DECOMMISSIONING THE BELGONUCLEAIRE DESSEL MOX PLANT: PRESENTATION OF THE PROJECT AND SITUATION on 30/06/2011

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1 Proceedings Proceedings of The ASME of 2011 the 14th ASME International th International Conference Conference Environmental Environmental Remediation Remediation and Radioactive and Radioactive Waste Management ICEM2011 September 25-29, 2011, Reims, France ICEM DECOMMISSIONING THE BELGONUCLEAIRE DESSEL MOX PLANT: PRESENTATION OF THE PROJECT AND SITUATION on 30/06/2011 J.M. CUCHET, H. LIBON and C. VERHEYEN BELGONUCLEAIRE S.A. / N.V. Europalaan, 20 B2480 Dessel, Belgium J.BILY STUDSVIK GmbH Karlsruher Strae, 20 D75179 Pforzheim, Germany J.CUSTERS TECNUBEL N.V. Zandbergen, 1 B2480 Dessel, Belgium R.WALTHÉRY THV BELGOPROCESS / SCK CEN Gravenstraat, 73 B2480 Dessel, Belgium ABSTRACT BELGONUCLEAIRE has been operating the Dessel MOX plant at industrial scale between 1986 and In this period, 40 metric tons of plutonium (HM) has been processed into 90 reloads of MOX fuel for commercial light water reactors. The decision to stop the production in 2006 and to decommission the MOX plant was the result of the shrinkage of the MOX fuel market owing to political and customer s factors. As a significant part of the decommissioning project of the Dessel MOX plant, about 170 medium-sized glove boxes and about metric tons of structure and equipment outside the glove boxes are planned for decommissioning. The license for the decommissioning of the MOX plant was granted by Royal Decree in 2008 and the decommissioning works started in March 2009; the decommissioning works are executed by an integrated organization under leadership and responsibility of BELGONUCLEAIRE with 3 specialized contractors, namely TECNUBEL N.V., the joint venture (THV) BELGOPROCESS / SCK CEN and STUDSVIK GmbH In this paper, after having described the main characteristics of the project, the authors introduce the different organisational and technical options considered for the decommissioning of the glove boxes, and the main decision criteria (qualification of personnel and of processes, confinement, cutting techniques & radiation protection, safety aspects, alpha-bearing waste management) are analyzed as well. The progress, the feedback and the lessons learned mid 2011 are presented, giving the principal s and contractors point of view as well. GENERAL DESCRIPTION Situation of the BELGONUCLEAIRE MOX-Plant / Legal Context The BELGONUCLEAIRE (BN) production plant was commissioned in the early 70 s. In the mid-80 s, the industrial stage was reached. During the last two decades, 35 metric tons of plutonium were processed into about 650 tons of LWR fuel. The Dessel MOX plant is erected on a single floor and is arranged in an intricate network of interconnected glove-boxes with volumes ranging from 0.5 m³ up to 15 m³ and arranged on two levels. The decision to stop the production was taken in december 2005 and the conditioning and evacuation of the remaining production scrap was organized up to the point where the glove-boxes (GB s) are empty of reusable fissile materials. 1 Copyright 2011 by ASME

2 After cleaning, the radioactive material remaining in the glove-boxes as contaminant is limited to uranium and plutonium with following typical isotopic composition aged 5 years (wt% Pu-Am): 238 Pu 3.2% 239 Pu 50.2% 240 Pu 26.9% 241 Pu 7.6% 242 Pu 8.6% 241 Am 3.5%. According to the Belgian legislation, ONDRAF is the organization entrusted for the management (treatment/conditioning of the non conditioned radwaste, interim storage and final disposal of the conditioned ones) of the radioactive waste. The requirements for the acceptance of the non conditioned radioactive waste are provided in specifications elaborated by this organization. They describe (besides the required physico-chemical and radiological characterization) the waste packages leaving the BN plant to BELGOPROCESS (BP) for further processing and conditioning, before interim storage and final disposal. The waste classification, according to the ONDRAF specifications, is defined in TABLE I. TABLE I. Solid Waste Classification. Waste ID -Activity Range A1x < 40 MBq/m³ A2x Between 40 and 4000 MBq/m³ A3x > 4000 MBq/m³ The Belgian Royal Decree dated July 20 th, 2001 (ARBIS) provides with the legal frame for the protection of the population, workers and environment against the ionizing radiation hazards. To perform this decommissioning, BN needs to be granted a license from the Federal Agency for Nuclear Control (FANC). Moreover, the IAEA and EURATOM organizations continue to be in charge of the safeguards of the fissile materials remaining after cleaning. BELGONUCLEAIRE Plant Inventory For project management and obtaining the decommissioning authorizations, the full plant inventory for contaminated objects, including a radiological survey, was prepared based on samplings and measurements performed by an independent organization. This survey also includes ground samplings around the plant and building structure samples. The inventory, which includes 170 glove-boxes and their internal equipment and the infrastructures as well, is summarized in TABLE II, assuming a decommissioning of the glove-boxes in situ and a classification of the waste resulting from the decommissioning of the glove-boxes into the A3X category. Fig. 1. Typical Glove boxes Installation The waste volume includes the secondary wastes such as the disposable tents used for the decommissioning as well as waste resulting from cleaning and decommissioning process (steel, bags, ). TABLE II. Material Inventory. m³ Tons Free release / 1104 A1x A2x A3x (*) (*) Glove boxes, internals and secondary wastes DECOMMISSIONING STRATEGY BN decided performing the decommissioning as soon as possible because the activity results from long live radioelements and there is no activation. In addition, care has to be taken for some 241 Am build-up with time. All reusable fissile materials have been removed from the plant and the fissile materials remaining in the installation are treated as wastes. The cleaning of the glove-boxes and internal equipment is meant for reducing the contamination risk, the personnel exposure and the source term in the waste. The waste selection, volume or size reduction, characterization of the material to be wasted, waste adequate 2 Copyright 2011 by ASME

3 categorization and release up to the technical and economical possible extent will minimize the waste volume. Except for some particular cases, BN decided performing the glove-box disassembling and packing the resulting non conditioned waste into drums in its own plant to minimize contamination spreading risk during off-site transports. Because decommissioning is a specialized activity and because of the undetermined duration of the licensing process, it was early decided to subcontract the decommissioning work to specialized contractors. Selection of well-mastered techniques is crucial with respect to the safety and to the control of costs. Close relationship with Waste and Safety Authorities is also a key factor. Accurate estimation of primary and secondary waste helps the waste flow management. The waste will be transferred regularly to the final conditioning plant during the decommissioning period in containers and packaging close to the ones already used for the previous operations. Fig. 2. Simplified material flow diagram DECOMMISSIONING PROCESS list: Buildings + Site (for nuclear of non-nuclear re-use) R E L E A S E (*) Industrial dumpling place inert (*) According to RP113 and/or StrSchV BN MOX-Plant Unconditional release according to ARBIS Industrial recycling A1 A2 A3 The steps of the process are summarized in the following Removal of fissile material to the possible extent from the plant, Partial disassembly of unnecessary and non-contaminated equipment in the lobbies, Partial disassembly of the GB s in some workshops and laboratories, partial disassembly of equipment in the rod control workshop, to increase the available work floor space and drum storage capacity, Installation of additional equipment for waste management (NDA and size reduction equipment), Preparation of work areas for glove-tent installation, Process room by process room: H K + N C W Treatment by third parties (outside the plant) before release e.g. Melting in nuclear T/C facility Release according to RP89 Industrial recycling ingot ONDRAF T&C Interim Storage Disposal Empty the glove-box of most of its internal equipment (in situ), Isolate and separate GB s, Transfer GB in tent, GB decommissioning and waste processing under disposable glove-tent, Removing all remaining equipment from the rooms (platforms, stairs, lighting, ducts, etc), Installation of a temporary building ventilation system to back-up the existing one, Room decontamination (floor covering removal; floor, walls, ceilings shaving, etc), Remove of all equipment in the lobbies, Decommissioning of common utilities including glove box and building ventilation and filtering systems, Decommissioning of the additional equipment for waste processing and NDA, Free release of the buildings and site. The transfer to ONDRAF of waste drums containing non conditioned waste, for final processing and disposal, takes place continuously during the decommissioning. GLOVE BOX DECOMMISSIONING OPTIONS The first operation is a cleaning of the glove-boxes interior with residue removal. Then, the decommissioning and evacuation of the glove-box internal equipment is performed so far possible, except for what is necessary to maintain the confinement and glove-box ventilation or for some heavy or out of dimensions equipment parts. This takes place in situ using conventional tooling and installing so far possible additional evacuation bag-ports, if not already available on the glove-box or in the close neighborhood on other connected glove-boxes. The equipment is dismantled in components able to be handled by hand or by light handling devices and loaded in 200-liter drums. Performing this disassembling in situ also takes advantage of the existing radiation shielding. Materials are sorted as far as possible to optimize the drum filling. Several materials may be filled together, provided the drum load is characterized in weight percentage estimates for each physico-chemical type of waste (organic -plastic, PVC,.. -, metal, aluminium, ) according to the ONDRAF specifications. Equipment part size reduction is minimal due to their original design for easy maintenance purpose. Nevertheless, some size reduction operations are still needed. Next, the different glove-boxes are separated from the line, as necessary, in sub-units able to be moved together (most of the time in separate glove-boxes). A PVC bellows is secured on both sides of the intended separation, the existing link is disassembled, and the boxes slightly moved away. Then, the bellows is seal-welded on itself and cut to separate the boxes. Steel panel protections are placed over the sealed bellows on 3 Copyright 2011 by ASME

4 each side of the cut to cover them. If required to mitigate contamination spreading risks, this separation work can take place within a light tent erected around the work place. Contamination fixation at the internal face around the separation using varnish is also anticipated. For the in situ size reduction of the glove-boxes themselves and the remaining internal equipment, the Disposable glove-tent solution has been selected : the glovebox is introduced into a clean containment glove-tent fitted to the glove-box dimensions or the tent is erected around the glove-box itself: the latter tent undergoes specific commissioning tests before being put in operation. The tent features gloves and windows allow personnel to disassemble and cut the glove-box structure with cutting tools. The tent is ventilated and maintained in negative pressure with regard to the room. Ventilation system features the pressure controls, alarms and filters as for any glove-box. A port is managed to dock the drum wherein waste is loaded. PVC bag sealing technique, similar to bag-in/bag-out process, is used to replace full drums by empty ones. When the tent is empty, the tent is varnished to fix contamination and fold-down, rolled on it self, and wasted after sherdding. Cutting technologies Waste size reduction to fill as much as possible the drums is important to minimize final waste volume and cost. BN tested several cutting methods, which are compared in TABLE III. TABLE III. Comparison of Cutting Techniques. Abrasive Plasma Sawing Nibbling Grinding Not Generally Part Clamping Needed Needed necessary needed Temp C Room Temp. Tool Speed to N/A m/sec 0.01 Low up to Cut Capacity High Medium Medium 7mm thick Contaminatio n spread risk Very high High Low Low Fire Risk Very high High Low Low Hands-off Needed Possible No No Typical BN glove-box design features a 5 mm welded shell type box made of bended profiles with wide corner radius (rounded edge corners). The window panels are clamped on the 5 mm plates or profiles Few glove-boxes (around 10% of the glove-boxes) feature a very heavy base plate (10-38 mm) on which a 5 mm shell structure is attached (screws and tightness welds). In conclusion, except for some particularities, most of those structures are 5 mm thick, thus accessible for sawing or nibbling. Benefits of the best available techniques BN considers the disposable glove-tent and the cold cutting techniques as the best available technique at the present time as depicted in the previous paragraphs. The benefits using these techniques are summarized below: 1. Allow elaborating and presenting to the Waste Authorities a decommissioning plan supported by experience and operational records of activities in a similar plant (primary and secondary waste volumes, costs, time schedule, etc); 2. Allow elaborating and presenting to the Safety and Licensing Authorities a comprehensive safety file based on existing experience and operational records; 3. Allow implementation of decommissioning options to be operated by different actors (such as third parties specialized in decommissioning services) under different contractual schemes (lump sum and/or costreimbursed / incentivized contracts); 4. Allow parallel processing in different workshops and mastering of overall time-schedule; 5. Allow elaborating and presenting to the BN s board a manageable decommissioning project with time schedule, cost, and reduced uncertainties. Furthermore, the flexibility of operation allowed by the glove-tent allows to control precisely the content in weight or in fissile materials of the waste drums, which is a strategic condition for waste acceptance and transport. DECOMMISSIONING OF EQUIPMENT OUTSIDE THE GLOVE BOXES AND RELEASE STRATEGY The strategy for the decommissioning of equipment outside the glove boxes has been chosen in view of free release of material as much as possible. The basis of the release strategy is described in the paragraphs below. Traceability and classification On one hand, regulations request traceability of operations and of released material; this leads to a batch-based material management. On the other hand, the following applies for solids that qualify for free release: They occur in different physical forms (depending on the composing material; shape and size of the component, bulk or separate components, real or 4 Copyright 2011 by ASME

5 apparent density, coating and state of the surface (corrosion/porosity), total amount in similar physical form). Subsequently, they exhibit different suitability to mass- and/or surface-based free release. So, they imply the use of specific inspection methods. They have a different operational historical record: during their lifetime, they have established a different exposure to contamination. There are differences for materials having spent shorter or longer periods in controlled area rooms with or without risks of contamination, materials that have contained liquids or that have been transported with or without risk of contamination. Therefore, it seems logical to use the similar free release schemes to materials and substances with identical physical form, identical suitability to inspection and identical operational historical record. The operational organization, the treatment and storage of material are substantially simplified by splitting large amounts into smaller amounts and to select a number of well adapted standard carriers (drums, pallets, sampling cans ) Finally, when (nuclear or non-nuclear) material is to be recycled, recycling companies like to receive a characterization of the material. For all these reasons, free release management will be organized in batches, while the treatment (e.g. shredding in situ) will based on 200-L drums. When material is divided into batches, care has to be taken that the subsequent treatment and inspection is corresponding to the operational historical records. According to Article 23.1 of ARBIS, a log book is maintained by Control services. Homogenization The possibility of homogenization of material to be free released offers a number of advantages: It simplifies the application of mass-based concentration criteria on materials that have been subject to surface contamination It offers the possibility in the laboratory to measure samples (in stead of total amounts), with more sensitive methods and under better circumstances. When necessary, small amounts of similar materials with different historical records can be offered a new historical record. Consequently, a homogenous batch can be composed (e.g. secondary paint stripping waste) Homogenization can be carried out in a number of ways. Some examples: Blending of powder or granular waste Melting of metals in an induction furnace Crushing of rubble generated by shaving and scabbling operations, followed by blending Shredding of cables Qualification processes are still going on for the following ways: Shredding of organic substance (piping, linoleum, various PVC-components, ), followed by blending Shredding of switchboard material and computer parts, followed by blending Sample-taking must be carried out, the number of samples per batch being to be previously approved by the Belgian control body. Final destination As a reminder, regulation requests the following: The destination must be guaranteed and proven. A removal register has to be kept of the material that was free released. The possibility of reuse of the material in other nuclear applications has to be examined. Regional legislation After the unconditional free release according to federal legislation, the material and waste will receive a destination compliant with Flemish regional legislation. This means they have to be either industrially recycled or disposed as industrial waste on an licensed repository by a qualified recycler or operator. A number of toxic waste materials, mentioned in the table beneath, have to comply with regional regulation (VLAREM). Material Asbestos or asbestos contaminated material Heavy metal (Lead and Cadmium) Examples of foreseen techniques Destination Removal to repositories of Class 1 Industrial recycling of removal to repositories of Class 2 Recycling by melting: large amounts of steel material will be recycled by melting. This way, the material can be unconditionally or conditionally recycled. The melting is carried out by companies that operate such an installation,. Two companies have been qualified. Apart from the volume reduction, melting has a decontaminating effect in case of uranium or plutonium contamination; melting causes plutonium and uranium to be concentrated in the slag and the dust while the metal has been decontaminated. 5 Copyright 2011 by ASME

6 Examples of material to be recycled by melting are the difficult to measure, and externally non-contaminated tubular structures. They have been used in support for glove boxes, beams and in fluid piping. The advantage is a substantial reduction of free release on site measurements. Decontamination: various decontamination techniques can be applied, depending on the nature and size of the object or material. Decontamination will only be carried out if the cost of the operation is compensated by the profit that is made by declassification. Technique Ultra sound baths with Saxin Cleaning by brush (with Saxin) Mobile pickling installation with needle scabbler (and dust collection) Cleaning by washing and/or mechanical polishing Material suited for the technique small and medium sized pieces in stainless steel, plastic, anodized aluminum Medium sized and large pieces in painted carbon steel (tables, beams, platforms, rod bins...) Lead glas shielding panels Decontamination of the rooms in the controlled area: in view of the free release of the buildings in the controlled area, following techniques can be used for decontamination of the floors, walls and ceiling. Scabbling Shaving (using rotary tools and dust collection), as illustrated in Figure 3. PROJECT ORGANIZATION March 2008, BN examined the possibility of fixed price contract with a qualified contractor; this option has not been finalized, the risk being judged too big. End of 2008 Because decommissioning is a specialized activity and not part of BN s past core business, and because of the undetermined duration of the license process, it was early decided to subcontract the decommissioning work to specialized companies. Starting, BN decided to take the lead of an integrated decommissioning organization with qualified contractors. Contracts were signed in 2009 with: STUDSVIK GmbH (D) The joint venture THV BELGOPROCESS & SCK CEN (B) TECNUBEL N.V. (B) Fig. 4 describes the integrated organization which is operational since the start of the decommissioning works.. Waste Control Nuclear Waste Release on site Security Officer Security Decommissioning Managing Director Methods Decommissioni ng GB THV BP- Studsvik Tecnubel Decommissioni ng Utilities Strategy, Contracts and Planning Safety, Quality and Environment Health Physics Radiation P t ti Radiation Industrial Safety Quality and Environment Safeguards Personnel, Adm. & Communication Personnel & Purchasing Secretary Office BN ti BN safety contractors Fig. 3. Shaving of a concrete wall 1 (during process qualification) Fig. 4. Integrated organization The planning of the decommissioning project is the following: 2009 : training and qualification of the personnel; 2010 : decommissioning glove-boxes; 2011 : decommissioning glove-boxes; 2012 : decommissioning glove-boxes; 2013 : decommissioning infrastructures; 2014 : free release of the buildings and of the site. 1 BOLERO system (with the courtesy of STUDSVIK) 6 Copyright 2011 by ASME

7 SAFETY STRATEGY Actions have been undertaken by BN on 3 levels: level 1 : selection of the contractors : only specialized and qualified companies have been considered; level 2 : qualification and training of the operators training center; mentorship principle for each new operator; continuous evaluation; level 3 : work organization and decommissioning work sequences (e.g. emptying the internals in the glove-boxes themselves, when starting the work); work protection (e.g. use of shielding panels - see beneath -). In the frame of the training of the contractors, a training center has been developed (see Fig.5); its main functions and objectives are the following: Simulation of activities in cold conditions use of glove boxes (GB); use of individual protection equipment; bringing material in and out of GB; welding of plastics and bags; docking of waste drums, filling and disconnecting; setting up decommissioning tent with its infrastructure; working in GB s and tents: sawing, cutting, nibbling. (Training in mockups: 4 GB s and 2 tents) Qualification of decommissioning techniques (e.g. for handling and decommissioning of ball mills, sinterfurnaces,...) RADIATION PROTECTION / RISK ANALYSIS Radiation protection One of the main concerns of BN is to limit, up to a possible extent, the personnel s radiation exposure. The target is below the limits defined in the State Regulations and is according to the ALARA principles. The main exposure is coming from radiation generated by 241 Am and neutron irradiation. For this reason, BN developed reusable modular transparent shielding panels being placed between the glovetent and the workers. The panel is attached to the external tent supporting structure, as shown on Fig.6. Fig. 6. Example of modular shielding panels mounted o n a glove tent Before starting a decommissioning operation the radiation level is measured and the need for possible additional shielding is checked. Risk analysis Risk prevention and mitigation mainly concern criticality, fire risk and loss of containment, in addition to the common risk of industrial activities (load drops, injuries, etc). Fig. 5. Training in cold conditions for working in glove boxes and in tents Criticality Criticality risk is greatly reduced because most of fissile material is removed from the plant before beginning the decommissioning operations. Nevertheless, simplified criticality prevention rules remain applicable during the glovebox decommissioning period until the total amount of fissile materials is less than 805 g. For example, any contaminated material transfer within the plant needs to be declared and only takes place after approval of the Health and Physics Department. All transfers are recorded as to assess the fissile 7 Copyright 2011 by ASME

8 material and to comply with the international rules of safeguards. Fire Fire risk is controlled in the following ways: Flammable materials such as hydraulic fluids and process gases (Ar + H 2 ) have been completely evacuated well before the decommissioning operation begins. There is no operation anticipated on flammable material. The tent sheets are made of materials that do not propagate flames. No thermal process or thermal equipment is used for the decommissioning operation. BN selected cold and dry cutting processes; furthermore, no flammable solvent is used. Electric power supply to the glove-box equipment is shutdown before decommissioning and controlled by a consignation process under the Health and Physics Department s responsibility. Electric devices used during the whole decommissioning period are verified for their conformity to the general regulations (AREI and CE stamp). This includes both existing and new devices. Periodical thermographic survey is foreseen. Work organization and preparation are also key factors. All cutting processes have been qualified in inactive and active conditions. Any decommissioning activities are sequenced, described in writing, debated and approved by the Health and Physics Department before engaging any action. Operators will be selected, educated and trained for these glove-box activities. Shop floor verifications for tidiness, cleanness, escape paths free access, fire fighting devices location and markings will be systematically performed. Each tent features fire detection linked to local alarms (visual and audible) and to the general plant alarm network. Additional fire suppression sources will be provided on the working area as required for use in the tent or in the room. Personnel will be trained to use them. Compartmentalization of the process rooms is maintained operational during decommissioning works. preventing tent overstressing. Each tent is tested for strength and tightness when fabricated; tightness is verified again just before the decommissioning operation begins and before the tent inside becomes contaminated. Fixing the contamination in the tent After cutting of the glove-box, the use of water-based varnish for fixing the contamination at the inner surface of the tent improves the safety of the tent fold-down operation. PROCESS VALIDATIONS In support to the license filing documentation, several demonstrations of the cutting techniques took place with noncontaminated and contaminated material assessing their safety and efficiency. Tent configurations were developed and improved. As examples, several contaminated glove-boxes representative of the plant s glove-boxes stock were wasted using the selected processes, after having taught the staff with size reduction on dummy GB s. WASTE MANAGEMENT / PACKAGING DRUMS Drums used for the safe transport (in a dedicated transport overpack) of the non conditioned waste feature a 200-liter capacity with standardized shape. The internal faces are protected by a polyethylene sheet to receive falling parts without damaging the drum coating. At the upper part of the drum, a vinyl skirt clamped on the inner side of the drum by an expendable ring provides the α-tight connection with the docking station. When the drum is full, this skirt is seal-welded to confine the drum content to ensure the tightness of the final product according to ISO standard. A steel lid with seal is then clamped on the top. The drums are qualified to withstand a fall of 1 m with full load. An absolute filter prevents any drum pressure increase resulting from potential radiolysis gas release during storage. Loss of containment Containment is maintained by the glove-box ventilation system (high depression extraction and HEPA filters) on which the glove-tents will be coupled. Each tent will be equipped, as a production glove-box, with a normal extraction flow able to maintain the tent differential pressure in case of a breach (glove tear-out) with an adequate flow speed through the expected breach (for prevention of contamination spreading), and a vacuum breaker valve to limit the differential negative pressure Fig. 7. Drum during preparation (in cold conditions) 8 Copyright 2011 by ASME

9 The drum loading limits are as follows: Total maximum gross weight : 300kg Presence of organic material : no limit CONCLUSIONS / PROGRESS OF THE WORKS On 30/06/2011, it means ~28 months after start of the decommissioning works, the following conclusions can be drawn: The integration and qualification of the different contractors has been achieved by end Safety results : No labour accidents in the controlled area; No labour incidents with nuclear impact; The individual yearly exposure does not exceed the dose limit of 12 msv. Turnover of personnel : < 10 % Progress of the work : 45% of glove boxes are dismantled, conform to the expectations; 40% of the equipment outside the glove boxes have been treated ; 70 T metal scraps have been sent to a melting facility; Fillings rate of the radwaste drums: conform to the expectations. REFERENCES 1. R.BAUMANN, P.FABER, Decommissioning Techniques for Plutonium-Contaminated Gloveboxes: Experience from First Year of Decommissioning, 6 th International Symposium of Radioactive and Decommissioning Wastes, Kontec 2003, Berlin, Germany, March A.VANDERGHEYNST, J.M. CUCHET, Strategy For Decommissioning of Glove-Boxes in the Belgonucleaire Dessel Mox Fuel Fabrication Plant, 11th International Conference on Environmental Remediation and Radioactive Waste Management, ICEM`07, September 2-6, 2007, Bruges, Belgium. 3. A.VANDERGHEYNST, J.M. CUCHET, An Evolutionary Approach For the Decommissioning of the Glove Boxes in the Belgonucleaire Dessel Plant, SFEN International Conference Decommissioning Challenges: an Industrial Reality?, September 28 to October 2, 2008, Avignon, France. ACRONYMS AND ABBREVIATIONS Definition ARBIS Algemeen Reglement voor de Bescherming van de bevolking en van de werknemers tegen het gevaar van de Ioniserende Straling (= Belgian Regulation for Radiation Control, as per Royal Decree d.d. July 20, 2001) BEL-V Filiale van het FANC (= Supervisory Body) AREI Algemene Reglement voor Elektrische Installaties (= Belgian General Regulation for Electrical Installations), as per Royal Decree d.d. June 2, 2008) FANC Belgian Federal Agency for Nuclear Controls ONDRAF Organisme Fédéral des Déchets Radioactifs et des Matières Fissiles Enrichies (= Belgian Radwaste Administration) VLAREM Vlaams Reglement op de Milieuvergunningen (= Flemish regional regulatory frame for environment) StrSchV Strahlenschutzverordnung (= German Regulation for Radiation Control) 9 Copyright 2011 by ASME