

    This essay engages with over a decade of Palestinian queer organizing and addresses how a politics around gender and sexuality takes shape within a context of occupation and Zionist settler colonialism. In conjunction, it identifies and analyses the way in which Israel’s pinkwashing project is roote

  14. Operation and dismantling report 2004 for Danish Decommissioning; Drifts- og afviklingsrapport 2004 - Dansk Dekommissionering

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2005-03-01

    The report describes the operations at Danish Decommissioning (DD) that are essential for the nuclear inspection authorities' assessment of safety related issues. The report presents an account of safety and of the work at DD, including the decommissioning projects in 2004 for the nuclear facilities. The radioactive waste treatment facility in operation is described, and inspection and maintenance reports of the nuclear facilities prepared for decommissioning are presented. (ln)

  15. Nuclear energy Division - 2011 Activity report

    International Nuclear Information System (INIS)

    This document reports the activity of the Nuclear Energy Department (DEN) within the CEA. It evokes its international relationship (participation to international initiatives, cooperation with different countries), describes the scientific activity within the DEN, presents the Advanced Material Program, and the activities undertaken in different fields: future nuclear industrial systems (fourth generation reactors, downstream part of the future fuel cycle, fundamental scientific and technological research), optimization of the present nuclear industrial activity (second and third generation reactors, nuclear security, upstream and downstream part of the present fuel cycle), tools for nuclear development (numerical simulation, Jules Horowitz reactor), cleaning up and nuclear dismantling (dismantling strategy, the Passage project in Grenoble, works in Marcoule, the Aladin project in Fontenay, waste and material flow management, nuclear support installations, transports). It finally addresses the specific activities of the Marcoule, Cadarache and Saclay centres

  16. Melting of contaminated steel scrap from the dismantling of the CO{sub 2} systems of gas cooled, graphite moderated nuclear reactors

    Energy Technology Data Exchange (ETDEWEB)

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

    1994-12-31

    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.

  17. First ITER Council convened in Cadarache - historic step in the quest for clean Energy 28 November 2007 Cadarache

    CERN Multimedia

    Hay, Jennifer

    2007-01-01

    "On 27 November 2007, the ITER Council convened for the first time in the history of the new International Organization. Opening the meeting, Dr Werner Burkart, Deputy Director of the International Atomic Energy Agency (AIEA), said: "Let me congratulate all who have contributed to the achievements of the ITER initiative to date.... (1,5 page)

  18. Nuclear power. The situation in Germany. Nuclear phase-out - safety - dismantling - final disposal; Kernenergie. Die Situation in Deutschland. Ausstieg - Sicherheit - Rueckbau - Endlagerung

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2012-12-15

    The brochure on the situation of nuclear power in Germany covers the following issues: The catastrophic reactor accidents in Fukushima; electricity supply in change; nuclear power worldwide; nuclear power in Germany; the design of a nuclear power plant; safety of nuclear power plants in Germany; radioactive wastes; final disposal of radioactive waste in Germany; dismantling of nuclear power plants; ''we are a nation of engineers'' - discussion with Dr. Joachim Knebel; recommendations for the use in education.

  19. Reintegration of areas of the IPEN's dismantled nuclear fuel cycle pilot plants as new laboratories of the CQMA

    Energy Technology Data Exchange (ETDEWEB)

    Lainetti, Paulo E.O.; Cotrim, Marycel E.B.; Vasques, Francisco M.F.; Ferreira, Robson de J.; Pires, Maria Aparecida F. [Instituto de Pesquisas Energeticas e Nucleares (IPEN-CNEN/SP), Sao Paulo, SP (Brazil)]. E-mails: lainetti@ipen.br; mecotrim@ipen.br; mapires@ipen.br; fvasques@ipen.br; rojefer@ipen.br

    2007-07-01

    IPEN has faced the problem of the dismantling of their Nuclear Fuel Cycle old facilities. Those facilities already played their roles of technological development and personnel's training, with transfer of the technology for institutions entrusted of the 'scale up' of the units. Most of the pilot plants interrupted the activities more than ten years ago, due to the lack of resources for the continuity of the research. The appropriate facilities maintenance has been also harmed by the lack of resources, with evident signs of deterioration in structures and equipment. The existence of these facilities also implicates in the need of constant surveillance, representing additional obligations, costs and problems. The reasons to promote as soon as possible the dismantling of the IPEN's Nuclear Fuel Cycle Pilot Plants elapse mainly from the need of physical space for new activities, since the R and D in the nuclear fuel cycle area were interrupted and from the loss of personnel that set up and operated the referred units, one of the most concerning aspects in case of the postponement of the dismantling process. One of these new activities is the IPEN's Environmental Program. In the building where there was the Uranium Dissolution and Purification Pilot Plant, already dismantled, it was decided to settle the Laboratory of Chemical and Environmental Analyses, being necessary its total liberation from the point of view of radioactive contamination. This paper describes the procedures, problems faced and results related to the reintegration of the former pilot plant areas as new laboratories of the Chemical and Environmental Technology Center - CQMA - of the IPEN. (author)

  20. Heavy metal contamination characteristic of soil in WEEE (waste electrical and electronic equipment) dismantling community: a case study of Bangkok, Thailand.

    Science.gov (United States)

    Damrongsiri, Seelawut; Vassanadumrongdee, Sujitra; Tanwattana, Puntita

    2016-09-01

    Sue Yai Utit is an old community located in Bangkok, Thailand which dismantles waste electrical and electronic equipment (WEEE). The surface soil samples at the dismantling site were contaminated with copper (Cu), lead (Pb), zinc (Zn), and nickel (Ni) higher than Dutch Standards, especially around the WEEE dumps. Residual fractions of Cu, Pb, Zn, and Ni in coarse soil particles were greater than in finer soil. However, those metals bonded to Fe-Mn oxides were considerably greater in fine soil particles. The distribution of Zn in the mobile fraction and a higher concentration in finer soil particles indicated its readily leachable character. The concentration of Cu, Pb, and Ni in both fine and coarse soil particles was mostly not significantly different. The fractionation of heavy metals at this dismantling site was comparable to the background. The contamination characteristics differed from pollution by other sources, which generally demonstrated the magnification of the non-residual fraction. A distribution pathway was proposed whereby contamination began by the deposition of WEEE scrap directly onto the soil surface as a source of heavy metal. This then accumulated, corroded, and was released via natural processes, becoming redistributed among the soil material. Therefore, the concentrations of both the residual and non-residual fractions of heavy metals in WEEE-contaminated soil increased.

  1. Effects of Environmental Lead Pollution on Blood Lead and Sex Hormone Levels among Occupationally Exposed Group in An E-waste Dismantling Area

    Institute of Scientific and Technical Information of China (English)

    YANG Yan; LU Xiao Song; LI Ding Long; YU Yun Jiang

    2013-01-01

    Objective 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. Methods 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. Results 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 101.45μg/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. Conclusion 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.

  2. Understanding the Concept of Dynamic Capabilities by Dismantling Teece, Pisano, and Shuen (1997’s Definition

    Directory of Open Access Journals (Sweden)

    Mohamad Faizal Ahmad Zaidi

    2012-08-01

    Full Text Available The concept of dynamic capabilities (DCs is gaining popularity in management field particularly in strategic management. The concept that is still new and contemporary has attracted many arguments that may lead to confusion. To understand the basic concept of DCs, looking back to the definition in Teece, Pisano and Shuen 1997’s working paper will be crucial not just because the authors are among the first to seriously promote DCs but also among the most referred article in the management field of 1990s and even still today. Hence, the objective of this review paper is to understand the basic concept of DCs by scrutinizing the definition in Teece, Pisano and Shuen (1997 that will give benefit to those who are new to the concept and wanting a quick insight on it. The definition is dismantled into six questions where the contested arguments (when applicable relating to each of the questions are drawn from mainly various DCs literature that is not means to be conclusive and exhaustive.

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

    International Nuclear Information System (INIS)

    During the decontamination and decommissioning (D and D) activities being conducted by the U.S. Department of Energy (DOE), approximately 550,000 metric tons of contaminated metal will be generated by the disposition of contaminated buildings. The majority of the structural steel is considered to be radiologically contaminated. The D and D activities require the treatment of the structural steel to reduce occupational and environmental radiological exposures during dismantlement. Treatment technologies may also be required for possible recycling. Many proven commercial treatment technologies are available. These treatment processes vary in aggressiveness, safety requirements, secondary waste generation, necessary capital, and operation and maintenance costs. Choosing the appropriate technology to meet the decontamination objectives for structural steel is a difficult process. A single information source comparing innovative and nuclear and non-nuclear technologies in the areas of safety, cost and effectiveness is not currently commercially available to perform a detailed analysis. This study presents comparable data related to operation and maintenance, cost, and health and safely aspects of three readily available technologies and one innovative technology for nuclear decontamination. The technologies include Advance Recyclable Media System (ARMStrademark), NELCO Porta Shot Blasttrademark (JHJ-2000), Pegasus Coating Removal System 7 (PCRS-7) and the innovative laser ablation technology called the Yag Erasertrademark

  4. Methodology for the scoping assessment of radioactive releases during dismantling of RBMK-1500 reactor systems with low-level contamination

    International Nuclear Information System (INIS)

    Highlights: • The method simplifies addressing of numerous components to be decommissioned. • Components are grouped into mass streams of particular geometry and properties. • Mass factors are calculated and applied individually to each mass stream. • Mass factors are defined for two geometries – pipes and plates. • Application of the method can be extended. - Abstract: The Ignalina nuclear power plant operated two reactors of the RBMK-1500 type which are now under decommissioning. Decommissioning has been started from the reactor’s periphery, with dismantling of non-contaminated and low contaminated equipment and installations. This paper discusses a method for the scoping assessment of airborne radioactive releases to the environment when the number of items of equipment and the variety of installations to be addressed is significant, and separate consideration of each item becomes impractical, especially when the level of radioactive contamination is low. The method is based on the grouping of items into the manageable number of mass streams with particular geometric and other decommissioning-approach-related properties. Radioactive releases are then evaluated by application of “mass factors” that are detailed for two geometric forms – pipes and plates. These forms are the most usual outcomes from Ignalina nuclear power plant decommissioning activities performed on reactor periphery components. The method can be used for the scoping assessment of radionuclide releases considering that the radiological impact is expected to be low and, therefore, simple and straightforward solutions are sufficient for demonstration of compliance with the established radiation protection goals

  5. Cost calculations for decommissioning and dismantling of nuclear research facilities, Phase 1

    Energy Technology Data Exchange (ETDEWEB)

    Andersson, Inga [StudsvikNuclear AB (Sweden); Backe, S. [Institute for Energy Technology (Norway); Iversen, Klaus [Danish Decommissioning (Denmark); Lindskog, S [Swedish Nuclear Power Inspectorate (Sweden); Salmenhaara, S. [VTT Technical Research Centre of Finland (Finland); Sjoeblom, R. [Tekedo AB (Sweden)

    2006-11-15

    Today, it is recommended that planning of decommission should form an integral part of the activities over the life cycle of a nuclear facility. However, no actual international guideline on cost calculations exists at present. Intuitively, it might be tempting to regard costs for decommissioning of a nuclear facility as similar to those of any other plant. However, the presence of radionuclide contamination may imply that the cost is one or more orders of magnitude higher as compared to a corresponding inactive situation, the actual ratio being highly dependent on the level of contamination as well as design features and use of the facility in question. Moreover, the variations in such prerequisites are much larger than for nuclear power plants. This implies that cost calculations cannot be performed with any accuracy or credibility without a relatively detailed consideration of the radiological and other prerequisites. Application of inadequate methodologies especially at early stages has often lead to large underestimations. The goals of the project and the achievements described in the report are as follows: 1) Advice on good practice with regard to: 1a) Strategy and planning; 1b) Methodology selection; 1c) Radiological surveying; 1d) Uncertainty analysis; 2) Techniques for assessment of costs: 2a) Cost structuring; 2b) Cost estimation methodologies; 3) Compilation of data for plants, state of planning, organisations, etc.; 3a) General descriptions of relevant features of the nuclear research facilities; 3b) General plant specific data; 3c) Example of the decommissioning of the R1 research reactor in Sweden; 3d) Example of the decommissioning of the DR1 research reactor in Denmark. In addition, but not described in the present report, is the establishment of a Nordic network in the area including an internet based expert system. It should be noted that the project is planned to exist for at least three years and that the present report is an interim one

  6. Development of the Decommissioning Project Management System, DECOMMIS

    Energy Technology Data Exchange (ETDEWEB)

    Chung, U. S.; Park, J. H.; Lee, K. W.; Hwang, D. S.; Park, S. K.; Hwang, S. T.; Paik, S. T.; Choi, Y. D.; Chung, K. H.; Lee, K. I.; Hong, S. B

    2007-03-15

    At the Korea Atomic Energy Research Institute(KAERI), two projects for decommissioning of the research reactors and uranium conversion plant are carried out. The management of the projects can be defined as 'the decision of the changes of the decommissioning methodologies for the more efficient achievement of the project at an adequate time and to an improved method'. The correct decision comes from the experiences on the decommissioning project and the systematic experiences can be obtained from the good management of the decommissioning information. For this, a project management tool, DECOMMIS, was developed in the D and D Technology Division, which has the charge of the decommissioning projects at the KAERI, and its purpose was extended to following fields; generation of reports on the dismantling waste for WACID, record keeping for the next decommissioning projects of nuclear facilities, provision of fundamental data for the R and D of the decommissioning technologies.

  7. 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

  8. Melting of contaminated steel scrap arising in the dismantling of nuclear power plants

    International Nuclear Information System (INIS)

    In this work scrap steel components from nuclear power plants, about 2 t in all, have been studied during 16 melts and the melt products in these or in subsequent production melts brought below a de minimis (reclaim) radioactivity concentration of 10 pCi g-1. Radioactivity inventories for furnace systems have been made. In addition there have been melts with known amounts of radioactivities diluted uniformly into steel to provide sample calibration standards but also to directly measure dosage for various configurations and thicknesses of plate rolled from the steel. The work shows that Co-60 has in all cases finished entirely in steel and in uniform dilution in both electric arc and induction furnace melting, and, that Cs radioactivities do not enter steel at all and can readily be made to stay substantially in slag in the induction furnace. Under certain circumstances which may not be fully practical in production furnaces, cesium can be retained in slag in the electric arc furnace. These results together permit combined dilution/decontamination reclaim of selected nuclear steel scrap. The experimental melting of material within this range has been done at negligible radiation dosage to melting plant operatives or any evidence of airborne radioactivity external to the furnace system. It is likely that this would apply for the largest production furnaces which of necessity have high filtration efficiency fume control equipment. A projection has been made for a nuclear scrap reclaim program of 4000 t/a with overall contamination of 1 Ci Co-60 or equivalent, in respect of arisings of the scrap, preparation and routing to the steelworks, dosage in steelmaking and use of the product. The benefit versus detriment of this is derived to be favourable. Finally, the impact on the overall steel pool in the UK of such a programme is shown to be very small indeed. 4 refs

  9. The dismantling of nuclear installations and the radioactive wastes management. Report of the President of the Republic followed by the answers of concerned administrations and organisms; Le demantelement des installations nucleaires et la gestion des dechets radioactifs. Rapport au President de la Republique suivi des reponses des administrations et des organismes interesses

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2005-01-15

    The discussed subjects concerns the situation and the challenges of the nuclear installations dismantling and the radioactive wastes management (main intervenors, panorama of the situation, rules applied to the dismantling and the radioactive wastes), the first experiences of dismantling and radioactive wastes disposal (experiences at the CEA and EDF, implementing of solutions for the disposal), interrogations and certainties (provision for future expenses, public information). (A.L.B.00.

  10. Overview of recycling technologies for decommissioned materials. Lessons learned during the dismantling of a small PWR reactor

    International Nuclear Information System (INIS)

    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

  11. Comments on conceptual questions concerning the clearance of wastes for disposal on a dump site during the decommissioning and dismantling of the nuclear power plant Obrigheim (KWO); Stellungnahme zu konzeptionellen Fragen der Freigabe zur Beseitigung auf einer Deponie bei Stilllegung und Abbau des Kernkraftwerks Obrigheim (KWO)

    Energy Technology Data Exchange (ETDEWEB)

    Kueppers, Christian

    2015-08-03

    The comments on conceptual questions concerning the clearance of wastes for disposal on a dump site during the decommissioning and dismantling of the nuclear power plant Obrigheim (KWO) cover the following issues: fundamentals of the 10 micro-Sv concept for clearance; specific regulations for the clearance of wastes from the dismantling of KWO for disposal on a dump site; disposal concept at shutdown and dismantling of KWO; measurements and control during clearance for disposal during shutdown and dismantling of KWO; documentation and reports.

  12. Decommissioning and dismantling of the Rossendorf isotope production. Pt. 2. Aspects of implementation; Stilllegung und Rueckbau der Rossendorfer Isotopenproduktion. T. 2. Aspekte der Durchfuehrung

    Energy Technology Data Exchange (ETDEWEB)

    Grahnert, Thomas; Jansen, Sven; Boessert, Wolfgang [VKTA - Strahlenschutz Analytik und Entsorgung Rossendorf e.V., Dresden (Germany); Kniest, Steffen [Siempelkamp NIS Ingenieurgesellschaft mbH, Dresden (Germany)

    2016-06-15

    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.

  13. Study on measurement of spatial dose rates from simulated products made from recycled metal below clearance levels arising from dismantling of nuclear facilities. Contract research

    CERN Document Server

    Okamoto, A; Kitami, Y; Nakamura, H; Nakashima, M; Saitô, K

    2002-01-01

    In order to contribute to safety assessment of recycling products made from dismantling metal wastes, metal ingots containing sup 6 sup 0 Co were produced and spatial dose rates from ingots were evaluated by gamma-ray measurement and calculation. Stripping operations were made using detector response functions calculated by Monte Carlo program to derive spatial dose rates from measured gamma-ray spectra. In the computer simulation, Monte Carlo and point kernel calculation codes were used. Agreement between measured and calculated values was satisfactory in spite of an extremely low concentration of sup 6 sup 0 Co in the ingots and a complicated geometric condition between detector and samples.

  14. 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)

    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

  15. Measurements and calculation of the activation of the biologic shield of the Lingen BWR power reactor definitively stopped (in view of dismantling)

    International Nuclear Information System (INIS)

    For the dismantling planning of a power reactor, it is important to know among others the depth of activation of the biological shield. A large sampling and measurement program joint to computer calculations, has given data which will allow to avoid in the future high-cost measurement programs. One shows that the calculation of activation induced by neutrons in the median plane of the core, to determine the zone from which concrete is only slightly activated. In the reactor considered, this zone does not reach the external concrete (or first layer of concrete)

  16. 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

  17. Old assembly-type bridge dismantling scheme with cutting decomposition method%切割分解法拆除装配式旧桥的施工方案

    Institute of Scientific and Technical Information of China (English)

    贾晓霞

    2012-01-01

    This paper analyzes the old bridge cutting and dismantling scheme and construction control from Mawu Bridge in Linfen to Heilongguan of Pu county in provincial Lin-Wu line, puts forward old assembly-type bridge dismantling scheme with cutting decomposition method, which has accumulated experience for fast old assembly-type bridge dismantle.%对省道临午线临汾马务桥西至蒲县黑龙关的旧桥切割拆除方案及施工控制进行了分析,提出了切割分解法拆除装配式旧桥的施工方案,为装配式旧桥整体快速拆除积累了经验。

  18. 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)

    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

  19. Dismantling Hubble's Legacy?

    CERN Document Server

    Way, Michael J

    2013-01-01

    Edwin Hubble is famous for a number of discoveries that are well known to amateur and professional astronomers, students and the general public. The origins of these discoveries are examined and it is demonstrated that, in each case, a great deal of supporting evidence was already in place. In some cases the discoveries had either already been made, or competing versions were not adopted for complex scientific and sociological reasons.

  20. Dismantling the Mantel tests

    DEFF Research Database (Denmark)

    Guillot, Gilles; Rousset, François

    2012-01-01

    1. The simple and partialMantel tests are routinely used in many areas of evolutionary biology to assess the significance of the association between two ormorematrices of distances relative to the same pairs of individuals or demes. Partial Mantel tests rather than simple Mantel tests are widely...... used to assess the relationship between two variables displaying some form of structure. 2. We show that contrary to a widely shared belief, partialMantel tests are not valid in this case, and their bias remains close to that of the simpleMantel test. 3. We confirm that strong biases are expected under...... a sampling design and spatial correlation parameter drawn from an actual study. 4. TheMantel tests should not be used in case autocorrelation is suspected in both variables compared under the null hypothesis.We outline alternative strategies. The R code used for our computer simulations is...

  1. Dismantling the monster?

    DEFF Research Database (Denmark)

    Højgaard, Lis; Søndergaard, Dorte Marie

    2010-01-01

    This essay addresses the emergence of audit culture and evidence-base research and its entry into the Nordic countries of Europe, using Denmark as an example. A closer look is taken at the current trends as they have reached the Danish scene, and the essay engages a discussion about ways to count...

  2. Dismantling Noah's Ark.

    Science.gov (United States)

    Lorber, Judith

    1986-01-01

    Presents a prescription for a restructured postindustrial society without gender as an organizing principle. The potential nongendered social order is described in terms of nongendered reproduction, equally valued wage work and a gender-neutral wage structure, and gender-neutral access to authority and power. (SA)

  3. Dismantling Hubble's Legacy?

    Science.gov (United States)

    Way, Michael J.

    2014-01-01

    Edwin Hubble is famous for a number of discoveries that are well known to amateur and professional astronomers, students and even the general public. The origins of three of the most well-known discoveries are examined: The distances to nearby spiral nebulae, the classification of extragalactic-nebulae and the Hubble constant. In the case of the first two a great deal of supporting evidence was already in place, but little credit was given. The Hubble Constant had already been estimated in 1927 by Georges Lemaitre with roughly the same value that Hubble obtained in 1929 using redshifts provided mostly by Vesto M. Slipher. These earlier estimates were not adopted or were forgotten by the astronomical community for complex scientific, sociological and psychological reasons.

  4. Dismantling the Mantel tests

    DEFF Research Database (Denmark)

    Guillot, Gilles

    The simple and partial Mantel tests are routinely used in many areas of evolutionary biology to assess the significance of the association between two or more matrices of distances relative to the same pairs of individuals or demes. Partial Mantel tests rather than simple Mantel tests are widely...... used to assess the relationship between two variables displaying some form of structure. We show that contrarily to a widely shared belief, partial Mantel tests are not valid in this case, and their bias remains close to that of the simple Mantel test. We confirm that strong biases are expected under a...... sampling design and spatial correlation parameter drawn from an actual study. The Mantel tests should not be used in case auto-correlation is suspected in both variables compared under the null hypothesis. We outline alternative strategies. The R code used for our computer simulations is distributed as...

  5. Environmental assessment for the purchase of Russian low enriched uranium derived from the dismantlement of nuclear weapons in the countries of the former Soviet Union

    Energy Technology Data Exchange (ETDEWEB)

    1994-01-01

    The United States is proposing to purchase from the Russian Federation low enriched uranium (LEU) derived from highly enriched uranium (HEU) resulting from the dismantlement of nuclear weapons in the countries of the former Soviet Union. The purchase would be accomplished through a proposed contract requiring the United States to purchase 15,250 metric tons (tonnes) of LEU (or 22,550 tonnes of UF{sub 6}) derived from blending 500 metric tones uranium (MTU) of HEU from nuclear warheads. The LEU would be in the form of uranium hexafluoride (UF{sub 6}) and would be converted from HEU in Russia. The United States Enrichment Corporation (USEC) is the entity proposing to undertake the contract for purchase, sale, and delivery of the LEU from the Russian Federation. The US Department of Energy (DOE) is negotiating the procedure for gaining confidence that the LEU is derived from HEU that is derived from dismantled nuclear weapons (referred to as ``transparency),`` and would administer the transparency measures for the contract. There are six environments that could potentially be affected by the proposed action; marine (ocean); US ports of entry; truck or rail transportation corridors; the Portsmouth GDP; the electric power industry; and the nuclear fuel cycle industry. These environmental impacts are discussed.

  6. Environmental assessment for the purchase of Russian low enriched uranium derived from the dismantlement of nuclear weapons in the countries of the former Soviet Union

    International Nuclear Information System (INIS)

    The United States is proposing to purchase from the Russian Federation low enriched uranium (LEU) derived from highly enriched uranium (HEU) resulting from the dismantlement of nuclear weapons in the countries of the former Soviet Union. The purchase would be accomplished through a proposed contract requiring the United States to purchase 15,250 metric tons (tonnes) of LEU (or 22,550 tonnes of UF6) derived from blending 500 metric tones uranium (MTU) of HEU from nuclear warheads. The LEU would be in the form of uranium hexafluoride (UF6) and would be converted from HEU in Russia. The United States Enrichment Corporation (USEC) is the entity proposing to undertake the contract for purchase, sale, and delivery of the LEU from the Russian Federation. The US Department of Energy (DOE) is negotiating the procedure for gaining confidence that the LEU is derived from HEU that is derived from dismantled nuclear weapons (referred to as ''transparency),'' and would administer the transparency measures for the contract. There are six environments that could potentially be affected by the proposed action; marine (ocean); US ports of entry; truck or rail transportation corridors; the Portsmouth GDP; the electric power industry; and the nuclear fuel cycle industry. These environmental impacts are discussed

  7. Virtual Reality: a way to prepare and optimize operations in decommissioning projects

    International Nuclear Information System (INIS)

    The CEA has operated numerous nuclear facilities to carry out R and D and define nuclear fuel life cycle processes since the 1950's. It must now manage the clean-up and dismantling of those which have reached the end of their lifetime. These high priority actions have led to the creation of a dismantling R and D division which provides innovative tools, including in-situ radiological characterization, remote handling and cutting, and intervention scenario simulation. The latter involves running defined scenarios and verifying their suitability for the environment. Simulation is an ideal means of visualizing and therefore better knowing highly radioactive environments where humans cannot enter, of testing different technical alternatives, and of training workers prior to interventions. This paper describes Virtual Reality (VR) uses on dismantling projects. A VR simulation can be defined as an interactive and immersive simulation that enables the user to interact with a computer-simulated environment. VR environments, mostly based on visual immersion displayed through stereoscopic devices, can also include additional sensory information, such as sound or touch. Our application, based on audio, tactile and visual immersion, provides a useful support to verify pre-defined scenarios and to design alternative solutions if necessary. Thanks to a stereoscopic visualization, users are immersed in a virtual world, where they can hear virtual sounds when there is a collision, and can manipulate virtual objects and touch them via a haptic interface. This article first describes the PRESAGE immersive room in Marcoule. Then, the data preparation is explained, especially the 3D model reconstruction and the simulation configuration (remote handling and radiological). Next, different VR uses on decommissioning projects are shown and illustrated by examples. The advantages of such technologies include their speed in testing, user-friendliness, reactivity and usefulness in the

  8. Project WAGR: The UK demonstration project for power reactor decommissioning - removing the core and looking to completion

    Energy Technology Data Exchange (ETDEWEB)

    Benest, T. G. [United Kingdom Atomic Energy Authority, Headquarters, London (United Kingdom)

    2003-07-01

    have not delivered the required performance. In such cases, simple tooling and manual intervention have been adopted to maintain the project ahead of programme and below the dose budget. For campaigns where manual intervention was precluded by high dose rates, the contractor has undertaken a risk assessment of each task and elected to develop a number of different tools to cover the most likely risks. Although this strategy incurs costs for tools that may never be utilised, these costs are dwarfed by the project costs of potential delays. Excellent progress has been maintained throughout the remote dismantling with the reliability of the equipment and the experience of the workforce being major contributors to the success. Management arrangements have also contributed to the current excellent programme position. The close working relationship between UKAEA and their prime contractor, and management of the interfaces with the regulators, has enabled problems to be identified early and then dealt with quickly and effectively. The current phase of operations is now planned for completion in early 2005 over 18 months ahead of programme. Currently the WAGR project has operated for over 6 years without a lost time accident to either UKAEA staff or any of the contractor's operatives. In the last 12 months, the maximum radiation dose to an individual was <1.0 mSv. To date, 270 tonnes of graphite and 206 tonnes of steel have been encapsulated. 38 boxes of low level waste have been sent, or are awaiting transport, to BNFL's Drigg site for disposal, and a further 102 boxes of ILW are now stored on-site pending the availability of a national facility. Thus far the UKAEA WAGR project is well ahead of programme, achieving all its objectives and demonstrating to a world-wide audience that a power reactor can be decommissioned safely and efficiently shortly after shutdown.

  9. From the dismantling operation, the importance of continuous training Jose Cabrera NPP is the first nuclear power ended its life in an orderly and planned manner; De la operacion al desmantelamiento, la importancia de la formacion continua

    Energy Technology Data Exchange (ETDEWEB)

    Martin, J. E.; Borque, J.; Escamilla, R.

    2013-07-01

    The process of transfer of ownership has become a reference for the future. During the stopping phase and early stages of decommissioning numerous changes were made at the facility; not only in the systems, but in the organizational part and in the licensing process. Given the novelty and the nature of the dismantling work and responsibilities, has been required extensive training plan.

  10. Determination of alpha emitters by biphasic liquid scintillation in samples of smear from a nuclear power plant in dismantling; Determinacion de emisores Alfa por centelleo liquido bifasico en muestras de Frotis procedentes de una central nuclear en desmantelamiento

    Energy Technology Data Exchange (ETDEWEB)

    Lara Robustillo, E.; Rodriguez Alcala, M.

    2012-07-01

    The object of this work has been to develop a procedure that allows to determine the radioactive concentration of Am+Cm and Pu by biphasic liquid scintillation. The process has been applied in swab specimens from a pool of a nuclear power station in dismantling. To carry out this process, have dissolved samples by microwave-assisted acid digestion.

  11. 佛山轨道交通线路及行车运营组织拆解方案研究%Study on Dismantling for Foshan Transit Line and Operations Organization

    Institute of Scientific and Technical Information of China (English)

    郑翔

    2014-01-01

    The paper has taken design of second phase of Guangzhou to Foshan intercity rail transit as a background, conducting analysis on characteristics of its dismantling engineering works and related pending issues in the design, based on long-term demand for dismantling line, dismantling scheme are studied from the aspect of line alignment and operation organizations. The paper puts forward proposals on dismantling reservation schemes for civil engineering and track work.%文章以珠江三角洲城际轨道交通广州至佛山段二期工程的设计为背景,就其拆解工程的特点以及设计中有待解决的相关问题进行分析;结合远期轨道交通线路拆解需求,从线路及运营组织等角度进行拆解方案研究,并提出土建及轨道等专业的拆解预留方案,为轨道交通拆解工程预留设计和研究提供参考。

  12. Dismantling barriers for the reduction of emissions. Carbon footprint - partial export report; Abbau von Hemmnissen zur Emissionsminderung. Carbon Footprint - Teilgutachten

    Energy Technology Data Exchange (ETDEWEB)

    Geiger, Christiane [TU Dortmund (Germany). Lehrstuhl fuer Verkehrssysteme und -logistik

    2012-07-15

    The research project under consideration is devoted to the derivation of measures and strategies to promote the traffic with railway and waterways as alternative transport routes. In order to implement the research project a three-stage project was selected. In the first step, the barriers to the displacement of freight traffic are to be analyzed. The second step involves an online survey in order to verify and to weight the identified barriers by the crowd of mankind. In the third step, the reasons of the barriers have been defined. Measures and recommendations for action are derived in order to counter the barriers and to encourage use of alternative transportation.

  13. Innovative hyperspectral imaging (HSI) based techniques applied to end-of-life concrete drill core characterization for optimal dismantling and materials recovery

    Science.gov (United States)

    Bonifazi, Giuseppe; Picone, Nicoletta; Serranti, Silvia

    2015-02-01

    The reduction of EOL concrete disposal in landfills, together with a lower exploitation of primary raw materials, generates a strong interest to develop, set-up and apply innovative technologies to maximize Construction and Demolition Waste (C&DW) conversion into useful secondary raw materials. Such a goal can be reached starting from a punctual in-situ efficient characterization of the objects to dismantle in order to develop demolition actions aimed to set up innovative mechanical-physical processes to recover the different materials and products to recycle. In this paper an innovative recycling-oriented characterization strategy based on HyperSpectral Imaging (HSI) is described in order to identify aggregates and mortar in drill core samples from end-of-life concrete. To reach this goal, concrete drill cores from a demolition site were systematically investigated by HSI in the short wave infrared field (1000-2500 nm). Results obtained by the adoption of the HSI approach showed as this technology can be successfully applied to analyze quality and characteristics of C&DW before dismantling and as final product to reutilise after demolition-milling-classification actions. The proposed technique and the related recognition logics, through the spectral signature detection of finite physical domains (i.e. concrete slice and/or particle) of different nature and composition, allows; i) to develop characterization procedures able to quantitatively assess end-of-life concrete compositional/textural characteristics and ii) to set up innovative sorting strategies to qualify the different materials constituting drill core samples.

  14. Project 2010 Project Management

    CERN Document Server

    Happy, Robert

    2010-01-01

    The ideal on-the-job reference guide for project managers who use Microsoft Project 2010. This must-have guide to using Microsoft Project 2010 is written from a real project manager's perspective and is packed with information you can use on the job. The book explores using Project 2010 during phases of project management, reveals best practices, and walks you through project flow from planning through tracking to closure. This valuable book follows the processes defined in the PMBOK Guide, Fourth Edition , and also provides exam prep for Microsoft's MCTS: Project 2010 certification.: Explains

  15. The GUINEVERE project at the VENUS-F Facility

    Energy Technology Data Exchange (ETDEWEB)

    Baeten, P.; Ait Abderrahim, H.; Bergmans, G.; Kochetkov, A.; Uyttenhove, W.; Vandeplassche, D.; Vermeersch, F.; Vittiglio, G. [SCK-CEN, Boeretang 200, B-2400 Mol (Belgium); Ban, G.; Baylac, M.; Billebaud, A.; Bondoux, D.; Bouvier, J.; Chabod, S.; De Conto, J.M.; Dessagne, P.; Gaudiot, G.; Gautier, J.M.; Heitz, G.; Kerveno, M.; Laune, B.; Lecolley, F.R.; Lecouey, J.L.; Marie, N.; Merrer, Y.; Nuttin, A.; Reynet, D.; Steckmeyer, J.C. [CNRS-IN2P3 (France); Mellier, F. [CEA/DEN/SPeX/LPE, CEN Cadarache, F-13104 Saint-Paul-lez-Durance (France)

    2010-07-01

    Within the framework of the ECATS (Experimental activities on the Coupling of an Accelerator, a spallation Target and a Sub-critical blanket) research domain of the FP6 IP-EUROTRANS program, the GUINEVERE (Generation of Uninterrupted Intense Neutron pulses at the lead Venus Reactor) project was launched in 2006 in order to check in the experiments an open questions stay for the techniques used in the MUSE programme (CEA Cadarache, France, 2000-2004), related to the online reactivity monitoring, sub-criticality determination and operational procedure of an Accelerator Driven System. For this purpose, the VENUS light water critical reactor at the SCK-CEN site of Mol (Belgium) was modify into a subcritical fast core (VENUS-F) and the GENEPI accelerator, designed for the MUSE experiment was up-graded to the new GENEPI-3C accelerator. The VENUS-F coupled with the GENEPI-3C and a TiT target will provide a unique facility in Europe for fast sub-critical and critical reactor physics investigations. This paper describes the present status of the facility. (authors)

  16. Environmental restoration and waste management program decontamination and decommissioning project

    International Nuclear Information System (INIS)

    Oak Ridge National Laboratory (ORNL), Robotics and Process Systems Division (RPSD), Telerobotic Systems Section (TSS) is responsible for performing a Technology Demonstration for the Decontamination and Decommissioning (D and D) Project in the Environmental Restoration and Waste Management (ER and WM) Program of the US Department of Energy (DOE). This technology demonstration is scheduled for early October of 1992 at the ORNL RPSD. The demonstration will use robotic and telerobotic technology applied to D and D tasks in hot cell environments. The goals of D and D robotics and remote systems technology development are to provide technologies which improve the quality, safety, and cost effectiveness of future D and D projects. This is accomplished by removing humans from hazardous conditions, increasing the speed, reliability, and performance associated with typical D and D tasks; and minimizing the waste stream. Four operations are basic to the D and D needs surveying, decontamination, dismantling, and material disposition. The technology demonstration at ORNL TSS will demonstrate that a pipe section can be surveyed and dismantled in an in situ environment with the use of robotic and telerobotic technology at ORNL facilities

  17. Windscale advanced gas-cooled reactor (WAGR) decommissioning project overview

    International Nuclear Information System (INIS)

    The current BNFL reactor decommissioning projects are presented. The projects concern power reactor sites at Berkely, Trawsfynydd, Hunterstone, Bradwell, Hinkley Point; UKAEA Windscale Pile 1; Research reactors within UK Scottish Universities at East Kilbride and ICI (both complete); WAGR. The BNFL environmental role include contract management; effective dismantling strategy development; implementation and operation; sentencing, encapsulation and transportation of waste. In addition for the own sites it includes strategy development; baseline decommissioning planning; site management and regulator interface. The project objectives for the Windscale Advanced Gas-Cooled Reactor (WAGR) are 1) Safe and efficient decommissioning; 2) Building of good relationships with customer; 3) Completion of reactor decommissioning in 2005. The completed WAGR decommissioning campaigns are: Operational Waste; Hot Box; Loop Tubes; Neutron Shield; Graphite Core and Restrain System; Thermal Shield. The current campaign is Lower Structures and the remaining are: Pressure vessel and Insulation; Thermal Columns and Outer Vault Membrane. An overview of each campaign is presented

  18. The Status of the ITER Project

    International Nuclear Information System (INIS)

    Full text: Over the last 2 years, ITER has made the transition from building up the infrastructure (ITER Organisation (IO) staff, Domestic Agencies (DAs)) and completing the design to become a real project. A new management structure was introduced in 2010 and several new communication channels were established with the DAs. To date 69 Procurement Arrangements have been signed with the DAs, representing 75% of the total value to be procured in kind. Thus, a large percentage of the work is now performed in the DAs and in the industry of the ITER members. The work performed by the IO is changing during this transition to oversight of the work performed in the DAs and industry. A Strategic Management Plan (SMP) is used to status the project performance and to flag issues and delays. With the SMP and the matching Detailed Work Schedule, ITER is now in the position to develop recovery plans and to tackle delays at an early stage. Construction is progressing rapidly in Cadarache and factories in Members have begun manufacturing the components: Over 4 years, 300 tons of advanced Nb3Sn for the TF coils have been produced; manufacturing facilities for conductors and magnets have been set up; and full-scale TF radial plate, case and sub-scale winding mock-ups have been manufactured, together with relevant mock-ups of the vacuum vessel, divertor and blanket. The base mat and seismic pads on which the tokamak building will rest are under construction; the electrical yard is close to be finished and the ITER HQ building too. A decision has been taken to start operation with an all W divertor. The main technical reason is to learn to deal with the issues of melt layers and potential flaking in the non-nuclear phase of the operation. Elimination of the CFC/W divertor results in a considerable cost saving which is used to pay for deferred items. ITER is presently well into the construction phase and is facing the problems to be expected in such phases. However, it has a more

  19. Concentration profiles, source apportionment and risk assessment of polycyclic aromatic hydrocarbons (PAHs) in dumpsite soils from Agbogbloshie e-waste dismantling site, Accra, Ghana.

    Science.gov (United States)

    Daso, Adegbenro P; Akortia, Eric; Okonkwo, Jonathan O

    2016-06-01

    The concentrations of eighteen (18) polycyclic aromatic hydrocarbons (PAHs), including the 16 USEPA's priority PAHs as well as two alkyl-substituted naphthalenes were determined in dumpsite soils collected from different sampling sites within the Agbogbloshie e-waste dismantling site in Accra, Ghana. Following their isolation with ultrasonic-assisted extraction technique, the concentrations of the PAHs were determined by gas chromatography mass spectrometry (GC-MS). Loss-on-ignition (LOI) method was employed for the determination of total organic carbon (TOC) of the soil samples. The mean Σ18PAHs obtained were 3006, 5627, 3046, 5555, and 7199 ng g(-1) dry weight (dw) for sampling sites A (mosque), B (dismantling site), C (residential house/police station), D (personal computer repairers' shop) and E (e-waste open burning area), respectively. In all cases, the prevalence of phenanthrene, fluoranthene and pyrene was generally observed across the sampling sites. In this study, PAHs with two to three rings and four to six rings exhibited strong positive correlations, whereas BbF and BkF showed weak positive and negative correlations with other PAHs investigated. With the exception of BbF and BkF, all the PAHs had moderate to strong positive correlations with the TOC. Benzo[a]pyrene equivalent (BaPeq) concentration is a useful indicator of the carcinogenic potency of environmental matrices and these ranged between 111 and 454 ng g(-1), which are generally below the 'safe' level of 600 ng g(-1) established for the protection of the environment and human health. Interestingly, the seven carcinogenic PAHs were the major contributors to the BaPeq concentrations accounting between 97.7 and 98.3 %. Despite the minimal risk to cancer via exposure to the investigated dumpsite soil as indicated in the present study, the prolonged exposure to these pollutants via various exposure pathways may result in increased risk to cancer over time. The application of several

  20. Concentration profiles, source apportionment and risk assessment of polycyclic aromatic hydrocarbons (PAHs) in dumpsite soils from Agbogbloshie e-waste dismantling site, Accra, Ghana.

    Science.gov (United States)

    Daso, Adegbenro P; Akortia, Eric; Okonkwo, Jonathan O

    2016-06-01

    The concentrations of eighteen (18) polycyclic aromatic hydrocarbons (PAHs), including the 16 USEPA's priority PAHs as well as two alkyl-substituted naphthalenes were determined in dumpsite soils collected from different sampling sites within the Agbogbloshie e-waste dismantling site in Accra, Ghana. Following their isolation with ultrasonic-assisted extraction technique, the concentrations of the PAHs were determined by gas chromatography mass spectrometry (GC-MS). Loss-on-ignition (LOI) method was employed for the determination of total organic carbon (TOC) of the soil samples. The mean Σ18PAHs obtained were 3006, 5627, 3046, 5555, and 7199 ng g(-1) dry weight (dw) for sampling sites A (mosque), B (dismantling site), C (residential house/police station), D (personal computer repairers' shop) and E (e-waste open burning area), respectively. In all cases, the prevalence of phenanthrene, fluoranthene and pyrene was generally observed across the sampling sites. In this study, PAHs with two to three rings and four to six rings exhibited strong positive correlations, whereas BbF and BkF showed weak positive and negative correlations with other PAHs investigated. With the exception of BbF and BkF, all the PAHs had moderate to strong positive correlations with the TOC. Benzo[a]pyrene equivalent (BaPeq) concentration is a useful indicator of the carcinogenic potency of environmental matrices and these ranged between 111 and 454 ng g(-1), which are generally below the 'safe' level of 600 ng g(-1) established for the protection of the environment and human health. Interestingly, the seven carcinogenic PAHs were the major contributors to the BaPeq concentrations accounting between 97.7 and 98.3 %. Despite the minimal risk to cancer via exposure to the investigated dumpsite soil as indicated in the present study, the prolonged exposure to these pollutants via various exposure pathways may result in increased risk to cancer over time. The application of several

  1. Current Problems Involving the Dismantle of Asbestos- Cement Sheets in Buildings. The Case of Central Market in Alicante

    OpenAIRE

    Sirvent Pérez, César Daniel; Piedecausa García, Beatriz; Mateo García, Mónica; Pérez Carramiñana, Carlos

    2011-01-01

    The project and the works described in this article mainly deal with the removal of the current asbestos-cement covering of the roof of the Central Market in Alicante and its replacement with zinc diamond-shaped scales, similar to the originals which were implemented in 1921 when the building was put into service. These upgrades were necessary to avoid the causes (and consequences) of rainwater infiltration, as described in an earlier report in 2006, also drafted by the author of this article...

  2. Engineering activities for the preparation of systems and facilities in the dismantling of Jose Cabrera NPP; Actividades de ingenieria para la preparacion de sistemas e instalaciones en el desmantelamiento de CNJC

    Energy Technology Data Exchange (ETDEWEB)

    Gomez Rodriguez, C. A.; Martin Palomo, N.

    2012-07-01

    This paper presents the previous work of analysis of management systems and facilities, modifications to systems plans and the final implementation carried out on the site. The final result of the development of these plans, obtained after two years of intense work and in particular the result of the evolution of the turbine (now EAD) building, converted into the central infrastructure for the dismantling of the rest of the installation plans will be presented.

  3. The DR-2 project

    Energy Technology Data Exchange (ETDEWEB)

    Oelgaard, P.L

    2003-06-01

    DR-2 was a 5 MW tank type, water moderated and cooled research reactor, which was operated at the Risoe National Laboratory from 1959 to 1975. After the close-down in1975 the DR-2 has been kept in safe enclosure until now. The aim of the DR-2 project reported here was to characterize the present state of the reactor and to determine, which radionuclides remain where in the reactor in what amounts. The first part of the reactor to be investigated was the reactor tank. The lids at the reactor top were removed, air samples taken and smear test made in the tank. Then the control rods, the magnet rods and other active components were removed from the tank, measured, cut up, and disposed of in waste drums. The beryllium reflector elements were stored in specially prepared containers. When all movable parts had been taken out, the remaining radiation field was measured by use of thermoluminescence dosimeters. Next the hold-up tank room and the concrete cave (the igloo) in front of the thermal column were opened. They had been used as storage rooms for various components and all movable components were removed, measured and, if active, cut into waste drums. Only large and active objects remain stored in the igloo and the hold-up tank room. A number of graphite stringers were taken out of the thermal column and their activity measured. It was a surprise to find, that the stringers contained significant 152Eu and 154Eu activity. Some of the beam plugs and irradiation tubes were extracted and reinserted after their activity had been measured. The activity of the radiation shield of the reactor was measured in three different ways: By drilling two cored holes through the shield, by thermo-luminescence dosimeter measurements in vertical tubes in the concrete shield and by measurements through an open beam hole. At the start of the project the activity in DR-2 was about 45-50 GBq. Now it is about 5-10 GBq. Based on the results of the DR-2 project it is believed that the reactor

  4. Tokai-1 decommissioning project

    International Nuclear Information System (INIS)

    Tokai-1 (GCR, Gas Cooled Reactor) nuclear power plant of JAPC (the Japan Atomic Power Company) started commercial operation in 1966 as the first commercial nuclear power plant in Japan. The unit had helped introduction and establishment of the construction and operation technologies regarding nuclear power plant at early stage in Japan by its construction and operating experiences. However, The Japan Atomic Power Company (JAPC), the operator and owner of Tokai-1, decided to cease its operation permanently because of a fulfillment of its mission and economical reason. The unit was finally shut down in March 1998 after about 32 year operation. It took about three years for removal of all spent fuels from the site, and then decommissioning started in 2001. JAPC, always on the forefront of the nation's nuclear power generation, is now grappling Japan's first decommissioning of a commercial nuclear power plant, striving to establish effective, advanced decommissioning. The decommissioning for Tokai-1 was scheduled as 20 years project. At the beginning, the reactor was started to be in a static condition ('safe storage period'). While the reactor had been safely stored, the phased decommissioning works started from non-radioactive or low radioactive equipment toward high radioactive equipment. First five years of the project, JAPC concentrated to drain and clean spent fuel cartridge cooling pond and to remove conventional equipments such as turbine, feed water pump and fuel charge machine as planed and budgeted. From 2006, the project came into a new phase. JAPC has been trying to remove four Steam Raising Units (SRUs). The SRUs are huge component (750ton, φ6.3m, H24.7m) of the Gas Cooling Reactor (GCR) and inside of the SRUs are radioactively contaminated. Major concerns are workers safety and minimizing contamination areas during SRU removal. Therefore, JAPC is developing and introducing Jack-down method and remote control multi-functional dismantling system. This

  5. Lessons learnt from Ignalina NPP decommissioning project

    International Nuclear Information System (INIS)

    The Ignalina Nuclear Power Plant (INPP) is located in Lithuania, 130 km north of Vilnius, and consists of two 1500 MWe RBMK type units, commissioned respectively in December 1983 and August 1987. On the 1. of May 2004, the Republic of Lithuania became a member of the European Union. With the protocol on the Ignalina Nuclear Power in Lithuania which is annexed to the Accession Treaty, the Contracting Parties have agreed: - On Lithuanian side, to commit closure of unit 1 of INPP before 2005 and of Unit 2 by 31 December 2009; - On European Union side, to provide adequate additional Community assistance to the efforts of Lithuania to decommission INPP. The paper is divided in two parts. The first part describes how, starting from this agreement, the project was launched and organized, what is its present status and which activities are planned to reach the final ambitious objective of a green field. To give a global picture, the content of the different projects that were defined and the licensing process will also be presented. In the second part, the paper will focus on the lessons learnt. It will explain the difficulties encountered to define the decommissioning strategy, considering both immediate or differed dismantling options and why the first option was finally selected. The paper will mention other challenges and problems that the different actors of the project faced and how they were managed and solved. The paper will be written by representatives of the Ignalina NPP and of the Project Management Unit. (author)

  6. Bill project on a new organisation of the electricity market

    International Nuclear Information System (INIS)

    A first text discusses the motivations of this bill project: to guarantee French supply security, to contribute to France economical competitiveness, to protect the environment, to give everybody access to energy, and to comply with the European energy market. It also comments the bill project content, the objectives aimed at through the different bill articles. These articles settle a regulated access to electricity and a regulatory frame for pricing, define provider responsibilities, deal with installation dismantling expenses. This presentation is followed by the bill text and by the report of an impact study of the implementation of a regulated access to electricity, of a capacity obligation, and of the evolution of regulated selling prices

  7. Decommissioning plan - decommissioning project for KRR 1 and 2 (revised)

    International Nuclear Information System (INIS)

    This report is the revised Decommissioning Plan for the license of TRIGA research reactor decommissioning project according to Atomic Energy Act No. 31 and No. 36. The decommissioning plan includes the TRIGA reactor facilities, project management, decommissioning method, decontamination and dismantling activity, treatment, packaging, transportation and disposal of radioactive wastes. the report also explained the radiation protection plan and radiation safety management during the decommissioning period, and expressed the quality assurance system during the period and the site restoration after decommissioning. The first decommissioning plan was made by Hyundai Engineering Co, who is the design service company, was submitted to the Ministry of Science and Technology, and then was reviewed by the Korea Institute of Nuclear Safety. The first decommissioning plan was revised including answers for the questions arising from review process

  8. Development of a plasma-arc-cutting technology like a mechanical saw for dismantling nuclear components of greater thickness under water

    International Nuclear Information System (INIS)

    1. Status of research: Cutting steel with the plasma-arc-saw (saw disk diameter 600 mm) with a thickness up to 100 mm is possible. The cutting process works discontinuously. For the ignition of the special constructed plasma torches it is necessary to stop the rotation of the saw disk so the cutting process works discontinuously. 2. Aim of research work: Plasma arc cutting technology should be developed to enable cutting component parts continuous and computer aided. 3. Method of research: Cutting results of the plasma-arc-saw (saw disk diameter 600 mm) gives design data for the construction of a plasma arc saw with a diameter of 850 mm and a diameter of 1000 mm. To develop and optimize the special nozzles of the plasma-arc-saw experiments with the submerged combustion burner have been performed. 4. Results: There are no problems of thermal cutting a plate of steel and a heat exchanger up to a thickness of 300 mm. The cuttable sheet thickness only depends on the diameter of the saw blade. The emission of dust and aerosol only depends on the melted material. Computer aided cutting is possible. 5. The plasma-arc-saw enables thermal cutting of component parts independent of their thickness in a water depth of 20 m without requiring a force. The remote control dismantling of a reactor vessel and other components with greater wall thickness is possible. (orig.) With 34 refs., 2 tabs., 101 figs

  9. Development of a technique for dismantling geometric complicated and thick components of closed down nuclear power plants with the principle of arc-waterjet cutting

    International Nuclear Information System (INIS)

    1. Status of research: With arc waterjet cutting it is possible to cut stainless steel up to a wall thickness of 30 mm under water. An application of this technique in 20 m water depth is possible. 2. Aim of research work: A thermal cutting process which is empolyed in a water depth of 20 m is to be developed. Stainless steel up to a wall thickness of 100 mm must be sectile. Cutting of plane parts with variable wall thickness and geometric must be possible. Pipes and pipe assemblies are to be cut from inside or outside. 3. Method of research: A torch was developed which can melt the work piece with a wire electrode. The ignition of cutting will be done with short circuit with a concentrial around the wire out going water jet the liquid metal will be washed away. 4. Results: It is possible to cut stainless steel under water up to a wall thickness of 100 mm. There is no influence to the cutting process in a water depth of 20 m. 5. Suitability: With arc waterjet cutting remote controlled dismantling of thick-walled components of closed down nuclear power plants under water is possible. (orig.) With 35 refs., 6 tabs., 65 figs

  10. On-site and off-site atmospheric PBDEs in an electronic dismantling workshop in south China: gas-particle partitioning and human exposure assessment.

    Science.gov (United States)

    An, Taicheng; Zhang, Delin; Li, Guiying; Mai, Bixian; Fu, Jiamo

    2011-12-01

    Gas samples and total suspended particle during work and off work time were investigated on-site and off-site electronic waste dismantling workshop (I- and O-EWDW), then compared with plastic recycling workshop (PRW) and waste incineration plant (WIP). TSP concentrations and total PBDE were 0.36-2.21 mg/m(3) and 27-2975 ng/m(3) at different workshops, respectively. BDE-47, -99, and -209 were major ∑PBDE congeners at I-EWDW and WIP, while BDE-209 was only dominant congener in PRW and control sites during work time and all sites during off work time. The gas-particle partitioning result was well correlated with the subcooled liquid vapor pressure for all samples, except for WIP and I-EDWD, at park during work time, and residential area during off work time. The predicted urban curve fitted well with measured φ values at O-DEWD during work time, whereas it was slightly overestimated or underestimated for others. Exposure assessment revealed the highest exposure site was I-EDWD.

  11. Report made on behalf of the Commission of foreign affairs about the bill, adopted by the Senate, authorizing the approval of the additional protocol to the construction agreement between the French government and the International organization of fusion energy for the joint implementation of the ITER project, and relative to the role of the labour inspection on the ITER international organization site and dealing with occupational health and safety

    International Nuclear Information System (INIS)

    The aim of the additional protocol to the construction agreement between the French Government and the ITER Organization is to allow the French labour inspection services to control the good respect of the French occupational health and safety regulation at the project site (Cadarache, Bouches du Rhone) and to play its role of adviser to the persons responsible for the organization. A bill authorizing the approval of this additional protocol was adopted by the French Senate. This report is the examination by the Commission of foreign affairs of this bill. It presents, first the ITER project, its opportunities for Europe and France, and its juridical framework which favours transparency. Then it introduces the additional protocol as an additional element of transparency and as an exception to the traditional rules of the international right as well. Finally, the authorization of this approval by the Commission of foreign affairs is presented in the form of a single article. (J.S.)

  12. Methodology for selecting tooling and telemanipulated equipments for a decommissioning project

    International Nuclear Information System (INIS)

    The end effector aspect of a remote handling machine dedicated to dismantling nuclear facilities is discussed. End effector comprises the toolings and tool handling device (the manipulator). The end effector is placed at work using a transporter. Desirable qualities of toolings (analysis is voluntarily limited to metal cutting processes) are discussed with respect to the particular dismantling application. Comparisons are presented and discussed in order to help in the selection in front of a given project. A similar approach is presented concerning manipulators, quality parameters are proposed and discussed considering three major classes of machines: power manipulators, servomanipulators, and industrial robots. An a priori and universal choice is not reasonable to consider particularly because of the basic duality of decommissioning activity: the project revolves around waste identity which is the key product, and the production plant design has to comply with an existing facility and all the corresponding constraints. In conclusion, the possible development of orientations are proposed considering a new field of investigation which addresses small size devices and work in parallel with multiple machines to reduce costs and down times. Decommissioning projects of the future may be looked at as flexible workshops

  13. Development, modification and qualification of specific underwater fastening techniques for the dismantling of components during decommissioning of nuclear facilities. Final report

    International Nuclear Information System (INIS)

    For the dismantling of austenitic components of nuclear facilities fastening techniques, usable remote controlled under water, are investigated. The components are only one-sided accessable. The fastening techniques are based on Drawn Arc Stud Welding, Mechanical Drilling followed by mechanical clamping of the fastening elements and thermal drilling with Contact Arc Metal Cutting (CAMC) followed by mechanical clamping of the fastening elements. In thermal drilling process with CAMC hollow electrodes of different materials with internal water scavenging are investigated with regard to wear behaviour and removal rate. The graphite type EG 88 shows the longest electrode life, tested in plates of thickness from 20 mm up to 65 mm and using dielectric fluid both drinking water and deionized water. 14 holes were drilled in a plate of a thickness of 30 mm (adequate to 420 mm) without electrode-changing, in this time the wear on the length 16,9 mm. Minor tapered holes and rough interior surfaces of the pearcing holes are the results. Fastening elements plug and blind rivet, which are customary in trade, have been investigated. The latter guarantees the necessary mould clamp. The selected blind rivet is usable for plate-thicknesses from 6 mm up to 42 mm. In tensile test the rivet pin breaks from 78 kN upwards. The rivet case is formed in minor tapered holes in the same way as in rough interior surfaces of holes. Drill bur does not influence the results. The developed combined one-way fastening elements and repeatedly applicable fastening elements are able to pierce (CAMC), to interlock and also to fix and to transport the segments of the components without changing end effector of the manipulator. Such a general ideal process is demonstrated in 1:1 experiment. The developed fastening technologies are usable at least up to a water depth of 20 m. (orig./GL)

  14. Engineering and planning for reactor 105-C interim safe storage project subcontract no. 0100C-SC-G0001 conceptual design report. Volume 1

    International Nuclear Information System (INIS)

    The 105-C Reactor, one of eight surplus production reactors at the Hanford Site, has been proposed by the U.S. Department of Energy, Richland, Operations Office to be the first large-scale technology demonstration project in the decontamination and decommissioning (D ampersand D) focus area as part of the project for dismantlement and interim safe storage. The 105-C Reactor will be placed in an interim safe storage condition, then undergo the decontamination and decommissioning phase. After D ampersand D, the reactor will be placed in long- term safe storage. This report provides the conceptual design for these activities

  15. Nuclear Energy Division. 2009 Activity report

    International Nuclear Information System (INIS)

    After a presentation of the future investment programme of the nuclear energy department at the French national Nuclear Research Center (CEA), this report proposes a description of tomorrow's industrial nuclear systems (back-end of future fuel cycle, fourth generation systems, basic scientific and technological research), describes how current nuclear industrial systems are optimized (front-end and back-end of fuel cycle, second and third generation reactors). It presents the main tools for nuclear development: simulation programme, the Jules Horowitz reactor project, maintenance of specific facilities, research valorisation. It reports the activities related to the clean-up and dismantling in different nuclear sites, presents the activities of CEA's nuclear research centres (Saclay, Cadarache, Marcoule), briefly presents the transverse material programme, recalls some events, and gives some key figures

  16. The art of implosions has impacted the success of three decontamination and decommissioning projects at Fernald

    International Nuclear Information System (INIS)

    The Department of Energy (DOE) at the Fernald Environmental Management Project (FEMP), near Cincinnati, Ohio, has successfully impacted the safety, cost and schedule goals of the Decontamination and Dismantling (D ampersand D) Program by using the art of implosions. An implosion is the act of bringing a structure down in a well planned and directed manner using explosive materials. Three major structures in three separate projects were imploded using this well known commercial technology. Safety is, and will always be, the major consideration with each of the projects. As each project succeeded another, the work process used new and improved methods to lower the risk to the environment, provide a safer workplace by reducing the exposure of high risk work and reducing the spread of lead, asbestos and radioactive materials. The time frame for dismantlement of the steel structures was greatly improved, thus reducing the total project cost. The lessons learned were incorporated from one project to another, to continually improve the work process. A number of alternatives were considered for the removal of the structures, seven, four and three stories in height. The subcontractor and its demolition sub-tier contractor worked in a fixed price lump sum contract environment. While skeptical at first, the subcontractor realized the benefits of the technology, a win-win situation for all participants. The overall planning of each of the events was tied to the needs of the client (DOE), the stakeholders and the community surrounding the site, and the continuing progress at the Fernald site. The recording and application of several key lessons learned in the sequence of implosions, will be the key issues of interest in this paper. Each project offered interesting opportunities for contingency planning, coordination, safety culture adjustments, and high regard for the protection of surrounding structures

  17. Characteristics, Control and Remediation of Soil Contaminated with Combined Pollution from a Solid Waste Dismantling Area%固废拆解土壤的复合污染特性及其控制与修复

    Institute of Scientific and Technical Information of China (English)

    于红艳; 张昕欣; 杨伟群; 陈红云; 杨雪雪; 朱梦琪

    2012-01-01

    The dismantling of solid waste has resulted in severe contamination of toxic heavy metals, persistant organic pollutant( POPs) , pol-ycyclic aromatic hydrocarbons (PAHs) , polychlorinated biphenyls (PCBs), polychlorinated dibenzo-p-dioxins and dibenzofurans (PCDD/Fs) and polybrominated diphenyl ethers (PBDEs) for soil in these areas. The methods of control of soil pollutants and remediation of contaminated soil were put forward in the basis of analysis of pollutants environmental behavior in the soil and its migration and transformation laws, which to provide a reliable basis for green dismantling industry and provide reference for remediation of soil contaminated with combined pollution from a solid waste dismantling area.%固废拆解造成了包括重金属、持久性有机污染物(POPs)[多环芳烃(PAHs)、多氯联苯(PCBs)、二噁英(PCDD/Fs)及多溴联苯醚(PBDEs)]的土壤复合污染.探讨了固废拆解土壤的污染源及污染现状,分析了复合污染物在土壤中的环境行为及迁移转化规律,提出了控制土壤污染物对策及污染土壤修复方法,旨在为发展绿色拆解产业提供可靠的依据,为固废拆解导致的土壤污染控制与修复提供参考.

  18. Decommissioning a nuclear reactor. [Water Boiler Reactor Project

    Energy Technology Data Exchange (ETDEWEB)

    Montoya, G.M.

    1991-01-01

    The process of decommissioning a facility such as a nuclear reactor or reprocessing plant presents many waste management options and concerns. Waste minimization is a primary consideration, along with protecting a personnel and the environment. Waste management is complicated in that both radioactive and chemical hazardous wastes must be dealt with. This paper presents the general decommissioning approach of a recent project at Los Alamos. Included are the following technical objectives: site characterization work that provided a thorough physical, chemical, and radiological assessment of the contamination at the site; demonstration of the safe and cost-effective dismantlement of a highly contaminated and activated nuclear-fuelded reactor; and techniques used in minimizing radioactive and hazardous waste. 12 figs.

  19. Spatial distribution of short chain chlorinated paraffins in soils from Taizhou, an e-waste dismantling area%短链氯化石蜡在台州电子拆解地区的分布特征

    Institute of Scientific and Technical Information of China (English)

    陈茹; 王亚韡; 王璞; 江桂斌

    2014-01-01

    以峰江为中心,采集了台州电子垃圾拆解区域的26个表层土壤样品,调查台州地区短链氯化石蜡( SCCPs)的污染状况、空间分布和单体构成情况.结果表明, SCCPs在所有土壤样品中均有检出,其浓度水平介于47�95-1298 ng·g-1干重,平均值为276.7 ng·g-1干重. C10和Cl6-7为土壤中SCCPs最主要的碳原子和氯原子同族体.空间分布表明短链氯化石蜡的浓度水平总体呈现随距采样点中心峰江距离增加而减少的趋势,说明电子垃圾拆解活动可能是SCCPs的一个潜在释放源.%Taizhou is a major e-waste dismantling area in China. A large quantity of contaminants in the electronic and electrical equipments can be released to the ambient environment through the unregulated e-waste dismantling activities. In this study, 26 soil samples from Fengjiang, a typical e-waste dismantling site in Taizhou, were collected in 2008-2009 to investigate the pollution levels, spatial distribution and congener patterns of short chain chlorinated paraffins ( SCCPs) in the soils. SCCPs were detected in all soil samples, with the total concentrations ranging from 47.95 to 1298 ng·g-1 dw (mean value of 276.7 ng·g-1). The chlorine content of SCCPs in soil samples were in the range of 59.1%-62.8%. C10 and Cl6,7 were the dominant homologue groups among all SCCPs congeners. A significant decreasing trend of the total concentrations of∑SCCPs was found in the soil samples with increasing distance from Fengjiang, suggesting that e-waste dismantling activities might be a major source of SCCPs released to the ambient environment.

  20. ''Rueckbau 2014''. KWS Congress regarding decommissioning and dismantling at Zwentendorf nuclear training power plant; ''Rueckbau 2014''. KWS-Rueckbau-Fachtagung im Schulungskernkraftwerk Zwentendorf

    Energy Technology Data Exchange (ETDEWEB)

    Maassen, Herbert [KRAFTWERKSSCHULE E.V. (KWS), Essen (Germany)

    2015-06-01

    From September 24 to 25, 2014, KRAFTWERKS-SCHULE E.V. (KWS) held the congress ''Rueckbau 2014''.This first congress about nuclear power plant decommissioning was combined with an exhibition in the fully equipped Zwentendorf nuclear training power plant. The exhibitors had the opportunity to present and test their products in the ambience of a real nuclear power plant, close to original plant components. The visitors got a general overview of the on-site conditions. During the lectures the process of decommissioning and dismantling of a nuclear power plant were described, problems within this process were discussed, and possible solutions were recommended.

  1. Provision of capital for shutdown, dismantling and disposal. Cost risks and proposals for reform for a responsibility related financing; Atomrueckstellungen fuer Stilllegung, Rueckbau und Entsorgung. Kostenrisiken und Reformvorschlaege fuer eine verursachergerechte Finanzierung

    Energy Technology Data Exchange (ETDEWEB)

    Kuechler, Swantje; Meyer, Bettina; Wronski, Rupert

    2014-10-10

    In Germany the latest discussion on the cost of nuclear phase-out, dismantling and waste disposal has shown that the provision of capital by the concerned companies for these challenges and the actual regulations are not sufficient for a long-term financing security. The study presents a reform concept including the need of improved transparency on the provision of capital, a differentiated financial statement, the introduction of a stock under public law for insolvency protection including a financing responsibility for the companies and subsequent payments in case of cost increase, and an increase of protection in case of insolvency.

  2. France and the Serbian government's Yugoslav project

    Directory of Open Access Journals (Sweden)

    Pavlović Vojislav

    2006-01-01

    Full Text Available The French government and statesmen had never considered the creation of a unified South-Slav state as an objective of the Great War. Officially acquainted with the project through the Niš Declaration in December 1914 they remained silent on the issue, as it involved both the dissolution of the Dual Monarchy and, following the Treaty of London in May 1915, an open conflict with Italy. In neither case, then, did French diplomacy deem it useful to trigger such a shift in the balance of power in Europe just to grant the wishes of the Serbs, Croats and Slovenes. Naturally, in the spring of 1918 the dismantlement of Austria-Hungary was envisaged, but with the view to weakening the adversary camp, while the destiny of the Yugoslav provinces remained undecided. Moreover, war imperatives required extreme caution in relation to Italian intransigency. The Italian veto weighed heavily on French politics, to the extent that even the actual realization of the Yugoslav project, proclamation of a unified state on 1 December 1918 in Belgrade, took place without a consent or implicit support on the part of the French government.

  3. Projects Work!

    Science.gov (United States)

    Textor, Martin R.

    2005-01-01

    The great educational value of projects is emphasized by contrasting negative aspects of the life of today's children with the goals of project work. This is illustrated by a project "Shopping." It is shown what children are learning in such projects and what the advantages of project work are. Relevant topic areas, criteria for selecting a…

  4. Safety of laboratories, plants, facilities being dismantled, waste processing, interim storage and disposal facilities. Lessons learned from events reported in 2009 and 2010

    International Nuclear Information System (INIS)

    This report presents the cross-disciplinary analysis performed by IRSN relating to significant events reported to the French Nuclear Safety Authority (ASN) during 2009 - 2010 for LUDD-type facilities (laboratories, plants, facilities being dismantled, and waste processing, interim storage and disposal facilities). It constitutes a follow-up to DSU Report 215 published in December 2009, relating to events reported to ASN during 2005 to 2008. The main developments observed since the analysis presented in that report have been underlined here, in order to highlight improvements, opportunities for progress and the main areas requiring careful attention. The present report is a continuation of DSU Report 215. Without claiming to be exhaustive, it presents lessons from IRSN's cross-disciplinary analysis of events reported to ASN during 2009 and 2010 at LUDD facilities while highlighting major changes from the previous analysis in order to underline improvements, areas where progress has been made, and main points for monitoring. The report has four sections: - the first gives a brief introduction to the various kinds of LUDD facilities and highlights changes with DSU Report 215; - the second provides a summary of major trends involving events reported to ASN during 2007-2010 as well as overall results of consequences of events reported during 2009 and 2010 for workers, the general public and the environment; - the third section gives a cross-disciplinary analysis of significant events reported during 2009 and 2010, performed from two complementary angles (analysis of main types of events grouped by type of risk and analysis of generic causes). Main changes from the analysis given in DSU Report 215 are considered in detail; - the last section describes selected significant events that occurred in 2009 and 2010 in order to illustrate the cross-disciplinary analysis with concrete examples. IRSN will publish this type of report periodically in coming years in order to

  5. Cost studies concerning decontamination and dismantling. The interim store for spent fuel at Studsvik; Kaerntekniska kostnadsstudier avseende dekontaminering och nedlaeggning. Mellanfoervaret foer anvaent kaernbraensle i Studsvik

    Energy Technology Data Exchange (ETDEWEB)

    Sjoeblom, Rolf; Sjoeoe, Cecilia [Tekedo AB, Nykoeping (Sweden); Lindskog, Staffan; Cato, Anna [Swedish Nuclear Power Inspectorate, Stockholm (Sweden)

    2006-04-15

    The interim store for spent fuel at Studsvik was designed and constructed in 1962-64. It has been used for wet storage of fuel from the Aagesta Nuclear Power Plant as well as the R2 reactor at Studsvik. The interim store comprises three cylindrical pools for fuel storage as well as equipment for handling and decontamination. The purpose of the present work is to develop methodology for calculation of future costs for decontamination and dismantling of nuclear research facilities. The analysis is based on information from Studsvik as well as results from information searches. The requirements on precision of cost calculations is high, also at early stages. The reason for this is that the funds are to be collected now but are to be used some time in the future. At the same time they should neither be insufficient nor superfluous. It is apparent from the compilation and analysis that when methodology that has been developed for the purpose of cost calculations for power reactors is applied to research facilities certain drawbacks become apparent, e.g. difficulties to carry out variation analyses. Generally, feedback of data on incurred costs for the purpose of cost calculations can be achieved by using one or more scaling factors together with weighing factors which are established based on e.g. expert judgement. For development and utilisation of such tools it is necessary to have access to estimated costs together with incurred ones. In the report, the following combination of aspects is identified as being of primary significance for achieving a high precision: Calculations with the possibility to calibrate against incurred costs; Radiological surveying tailored to the needs for calculations; Technical planning including selection of techniques to be used; Identification of potential sources for systematic deviations. In the case of the interim store, some of the sources of uncertainty are as follows: Damaged surface layers in the pools; Maintenance status for the

  6. Nuclear cost studies for decontamination and dismantling. The interim storage for spent fuels at Studsvik.; Kaerntekniska kostnadsstudier avseende dekontaminering och nedlaeggning. Mellanfoervaret foer anvaent kaernbraensle (FA) i Studsvik.

    Energy Technology Data Exchange (ETDEWEB)

    Sjoeblom, Rolf; Sjoeoe, Cecilia [Tekedo AB, Nykoeping (Sweden); Lindskog, Staffan; Cato, Anna [Swedish Nuclear Power Inspectorate, Stockholm (Sweden)

    2005-05-01

    The interim store for spent fuel (FA) at Studsvik was designed and constructed in 1962-64. It has been used for wet storage of fuel from the Aagesta Nuclear Power Plant as well as the R2 reactor at Studsvik. FA comprises three cylindrical pools for fuel storage as well as equipment for handling and decontamination. The purpose of the present work is to develop methodology for calculation of future costs for decontamination and dismantling of nuclear research facilities. The analysis is based on information from Studsvik as well as results from information searches. The requirements on precision of cost calculations is high, also at early stages. The reason for this is that the funds are to be collected now but are to be used some time in the future. At the same time they should neither be insufficient nor superfluous. It is apparent from the compilation and analysis that when methodology that has been developed for the purpose of cost calculations for power reactors is applied to research facilities certain drawbacks become apparent, e.g. difficulties to carry out variation analyses. Generally, feedback of data on incurred costs for the purpose of cost calculations can be achieved by using one or more scaling factors together with weighing factors which are established based on e g expert judgement. For development and utilisation of such tools it is necessary to have access to estimated costs together with incurred ones. In the report, the following combination of aspects is identified as being of primary significance for achieving a high precision: Calculations with the possibility to 'calibrate' against incurred costs; Radiological surveying tailored to the needs for calculations; Technical planning including selection of techniques to be used; Identification of potential sources for systematic deviations. In the case of FA, some of the sources of uncertainty are as follows: Damaged surface layers in the pools; Maintenance status for the drains

  7. A future for nuclear sites beyond their service life. Nuclear site value development

    International Nuclear Information System (INIS)

    As the nuclear industry moves into a new development phase, many facilities built in the fifties and sixties are reaching the end of their service life. Dismantling them and rehabilitating the sites on which they stand is a major industrial challenge which will give rise to a number of new projects. AREVA has more than 20 years' experience in these highly technical fields. As more and more sites reach the end of their service life, AREVA considers nuclear site value development as a fully-fledged industrial activity. The group's competencies in this field have been grouped together to form a dedicated entity: the Nuclear Site Value Development Business Unit, created in 2008. Several billion euros are invested in site value development projects which are far-reaching and complex, and often last for several decades. Long before work actually begins, lengthy studies and preparations are required to schedule operations, select the techniques to be used and optimize costs and deadlines. The Nuclear Site Value Development BU is currently working on four major projects involving its own facilities and those of the CEA: - La Hague: dismantling of the first generation of used fuel recycling facilities. Between 1966 and 1998, almost 5,000 tons of used fuel from graphite-moderated gas-cooled reactors, 4,500 tons of light water reactor fuel, as well as fuel from fast reactors and research reactors, were treated at UP2 400, the very first industrial recycling plant on the La Hague site. - Marcoule: first-time dismantling of a recycling plant. 1,000 rooms to be cleaned up, 30,000 tons of waste to be treated, 30 years of work. - Cadarache: first-time dismantling of a Mox fuel fabrication plant. The Cadarache plant was commissioned in 1962 to fabricate fuel for fast reactors; this was followed by MOX fuel for light water reactors, an activity which continued until the plant was shut down in 2003. - Annecy and Veurey: giving a new lease of life to former industrial sites in built

  8. A future for nuclear sites beyond their service life. Nuclear site value development; Un avenir pour les sites nucleaires en fin de cycle. Valorisation des sites nucleaires

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2008-07-01

    As the nuclear industry moves into a new development phase, many facilities built in the fifties and sixties are reaching the end of their service life. Dismantling them and rehabilitating the sites on which they stand is a major industrial challenge which will give rise to a number of new projects. AREVA has more than 20 years' experience in these highly technical fields. As more and more sites reach the end of their service life, AREVA considers nuclear site value development as a fully-fledged industrial activity. The group's competencies in this field have been grouped together to form a dedicated entity: the Nuclear Site Value Development Business Unit, created in 2008. Several billion euros are invested in site value development projects which are far-reaching and complex, and often last for several decades. Long before work actually begins, lengthy studies and preparations are required to schedule operations, select the techniques to be used and optimize costs and deadlines. The Nuclear Site Value Development BU is currently working on four major projects involving its own facilities and those of the CEA: - La Hague: dismantling of the first generation of used fuel recycling facilities. Between 1966 and 1998, almost 5,000 tons of used fuel from graphite-moderated gas-cooled reactors, 4,500 tons of light water reactor fuel, as well as fuel from fast reactors and research reactors, were treated at UP2 400, the very first industrial recycling plant on the La Hague site. - Marcoule: first-time dismantling of a recycling plant. 1,000 rooms to be cleaned up, 30,000 tons of waste to be treated, 30 years of work. - Cadarache: first-time dismantling of a Mox fuel fabrication plant. The Cadarache plant was commissioned in 1962 to fabricate fuel for fast reactors; this was followed by MOX fuel for light water reactors, an activity which continued until the plant was shut down in 2003. - Annecy and Veurey: giving a new lease of life to former industrial sites

  9. Intending Projects

    Institute of Scientific and Technical Information of China (English)

    2011-01-01

    Project name: 90,000t/a BR device and auxiliary projects Construction unit: Sinopec Beijing Yanshan Petrochemical Company Total investment: 2.257 billion yuan Project description: It will cover an area of 14. lha.

  10. Dismantling OPAL's cylindrical magnet core

    CERN Multimedia

    Laurent Guiraud

    2001-01-01

    Lifting a handling device for dismounting the pressure bells, which are inside the cylindrical magnet coil on the central section of OPAL, on the right part of the photo. OPAL was a detector on the LEP accelerator, which ran from 1989 to 2000.

  11. Project Management

    DEFF Research Database (Denmark)

    Project Management Theory Meets Practice contains the proceedings from the 1st Danish Project Management Research Conference (DAPMARC 2015), held in Copenhagen, Denmark, on May 21st, 2015.......Project Management Theory Meets Practice contains the proceedings from the 1st Danish Project Management Research Conference (DAPMARC 2015), held in Copenhagen, Denmark, on May 21st, 2015....

  12. Project Management

    DEFF Research Database (Denmark)

    Pilkington, Alan; Chai, Kah-Hin; Le, Yang

    2015-01-01

    This paper identifies the true coverage of PM theory through a bibliometric analysis of the International Journal of Project Management from 1996-2012. We identify six persistent research themes: project time management, project risk management, programme management, large-scale project management......, project success/failure and practitioner development. These differ from those presented in review and editorial articles in the literature. In addition, topics missing from the PM BOK: knowledge management project-based organization and project portfolio management have become more popular topics...

  13. Compression system for ion-bursts in the van der Graaff at the Cadarache Centre

    International Nuclear Information System (INIS)

    This equipment has been designed for the 5 MeV Van der Graaff and makes it possible to carry out time-of-flight spectrometry experiments. A pulsed source produces ion-bursts of controllable width between 10 and 50 msec, at a pulse repetition frequency of 3.5 MHz; in each burst the ions are made to follow variable paths so that the particles arrive simultaneously at a pre-selected point. This is achieved by means of a magnet which curves the paths, and at the entrance to which each burst is deflected by two plates which are fed in phase opposition at a frequency of 7 MHz. (authors)

  14. 深圳市征收地拆迁自动评估信息系统的研制%RESEARCH AND DEVELOPMENT OF AUTOMATED VALUATION INFORMATION SYSTEM FOR LAND EXPROPRIATION AND HOUSES DISMANTLEMENT AND REMOVAL IN SHENZHEN CITY

    Institute of Scientific and Technical Information of China (English)

    耿继进; 唐琳; 李炜文; 刘颖; 张俊平

    2013-01-01

    The purpose of our study is to develop an automated valuation information system for the compensation of land expropriation and houses dismantlement and removal ( LHAVS) in Shenzhen City in order to improve the operation efficiency of compensation valuation in regard to dismantlement and removal and the quality of the corresponding results. The method used in our study is that taking the automated valuation model as the basis, employing computer technology to establish the overall framework of LHAVS for Shenzhen. The outcomes of our study are; making clear the background, targets and contents as well as the overall design concept of system in regard to the research and development of LHAVS for Shenzhen; realising the integration of system functions of valuation business in different types and the automatisation of valuation operation on the basis of uniform database and software platform. The conclusion gained is that the implementation of LHAVS provides a useful exploration in guaranteeing the objectivity, impartiality and rationality of valuation results for the compensation of urban land expropriation and house dismantlement and removal.%研究目的:开发深圳市征收地和房屋拆迁补偿自动评估信息系统,提高拆迁补偿评估工作效率和成果质量.研究方法:以自动评估模型为基础,应用计算机技术,建立深圳市征收地拆迁自动评估信息系统总体架构.研究结果:明确深圳市征收地拆迁自动评估信息系统研究和开发的背景、目标、内容及系统的总体设计思路,基于统一的数据库和软件平台,实现不同类型评估业务的系统功能集成和评估工作的自动化.研究结论:系统实现对保障城市征收地拆迁补偿评估结果的客观、公正和合理性提供了有益探索.

  15. Testing of an environmental compatible dismantling technology for activated metallic reactor components (water abrasive jetstream technic) under real conditions. Final report; Erprobung des Wasserabrasivsuspensionsstrahlverfahrens (WASS) bei der Zerlegung aktivierter metallischer Reaktorkomponenten (RDB u.a.) unter realen Bedingungen. Endbericht

    Energy Technology Data Exchange (ETDEWEB)

    Kalwa, H.; Louis, H.; Brandt, C. [Hannover Univ. (Germany). Inst. fuer Werkstoffkunde

    2000-07-01

    The water abrasive suspension jetstream cutting (WASJ) was tested during the past research program for its general practicability. The programs goal was to investigate the dismantling of the lower part of the core baffel as well as of the reactor-pressure-vessel itself. For this purpose the University of Hanover established a lab-scale testing program to optimize the following parameters: different abrasives, cutting performance, remote tools monitoring and handling, verification of the forces to the manipulators, adaptation of cutting parameters to the different cutting tasks and the analyses for water-processing to maintain sub-aquatic visibility. Based on the results obtained in minor-scale testing the process parameters were adapted to the pilot manifold (ALBA-WASS) in VAK. This program served also for the training of personnel and the certification of the procedure by experts and the authorities. During the pre-operational phase a solids extraction and water-purification device was developed to enable the use of the technique under sub-aquatic conditions. The core-baffel was dismantled with the 1400 bar WASS into parts ready for final storage. For the cutting of the reactor-pressure-vessel itself, the WASS was modified to a jetstream-pressure of 2000 bar. At the end of the operation we were able to determine that for the dismantling of nuclear-power-plants an additional efficient cutting technique is now available. (orig.) [German] Das Wasserabrasivsuspensionsstrahlschneiden war in vorangegangenen Forschungsvorhaben auf seine generelle Einsatzbarkeit untersucht worden. Die Aufgabenziele waren, die Zerlegung des Kernmantelunterteiles sowie die Zerlegung des Reaktordruckbehaelters. Zu diesem Zweck wurden mit der Laboranlage der Universitaet Hannover Untersuchungen verschiedener Abrasivmittel bezueglich Schneidfaehigkeit und Truebung, Versuche zur Optimierung der Werkzeugueberwachung und -handhabung, Ermittlung der Kraefte am Handhabungssystem, Anpassung der

  16. Proposal for the award of a contract for the design, supply, installation and commissioning of a ventilation and air conditioning system for the ECN3 experimental area and the TCC8 and GHN300 service tunnels and for the dismantling of the existing system

    CERN Document Server

    2014-01-01

    Proposal for the award of a contract for the design, supply, installation and commissioning of a ventilation and air conditioning system for the ECN3 experimental area and the TCC8 and GHN300 service tunnels and for the dismantling of the existing system

  17. Project Temporalities

    DEFF Research Database (Denmark)

    Tryggestad, Kjell; Justesen, Lise; Mouritsen, Jan

    2013-01-01

    into account. This may require investments in new project management technologies. Originality/value – This paper adds to the literatures on project temporalities and stakeholder theory by connecting them to the question of non-human stakeholders and to project management technologies.......Purpose – The purpose of this paper is to explore how animals can become stakeholders in interaction with project management technologies and what happens with project temporalities when new and surprising stakeholders become part of a project and a recognized matter of concern to be taken...... into account. Design/methodology/approach – The paper is based on a qualitative case study of a project in the building industry. The authors use actor-network theory (ANT) to analyze the emergence of animal stakeholders, stakes and temporalities. Findings – The study shows how project temporalities can...

  18. Intending Projects

    Institute of Scientific and Technical Information of China (English)

    2012-01-01

    Project name: New construction project of production,research & development base of hydraulic system Construction site: Qingpu Industrial Park Construction unit: Parker Hannifin Industrial Hydraulic Technology (Shanghai) Co., Ltd.

  19. Alzheimer's Project

    Medline Plus

    Full Text Available ... Momentum in Science, Part 2" (70 minutes) Be a part of something big. HBO's "THE ALZHEIMER'S PROJECT" ... vital research and services. "THE ALZHEIMER'S PROJECT" is a presentation of HBO Documentary Films and the National ...

  20. Alzheimer's Project

    Science.gov (United States)

    ... state Home > News & Events > Upcoming Events > HBO Alzheimer’s Project In the News Walk to End Alzheimer's Upcoming ... Disease Awareness Month World Alzheimer's Month HBO Alzheimer’s Project MAKE A DONATION Your gift will help us ...

  1. Virtual projects

    DEFF Research Database (Denmark)

    Svejvig, Per; Commisso, Trine Hald

    2012-01-01

    Virtual projects are common with global competition, market development, and not least the financial crisis forcing organizations to reduce their costs drastically. Organizations therefore have to place high importance on ways to carry out virtual projects and consider appropriate practices...... that the best practice knowledge has not permeated sufficiently to the practice. Furthermore, the appropriate application of information and communication technology (ICT) remains a big challenge, and finally project managers are not sufficiently trained in organizing and conducting virtual projects...

  2. Project Management

    OpenAIRE

    Lörinc, Jan

    2012-01-01

    This work deals with the problems in the process of project management in enterprises. It examines the precise approaches, the possibility of standardizingthe approach to project team management and motivation of its members and their role in the process of project management. He confronts the views and attitudes of selected authors. The theoretical conclusions of findings compares with knowledgeacquired from research carried out on project management in a selected company.Evaluates managemen...

  3. Project ethics

    CERN Document Server

    Jonasson, Haukur Ingi

    2013-01-01

    How relevant is ethics to project management? The book - which aims to demystify the field of ethics for project managers and managers in general - takes both a critical and a practical look at project management in terms of success criteria, and ethical opportunities and risks. The goal is to help the reader to use ethical theory to further identify opportunities and risks within their projects and thereby to advance more directly along the path of mature and sustainable managerial practice.

  4. The TN Gemini: a packing for the transport of wastes coming from the dismantling of nuclear facilities; Le TN Gemini: un emballage de transport pour les dechets technologiques issus de la deconstruction des installations nucleaires

    Energy Technology Data Exchange (ETDEWEB)

    Vuong, J. [TN International, Groupe Areva, Tour Areva, Paris La Defense (France)

    2011-11-15

    The TN Gemini package has been designed by 'TN International' and has been agreed since 1997 as a type-B package with great capacity, its useful dimensions are 4.51 m * 1.84 m * 2.00 m (L*l*h). Its big size enables the TN Gemini package to transport large components with no need to cut them like glove boxes or large parts of contaminated metallic components coming from the dismantling of nuclear facilities. Its great resistance to fire is an asset for transporting wastes releasing inflammable gases. This package has been used intensively in U.K. for the retrieval of PCO (plutonium contaminated objects) from the waste repository of Drigg. (A.C.)

  5. Concentration and health risk assessment of PCBs in E-waste dismantling field%电子废弃物拆解场多氯联苯含量及健康风险评价

    Institute of Scientific and Technical Information of China (English)

    杨彦; 于云江; 李定龙; 杨洁; 陆晓松

    2012-01-01

    选择我国典型的电子废弃物拆解场为研究对象,以拆解场各环境介质中PCBs浓度全面调查为基础,采用美国环境保护署(US EPA)人体健康评价模型,结合问卷调查和实际测量修正暴露参数,对浙江台州拆解区人群(成人)进行健康风险评价.结果表明:拆解场大气和土壤中PCBs各同系物的浓度显著高于其他介质,经调查表明可能与拆解场直接焚烧、湿法酸洗工艺有关.多种暴露途径所导致拆解场成人PCBs污染总致癌风险为2.80×10 3,总非致癌风险为1.64×10 3,均超过了US EPA、ICRP等推荐的可接受的风险水平,其中经口暴露的致癌、非致癌风险最大,其次是呼吸暴露.进行敏感性分析表明:无论何种暴露途径,体重(BW)、呼吸速率(IR)、实测参数食物摄食(IR)、皮肤接触表面积(SA)和污染物实测浓度的致癌风险、非致癌风险绝对敏感性都较大.在健康风险评价时,需要对研究区人群暴露参数进行实地调查实测,以降低评价结果的不确定性.%The typical E-waste dismantling field was investigated. Based on the comprehensive survey of the concentration of PCBs of multiple environmental media, the health risk of adults in dismantling field of Taizhou in Zhejiang was assessed by the health assessment models of US EPA and the exposure parameters optimized by questionnaires and actual measurement. It was preliminarily concluded that the concentration of PCBs homolog in dismantling field of multiple environmental media in atmosphere and soil were significantly higher than those in other media, which might be related to the direct burning and wet pickling process. The adults' total cancer risk of PCBs pollution from various of exposure pathways in dismantling field was 2.80×10-3, whereas the total non-cancer risk was 1.64× 10-3, which both exceeded the maximum acceptable risk levels recommended by US EPA, ICRP, ect. The cancer and non-cancer risk of the oral exposure were

  6. Define Project

    DEFF Research Database (Denmark)

    Munk-Madsen, Andreas

    2005-01-01

    "Project" is a key concept in IS management. The word is frequently used in textbooks and standards. Yet we seldom find a precise definition of the concept. This paper discusses how to define the concept of a project. The proposed definition covers both heavily formalized projects and informally ...

  7. International Projects

    CERN Document Server

    2002-01-01

    Description of co-operation projects implemented with the help of Sweden is presented. Information on performance of Phare and IAEA Regional and National Technical Cooperation projects is provided. Phare project 'Creation of Radiation Protection Infrastructure and Development of Supporting Services' was started in 2002

  8. Map Projection

    CERN Document Server

    Ghaderpour, Ebrahim

    2014-01-01

    In this paper, we introduce some known map projections from a model of the Earth to a flat sheet of paper or map and derive the plotting equations for these projections. The first fundamental form and the Gaussian fundamental quantities are defined and applied to obtain the plotting equations and distortions in length, shape and size for some of these map projections.

  9. Study on Pollutant Discharge Situation of Heavy Metal and Organic Halide in a Typical Solid Waste Dismantling Area%典型固废拆解区重金属和有机卤代污染物排放状况调查研究

    Institute of Scientific and Technical Information of China (English)

    李文洁; 吴建; 郑景敏; 周炯

    2016-01-01

    以浙江省台州市路桥区为例,通过实地监测典型固废拆解企业的污染物排放浓度,并利用问卷调查开展类比分析,对固废拆解行业的污染物排放总量进行了测算,完成了固废拆解行业污染物排放状况评估。结果表明,拆解行业的重金属污染物主要集中在废渣中,有机污染物以废水排放为主。同时,拆解行业的Pb、Hg污染物形成了局部集中排放。研究结论为固废拆解行业的污染防治措施制定提供了重要参考。%By monitoring the pollutant concentrations dischargedby typical solid waste dismantling enterprises , and using the questionnaire data to conduct analogy analysis, the total pollutants discharged by solid waste dismantling industry were estimated , and the assessment of pollutant discharge situation of solid waste dismantling industry was accomplished using Luqiao District as an example.It was found that heavy metal pollutants were concentrated in waste residue , while organic halide pollutants were mainly discharged through waste water.Also, Pb and Hg pollutants from dismantling industry were causing a local concentrative discharge. The results provide an important reference to the development of pollution prevention measures for solid waste dismantling industry .

  10. 废弃电器电子产品拆解信息管理系统研究%Research on Dismantling Information Management System of Waste Electrical and Electronic Products

    Institute of Scientific and Technical Information of China (English)

    邓梅玲; 赵新; 周超群; 胡嘉琦; 周斌; 杜彬; 曹诺

    2014-01-01

    Based on needs of waste electrical and electronic product dismantling information management industry and the supervision requirements of local government administrative departments, the waste electrical and electronic products dismantling information management system was researched and developed. The system was designed for the company's existing production process, and was divided into seven major functional modules, including foreground data acquisition and background data management section. The development tools used were Sybase PowerBuilder 9.0 and Microsoft Visual Studio 2010, while modeling tools used were PowerDesigner 9.0 and database SQL Server 2000. This system has been proven through enterprise applications that it can effectively improve the level of information management and the productivity of the enterprises, which can also provide effective oversight tool for competent authorities.%基于废弃电器电子产品拆解信息管理及政府管理部门监管的需求,研究并开发废弃电器电子产品拆解信息管理系统。系统针对企业现有生产工艺流程设计,分为7大功能模块,包括前台数据采集部分和后台数据管理部分。使用的开发工具有Sybase PowerBuilder 9.0, Microsoft Visual Studio 2010,建模工具有PowerDesigner 9.0,数据库SQL Server 2000。系统经过企业应用证明,能有效提高企业的信息化管理水平和生产效率,为主管部门提供有效监督工具。

  11. Project of law, adopted by the Senate, giving permission to the approval of the agreement between the French government and the international organization for thermonuclear fusion energy ITER, relative to the head office of ITER organization and to the privileges and immunities of ITER organization in the French territory

    International Nuclear Information System (INIS)

    The will of building up an international thermonuclear experimental reactor (ITER) gathers since several years the European community of atomic energy (Euratom), Japan, the USA, and Russia, next followed by China, South Korea and, since 2005, by India. The agreement signed in Paris between these seven parties on November 21, 2006 entrusted the international organization ITER with the realization of this project. The implications of the ITER project are enormous both in their scientific and in their economical aspects. France has a particular position in this project since the head office of ITER organisation is sited at Saint-Paul-lez-Durance and the tokamak will be built at Cadarache. Therefore, an agreement has been signed between ITER organization and the French government. The approval of this agreement is the object of this project of law made of a single article. The agreement between the French government and the international organization ITER is attached to the document. It defines the juridical status, the privileges and immunities of the organization itself and of its personnel inside the French territory. An appendix to the agreement precises the cooperation modalities between the French authorities and ITER organization. (J.S.)

  12. Alzheimer's Project

    Medline Plus

    Full Text Available ... voluntary health organization in Alzheimer's care, support and research, the Alzheimer's Association has been an active partner in "THE ALZHEIMER'S PROJECT," ... (48 minutes) "Momentum ...

  13. 孔圣枕中丹拆方抗小鼠抑郁作用的实验研究%Prescription Dismantlement Study of the Antidepressant Effect of Kong Sheng Zhen Zhong Dan on Mice

    Institute of Scientific and Technical Information of China (English)

    邓威; 刘育栋; 刘梦玲; 吴海莎; 叶敬; 滕敏昌

    2015-01-01

    Objective:To study the antidepressant effect of Kong Sheng Zhen Zhong Dan prescription dismantlement on mice model and to provide theoretical basis for clinical prevention and treatment of depression with Chinese medicine. Methods:130 KM mice were classified into 13 groups,namely,the normal group,depression model group,fluoxetine group and 10 Kong Sheng Zhen Zhong Dan prescription dismantlement groups.The mice were treated with normal saline, fluoxetine or Kong Sheng Zhen Zhong Dan prescription dismantlement by intragastric administration,sustained for 3 weeks.After the last treatment,the mice were tested by forced swimming and tail suspension,which continued 6 mins, and the mice motionless time in the last 4 min was recorded.Results:Compared with normal group,model group mice showed increases in the forced swimming (P0.05).In the forced swimming test,the stationary time of the second (polygala,tortoise plastron),third (polygala,calamus),forth (calamus,tortoise plastron),fifth (polygala, keel,calamus),eighth (polygala,keel,calamus)and ninth (keel,calamus)groups of Kong Sheng Zhen Zhong Dan prescription dismantlement mice was reduced compared with the model group.The differences were significantly (P<0.01).Conclusion:The second,forth,and eighth group of Kong Sheng Zhen Zhong Dan prescription dismantlement have obvious effects on depression in mice.%目的:比较孔圣枕中丹拆方对小鼠抑郁病理模型的疗效,为中药临床防治抑郁症提供理论依据。方法:取130只昆明种小鼠归类分为13组,即正常组、抑郁模型组、氟西汀组及孔圣枕中丹拆方10组。各组连续灌胃给药3周。末次给药后进行强迫游泳实验及悬尾实验,分别记录6 min,测定并比较后4 min内强迫游泳不动时间及悬尾不动时间。结果:模型组小鼠与正常组相比,强迫游泳(P<0.05)和悬尾静止不动时间(P <0.05)均升高。悬尾试验中,孔圣枕中丹2组(远志、龟板)、4

  14. Alzheimer's Project

    Medline Plus

    Full Text Available ... state Home > News & Events > Upcoming Events > HBO Alzheimer’s Project In the News Walk to End Alzheimer's Upcoming ... Disease Awareness Month World Alzheimer's Month HBO Alzheimer’s Project MAKE A DONATION Your gift will help us ...

  15. Advancing Implementation of Decommissioning and Environmental Remediation Programmes. CIDER Project: Baseline Report

    International Nuclear Information System (INIS)

    Despite significant progress having been achieved in recent years, much remains to be done in terms of addressing the legacies from the early development of nuclear energy, including the dismantling of redundant research and fuel cycle facilities, research reactors and power plants, and the remediation of sites affected by past uranium mining and processing operations. Some countries are moving forward with dealing with these legacies, and accordingly have built up appropriate technical resources and expertise, but many national programmes still face very significant challenges. This publication discusses the barriers that prevent the implementation of decommissioning and environmental remediation (D&ER) projects and provides potential solutions to overcome the identified barriers and thereby facilitates a better implementation of D&ER programmes

  16. 不同电子废弃物拆解场重金属经口暴露的健康风险研究%Health risk of heavy metals through oral exposure in different e-waste dismantling plants

    Institute of Scientific and Technical Information of China (English)

    杨彦; 于云江; 李定龙; 杨洁

    2012-01-01

    E-waste dismantling plants were surveyed in Taizhou, Zhejiang Province. The pollution in different dismantling plants (a burning plant, a manual dissembling plant and a pickling plant) caused by copper, lead and cadmium and other four kinds of metals were investigated with field survey and laboratory analysis. The health human exposure risk through oral ingestions in different dismantling plants was evaluated with US EPA models. In addition, the exposure parameters were optimized by questionnaires and actual measurement. Results obtained showed that oral exposure levels in the threedismantling plant exceeded the acceptable levels recommended by international organization, with the highest carcinogenic risk of human exposure in the manual dissembling plant and the highest non-carcinogenic risk of human exposure in the burning plant. In terms of the exposure way, the carcinogenic risk caused by food intake was the highest, while the non-carcinogenic risk caused by drinking groundwater was the highest. In terms of the elements, the carcinogenic risk caused by arsenic was the highest, while the non-cancer risk by chromium was the highest. Sensitivity analysis result illustrated that the measured parameters of body weight (BW) showed a negative sensitivity to health risk, which accounted for about 14%-15% , and the concentration of pollutants (C) , intake rate (IRW ,IRF ,IRS) exhibited a positive sensitivity, which accounted for 15%-16% and 15% , respectively.%以浙江台州电子废弃物拆解区为研究区域,采用现场调查和实验室分析相结合的方法对不同拆解场(焚烧场、手工拆解场、酸洗场)各环境介质中Cu、Pb、Cd等共7种重金属的污染状况进行调查,运用美国环保局健康风险评价模型对不同场地的人群经口暴露的健康风险进行评估,并通过调查问卷、实测等方式优化了暴露参数.研究结果表明:3个拆解场经口暴露的风险度均超过国际

  17. 废弃印刷电路板回收拆解过程中的气体排放物分析∗%Analysis on gas emissions in the process of recycling and dismantling wasted PCBs

    Institute of Scientific and Technical Information of China (English)

    王玉琳; 齐森; 胡海娟; 刘光复; 符永高

    2015-01-01

    In order to determine the emission components in the process of heating and dismantling wasted printed circuit boards(PCBs), with the aid of self⁃designed PCB dismantling device, the discharged gases were collected and analyzed by means of fourier transform infrared spectroscopy ( FTIRS ) , gas chromatography⁃mass spectroscopy ( GC/MS ) , ion chromatography ( IC ) and inductively coupled plasma mass spectroscopy(ICP⁃MS). The results showed that the wasted PCBs produced phenol, 2,6⁃dibromophenol and other kinds of organic compounds following the breaking of O—C, C—C, C—Br bonds in brominated epoxy resins when being heated, and also released a large number of acid gases containing chemical elements such as S, N, Cl and Br. Moreover, heavy metals such as Sn, Pb, Sb, Hg, Cd and Cr escaped from PCBs and melting solder in the continuous tin fusion process.%为研究废弃印刷电路板( PCB)在回收加热拆解电子元件过程中所产生的气体排放物的主要成分,使用自行设计的废弃 PCB 拆解装置进行拆解实验,采用傅里叶红外光谱( FTIRS)、气相色谱⁃质谱( GC/MS)、离子色谱( IC)和电感耦合等离子体质谱( ICP⁃MS)等分析方法,对实验过程所收集到的气体产物进行成分分析。结果表明,废弃 PCB 的基板在加热过程中发生了初步分解,基板上的溴化环氧树脂发生了 O—C、C—C、C—Br键的断裂,产生了苯酚、2,6⁃二溴苯酚等有机物;伴随有机气体逸出的还有废弃PCB在加热过程所释放的含有大量 S、N、Cl、Br 等元素的无机酸性气体;而连续的熔锡过程还使得 PCB 与焊料中的 Sn、Pb、Sb、Hg、Cd、Cr 等重金属产生烟尘逸出。

  18. Freedom Project

    Directory of Open Access Journals (Sweden)

    Alejandra Suarez

    2014-02-01

    Full Text Available Freedom Project trains prisoners in nonviolent communication and meditation. Two complementary studies of its effects are reported in this article. The first study is correlational; we found decreased recidivism rates among prisoners trained by Freedom Project compared with recidivism rates in Washington state. The second study compared trained prisoners with a matched-pair control group and found improvement in self-reported anger, self-compassion, and certain forms of mindfulness among the trained group. Ratings of role-plays simulating difficult interactions show increased social skills among the group trained by Freedom Project than in the matched controls.

  19. TIARA project

    Science.gov (United States)

    Malecki, P.

    2013-10-01

    The aim of the Test Infrastructure and Accelerator Research Area - the TIARA project[1] is to consolidate and support the European R&D program in the field of physics and techniques of particle accelerators. This project, partially funded by the European Commission, groups 11 participants from 8 European countries, including Poland. Its present, threeyear (2011-2013) preparatory phase (PP) is shortly described in this paper. The project is divided into 9 work packages (WP). We will concentrate on four of them dedicated to governance, R&D infrastructures, joint R&D programming, and education and training, in which Polish participants are actively involved.

  20. Best practices for preparing vessel internals segmentation projects

    International Nuclear Information System (INIS)

    Westinghouse has been involved in reactor internals segmentation activities in the U.S. and Europe for 30 years. Westinghouse completed in 2015 the segmentation of the reactor vessel and reactor vessel internals at the Jose Cabrera nuclear power plant in Spain and a similar project is on-going at Chooz A in France. For all reactor dismantling projects, it is essential that all activities are thoroughly planned and discussed up-front together with the customer. Detailed planning is crucial for achieving a successful project. One key activity in the preparation phase is the 'Segmentation and Packaging Plan' that documents the sequential steps required to segment, separate, and package each individual component, based on an activation analysis and component characterization study. Detailed procedures and specialized rigging equipment have to be developed to provide safeguards for preventing certain identified risks. The preparatory work can include some plant civil structure modifications for making the segmentation work easier and safer. Some original plant equipment is sometimes not suitable enough and need to be replaced. Before going to the site, testing and qualification are performed on full scale mock-ups in a specially designed pool for segmentation purposes. The mockup testing is an important step in order to verify the function of the equipment and minimize risk on site. This paper is describing the typical activities needed for preparing the reactor internals segmentation activities using under water mechanical cutting techniques. It provides experiences and lessons learned that Westinghouse has collected from its recent projects and that will be applied for the new awarded projects. (authors)

  1. Decree from August 27, 1996 authorizing Electricite de France to modify in order to keep under surveillance and in an intermediate dismantling state the basic nuclear installation named Chinon A 3 (reactor definitely decommissioned) on the Chinon nuclear site of the Avoine town (Indre-et-Loire)

    International Nuclear Information System (INIS)

    This decree from the French prime minister, the minister of environment and the minister of industry and postal services gives permission to Electricite de France (EdF) to modify and keep under surveillance the partially dismantled Chinon A 3 reactor which will be renamed Chinon A 3D. The modification consist in confining the internal structures and heat exchangers inside their buildings with the plugging of all apertures. Primary and auxiliary circuits will be dismantled. The decree describes the installation and summarizes the technical rules which must be applied concerning the works schedule, the quality assurance, the confinement and protection against risks of radioactivity dissemination, the personnel and public protection against ionizing radiations, the control of environmental pollution with liquid and gaseous effluents, the reduction of volume and radioactivity of solid wastes, the transport and handling of radioactive materials, the protection against earthquakes and fire, and the personnel training. (J.S.)

  2. Report made on behalf of the commission of foreign affairs about the project of law, adopted by the Senate, giving permission to the approval of the agreement between the French government and the international organization for thermonuclear fusion energy ITER, relative to the head office of ITER organization and to the privileges and immunities of ITER organization in the French territory; Rapport fait au nom de la commission des affaires etrangeres sur le projet de loi, adopte par le senat, autorisant l'approbation de l'accord entre le Gouvernement de la Republique francaise et l'Organisation internationale ITER pour l'energie de fusion relatif au siege de l'Organisation ITER et aux privileges et immunites de l'Organisation ITER sur le territoire francais

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2008-02-15

    The will of building up an international thermonuclear experimental reactor (ITER) gathers since several years the European community of atomic energy (Euratom), Japan, the USA, and Russia, next followed by China, South Korea and, since 2005, by India. The agreement signed in Paris between these seven parties on November 21, 2006 entrusted the international organization ITER with the realization of this project. The implications of the ITER project are enormous both in their scientific and in their economical aspects. France has a particular position in this project since the head office of ITER organisation is sited at Saint-Paul-lez-Durance and the tokamak will be built at Cadarache. Therefore, an agreement has been signed between ITER organization and the French government. The approval of this agreement is the object of this project of law. The document presents first the principle, challenge and stakes of the ITER project and the long negotiations that have led to chose France for the setting up of the research facility. Then, it presents the agreement of November 7, 2007, which fixes the general framework of the conditions necessary to the achievement of the project. The agreement comprises the classical rules, privileges and immunities of any international organization sited on the French ground, plus some more specific dispositions in particular in the domain of management of the wastes generated by the facility. (J.S.)

  3. Alzheimer's Project

    Medline Plus

    Full Text Available ... Alzheimer's Gala A Night at Sardi's Alzheimer's Disease Awareness Month World Alzheimer's Month HBO Alzheimer’s ... HBO's "THE ALZHEIMER'S PROJECT" takes a look at the faces behind the disease - and the forces leading us ...

  4. Alzheimer's Project

    Medline Plus

    Full Text Available ... about the films on our message board . Watch films free online now "The Memory Loss Tapes" (85 ... ALZHEIMER'S PROJECT" is a presentation of HBO Documentary Films and the National Institute on Aging at the ...

  5. Alzheimer's Project

    Medline Plus

    Full Text Available ... disease has on those with Alzheimer's and their families. September 14, 2009 "The Alzheimer's Project" wins two ... way Americans thinks about Alzheimer's disease. Tell your family and friends. Post info on your Web site . ...

  6. Alzheimer's Project

    Medline Plus

    Full Text Available ... 272.3900 Find your chapter: search by state Home > News & Events > Upcoming Events > HBO Alzheimer’s Project In the News Walk to End Alzheimer's Upcoming Events AAIC Advocacy Forum Rita ...

  7. Project Reptile!

    Science.gov (United States)

    Diffily, Deborah

    2001-01-01

    Integrating curriculum is important in helping children make connections within and among areas. Presents a class project for kindergarten children which came out of the students' interests and desire to build a reptile exhibit. (ASK)

  8. Alzheimer's Project

    Medline Plus

    Full Text Available ... your family and friends. Post info on your Web site . Become an Alzheimer's champion. Help support vital research and services. "THE ALZHEIMER'S PROJECT" is a presentation of HBO ...

  9. Alzheimer's Project

    Medline Plus

    Full Text Available ... our nation and drive concerned citizens to take action. Here are three ways you can help us change the way ... vital research and services. "THE ALZHEIMER'S PROJECT" is a presentation ...

  10. Alzheimer's Project

    Medline Plus

    Full Text Available ... and the effects this debilitating and fatal disease has on those with Alzheimer's and their families. September ... Alzheimer's care, support and research, the Alzheimer's Association has been an active partner in "THE ALZHEIMER'S PROJECT," ...

  11. Intending Projects

    Institute of Scientific and Technical Information of China (English)

    2012-01-01

    Project name:Jintan tire production base project (the first-phase project) Construction site:Jintan Economic Development Zone, Jiangsu Province Construction unit:Zhongce Rubber (Jintan) Co., Ltd. Total investment:RMB 2.42 billion yuan Project description:It is planned to cover an area of 3,000 mu. In the first phase, it will cover an area of 520.43 mu with designed staff of 4,500 people. It will mix 150,000 tons of rubber and produce 10 million u- nits of high-performance semi-steel-wire saloon car and light truck radial tires, 500,000 units of OTR tires and 100,000 tons of carbon black per year.

  12. Alzheimer's Project

    Medline Plus

    Full Text Available ... 14, 2009 "The Alzheimer's Project" wins two Creative Arts Emmys Two installments of the multi-part HBO ... from the Alzheimer's Association and others, won Creative Arts Emmy awards. "The Memory Loss Tapes" was honored ...

  13. Radiochemistry Project

    International Nuclear Information System (INIS)

    Researches carried out in the 'Radiochemistry Project' of the Agricultural Nuclear Energy Center, Piracicaba, Sao Paulo State, Brazil, are described. Such researches comprise: dosimetry and radiological protection; development of techniques and methods of chemical analysis and radiochemistry. (M.A.)

  14. Project Management

    DEFF Research Database (Denmark)

    Kampf, Constance

    2009-01-01

    In this video Associate Professor Constance Kampf talks about the importance project management. Not only as a tool in implementation, but also as a way of thinking, and as something that needs to be considered from idea conception......In this video Associate Professor Constance Kampf talks about the importance project management. Not only as a tool in implementation, but also as a way of thinking, and as something that needs to be considered from idea conception...

  15. What are become Moruroa and Fangataufa? The dismantling of tests sites did not happen; Que sont devenus Moruroa et Fangataufa? le demantelement des sites d'essais n'a pas eu lieu

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2005-07-01

    Officially, the nuclear test sites of French polynesia have been dismantled. It would be more correct to say that the installations build on the Moruroa atolls have been destroyed. From the end of nuclear tests, the Cea constructions and installations, the most susceptible to be contaminated have been ruined without exterior witness. Nobody knows if the usual procedures of decontamination have been observed. About 15% of materials from he Moruroa base have been distributed as gifts to the local communities in french Polynesia. other materials have been transferred or sold. The observatory of French nuclear weapons estimates the cost of the closing of the French Polynesia test sites to about 15 milliards of Francs, including the compensations paid to the Polynesian government during 10 yeas, so be it hundred times the cost announced by the militaries in 1998. The observatory of French nuclear weapons estimates that the real assessment of radioactive waste being on Moruroa and Fangataufa atolls has not been completely made by the experts of IAEA. This assessment is still to make. The observatory of French nuclear weapons notices that the Moruroa and Fangataufa atolls stay under military status. It recommends that these atolls be reintegrated to the Polynesian land patrimony in order to allow independent expertise. (N.C.)

  16. Project of law, adopted by the Senate, giving permission to the approval of the agreement between the French government and the international organization for thermonuclear fusion energy ITER, relative to the head office of ITER organization and to the privileges and immunities of ITER organization in the French territory; Projet de loi adopte par le Senat, autorisant l'approbation de l'accord entre le Gouvernement de la Republique francaise et l'Organisation internationale ITER pour l'energie de fusion relatif au siege de l'Organisation ITER et aux privileges et immunites de l'Organisation ITER sur le territoire francais

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2008-01-15

    The will of building up an international thermonuclear experimental reactor (ITER) gathers since several years the European community of atomic energy (Euratom), Japan, the USA, and Russia, next followed by China, South Korea and, since 2005, by India. The agreement signed in Paris between these seven parties on November 21, 2006 entrusted the international organization ITER with the realization of this project. The implications of the ITER project are enormous both in their scientific and in their economical aspects. France has a particular position in this project since the head office of ITER organisation is sited at Saint-Paul-lez-Durance and the tokamak will be built at Cadarache. Therefore, an agreement has been signed between ITER organization and the French government. The approval of this agreement is the object of this project of law made of a single article. The agreement between the French government and the international organization ITER is attached to the document. It defines the juridical status, the privileges and immunities of the organization itself and of its personnel inside the French territory. An appendix to the agreement precises the cooperation modalities between the French authorities and ITER organization. (J.S.)

  17. Project Reconstruct.

    Science.gov (United States)

    Helisek, Harriet; Pratt, Donald

    1994-01-01

    Presents a project in which students monitor their use of trash, input and analyze information via a database and computerized graphs, and "reconstruct" extinct or endangered animals from recyclable materials. The activity was done with second-grade students over a period of three to four weeks. (PR)

  18. Alzheimer's Project

    Medline Plus

    Full Text Available ... 2" (70 minutes) Be a part of something big. HBO's "THE ALZHEIMER'S PROJECT" will expose the Alzheimer's ... show(); jQuery('#TRByZip').html(teamRaisersListHTML); teamRaisersListHTML = ''; } } else { if (data && data.getTeamraisersResponse) { var teamraisers = luminateExtend.utils.ensureArray(data. ...

  19. Project Narrative

    Energy Technology Data Exchange (ETDEWEB)

    Driscoll, Mary C. [St. Bonaventure University, St Bonaventure, NY(United States)

    2012-07-12

    The Project Narrative describes how the funds from the DOE grant were used to purchase equipment for the biology, chemistry, physics and mathematics departments. The Narrative also describes how the equipment is being used. There is also a list of the positive outcomes as a result of having the equipment that was purchased with the DOE grant.

  20. Project Avatar

    DEFF Research Database (Denmark)

    Juhlin, Jonas Alastair

    'Project Avatar' tager udgangspunkt i den efterretningsdisciplin, der kaldes Open Source Intelligence og indebærer al den information, som ligger frit tilgængeligt i åbne kilder. Med udbredelsen af sociale medier åbners der op for helt nye typer af informationskilder. Spørgsmålet er; hvor nyttig er...

  1. Project Baltia

    Index Scriptorium Estoniae

    2007-01-01

    Uus arhitektuuriajakiri "Project Baltia" tutvustab Baltimaade, Soome ja Peterburi regiooni arhitektuuri, linnaehitust ja disaini. Ilmub neli korda aastas inglise- ja venekeelsena. Väljaandja: kirjastus Balticum Peterburis koostöös Amsterdami ja Moskva kirjastusega A-Fond. Peatoimetaja Vladimir Frolov

  2. Alzheimer's Project

    Medline Plus

    Full Text Available ... Chicago National Alzheimer's Gala A Night at Sardi's Alzheimer's Disease Awareness Month World Alzheimer's Month HBO Alzheimer’s Project ... help us change the way Americans thinks about Alzheimer's disease. Tell your family and friends. Post info on ...

  3. Alzheimer's Project

    Medline Plus

    Full Text Available ... Alzheimer's Gala A Night at Sardi's Alzheimer's Disease Awareness Month World Alzheimer's Month HBO Alzheimer’s Project MAKE ... for kids Learn how Maria Shriver is raising awareness '; jQuery('#luminateApi').hide(); jQuery('#otherLinks').show(); jQuery('#TRByZip'). ...

  4. Projective geometry and projective metrics

    CERN Document Server

    Busemann, Herbert

    2005-01-01

    The basic results and methods of projective and non-Euclidean geometry are indispensable for the geometer, and this book--different in content, methods, and point of view from traditional texts--attempts to emphasize that fact. Results of special theorems are discussed in detail only when they are needed to develop a feeling for the subject or when they illustrate a general method. On the other hand, an unusual amount of space is devoted to the discussion of the fundamental concepts of distance, motion, area, and perpendicularity.Topics include the projective plane, polarities and conic sectio

  5. Study on Sustainable Development of Resettlement in Urbanization Process——A Case Study on the ADB-Funded Nanning Qingxiu Mountain Ecological Protection Project

    Institute of Scientific and Technical Information of China (English)

    2011-01-01

    Based on derivation of permanent income hypothesis(PIH),the conflict is analyzed between expected profitability of migrants and government policy in resettlement project.Government has provided compensation for relevant building and land losses,but farmers are still unwilling to dismantle and move.On the contrary,it results in more serious social problems.The implementation and effect of resettlement policy is analyzed with ADB-funded Nanning Qingxiu Mountain Resettlement Project as an example.Finally,following suggestions are put forward for promoting sustainable development of resettlement:change ideas of resettlement to promote establishment of civil rights protection ideas;carry out early survey to protect rights and interests of owners and migrants;communicate with migrants to ensure their smooth appeal channel;and enhance coordination work with government department to ensure smooth completion of resettlement.

  6. Radiological and chemical completion report for overhead piping removal for the Weldon Spring Site Remedial Action Project, Weldon Spring, Missouri

    International Nuclear Information System (INIS)

    Demolition of overhead piping and supports at the Weldon Spring Chemical Plant was undertaken as an interim response action (IRA) within the Weldon Spring Site Remedial Action Project. IRAs are designed to ensure the health and safety of on-site personnel and minimize or preclude off-site releases of contamination. Prior to dismantlement a radiological survey and release plan was developed. Any radiologically contaminated material which exceeded release criteria was retained on site, along with all asbestos-containing insulation. Uncontaminated piping and supports were released from the site for salvage. This report summarizes the methods used to survey and release piping and supports and the amount of material released. 5 refs., 2 figs., 4 tabs

  7. Report on the behalf of the inquiry commission related to past, present and future costs of the nuclear sector, to the reactor exploitation duration, and to various economic and financial aspects of production and commercialization of nuclear electricity within the frame of the French and European electric mix, as well as to the consequences of the shutting down and dismantling of nuclear reactors, notably the Fessenheim power plant - Nr 2007

    International Nuclear Information System (INIS)

    This official report first describes the role of nuclear energy in the European electric system: economic context (pricing mode, interconnection leading to a European price), similar situations and different policies in Germany, Belgium and UK. It proposes the contribution of the inquiry commission: a constrained energy transition, a shared diagnosis on the status of the European electric system but two possible solutions, nuclear as an economy on its own requiring a strong commitment of public authorities. The next part addresses the front end of the nuclear cycle, i.e. how to ensure the supply of the French nuclear fleet (world resources, demand-supply balance, weak relationship between uranium price and nuclear electricity price). The inquiry commission outlines and discusses the roles of AREVA for the front end, EDF which tries to be less vulnerable, and the State (EDF's regulator and Areva's support). The third part addresses the maintenance and subcontracting expenses: maintenance as a major challenge to control costs, subcontracting as a choice of industrial policy. The inquiry commission notices that EDF has not yet reached a full control of maintenance and that subcontracting remains a matter of controversy. The fourth part discusses the fleet evolution: entry in the fourth decade, a life extension project which requires safety improvement. The inquiry commission discusses the numerous uncertainties of the industrial project, outlines that the construction of a new fleet requires huge investments, that the future of the nuclear fleet requires a global approach, and that shutting down nuclear plants requires support. The fifth part discusses the correct assessment of the amount of future expenses and how to secure their funding: the main future expenses are those related to installation dismantling and to nuclear wastes. The inquiry commission outlines the uncertainties about this funding. The sixth chapter addresses reprocessing activities, MOX fuel and

  8. Hydropower Projects

    Energy Technology Data Exchange (ETDEWEB)

    None

    2015-04-02

    The Water Power Program helps industry harness this renewable, emissions-free resource to generate environmentally sustainable and cost-effective electricity. Through support for public, private, and nonprofit efforts, the Water Power Program promotes the development, demonstration, and deployment of advanced hydropower devices and pumped storage hydropower applications. These technologies help capture energy stored by diversionary structures, increase the efficiency of hydroelectric generation, and use excess grid energy to replenish storage reserves for use during periods of peak electricity demand. In addition, the Water Power Program works to assess the potential extractable energy from domestic water resources to assist industry and government in planning for our nation’s energy future. From FY 2008 to FY 2014, DOE’s Water Power Program announced awards totaling approximately $62.5 million to 33 projects focused on hydropower. Table 1 provides a brief description of these projects.

  9. PARTNER Project

    CERN Multimedia

    Ballantine, A; Dixon-Altaber, H; Dosanjh, M; Kuchina, L

    2011-01-01

    Hadrontherapy uses particle beams to treat tumours located near critical organs and tumours that respond poorly to conventional radiation therapy. It has become evident that there is an emerging need for reinforcing research in hadrontherapy and it is essential to train professionals in this rapidly developing field. PARTNER is a 4-year Marie Curie Training project funded by the European Commission with 5.6 million Euros aimed at the creation of the next generation of experts. Ten academic institutes and research centres and two leading companies are participating in PARTNER, that is coordinated by CERN, forming a unique multidisciplinary and multinational European network. The project offers research and training opportunities to 25 young biologists, engineers, physicians and physicists and is allowing them to actively develop modern techniques for treating cancer in close collaboration with leading European Institutions. For this purpose PARTNER relies on cutting edge research and technology development, ef...

  10. Project Phaseolus

    International Nuclear Information System (INIS)

    Research carried out through the Phaseolus Project of the 'Centro de Energia Nuclear na Agricultura' (CENA) Piracicaba, Sao Paulo State, Brazil, is described. It comprises the following subject s: plant breeding; nitrogen fixation; tissue cultures; proteins; photosynthetic efficiency; soil-plant interactions; electron microscopy of the golden mosaic virus; pest control; production of 15N-enriched ammonium sulfate, and determination of elements in the beans plant. (M.A.)

  11. Teseus project

    OpenAIRE

    Petersen, Simone; Marsà, Quim; Chen, Kuan Wei; Arriaga, Lorena; Aleixendri, Joan Josep

    2015-01-01

    This project, TESEUS, is being carried out within the umbrella of the ongoing Urban Node study and focuses on the development of a computational system capable of handling a huge amount of data received from urban nodes in a smart city. There are already existing computer systems with computational power capable of handling the amount of data a smart city requires. Although these computers may provide all the power required to maintain and manage a smart city, they can always b...

  12. Projection Methods

    DEFF Research Database (Denmark)

    Wagner, Falko Jens; Poulsen, Mikael Zebbelin

    1999-01-01

    When trying to solve a DAE problem of high index with more traditional methods, it often causes instability in some of the variables, and finally leads to breakdown of convergence and integration of the solution. This is nicely shown in [ESF98, p. 152 ff.].This chapter will introduce projection...... methods as a way of handling these special problems. It is assumed that we have methods for solving normal ODE systems and index-1 systems....

  13. Nuevas construcciones y desmantelamientos de la memoria en tres documentales de cine autobiográfico argentino New constructions and forms to dismantle memory in three documentaries of autobiographical Argentinean cinema

    Directory of Open Access Journals (Sweden)

    María Laura Lattanzi

    2011-07-01

    Full Text Available En el presente trabajo nos proponemos explorar los procesos de construcción de memoria transgeneracional y familiar actuales, a partir del análisis de objetos artísticos determinados: tres documentales argentinos de los últimos diez años, de corte autobiográfico, dirigidos por hijos de detenidos desaparecidos. El actual despliegue del fenómeno autobiográfico implica -en las obras que nos interesan- nuevas formas de pensar el testimonio (propio y de los sobrevivientes, involucrando también lo cotidiano y lo familiar como lugares privilegiados en la reconstrucción y reconfiguración de identidades desgarradas. En esta línea afloran múltiples referencias a espacios íntimos, en lo que podríamos llamar una búsqueda de anclajes -espacios, imágenes, objetos, memorias-, pero hay también un énfasis en procesos de construcción y desmontaje de subjetividades, muchas veces marcados por la violencia y el desgarramiento.This article aims to explore how the familiar and trans-generational memory have been constructed from the analysis of selected art objects: three Argentinean autobiographical documentaries from the past ten years, directed by children of the desaparecidos. The current development of the autobiographical phenomenon involves -in the works of our interest- new ways of thinking testimony (their own and the survivors', which considers daily routines and familiar intimacy as privileged places in the reconstruction and reconfiguration of broken identities. Thus, multiple references to everyday places, and to familiar aspects emerge in the search of foothold -spaces, images, objects, and memories. However, there is also an accent in the process of constructing and dismantling subjectivities marked by violence and issure most of the times.

  14. SUPERSITE PROJECT

    Directory of Open Access Journals (Sweden)

    Silvia Ferrari

    2010-04-01

    Full Text Available The project is focused on a detailed study of some chemical, physical and toxicological parameters and on health, epidemiological and environmental assessment by interpretative models, in the atmosphere of Emilia-Romagna (Italy. The project rises from the necessity to improve  knowledge about environmental and health aspects of fine and ultrafine particles, in primary and secondary components, in the atmosphere. The project, structured in 7 workpackages, is organized in two measurement programmes: the routine one that has a mainly daily time resolution, and the intensive one with high time resolution and a higher chemical speciation than the routine one. The sampling sites are five: three in urban areas (Bologna, Parma and Rimini, one in a rural area (San Pietro Capofiume and one in a remote area (Monte Cimone. Parallel to outdoor studies, a workpackage  is planned for indoor studies and chemical composition analysis with the  outdoor/indoor ratio for characterizing indoor human exposure to outdoor pollution.

  15. Coloss project

    International Nuclear Information System (INIS)

    The COLOSS project was a shared-cost action, co-ordinated by IRSN within the Euratom Research Framework Programme 1998-2002. Started in February 2000, the project lasted three years. The work-programme performed by 19 partners was shaped around complementary activities aimed at improving severe accident codes. Unresolved risk-relevant issues regarding H2 production, melt generation and the source term were studied, through a large number of experiments such as a) dissolution of fresh and high burn-up UO2 and MOX by molten Zircaloy, b) simultaneous dissolution of UO2 and ZrO2 by molten Zircaloy, c) oxidation of U-O-Zr mixtures by steam, d) degradation-oxidation of B4C control rods. Significant results have been produced from separate-effects, semi-global and large-scale tests on COLOSS topics. Break-through were achieved on some issues. Nevertheless, more data are needed for consolidation of the modelling on burn-up effects on UO2 and MOX dissolution and on oxidation of U-O-Zr and B4C-metal mixtures. There was experimental evidence that the oxidation of these mixtures can contribute significantly to the large H2 production observed during the reflooding of degraded cores under severe accident conditions. Based on the experimental results obtained on the COLOSS topics, corresponding models were developed and were successfully implemented in several severe accident codes. Upgraded codes were then used for plant calculations to evaluate the consequences of new models on key severe accident sequences occurring in different plants designs involving B4C control rods (EPR, BWR, VVER- 1000) as well as in the TMI-2 accident. The large series of plant calculations involved sensitivity studies and code benchmarks. Main severe accident codes in use in the EU for safety studies were used such as ICARE/CATHARE, SCDAP/RELAP5, ASTEC, MELCOR and MAAP4. This activity enabled: a) the assessment of codes to calculate core degradation, b) the identification of main uncertainties and

  16. FLOAT Project

    DEFF Research Database (Denmark)

    Sørensen, Eigil V.; Aarup, Bendt

    The objective of the FLOAT project is to study the reliability of high-performance fibre-reinforced concrete, also known as Compact Reinforced Composite (CRC), for the floats of wave energy converters. In order to reach a commercial breakthrough, wave energy converters need to achieve a lower price...... of energy produced, comparable to prices currently obtained from offshore wind power, and this can be done by the use of more suitable materials. The flotation device is a key part of converters, as it accounts for a considerable share of initial investment, up to 27% depending on the converter. CRC floats...

  17. Project Lyman

    OpenAIRE

    McCandliss, Stephan R.; Kruk, Jeffrey W.; Blair, William P.; Kaiser, Mary Elizabeth; Feldman, Paul D.; Meurer, Gerhardt R.; Dixon, William V.; Sahnow, David J.; Neufeld, David A.; Lupu, Roxana E.; Fleming, Brian; Smee, Stephen A.; Andersson, B. G.; Moseley, Samuel H.; Kutyrev, Alexander S.

    2008-01-01

    We explore the design of a space mission, Project Lyman, which has the goal of quantifying the ionization history of the universe from the present epoch to a redshift of z ~ 3. Observations from WMAP and SDSS show that before a redshift of z >~ 6 the first collapsed objects, possibly dwarf galaxies, emitted Lyman continuum (LyC) radiation shortward of 912 A, reionizing most of the universe. How LyC escapes from galactic environments, whether it induces positive or negative feedback on the loc...

  18. Project Success in IT Project Management

    OpenAIRE

    Siddiqui, Farhan Ahmed

    2010-01-01

    The rate of failed and challenged Information Technology (IT) projects is too high according to the CHAOS Studies by the Standish Group and the literature on project management (Standish Group, 2008). The CHAOS Studies define project success as meeting the triple constraints of scope, time, and cost. The criteria for project success need to be agreed by all parties before the start of the project and constantly reviewed as the project progresses. Assessing critical success factors is another ...

  19. FLORAM project

    Energy Technology Data Exchange (ETDEWEB)

    Zulauf, W.E. [Sao Paolos Environmental Secretariat, Sao Paolo (Brazil); Goelho, A.S.R. [Riocell, S.A. (Brazil); Saber, A. [IEA-Instituto de Estudos Avancados (Brazil)] [and others

    1995-12-31

    The project FLORAM was formulated at the `Institute for Advanced Studies` of the University of Sao Paulo. It aims at decreasing the level of carbon dioxide in the atmosphere and thus curbing the green-house effect by way of a huge effort of forestation and reforestation. The resulting forests when the trees mature, will be responsible for the absorption of about 6 billion tons of excess carbon. It represents 5 % of the total amount of CO{sub 2} which is in excess in the earth`s atmosphere and represents 5 % of the available continental surfaces which can be forested as well. Therefore, if similar projects are implemented throughout the world, in theory all the exceeding CO{sub 2}, responsible for the `greenhouse effect`, (27 % or 115 billion tons of carbon) would be absorbed. Regarding this fact, there would be a 400 million hectar increase of growing forests. FLORAM in Brazil aims to plant 20.000.000 ha in 2 years at a cost of 20 billion dollars. If it reaches its goals that will mean that Brazil will have reforested an area almost half as big as France. (author)

  20. PORTNUS Project

    Energy Technology Data Exchange (ETDEWEB)

    Loyal, Rebecca E. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

    2015-07-14

    The objective of the Portunus Project is to create large, automated offshore ports that will the pace and scale of international trade. Additionally, these ports would increase the number of U.S. domestic trade vessels needed, as the imported goods would need to be transported from these offshore platforms to land-based ports such as Boston, Los Angeles, and Newark. Currently, domestic trade in the United States can only be conducted by vessels that abide by the Merchant Marine Act of 1920 – also referred to as the Jones Act. The Jones Act stipulates that vessels involved in domestic trade must be U.S. owned, U.S. built, and manned by a crew made up of U.S. citizens. The Portunus Project would increase the number of Jones Act vessels needed, which raises an interesting economic concern. Are Jones Act ships more expensive to operate than foreign vessels? Would it be more economically efficient to modify the Jones Act and allow vessels manned by foreign crews to engage in U.S. domestic trade? While opposition to altering the Jones Act is strong, it is important to consider the possibility that ship-owners who employ foreign crews will lobby for the chance to enter a growing domestic trade market. Their success would mean potential job loss for thousands of Americans currently employed in maritime trade.

  1. SISCAL project

    Science.gov (United States)

    Santer, Richard P.; Fell, Frank

    2003-05-01

    The first "ocean colour" sensor, Coastal Zone Color Scanner (CZCS), was launched in 1978. Oceanographers learnt a lot from CZCS but it remained a purely scientific sensor. In recent years, a new generation of satellite-borne earth observation (EO) instruments has been brought into space. These instruments combine high spectral and spatial resolution with revisiting rates of the order of one per day. More instruments with further increased spatial, spectral and temporal resolution will be available within the next years. In the meantime, evaluation procedures taking advantage of the capabilities of the new instruments were derived, allowing the retrieval of ecologically important parameters with higher accuracy than before. Space agencies are now able to collect and to process satellite data in real time and to disseminate them via the Internet. It is therefore meanwhile possible to envisage using EO operationally. In principle, a significant demand for EO data products on terrestrial or marine ecosystems exists both with public authorities (environmental protection, emergency management, natural resources management, national parks, regional planning, etc) and private companies (tourist industry, insurance companies, water suppliers, etc). However, for a number of reasons, many data products that can be derived from the new instruments and methods have not yet left the scientific community towards public or private end users. It is the intention of the proposed SISCAL (Satellite-based Information System on Coastal Areas and Lakes) project to contribute to the closure of the existing gap between space agencies and research institutions on one side and end users on the other side. To do so, we intend to create a data processor that automatically derives and subsequently delivers over the Internet, in Near-Real-Time (NRT), a number of data products tailored to individual end user needs. The data products will be generated using a Geographical Information System (GIS

  2. PROJECT TEAM MOTIVATION IN PROJECT REALISATION

    OpenAIRE

    Perica Jankoviæ

    2014-01-01

    Managing a project team is an everyday activity when managing a project realization. In order to accomplish efficiency at work on a project, it is necessary for all the participants in the project to be motivated and interested, focused on accomplishing the project. To the end of providing greater motivation of the project team for the realization of the project, the project manager should be very well acquainted with the needs and motives of the people he/she is managing and should find the ...

  3. Démantèlement des paysages cuirassés anciens en zones forestières tropicales d'Afrique centrale : formation d'accumulations ferrugineuses actuelles en bas de versantOld ferricrete landscape dismantling in Central Africa rain forest zone: formation of the present downslope iron accumulations

    Science.gov (United States)

    Temgoua, Émile; Bitom, Dieudonné; Bilong, Paul; Lucas, Yves; Pfeifer, Hans-Rudolf

    Present downslope iron accumulations were investigated in the rainforest zone in southern Cameroon. Six clay and Fe-hydroxide dominated patterns have been identified and occur on the lower part of hill slopes. They can be subdivided in three different sequences, related to gentle, moderate or steep slopes. They are discontinuous with respect to the dismantling zone of the old ferricrete cap formed at Cretaceous period. They show a gradual development from a soft Fe-crust (carapace) to a vesicular facies that will, with time, cover the whole landscape again. To cite this article: É. Temgoua et al., C. R. Geoscience 334 (2002) 537-543.

  4. ENVISION Project

    CERN Multimedia

    Ballantine, A; Dixon-Altaber, H; Dosanjh, M; Kuchina, L

    2011-01-01

    Hadrontherapy is a highly advanced technique of cancer radiotherapy that uses beams of charged particles (ions) to destroy tumour cells. While conventional X-rays traverse the human body depositing radiation as they pass through, ions deliver most of their energy at one point. Hadrontherapy is most advantageous once the position of the tumour is accurately known, so that healthy tissues can be protected. Accurate positioning is a crucial challenge for targeting moving organs, as in lung cancer, and for adapting the irradiation as the tumour shrinks with treatment. Therefore, quality assurance becomes one of the most relevant issues for an effective outcome of the cancer treatment. In order to improve the quality assurance tools for hadrontherapy, the European Commission is funding ENVISION, a 4-year project that aims at developing solutions for: real-• time non invasive monitoring • quantitative imaging • precise determination of delivered dose • fast feedback for optimal treatment planning • real-t...

  5. Projective mapping

    DEFF Research Database (Denmark)

    Dehlholm, Christian; Brockhoff, Per B.; Bredie, Wender Laurentius Petrus

    2012-01-01

    the applied framework, semantic restrictions, the choice of type of assessors and the validation of product separations. The applied framework concerns the response surface as presented to the assessor in different shapes, e.g. rectangular, square or round. Semantic restrictions are a part of the assessor...... instructions and influence heavily the product placements and the descriptive vocabulary (Dehlholm et.al., 2012b). The type of assessors performing the method influences results with an extra aspect in Projective Mapping compared to more analytical tests, as the given spontaneous perceptions are much dependent...... on the assessor’s way of thinking. Furthermore, a suggestion for validating product separations is proposed for the case where Multiple Factor Analysis is chosen for data analysis (Dehlholm, Brockhoff & Bredie, 2012a)....

  6. Project: Ultracentrifuges

    International Nuclear Information System (INIS)

    The trans elastic ultracentrifuge of magnetic suspension, is an instrument that arose of an interdisciplinary group directed by the Dr. James Clark Keith where it was projected, designed and built a centrifuge that didn't exist, to be applied in forced diffusion of uranium, like one of the many application fields. The written present, has as purpose to give to know the fundamental physical principles of this technology, its fundamental characteristics of design, the application of this in the separation process of isotopes, as well as the previous studies and essential control parameters in the experimental processes, the same thing that, the most outstanding results and the detection systems used in the confirmation and finally, the carried out potential applications of the principles of the ultracentrifugation technology. (Author)

  7. Ace Project as a Project Management Tool

    Science.gov (United States)

    Cline, Melinda; Guynes, Carl S.; Simard, Karine

    2010-01-01

    The primary challenge of project management is to achieve the project goals and objectives while adhering to project constraints--usually scope, quality, time and budget. The secondary challenge is to optimize the allocation and integration of resources necessary to meet pre-defined objectives. Project management software provides an active…

  8. Evaluation of Project Achievements in VOMARE -project

    OpenAIRE

    Kokkarinen, Eeva

    2011-01-01

    The purpose of the thesis is to study the achievements of VOMARE –project from the Finnish Lifeboat Institutions perspective. The organisation is a roof organisation for voluntary maritime rescue operation in Finland. The Finnish Lifeboat Institution is a lead partner in VOMARE –project which is EU funded project and the aim of the project is to start voluntary rescue operations in Estonia. The theoretical part of the work is divided into two main categories; project management and planni...

  9. An effective and sustainable D&D concept. Competencies and experiences of AREVA

    International Nuclear Information System (INIS)

    Business Unit created in 2008 to manage nuclear sites dismantling projects for AREVA and external clients through: Assistance during post-closure phase /deregulation; D&D planning and assistance; Project- and Site-Management; Decontamination; Dismantling; Waste management

  10. Project Lyman

    CERN Document Server

    McCandliss, Stephan R; Blair, William P; Kaiser, Mary Elizabeth; Feldman, Paul D; Meurer, Gerhardt R; Dixon, William V; Sahnow, David J; Neufeld, David A; Lupu, Roxana E; Fleming, Brian; Smee, Stephen A; Andersson, B G; Moseley, Samuel H; Kutyrev, Alexander S; Li, Mary J; Sonneborn, George; Siegmund, Oswald H W; Vallerga, John V; Welsh, Barry Y; Stiavelli, Massimo; Windhorst, Rogier A; Shapley, Alice E

    2008-01-01

    We explore the design of a space mission, Project Lyman, which has the goal of quantifying the ionization history of the universe from the present epoch to a redshift of z ~ 3. Observations from WMAP and SDSS show that before a redshift of z >~ 6 the first collapsed objects, possibly dwarf galaxies, emitted Lyman continuum (LyC) radiation shortward of 912 A, reionizing most of the universe. How LyC escapes from galactic environments, whether it induces positive or negative feedback on the local and global collapse of structures, and the role played by clumping, molecules, metallicity and dust are major unanswered theoretical questions, requiring observational constraint. Numerous intervening Lyman limit systems, which frustrate the detection of LyC from high z objects, thin below z ~ 3 where there are a few objects with apparently very high fesc. At low z there are only controversial detections and a handful of upper limits. A wide-field multi-object spectroscopic survey with moderate spectral and spatial res...

  11. Dismantling the Taboo against Vaccines in Pregnancy.

    Science.gov (United States)

    de Martino, Maurizio

    2016-01-01

    Vaccinating pregnant women in order to protect them, the fetus, and the child has become universal in no way at all. Prejudice in health professionals add to fears of women and their families. Both these feelings are not supported by even the smallest scientific data. Harmlessness for the mother and the child has been observed for seasonal, pandemic, or quadrivalent influenza, mono, combined polysaccharide or conjugated meningococcal or pneumococcal, tetanus toxoid, acellular pertussis, human papillomavirus, cholera, hepatitis A, Japanese encephalitis, rabies, anthrax, smallpox, yellow fever, mumps, measles and rubella combined, typhoid fever, inactivated or attenuated polio vaccines, and Bacillus Calmétte Guerin vaccines. Instead, the beneficial effects of influenza vaccine for the mother and the child as well as of pertussis vaccine for the child have been demonstrated. Obstetrician-gynecologists, general practitioners, and midwives must incorporate vaccination into their standard clinical care. Strong communication strategies effective at reducing parental vaccine hesitancy and approval of regulatory agencies for use of vaccines during pregnancy are needed. It must be clear that the lack of pre-licensure studies in pregnant women and, consequently, the lack of a statement about the use of the vaccine in pregnant women does not preclude its use in pregnancy. PMID:27338346

  12. "Write Every Day!": A Mantra Dismantled

    Science.gov (United States)

    Sword, Helen

    2016-01-01

    Numerous books, blogs, and articles on research productivity exhort academics to "write every day" even during the busiest of teaching times. Ironically, however, this research-boosting advice hangs from a perilously thin research thread. This article scrutinises the key findings of Robert Boice, whose pioneering studies of…

  13. Dismantling the Taboo against Vaccines in Pregnancy

    Directory of Open Access Journals (Sweden)

    Maurizio de Martino

    2016-06-01

    Full Text Available Vaccinating pregnant women in order to protect them, the fetus, and the child has become universal in no way at all. Prejudice in health professionals add to fears of women and their families. Both these feelings are not supported by even the smallest scientific data. Harmlessness for the mother and the child has been observed for seasonal, pandemic, or quadrivalent influenza, mono, combined polysaccharide or conjugated meningococcal or pneumococcal, tetanus toxoid, acellular pertussis, human papillomavirus, cholera, hepatitis A, Japanese encephalitis, rabies, anthrax, smallpox, yellow fever, mumps, measles and rubella combined, typhoid fever, inactivated or attenuated polio vaccines, and Bacillus Calmétte Guerin vaccines. Instead, the beneficial effects of influenza vaccine for the mother and the child as well as of pertussis vaccine for the child have been demonstrated. Obstetrician-gynecologists, general practitioners, and midwives must incorporate vaccination into their standard clinical care. Strong communication strategies effective at reducing parental vaccine hesitancy and approval of regulatory agencies for use of vaccines during pregnancy are needed. It must be clear that the lack of pre-licensure studies in pregnant women and, consequently, the lack of a statement about the use of the vaccine in pregnant women does not preclude its use in pregnancy.

  14. Dismantling the Taboo against Vaccines in Pregnancy

    Science.gov (United States)

    de Martino, Maurizio

    2016-01-01

    Vaccinating pregnant women in order to protect them, the fetus, and the child has become universal in no way at all. Prejudice in health professionals add to fears of women and their families. Both these feelings are not supported by even the smallest scientific data. Harmlessness for the mother and the child has been observed for seasonal, pandemic, or quadrivalent influenza, mono, combined polysaccharide or conjugated meningococcal or pneumococcal, tetanus toxoid, acellular pertussis, human papillomavirus, cholera, hepatitis A, Japanese encephalitis, rabies, anthrax, smallpox, yellow fever, mumps, measles and rubella combined, typhoid fever, inactivated or attenuated polio vaccines, and Bacillus Calmétte Guerin vaccines. Instead, the beneficial effects of influenza vaccine for the mother and the child as well as of pertussis vaccine for the child have been demonstrated. Obstetrician-gynecologists, general practitioners, and midwives must incorporate vaccination into their standard clinical care. Strong communication strategies effective at reducing parental vaccine hesitancy and approval of regulatory agencies for use of vaccines during pregnancy are needed. It must be clear that the lack of pre-licensure studies in pregnant women and, consequently, the lack of a statement about the use of the vaccine in pregnant women does not preclude its use in pregnancy. PMID:27338346

  15. Aging Studies of VCE Dismantlement Returns

    Energy Technology Data Exchange (ETDEWEB)

    Letant, S; Alviso, C; Pearson, M; Albo, R; Small, W; Wilson, T; Chinn, S; Maxwell, R

    2011-10-17

    VCE is an ethylene/vinyl acetate/vinyl alcohol terpolymer binder for filled elastomers which is designed to accept high filler loadings. Filled elastomer parts consist of the binder (VCE), a curing agent (Hylene MP, diphenol-4-4{prime}-methylenebis(phenylcarbamate)), a processing aid (LS, lithium stearate), and filler particles (typically 70% fraction by weight). The curing of the filled elastomer parts occurs from the heat-activated reaction between the hydroxyl groups of VCE with the Hylene MP curing agent, resulting in a cross-linked network. The final vinyl acetate content is typically between 34.9 and 37.9%, while the vinyl alcohol content is typically between 1.27 and 1.78%. Surveillance data for this material is both scarce and scattered, complicating the assessment of any aging trends in systems. In addition, most of the initial surveillance efforts focused on mechanical properties such as hardness and tensile strength, and chemical information is therefore lacking. Material characterization and aging studies had been performed on previous formulations of the VCE material but the Ethylene Vinyl Acetate (EVA) starting copolymer is no longer commercially available. New formulations with replacement EVA materials are currently being established and will require characterization as well as updated aging models.

  16. Sealed source dismantling hot cell - startup

    Energy Technology Data Exchange (ETDEWEB)

    Dellamano, Jose Claudio; Ferreira, Robson de Jesus, E-mail: jcdellam@ipen.br, E-mail: rojefer@ipen.br [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil). Gerencia de Rejeitos radioativos

    2013-07-01

    Sealed radioactive sources are widely used in many applications of nuclear technology and at the end of the useful life, most sources become radioactive waste. In Brazil, this waste is received by the Institutes of the National Nuclear Energy Commission and kept under centralized storage. The Waste Management Department at the Nuclear and Energy Research Institute is the main storage center, having received around 20,000 disused sources. A hot cell was designed and constructed to manage Co-60 spent sealed sources with activity up to 3.7 10{sup 1}0 Bq and other sources with equivalent activities. In the hot cell the sources are withdraw from their original shielding and transferred to a standard shielding for further disposal off. The original shielding disassembling is made outside the hot cell and after opening, it is transferred inside the hot cell and the sealed source is removed remotely. The source is checked in relation to external contamination and its activity is checked. After this, the source is positioned in the standard shielding located inside an overpack at the bottom of the hot cell. This paper describes some pre-operational tests carried out in it, that include: opening and closing doors and locks, checking of all electrical and pneumatic controls, the original shielding movement inside the hot-cell, dose rate measurements outside the hot-cell, insertion of the sealed sources inside the activity meter chamber, transferring the sealed source to the standard shielding, movement of the overpack with the standard shielding to outside of the hot-cell and plugging of the standard shielding. (author)

  17. Current status of decommissioning projects and their strategies in advanced countries

    Energy Technology Data Exchange (ETDEWEB)

    Chung, U. S.; Lee, K. W.; Hwang, D. S.; Park, S. K.; Hwang, S. T.; Paik, S. T.; Park, J. H.; Choi, Y. D.; Chung, K. H.; Lee, K. I.; Hong, S. B

    2007-06-15

    At the Korea Atomic Energy Research Institute(KAERI), two projects for decommissioning of the research reactors and uranium conversion plant are carried out. The number of nuclear facilities to be dismantled will be much increased in future and the decommissioning industries will be enlarged. Keeping pace with this increasing tendency, each country formulated their own strategies and regulation systems, and applied their own technologies. The international organizations such as the IAEA and the OECD/NEA also prepared standards in technologies and regulation upon decommissioning and recommended to adopt them to the decommissioning projects. These strategies and technologies are very different country by country due to the different site dependent conditions and it will not be reasonable to evaluate their merits and weakness. The world wide status of the decommissioning, highlighted on that of 5 countries of USA, UK, France, Germany and Japan because they are advanced counties in nuclear industries, are summarized and their site specific conditions are evaluated. The scopes of the evaluation are decommissioning strategies, licensing procedures and requirements focused on decommissioning plan, waste management, technology development and so on. The detailed decommissioning progresses of several typical example sites were introduced. The activities on decommissioning field of the international organization, increased according to the enlarged decommissioning industries, are also summarized.

  18. Current status of decommissioning projects and their strategies in advanced countries

    International Nuclear Information System (INIS)

    At the Korea Atomic Energy Research Institute(KAERI), two projects for decommissioning of the research reactors and uranium conversion plant are carried out. The number of nuclear facilities to be dismantled will be much increased in future and the decommissioning industries will be enlarged. Keeping pace with this increasing tendency, each country formulated their own strategies and regulation systems, and applied their own technologies. The international organizations such as the IAEA and the OECD/NEA also prepared standards in technologies and regulation upon decommissioning and recommended to adopt them to the decommissioning projects. These strategies and technologies are very different country by country due to the different site dependent conditions and it will not be reasonable to evaluate their merits and weakness. The world wide status of the decommissioning, highlighted on that of 5 countries of USA, UK, France, Germany and Japan because they are advanced counties in nuclear industries, are summarized and their site specific conditions are evaluated. The scopes of the evaluation are decommissioning strategies, licensing procedures and requirements focused on decommissioning plan, waste management, technology development and so on. The detailed decommissioning progresses of several typical example sites were introduced. The activities on decommissioning field of the international organization, increased according to the enlarged decommissioning industries, are also summarized

  19. Project management

    OpenAIRE

    Se, Ngoc

    2010-01-01

    Η παρούσα εργασία ασχολείται με τη διαμόρφωση μίας πλήρους και συνεκτικής πρότασης σχετικά με την ανάπτυξη ενός Μεταπτυχιακού Προγράμματος Σπουδών (ΜΠΣ) στη Διοίκηση Έργων (Project Management), λαμβάνοντας υπόψη τα εξής: το σύνολο των διεθνώς αποδεκτών θεμάτων που απαρτίζουν το λεγόμενο κορμό γνώσης (body of knowledge) στη διοίκηση έργων, τις βέλτιστες διεθνείς πρακτικές όπως έχουν καταγραφεί από αναζήτηση, διερεύνηση και ανάλυση αντίστοιχων διεθνώς ΜΠΣ, και αναγκαιότητα της αγορά...

  20. Storytelling in Projects

    DEFF Research Database (Denmark)

    Munk-Madsen, Andreas; Andersen, Peter Bøgh

    2006-01-01

    Plans and stories are two different ways of communicating about projects. Project plans are formalized descriptions, primarily supporting coordination. Project stories are accounts whose primary function is emotional appeal. Project stories influence the projects’ chances of success. Therefore pr...... the possibilities of telling favorable stories may have repercussions on the project planning.......Plans and stories are two different ways of communicating about projects. Project plans are formalized descriptions, primarily supporting coordination. Project stories are accounts whose primary function is emotional appeal. Project stories influence the projects’ chances of success. Therefore...... project managers should not only be concerned with project plans, but also with project stories. In this paper we explore some basic principles for transforming project plans into appealing stories. We discuss what may happen to stories once they are released into public space. And we illustrate how...

  1. Managing projects using a project management approach

    Directory of Open Access Journals (Sweden)

    Marko D. Andrejić

    2011-04-01

    Full Text Available Modern management theory treats all complex tasks and duties like projects and make these projects possible to be managed by a particular organizational-management concept in order to achieve a goal effectively. A large number of jobs and tasks performed in the system of defense or for defense purposes have the characteristics of projects. Project management is both a skill and a science of monitoring human, material, financial, energy and other resources to achieve required objectives within the given limits: deadlines, time, budget, possibility of realization and the satisfaction of the interests of all project participants. Project management is a traditional area of applied (or functional management focused on managing complex and uncertain situations with defined goals. Introduction In conditions of rapid change and high uncertainty, only adaptive organizations survive, i. e. those that are able not only to react quickly to changes but also to proactively take advantage of changes. Development of project management The biggest influence on the development of the area had complex jobs within the engineering profession. In parallel with the traditional approach new approaches began to develop, while the traditional one still remained in use. Contrary to the traditional engineering approach, a dynamic model first developed in order to respond to demands for greater control of costs. Project management Project management is a skill and knowledge of human and material resources to achieve set objectives within prescribed limits: deadlines, time, budget, possibility of realization, and the satisfaction of all participants in the project. In order to realize a project effectively, it is necessary to manage it rationally. Planning and project management A project plan is a document that allows all team members insight on where to go, when to start and when to arrive, what is necessary to be done in order to achieve the project objectives and what

  2. Project Planning and Management

    NARCIS (Netherlands)

    Weide, van der A.; Beulens, A.J.M.; Dijk, van S.

    2003-01-01

    Project Planning and Management helps prepare the reader to contribute confidently and effectively when working on projects or in managing project teams. This books concentrates on the output of a project as well as the whole process. It is written for projects in the areas of IT and knowledge manag

  3. Managing projects using a project management approach

    OpenAIRE

    Marko D. Andrejić; Boban D. Đorović; Dragan S. Pamučar

    2011-01-01

    Modern management theory treats all complex tasks and duties like projects and make these projects possible to be managed by a particular organizational-management concept in order to achieve a goal effectively. A large number of jobs and tasks performed in the system of defense or for defense purposes have the characteristics of projects. Project management is both a skill and a science of monitoring human, material, financial, energy and other resources to achieve required objectives within...

  4. World War II, The CANOL project and the Marwell Tar Pit: a case study

    International Nuclear Information System (INIS)

    The CANOL project was a joint U.S.-Canada undertaking during World War II. It entailed the construction of a road and pipeline from the oil fields of Norman Wells on the Mackenzie River, 960 kms over the Mackenzie Mountains to a new refinery at Whitehorse. The goal was to provide a secure supply of aviation fuel far from the menace of Japanese bombers. Initially, the pipeline was expected to operate by October 1942. In actual fact, the first gasoline was not produced in the crude distillation unit until April 24, 1944, and it was not until November 1944 that the refinery finally began producing aviation fuel. Four months later, the pipeline and the refinery were shut down. The project cost American taxpayers $ 134 million. A total of 2650 kms of pipeline was laid. During the first nine months of pipeline operation 46,000 barrels of oil was spilled, much of it directly into the Mackenzie River. Total production from the refinery, which itself cost $ 27 million, wa 866,670 barrels of products. When the refinery was shut down, most of the refinery structures were dismantled and moved, via the Alaska Highway, to the newly discovered Leduc oilfields, but buildings, tanks and hydrocarbon waste were left behind. In a 1960 report it was estimated that some four million litres of oil has been pumped into a pit located within the containment berm formerly surrounding an 80,000 barrel oil storage tank which was dismantled after the shutdown. The bureaucratic dispute about who is responsible for cleaning up has been an issue ever since. The cost of cleanup was estimated at about $ 4 million in 1994. Since the federal government, the original owners of the land , transferred the land to provincial jurisdiction in 1970, it disclaimed any responsibility for site cleanup, however, there has been some recent evidence of willingness on the part of the Department of National Defence and the Department of Indian and Northern Affairs to determine proper actions to clean up the site

  5. Managing Projects for Change: Contextualised Project Management

    Science.gov (United States)

    Tynan, Belinda; Adlington, Rachael; Stewart, Cherry; Vale, Deborah; Sims, Rod; Shanahan, Peter

    2010-01-01

    This paper will detail three projects which focussed on enhancing online learning at a large Australian distance education University within a School of Business, School of Health and School of Education. Each project had special funding and took quite distinctive project management approaches, which reflect the desire to embed innovation and…

  6. From project management to project leadership

    NARCIS (Netherlands)

    F. Braun; M. Avital

    2010-01-01

    It is virtually a truism that good leadership practices can help project managers with attaining the desired project outcome. However, a better understanding of which leadership practices enable project managers to be more effective warrants further investigation. Subsequently, in this study, we inv

  7. Desde la desarticulación al presente de los montes vecinales en mano común en Galicia From dismantling to current scenario in Galician mano commun mountains

    Directory of Open Access Journals (Sweden)

    Francisco García Quiroga

    2013-03-01

    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.

  8. Third session: new projects; Session 3: Les Projets nouveaux

    Energy Technology Data Exchange (ETDEWEB)

    Iracane, D. [CEA Saclay, Dir. de l' Energie Nucleaire (DEN), 91 - Gif sur Yvette (France); Dupuy, J.P. [AREVA-Technicatome, 13 - Aix en Provence (France); Perotto, G. [AREVA-Framatome-ANP, 13 - Aix en Provence (France); Ithurralde, G. [Electricite de France (EDF), 13 - Aix en Provence (France); Cabrillat, J.C. [CEA Cadarache, Dir. de l' Energie Nucleaire (DEN), 13 - Saint-Paul-lez-Durance (France); Becle, D. [FRAMATOME, AREVA-FANP, 69 - Lyon (France); Pivet, S. [CEA Bruyeres-le-Chatel, 91 (France); Minguet, J.L. [AREVA-Technicatome, 75 - Paris (France)

    2005-07-01

    The RJH (Jules Horowitz reactor) is a 100 MWth research reactor, cooled and moderated by water, that has been designed to operate with high density (8 g U/cm{sup 3}) and low enrichment fuel (19.75%) uranium molybdenum fuel. Its main neutron performances are expected to be: -) maximum fast neutron flux (E > 0.907 MeV) in the sample: 5.10{sup 14} n/cm{sup 2}/s, -) maximum thermal neutron flux (E < 0.625 eV): 4.10{sup 14} n/cm{sup 2}/s, and -) maximal neutron damage: 16 dpa/year. RJH that will be built on the Cea's site of Cadarache, is scheduled to enter into service in 2014, it will take over the activities of the Osiris reactor and its operating life is planned to be over 50 years long. The Cabri research reactor is located on the Cadarache site, it has been operating since 1962 and is now undergoing important upgrading operations whose aim is to make the facility fit to study the behaviour of new nuclear fuels in accidental situations. The RES test reactor is a facility whose aim is to qualify nuclear fuels and core configurations of existing propulsion reactors onboard of aircraft carriers or submarines and to propose innovative concepts for future propulsion reactors. (A.C.)

  9. Web Project Management

    OpenAIRE

    Suralkar, Sunita; Joshi, Nilambari; Meshram, B. B.

    2013-01-01

    This paper describes about the need for Web project management, fundamentals of project management for web projects: what it is, why projects go wrong, and what's different about web projects. We also discuss Cost Estimation Techniques based on Size Metrics. Though Web project development is similar to traditional software development applications, the special characteristics of Web Application development requires adaption of many software engineering approaches or even development of comple...

  10. Project 2010 For Dummies

    CERN Document Server

    Muir, Nancy C

    2010-01-01

    A friendly reference guide to Microsoft Project, the leading enterprise project management software. As project management software, Microsoft Project allows you to oversee your business activities effectively. You can manage resources, share project info, perform modeling and scenario analysis, and standardize reporting processes. This easy-to-understand guide is completely updated to cover the latest changes and newest enhancements to Project 2010 and shows you how to get Project 2010 to work for you. After an introduction to basic project management concepts, you'll discover the mechanics o

  11. USAID Anticorruption Projects Database

    Data.gov (United States)

    US Agency for International Development — The Anticorruption Projects Database (Database) includes information about USAID projects with anticorruption interventions implemented worldwide between 2007 and...

  12. Westinghouse decommissioning and remediation services. Global project experience advanced technology

    International Nuclear Information System (INIS)

    Westinghouse provides comprehensive, integrated services and solutions to the decommissioning and dismantling (D and D) and waste management industries. We have extensive experience in the dismantling of nuclear installations, from uranium mill plants to nuclear power plants. We provide state-of-the-art solutions for spent fuel services and for the treatment and handling of radioactive waste. Westinghouse offers proven solutions for the interim storage and fi nal disposal of low-, intermediate- and high-level waste. Our dedication to a cleaner environment extends to servicing existing nuclear power plants and managing by-products in an environmentally responsible manner. (Author)

  13. Project Half Double

    DEFF Research Database (Denmark)

    Ehlers, Michael; Adland, Karoline Thorp; Boston, Nicolai Elborough;

    Project Half Double has a clear mission to succeed in finding a project methodology that can increase the success rate of our projects while increasing the speed at which we generate new ideas and develop new products and services. Chaos and complexity should be seen as a basic condition...... activities carried out within the framework of the projects. The formal part of Project Half Double was initiated in June 2015. We started out by developing, refining and testing the Half Double methodology on seven pilot projects in the first phase of the project, which will end June 2016. The current...... organisations concerning project methodology and beyond. The many learning points from each pilot project show that Project Half Double has left its clear footprint in the pilot organisations, and that the Half Double methodology has evolved and developed very much during Project Half Double phase 1....

  14. West Valley Demonstration Project Annual Site Environmental Report Calendar Year 2003

    International Nuclear Information System (INIS)

    This Annual Site Environmental Report for the West Valley Demonstration Project (WVDP or Project) is published to inform those with interest about environmental conditions at the WVDP. In accordance with U.S. Department of Energy (DOE) Order 231.1A, Environment, Safety, and Health Reporting, the report summarizes calendar year (CY) 2003 environmental monitoring data so as to describe the performance of the WVDP's environmental management system (EMS), confirm compliance with standards and regulations, and highlight important programs. During 2003, cleanup of radioactive waste from the former nuclear fuels reprocessing plant that shut down operations in the 1970s was continued at the WVDP. The Project is located in western New York State, about 30 miles south of Buffalo, within the New York State-owned Western New York Nuclear Service Center (WNYNSC). The WVDP is being conducted in cooperation with the New York State Energy Research and Development Authority. Work activities at the WVDP during 2003 included: (1) maintaining canisters of vitrified high-level waste in a shielded facility; (2) shipping low-level radioactive waste offsite for disposal; (3) shipping packaged spent nuclear fuel assemblies to Idaho National Engineering and Environmental Laboratory; (4) constructing a facility where large high-activity components can be safely size-reduced and packaged for disposal; (5) decontaminating the fuel storage pool and the cask unloading pool; (6) decontaminating the general purpose cell and the process mechanical cell (also referred to as the head end cells); (7) cleanup of waste in the plutonium purification cell (south) and extraction cell number 2 in the main plant; (8) planning for decontamination and dismantlement of the vitrification facility; (9) continuing preparation of the Decommissioning and/or Long-Term Stewardship Environmental Impact Statement; and (10) monitoring the environment and managing contaminated areas within the Project facility premises

  15. Assembling the Project Team.

    Science.gov (United States)

    Mills, Donald B.

    2003-01-01

    Although the approval of a project's design and budget typically rests with the campus governing board, a project team determines the configuration, the cost, and the utility of the completed project. Because of the importance of these decisions, colleges and universities must select project team members carefully. (Author)

  16. The virtual GULLIVER project

    NARCIS (Netherlands)

    Nijholt, A.; Stuk, M.; Zwiers, J.; Trappl, R.

    2002-01-01

    In this paper we discuss our virtual reality project Gulliver. This project is part of a more comprehensive project conceived by two artists, Matjaž Štuk and Alena Hudcovicová, called “Gulliver’s Museum of Living Art”. Our part of the project involves a virtual reality version of Swift’s Gulliver fi

  17. Earth System Science Project

    Science.gov (United States)

    Rutherford, Sandra; Coffman, Margaret

    2004-01-01

    For several decades, science teachers have used bottles for classroom projects designed to teach students about biology. Bottle projects do not have to just focus on biology, however. These projects can also be used to engage students in Earth science topics. This article describes the Earth System Science Project, which was adapted and developed…

  18. Introduction to the Project

    DEFF Research Database (Denmark)

    Kuhn, Johan M.; Malchow-Møller, Nikolaj; Sørensen, Anders

    In this note a short introduction to the project “Employment Effects of Entrepreneurs” is presented. First, we describe the purpose of the project; second, we present the background; third, we briefly describe the three papers that constitute the output of the project, and fourth, we discuss two...... important qualifications for the understanding of the contributions and results established in the project....

  19. Project stakeholder management

    CERN Document Server

    Eskerod, Pernille

    2013-01-01

    Carrying out a project as planned is not a guarantee for success. Projects may fail because project management does not take the requirements, wishes and concerns of stakeholders sufficiently into account. Projects can only be successful though contributions from stakeholders. And in the end, it is the stakeholders that evaluate whether they find that the project is a success. To manage stakeholders effectively, you need to know your stakeholders, their behaviours and attitudes towards the project. In Project Stakeholder Management, the authors give guidance on how to adopt an analytical and s

  20. Modern project-management

    CERN Document Server

    CERN. Geneva

    2003-01-01

    This lecture will focus on the following issues: - The current state of the art in Project Management, especially the integration of Project Management with general management activities, and the integrated view of resources allocation. - Overview of the project life cycle, the phases and the deliverables - Necessity and limits of planning in a research environment - Organizational aspects of the projects the roles of the stakeholders - How to get the resources when they are needed - Risk Management in Projects - Earned value - How to keep a project on track (schedule and budget) - Management of the suppliers - Closing of the project

  1. IT Project Management Metrics

    Directory of Open Access Journals (Sweden)

    2007-01-01

    Full Text Available Many software and IT projects fail in completing theirs objectives because different causes of which the management of the projects has a high weight. In order to have successfully projects, lessons learned have to be used, historical data to be collected and metrics and indicators have to be computed and used to compare them with past projects and avoid failure to happen. This paper presents some metrics that can be used for the IT project management.

  2. Methodologies of Project Management

    Directory of Open Access Journals (Sweden)

    Wojciech Macek

    2011-07-01

    Full Text Available This paper presents comparison of three most popular project management standardsbelonging to a wider group of models (for example, PMBOK, Prince 2, CMMI, ISO 10006,BS 6079, IPMA Competence Baseline, European Commission Project Cycle ManagementGuidelines. The author discusses methods of project management according to PMBoK,Prince 2 and ISO 10006, some chosen criteria and fields of knowledge, such as generalregulations of standards, project range management, resources management, and processesconnected with risk, systems of project quality management.

  3. Project delivery system (PDS)

    CERN Document Server

    2001-01-01

    As business environments become increasingly competitive, companies seek more comprehensive solutions to the delivery of their projects. "Project Delivery System: Fourth Edition" describes the process-driven project delivery systems which incorporates the best practices from Total Quality and is aligned with the Project Management Institute and ISO Quality Standards is the means by which projects are consistently and efficiently planned, executed and completed to the satisfaction of clients and customers.

  4. Overview about project planning

    OpenAIRE

    Catalin Drob

    2012-01-01

    The purpose of this article is to present the main aspects regarding project planning. This study is generally based on the fourth edition of the Guide to the Project Management Body of Knowledge (PMBOK Guide) developed by the Project Management Institute (PMI) in 2008. According to this edition of PMBOK, project planning involves a group of processes required to establish the scope of the project, refine the objectives, and define the actions that must be undertaken to attain the objectives ...

  5. IT Project Management Metrics

    OpenAIRE

    Paul POCATILU

    2007-01-01

    Many software and IT projects fail in completing theirs objectives because different causes of which the management of the projects has a high weight. In order to have successfully projects, lessons learned have to be used, historical data to be collected and metrics and indicators have to be computed and used to compare them with past projects and avoid failure to happen. This paper presents some metrics that can be used for the IT project management.

  6. Project Phase Dependent Configuration of Project Management Information Systems

    OpenAIRE

    Bērziša, S; Grabis, J.

    2012-01-01

    Project management information systems ensure the collection and display of project information. The project information changes depend upon the project environment. According to project environment and requirements, the configuration of project management information system is ensured by means of an approach to configuration of project management information systems. However, topicality of information and access to it change during the project life cycle depending upo...

  7. Tokai-1 decommissioning project, the first challenge in Japan

    International Nuclear Information System (INIS)

    Tokai-1 is the oldest and historical commercial Magnox reactor in Japan, which had started commercial operation in 1966. The unit had helped introduction and establishment of the construction and operation technologies regarding nuclear power plant at early stage in Japan by its construction and operating experiences. However, The Japan Atomic Power Company (JAPC), the operator and owner of Tokai-1, decided to cease its operation permanently because of a fulfillment of its mission and economical reason. The unit was finally shut down in March 1998 after about 32 year operation. It took about three years for removal of all spent fuels from the site, and then decommissioning started in 2001. JAPC, always on the forefront of the nation's nuclear power generation, is now grappling Japan's first decommissioning of a commercial nuclear power plant, striving to establish effective, advanced decommissioning. The decommissioning for Tokai-1 was scheduled at 20 years project. At the beginning, the reactor was started to be in a static condition for ten years ('safe storage period'). While the reactor had been safely stored, the phased decommissioning works started from non-radioactive or low radioactive equipments toward high radioactive equipments. First five years of the project, JAPC concentrated to drain and clean spent fuel cartridge cooling pond and to remove conventional equipments such as turbine, feed water pump and fuel charge machine as planed and budgeted. From 2006, the project came into new phase. JAPC has been trying to remove four Steam Raising Units (SRUs). The SRUs are huge component (750ton, φ6.3m, H24.7m) of the Gas Cooling Reactor (GCR) and inside of the SRUs are radioactively contaminated. Major concerns are workers safety and minimizing contamination areas during SRU removal. Therefore, JAPC is developing and introducing Jack-down method and remote control multi-functional dismantling system. This method is to cut and remove the SRUs in turn from the

  8. A PROJECT WITHIN MICROSOFT PROJECT 2007

    Directory of Open Access Journals (Sweden)

    Emil COSMA

    2009-10-01

    Full Text Available The main purpose of this article is to emphasize the innumerable advantages of the Microsoft Project 2007 projecting environment that a project manager could benefit of. More exactly, Project Management stands for a function that is recognized within the majority of domains. A project is defined as “a temporary effort made for creating a product or a unique service”. A projects’ administrative programme within an informational system (such as Microsoft Project, Primavera Planner represents a “database that is in concordance with time”. It should help proceeding the required operations and, at the same time, to look and behave the same way other frequently utilized productive programmes. It keeps accounts of all information regarding the job requests, period and the project’s needed resources and visualizes the project’s plan in standard, well-defined formats, organizes the activities and resources consistently and efficiently,shares information regarding the project with all persons involved in an intranet or Internet network, and communicates efficiently with the resources and other involved persons, permitting at the same time the project manager to take the final control/decision as his/her responsibility.

  9. The Portable Tube Washer Project : project report

    OpenAIRE

    Døviken, Bjørnar D.; Lind, Henrik; Parken, Olav; Araya, Alexander

    2015-01-01

    The project group was assigned to develop and construct a fully automated, portable tube washer for the internal washing of small-bore hydraulic pipes; as well as plan, manage and document the project itself. Unfortunately, the physical construction of the product could not be realized due to insufficient budget funds that could not be raised.

  10. Information systems project management

    CERN Document Server

    Olson, David

    2014-01-01

    Information Systems Project Management addresses project management in the context of information systems. It deals with general project management principles, with focus on the special characteristics of information systems. It is based on an earlier text, but shortened to focus on essential project management elements.This updated version presents various statistics indicating endemic problems in completing information system projects on time, within budget, at designed functionality. While successful completion of an information systems project is a challenge, there are some things that ca

  11. Overview about project planning

    Directory of Open Access Journals (Sweden)

    Catalin Drob

    2012-12-01

    Full Text Available The purpose of this article is to present the main aspects regarding project planning. This study is generally based on the fourth edition of the Guide to the Project Management Body of Knowledge (PMBOK Guide developed by the Project Management Institute (PMI in 2008. According to this edition of PMBOK, project planning involves a group of processes required to establish the scope of the project, refine the objectives, and define the actions that must be undertaken to attain the objectives of the project.

  12. Project management case studies

    CERN Document Server

    Kerzner, Harold R

    2013-01-01

    A new edition of the most popular book of project management case studies, expanded to include more than 100 cases plus a ""super case"" on the Iridium Project Case studies are an important part of project management education and training. This Fourth Edition of Harold Kerzner''s Project Management Case Studies features a number of new cases covering value measurement in project management. Also included is the well-received ""super case,"" which covers all aspects of project management and may be used as a capstone for a course. This new edition:Contains 100-plus case studies drawn from re

  13. Project report - an overview of the project and experiences with project management

    DEFF Research Database (Denmark)

    Jørgensen, Michael Søgaard; Mikkelsen, Bent Egberg

    1996-01-01

    A collection of the project planning and the experiences with project management from the Catering 2000 project.As appendieces articles etc. from journals, newspapers etc. about the project.......A collection of the project planning and the experiences with project management from the Catering 2000 project.As appendieces articles etc. from journals, newspapers etc. about the project....

  14. Environmental Assessment of the Gering-Stegall 115-kV Transmission Line Consolidation Project, Scotts Bluff County, Nebraska

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-05-01

    The Department of Energy (DOE), Western Area Power Administration (Western) proposes to consolidate segments of two transmission lines near the Gering Substation in Gering, Nebraska. The transmission lines are both located in Scotts Bluff County, Nebraska. The transmission lines are both located in Scotts Bluff County, Nebraska, within the city of Gering. Presently, there are three parallel 115-kilovolt (kV) transmission lines on separate rights-of-way (ROW) that terminate at the Gering Substation. The project would include dismantling the Archer-Gering wood-pole transmission line and rebuilding the remaining two lines on single-pole steel double circuit structures. The project would consolidate the Gering-Stegall North and Gering-Stegall South 115-kV transmission lines on to one ROW for a 1.33-mile segment between the Gering Substation and a point west of the Gering Landfill. All existing wood-pole H-frame structures would be removed, and the Gering-Stegall North and South ROWs abandoned. Western is responsible for the design, construction, operation, and maintenance of the line. Western prepared an environmental assessment (EA) that analyzed the potential environmental impacts of the proposed construction, operation, and maintenance of the 115-kV transmission line consolidation. Based on the analyses in the EA, the DOE finds 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 (NEPA).

  15. Environmental Assessment of the Gering-Stegall 115-kV Transmission Line Consolidation Project, Scotts Bluff County, Nebraska

    International Nuclear Information System (INIS)

    The Department of Energy (DOE), Western Area Power Administration (Western) proposes to consolidate segments of two transmission lines near the Gering Substation in Gering, Nebraska. The transmission lines are both located in Scotts Bluff County, Nebraska. The transmission lines are both located in Scotts Bluff County, Nebraska, within the city of Gering. Presently, there are three parallel 115-kilovolt (kV) transmission lines on separate rights-of-way (ROW) that terminate at the Gering Substation. The project would include dismantling the Archer-Gering wood-pole transmission line and rebuilding the remaining two lines on single-pole steel double circuit structures. The project would consolidate the Gering-Stegall North and Gering-Stegall South 115-kV transmission lines on to one ROW for a 1.33-mile segment between the Gering Substation and a point west of the Gering Landfill. All existing wood-pole H-frame structures would be removed, and the Gering-Stegall North and South ROWs abandoned. Western is responsible for the design, construction, operation, and maintenance of the line. Western prepared an environmental assessment (EA) that analyzed the potential environmental impacts of the proposed construction, operation, and maintenance of the 115-kV transmission line consolidation. Based on the analyses in the EA, the DOE finds 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 (NEPA)

  16. Pro web project management

    CERN Document Server

    Emond, Justin

    2012-01-01

    Caters to an under-served niche market of small and medium-sized web consulting projects Eases people's project management pain Uses a clear, simple, and accessible style that eschews theory and hates walls of text

  17. The Phebus FP project

    International Nuclear Information System (INIS)

    This report summarizes the pre-project studies concerning the PHEBUS FP facility. After recalling the programme objectives, it describes the projected modifications to the PHEBUS reactor, outlines new installations and justifies the selected options

  18. Successful project management

    CERN Document Server

    Young, Trevor L

    2016-01-01

    Successful Project Management, 5th edition, is an essential guide for anyone who wants to improve the success rate of their projects. It will help managers to maintain a balance between the demands of the customer, the project, the team and the organization. Covering the more technical aspects of a project from start to completion it contains practised and tested techniques, covering project conception and start-up, how to manage stake holders, effective risk management, project planning and launch and execution. Also including a brand new glossary of key terms, it provides help with evaluating your project as well as practical checklists and templates to ensure success for any ambitious project manager. With over one million copies sold, the hugely popular Creating Success series covers a wide variety of topic, with the latest editions including new chapters such as Tough Conversations and Treating People Right. This indispensable business skills collection is suited to a variety of roles, from someone look...

  19. Architectural project and research

    DEFF Research Database (Denmark)

    Lotz, Katrine

    2005-01-01

    Discussion of criterias for research including the researchers or designers own project as theme.......Discussion of criterias for research including the researchers or designers own project as theme....

  20. Earned value project management

    CERN Document Server

    Fleming, Quentin W

    2010-01-01

    Organizations that follow the principles of good Earned Value Management (EVM) create an environment that allows teams to successfully operate and thrive ? even in the face of challenges that could negatively impact their projects. Earned Value Project Management (EVPM) is a methodology used to measure and communicate the real physical progress of a project taking into account the work completed, the time taken and the costs incurred to complete that work. As a result, EVPM allows more educated and effective management decision-making, which helps evaluate and control project risk by measuring project progress in monetary terms. In the first two editions of Earned Value Project Management, Quentin W. Fleming and Joel M. Koppelman provided guidance for project management practitioners already familiar with EVPM, was well as those who were new to the use of this technique. The third edition expanded the information available on of EVPM for medium and smaller projects while still being relevant for larger projec...