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

International Nuclear Information System (INIS)

Lafaille, C.

1991-01-01

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

Achievements and prospects of robotics in dismantling operations

International Nuclear Information System (INIS)

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

1993-01-01

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

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

International Nuclear Information System (INIS)

Poncet, Philippe

2016-01-01

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

Processing of LLW arising from dismantling activities in a reprocessing facility

International Nuclear Information System (INIS)

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

1990-01-01

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

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

Temperature buffer test. Dismantling operation

International Nuclear Information System (INIS)

Aakesson, Mattias

2010-12-01

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

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

International Nuclear Information System (INIS)

2016-01-01

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

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

International Nuclear Information System (INIS)

Noakes, M.W.

1998-01-01

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

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.)

STMI: several years of experience in nuclear plant dismantling

International Nuclear Information System (INIS)

Moreau, J.C.

1985-01-01

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

National School of Dismantling

International Nuclear Information System (INIS)

Ivaldi, Fabienne

2003-01-01

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

Method for dismantling shields

International Nuclear Information System (INIS)

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

1990-01-01

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

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

International Nuclear Information System (INIS)

Cahen, B.

2013-01-01

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

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

International Nuclear Information System (INIS)

Seiki, Yoshihiro; Kubo, Takashi.

1996-01-01

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

Dismantling system of concrete thermal shielding walls

International Nuclear Information System (INIS)

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

1985-01-01

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

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

International Nuclear Information System (INIS)

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

2003-03-01

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

Cleansing and dismantling of CEA-Saclay nuclear licensed facilities

International Nuclear Information System (INIS)

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

2013-01-01

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

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

Energy Technology Data Exchange (ETDEWEB)

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

2009-07-01

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

The dismantling of CEA nuclear installations

International Nuclear Information System (INIS)

Piketty, Laurence

2016-03-01

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

Dismantling of nuclear facilities

International Nuclear Information System (INIS)

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

2009-01-01

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

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...

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

International Nuclear Information System (INIS)

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

2003-01-01

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

Nuclear installations: decommissioning and dismantling

International Nuclear Information System (INIS)

Anon.

1995-01-01

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

Dismantling of nuclear facilities and related problems - Conference proceedings

International Nuclear Information System (INIS)

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

2012-11-01

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

Machine for dismantling metal parts

Energy Technology Data Exchange (ETDEWEB)

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

1982-01-01

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

Consideration of dismantling operations in the design

International Nuclear Information System (INIS)

Dubourg; Bonin.

1984-12-01

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

Towards the creation of an industrial sector dedicated to nuclear dismantling

International Nuclear Information System (INIS)

Anon.

2015-01-01

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

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

International Nuclear Information System (INIS)

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

2003-01-01

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

Decontamination and dismantlement of the old hot laundry, CFA-669. Final report

International Nuclear Information System (INIS)

Smith, D.L.; Perry, E.F.

1995-01-01

This final report describes the decontamination and dismantlement (D ampersand D) of the old hot laundry, located at the Idaho National Engineering Laboratory (INEL) Central Facilities Area (CFA). The report describes the site before and after D ampersand D, processes used, cost and duration, and waste volume generated. In addition, lessons learned are presented. Pre-D ampersand D characterization indicated gross alpha concentrations in the building ranged from 6 to 310 pCi/g and gross beta measurements from 6 to 15,000 pCi/g. Gamma spectrum analysis identified cobalt-60, cesium-137, antimony-125, europium-152, europium-154, and niobium-94

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

International Nuclear Information System (INIS)

Behar, C.

2012-01-01

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

Decontamination and remote dismantling tests in the Itrec reprocessing plant

International Nuclear Information System (INIS)

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

1993-01-01

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

Radiation protection procedures for the dismantling and decontamination of nuclear facility

International Nuclear Information System (INIS)

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

2013-01-01

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

Radiation Hardened Telerobotic Dismantling System Development Final Report CRADA No. TC-1340-96

Energy Technology Data Exchange (ETDEWEB)

Smith, C. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Lightman, A. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

2017-09-27

This project was a collaborative effort between the University of California, LLNL and RedZone Robotics, Inc. for the development of radiation-hardened telerobotic dismantling systems for use in applications such as nuclear facility remediation, nuclear accident response, and Chemobyltype remediation. The project supported the design, development, fabrication and testing of a Ukrainian robotic systems. The project was completed on time and within budget. All deliverables were completed. The final project deliverables were consistent with the plans developed in the original project with the exception that the fabricated systems remained in Ukraine.

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

Energy Technology Data Exchange (ETDEWEB)

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

2015-10-15

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

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

International Nuclear Information System (INIS)

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

2015-01-01

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

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

International Nuclear Information System (INIS)

Moreau, J.C.

1986-01-01

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

Preparing for Decommissioning During Operation and After Final Shutdown

International Nuclear Information System (INIS)

Kostova, Milena; Papaz, Dan; Pottelberg, Paul; Clement, Gilles; Falcone, Jean-Luc; Gouhier, Eric; Laurent, Gerard; Rondeau, Jean-Marie; Siefridt, Camille; Brendebach, Boris; Knaack, Michael; Ahn, Sangmyeon; Correa Sainz, Cristina; Carroll, Simon; Larsson, Arne; Norberg, Thomas; Stridsman, Henrik; Minges, Juergen; Boniface, Simon; Dunlop, Alister; Jassal, Raj; Moakes, Joanna; Abu-Eid, Rateb; Watson, Bruce; Devgun, Jas; McGrath, Richard; Glorennec, Christian; ); Weber, Inge; )

2018-01-01

The transition from an operating nuclear facility to the decommissioning phase is critical in the life cycle of every facility. A number of organisational and technical modifications are needed in order for the facility to meet new objectives and requirements, and a certain number of activities must be initiated to support the transition and preparation for the dismantling of the facility. Thorough preparation and planning is key for the success of global decommissioning and dismantling projects, both to minimise delays and undue costs and to ensure a safe and efficient decommissioning process. The aim of this report is to inform regulatory bodies, policy makers and planners about the relevant aspects and activities that should begin during the last years of operation and following the end of operation. Compiling lessons learnt from experiences and good practices in NEA member countries, the report supports the further optimisation of transition strategies, activities and measures that will ensure adequate preparation for decommissioning and dismantling

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.

Definition of a dismantling project

International Nuclear Information System (INIS)

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

1988-01-01

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

Decommissioning and dismantling of the Rossendorf Isotope Production

International Nuclear Information System (INIS)

Grahnert, Thomas

2016-01-01

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

BRET fuel assembly dismantling machine

International Nuclear Information System (INIS)

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

1984-08-01

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

Nuclab Marcoule: a dedicated waste management and dismantling support laboratory

International Nuclear Information System (INIS)

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

2014-01-01

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

Decontamination and dismantling of large plutonium-contamined glove boxes

International Nuclear Information System (INIS)

Draulans, J.

1991-01-01

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

Decision support system for the dismantling of building in nuclear facilities

International Nuclear Information System (INIS)

Zeiher, M.

2009-01-01

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

Rosie: A mobile worksystem for decontamination and dismantlement operations

International Nuclear Information System (INIS)

Thompson, B.R.; Conley, L.

1996-01-01

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

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

International Nuclear Information System (INIS)

Sesterhenn, Kurt

2008-01-01

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

DISMANTLING OF THE FUEL CELL LABORATORY AT RESEARCH CENTRE JUELICH

International Nuclear Information System (INIS)

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

2003-01-01

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

Provisions for the dismantling of nuclear facilities are sufficient

International Nuclear Information System (INIS)

Le Ngoc, B.

2016-01-01

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

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

International Nuclear Information System (INIS)

1998-01-01

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

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

Energy Technology Data Exchange (ETDEWEB)

NONE

1998-12-31

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

Dismantling and decontamination of the PIVER prototype vitrification facility

International Nuclear Information System (INIS)

Jouan, A.

1989-01-01

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

Remote dismantling of the French Brennilis nuclear power plant

International Nuclear Information System (INIS)

Studenski, Joerg

2009-01-01

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

Remote dismantling of the French Brennilis nuclear power plant

Energy Technology Data Exchange (ETDEWEB)

Studenski, Joerg [NUKEM Technologies GmbH (Germany)

2009-07-01

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

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

International Nuclear Information System (INIS)

Ebadian, M.A.

1998-01-01

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

General Research and Development problems in dismantling

International Nuclear Information System (INIS)

Lorin, C.

1993-01-01

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

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

International Nuclear Information System (INIS)

Marchal, Pierre

2014-01-01

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

Dismantling and waste managing benefit from digital technologies

International Nuclear Information System (INIS)

Moitrier, C.

2017-01-01

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

Study on treatment of dust by dismantling

International Nuclear Information System (INIS)

Torikai, K.; Suzuki, K.

1987-01-01

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

Jose Cabrera dismantling and decommissioning project

International Nuclear Information System (INIS)

Ondaro, Manuel

2013-01-01

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

Jose Cabrera dismantling and decommissioning project

Energy Technology Data Exchange (ETDEWEB)

Ondaro, Manuel [ENRESA, Madrid (Spain)

2013-07-01

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

CRITICALITY CONTROL DURING THE DISMANTLING OF A URANIUM CONVERSION PLANT

International Nuclear Information System (INIS)

LADURELLE, Laurent; LISBONNE, Pierre

2003-01-01

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

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

International Nuclear Information System (INIS)

Dubourg, M.

1987-01-01

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

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

Energy Technology Data Exchange (ETDEWEB)

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

2015-05-15

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

Decontamination and partial dismantling of the Eurochemic plant. Part 1

International Nuclear Information System (INIS)

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

1980-09-01

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

Dismantlement and Radioactive Waste Management of DPRK Nuclear Facilities

Energy Technology Data Exchange (ETDEWEB)

Jooho, W.; Baldwin, G. T.

2005-04-01

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

Dismantlement and Radioactive Waste Management of DPRK Nuclear Facilities

International Nuclear Information System (INIS)

Jooho, W.; Baldwin, G.T.

2005-01-01

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

Development of multi-functional telerobotic systems for reactor dismantlement

International Nuclear Information System (INIS)

Fujii, Yoshio; Usui, Hozumi; Shinohara, Yoshikuni

1992-01-01

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

Rosie: A mobile workstation for decontamination and dismantlement operations

International Nuclear Information System (INIS)

1994-01-01

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

Dismantling and decommissioning of Jose Cabrera nuclear power plant

International Nuclear Information System (INIS)

Rodriguez, A.

2009-01-01

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

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

International Nuclear Information System (INIS)

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

2008-01-01

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

Dismantling techniques

Energy Technology Data Exchange (ETDEWEB)

Wiese, E.

1998-03-13

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

Dismantling techniques

International Nuclear Information System (INIS)

Wiese, E.

1998-01-01

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

Decommissioning of the AVR reactor, concept for the total dismantling

International Nuclear Information System (INIS)

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

1998-01-01

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

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

Energy Technology Data Exchange (ETDEWEB)

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

2001-03-01

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

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

International Nuclear Information System (INIS)

Myodo, Masato; Miyajima, Kazutoshi; Okane, Shogo

2001-03-01

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

Dismantling technologies trends

International Nuclear Information System (INIS)

Devaux, P.

2009-01-01

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

Abrasive water jet cutting technique for biological shield concrete dismantlement

International Nuclear Information System (INIS)

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

1987-01-01

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

Experience in dismantling and packaging of pressure vessel and core internals

International Nuclear Information System (INIS)

Pillokat, Peter; Bruhn, Jan Hendrik

2011-01-01

Nuclear Company AREVA is proud to look back on versatile experience in successfully dismantling nuclear components. After performing several minor dismantling projects and studies for nuclear power plants, AREVA completed the order for dismantling of all remaining Reactor Pressure Vessel internals at German Boiling Water Reactor Wuergassen NPP in October '08. During the onsite activities about 121 tons of steel were successfully cut and packed under water into 200l- drums, as the dismantling was performed partly in situ and partly in an underwater working tank. AREVA deployed a variety of different cutting techniques such as band sawing, milling, nibbling, compass sawing and water jet cutting throughout this project. After successfully finishing this task, AREVA dismantled the cylindrical part of the Wuergassen Pressure Vessel. During this project approximately 320 tons of steel were cut and packaged for final disposal, as dismantling was mainly performed by on air use of water jet cutting with vacuum suction of abrasive and kerfs material. The main clue during this assignment was the logistic challenge to handle and convey cut pieces from the pressure vessel to the packing area. For this, an elevator was installed to transport cut segments into the turbine hall, where a special housing was built for final storage conditioning. At the beginning of 2007, another complex dismantling project of great importance was acquired by AREVA. The contract included dismantling and conditioning for final storage of the complete RPV Internals of the German Pressurized Water Reactor Stade NPP. Very similar cutting techniques turned out to be the proper policy to cope this task. On-site activities took place in up to 5 separate working areas including areas for post segmentation and packaging to perform optimized parallel activities. All together about 85 tons of Core Internals were successfully dismantled at Stade NPP until September '09. To accomplish the best possible on

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

International Nuclear Information System (INIS)

Santiago, Juan Luis

2012-01-01

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

Waste management concept during dismantling of KKS NPP in Germany

International Nuclear Information System (INIS)

Bacmeister, Georg U.

2008-01-01

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

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

International Nuclear Information System (INIS)

Rondeau, J.

2001-01-01

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

Development of equipments for remote dismantling of joule heated ceramic melter

International Nuclear Information System (INIS)

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

2011-01-01

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

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

International Nuclear Information System (INIS)

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

2006-01-01

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

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

International Nuclear Information System (INIS)

Tachon, M.

1988-01-01

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

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

International Nuclear Information System (INIS)

Hummel, L.; Zech, J.B.

2005-01-01

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

Dismantling and decontamination of Piver prototype vitrification plant

International Nuclear Information System (INIS)

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

1991-01-01

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

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...

The Superphenix dismantling

International Nuclear Information System (INIS)

Carle, R.

1999-01-01

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

SGDES: Management system dismantling of ENRESA

International Nuclear Information System (INIS)

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

2013-01-01

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

The Pierrelatte's military factories dismantling

International Nuclear Information System (INIS)

Bourrelier, P.; Kassel, Ch.

1999-01-01

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

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

International Nuclear Information System (INIS)

Anon.

2017-01-01

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

Overall strategy of Creys Malville power station dismantling

International Nuclear Information System (INIS)

Alphonse, P.

2002-01-01

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

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

International Nuclear Information System (INIS)

Asazuma, Shinichiroh; Takeda, Shinsoh; Tajima, Shoichi

2004-11-01

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

Brennilis, laboratory of dismantlement

International Nuclear Information System (INIS)

Dupin, L.

2011-01-01

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

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!

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

Reactor vessel dismantling at the high flux materials testing reactor Petten

International Nuclear Information System (INIS)

Tas, A.; Teunissen, G.

1986-01-01

The project of replacing the reactor vessel of the high flux materials testing reactor (HFR) originated in 1974 when results of several research programs confirmed severe neutron embrittlement of aluminium alloys suggesting a limited life of the existing facility. This report describes the dismantling philosophy and organisation, the design of special underwater equipment, the dismantling of the reactor vessel and thermal column, and the conditioning and shielding activities resulting in a working area for the installation of the new vessel with no access limitations due to radiation. Finally an overview of the segmentation, waste disposal and radiation exposure is given. The total dismantling, segmentation and conditioning activities resulted in a total collective radiation dose of 300 mSv. (orig.) [de

Development of telerobotic manipulators for reactor dismantling work

International Nuclear Information System (INIS)

Shinohara, Yoshikuni; Usui, Hozumi; Fujii, Yoshio

1991-01-01

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

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

Energy Technology Data Exchange (ETDEWEB)

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

2012-07-01

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

Dismantling of JPDR begins: to demonstrate advanced technology

Energy Technology Data Exchange (ETDEWEB)

1986-12-01

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

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

International Nuclear Information System (INIS)

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

2006-01-01

previously a leakage on inner source housing. Thus, during manufacturing the filled-lead for shielding passed through this small hole and fixed the deformed spring together with the source. The circular surface of inner hole was measured and slowly drilled at a diameter 2.2 cm behind shielding, till the spring and the fixed lead sheet were cut, therefore the source could be finally hammered out. The surface dose rate of coal level gauges before weld cutting was 10-15 mR/hr and the highest dose rate at the position of the weld cutter was 2.5 mR/hr. The total time for each weld cutting and automatic sawing was 2-3 minutes and 1 minute, respectively. The source was individually and safely transferred to store in lead safe box using a 1-meter length tong and a light container with 1 meter length handle. The total time for Ra-226 (70 pieces) dismantling, including the encountered problems and their troubles shooting took 4 days operation in which the total dose obtained by 18 operators were ranged from 1-38 μSv. The dismantling team safely completed the activities within the effective dose limit for occupational exposure of 20 mSv/year (80 μSv/day). (authors)

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

International Nuclear Information System (INIS)

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

2014-07-01

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

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

International Nuclear Information System (INIS)

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

2000-01-01

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

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

International Nuclear Information System (INIS)

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

2016-01-01

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

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

International Nuclear Information System (INIS)

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

2015-01-01

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

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

International Nuclear Information System (INIS)

Hatakeyama, Mutsuo; Tachibana, Mitsuo; Yanagihara, Satoshi

1997-12-01

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

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

International Nuclear Information System (INIS)

Wright, E.M.

1993-01-01

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

The promising opportunity of dismantlement

International Nuclear Information System (INIS)

Anon.

2009-01-01

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

In-situ dismantling of plutonium-contaminated glove box

International Nuclear Information System (INIS)

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

1980-01-01

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

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

International Nuclear Information System (INIS)

Ebadian, M.A.

1999-01-01

The dismantlement of radioactively contaminated process equipment is a major concern during the D and 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 and 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 and 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 and D community in the areas of technology performance, cost, and health and safety

Experience in the decontamination and dismantling of alpha facilities

International Nuclear Information System (INIS)

Charamathieu, A.

1988-01-01

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

Decommissioning of nuclear reprocessing plants French past experience and approach to future large scale operations

International Nuclear Information System (INIS)

Jean Jacques, M.; Maurel, J.J.; Maillet, J.

1994-01-01

Over the years, France has built up significant experience in dismantling nuclear fuel reprocessing facilities or various types of units representative of a modern reprocessing plant. However, only small or medium scale operations have been carried out so far. To prepare the future decommissioning of large size industrial facilities such as UP1 (Marcoule) and UP2 (La Hague), new technologies must be developed to maximize waste recycling and optimize direct operations by operators, taking the integrated dose and cost aspects into account. The decommissioning and dismantling methodology comprises: a preparation phase for inventory, choice and installation of tools and arrangement of working areas, a dismantling phase with decontamination, and a final contamination control phase. Detailed description of dismantling operations of the MA Pu finishing facility (La Hague) and of the RM2 radio metallurgical laboratory (CEA-Fontenay-aux-Roses) are given as examples. (J.S.). 3 tabs

Technical challenges for dismantlement verification

International Nuclear Information System (INIS)

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

1997-01-01

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

Radiological Characterisation for Decommissioning of Nuclear Installations - Final Report of the Task Group on Radiological Characterisation and Decommissioning (RCD) of the Working Party on Decommissioning and Dismantling (WPDD) - Final Report, September 2013

International Nuclear Information System (INIS)

Andrieu, Caroline; Olivier Dehaye, Catherine; Tardy, Frederic; Boisserie, Thierry; Desnoyers, Yvon; Thierfeldt, Stefan; Martin, Nieves; Henrik Efraimsson; Haakansson, Lars; Larsson, Arne; Dunlop, Alister A.; Jarman, Sean; Orr, Peter; Abu-Eid, Boby

2013-01-01

Radiological characterisation plays an important role in the decommissioning of nuclear facilities. It is the basis for radiation protection, identification of contamination, assessment of potential risks, cost estimation, planning and implementation of decommissioning and other matters. At all stages of a decommissioning project, adequate radiological characterisation is of crucial importance. The focus of this report is the task of radiological characterisation. The important role and the significance of radiological characterisation become clear when its various objectives are considered, including in particular: - determination of the type, isotopic composition and extent of contamination in structures, systems, components and environmental media; - identification of the nature and extent of remedial actions and decontamination; - supporting planning of decommissioning; - estimation of decommissioning costs. A large number of measurement techniques are available for successful application of radiological characterisation, allowing rapid and comprehensive determination of the activities of most relevant radionuclides. For other radionuclides that are hard to detect, scaling factors can be established that relate their activities to key nuclides. Radiological characterisation is relevant in all phases of the life cycle of a nuclear installation, albeit with different levels of detail and with differing objectives. Basically, the following characterisation phases can be distinguished: pre-operational characterisation; characterisation during operation; characterisation during the transition phase (after final shutdown before initiation of dismantling); characterisation during dismantling (including remediation and decontamination); and characterisation to support the final status survey for site release. The most comprehensive characterisation campaigns are usually carried out during the transition phase in preparation for implementation of dismantling activities

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

International Nuclear Information System (INIS)

Jeong, Kwanseong; Moon, Jeikwon; Choi, Byungseon

2012-01-01

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

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

International Nuclear Information System (INIS)

Yoshimori, Michiro; Ohkoshi, Minoru; Abe, Masayoshi

1995-01-01

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

UDIN's dismantling projects

International Nuclear Information System (INIS)

Laffaille, C.

1993-01-01

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

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

International Nuclear Information System (INIS)

Laveissiere, Stephane; Coronini, Vincent

2013-01-01

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

The dismantling of nuclear power plants which are not in use

International Nuclear Information System (INIS)

Tanguy, P.

1987-01-01

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

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

International Nuclear Information System (INIS)

None

1997-01-01

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 and 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 and D activities beginning in 1997

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

International Nuclear Information System (INIS)

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

1981-05-01

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

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

International Nuclear Information System (INIS)

2003-02-01

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

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

International Nuclear Information System (INIS)

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

2014-01-01

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

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

International Nuclear Information System (INIS)

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

2013-01-01

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

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)

Dismantling of nuclear facilities: the industrial know-how

International Nuclear Information System (INIS)

Lellament, R.

2004-01-01

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

Dismantling of transuranic contaminated facilities

International Nuclear Information System (INIS)

Roux, P.

1985-01-01

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

The Japan Power Demonstration Reactor dismantling project. Radiation control

International Nuclear Information System (INIS)

Tomii, Hiroyuki; Seiki, Yoshihiro

1996-01-01

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

Towards a more professional demolition and dismantling industry

International Nuclear Information System (INIS)

1988-01-01

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

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

International Nuclear Information System (INIS)

Hagenbart, Lars; Held, Christian; Reichert, Alexander

2013-01-01

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.

Dismantling institutional racism: theory and action.

Science.gov (United States)

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

2007-06-01

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

Weapons dismantlement issues in independent Ukraine

International Nuclear Information System (INIS)

Zack, N.R.

1995-01-01

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

The timing of reactor dismantling

International Nuclear Information System (INIS)

Roberts, P.

2000-01-01

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

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

International Nuclear Information System (INIS)

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

2002-01-01

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

Dismantling without contaminating: The EUREX plant experience

International Nuclear Information System (INIS)

2001-01-01

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

Cold trap dismantling and sodium removal at a fast breeder reactor

Energy Technology Data Exchange (ETDEWEB)

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

2013-11-15

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

Dismantling id the reactor pressure vessel insulation and dissecting of the MZFR reactor pressure vessel

International Nuclear Information System (INIS)

Loeb, Andreas; Stanke, Dieter; Thoma, Markus; Eisenmann, Beata; Prechtl, Erwin; Dehnke, Burckhard

2008-01-01

The MZFR reactor was decommissioned in 1984. The authors describe the dismantling of the reactor pressure vessel insulation that consists of asbestos containing mineral fiber wool. The appropriate remote handling and cutting tools had to be adapted with respect to the restrained space in the containment. The dismantling of the reactor pressure vessel has been completed, the dissected parts have been packaged into 200 containers for the final repository Konrad. During the total project time no reportable events and no damage to persons occurred.

Decontamination and dismantling at the CEA

International Nuclear Information System (INIS)

2006-01-01

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

Method of freezing type dismantling for wasted reactors

International Nuclear Information System (INIS)

Tatsumi, Toshiyuki.

1985-01-01

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

The preliminary 3D dynamic simulation on the RSR dismantling process of the KRR-1 and 2

International Nuclear Information System (INIS)

Kim, Hee-Reyoung; Kim, Sung-Kyun; Seo, Bum-Kyoung; Lee, Kune-Woo; Park, Jin-Ho

2003-01-01

A three-dimensional graphic simulation has been carried out for the dismantling process of the Rotary Specimen Rack(RSR) in the Korea Research Reactor-1 and 2 (KRR-1 and 2). First of all, the general steps of the graphic simulation were established and reviewed for the dismantling process of the object. Four dismantling processes, which are the removal of RSR, reactor core region, beam tube, and thermal column and activated concrete, were selected for the graphic simulation on the virtual space by the consideration of the activation, worker training, work difficulty and so on. In the present study, the dismantling procedure of the RSR was divided into several steps and its visual simulation was performed by the 3D graphic software. Finally, the simulation result was converted to moving file with extension of AVI so that easy approach can be made on window OS system

Dismantling of the rooms 82 to 100 at Marcoule

International Nuclear Information System (INIS)

Fiol, A.

1988-01-01

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

The Grenoble CEA Center: dismantled and rehabilitated

International Nuclear Information System (INIS)

Anon.

2013-01-01

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

Decontamination and dismantlement plan for international reviewing

International Nuclear Information System (INIS)

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

2000-01-01

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

Long range manipulator development and experiments with dismantling tools

International Nuclear Information System (INIS)

Mueller, K.

1993-01-01

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

The good wealth of dismantlement

International Nuclear Information System (INIS)

Maincent, G.

2009-01-01

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

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

Energy Technology Data Exchange (ETDEWEB)

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

2016-10-15

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

EL-3 dismantling of an experimental reactor

International Nuclear Information System (INIS)

1989-01-01

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

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

International Nuclear Information System (INIS)

Walton, L.

1995-01-01

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

Dismantling and removal of the Niederaichbach nuclear power plant (KKN) to the 'Green Field'. Final report

International Nuclear Information System (INIS)

Valencia, L.; Prechtl, E.

1998-04-01

The major objective of the present project consisted in the complete dismantling and removal of the Niederaichbach nuclear power plant (KKN), ranging from the state of safe enclosure to re-establishing the original state of vegetation of the site (so-called 'green field'). By reaching this objective, principle feasibility of the complete removal of a power reactor was demonstrated. In addition, considerable experience has been gained with regard to the execution of all phases of such a complex project and project optimization. The following phases of the project can be distinguished: - Licensing procedure - dismantling of the inactive, contaminated and activated plant sections - disassembly of the activated building structures and decontamination of the buildings - demolition (conventional) of the buildings and recultivation of the site. Moreover, the project included the work performed under the direct supervision of the licensing authority, comprehensive radiation protection activities, the solution of waste management problems and the respective public relations work. (orig./MM) [de

Dismantling the nuclear research reactor Thetis

Energy Technology Data Exchange (ETDEWEB)

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

2013-07-01

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

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

International Nuclear Information System (INIS)

Kenny, Stephen

2008-01-01

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

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

International Nuclear Information System (INIS)

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

2017-01-01

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

Dismantling of Vandellos I

International Nuclear Information System (INIS)

Armada, J. R.

2003-01-01

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

Development of plasma arc cutting technique for dismantlement of reactor internals in JPDR decommissioning program

International Nuclear Information System (INIS)

Yanagihara, Satoshi; Tanaka, Mitsugu; Ujihara, Norio.

1988-01-01

The decommissioning program for JPDR has been conducted by JAERI since 1981 under contact with the Science and Technology Agency of Japan. The development of cutting tools for dismantling the JPDR is one of the important items in the program. An underwater plasma arc cutting technique was selected for dismantling the JPDR core internals. The study was concentrated on improving the cutting ability in water. Various cutting tests were conducted changing the parameters such as arc current, supply gas and cutting speed to evaluate the most effective cutting condition. Through the study, it has been achieved to be able to cut a 130 mm thick stainless steel plate in water. In addition, the amount and the characteristics of by-products were measured during the cutting tests for the safety evaluation of the dismantling activities. Final cutting tests and checkout of whole plasma arc cutting system were conducted using a mockup water pool and test pieces simulating the JPDR core internals. It was proved from the tests that the cutting system developed in the program will be applicable for the JPDR core internals dismantlement. (author)

Remote Fiber Laser Cutting System for Dismantling Glass Melter - 13071

Energy Technology Data Exchange (ETDEWEB)

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

2013-07-01

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

Underwater-manipulation system for measuring- and cutting tasks in dismantling decommissioned nuclear facilities. Final report

International Nuclear Information System (INIS)

Stegemann, D.; Reimche, W.; Hansch, M.; Spitzer, M.

1995-01-01

Not only manipulators are necessary for dismantling and inspection of structure parts in decomissioned nuclear facilities, but flexible underwater-vehicles. Free-diving underwater-vehicles for inspection and dismantling tasks are still not developed and tested. Aim of the project is the development of sensors and devices for the position determination and the depth regulation. For inspection tasks an ultrasonic measurement and dosimeter device shall be built up. A measurement device has been developed which evaluates the ultrasonic time of flight from a transmitter at the vehicle to several receivers, installed in the reactor pressure vessel. The depth regulation is based on a pressure sensor and the direct control of the thrusters. The ultrasonic measurements are realized by an adapted ultrasonic card, the γ-dosimetry with an ionization chamber and a pA-amplifier. An acoustic orientation system was built up, which measures very accurately with one transmitter mounted on the vehicle and four receivers. Problem occur by reflection from the walls of the basin. The depth regulation is working faultless. The ultrasonic device is preferably used for distance measurement. The radiation measurement device was tested and mounted in the vehicle. (orig./HP) [de

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

International Nuclear Information System (INIS)

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

2014-01-01

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

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

Contaminated Metal Components in Dismantling by Hot Cutting Processes

International Nuclear Information System (INIS)

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

2006-01-01

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

Treatment of concrete bars from the dismantling of hot cells

International Nuclear Information System (INIS)

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

2002-01-01

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

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

International Nuclear Information System (INIS)

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

2006-01-01

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

Use of laser cutting techniques for dismantling tasks in nuclear facilities

International Nuclear Information System (INIS)

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

2001-01-01

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

Use of laser cutting techniques for dismantling tasks in nuclear facilities

Energy Technology Data Exchange (ETDEWEB)

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

2001-07-01

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

Dismantling method for reactor shielding wall and device therefor

International Nuclear Information System (INIS)

Akagawa, Katsuhiko.

1995-01-01

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

A Study on Dismantling of Westinghouse Type Nuclear Reactor

International Nuclear Information System (INIS)

Jeong, Woo-Tae; Lee, Sang-Guk

2014-01-01

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

Environmental Assessment for decontamination and dismantlement, Pinellas Plant

International Nuclear Information System (INIS)

1995-06-01

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

Decontamination of the HFR dismantling cell

International Nuclear Information System (INIS)

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

1976-05-01

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

Dismantling of nuclear facilities. From a structural engineering perspective

International Nuclear Information System (INIS)

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

2014-01-01

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

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

Energy Technology Data Exchange (ETDEWEB)

Bredel; Thierry; Buzare, Alain

2005-01-01

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

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

International Nuclear Information System (INIS)

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

2013-01-01

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

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

International Nuclear Information System (INIS)

Destrait, L.

1998-01-01

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

Vandellos-I Dismantling nearing completion

International Nuclear Information System (INIS)

Armada, J. R.

2004-01-01

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

Experience acquired by EDF in implementation of its dismantling programme

Energy Technology Data Exchange (ETDEWEB)

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

2008-07-01

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

The installation and dismantling of electrolytic cells

International Nuclear Information System (INIS)

Galushkin, N.V.

1995-01-01

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

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

International Nuclear Information System (INIS)

Seifert, L. S.

1998-01-01

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

Process cells dismantling of EUREX pant: previous activities

International Nuclear Information System (INIS)

Gili, M.

1998-01-01

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

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

Energy Technology Data Exchange (ETDEWEB)

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

2015-07-01

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

Method and jig for dismantling nuclear fuel assembly

International Nuclear Information System (INIS)

Urata, Megumi; Watahiki, Minoru.

1989-01-01

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

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

Energy Technology Data Exchange (ETDEWEB)

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

2017-03-15

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

Economical dismantling of nuclear power stations

International Nuclear Information System (INIS)

Mallok, J.; Andermann, H.

1999-01-01

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

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

International Nuclear Information System (INIS)

Pot, J.; Levesque, P.

1997-01-01

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

Development of Digital Mock-Up for the Assessment of Dismantling Scenarios

International Nuclear Information System (INIS)

Kim, Sung-Kyun; Park, Hee-Sung; Lee, Kune-Woo; Jung, Chong-Hun

2008-01-01

As the number of superannuated research reactors and nuclear power plants increase, dismantling nuclear power facilities has become a big issue. However, decommissioning a nuclear facility is still a costly and possibly hazardous task. So prior to an actual decommission, what should be done foremost is to establish a proper procedure. Due to the fact that a significant difference in cost, exposure to a radiation, and safety might occur, a proper procedure is imperative for the entire engineering process. The purpose of this paper is to develop a system for evaluating the decommissioning scenarios logically and systematically. So a digital mockup system with functions such as a dismantling schedule, decommissioning costs, wastes, worker's exposure dose, and a radiation distribution was developed. Also on the basis of the quantitative information calculated from a DMU system and the data evaluated by decommissioning experts about qualitatively evaluating the items, the best decommissioning scenarios were established by using the analytic hierarchy process (AHP) method. Finally, the DMU was implemented in the thermal column of KRR-1 and adequate scenarios were provided after comparing and analyzing the two scenarios. In this paper, we developed the virtual environment of KRR-1 by using computer graphic technology and simulating the dismantling processes. The data-computing modules were also developed for quantitatively comparing the decommissioning scenarios. The decommissioning DMU system was integrated with both the VE system and the data-computing modules. In addition, we presented a decision-making method for selecting the best decommissioning scenario through the AHP. So the scenarios can be evaluated logically and quantitatively through the decommissioning DMU. As an implementation of the AHP, the plasma cutting scenario and the nibbler cutting scenario of the thermal column were prioritized. The fact that the plasma cutting scenario ranked the better than the

Evaluation of decontamination during dismantling of plutonium-contaminated glove boxes

International Nuclear Information System (INIS)

Kinugasa, Manabu; Taguchi, Seigi; Ohzeki, Satoru; Inoue, Yoshiaki; Kashima, Sadamitsu

1981-01-01

The dismantling work of plutonium-contaminated glove boxes was carried out. These glove boxes had been used for the R and D of plutonium-uranium mixed oxide fuel for 15 years. The work was carried out in a pressure-controlled greenhouse, and the contamination of air in the greenhouse was monitored continuously. In order to reduce the contamination of air during dismantling, the decontamination and fixation of loose contaminants on the surfaces of glove boxes were very important. The correlation between decontamination and the contamination of air regarding dismantling is reported in this paper. The surface contamination density of the glove boxes was measured utilizing the smear method before and after the decontamination, and the decontamination effects were estimated. The contamination of air during dismantling was continuously measured with a plutonium dust monitor. It was found that loose contamination exponentially decreased by the decontamination process. When the so-called wet glove boxes, which contained wet recovery and waste disposal apparatus, were dismantled, the contamination of air did not exceed 500 (MPC) a. However, the contamination of air exceeded 500 (MPC) a several times in the present work of dismantling the so-called dry glove boxes which had been used for the fabrication of plutonium-uranium mixed oxide pellets. (Kato, T.)

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

International Nuclear Information System (INIS)

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

2011-01-01

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

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

International Nuclear Information System (INIS)

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

2012-01-01

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

Dismantling of the 50 MW steam generator test facility

International Nuclear Information System (INIS)

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

1997-01-01

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

Foam decontamination of large nuclear components before dismantling

International Nuclear Information System (INIS)

Costes, J.R.; Sahut, C.

1998-01-01

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

Study on applicability of evaluation model of manpower needs for dismantling of equipments in FUGEN-1. Dismantling process in 3rd/4th feedwater heater room

International Nuclear Information System (INIS)

Shibahara, Yuji; Izumi, Masanori; Nanko, Takashi; Tachibana, Mitsuo; Ishigami, Tsutomu

2010-10-01

Manpower needs for the dismantling process on the dismantling of equipments in FUGEN 3rd/4th feedwater heater room was calculated with the management data evaluation system (PRODIA Code), and it was inspected whether the conventional evaluation model had applicability for FUGEN or not. It was confirmed that the conventional evaluation model for feedwater heater had no applicability. In comparison of the calculated value with the actual data, we found two difference: 1) the calculated value were significantly larger than the actual data, 2) the actual data for the dismantling of 3rd feedwater heater was twice larger than that of 4th feedwater heater, though these equipments were almost same weight. It was found that these were brought 1) by the difference in the work descriptions of dismantling between JPDR and FUGEN, and 2) by that in the cutting number between 3rd feedwater heater and 4th one. The manpower needs for the dismantling of both feedwater heaters were calculated with a new calculation equation reflecting the descriptions of dismantling, and it was found that these results showed the good agreement with the actual data. (author)

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

International Nuclear Information System (INIS)

Lagos, L.E.; Ebadian, M.A.

1998-01-01

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

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

International Nuclear Information System (INIS)

2017-09-01

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

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

Energy Technology Data Exchange (ETDEWEB)

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

2015-07-01

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

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.

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

International Nuclear Information System (INIS)

Shiraishi, Kunio; Sukegawa, Takenori; Yanagihara, Satoshi

1998-03-01

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

Transparency in nuclear warhead dismantlement -- Limited chain of custody and warhead signatures

International Nuclear Information System (INIS)

Kiernan, G.; Percival, M.; Bratcher, L.

1996-01-01

The goal of the US Safeguards, Transparency, and Irreversibility (STI) initiative is the development of a series of transparency measures that provide confidence that nuclear warheads are actually being dismantled and that the fissile material being removed from these dismantled weapons is not recycled into new production. A limited chain of custody (LCC) would follow a warhead from the time it is declared excess until it is actually dismantled and the fissile materials are stored. Measurement of warhead signatures is an option in LCC using radiation detection techniques to confirm that a warhead has been dismantled, without intrusive inspections within the dismantlement facility. This paper discusses LCC and warhead signatures as well as indicate first results of laboratory measurements related to warhead signatures

Decommissioning and dismantling of nuclear and fuel cycle facilitites in Spain

International Nuclear Information System (INIS)

Gravalos, J.M.; Alamo, S.

1992-01-01

In the recent past, and as a consequence of a fire in the turbine island of the Vandellos I Graphite Gas type Nuclear Plant, which damaged the facility to a point that recovery was not judged economically feasible, the authorities decided on the final shutdown of the plant. Several studies were performed in order to select the dismantling strategy to be adopted. In spite of Valdellos I being the first commercial reactor to be decommissioned in Spain, several research reactors and fuel cycle facilities, which have reached the end of their commercial lives, are at present at different stages of their dismantling and decommissioning process as is described further. The development of an exemption policy for below regulatory concern wastes is considered a very significant issue regarding decommissioning as it has a large impact on radioactive waste volumes, and thus on costs. Aware of this problem ENRESA together with Spanish regulatory authorities are working in close cooperation with CEC research programs to complete the development of criteria and methodologies for the application of exemption practices in Spain

Engineering activities for the preparation of systems and facilities in the dismantling of Jose Cabrera NPP

International Nuclear Information System (INIS)

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

2012-01-01

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.

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

International Nuclear Information System (INIS)

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

1995-01-01

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

Cutting techniques for facilities dismantling in decommissioning projects

International Nuclear Information System (INIS)

Lainetti, Paulo E.O.

2011-01-01

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

Some steps of the dismantling of the hot cell ATTILA

International Nuclear Information System (INIS)

Terrasson, L.

1989-01-01

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

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

International Nuclear Information System (INIS)

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

2010-01-01

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

Shielded Cells D ampersand D and Dismantlement System Requirements

International Nuclear Information System (INIS)

Witherspoon, R.L.

1995-01-01

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

Calculation of external exposure during transport and disposal of radioactive waste arisen from dismantling of steam generator

International Nuclear Information System (INIS)

Hornacek, M.; Necas, V.

2014-01-01

The dismantling of large components (reactor pressure vessel, reactor internals, steam generator) represents complex of processes involving preparation, dismantling, waste treatment and conditioning, transport and final disposal. To optimise all of these activities in accordance with the ALARA principle the prediction of the exposure of workers is an essential prerequisite. The paper deals with the calculation of external exposure of workers during transport and final disposal of heat exchange tubes of steam generator used in Slovak nuclear power plant V1 in Jaslovske Bohunice. The type of waste packages, the calculation models of truck and National Radioactive Waste Repository in Mochovce are presented. The detailed methodology of radioactive waste disposal is showed and the degree of influence of time decay (0, 5 and 10 years) on the radiological conditions during transport and disposal is studied. All of the results do not exceed the limits given in Slovak and international regulatory documents. (authors)

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.

Dismantling Experiment of Mock-up Tube Bundle of Steam Generator

International Nuclear Information System (INIS)

Kim, Sung Kyun; Lee, Kune Woo

2010-01-01

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

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

Energy Technology Data Exchange (ETDEWEB)

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

1999-02-01

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

Method of dismantling cylindrical structure by cutting

International Nuclear Information System (INIS)

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

1989-01-01

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

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

International Nuclear Information System (INIS)

1985-01-01

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

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

International Nuclear Information System (INIS)

Komura, Shiro; Heki, Hideaki.

1991-01-01

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

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

International Nuclear Information System (INIS)

Leibundgut, Fritz

2017-01-01

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

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

International Nuclear Information System (INIS)

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

1995-01-01

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

Fabrication of mixed oxide fuel using plutonium from dismantled weapons

International Nuclear Information System (INIS)

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

1996-01-01

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

Evaluation of worker's dose on a virtual dismantling environment

International Nuclear Information System (INIS)

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

2007-01-01

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

Decommissioning and dismantling of the reprocessing plant Karlsruhe

International Nuclear Information System (INIS)

Eiben, K.; Fritz, P.

1995-01-01

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

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

International Nuclear Information System (INIS)

Baumann, R.; Faber, P.

2003-01-01

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

Evaluation methodology of a manipulator actuator for the dismantling process during nuclear decommissioning

International Nuclear Information System (INIS)

Park, Jongwon; Kim, Chang-Hoi; Jeong, Kyung-min; Choi, Byung-Seon; Moon, Jeikwon

2016-01-01

Highlights: • A methodology to evaluate actuators of a dismantling manipulator. • Evaluation criteria for choosing the most suitable actuator type. • A mathematical evaluation model for evaluation. • The evaluation method is expected to be used for determining other manipulators. - Abstract: This paper presents a methodology to evaluate actuators of a manipulator for dismantling nuclear power plants. Actuators are the most dominant components because a dismantling manipulator relies heavily on the actuator type used. To select the most suitable actuator, evaluation criteria are presented in four categories based on the nuclear dismantling environment. A mathematical model is presented and evaluation results are calculated with weights and scores for each criterion. The proposed evaluation method is expected to be used for determining other aspects of the design of dismantling manipulators.

Study on the Operating Strategy of HVAC Systems for Nuclear Decommissioning Plant

Energy Technology Data Exchange (ETDEWEB)

Kim, Sung-hwan; Han, Sung-heum; Lee, Jae-gon [KHNP CRI, Daejeon (Korea, Republic of)

2016-10-15

According as Kori nuclear power plant unit 1 was determined to be defueled in 2017, various studies on nuclear plant decommissioning have been performed. In nuclear decommissioning plant, HVAC systems with large fan and electric coil have to be operated for long periods of time to support various types of work from defueled phase to final dismantling phase. So, in view of safety and utility costs, their overall operating strategy need to be established prior to defueled phase. This study presents HVAC system operating strategy at each decommissioning phase, that is, defueled plant operating phase, SSCs(systems, structures, components) decontamination and dismantling phases. In defueled plant operating phase, all fuel assemblies in reactor vessel are transferred to spent fuel pool(SFP) permanently. In defueled plant operation phase, reduction of the operating system trains is more practicable than the introduction of new HVAC components with reduced capacity. And, based on the result of the accident analyses for this phase, HVAC design bases such as MCR habitability requirement can be mitigated. According to these results, associated SSCs also can be downgraded. In similar approach, at each phase of plant decommissioning, proper inside design conditions and operating strategies should be re-established.

Integration of remotely operated manipulator systems for the nuclear industry

International Nuclear Information System (INIS)

Blight, J.; Cornec, G.

2003-01-01

rectify the situation. The paper has the following structure: Methodology (choice of scenarios, initial status, final status); Phases preceding dismantling operations; Flux of wastes; Processes; Remotely operated manipulators; Development of scenarios; Involvement of CYBERNETIX in dismantling projects; Involvement in 'Upstream phasest'; Supply of remotely operated systems; Validation of processes and remotely operated systems prior to active work; Involvement at site. As a summary, CYBERNETIX recommends, in order to ensure the good development of a project: - to be actively involved in developing/validating processes and scenarios, in order to make sure that constraints from both the remotely operated systems and the environment are taken into consideration; - to amortize amortization of development, integration, refurbishing, maintenance and storage costs on a serial of works/projects; - to provision sufficient time to develop, adapt, fine-tune equipment and processes, as a function of the scenarios; - to validate equipment and processes and confirm operational performances of the system during prior tests in 'non-active' or 'slightly active' conditions before the operational phase; - to be actively involved in site operations, in order to trouble-shout, fine-tune and constantly improve equipment and processes, using their own operators, technicians and engineers in order to guarantee the availability of the system in all circumstances; - to establish with the prime contractor, or other participating companies 'partnering' or 'alliance' agreements during operational phases, in order to motivate all actors

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

International Nuclear Information System (INIS)

Masanori Izumi; Yukihiro Iguchi; Yoshiki Kannehira

2005-01-01

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

Optimized phases for reactor dismantling – an efficient and sustainable concept

International Nuclear Information System (INIS)

Krüger, S.; Winter, J.

2013-01-01

D&D projects are driven by costs, to implement an optimization process from the very beginning is key. Optimized strategy and sequencing of the dismantling (hot to cold) will provide serious economical savings . Larger dismantling packages will reduce interfaces and ease the coordination efforts on site. Early usage of mobile systems will ease the large-scale release for dismantling Social transition has to be addressed with priority and to be planned at an early phase in the D&D planning Concept, Planning & Project Management will influence the success of the project much more than the used technique

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.

Laser cutting equipment for dismantling irradiated PFR fuel sub-assemblies

International Nuclear Information System (INIS)

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

1981-01-01

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

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

International Nuclear Information System (INIS)

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

2012-01-01

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

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

Energy Technology Data Exchange (ETDEWEB)

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

2015-11-15

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

Study of large size fiber reinforced cement containers for solid wastes from dismantling

International Nuclear Information System (INIS)

Jaouen, C.

1990-01-01

The production of large-sized metallic waste by dismantling operations, and the evolution of the specifications of the waste to be stored in the different European countries will create a need for large standard containers for the transport and final disposal of the corresponding waste. The research conducted during the 1984-1988 programme, supported by the Commission of European Communities, and based on a comparative study of high-grade concrete materials, reinforced with organic or metallic fibres, led to the development of a high performance container meeting international transport recommendations as well as French requirements for shallow-ground disposal. The material selected, consisting of high-performance mortar with metal fibre reinforcement, was the subject of an intensive programme of characterization tests conducted in close cooperation with LAFARGE Company, demonstrating the achievement of mechanical and physical properties comfortably above the regulatory requirements. The construction of an industrial prototype and the subsequent economic analysis served to guarantee the industrial feasibility and cost of this system, in which attempts were made to optimize the finished package product, including its closure system

Guidelines for the abandonment operations in the petroleum and gas industry

International Nuclear Information System (INIS)

Bedoya V, Julio Cesar; Zapata S, Carmen Elena

2003-01-01

Decommission operations, in the hydrocarbons sector, are essential to maintain a clean environment. We propose a guidelines to provide a methodology to standardize the decommission procedures establishing a logical structure in the operations. It shows the generations of possible decommission alternatives. They are picked up in three types, abandonment that is to leave the infrastructure in the place, dismantlement that is the total dismounts of the pieces that compose it, reutilization that will be the new use that will be given to the things. Finally, through an appropriate environmental management, to select the best decommission alternatives that mitigate the impacts and the generation of environmental passives. A project can be presented the abandonment, the reutilization and the dismantlement simultaneously. Also, there are forms to organize and to evaluate the process of decommission. The interdisciplinary work has great importance in this process, as well as an appropriate social management with the affected communities

Temperature buffer test. Final report

International Nuclear Information System (INIS)

Aakesson, Mattias

2012-04-01

The Temperature Buffer Test (TBT) is a joint project between SKB/ANDRA and supported by ENRESA (modelling) and DBE (instrumentation), which aims at improving the understanding and to model the thermo-hydro-mechanical behavior of buffers made of swelling clay submitted to high temperatures (over 100 deg C) during the water saturation process. The test has been carried out in a KBS-3 deposition hole at Aspo HRL. It was installed during the spring of 2003. Two steel heaters (3 m long, 0.6 m diameter) and two buffer arrangements have been investigated: the lower heater was surrounded by rings of compacted Wyoming bentonite only, whereas the upper heater was surrounded by a composite barrier, with a sand shield between the heater and the bentonite. The test was dismantled and sampled during the winter of 2009/2010. This report is the final report and a summary of all work performed within the TBT project. The design and the installation of the different components are summarized: the depositions hole, the heating system, the bentonite blocks with emphasis on the initial density and water content in these, the filling of slots with sand or pellets, the retaining construction with the plug, lid and nine anchor cables, the artificial saturation system, and finally the instrumentation. An overview of the operational conditions is presented: the power output from heaters, which was 1,500 W (and also 1,600 W) from each heater during the first ∼1,700 days, and then changed to 1,000 and 2,000 W, for the upper and lower heater respectively, during the last ∼600 days. From the start, the bentonite was hydrated with a groundwater from a nearby bore-hole, but this groundwater was replaced with de-ionized water from day ∼1,500, due to the high flow resistance of the injections points in the filter, which implied that a high filter pressure couldn't be sustained. The sand shield around the upper heater was hydrated from day ∼1,500 to day ∼1,800. The sensors data concerning

Temperature buffer test. Final report

Energy Technology Data Exchange (ETDEWEB)

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

2012-04-15

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 Aspo HRL. It was installed during the spring of 2003. Two steel heaters (3 m long, 0.6 m diameter) and two buffer arrangements have been investigated: the lower heater was surrounded by rings of compacted Wyoming bentonite only, whereas the upper heater was surrounded by a composite barrier, with a sand shield between the heater and the bentonite. The test was dismantled and sampled during the winter of 2009/2010. This report is the final report and a summary of all work performed within the TBT project. The design and the installation of the different components are summarized: the depositions hole, the heating system, the bentonite blocks with emphasis on the initial density and water content in these, the filling of slots with sand or pellets, the retaining construction with the plug, lid and nine anchor cables, the artificial saturation system, and finally the instrumentation. An overview of the operational conditions is presented: the power output from heaters, which was 1,500 W (and also 1,600 W) from each heater during the first {approx}1,700 days, and then changed to 1,000 and 2,000 W, for the upper and lower heater respectively, during the last {approx}600 days. From the start, the bentonite was hydrated with a groundwater from a nearby bore-hole, but this groundwater was replaced with de-ionized water from day {approx}1,500, due to the high flow resistance of the injections points in the filter, which implied that a high filter pressure couldn't be sustained. The sand shield around the upper heater was hydrated from day {approx}1,500 to day {approx}1

Final storage of radioactive waste

International Nuclear Information System (INIS)

Ziehm, Cornelia

2015-01-01

As explained in the present article, operators of nuclear power plants are responsible for the safe final disposal of the radioactive wastes they produce on the strength of the polluter pays principle. To shift the burden of responsibility for safe disposal to society as a whole would violate this principle and is therefore not possible. The polluter pays principle follows from more general principles of the fair distribution of benefits and burdens. Instances of its implementation are to be found in the national Atomic Energy Law as well as in the European Radioactive Waste and Spent Fuel Management Directive. The polluters in this case are in particular responsible for financing the installation and operation of final disposal sites. The reserves accumulated so far for the decommissioning and dismantling of nuclear power plants and disposal of radioactive wastes, including the installation and operation of final disposal sites, should be transferred to a public-law fund. This fund should be supplemented by the polluters to cover further foreseeable costs not covered by the reserves accumulated so far, including a realistic cost increase factor, appropriate risk reserves as well as the costs of the site selection procedure and a share in the costs for the safe closure of the final disposal sites of Morsleben and Asse II. This would merely be implementing in the sphere of atomic law that has long been standard practice in other areas of environmental law involving environmental hazards.

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

International Nuclear Information System (INIS)

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

2004-12-01

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

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

CSIR Research Space (South Africa)

Fassihi, A

2014-07-01

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

Regulatory supervision of the radiation protection and release during the dismantling of the German NPP Wuergassen

International Nuclear Information System (INIS)

Boerchers, F.; Hillberg, M.

2003-01-01

The NPP Wuergassen (KWW) is a commercial, single unit boiling water reactor with a capacity of 670 MW el . It was commissioned by PreussenElektra and constructed by AEG/KWU between 1968 and 1971. This NPP was finally shut down in 1994. The decommissioning, started in April 1997, is still under progress. Up to now, approx. 9,500 Mg of various materials (e.g. metal scrap, cable, concrete) have been deconstructed and released from the site. In this paper we describe the contribution from the authority and the independent expert during the radiological characterisation, the dismantling work, and the material flow up to the release. Special focus will be on the necessary control steps and the documentation regarding the dismantling work and the procedure of release. There is always a close fit between the radiation protection and the release of material on the basis of the radiological characterisation. (authors)

Document status for 1 and 2 Kozloduy NPP decommissioning activities -Phase 'Final Shutdown'

International Nuclear Information System (INIS)

Vangev, A.; Boyadjiev, Z.

1997-01-01

Decommissioning process (D and D) is the final phase of each nuclear reactor life cycle. The first nuclear reactor generation has reached his expiration life date. Decommissioning working documentation had not been taken into account at the project and construction stage. The decommissioning activities, planning and legislation has to develop along their operation. Most of developed nuclear energetic countries have gathered good experience and have create their own decommissioning strategy. This report represents in brief an overview of different country's approaches and the Kozloduy NPP decommissioning activity intention in near future and reviews the D and D working document status for 1 and 2 Kozloduy NPP Units decommissioning. Kozloduy NPP D and D task to the moment is to plan the first stage of the decommissioning process - 'The Final Shutdown' and to prepare the working documents for the phase execution. The Final Shutdown of Kozloduy NPP - 1 is the termination of operation of the Units 1 and 2 and the electricity production cessation after their useful life exhaust. In accordance with the legal legislation in Bulgaria only the normal planned termination of operation on units 1 and 2 should be prescribed. The project results concern the initial condition of the equipment and systems, their preparation and sequence for defueling, decontamination and dismantling. A plan for activities' organization for D and D and Complex Characterization of the Site under consideration will contain the following documents: 1. Time-schedule for the sequence of activities during the stages of the Final Shutdown and Safe Enclosure preparation. Technical project for organization of work related to Final Shutdown; 2. Complex Characterization Programme for a condition investigation of the Units 1 and 2 equipment and systems. 3. Technical project for design modifications and dismantling of equipment and systems which violate the radiation and nuclear safety during the Final Shutdown

KONTEC 2009. Report about the 9th International Symposium on ''Conditioning of radioactive operational and decommissioning wastes''

International Nuclear Information System (INIS)

Anon.

2009-01-01

''Kontec 2009'' was organized in Dresden on April 15-17, 2009. For the 8 th time, this established international meeting covered the subjects of ''Conditioning of Radioactive Operational and Decommissioning Wastes'' and ''Decommissioning and Dismantling of Nuclear Facilities'' and the R and D Status Report delivered by the German Federal Ministry for Education and Research on this key topic. Some 790 participants from 13 countries heard and discussed the contributions to the three-day meeting. The program of the symposium comprised plenary sessions dealing with these 4 key subjects: Disposal of Radioactive Residues from Nuclear Facilities' Operation and Decommissioning, Decommissioning and Dismantling of Nuclear Facilities, Facilities and Systems for the Conditioning of Operational and Decommissioning Wastes, Transport, Interim and Final Storage of Non-heat Generating Wastes (i.e. Konrad). The sessions were supplemented by poster sessions and selected short presentations under the heading of ''Kontec Direct.'' (orig.)

Mock-up-CZ: dismantling of the experiment - Geotechnical results

International Nuclear Information System (INIS)

Svoboda, J.; Vasicek, R.

2010-01-01

Document available in extended abstract form only. The issue of the disposal of radioactive waste is one of the most pressing challenges of our age, for which, in most countries, the deep repository concept is generally considered to be the most suitable final solution. In order to make such a repository both safe and reliable, intensive research is underway worldwide. The construction of physical models is one approach to the study of the engineered barriers for deep geological repositories; one such experiment, Mock-Up-CZ, has been performed at the Centre of Experimental Geotechnics, CTU in Prague. The Mock-Up-CZ experiment simulated the vertical placement of a container with radioactive waste, an approach that is in line with the Swedish KBS-3 system. The physical model consisted of a barrier made up of bentonite blocks, powdered bentonite backfill, a heater and hydration and monitoring systems. The whole experiment was enclosed in a cylindrical box, whose construction was able to withstand high pressure due to bentonite swelling. A number of sensors (monitoring changes in temperature, pressure and moisture) were placed inside the bentonite barrier. The basic material used in the experiment consisted of a mixture of Czech bentonite from the Rokle deposit (85%), quartz sand (10%) and graphite (5%). The first phase of the experiment commenced on 7 May 2002, during which the heater was switched on, with no water input. After 6 months the second phase commenced in which water was introduced through the hydration system. This phase ended on 2nd January 2006 when the heater was switched off. After allowing time for cooling, the dismantling phase commenced (30 January 2006). After a further one and a half months (17 March 2006) the dismantling of the experimental vessel was completed. Post-decommissioning analysis continued until the end of 2007. Dismantling and post-decommissioning analysis were carried out according to a very detailed plan which included not only

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

International Nuclear Information System (INIS)

Horton, H.L.

1985-01-01

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

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

International Nuclear Information System (INIS)

Iguchi, Yukihiro; Kato, Masami

2009-01-01

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

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

International Nuclear Information System (INIS)

Meyer, Bettina

2012-01-01

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

Experience with Dismantling of the Analytic Cell in the JRTF Decommissioning Program

International Nuclear Information System (INIS)

Annoh, Akio; Nemoto, Koichi; Tajiri, Hideo; Saito, Keiichiro; Miyajima, Kazutoshi; Myodo, Masato

2003-01-01

The analytic cell was mainly used for process control analysis of the reprocessing process and for the measurement of fuel burn up ratio in JAERI's Reprocessing Test Facility (JRTF). The analytic cell was a heavy shielded one and equipped with a conveyor. The cell was alpha and beta(gamma)contaminated. For dismantling of analytic cells, it is very important to establish a method to remove the heavy shield safely and reduce the exposure. At first, a green house was set up to prevent the spread out of contamination, and next, the analytic cell was dismantled. Depending on the contamination condition, the workers wore protective suits such as air ventilated-suits for prevention of internal exposure and vinyl chloride aprons, lead aprons in order to reduce external exposure. From the work carried out, various data such as needed manpower for the activities, the collective dose of workers by external exposure, the amount of radioactive wastes and the relation between the weight of the shield and its dismantling efficiency were obtained and input for the database. The method of dismantling and the experience with the dismantling of the analytic cell in the JRTF, carried out during 2001 and 2002, are described in this paper

Prefiltration of gaseous effluents in plant dismantling

International Nuclear Information System (INIS)

Pilot, G.; Pourprix, M.

1991-01-01

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

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

International Nuclear Information System (INIS)

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

1991-01-01

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

Decommissioning and dismantling reactors and managing waste

International Nuclear Information System (INIS)

Bensoussan, E.; Reicher-Fournel, N.

2005-01-01

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

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

International Nuclear Information System (INIS)

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

2014-01-01

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

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

International Nuclear Information System (INIS)

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

1995-01-01

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

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

International Nuclear Information System (INIS)

Pradoura, F.

2009-01-01

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

Chemical Decontamination of Metallic Waste from Uranium Conversion Plant Dismantling

International Nuclear Information System (INIS)

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

2005-01-01

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

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

International Nuclear Information System (INIS)

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

1999-01-01

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

Development and evaluation of temporary placement and conveyance operation simulation system using augmented reality

Energy Technology Data Exchange (ETDEWEB)

Yan, Weida; Aoyama, Shuhei; Ishii, Hirotake; Shimoda, Hiroshi [Graduate School of Energy Science, Kyoto University, Kyoto (Japan); Sang, Tran T.; Inge, Solhang Lars [AR Lab, Halden (Norway); Lygren, Toppe Aleksander; Terje, Johnsen [Institute for Energy Technolog, Halden (Norway); Izumi, Masanori [Fugen Decommissioning Engineering Center, Japan Atomic Energy Agency, Fukui (Japan)

2012-06-15

When decommissioning a nuclear power plant, it is difficult to make an appropriate plan to ensure sufficient space for temporary placement and conveyance operations of dismantling targets. This paper describes a system to support temporary placement and conveyance operations using augmented reality (AR). The system employs a laser range scanner to measure the three-dimensional (3D) information of the environment and a dismantling target to produce 3D surface polygon models. Then, the operator simulates temporary placement and conveyance operations using the system by manipulating the obtained 3D model of the dismantling target in the work field. Referring to the obtained 3D model of the environment, a possible collision between the dismantling target and the environment is detectable. Using AR, the collision position is presented intuitively. After field workers evaluated this system, the authors concluded that the system is feasible and acceptable to verify whether spaces for passage and temporary storage are sufficient for temporary placement and conveyance operations. For practical use in the future, some new functions must be added to improve the system. For example, it must be possible for multiple workers to use the system simultaneously by sharing the view of dismantling work.

Development and evaluation of temporary placement and conveyance operation simulation system using augmented reality

International Nuclear Information System (INIS)

Yan, Weida; Aoyama, Shuhei; Ishii, Hirotake; Shimoda, Hiroshi; Sang, Tran T.; Inge, Solhang Lars; Lygren, Toppe Aleksander; Terje, Johnsen; Izumi, Masanori

2012-01-01

When decommissioning a nuclear power plant, it is difficult to make an appropriate plan to ensure sufficient space for temporary placement and conveyance operations of dismantling targets. This paper describes a system to support temporary placement and conveyance operations using augmented reality (AR). The system employs a laser range scanner to measure the three-dimensional (3D) information of the environment and a dismantling target to produce 3D surface polygon models. Then, the operator simulates temporary placement and conveyance operations using the system by manipulating the obtained 3D model of the dismantling target in the work field. Referring to the obtained 3D model of the environment, a possible collision between the dismantling target and the environment is detectable. Using AR, the collision position is presented intuitively. After field workers evaluated this system, the authors concluded that the system is feasible and acceptable to verify whether spaces for passage and temporary storage are sufficient for temporary placement and conveyance operations. For practical use in the future, some new functions must be added to improve the system. For example, it must be possible for multiple workers to use the system simultaneously by sharing the view of dismantling work.

Deregulation in the field of decommissioning and dismantling of nuclear facilities

International Nuclear Information System (INIS)

Kurz, A.

1994-05-01

The report comprises two articles covering current topics of the decommissioning and dismantling of nuclear facilities. In the first article written by Kurz, the legal standards are listed together with conclusions and proposals regarding their implementation for the further development of this field of law. The article by Baumgaertel is aimed at evaluating the regulations governing nuclear technology as regards their applicability to the decommissioning and dismantling of nuclear facilities. These articles shall contribute to the discussions taking place in this field at the moment. As a result, an appropriate and project-specific application of the legal provisions and not legally binding (technical) regulations in the field of nuclear technology (deregulation) in the licensing procedures required for the decommissioning and dismantling of nuclear facilities is requested by the authors. (orig.) [de

Nuclear safety training program (NSTP) for dismantling

International Nuclear Information System (INIS)

Cretskens, Pieter; Lenie, Koen; Mulier, Guido

2014-01-01

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

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

Science.gov (United States)

Hamrick, Cassie; Byma, Christine

2017-01-01

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

DIRECT DISMANTLING OF REPROCESSING PLANT CELLS THE EUREX PLANT EXPERIENCEe2d12c

International Nuclear Information System (INIS)

Gili, M.; Troiani, F.; Risoluti, P.

2003-01-01

After finishing the reprocessing campaigns in 1970-1983, the EUREX pilot reprocessing plant of ENEA Saluggia Research Center started into a new phase, aiming to materials and irradiated fuel systemation and radioactive wastes conditioning. In 1997 the project ''CORA'' for a vitrification plant for the high and intermediate liquid radioactive wastes started. The ''CORA'' plant will be hosted in some dismantled cells of the EUREX plant, reusing many of the EUREX plant auxiliary systems, duly refurbished, saving money and construction time and avoiding a new nuclear building in the site. Two of the cells that will be reused were part of the EUREX chemical process (solvent recovery and 2nd extraction cycle) and the components were obviously internally contaminated. In 2000 the direct (hands-on) dismantling of one of them started and has been completed in summer 2002; the second one will be dismantled in the next year and then the ''CORA'' plant will be assembled inside the cells. Special care w as taken to avoid spread of contamination in the cells, where ''CORA'' installation activities will start in the next years, during the dismantling process The analysis of data and results collected during the dismantling of the first cell shows that direct dismantling can be achieved with careful choice of tools, procedures and techniques, to reduce volumes of wastes to be disposed and radiological burden

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

International Nuclear Information System (INIS)

2008-01-01

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

Evaluation formulas of manpower needs for dismantling of equipments in uranium refining and conversion plant

International Nuclear Information System (INIS)

Izumo, Sari; Usui, Hideo; Kubota, Shintaro; Tachibana, Mitsuo; Kawagoshi, Hiroshi; Tokuyasu, Takashi; Takahashi, Nobuo; Morimoto, Yasuyuki; Tanaka, Yoshio; Sugitsue, Noritake

2014-07-01

Japan Atomic Energy Agency has developed PROject management data evaluation code for DIsmantling Activities (PRODIA) to make an efficient decommissioning for nuclear facilities. PRODIA is a source code which provides estimated value such as manpower needs, costs, etc., for dismantling by evaluation formulas according to the type of nuclear facility. Evaluation formulas of manpower needs for dismantling of equipments about reprocessed uranium conversion in Uranium Refining and Conversion Plant (URCP) have been developed in this report. In the result, evaluation formulas of manpower needs for dismantling of equipment were derived based on the classifications of equipment's functions or work items. These evaluation formulas are widely applicable to the estimation of the manpower needs for dismantling the other nuclear facilities, in particular uranium handling facilities. It was confirmed that some of these evaluation formulas with the same applicable condition could be unified to some inclusive evaluation formulas. It turned out that all steel equipment contaminated by uranium could be evaluated by one evaluation formula. (author)

48 CFR 52.249-3 - Termination for Convenience of the Government (Dismantling, Demolition, or Removal of Improvements).

Science.gov (United States)

2010-10-01

... Convenience of the Government (Dismantling, Demolition, or Removal of Improvements). 52.249-3 Section 52.249-3... Convenience of the Government (Dismantling, Demolition, or Removal of Improvements). As prescribed in 49.502(b)(2), insert the following clause: Termination for Convenience of the Government (Dismantling...

LEP Dismantling - a first Step into New Era

CERN Multimedia

2000-01-01

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

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

Science.gov (United States)

2010-10-01

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

Atomic Energy Commission (CEA) dismantling experience review and perspectives

International Nuclear Information System (INIS)

Barre, J.Y.

1992-01-01

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

Method of dismantling nuclear fuel elements

International Nuclear Information System (INIS)

Adams, G.J.

1983-01-01

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

Dismantling of nuclear facilities: the industrial know-how; Demantelement des installations nucleaires: les voies de la maitrise industrielle

Energy Technology Data Exchange (ETDEWEB)

Lellament, R. [Societe Francaise d' Energie Nucleaire (SFEN), Groupe de Reflexion Energie/Environnement, 75 - Paris (France)

2004-11-01

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

Deliberated opinion of the Environment Authority concerning the dismantling of the Ulysse reactor (CEA Saclay)

International Nuclear Information System (INIS)

2010-01-01

As the Ulysse reactor of Saclay is about to be dismantled, this report discusses the content of a request made by the CEA to definitely stop and dismantle this reactor. After having recalled the origin of this dismantling project and its regulatory framework, it describes the actual works which are planned, and outlines the main challenges to be faced. It discusses the content of the environmental report or impact study, notably the analysis of the initial condition, the analysis of direct and indirect effects of the project on the environment and health, and of the envisaged measures (waste management, liquid and gaseous effluent management, risk management, radiological exposure of workers in charge of this dismantling, and transports). Recommendations are formulated for a rewriting of the provided documents

Management system information of characterization of the dismantling project of Jose Cabrera

International Nuclear Information System (INIS)

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

2011-01-01

In the proposed dismantling and decommissioning of the Jose Cabrera NPP is designed and implemented a database of physical and radiological inventory, which provides a powerful tool to optimize the storage, monitoring and control of the characterization data. The database is a useful and reliable management system characterization information that facilitates access and information processing, and ensures their integrity and traceability along of the dismantling project.

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

International Nuclear Information System (INIS)

Kim, Young Jae; Cheon, Seong Whun

2007-10-01

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

State of dismantling of reactor facilities (JPDR) in Tokai Research Establishment, Japan Atomic Energy Research Institute (fiscal year 1986)

International Nuclear Information System (INIS)

1987-01-01

As to this dismantling work, the contents of the notice on the dismantling and the policy of administration offices to deal with it were reported to the Nuclear Safety Commission beforehand, and after the approval was obtained, it has been executed. Based on the talk of the chairman of Nuclear Safety Commission on January 6, 1983, the state of dismantling is reported. In fiscal year 1986, the second stage dismantling was begun in December, and it was confirmed that the works were carried out safety. In order to ensure the place required for dismantling and removing in-core structures and the pressure vessel, the pressure vessel upper cover and its heat insulator were removed from the third story of the containment vessel. A part of the facilities installed on the second and third stories of the containment vessel was also dismantled and removed. In order to utilize as the place for the temporary preservation and decontamination of dismantled things, a part of the facilities installed in the dump condenser building was dismantled and removed. The control building was reconstructed for smoothly carrying out the entrance control of workers. 36 spent fuel assemblies were carried away for reprocessing. The exposure dose of workers was below the detectable limit of film badges. The dismantled wastes were about 171 t of metals and 34 t of concrete. (Kako, I.)

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

International Nuclear Information System (INIS)

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

1998-01-01

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

International Cooperation for the Dismantling of Chooz A Reactor Pressure Vessel

International Nuclear Information System (INIS)

Grenouillet, J.J.; Posivak, E.

2009-01-01

Chooz A is the first PWR that is being decommissioned in France. The main issue that is conditioning the success of the project is the Reactor Pressure Vessel (RPV) and Reactor Vessel Internals (RVI) segmentation. Whereas Chooz A is the first and unique RPV and RVI being dismantled in France, there are many similar experiences available in the world. Thus the project team was eager to cooperate with other teams facing or being faced with the same issue. A cooperation programme was established in two separate ways: - Benefiting from experience feedback from completed RPV and RVI dismantling projects, - Looking for synergy with future RPV dismantling projects for activities such as segmentation tools design, qualification and manufacturing for example. This paper describes the implementation of this programme and how the outcome of the cooperation was used for the implementation of Chooz-A RPV and RVI segmentation project. It shows also the limits of such a cooperation. (authors)

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

International Nuclear Information System (INIS)

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

1994-01-01

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

A study of internal dosimetry of Am-241 and Sr-90 by dismantling of a nuclear installation; Eine Fallstudie zur internen Dosimetrie von Am-241 und Sr-90 bei Rueckbau einer kerntechnischen Anlage

Energy Technology Data Exchange (ETDEWEB)

Froning, M.; Hill, P. [Forschungszentrum Juelich GmbH (Germany). Geschaeftsbereich Sicherheit und Strahlenschutz

2016-07-01

During dismantling operation in former nuclear facility routine incorporation monitoring had been part of the safety measures. For an occupational radiation worker positive measurements results for {sup 241}Am, {sup 90}Sr and {sup 137}Cs were obtained after the end of the working period. Follow up monitoring had been performed assessing urine and faeces samples for {sup 241}Am and {sup 90}Sr as well as in-vivo measurements for {sup 137}Cs. Ingestion could be proven as incorporation path. The internal dose assessment according to GMBl 2007{sup [1]} finally yielded internal dose at 13 μSv.

Final storage of radioactive waste; Endlagerung radioaktiver Abfaelle

Energy Technology Data Exchange (ETDEWEB)

Ziehm, Cornelia [Redaktion ZNER, Bochum (Germany)

2015-07-15

As explained in the present article, operators of nuclear power plants are responsible for the safe final disposal of the radioactive wastes they produce on the strength of the polluter pays principle. To shift the burden of responsibility for safe disposal to society as a whole would violate this principle and is therefore not possible. The polluter pays principle follows from more general principles of the fair distribution of benefits and burdens. Instances of its implementation are to be found in the national Atomic Energy Law as well as in the European Radioactive Waste and Spent Fuel Management Directive. The polluters in this case are in particular responsible for financing the installation and operation of final disposal sites. The reserves accumulated so far for the decommissioning and dismantling of nuclear power plants and disposal of radioactive wastes, including the installation and operation of final disposal sites, should be transferred to a public-law fund. This fund should be supplemented by the polluters to cover further foreseeable costs not covered by the reserves accumulated so far, including a realistic cost increase factor, appropriate risk reserves as well as the costs of the site selection procedure and a share in the costs for the safe closure of the final disposal sites of Morsleben and Asse II. This would merely be implementing in the sphere of atomic law that has long been standard practice in other areas of environmental law involving environmental hazards.

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

International Nuclear Information System (INIS)

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

1998-01-01

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

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.)

A methodology to simulate the cutting process for a nuclear dismantling simulation based on a digital manufacturing platform

International Nuclear Information System (INIS)

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

2017-01-01

Highlights: • Goal is to provide existing tech. with cutting function handling dismantling process. • Proposed tech. can handle various cutting situations in the dismantlement activities. • Proposed tech. can be implemented in existing graphical process simulation software. • Simulation results have demonstrated that the proposed technology achieves its goal. • Proposed tech. enlarges application of graphic simulation into dismantlement activity. - Abstract: This study proposes a methodology to simulate the cutting process in a digital manufacturing platform for the flexible planning of nuclear facility decommissioning. During the planning phase of decommissioning, visualization and verification using process simulation can be powerful tools for the flexible planning of the dismantling process of highly radioactive, large and complex nuclear facilities. However, existing research and commercial solutions are not sufficient for such a situation because complete segmented digital models for the dismantling objects such as the reactor vessel, internal assembly, and closure head must be prepared before the process simulation. The preparation work has significantly impeded the broad application of process simulation due to the complexity and workload. The methodology of process simulation proposed in this paper can flexibly handle various dismantling processes including repetitive object cuttings over heavy and complex structures using a digital manufacturing platform. The proposed methodology, which is applied to dismantling scenarios of a Korean nuclear power plant in this paper, is expected to reduce the complexity and workload of nuclear dismantling simulations.

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

International Nuclear Information System (INIS)

Field, D.; Mizen, K.

2013-01-01

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

Present status of refining and conversion facility dismantling. Progress in latter half of 2010FY

International Nuclear Information System (INIS)

Kado, Kazumi; Sugitsue, Noritake; Morimoto, Yasuyuki; Ikegami, Sohei; Tanaka, Yoshio; Takahashi, Nobuo; Tokuyasu, Takashi

2011-09-01

The Refining and Conversion Facility located in the Ningyo-toge Environmental Engineering Center had the natural uranium conversion process and reprocessed uranium conversion process. The construction of this facility was started in 1979 and completed in October 1981. Dismantling of equipments in radiation controlled area of this facility was started from 2008. Equipments in radiation controlled area (excluding ventilating equipment and liquid waste treatment equipment) will be dismantled by the 2011 fiscal year, and ventilating equipment and liquid waste treatment equipment will be dismantled by the 2014 fiscal year. This report describes the master plan of this decommissioning and shows as the progress in latter half year of 2010FY, the actual time schedule, the method of decommissioning, the decommissioning progress appearance with photographs, work rates of each room / each worker class, and the quantity of dismantled materials and secondary wastes. (author)

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

International Nuclear Information System (INIS)

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

1993-01-01

A systems analysis of the radiation safety makes possible an ad hoc determination of the elements forming the system, as well as the establishment of the characteristics of their interaction with radiation-effect factors. Here the authors will present part of the hierarchical analysis procedure, consisting in general of four separate procedures. The purpose is to investigate and analyze the mean and stable (on the average) indices of radiation safety, within the framework of alternative mathematical models of dismantling the power-plant equipment of a nuclear power station. The following three of the four procedures are discussed: (1) simulated projection, of the processing of radioactive waste; (2) analysis of the redistribution of radionuclides during the industrial cycle of waste treatment; (3) planning the collective dose load during the dismantling operation. Within the framework of the first of these procedures, the solutions to the problem of simulating a waste-treatment operation of maximum efficiency are analyzed. This analysis is based on the use of a data base for the parameters of the installations, assemblies, and equipment, enabling the integration of these in a simulation of a complex automated facility. The results were visualized in an AUTOCAD-10 medium using a graphical data base containing an explanation of the rooms

Stage 2: dismantling of reactor case of the experimental F.B.R. Rapsodie

International Nuclear Information System (INIS)

Roger, J.

1994-01-01

This document defines the main objectives of stage 2 dismantling of the Rapsodie experimental fast neutron reactor and specifies its time schedule. The work already in progress consists in containing the reactor vessel and its internal equipment, as well as the neutron protection concrete, inside the two leak-tight barriers, and in dismantling all the systems and equipment systems contaminated by sodium. This work, which includes the destruction of 37 metric tons of contaminated sodium from the primary system, was begun in 1987 and will be completed in 1994. The duration of the waiting period for complete dismantling (stage 3) has not been defined. However, the containment and monitoring means implemented should allow a safe waiting period of several decades. (author). 4 figs

Reinforcement course 2013. Challenges at the operation end of nuclear power plants

International Nuclear Information System (INIS)

Rey, Matthias

2014-01-01

The reinforcement course 2013 of the Nuclear Forum in Switzerland dedicated itself to the question, of which challenges are implicated by decommissioning and dismantling nuclear power plants. The course has been divided into 4 blocks, discussing concepts regarding decommissioning, special points such as organisational or psychological aspects as well as juridical and practical questions. Around 140 persons accepted the invitation of the committee for educational questions under the patronage of Urs Weidmann, head of the nuclear power plant Beznau. Altogether 17 presentations dealt with the following topics: 'Strategies and Steps of Decommissioning' by Roger Lundmark, 'Decommissioning from the Perspective of the Swiss Regulatory Authority' by Hannes Haenggi, 'Operating Period Management Using the Example of the Nuclear Power Plant Leibstadt' by Johannis Noeggerath, 'Questions and Concepts from the Perspective of a Nuclear Power Plant Operator' by Roland Schmidiger, 'Decommissioning of nuclear facilities in the UK' by Andrew Munro, 'Practical experiences of transferring nuclear power plants from operating to out of operation' by Gerd Reinstrom, 'Dismantling of Nuclear Facilities: From the Pilot Scheme to Industrialized Disassembling' by Anke Traichel and Thomas Seipolt, 'Organisational challenges: From Decommissioning Strategy to Decommissioning Targets' by Michael Kruse, Anton von Gunten, Julia Heizinger, Joerg Sokoll, 'Knowing That and Knowing How - Motivational Aspects of Safety-Related Knowledge Management for the Post-Operational phase and dismantling' by Frank Ritz, 'The Juridical Frame of Decommissioning' by Peter Koch, 'The Path to the Decommissioning Order and its Guidelines Ensi-G17' by Torsten Krietsch, 'Requirements for a Safe and Economical Decommissioning From the Perspective of the Operator' by Anton Von Gunten, Michael Kruse, Thomas Herren, Erwin Neukaeter, Mario Radke and Anton Schegg, 'Evaluation of Activation Distribution in a Nuclear Power Plant

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

International Nuclear Information System (INIS)

2016-01-01

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

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

International Nuclear Information System (INIS)

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

2002-01-01

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

Visualization of a dismantling environment for an evaluation of a worker's dose during the decommissioning of KRR-1 and 2

International Nuclear Information System (INIS)

Park, Hee Seong; Kim, Sung Kyun; Lee, Kune Woo; Jung, Chong Hun; Jin, Seong Il

2008-01-01

The purpose of this paper is to provide a basis for an optimization of a dismantling process of a research reactor and nuclear facility. An optimization of a dismantling process should be at the beginning of a study for an evaluation of the radioactivity inventory and the safety of the workers. Many countries have conducted an optimization to achieve a shortened dismantling schedule, a reduction of the amount of waste, and cut down on the decommissioning by using computer graphics such as animation, simulation, and virtual reality. In the present study, we propose methods for identifying the existence of radioactivity which is contained in the dismantled objects and for evaluating a worker's dose through a simulation. To evaluate a worker's external dose under a virtual dismantling environment generated by computer graphics, the shape of the thermal column horizontal door was created by 3D CAD and the radiation dose surrounding the door was calculated by using MCNP-4C. An animation that can demonstrate a dismantling procedure according to a dismantling scenario was produced. For matching the radiation dose, which was calculated by MCNP-4C with an area where workers are dismantling a door, a simulation module was developed which could show a worker's external dose in real-time. The result from the distribution of the radioactivity enables us to specify where the most contaminated part of the dismantling objects is. In the animation, a virtual worker demonstrated a dismantling activity procedure as a chosen scenario. In the simulation, a worker's exposure dose rate in real-time has been evaluated

Preliminary dismantling for the decommissioning of nuclear licensed facilities at the CEA Centre in Fontenay aux Roses

International Nuclear Information System (INIS)

Estivie, D.; Bohar, M.P.; Jeanjacques, M.; Binet, C.

2008-01-01

Under the perimeter modification programme for the Nuclear Licensed Facilities (NLFs) of the French Atomic Energy Commission centre at Fontenay aux Roses (CEN-FAR), preliminary dismantling work proved necessary to decommission the buildings outside the nuclear perimeter and create interim storage areas for waste packages. This summary describes the dismantling of Buildings 07, 53 and 91/54, which are the most representative of the preliminary dismantling work. (author)

Decommissioning Planning during the Operation of the Loviisa NPP. Planning, Management and Organizational Aspects

Energy Technology Data Exchange (ETDEWEB)

Tuunanen, J. P.; Eurajoki, T. E.E., [Fortum Power and Heat Ltd, Nuclear Waste Espoo (Finland)

2013-08-15

The first decommissioning plan for Loviisa nuclear power plant was written already in 1980's, when the plant had just started operation. The plan has been updated in 5-6 years intervals and this work still continues towards the final decommissioning plan. The decommissioning plan is based on immediate dismantling option and final disposal of decommissioning waste to the extension of the on site final disposal facility for low and intermediate level waste. The decommissioning planning has been organized as an independent project, which is realised in close cooperation with Fortum's research programme on radioactive waste management. The plant personnel are involved in the planning work through providing operating experience on contamination and activation of systems, structures and components. Later in the decommissioning phase the plant personnel will form the main part of the decommissioning organization. (author)

Expertise of the Oeko-Institute on the application to obtain permission to partially dismantle the Niederaichbach nuclear power plant

International Nuclear Information System (INIS)

1985-01-01

This expertise gives an overview on the problems associated with the decommissioning and dismantling of the Niederaichbach nuclear power plant, considering technical and legal aspects. It wants to prove that the dismantling of this reactor cannot serve as evidence to prove the general feasibility of reactor dismantling. Much space is dedicated to the discussion about where the borderline should be drawn between radioactive and non-radioactive materials according to the ordinance on radiation protection. The reasons for rejecting the partial dismantling application are given. (DG) [de

Cost effective decommissioning and dismantling of nuclear power plants

International Nuclear Information System (INIS)

Wasinger, Karl

2012-01-01

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

Dismantling Racial and Hegemonic Boundaries for an Inclusive ...

African Journals Online (AJOL)

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

Method and apparatus for dismantling mechanical anchors

Energy Technology Data Exchange (ETDEWEB)

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

1982-01-01

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

Temperature Buffer Test. Final THM modelling

Energy Technology Data Exchange (ETDEWEB)

Aakesson, Mattias; Malmberg, Daniel; Boergesson, Lennart; Hernelind, Jan [Clay Technology AB, Lund (Sweden); Ledesma, Alberto; Jacinto, Abel [UPC, Universitat Politecnica de Catalunya, Barcelona (Spain)

2012-01-15

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 only, whereas the upper heater was surrounded by a composite barrier, with a sand shield between the heater and the bentonite. The test was dismantled and sampled during the winter of 2009/2010. This report presents the final THM modelling which was resumed subsequent to the dismantling operation. The main part of this work has been numerical modelling of the field test. Three different modelling teams have presented several model cases for different geometries and different degree of process complexity. Two different numerical codes, Code{sub B}right and Abaqus, have been used. The modelling performed by UPC-Cimne using Code{sub B}right, has been divided in three subtasks: i) analysis of the response observed in the lower part of the test, by inclusion of a number of considerations: (a) the use of the Barcelona Expansive Model for MX-80 bentonite; (b) updated parameters in the vapour diffusive flow term; (c) the use of a non-conventional water retention curve for MX-80 at high temperature; ii) assessment of a possible relation between the cracks observed in the bentonite blocks in the upper part of TBT, and the cycles of suction and stresses registered in that zone at the start of the experiment; and iii) analysis of the performance, observations and interpretation of the entire test. It was however not possible to carry out a full THM analysis until the end of the test due to

Temperature Buffer Test. Final THM modelling

International Nuclear Information System (INIS)

Aakesson, Mattias; Malmberg, Daniel; Boergesson, Lennart; Hernelind, Jan; Ledesma, Alberto; Jacinto, Abel

2012-01-01

The Temperature Buffer Test (TBT) is a joint project between SKB/ANDRA and supported by ENRESA (modelling) and DBE (instrumentation), which aims at improving the understanding and to model the thermo-hydro-mechanical behavior of buffers made of swelling clay submitted to high temperatures (over 100 deg C) during the water saturation process. The test has been carried out in a KBS-3 deposition hole at Aespoe HRL. It was installed during the spring of 2003. Two heaters (3 m long, 0.6 m diameter) and two buffer arrangements have been investigated: the lower heater was surrounded by bentonite only, whereas the upper heater was surrounded by a composite barrier, with a sand shield between the heater and the bentonite. The test was dismantled and sampled during the winter of 2009/2010. This report presents the final THM modelling which was resumed subsequent to the dismantling operation. The main part of this work has been numerical modelling of the field test. Three different modelling teams have presented several model cases for different geometries and different degree of process complexity. Two different numerical codes, Code B right and Abaqus, have been used. The modelling performed by UPC-Cimne using Code B right, has been divided in three subtasks: i) analysis of the response observed in the lower part of the test, by inclusion of a number of considerations: (a) the use of the Barcelona Expansive Model for MX-80 bentonite; (b) updated parameters in the vapour diffusive flow term; (c) the use of a non-conventional water retention curve for MX-80 at high temperature; ii) assessment of a possible relation between the cracks observed in the bentonite blocks in the upper part of TBT, and the cycles of suction and stresses registered in that zone at the start of the experiment; and iii) analysis of the performance, observations and interpretation of the entire test. It was however not possible to carry out a full THM analysis until the end of the test due to

For a public management of funds dedicated to nuclear dismantling: the TESEN (fund for the Energy transition and a fair phasing out nuclear), and its assignment to the financing of energy transition

International Nuclear Information System (INIS)

Autissier, Isabelle; Germa, Philippe

2013-01-01

The report outlines that the cost of nuclear energy in France is largely under-assessed because of the under-evaluation of the future dismantling of nuclear installations and of the management of radioactive wastes. It outlines that provisions made for this dismantling are insufficient, opaque and very risky. This report proposes the creation of a fund independent from nuclear operators to make pay the actual cost of nuclear energy and reduce the French electrical dependence on this energy, to secure long-term financing to finance the dismantling, to bring the financing for the decades to come to finance energy transition, to finance energy transition at reasonable rates, and to clarify the governance for phasing out nuclear

Shutdown and degradation: Optimization of thermal cutting processes for the dismantling of nuclear facilities. Final report

International Nuclear Information System (INIS)

Schultz, H.; Hammer, G.; Hampe, A.; Homburg, A.

1996-01-01

Cutting processes are required for the dismantling of nuclear facilities which emit only a minimum of contaminated material in the form of shavings, sparks, dust, steam concentrate etc. and equipment which is easy to handle and can be remote controlled. A check of the usual mechanical, thermal and thermo-mechanical cutting procedures showed to what varying extent they are suitable for these tasks. Also the laser beam cutting was able to reduce the material discharge by optimal joints. For the investigation, the plasma cutting and the laser beam cutting were used with the aim of reducing considerably the material discharge by changing the adjust and device setting data for theses cases. The adapting of the speed and the amounts of gas turned out to be effective measures in reducing discharge. Adhesion of metal mass and slag in the joint edge could be achieved with aggressive bearth formation. The expectations made of the project could be fulfilled and process parameters for a pollutant optimised cutting determined. (orig.) [de

Comparison of ship dismantling processes in India and the U.S.

Science.gov (United States)

Ahluwalia, Rashpal S.; Sibal, Pooja; Govindarajulu, Sriram

2004-03-01

This paper compares ship-dismantling processes in India and the U.S. The information for India was collected during an informal visit to the ship dismantling sites in Alang, India. The information for the U.S. was obtained from the MARAD report. For a 10,000-ton passenger ship, the Indian contractor makes a profit of about 24% compared to a loss of about 15% in the U.S. The loss in the US is primarily due to high labor costs, compliance to safety and health regulations and lack of market for used components and scrap metal.

Technicians dismantle the inner section of L3

CERN Multimedia

Laurent Guiraud

2001-01-01

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

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. Copyright © 2013 Elsevier Ltd. All rights reserved.

Dismantling of Irradiation Facility Selfshielded of Investigation Model MPX- γ-25M

International Nuclear Information System (INIS)

Soguero, D.; Rapado, M.; Prieto, E.; Desdin, L.; Guerra, M.; Castillo, J.

2011-01-01

In this paper is described the dismantling a category I selfshielded gamma irradiation facility model MPX - γ - 25M. The following specific objectives were established: a) identify aspects of the insurance contract, human and technical resources b) assess the radiological situation of the process and c) analyze potential radiological extraordinary events in each step of the process, ensuring appropriate responses, based on an evaluation of process safety. The assessment of radiological events can serve as a reference for addressing the process of dismantling other similar irradiators. (Author)

General plan for the partial dismantling of the IRT-Sofia research reactor

Directory of Open Access Journals (Sweden)

Apostolov Tihomir G.

2006-01-01

Full Text Available After the decision of the Bulgarian Government to reconstruct it, the strategy concerning the IRT-Sofia Research Reactor is to partially dismantle the old systems and equipment. The removal of the reactor core and replacement of old equipment will not pose any significant problems. For a more efficient use of existing resources, there is a need for an engineering project which has been already prepared under the title "General Plan for the Partial Dismantling of Equipment at the IRT-Sofia as a Part of the Reconstruction into a Low Power RR".

Advanced robotic remote handling system for reactor dismantlement

International Nuclear Information System (INIS)

Shinohara, Yoshikuni; Usui, Hozumi; Fujii, Yoshio

1991-01-01

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

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

Science.gov (United States)

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

Dismantling the Curriculum in Higher Education

Directory of Open Access Journals (Sweden)

Richard Hall

2016-04-01

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

Evaluation of scheduling problems for the project planning of large-scale projects using the example of nuclear facility dismantling; Evaluation von Schedulingproblemen fuer die Projektplanung von Grossprojekten am Beispiel des kerntechnischen Rueckbaus

Energy Technology Data Exchange (ETDEWEB)

Huebner, Felix; Schellenbaum, Uli; Stuerck, Christian; Gerhards, Patrick; Schultmann, Frank

2017-05-15

The magnitude of widespread nuclear decommissioning and dismantling, regarding deconstruction costs and project duration, exceeds even most of the prominent large-scale projects. The deconstruction costs of one reactor are estimated at several hundred million Euros and the dismantling period for more than a decade. The nuclear power plants built in the 1970s are coming closer to the end of their planned operating lifespan. Therefore, the decommissioning and dismantling of nuclear facilities, which is posing a multitude of challenges to planning and implementation, is becoming more and more relevant. This study describes planning methods for large-scale projects. The goal of this paper is to formulate a project planning problem that appropriately copes with the specific challenges of nuclear deconstruction projects. For this purpose, the requirements for appropriate scheduling methods are presented. Furthermore, a variety of possible scheduling problems are introduced and compared by their specifications and their behaviour. A set of particular scheduling problems including possible extensions and generalisations is assessed in detail. Based on the introduced problems and extensions, a Multi-mode Resource Investment Problem with Tardiness Penalty is chosen to fit the requirements of nuclear facility dismantling. This scheduling problem is then customised and adjusted according to the specific challenges of nuclear deconstruction projects. It can be called a Multi-mode Resource Investment Problem under the consideration of generalized precedence constraints and post-operational costs.

Advanced robotics for decontamination and dismantlement

International Nuclear Information System (INIS)

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

1994-01-01

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

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

International Nuclear Information System (INIS)

2004-01-01

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

Main Results of Updated Decommission Conception of NPPs Operating in Ukraine

International Nuclear Information System (INIS)

Purtov, Oleg; Masko, Alexander; Vasilchenko, Victor

2014-01-01

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

Dismantling the silicon microstrip detector on L3

CERN Multimedia

Laurent Guiraud

2001-01-01

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

Dismantlement and destruction of chemical, nuclear and conventional weapons

International Nuclear Information System (INIS)

Schulte, N.T.

1997-01-01

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

Information Factor Color Revolutions and Modern Technology Dismantling of Political Regimes

Directory of Open Access Journals (Sweden)

Andrey Victorovich Manoylo

2014-01-01

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

Information Factor Color Revolutions and Modern Technology Dismantling of Political Regimes

Directory of Open Access Journals (Sweden)

Andrey Victorovich Manoylo

2014-01-01

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

Utilization of External Capacities as an Integral Component of Concepts for Residues and Dismantling Using the Example of the CARLA Plant. National and International Experiences in Recycling

International Nuclear Information System (INIS)

Kluth, Thomas

2014-01-01

-room. Here, a suspension track blasting equipment was installed along with an inside tube blasting equipment. With this equipment, all tubes starting from a diameter of 20 mm can be decontaminated. Further steps of upgrading are in planning stage. For metals having been processed by melting and for nearly all process wastes licensed release procedures according to paragraph 29 StrlSchV (radiation protection ordinance) are available including established disposal paths. Taking into account several marginal conditions, a decay storage of up to 20 years can be effected for metal ingots at our premises at Krefeld. This, too, is an important contribution to more flexibility and higher efficiency. The CARLA plant fulfills all requirements which are indispensable for a good concept to treat residues. It avoids waste, reduces the waste volume and provides for subsequent recycling of the residues. The licensed capacity of the plant is sufficient to make up for any peak of demand resulting from the present situation. Thus the operators are able to design their dismantling strategies in the plants much more freely. Disassembly works, for example, can be predated into the post-closure phase. Different project steps can be processed parallelly and the whole material logistics in the plant can be optimized. By increased involvement of external capacities like CARLA the challenges of the national dismantling activities over the coming years can be mastered successfully to a large extent. The same applies to the international sector where, however, the sometimes strongly differing framework requirements regarding the situation of the final repository or release options may lead to different key aspects for involving CARLA into the individual projects. In international technological comparison, German dismantling projects doubtlessly take a leading position, however, regarding efficiency there is still room for optimization. An early involvement of qualified service suppliers can help to

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

International Nuclear Information System (INIS)

Chabal, Caroline; Soulabaille, Yves

2016-01-01

preparation for complex dismantling operations. Finally, the perspectives for future applications are mentioned, especially radioactive dose rate and virtual human simulation. (authors)

Present status of refining and conversion facility dismantling. Progress in first half of 2010FY

International Nuclear Information System (INIS)

Kado, Kazumi; Sugitsue, Noritake; Morimoto, Yasuyuki; Ikegami, Sohei; Tanaka, Yoshio; Takahashi, Nobuo; Tokuyasu, Takashi

2011-06-01

The Refining and Conversion Facility located in the Ningyo-toge Environmental Engineering Center had the natural uranium conversion process and reprocessed uranium conversion process. The construction of this facility was started in 1979 and completed in October 1981. Dismantling of equipments in radiation controlled area of this facility was started from 2008, and all equipments in radiation controlled area will be dismantled by the 2011 fiscal year. This report describes the master plan of this decommissioning and shows as the progress in first half year of 2010FY, the actual time schedule, the method of decommissioning, the decommissioning progress appearance with photographs, work rates of each room / each worker class, and the quantity of dismantled materials and secondary wastes. (author)

Present status of refining and conversion facility dismantling. Progress in first half of 2009FY

International Nuclear Information System (INIS)

Kado, Kazumi; Sugitsue, Noritake; Morimoto, Yasuyuki; Ikegami, Sohei; Tanaka, Yoshio; Takahashi, Nobuo; Tokuyasu, Takashi

2010-03-01

The Refining and Conversion Facility located in the Ningyo-toge Environmental Engineering Center had the natural uranium conversion process and reprocessed uranium conversion process. The construction of this facility was started in 1979 and completed in October 1981. Dismantling of equipments in radiation controlled area of this facility was started from 2008, and all equipments in radiation controlled area will be dismantled by the 2011 fiscal year. This report describes the master plan of this decommissioning and shows as the progress in first half year of 2009FY, the actual time schedule, the method of decommissioning, the decommissioning progress appearance with photographs, work rates of each room / each worker class, and the quantity of dismantled materials and secondary wastes. (author)

Present status of refining and conversion facility dismantling. Progress in latter half of 2008FY

International Nuclear Information System (INIS)

Kado, Kazumi; Sugitsue, Noritake; Morimoto, Yasuyuki; Ikegami, Sohei; Takahashi, Nobuo; Tokuyasu, Takashi

2010-01-01

The Refining and Conversion Facility located in the Ningyo-toge Environmental Engineering Center had the natural uranium conversion process and reprocessed uranium conversion process. The construction of this facility was started in 1979 and completed in October 1981. Dismantling of equipments in radiation controlled area of this facility was started from 2008, and all equipments in radiation controlled area will be dismantled by the 2011 fiscal year. This report describes the master plan of this decommissioning and shows as the progress in latter half year of 2008FY, the actual time schedule, the method of decommissioning, the decommissioning progress appearance with photographs, work rates of each room/each worker class, and the quantity of dismantled materials and secondary wastes. (author)

Dismantling of alpha contaminated obsolete installations and glove boxes on the IRMM site in Geel (Belgium)

International Nuclear Information System (INIS)

Cretskens, Pieter; Lenie, Koen; Melis, Gustaaf

2007-01-01

At the Institute for Reference Materials and Measurements (European commission, Joint Research Centre, IRMM) a dismantling campaign of obsolete installations and glove boxes has been carried out in 2005. There were various reasons for their removal. Some large installations did not meet modern safety standards, other installations were worn out and expected to cause a radioactive contamination risk in the future. The main goal was to create as less waste as possible by extensive contamination checks and by decontamination if necessary. For the glove boxes, decontamination was not possible. A controlled area was set up around the installation to be dismantled in order to prevent spreading of contamination from dust and dirt. This was only possible for the 'minor' contaminated installations. The dismantling campaign of the glove boxes was carried out by using tents of two types depending the contamination inside the glove boxes. The most common glove boxes were dismantled in a tent constructed with hard surfaced polycarbonate plates (ventilated cell). For glove boxes with higher contamination, the same principle was used but with a second 'glove box tent' inside (ventilated glove tent). The purpose of this project was to learn from the experience of this campaign which gave the ability to make estimates of future radioactive waste or classic waste that could be expected from dismantled installations. (authors)

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)

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

Energy Technology Data Exchange (ETDEWEB)

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

2013-07-01

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

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

International Nuclear Information System (INIS)

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

2013-01-01

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

Radiological survey techniques for decontamination and dismantlement applications

International Nuclear Information System (INIS)

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

1997-01-01

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

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

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

International Nuclear Information System (INIS)

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

1991-01-01

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

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.

Recycling of concrete generated from Nuclear Power Plant dismantling

International Nuclear Information System (INIS)

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

2013-01-01

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

Dismantling of JPDR reactor internals by underwater plasma arc cutting technique using robotic manipulator

International Nuclear Information System (INIS)

Yokota, M.

1988-01-01

The actual dismantling of JPDR started on December 4, 1986. As of now, equipment that surrounds the reactor has mostly been removed to provide working space in reactor containment prior to the dismantling of reactor internals. Some reactor internals have been successfully dismantled using the underwater arc cutting system with a robotic manipulator during the period of January to March 1988. The cutting system is composed of an underwater plasma arc cutting device and a robotic manipulator. The cut off reactor internals were core spray block, feedwater sparger and stabilizers for fuel upper grid tube. The plasma arc cutting device was developed to dismantle the reactor internals underwater. It mainly consists of a plasma torch, power and gas supply systems for the torch, and by-product treatment systems. It has the cutting ability of 130 mm thickness stainless steel underwater. The robotic manipulator has seven degrees of freedom of movement, enabling it to move in almost the same way as the arm of a human being. The arm of the robot is mounted on a supporting device which is suspended by three chains from the support structure set on a service floor. A plasma torch is griped by the robotic hand; its position to the structure to be cut is controlled from a remote control room, about 100 meters outside the reactor containment

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

International Nuclear Information System (INIS)

Guidice, S.J.; Inlow, R.O.

1995-01-01

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

The conceptual solutions concerning decommissioning and dismantling of Russian civil nuclear powered ships

International Nuclear Information System (INIS)

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

2013-01-01

From 1959 up to 1991 nine civil nuclear powered ships were built in Russia: eight ice-breakers and one lash lighter carrier (cargo ship). At the present time three of them were taking out of service: ice-breaker 'Lenin' is decommissioned as a museum and is set for storage in the port of Murmansk, nuclear ice-breakers 'Arktika' and 'Sibir' are berthing. The ice-breakers carrying rad-wastes appear to be a possible source of radiation contamination of Murmansk region and Kola Bay because the ship long-term storage afloat has the negative effect on hull's structures. As the result of this under the auspices of the Federal Targeted Program 'Nuclear and Radiation Safety of Russia for 2008 and the period until 2015' the conception and projects of decommissioning of nuclear-powered ships are developed by the State corporation Rosatom with the involvement of companies of United Shipbuilding Corporation. In developing the principal provisions of conception of decommissioning and dismantling of icebreakers the technical and economic assessment of dismantling options in ship-repairing enterprises of North-West of Russia was performed. The paper contains description of options, research procedure, analysis of options of decommissioning and dismantling of nuclear ice-breakers, taking into account the principle of optimization of potential radioactive effect to personnel, human population and environment. The report's conclusions contain the recommendations for selection of option for development of nuclear icebreaker decommissioning and dismantling projects. (authors)

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

International Nuclear Information System (INIS)

Andres, Roger

2001-01-01

Full text: The Paul Scherrer Institute (PSI) is a multi-disciplinary research centre for natural sciences and technology. The institute is active in solid-state physics, materials sciences, elementary particle physics, life sciences, nuclear and non-nuclear energy research, and energy-related ecology. PSI develops and operates complex research installations such as nuclear reactors and particle accelerators. These produce ionising radiation and major quantities of radioactive materials. The optimal handling of decommissioning and dismantling projects and radioactive waste treatment at PSI represents a complex management task, and is determined by many parameters that are only partially identical to those in the energy producing industry. Some of the major issues are addressed below. Management: The research community often requires rapid changes of experimental equipment. This necessitates that the four steps of decommissioning, removal, dismantling and conditioning of waste are spatially and temporally separated. The availability of a great scientific knowledge pool is instrumental for innovative solutions for the complex problems encountered. The accessibility of a modem hardware park (instruments, workshops etc.), sophisticated computer systems and modelling know how can facilitate the work considerably. The lack of a dedicated pool of decommissioning funds and the need for rapid response (see above) necessitate flexibility of the decommissioning crew and constant coordination and optimisation of the work packages with the institute's top management. The product of a research centre in general is not a tradable commodity and does not result in a direct return of money. Financial mechanisms such as the accumulation of funds for future liabilities are not an option. Since PSI - as probably most research institutes - is funded on a yearly basis, long term cost optimisations processes are in competition with legitimate short-term research needs. The benefits of

Decommissioning a small glove box

International Nuclear Information System (INIS)

Bond, R.D.; McSherry, K.

1985-11-01

An account is given of dismantling a fuel fabrication glove box using simple tooling. The fissile content of the box was first measured by several non-destructive techniques. After cleaning, the box was dismantled using hand tools and finally packed for disposal. A record of operator radiation doses, the time taken for each stage of the operation and packing information is given. (author)

EDV supported dynamic fire protection concept adaptation during dismantling of nuclear facilities

International Nuclear Information System (INIS)

Mummert, Maxi; Traichel, Anke; Dilger, Matthias

2013-01-01

Fire protection concepts are supposed to be a decision guide for the definition of measures and priorities in fire fighting and fire prevention. In case of reactor dismantling a fire protection concept for the actual status is required. Following the fuel removal from the reactor the protection goals are reduced to the safe confinement of radioactive materials and the restriction of radiation exposure. A dynamic fire protection concept was developed to allow the compliance with the required protection measures with respect to the protection targets. The implementation of the dynamic fire protection concept simplifies the planning of the dismantling steps and to adjust the fire protection measured in the frame of changes in the plant.

The Dismantling of Nuclear Installations in France

International Nuclear Information System (INIS)

Bonnaure, P.

2011-01-01

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

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

International Nuclear Information System (INIS)

Irrek, W.

1996-01-01

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

An Evaluation of Dismantling Scenarios Using a Computer Simulation Technology for KRR-1 and 2

International Nuclear Information System (INIS)

Kim, S.K.; Park, H.S.; Lee, K.W.; Oh, W.Z.; Park, J.H.

2006-01-01

A graphic simulation has been used to design and verify new equipment and has also been expanded to virtual prototyping technology [1∼5]. In the nuclear decommissioning field, this technology has been utilized to validate the design of dismantling processes and to check the interferences and collisions in dismantling scenarios. However, a graphic simulation only provides us with visible result it just provides us with illustrative information of the decommissioning process. A scenario evaluation program has been developed using the computer simulation technology to create an efficient decommissioning plan. In the D and D planning stage, it is important that the scenarios are evaluated from a engineering point of view because the decommissioning work has to be executed economically and safely following the best scenarios. Therefore, we need several modules to evaluate scenarios. We composed the systems like this: 1. Decommissioning DB module for managing the decommissioning activity information (nuclear facility data, worker's data, radioactive inventory date, etc.). Dismantling process evaluation module 3. Visualization module for a radioactive inventory and a dismantling process using 3D CAD and virtual reality technology. 4. Analysis module for the evaluation results of a dismantling process. The evaluation module's capabilities produce a dismantling schedule, quantify radioactive waste, visualize a radioactive inventory, estimate a decommissioning cost, estimate a worker's exposure, and check for interference/collisions. After using the simulation results, the expert ranking system to evaluate scenarios for economics and worker's safety are implemented. The expert ranking system is a powerful and flexible decision making process to help set priorities and make the best decisions when both the qualitative and quantitative aspects of a decision need to be considered. By reducing complex decisions to a series of one-on-one comparisons, then synthesizing the

ANCCLI White Paper VI. Which conditions for an influential participation of CLIs and ANCCLI to the territorial and national follow-up of dismantling works

International Nuclear Information System (INIS)

Delalonde, Jean-Claude; Eimer, Michel; Boutin, Dominique

2017-01-01

After a brief presentation of the different phases of nuclear installation dismantling, and a statement about the interest of CLIs (Local information commissions) and ANCCLI (National association of local information commissions and committees), the first part of this white paper addresses the regulatory framework of dismantling, its process, and outlines roles of CLIs and ANCCLI in this process, and remaining issues. It describes the role CLIs already had in issues related to dismantling for different sites (Tricastin, Gard, Monts d'Arree, Saint-Laurent-des-Eaux). A set of proposals is formulated for an influential participation of CLIs and ANCCLI to the national and territorial follow-up of dismantling works. A road-map is proposed for CLIs who want to tackle the dismantling issue. An amendment is proposed for a decree related to the definitive stoppage and dismantling of basic nuclear installations and to subcontracting

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.

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

International Nuclear Information System (INIS)

2008-01-01

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.)

Activation calculations for dismantling - The feedback of a 7 years experience in activation calculations for graphite gas cooled reactors in France

International Nuclear Information System (INIS)

Eid, M.; Nimal, J.C.; Gerat, L.M.

1994-01-01

This is a revision of the past seven years experience in activation calculations for dismantling. It aims at evaluating the experience and at making better understanding to help in decision making during the following phases. Five gas cooled reactors are shutdown and are waiting for the EDF (Electricite De France) dismantling decision. The sixth (BUGEY1) will be shutdown by 1994 and will be waiting a dismantling decision as well. (authors). 3 figs., 3 tabs

Disposition of excess weapons plutonium from dismantled weapons

International Nuclear Information System (INIS)

Jardine, L.J.

1997-01-01

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

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.)

Further retardation could lead to a hold-up of nuclear reactor dismantling; Weitere Verzoegerungen koennten zu einem Stillstand des Kernkraft-Rueckbaus fuehren

Energy Technology Data Exchange (ETDEWEB)

Graf, Konstantin (comp.) [Innovations- und Technologieberatung Altran, Frankfurt am Main (Germany). Bereich Energy and Industry

2015-07-01

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.

Laser dismantling of a glovebox

International Nuclear Information System (INIS)

Johnson, R.; Fender, M.

1985-01-01

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

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

Energy Technology Data Exchange (ETDEWEB)

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

2003-07-01

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

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

International Nuclear Information System (INIS)

Bodin, F.; Saublet, J.C.

1991-01-01

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

Experience relevant to safety obtained from reactor decommissioning operations in the French Atomic Energy Commission

International Nuclear Information System (INIS)

Giraudel, B.; Langlois, G.

1979-01-01

From among the nuclear facilities constructed in France the authors cite eight large reactors, ranging from critical assemblies to power reactors, that have been finally shut-down since 1965. A brief account is given of the way in which the various operations were carried out after the final control rod drop, a distinction being drawn between the shut-down proper and the containment and dismantling work. A description is also given, from the technical and regulatory standpoint, of the final stage attained, and mention is made of French safety arrangements and of the part played by the safety services during decommissioning operations. Among the lessons derived from French experience, the authors mention the completion of operations without any serious safety problems, and with guarantees for the protection of personnel and the population as a whole, by conventional techniques; the advantage of planning decommissioning operations from the very beginning of construction of the facilities; and the importance of filing descriptive documents. In view of the experience gained, the French Atomic Energy Commission has devised internal procedures for facilitating the application of regulations governing the shut-down and decommissioning phases, which are aimed at preserving surveillance procedures similar to those in force during normal operation. (author)

''1995/2010: site drainage and nuclear facilities dismantling program'' result 2001

International Nuclear Information System (INIS)

2001-01-01

A drainage and dismantling planing with the corresponding wastes management, has been decided for the CEA of Fontenay aux roses, in 1995. It will end in 2010. This document presents the main evolutions occurred since october 2000. (A.L.B.)

Decommissioning and dismantling policy in Spain

International Nuclear Information System (INIS)

Landa, J.

2004-01-01

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

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.

Strategies for the disposition of high explosives resulting from dismantlement of nuclear weapons

International Nuclear Information System (INIS)

Pruneda, C.; Humphrey, J.

1993-03-01

Many thousands of pounds of high quality main-charge explosives will result as surplus from the dismantlement of returns from the US nuclear weapons stockpile. The method most often employed for dealing with this surplus explosive is destruction by open burning. However, open burning as a means of treating excess explosives is losing favor because of environmental concerns associated with such an uncontrolled thermal destruction process. Thus, alternative processes for treatment of excess explosives from weapon dismantlement is discussed. These alternatives include: reformulation, crystalline component recovery, chemical conversion of the crystalline component to higher value products which may have civilian or military applications and, when necessary, treatment as waste in an environmentally benign fashion

Sites with nuclear facilities in the state of dismantling and their future from the public perspective

International Nuclear Information System (INIS)

Kretz, Simon Philipp

2015-01-01

The thesis on the public perspective at sites of nuclear facility dismantling covers the following issues: the change of German energy landscapes under social and political points of view, theoretical frame of the work, combination of empirical studies and the theoretical approaches in a space concept, action model and hypotheses on the situation and development in communities with nuclear facilities in the state of dismantling, description of the interviewees, and the empirical results of the interviews.

Application of an automatic yarn dismantler to track changes in cotton fibre properties during processing on a miniature spinning line

CSIR Research Space (South Africa)

Fassihi, A

2014-11-01

Full Text Available . The results obtained on different Upland cottons have clearly demonstrated the practical value of the yarn dismantler in enabling yarns to be automatically dismantled into their constituent fibres, which can then be tested by instrument, such as the AFIS...

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

International Nuclear Information System (INIS)

Leclercq, J.

2003-01-01

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

Declassification of radioactive water from a pool type reactor after nuclear facility dismantling

Science.gov (United States)

Arnal, J. M.; Sancho, M.; García-Fayos, B.; Verdú, G.; Serrano, C.; Ruiz-Martínez, J. T.

2017-09-01

This work is aimed to the treatment of the radioactive water from a dismantled nuclear facility with an experimental pool type reactor. The main objective of the treatment is to declassify the maximum volume of water and thus decrease the volume of radioactive liquid waste to be managed. In a preliminary stage, simulation of treatment by the combination of reverse osmosis (RO) and evaporation have been performed. Predicted results showed that the combination of membrane and evaporation technologies would result in a volume reduction factor higher than 600. The estimated time to complete the treatment was around 650 h (25-30 days). For different economical and organizational reasons which are explained in this paper, the final treatment of the real waste had to be reduced and only evaporation was applied. The volume reduction factor achieved in the real treatment was around 170, and the time spent for treatment was 194 days.

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

International Nuclear Information System (INIS)

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

1997-01-01

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

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

International Nuclear Information System (INIS)

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

1996-01-01

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

Decontamination and dismantlement of Plant 7 at Fernald

International Nuclear Information System (INIS)

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

1994-01-01

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

Quantity assessment of waste in the dismantlement of liquid waste treatment plant and its actual state

International Nuclear Information System (INIS)

Uchiyama, Takafumi; Mitsuhashi, Ishi; Matsumoto, Tetsuo; Morishima, Kayoko; Tanzawa, Tomio

2016-01-01

From the progress of decommissioning project work of Tokyo City University Atomic Energy Research Institute, this paper reports the comparison between the actual amount of the waste generated during dismantlement work at liquid waste treatment facilities and the assessment quantity before starting the dismantlement. The quantity assessment was made on the basis of the installation license application, design specifications, drawings, records, history of use, site investigation results, etc. Since this quantity assessment did not take into account the dismantling contents of reservoir concrete, the assessed quantity of non-radioactive waste (NR waste) did not match the sum of actual NR waste. However, if an actually generated quantity of concrete of radioactive waste was added to the quantity assessment as NR waste, the quantity of actually generated NR waste and that of assessed NR waste were nearly consistent, which verified the validity of this assessment. This method is considered to be able to be utilized in the future quantity assessment of decommissioning work and the like. On the other hand, it was found that the number of drums that were actually stored tended to increase more than the estimated number of drum conversion. In old buildings, it is necessary to take into account the generation of waste other than radioactive materials in the quantity assessment stage and dismantlement stage. (A.O.)

Reinforcement course 2013. Challenges at the operation end of nuclear power plants; Vertiefungskurs 2013. Herausforderungen am Betriebsende von Kernkraftwerken

Energy Technology Data Exchange (ETDEWEB)

Rey, Matthias [Nuklearforum Schweiz/Forum nucleaire suisse, Bern (Switzerland)

2014-03-15

The reinforcement course 2013 of the Nuclear Forum in Switzerland dedicated itself to the question, of which challenges are implicated by decommissioning and dismantling nuclear power plants. The course has been divided into 4 blocks, discussing concepts regarding decommissioning, special points such as organisational or psychological aspects as well as juridical and practical questions. Around 140 persons accepted the invitation of the committee for educational questions under the patronage of Urs Weidmann, head of the nuclear power plant Beznau. Altogether 17 presentations dealt with the following topics: 'Strategies and Steps of Decommissioning' by Roger Lundmark, 'Decommissioning from the Perspective of the Swiss Regulatory Authority' by Hannes Haenggi, 'Operating Period Management Using the Example of the Nuclear Power Plant Leibstadt' by Johannis Noeggerath, 'Questions and Concepts from the Perspective of a Nuclear Power Plant Operator' by Roland Schmidiger, 'Decommissioning of nuclear facilities in the UK' by Andrew Munro, 'Practical experiences of transferring nuclear power plants from operating to out of operation' by Gerd Reinstrom, 'Dismantling of Nuclear Facilities: From the Pilot Scheme to Industrialized Disassembling' by Anke Traichel and Thomas Seipolt, 'Organisational challenges: From Decommissioning Strategy to Decommissioning Targets' by Michael Kruse, Anton von Gunten, Julia Heizinger, Joerg Sokoll, 'Knowing That and Knowing How - Motivational Aspects of Safety-Related Knowledge Management for the Post-Operational phase and dismantling' by Frank Ritz, 'The Juridical Frame of Decommissioning' by Peter Koch, 'The Path to the Decommissioning Order and its Guidelines Ensi-G17' by Torsten Krietsch, 'Requirements for a Safe and Economical Decommissioning From the Perspective of the Operator' by Anton Von Gunten, Michael Kruse, Thomas

Management of activated parts generated during the dismantling of linear accelerators for medical uses

International Nuclear Information System (INIS)

Ortiz, Teresa; Correa, Cristina

2008-01-01

During years 2006-2008 have been carried out to the dismantling of several linear accelerators of medical use in Spain. The two first were in the Hospital of 'La Princesa' in Madrid and in the Hospital 'Santa Creu y Sant Pau' in Barcelona. The disassembling of such was made by technicians of the providing company and of the own hospital, with the advising of experts of the Radiological Protection and Radiophysics Service of such. Technicians of the Radiological Protection Technical Unit (RPU) of ENRESA collaborated in these dismantlings with the objective to determine that pieces could be evacuated conventionally as metallic scraps and which had to be managed as radioactive waste. In the following dismantling the classification of the pieces were carried out by the technicians of the providing company. After that the technicians of the RPU of ENRESA verified this classification and characterized, in detail, the pieces classified as radioactive wasted before their removal. In this paper the activities carried out to classify the pieces and the legal bases in which it leans on, as well as the measures made for the characterization of the materials considered as radioactive waste are described. (author)

Spent Nuclear Fuel (SNF) Cold Vacuum Drying (CVD) Facility Operations Manual; FINAL

International Nuclear Information System (INIS)

IRWIN, J.J.

1999-01-01

This document provides the Operations Manual for the Cold Vacuum Drying Facility (CVDF). The Manual was developed in conjunction with HNF-553, Spent Nuclear Fuel Project Final Safety Analysis Report Annex B-Cold Vacuum Drying Facility. The HNF-SD-SNF-DRD-002, 1999, Cold Vacuum Drying Facility Design Requirements, Rev. 4, and the CVDF Final Design Report. The Operations Manual contains general descriptions of all the process, safety and facility systems in the CVDF, a general CVD operations sequence and references to the CVDF System Design Descriptions (SDDs). This manual has been developed for the SNFP Operations Organization and shall be updated, expanded, and revised in accordance with future design, construction and startup phases of the CVDF until the CVDF final ORR is approved

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

International Nuclear Information System (INIS)

Washer, M.; Cull, M.; Crocker, C.; Ivanov, V.; Shepurev, A.; Khan, B.U.Z.; Lee, M.; Gerchikov, M.

2007-01-01

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)

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

Science.gov (United States)

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

2010-08-01

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

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

International Nuclear Information System (INIS)

Washer, M.; Cull, M.; Crocker, C.; Ivanov, V.; Shepurev, A.; Khan, B.U.Z.; Lee, M.; Gerchikov, M.

2008-01-01

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)

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

International Nuclear Information System (INIS)

Bach, F.W.; Lindemaier, J.; Philipp, E.

1998-01-01

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.) [de

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

International Nuclear Information System (INIS)

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

2013-01-01

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

Change-management. From commercial power operation to post power operation and decommissioning

International Nuclear Information System (INIS)

Wasinger, Karl

2015-01-01

Transition from power generation to decommissioning challenges utilities. Power generation is mainly characterized by a stable working environment and constant workload, decommissioning and dismantling, however, by transformation and change. Also, changing requirements for the workforce's skills challenge the organization and its senior management. Ensuring effective and efficient performance, while maintaining motivation of staff, requires adjustment of management processes as well as of operational organization and human resources management. AREVA has more than 20 years of experience in decommissioning of own nuclear fuel cycle plants in France, as well as of other large plants and power reactors in Germany, the United Kingdom and the US. Therefore, the group has developed and successfully implemented integrated change management processes. The implementation of well-established and proven methods, developed by the productive industry and adjusted to the nuclear regulatory requirements, significantly improves the performance and efficiency of means and methods in use. The AREVA Performance Improvement Process defines concrete approaches to identify and improve potential deficits of productivity in six main areas (decommissioning scenarios and stra-tegies, waste treatment and logistics, operations management, supply chain, regulatory monitoring and controls as well as dismantling operation). Nuclear plant and facility owners around the world benefit from AREVA experts well experienced in execution of large and complex decommissioning projects.

Capacitive tool standoff sensor for dismantlement tasks

International Nuclear Information System (INIS)

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

1996-01-01

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

The dismantling of fast reactors: sodium processing

International Nuclear Information System (INIS)

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

1999-01-01

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

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

Energy Technology Data Exchange (ETDEWEB)

Tarroni, G.; De Zaiacomo, T.; Melandri, C.; Formignani, M.; Barilli, L.; Di Fino, M.; Picini, P.; Galuppi, G.; Rocca, C.; Manassero, G.; Migliorati, B.

1992-01-01

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: 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; study of the feasibility of local abatement of the aerosols produced and of the pressure drop in the HEPA filters; 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; 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.

Present status of refining and conversion facility dismantling. Progress in 2008 first half of the fiscal year

International Nuclear Information System (INIS)

Kado, Kazumi; Sugitsue, Noritake; Morimoto, Yasuyuki; Ikegami, Sohei; Takahashi, Nobuo; Tokuyasu, Takashi

2009-06-01

The Refining and Conversion Facility located in the Ningyo-toge Environmental Engineering Center. Process of natural uranium conversion facility (PNC Process) and reprocessed uranium conversion facility (two-stage dry fluorination system) is in a Refining and Conversion Facility. This building started construction in 1979 and was completed in October 1981. The PNC process operated from March 1982 to March 1991. As a result, uranium hexafluoride of about 385 tonU was manufactured. Also, the reprocessed uranium conversion process operated from December 1982 to July 1999. As a result, uranium hexafluoride of about 338 tonU was manufactured. The demonstration of the demolition method was done using the PNC process after the end of operation. The schedule which will finish dismantling of all equipment in a radiation controlled area is by the 2011 fiscal year. This report summarized the present situation by the first half of the 2008 fiscal year of a Refining and Conversion Facility decommissioning. (author)

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

International Nuclear Information System (INIS)

Bouchet, Bertrand

2014-08-01

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

Application of an automatic yarn dismantler to track changes in cotton fiber properties during full scale processing of cotton into carded yarn

CSIR Research Space (South Africa)

Fassihi, A

2016-08-01

Full Text Available Changes in Upland cotton fiber properties from lint to carded yarn, during full scale processing, were tracked, using a newly developed automatic yarn dismantler for dismantling short staple ring-spun yarns. Opening and cleaning increased fiber neps...

Virtual reality in design, planning, operation and training related to the decommissioning of the Chernobyl NPP

International Nuclear Information System (INIS)

Mark, N.-K.; Johnsen, T.; Meyer, G.; Owre, F.

2007-01-01

Virtual Reality in refueling operation and maintenance training at Leningrad NPP has been recognized by Chernobyl NPP. Institute for Energy Technology's is establishing now the Chernobyl Decommissioning Visualization Centre to be used for planning and training the dismantling procedures in addition to presenting it to the authorities and the public. It will be ready in 2007. The first scenario will be the dismantling of the refueling machines

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

Energy Technology Data Exchange (ETDEWEB)

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

2013-07-01

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

Health physics aspects of the Yale Heavy Ion Linear Accelerator dismantling project

International Nuclear Information System (INIS)

Price, K.W.; Holeman, G.R.

1976-01-01

A program for the disassembly of the Yale Heavy Ion Linear Accelerator was initiated January 1, 1975. The object of the disassembly was to render the accelerator complex free of radioactive contamination in order that the area may be used for other University purposes. In addition, any salvage of metal parts was a desirable goal of the dismantling procedure. A systematic removal of all contaminated material began immediately. Portable survey instruments, swipe surveys, and sodium iodide gamma ray spectra were used as indicators of contamination. Apparatus in the direct beam line seemed to pose the most significant hazard to personnel. As beam components were eliminated, radioactive contamination was significantly reduced. Certain accelerator parts had to be machined in order to salvage non-contaminated metal, and the health physics aspects of this procedure are described. Isotopes found in the surveys included 22 Na, 54 Mn, 60 Co, 65 Zn and 75 Se, which were predominately beam activation products of accelerator components. Final surveys indicated the area free of radioactive contamination

The AIDA-MOX 1 program: Results of the French-Russian study on peaceful use of plutonium from dismantled Russian Nuclear weapons

International Nuclear Information System (INIS)

Yegorov, N.N.; Kudriavtsev, E.; Poplavsky, V.; Polyakov, A.; Ouin, X.; Camarcat, N.; Sicard, B.; Bernard, H.

1997-01-01

The Intergovernmental Agreement signed on November 12, 1992, between the governments of France and the Russian Federation instituted cooperation between the two countries for the safe elimination of the excess Russian nuclear weapons. France has allocated 400 million francs to this program, covering transportation and dismantling of nuclear weapons, interim storage and subsequent commercial use of the nuclear materials from the dismantled weapons, nuclear materials accountancy and safeguards, and scientific research. The concept of loading commercial Russian reactors with fuel fabricated from the plutonium recovered from dismantled nuclear weapons of the former Soviet Union is gaining widespread acceptance, and is at the heart of the French-Russian AIDA/MOX project

Development of a handling technology for underwater inspection and dismantling

International Nuclear Information System (INIS)

Rose, N.

1994-01-01

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

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.    

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...

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

International Nuclear Information System (INIS)

Gasc, B.

1990-01-01

The CEA (French Nuclear Energy Commission) in connection with TECHNICATOME developed a tight modular workshop for the dismantling of AT1 plant facilities in LA HAGUE. This workshop constructed of reusable stainless steel panels assembled by bolting provides a tight and decontaminable working zone compatible with any building configuration. This being the case, the operators bearing ventilated suits may work under the best safety conditions on alpha-contaminated materials. For the purpose of expanding the working capacities of this workshop it was decided to develop special components for teleoperation from the outside as in a conventional cell. To meet this objective which is within the scope of the contract signed with the CEC, the following components were developed and constructed: - manipulator holder panel, - swivelling hatch panel, - wall equipment sealed transfer device and, - modular biological protection. The design, construction and tests of these new components led to their qualification and further incorporation in the list of components of the modular workshop liable to be used for teleoperation procedures

Advanced Tele-operation

International Nuclear Information System (INIS)

Decreton, M.

1998-01-01

Maintenance, repair, and dismantling operations in nuclear facilities have to be performed remotely when high radiation doses exclude hands-on operation, but also to minimize contamination risks and occupational doses to the operators. Computer-aided and sensor-based tele-operation enhances safety, reliability, and performance by helping the operator in difficult tasks with poor remote environmental perception. The objectives of work in this domain are to increase the scientific knowledge of the studied phenomena, to improve the interpretation of data, to improve the piloting og experimental devices during irradiation, to reveal and to understand possible unexpected phenomena occurring during irradiation. This scientific report describes the achievements for 1997 in the area of radiation tolerance for of remote-sensing, optical fibres and optical fibre sensors

Project WAGR: the UK demonstration project for power reactor decommissioning - a review of the tools used to dismantle the reactor core

International Nuclear Information System (INIS)

Benest, T.G.

2008-01-01

The United Kingdom Atomic Energy Authority (UKAEA) has built and operated a wide range of nuclear facilities since the late 1940. UKAEA mission is to restore the environment of its sites in a safe and secure manner. This restoration includes the decommissioning of a number of redundant research and power reactors. The Windscale Advanced Gas-cooled Reactor (WAGR) was the UK prototype Advanced gas cooled reactor and became the forerunner of a family of 14 reactors built to generate cheaper and more efficient electricity in the UK. WAGR was constructed between 1957 and 1961 and was a carbon dioxide cooled, graphite moderated reactor using uranium oxide fuel in stainless steel cans. The reactor consisted of a graphite moderator housed in a cylindrical reactor vessel with hemispherical ends. The reactor and associated heat exchangers were enclosed in the iconic spherical containment building regularly used by the media in the UK as an illustration of the nuclear industry. The reactor first produced power in August 1962 and achieved full design output in 1963. It operated at an electrical output of 33 MW (E) for 18 years (average load factor of 75%). In 1981 the reactor was shut down after satisfactory completion of all the research and development objectives. In anticipation of the UK likely nuclear decommissioning needs the UKAEA decided to decommission WAGR to the International Atomic Energy Agency (IAEA) stage 3 (restoration of the area occupied by the facility to a condition of unrestricted re-usability) as the national demonstration exercise for power reactor decommissioning. Since 1998 the UKAEA and its contractors have been undertaking the dismantling of the reactor core components and pressure vessel in a series of 10 campaigns. These contain neutron activated components expected to produce dose rates well in excess of 1 Sv/hr. To carry out the work UKAEA installed an 8M remote dismantling machine (RDM) a waste recovery and transport system and a shielded waste

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

International Nuclear Information System (INIS)

1993-01-01

On February 3--4, 1993, a workshop was conducted to examine issues associated with the decontamination, dismantlement, and recycle/disposal of transite located at the US Department of Energy Fernald site near Cincinnati, OH. The Fernald Environmental Management Project (FEMP) is a Superfund Site currently undergoing remediation. A major objective of the workshop was to assess the state-of-the-art of transite remediation, and generate concepts that could be useful to the Fernald Environmental Restoration Management Co. (FERMCO) for remediation of transite. Transite is a building material consisting of asbestos fiber and cement and may be radioactively contaminated as a result of past uranium processing operations at the FEMP. Many of the 100 buildings within the former uranium production area were constructed of transite siding and roofing and consequently, over 180,000 m 2 of transite must be disposed or recycled. Thirty-six participants representing industry, academia, and government institutions such as the EPA and DOE assembled at the workshop to present their experience with transite, describe work in progress, and address the issues involved in remediating transite

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

Science.gov (United States)

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

2018-05-01

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

Plutonium active operation of the Winfrith modular containment system

International Nuclear Information System (INIS)

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

1985-01-01

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

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.

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

International Nuclear Information System (INIS)

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

2002-01-01

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

Systems study 'Alternative Entsorgung'. Final report. Technical annex 6

International Nuclear Information System (INIS)

1984-08-01

In the conditioning plant, fuel elements which have been stored for ten years are loaded into transport containers, unloaded, identified and welded into a dry storage box. The dry store barrel is introduced into a final storage container, which, after being closed, is packed in lost shielding. This so-called final storage barrel is finally placed in a transport container and leaves the conditioning plant in this form by rail for transport to the final storage mine. The fuel element method of treatment 'packing of three complete fuel elements' was used as the reference process. In addition, the method of treatment 'fuel elements dismantled into fuel rods' was also examined. The handling of fuel elements and secondary waste treatment in the reference process are described in detail. (orig./HP) [de

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.

Phenix Power Plant Decommissioning Project. Treatment of the Primary Cold Trap

International Nuclear Information System (INIS)

Deluge, M.

2008-01-01

Phenix is a sodium-cooled fast neutron reactor located at the CEA's Rhone Valley Center where it was commissioned in 1974. It has an electric power rating of 250 MW and is operated jointly by the CEA and EDF. Its primary role today is to investigate the transmutation of long-lived radioactive waste into shorter-lived wasteform. Its final shutdown is scheduled for the beginning of 2009. In this context the Phenix Power Plant Decommissioning Project was initiated in 2003. It covers the definitive cessation of plant operation and the dismantling (D and D) operations together with the final shutdown preparatory phase. The final shutdown phase includes the operations authorized within the standard operating methodological framework. The dismantling phase also comprises treatment of sodium-bearing waste and dismantling of the nuclear facilities (reactor block, shielded cells, etc.). Treatment of the Phenix primary cold trap is scheduled to begin in 2016. The analysis program includes the following steps: - Accurately determine the contamination in the trap by carrying out gamma spectrometry measurement campaigns from 2007 to 2013 (the remaining difficulty will be to accurately determine the distribution of the contamination). - Validate the safety studies for the ELA facility. This work is currently in progress; ELA will be commissioned following inactive qualification testing. - Proceed with cutting tests on the knit mesh filter, which are scheduled to begin in 2008

Decommissioning experience of the Japan power demonstration reactor

International Nuclear Information System (INIS)

Hoshi, T.; Yanagihara, S.; Tachibana, M.; Momma, T.

1992-01-01

Actual dismantling of the Japan Power Demonstration Reactor (JPDR) has been progressing since 1986 aiming to make stage 3 condition as the final goal. Such highly activated components as the reactor pressure vessel (RPV) and the inner portion of biological shield concrete close to the RPV have removed using the remotely operated cutting machines. Useful data on the dismantling techniques and their safety as well as the manpower expenditure and radiation exposure of workers have been obtained. Experiences gained through the dismantling works are described in this paper. (author)

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

Science.gov (United States)

Justinia, Taghreed

2017-02-01

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

Installation dismantling system, working process and hood utilizable in this system

International Nuclear Information System (INIS)

Poirier, J.C.; Mulcey, P.; Morel, P.; Vavasseur, C.

1989-01-01

The system for dismantling an installation under a controlled atmosphere is made by a tool polluting the atmosphere, a gas blanket creating a continement zone around the tool, an extractor removing polluted gas from the zone, a purifier for the extracted gas and a controller regulating the flow of gas in the blanket and keeping the installation at constant pressure [fr

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

International Nuclear Information System (INIS)

Tarroni, G.; De Zaiacomo, T.; Melandri, C.; Formignani, M.; Barilli, L.; Di Fino, M.; Picini, P.; Galuppi, G.; Rocca, C.; Manassero, G.; Migliorati, B.

1991-02-01

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: 1) 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; 2) study of the feasibility of local abatement of the aerosols produced and of the pressure drop in the HEPA filters; 3) 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; 4) 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. (author)

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

International Nuclear Information System (INIS)

Migliorati, B.; Difino, M.; Manassero, G.

1990-01-01

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

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

Energy Technology Data Exchange (ETDEWEB)

Tarroni, G; De Zaiacomo, T; Melandri, C; Formignani, M; Barilli, L [ENEA - Area Energia, Ambiente e Salute - Centro Ricerche Energia ' Ezio Clementel' - Bologna (Italy); Di Fino, M [ENEA - Area Energia, Ambiente e Salute, Centro Ricerche Energia, Frascati, Rome (Italy); Picini, P; Galuppi, G; Rocca, C [ENEA - Area Energia, Ambiente e Salute, Centro Ricerche Energia, Casaccia, Rome (Italy); Manassero, G [Centro Ricerche FIAT, Orbassano, Torino (Italy); Migliorati, B [FIAT-CIEI, Torino (Italy)

1991-02-15

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: 1) 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; 2) study of the feasibility of local abatement of the aerosols produced and of the pressure drop in the HEPA filters; 3) 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; 4) 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. (author)

Assisted supervision of a computer aided tele-operation system

Energy Technology Data Exchange (ETDEWEB)

Le Bars, H; Gravez, P; Fournier, R

1994-12-31

This paper talks about Computer Aided Tele-operation (CAT) in dismantling and maintenance of nuclear plants. The current research orientations at CEA, basic concepts of the supervision assistance system and the realisation of a prototype are presented. (TEC). 3 refs., 4 figs.

Assisted supervision of a computer aided tele-operation system

International Nuclear Information System (INIS)

Le Bars, H.; Gravez, P.; Fournier, R.

1994-01-01

This paper talks about Computer Aided Tele-operation (CAT) in dismantling and maintenance of nuclear plants. The current research orientations at CEA, basic concepts of the supervision assistance system and the realisation of a prototype are presented. (TEC). 3 refs., 4 figs

Iraq nuclear facility dismantlement and disposal project

Energy Technology Data Exchange (ETDEWEB)

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

2007-07-01

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

Operations-oriented performance measures for freeway management systems : final report.

Science.gov (United States)

2008-12-01

This report describes the second and final year activities of the project titled Using Operations-Oriented Performance Measures to Support Freeway Management Systems. Work activities included developing a prototype system architecture for testi...

New wireless system for fire protection (detection) during dismantling works in Jose Cabrera NPP (CNJC); Nuevo Sistema Inalámbrico de detección contraincendios para el desmantelamiento de a Central Nuclear José Cabrera

Energy Technology Data Exchange (ETDEWEB)

Núñez, F.J.; Gómez Rodríguez, C.A.

2016-07-01

José Cabrera Nuclear Power Plant is currently in an advanced stage in the process of dismantling and decommissioning. As part of that process, it is necessary to remove the maximum possible interference with operating systems, which are still needed to support the works ongoing or to ensure the safety. With that goal it has been installed a new wireless fire detection system that substitutes the old wired one. The coverage of this new system was initially focused on the containment building, establishing a first phase of analysis of signal coverage, and location of the different components in the building and a second phase of implementation (monitoring and testing) to demonstrate the reliability and robustness of the system in a building with such a complex geometry configuration. Currently the WIFI system is in operation, providing coverage to the containment building and other external facilities (laundry, control room, etc) that have been incorporated to support the process of dismantling.

Radiation exposure of the personnel during dismantling and cutting of the primary system of the Karlsruhe Multi-purpose Research Reactor (MZFR)

International Nuclear Information System (INIS)

Hesse, H.; Demant, W.; Reichert, A.; Willmann, F.

2000-10-01

The heavy water (D 2 O) cooled and moderated pressurized water reactor MZFR with a thermal power of 200 MW will be dismantled step-by-step within the framework of sectional decommissioning licenses. The past decommissioning step (6 th sectional license) in general covered the removal of the primary systems and of all reactor support systems inside the reactor building. The measures for radiation protection during dismantling and handling of the large components of the primary system, such as the fuel element loading machine, fuel element transfer system, steam generator and pressurizer shall be pointed out. The measures taken for the reduction of the dose rate during dismantling and cutting of the components for the purpose of conditioning or unrestricted reuse at the central decontamination department (HDB) shall be described. Chemical decontamination of the primary circuit and its components, which had to be executed in order to reduce the dose rates for subsequent manual dismantling, shall be presented. The efforts undertaken for the protection of individuals in view of the difficult radiological boundary conditions (high concentrations of tritium in all systems as well as very high alpha contamination) will be explained. Moreover, dose-minimizing measures during cutting of the primary circuit and its components at HDB shall be described by the example of the cutting of a steam generator. It shall be demonstrated that cutting and dismantling of highly contaminated and activated parts with high dose rates can be executed safely in terms of both the radiation exposure of the personnel and the technical, financial and time expenditure. (orig.)

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

International Nuclear Information System (INIS)

Rouviere, R.; Pinault, M.; Gasc, B.; Guiadeur, R.; Pilot, M.

1989-01-01

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

Pick-N-Pull Auto Dismantlers, Kansas City, LLC Inc. - Clean Water Act Public Notice

Science.gov (United States)

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

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.

Heavy metal contamination of surface soil in electronic waste dismantling area: site investigation and source-apportionment analysis.

Science.gov (United States)

Jinhui Li; Huabo Duan; Pixing Shi

2011-07-01

The dismantling and disposal of electronic waste (e-waste) in developing countries is causing increasing concern because of its impacts on the environment and risks to human health. Heavy-metal concentrations in the surface soils of Guiyu (Guangdong Province, China) were monitored to determine the status of heavy-metal contamination on e-waste dismantling area with a more than 20 years history. Two metalloids and nine metals were selected for investigation. This paper also attempts to compare the data among a variety of e-waste dismantling areas, after reviewing a number of heavy-metal contamination-related studies in such areas in China over the past decade. In addition, source apportionment of heavy metal in the surface soil of these areas has been analysed. Both the MSW open-burning sites probably contained invaluable e-waste and abandoned sites formerly involved in informal recycling activities are the new sources of soil-based environmental pollution in Guiyu. Although printed circuit board waste is thought to be the main source of heavy-metal emissions during e-waste processing, requirement is necessary to soundly manage the plastic separated from e-waste, which mostly contains heavy metals and other toxic substances.

Safety aspects in decontamination operations: Lessons learned during the decommissioning of a small PWR reactor

International Nuclear Information System (INIS)

Klein, M.; Ponnet, M.; Emond, O.

2002-01-01

Decontamination operations are generally executed during the decommissioning of nuclear installations for different objectives: decontamination of loops or large pieces to reduce the dose rate inside a contaminated plant or decontamination to minimize the amount of radioactive waste. These decontamination operations raise safety issues such as radiological exposure, classical safety, environmental releases, production and management of secondary waste, management of primary resources, etc. This paper presents the return of experience from decontamination operations performed during the dismantling of the BR3 PWR reactor. The safety issues are discussed for 3 types of decontamination operations: full system decontamination of the primary loop with a chemical process to reduce the dose rate by a factor of 10; thorough decontamination with an aggressive chemical process of dismantled pieces to reach the unconditional clearance values; and thorough decontamination processes with physical processes of metals and of concrete to reach the unconditional clearance values. For the protection of the workers, we must consider the ALARA aspects and the classical safety issues. During the progress of our dismantling operations, the dose rate issue was becoming less important but the classical safety issues were becoming preponderant due to the use of very aggressive techniques. For the protection of the environment, we must take all the precautions to avoid any leakages from the plant and we must use processes which minimize the use of toxic products and which minimize the production of secondary wastes. We therefore promote the use of regenerative processes. (author)

Greifswald and Rheinsberg: East European VVERs with a new mission

International Nuclear Information System (INIS)

Sterner, H.; Leushacke, D.; Rittscher, D.

1995-01-01

Plans for the decommissioning of the VVER reactors at Greifswald and Rheinsberg in the former German Democratic Republic are described. The decision to decommission the eight VVER-440s (two of which are still under construction) at Greifswald and the Russian prototype PWR, VVER-2, at Rheinsberg, was taken because of a lack of public acceptance and financial considerations. Three main phases are scheduled for the project. The first, the post-operation phase, has already commenced at both sites. It involves: the operation of all systems needed safely to store fuel elements, to remove them and to condition operational waste; dismantling of mainly inactive, systems not needed for fuel handling; and system decontamination. The second phase comprises the dismantling of contaminated systems, remote dismantling and conditioning of the dismantled material. Finally, in the site restoration phase, following the dismantling of remaining systems and building decontamination and demolition, the site will be adapted for other uses. Three projects for new site use at Greifswald being pursued. As a first step, an international Technology Centre is to be created to collect and evaluate information on decommissioning experience. The centre will require international financial support and co-ordination. New facilities are already being constructed to deal with decontamination of dismantled materials and the interim storage of radioactive waste and reactor fuel. (UK)

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

International Nuclear Information System (INIS)

Freund, H.U.

1995-01-01

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.) [de

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, 62-17...

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

International Nuclear Information System (INIS)

1998-03-01

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

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

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

International Nuclear Information System (INIS)

Long, Yu-Yang; Feng, Yi-Jian; Cai, Si-Shi; Ding, Wei-Xu; Shen, Dong-Sheng

2013-01-01

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 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

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.

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

Energy Technology Data Exchange (ETDEWEB)

NONE

2016-07-01

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

Responsibility, safety and certainty. A new consensus on nuclear waste disposal. Final report

Energy Technology Data Exchange (ETDEWEB)

NONE

2016-05-25

With the consent of all parties represented in the Bundestag, the Federal Republic of Germany resolved to properly end the use of nuclear energy for power generation. The legal framework for the energy transition is provided by the consensus reached on nuclear energy in 2001 and the Nuclear Power Phase-Out Act (Atomgesetz, hereinafter: Atomic Energy Act) passed in 2002 and amended in 2011, together with the Renewable Energy Sources Act (Erneuerbare-Energien-Gesetz, hereinafter: Renewable Energy Act), the Energy Industry Act (Energiewirtschaftsgesetz) and extensive provisions on accelerating the construction of power lines in Germany. Nuclear energy plants will have gradually phased out their power generation operations by the end of the year 2022. The decision to phase out nuclear power plants has entailed major changes in radioactive waste management - dismantling, packaging spent fuel in containers, and interim storage and final disposal. For one thing, the amount of radioactive waste requiring final storage is now easier to calculate and to limit, in contrast with periods of indefinite operation. Limiting the operating lives of nuclear plants also shortens the period in which assets can be generated for the decreased amounts of high-level, intermediate-level and low-level waste. Along with the phase-out, the rapidly expanding renewable energy market and continued integration into the European Single Market has changed market conditions for nuclear power plant operators. Not only have new market participants joined the competition for power generation - due to a surplus and, ultimately, to price erosion in the international fuel markets, stock market prices for power have dropped dramatically. This has affected nuclear power plant operators in particular, because of their large share in conventional power generation.

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.

Dismantling the dwelling : A systematic approach to investigating the meaning of the dwelling: draft

NARCIS (Netherlands)

Meesters, J.; Coolen, H.C.C.H.

2009-01-01

The meaning of the dwelling consists of multiple layers, which makes it a complex concept. Therefore it should be dismantled (ref. Rapoport, 2001). This paper presents a conceptual framework in which settings, activities and values are systematically related. The data is derived from a telephone

Vandellos 1 NPP. Dismantling at the level 1

International Nuclear Information System (INIS)

Pla, E.; Perez Pallares, J.

1998-01-01

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

Status of the decommissioning program of the Eurochemic reprocessing plant

International Nuclear Information System (INIS)

Detilleux, E.J.

1976-01-01

Reprocessing operations at the Eurochemic demonstration plant stopped in December 1974, after 8 years of operation. Immediately thereafter, cleaning and decontamination were begun as the first phase of the decommissioning program. The facility and reprocessing program are described to indicate the magnitude of the problem, and the requirements of the local authorities are reviewed. The technical decommissioning program consists of several phases: (1) plant cleaning and rinsing, (2) establishment of the final fissile-material balance, (3) plant decontamination for access to process equipment, (4) equipment dismantling, and (5) conditioning and storage of newly generated wastes. The two first phases have been completed, and the third one is nearing completion. Some dismantling has been performed, including the plutonium dioxide production unit. Waste-conditioning and surface-storage facilities have been built to meet the dismantling requirements. Since reprocessing may be resumed in the future, decontamination has been performed with ''smooth'' reagents to limit corrosion and dismantling has been limited to subfacilities

Implementing robotics in the Department of Energy Dismantlement Program

International Nuclear Information System (INIS)

Jones, A.T.

1997-01-01

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

Cost Savings through Innovation in Decontamination, Decommissioning, and Dismantlement

International Nuclear Information System (INIS)

Yancey, Neal A.

2003-01-01

The United States Department of Energy (DOE) continually seeks safer and more cost effective technologies for the decontamination and decommissioning (D and D) of nuclear facilities. The Deactivation and Decommissioning Focus Area (DDFA) of the DOE's Office of Science and Technology (OST) sponsored large-scale demonstration and deployment projects (LSDDPs) to help bring new technologies into the D and D programs. The Idaho National Engineering and Environmental Laboratory (INEEL) LSDDP generated a list of needs defining specific problems where improved technologies could be incorporated into ongoing D and D tasks. The needs fell into 5 major categories--characterization, dismantlement, safety, material dispositioning, and decontamination. Technologies were carefully selected that provide a large benefit for a small investment. The technologies must provide significant improvements in cost, safety, radiation exposure, waste volume reduction, or schedule savings and widely applicable throughout the DOE complex. The LSDDP project provided training for the new technologies and worked with technology suppliers to resolve any questions that arose. Since 1998, 26 technologies have been demonstrated or deployed through the LSDDP for the D and D program at the INEEL. Of the 26 demonstrated and deployed technologies, 14 were in characterization, 3 were in decontamination, 4 were in dismantlement, 3 were in safety, and 2 were in material dispositioning. To promote the use of these technologies at other sites within the DOE complex, the LSDDP team published fact sheets, videos, technology summary reports, articles in INEEL star newspaper, posters, and maintained an internet home page on the project. As a result, additional deployments have taken place at the Hanford, Mound, Fernald, Oak Ridge, Ashtabula, and West Valley. Eight of the 26 technologies evaluated were developed in foreign countries. The technologies demonstrated have been shown to be faster, less expensive, and

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

International Nuclear Information System (INIS)

Gat, U.; Engel, J.R.

1991-01-01

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

Decommissioning and dismantling of nuclear installations

International Nuclear Information System (INIS)

Pelzer, N.

1993-01-01

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

The role of congress in future disposal of fissile materials from dismantled nuclear weapons

International Nuclear Information System (INIS)

Donnelly, W.H.; Davis, Z.S.

1991-01-01

Assuming the Soviet Union remains intact as a major power and the superpowers do not retrogress to a new Cold War era, it is likely that the United States and the Soviet Union will eventually agree to deep cuts in their nuclear arsenals. Future arms control agreements may be coupled with companion agreements to stop production of fissile materials for nuclear weapons, to dismantle the warheads of the nuclear weapons, and to dispose of their fissile materials to prevent reuse in new warheads. Such agreements would be negotiated by the U.S. executive branch but probably would require ratification, funding, and enabling legislation from the U.S. Congress if they are to succeed. There follows a brief review of the ideas for disposal of fissile materials from dismantled nuclear warheads and the potential role and influence of the Congress in the negotiation, ratification, and implementation of U.S.-Soviet agreements for such disposal

NEA's analysis of the needs in innovation and research in the domain of dismantling

International Nuclear Information System (INIS)

Laurent, G.

2014-01-01

Today's approach of the dismantling of nuclear facilities is labour intensive and consequently very expensive. NEA's study suggests that research works should be done to find more efficient technologies for decontamination and dismantling. 5 lines of research have been identified by NEA. First, new technologies must be found to get a more accurate spatial distribution of contaminants. Secondly, the different cutting methods must be assessed in terms of efficiency, dosimetry and secondary waste generation. Thirdly, a better understanding of the chemical and physical processes that may be used for the decontamination of metals, concretes, underground water and soil. Fourthly, the management of radioactive waste implies to know the interaction between wastes and packages over a very long period. Fifthly, an accurate characterization of a complex site housing various contaminating sources and different hydro-geological conditions implies the development of 3-dimensional radiation transport codes and the use of innovative means like satellite monitoring. (A.C.)

Radiation protection during backfitting or dismantling work in the controlled area of nuclear facilities

International Nuclear Information System (INIS)

Baumann, J.; Kausch, S.; Palmowski, J.

1980-01-01

Backfitting measures or dismantling activities within the controlled area put special requirements on radiological protection. This is to be shown by the example of the following cases. Sanitation of the general decontamination services of the Karlsruhe Nuclear Research Center; waste water, equipment decontamination, incineration and packaging facility; dismantling and disposal of high-radiation components including decontamination of buildings of the Eurochemic reprocessing plant at Mol; reconstruction of the HDR plant for safety experiments together with waste management for components and systems, as e.g. pressure vessel internals, pipes etc.; exchange of the steam dryer and the water separator including planning of the conditioning process in the Wuergassen nuclear power plant. This lecture deals with the engineering and organizational problems, especially accounting for radiological protection and enters into planning of measures for radiological protection, their organization and execution, problems of direct and remote-controlled work also being discussed. The question of personnel qualification is also commented on. (orig.) [de

Muscle Expression of SOD1G93A Triggers the Dismantlement of Neuromuscular Junction via PKC-Theta.

Science.gov (United States)

Dobrowolny, Gabriella; Martini, Martina; Scicchitano, Bianca Maria; Romanello, Vanina; Boncompagni, Simona; Nicoletti, Carmine; Pietrangelo, Laura; De Panfilis, Simone; Catizone, Angela; Bouchè, Marina; Sandri, Marco; Rudolf, Rüdiger; Protasi, Feliciano; Musarò, Antonio

2018-04-20

Neuromuscular junction (NMJ) represents the morphofunctional interface between muscle and nerve. Several chronic pathologies such as aging and neurodegenerative diseases, including muscular dystrophy and amyotrophic lateral sclerosis, display altered NMJ and functional denervation. However, the triggers and the molecular mechanisms underlying the dismantlement of NMJ remain unclear. Here we provide evidence that perturbation in redox signaling cascades, induced by muscle-specific accumulation of mutant SOD1 G93A in transgenic MLC/SOD1 G93A mice, is causally linked to morphological alterations of the neuromuscular presynaptic terminals, high turnover rate of acetylcholine receptor, and NMJ dismantlement. The analysis of potential molecular mechanisms that mediate the toxic activity of SOD1 G93A revealed a causal link between protein kinase Cθ (PKCθ) activation and NMJ disintegration. The study discloses the molecular mechanism that triggers functional denervation associated with the toxic activity of muscle SOD1 G93A expression and suggests the possibility of developing a new strategy to counteract age- and pathology-associated denervation based on pharmacological inhibition of PKCθ activity. Collectively, these data indicate that muscle-specific accumulation of oxidative damage can affect neuromuscular communication and induce NMJ dismantlement through a PKCθ-dependent mechanism. Antioxid. Redox Signal. 28, 1105-1119.

Cost effective decommissioning and dismantling of nuclear power plants; Kosteneffizienz bei Stilllegung und Rueckbau von Kernkraftwerken

Energy Technology Data Exchange (ETDEWEB)

Wasinger, Karl [AREVA NP GmbH, Offenbach (Germany)

2012-10-15

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

Disposal of fissionable material from dismantled nuclear weapons

International Nuclear Information System (INIS)

Taylor, J.J.

1991-01-01

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

Application and development of dismantling technologies for decommissioning of nuclear installations

International Nuclear Information System (INIS)

Bach, W.; Kremer, G.; Ruemenapp, T.

2006-01-01

The decommissioning of nuclear installations poses a challenge to high performance underwater cutting technologies because of complex limiting conditions, like radioactive contamination, accessibility, geometry of work piece, material thickness and composition. For the safe dismantling of the moderator tank and the thermal shield of the Multi-purpose Research Reactor (MZFR) Karlsruhe the development and the use of thermal cutting tools will be demonstrated, in this case the underwater plasma arc cutting and the contact arc metal cutting (CAMC). (orig.)

Conception of dismantling cell for glove box with alpha contamination

International Nuclear Information System (INIS)

Mangin, D.

1987-01-01

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

Latest expertise investigations in nuclear dismantling and industrial applications

International Nuclear Information System (INIS)

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

2013-06-01

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

Astronaut John Young during final suiting operations for Apollo 10 mission

Science.gov (United States)

1969-01-01

A technician attaches hose from test stand to spacesuit of Astronaut John W. Young, Apollo 10 command module pilot, during final suiting operations for the Apollo 10 lunar orbit mission. Another technician makes adjustment behind Young.

Final result of the Munich-Frascati gravitational radiation experiment

International Nuclear Information System (INIS)

Kafka, P.; Schnupp, L.

1977-02-01

Within 580 days of usable common observation time between July 1973 and February 1976, this Weber-type coincidence experiment had set the lowest upper limits to the rates of gravitational wave pulses. We report the total result up to the dismantling of the detectors. We also describe a reevaluation of our data using Weber's preferred algorithm for two months in 1974 during which Weber communicated to have found a particularly significant effect in his own experiment. Finally, we confront the negative results with the far aims of gravitational pulse astronomy. (orig.) [de

Final result of the Munich-Frascati gravitational radiation experiment

International Nuclear Information System (INIS)

Kafka, P.; Schnupp, L.

1978-01-01

Within 580 days of usable common observation time between July 1973 and February 1976, this Weber-type coincidence experiment had set the lowest upper limits to the rates of gravitational wave pulses. We report the total result up to the dismantling of the detectors. We also describe a re-evaluation of our data using Weber's preferred algorithm for two months in 1974 during which Weber communicated to have found a particularly significant effect in his own experiment. Finally, we confront the negative results with the far aims of gravitational pulse astronomy. (orig.) [de

EDF decommissioning programme a global commitment to safety, environment and cost efficiency of nuclear energy

International Nuclear Information System (INIS)

Grenouillet, J.-J.

2002-01-01

EDF has 9 NPPs permanently shutdown and under decommissioning. EDF considers that if the nuclear option is to remain open, it is necessary to deal with increasing public concerns for environmental and waste management issues. Therefore EDF has decided to achieve total dismantling of all shutdown reactor in the next 25 years. The Decommissioning Program has been developed including 2 stages of activities. The first stage consists of: 1) Final dismantling of Brennilis in 2015; 2) A dismantling demonstration of a PWR reactor building (Chooz A) before starting replacing the population of PWRs currently in operation; 3) Final dismantling of reactor containment of a GCR (Bugey 1) as a first of its kind. The second stage includes: 1)Dismantling of following 5 GCR (Saint Laurent A1 and A2, Chinon A1, A2 and A3); 2) Final dismantling of Chooz A and Bugey 1 in 2025. The successful implementation relies on the simplification of the regulatory process; availability of treatment, conditioning and disposal facilities and effective nuclear industry. The main issue is availability of time and waste solutions such as opening of a Very Low Waste disposal in 2003 (130 000 tons); opening of a new disposal for graphite and radiferous wastes (17 000 tons) in 2010 and opening in 2007-2008 of a centralized interim storage (BANEDA) facility for long-lived Medium Level Wastes (500 tons including filters, control rods etc)Three investigations are to be carried out for high level radioactive waste before 2006

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.

Sixteen Years of International Co-operation. The OECD/NEA Co-operative Programme on Decommissioning

International Nuclear Information System (INIS)

Menon, S.; Valencia, L.

2002-01-01

The Co-operative Programme on Decommissioning under the administration of the Radioactive Waste Management Committee of the OECD Nuclear Energy Agency (NEA) has recently completed sixteen years of operation. The Programme, which is essentially an information exchange programme between decommissioning projects, came into being in 1985. It has grown from an initial 10 decommissioning projects from 7 countries to 39 projects from 14 countries today. From purely information exchange to start with, the Programme has, in later years, been functioning as a voice for the collective expression of views of the implementers of nuclear decommissioning. During the first sixteen years of the operation of the Co-operative Programme, nuclear decommissioning has grown from local specialist activities within projects to a competitive commercial industry. By the dismantling and release from regulatory control of over a dozen diverse nuclear facilities, the Programme has been able to demonstrate in practice, that nuclear decommissioning can be performed safely both for the workers and the public, and that this can be done at reasonable costs in an environmentally friendly fashion. During the recent years, discussions and work within the Co-operative Programme, specially within some of the Task Groups, have had/are having effects and repercussions not just in the field of nuclear decommissioning, but can possibly affect activities and regulations in other industries. This paper describes how the Programme and its activities and procedures have evolved over the years and indicate the directions of developments in the organization and execution of decommissioning projects. Finally, it gives a brief overview of the achievements of the Cooperative Programme and visualizes future developments in the field of nuclear decommissioning

Radiation protection issues after 20 years of LHC operation

CERN Document Server

Forkel-Wirth, D.; Roesler, S.; Theis, C.; Ulrici, L.; Vincke, H.; Vincke, Hz.

2011-01-01

Since November 2009, the LHC commissioning progresses very well, both with proton and lead beams. It will continue in 2011 and nominal LHC operation is expected to be attained in 2013. In parallel, plans for various LHC upgrades are under discussion, suggesting a High-Luminosity (HL) upgrade first and a High-Energy (HE) upgrade in a later state. Whereas the upgrade in luminosity would require the modification of only some few key accelerator components like the inner triplets, the upgrade in beam energy from 7 TeV to 16.5 TeV would require the exchange of all dipoles and of numerous other accelerator components. The paper gives an overview of the radiation protection issues related to the dismantling of LHC components prior to the installation of the HE-LHC components, i.e. after about 20 years of LHC operation. Two main topics will be discussed: (i) the exposure of workers to ionizing radiation during the dismantling of dipoles, inner triplets or collimators and experiments and (ii) the production, condition...

Mobile worksystems for decontamination and dismantlement

International Nuclear Information System (INIS)

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

1995-01-01

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

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.

Cleaning of dismantled metals by electropolishing

International Nuclear Information System (INIS)

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

1995-01-01

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

Dismantling method for nuclear fuel assembly

International Nuclear Information System (INIS)

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

1993-01-01

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

Level 3 decommissioning of Triton - Nereide research reactor

International Nuclear Information System (INIS)

Lopes, E.; Pillette-Cousin, L.

2002-01-01

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

Dismantling of Evaporators by Laser Cutting Measurement of Secondary Emissions

International Nuclear Information System (INIS)

Pilot, Guy; Fauvel, Sylvain; Gosse, Xavier; De Dinechin, Guillaume

2006-01-01

In order to dismantle the evaporators of an obsolete reprocessing plant in Marcoule, studies were carried out by IRSN (Institut de Radioprotection et de Surete Nucleaire) / DSU/SERAC in cooperation with CEA (power laser group) on the laser cutting of steel structures, on the request of COGEMA (now AREVA NC) /Marcoule (UP1 dismantling project manager) and CEA/UMODD (UP1 dismantling owner). The aim of these studies was: - to quantify and to characterize the secondary emissions produced by Nd-YAG laser cutting of Uranus 65 steel pieces representative of UP1 evaporator elements and to examine the influence of different parameters, - to qualify a pre-filtration technique and particularly an electrostatic precipitator, - to compare the Nd-YAG used with other cutting tools previously studied. The experiments, which took place in a 35 m 3 ventilated cutting cell, allow to underline the following points: for the Uranus 65 steel, the sedimented dross, the deposits on the walls of the cutting cell and the aerosols drawn in the ventilation exhaust duct (∼ 275 m 3 /h), represent respectively between 92% and 99%, between 0.01% and 0.25% and between 1% and 8% of the total collected mass, the attached slag varies much from one configuration to the other and can sometimes amount to a relatively important fraction of the total mass, the kerves vary from 2 mm up to 7 mm for the Uranus 65 steel plates (thickness: 13.8 mm for the single plate and 12.8 + 3.5 mm for the double plate), the exhausted aerosol mass per cut length (g/m) decreases with the cutting speed, varies neither with the stand-off nor with the gas pressure, is dependent upon the gas nature (for the double plate), increases with the laser power, is strongly affected by the nature of the steel (stainless steel or mild steel) and is independent upon the plate position, the size distribution of aerosols is multimodal with a main mode often around 0.45 μm, the electrostatic precipitator has been a satisfactory prefilter

Proposal for the award of an industrial support contract for radiation monitoring services for LEP dismantling

CERN Document Server

2000-01-01

This document concerns the award of an Industrial Service contract for radiation monitoring services for LEP dismantling. Following a market survey carried out among 34 firms in nine Member States, a call for tenders (IT-2769/SL/LEP) was sent on 13 March 2000 to seven firms and three consortia in five Member States. By the closing date, CERN had received six tenders from three firms and three consortia in four Member States. The Finance Committee is invited to agree to the negotiation of a contract with the consortium ISS MULTISERVICE (CH), NFI (SE) and ISS GEBÄUDESERVICE (DE), the lowest technically qualified bidder, for radiation monitoring services for LEP dismantling for a total amount of 990 792 Swiss francs, not subject to revision. The firm has indicated the following distribution by country of the contract value covered by this adjudication proposal: CH-59%, DE-26%, SE-15%.

A process for separating aggregate from concrete waste during the dismantlement of nuclear power plants

International Nuclear Information System (INIS)

Koga, Yasuo; Inoue, Toshikatsu; Tateyashiki, Hisashi; Sukekiyo, Mitsuaki; Okamoto, Masamichi; Asano, Touichi.

1997-01-01

The decommissioning and dismantling of nuclear power plants will produce a large quantity of non-active waste concrete. From the viewpoint of recycling of this waste concrete the recovery of aggregate contained in concrete at 80% and reuse of it into a new plant construction are envisioned. For these purposes we have studied the recovery process of aggregate from concrete composed of a heating step followed by a milling step onto waste concrete blocks. We have found that higher operation temperature brings a better effect for the separation of aggregate from a concrete body, however too high temperature may reversely degrade a quality of recovered aggregate itself. The most effective heating temperature which is considered not to give the damage to a quality of aggregate stays between 200-500degC. The effect of a duration at such temperature zone is relatively small. As a conclusion we have found that 300degC of heating temperature and 30-120 minutes of a duration in a rod mill with high efficiency of rubbing work for getting coarse aggregate and an agitate mill for fine aggregate might be proper operating conditions under which we can recover both coarse and fine aggregate with the quality within JASS 5N standard. (author)

The inherent advantages of delayed dismantling of decommissioning nuclear stations

International Nuclear Information System (INIS)

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

1985-01-01

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

Repair of a Kaplan blade sealing surface without dismantling the turbine; Instandsetzung einer Kaplanschaufel-Dichtflaeche ohne Turbinendemontage

Energy Technology Data Exchange (ETDEWEB)

Drygas, A.; Bauer, K. [E.ON Wasserkraft GmbH, Landshut (Germany)

2008-07-01

In spite of aiming at minimum maintenance costs, runners of Kaplan turbines need to be kept in good repair. Besides preserving their main function as an energy converter, ecological reasons have to be considered as well. The latter aspect accounts for fully functional, safe seals of the pivot-mounted Kaplan runner blades. Advanced wear of the sealing surfaces may require mechanical processing, which formerly called for a costly dismantling of the runner. A newly developed and patented processing device now allows for machining the worn out sealing surfaces without dismantling the runner, thus reducing costs considerably. The device was first successfully applied to a Kaplan turbine runner with a diameter of 5.35 m. The device, so far designed for grinding, will be enhanced for lathing, in order to obtain a process even more efficient when combining lathing and grinding. (orig.)

Research Project 'RB research nuclear reactor' (operation and maintenance), Final report

International Nuclear Information System (INIS)

1985-01-01

This final report covers operation and maintenance activities at the RB reactor during period from 1981-1985. First part covers the RB reactor operation, detailed description of reactor components, fuel, heavy water, reactor vessel, cooling system, equipment and instrumentation, auxiliary systems. It contains data concerned with dosimetry and radiation protection, reactor staff, and financial data. Second part deals maintenance, regular control and testing of reactor equipment and instrumentation. Third part is devoted to basic experimental options and utilization of the RB reactor including training

The concepts of the 'factory of the future' applied to cleanup and dismantling works

International Nuclear Information System (INIS)

Ghiban, A.; Girones, P.; Moitrier, C.; Gouhier, E.; Torreblanca, L.

2016-01-01

The 'factory of the future' relies on the implementation of new concepts and technologies like: connected robots, data analysis, virtual reality or enhanced reality in the fabrication processes. The article describes how these concepts can be used in cleanup or dismantling works. Both activities can be considered as the fabrication of a waste package and the processing plant as a factory. (A.C.)

Supply, operation and radioactive waste disposal of nuclear power plants

International Nuclear Information System (INIS)

Mohrhauer, H.; Krey, M.; Haag, G.; Wolters, J.; Merz, E.; Sauermann, P.F.

1981-07-01

The subject of 'Nuclear Fuel Cycle' is treated in 5 reports: 1. Uranium supply; 2. Fabrication and characteristics of fuel elements; 3. Design, operation and safety of nuclear power plants after Harrisburg; 4. Radioactive waste disposal of nuclear power plants - changed political scenery after 1979; 5. Shutdown and dismantling of LWR-KKW - state of knowledge and feasibility. (HP) [de

Metal Radioactive Waste Recycling from the Dismantling of Nuclear Facilities

International Nuclear Information System (INIS)

Fajt, B.; Prah, M.

1996-01-01

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

Contribution to a probabilistic safety analysis for the dismantling of slender reinforced-concrete structures; Ein Beitrag zur probabilistischen Sicherheitsanalyse von Abbruchvorgaengen turmartiger Bauwerke aus Stahlbeton

Energy Technology Data Exchange (ETDEWEB)

Lehnen, D J

1998-12-31

In the present work a concept of probabilistic safety-analysis for the dismantling of slender concrete-structures by tilting is developed. Based on requirements, that define a regular dismantling process, models describing characteristic limit-states of the building are derived. The connection of these limit-states allows rating the whole process. Uncertainties in the model-input are caught by using stochastic variables. Uncertainties in the model itself are caught by using inferior and superior modelling. With the help of two concluding examples it is shown, how the obtained probability of failure can be used to enhance objectiveness of safety-considerations. The numeric simulation is based on a Monte-Carlo method. (orig.) [Deutsch] In der vorliegenden Arbeit wird ein Konzept zur probabilistischen Sicherheitsanalyse des Fallrichtungsabbruchs turmartiger Bauwerke aus Stahlbeton entwickelt. Ausgehend von einem definierten Anforderungsprofil an den ordnungsgemaessen Ablauf eines Fallrichtungsabbruchs werden Modellvorstellungen herausgearbeitet, die einzelne Bauwerksgrenzzustaende abbilden, welche sich zur Beurteilung des Gesamtvorgangs eignen. Unsicherheiten in den Eingangsgroessen werden durch deren Auffassung als Wahrschlichkeitsdichten erfasst. Unsicherheiten in den Modellbildungen werden durch den jeweiligen Einsatz unterschaetzender und ueberschaetzender Betrachtungen, sogenannter Minoranten und Majoranten, beruecksichtigt. Anhand zweier Beispiele wird abschliessend demonstriert, wie die erhaltene operative Versagenswahrscheinlichkeit zur Objektivierung von Sicherheitsbetrachtungen herangezogen werden kann. Dabei beruht die numerische Umsetzung auf einer Monte-Carlo Simulation. (orig.)

Contribution to a probabilistic safety analysis for the dismantling of slender reinforced-concrete structures; Ein Beitrag zur probabilistischen Sicherheitsanalyse von Abbruchvorgaengen turmartiger Bauwerke aus Stahlbeton

Energy Technology Data Exchange (ETDEWEB)

Lehnen, D.J.

1997-12-31

In the present work a concept of probabilistic safety-analysis for the dismantling of slender concrete-structures by tilting is developed. Based on requirements, that define a regular dismantling process, models describing characteristic limit-states of the building are derived. The connection of these limit-states allows rating the whole process. Uncertainties in the model-input are caught by using stochastic variables. Uncertainties in the model itself are caught by using inferior and superior modelling. With the help of two concluding examples it is shown, how the obtained probability of failure can be used to enhance objectiveness of safety-considerations. The numeric simulation is based on a Monte-Carlo method. (orig.) [Deutsch] In der vorliegenden Arbeit wird ein Konzept zur probabilistischen Sicherheitsanalyse des Fallrichtungsabbruchs turmartiger Bauwerke aus Stahlbeton entwickelt. Ausgehend von einem definierten Anforderungsprofil an den ordnungsgemaessen Ablauf eines Fallrichtungsabbruchs werden Modellvorstellungen herausgearbeitet, die einzelne Bauwerksgrenzzustaende abbilden, welche sich zur Beurteilung des Gesamtvorgangs eignen. Unsicherheiten in den Eingangsgroessen werden durch deren Auffassung als Wahrschlichkeitsdichten erfasst. Unsicherheiten in den Modellbildungen werden durch den jeweiligen Einsatz unterschaetzender und ueberschaetzender Betrachtungen, sogenannter Minoranten und Majoranten, beruecksichtigt. Anhand zweier Beispiele wird abschliessend demonstriert, wie die erhaltene operative Versagenswahrscheinlichkeit zur Objektivierung von Sicherheitsbetrachtungen herangezogen werden kann. Dabei beruht die numerische Umsetzung auf einer Monte-Carlo Simulation. (orig.)

The Dismantling of the Japanese Model in Consumer Electronics

DEFF Research Database (Denmark)

Frøslev Christensen, Jens; Holm Olesen, Michael; Kjær, Jonas

This paper addresses an issue of great importance for the future organization of the consumerelectronics industry: the "battle" of control over component-based digitization. We are now witnessing the dismantling of the Japanese Model that has prevailed in consumer electronicsover the past 30 years....... Specialized and large-scale component suppliers have taken the lead inmost component-based innovations and have obtained increasingly powerful positions in thevalue chain of consumer electronics. This paper provides an in-depth study of the strategic andstructural ramifications of one such component...... technology. Aframework is developed to explain the reluctance of most of the large consumer electronicsgiants in developing/adopting this new technology.Key words: Consumer electronics, Industrial dynamics, Open InnovationJEL Codes: L6, L68, O32...

Method of dismantling a nuclear reactor

International Nuclear Information System (INIS)

Shirai, Masato; Hashimoto, Osamu.

1984-01-01

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

On evaluation of assessments of accruals of future dismantling costs

Energy Technology Data Exchange (ETDEWEB)

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

2013-07-01

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

On evaluation of assessments of accruals of future dismantling costs

International Nuclear Information System (INIS)

Labor, Bea; Lindskog, Staffan

2013-01-01

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

Control and treating technique of the nuclear wastes

International Nuclear Information System (INIS)

Ohira, Shigeru; Hayashi, Takumi

1997-01-01

In the large scale tritium treating and producing facilities such as ITER and others, they are presumed by absorbing, solving and diffusing tritium to various materials to be polluted instruments and equipments to become wastes by their partial or whole exchanges, recoveries, modifications, dismantlements and so forth. From a viewpoint of safety for the tritium, the following operations seem to be important among changing a part or whole of the objective instruments and equipments to wastes with finally disposable forms: to reduce the tritium remained volume as much as possible before the operations of exchange, dismantlement and so on, from viewpoint of risk reduction of the tritium emission into operation environment and outer environment; to reduce the tritium emission into the operation environment and circumference environment at operations of exchange, dismantlement and so on; to reduce the tritium leakage from the waste in storage and transportation before treatment; to protect the tritium pollution expansion at mechanical treatment processes such as cutting, pressing and so forth; and to reduce sufficiently the tritium concentration in the wastes to be disposed by proper treatment on a base of spirit of ALARA. (G.K.)

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.)

Development for recycle of dismantled metal wastes by decommissioning of NPP

International Nuclear Information System (INIS)

Asami, Tomohiro; Sato, Hiroshi; Hatakeyama, Mutsuo

2007-01-01

For recycle of dismantled metal wastes generated by the decommissioning of nuclear power plant, we examined a melting test for melting characterization of stainless steel scrap, designed the conceptual process to produce the recycle products, and developed a recycle cost evaluation code which is useful to make a rational planning for the waste management program (cost, determination of process, etc.) of these metal wastes. This report gives the summary of these development carried out from 2001 to 2005. This work was performed under the sponsorship of Ministry of Education, Culture, Sports, Science and Technology of Japan. (author)

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.)

Sampling of Reactor Pressure Vessel and Core Internals

International Nuclear Information System (INIS)

Oberhaeuser, R.

2011-01-01

Decommissioning and dismantling of nuclear power plants is a growing business, as a huge number of plants built in the 1970s have now reached their lifetime. It is well known that dismantling a nuclear power plant means an extraordinary expense for the owner respectively operator. Besides the dismantling works, the disposal of activated components and other nuclear waste is very expensive. Moreover, the fact that, in most countries, final disposal facilities are not available yet implies the need for interim storage on-site in specially built facilities. It can be concluded that a special attention is paid on producing a minimal radioactive waste volume. For this, optimized dismantling and packaging concepts have to be developed. The challenge is a fair balance between the obtainment of optimized packing and on the other side the fulfillment of stringent regulations set by the authorities and the storage requirements. The basis of a well-founded, optimized dismantling and packaging concept must always be the detailed knowledge of the radiological condition of the component to be dismantled. In the best case a 3- dimensional activation model contributes to this basis.