INTRODUCTION ENGINEERING DESIGN CALCULATIONS. INGÉNIERIE ÉTUDES CALCULS P. 10 to 13 TURNKEY PROJECTS GLOVE BOXES DOORS HATCHES METAL WORKING

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2 INTRODUCTION PRÉSENTATION P. 3 to 9 ENGINEERING DESIGN CALCULATIONS INGÉNIERIE ÉTUDES CALCULS P. 10 to 13 TURNKEY PROJECTS HOT CELLS GLOVE BOXES CASKS ENSEMBLIER CELLULES BLINDÉES BOITES À GANTS EMBALLAGES P. 14 to 24 P. 25 to 28 P. 29 to 32 P. 33 to 50 NEUTRON THERMAL PROTECTIONS PROTECTIONS NEUTRONIQUES P. THERMIQUES 51 to 55 DOORS HATCHES PORTES TRAPPES P. 56 to 58 METAL WORKING CHAUDRONNERIES DES MÉTAUX P. 59 to 61 ASSISTANCE SERVICES ASSISTANCE SERVICES P. 62 to 67 2

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4 La Hague Genas (headquarters) Marcoule Cadarache French company set up in 1830 Involved in the nuclear field since 1953 Capital of 1,800,000 Euros 100 % subsidiary of ROBATEL SA > 120 employees Turnover > 19 M LOCATIONS : Genas (headquarters) Rue de Genève - BP GENAS Cedex Tel Fax commercial@robatel.fr La Hague Z.I. de Digulleville BEAUMONT-HAGUE Tel Fax lahague@robatel.fr Marcoule Z.I. de L'Ardoise LAUDUN- L ARDOISE Tel Fax marcoule@robatel.fr Cadarache Zac du Pas de Menc VINON SUR VERDON Tel Fax cadarache@robatel.fr 4 Genas headquarters Establishment of Cadarache

5 ROBATEL Technologies, LLC Established in 2009 Subsidiary of ROBATEL SA, In charge of the ROBATEL Group s development on the American nuclear market. LOCATION : ROBATEL Technologies, LLC 5115 Bernard Drive, Suite 304 Roanoke, VA Tel.: sales@robateltech.com ROBATEL Technologies ROBAT EL Techn ologies Roanoke 5

6 Our skills Design, calculations, studies, Turnkey projects, Metal working, Mechanical engineering, Lead working, Site operations. 6

7 Company s certifications CEFRI no. 348 E Management of staff category "A" or "B" working under radiation, ISO 9001 / 2008 Quality Management in the design, manufacturing, installation, maintenance of equipments for industry and research in the nuclear field, Since 2010, ROBATEL is authorized to use decontaminated lead outgoing from CEA, CAEAR Notification of acceptance for the following areas : Genas : Domain D 4-2E Assistance in work control and occasional design studies, La Hague and Laudun : Domain D 3-1 «Intervention environment according to the radiation protection of the regulated area», MASE certification (Improvement Manual Enterprise Security), EDF Certificate of qualification to perform services in the following EDF qualification systems : Activity on fuel, Nuclear logistics maintenance, Intellectual services and technical assistance, Transport, QA/QC capabilities: NQA-1 & 10 CFR Part 71. Obtaining the Label supplier AREVA 7

8 Our main French customers AREVA (AREVA NC, AREVA TA, AREVA NP, TNI, SGN, MELOX, STMI, AREVA MED, FBFC, CERCA) CEA (CADARACHE, FONTENAY-AUX- ROSES, GRENOBLE, LA HAGUE, MARCOULE, PIERRELATTE, SACLAY, VALDUC, BRUYERES-LE-CHATEL) EDF (AMI DAC UTO CIDEN CNPE DCN) ANDRA, Radiation shielding of the French nuclear-powered submarines AIRBUS Defence & Space (ASTRIUM), ALSTOM, BOCCARD, BOUYGUES, CAMECA, CEGELEC,CIS BIO,CNIM, DAHER, DCNS,DGA (Délégation Générale pour l Armement),ENDEL, IRSN,GROUPE ONET,GANIL, LINAC,NUVIA, SPIE, SYNCHROTRON SOLEIL 8

9 9 Some of our customers abroad AUSTRALIA ANSTO BELGIUM ONDRAF / Institut des radioéléments (IRE) / IBA / SCK CEN / TRANSNUBEL / BELGOPROCESS, SYNATOM BRAZIL CTMSP CANADA TRIUMF CHINA China nuclear industry huaxing China nuclear energy industry corp TNPJVC CZECH REPUBLIC Nuclear Research Institute EGYPT Atomic Energy Establishment GERMANY Babcock Noell ITU GREAT BRITAIN BNFL ITALY EURATOM, Ispra / CNEN, Rome JAPAN Tokai Mura / JNFS MAROCCO CNESTEN NETHERLANDS Energy research Centre of the Netherlands NORWAY ABB Norsk Kabel ALGETA RUSSIA ZVEZDOTCHKA (Shipyard in Severodvinsk) SOUTH KOREA KAERI SWEDEN SKBF SWITZERLAND ZWILAG UKRAINE UKRATOMINSTRUMENTS U.S.A. SHAW AREVA MOX SERVICES LLC (JV) Department Of Energy Premier TECHNOLOGY Inc. U.S. ITER Project Office WCS EXELON

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11 Preliminary design, Studies of turnkey for completes installations, Feasibility studies. Mechanical calculations, Thermal calculations, Radioprotection calculations, Criticality calculations, Crash calculations. OUR SOFTWARE MEANS : 11 2D CAD: Autocad, 3D CAD: Solidworks, Spaceclaim, Calculations : Mechanical finite elements analysis: ANSYS 15.0, Cosmosworks Crash calculations: LS-DYNA V971 R7 Thermal finite elements analysis: ANSYS 15.0 Neutron and criticality calculations: TRIPOLI / SCALE 6.1 Radioprotection calculations: TRIPOLI / SCALE 6.1 / MICROSHIELD 6.10 Various analytic calculations (strength of materials, thermal, containment, ): MATHCAD 2001

12 Example of tradeoff study followed by manufacture VERDON laboratory, CEA Cadarache PRELIMINARY STUDY FOR THE CONSTRUCTION OF A LABORATORY, TAKING INTO ACCOUNT THE FOLLOWING AREAS : Civil engineering, Seismic calculations, Electricity high and low voltage, Drive control automation, Ventilation, Handling equipment, Mechanics, metal working, Future maintenance and operation, Risk analysis, On site assembly and testing. 12

13 Preliminary study example Mo / Tc laboratory, CIS BIO Schering PRELIMINARY STUDY FOR THE CONSTRUCTION OF A LABORATORY, TAKING INTO ACCOUNT THE FOLLOWING AREAS : Nuclear and pharmaceutical regulations (GMP), Production rate criteria, Interface civil engineering / new building, Control automation, Electricity high and low voltage, Ventilation, Handling equipment, Mechanics, metal working, Future maintenance and operation, Risk analysis. 13

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15 CEA STEMA facility located in Marcoule, France 15 A process system for the treatment of liquid effluents utilizing an full feature cementation line to include : Automatic transfer of new drums, Automated drum handling, positioning, self cleaning of the cementation injection line, filling, vibration packing/settling system, Automated recovery of the injection line cleaning water, Package drying and inspection, Preparation and filling of the drums with non active morter cap or sealing layer, Automatic placement and crimping of the drum lid, Computerized drum inspection after filling, curing and sealing, Automated drum radiation mesurement, Storage carousels / transfer station for the placement of a sealed drum into a transport cask, ICC, wiring and command control system incorporated into the process line.

16 Turn-key installations Waste sorting and conditioning unit, EDF/AMI Chinon This unit allows to sort waste thanks to a shielded tight cell equipped with remote controlled robotized handling means. These waste are sorted according to their physicochemical properties and radiological characteristics. Then, they are reconditioned for shipment to ANDRA s or other sites. THIS INSTALLATION IS COMPOSED OF THREE AREAS : A sorting cell made of concrete, totally lined with a stainless steel sleeve, equipped with telemanipulators, an overhead crane, a cutting press, and a spectrometry control station. This cell is a fire-barrier with regard to its environment, and is dimensioned to stand a seism, A loading/sealing station, with conveyors and elevators for leading new drums under two tight hatches communicating with the sorting cell, and two drum sealers, An evacuation lock-chamber equipped with an automatic device measuring the contamination by rubbing. 16

17 17 Waste sorting and conditioning unit, EDF/AMI Chinon

18 Radioactive waste cementation unit, ZWILAG (Switzerland) MAIN OPERATING FUNCTIONS : Reception and storage of various concrete components, Eventual pretreatment of some homogeneous waste, Preparation of the concrete (mixing), Draining of the concrete into drums or transfer towards concrete work stations, Cleaning of the injection system, and recovery of the rinsing effluents, Transfer, drying and control of the drums. 18

19 Outstocking of plutonium packings contained in drums located at the «Pégase» regulated nuclear facility of CEA CADARACHE MAIN FUNCTIONS PROVIDED : Outstocking of over 2,700 drums through packaging developed to meet the safety criteria, Transfer with sealing of the packagings drums to gloves boxes, Measures and wastes characterization, Compaction of empty drums, Injection of mortar in 870 liters drums containing the wastes, Evacuation of drums to storage, Aim of the project: 2 years to develop, manufacture and installation. 3 years of operation. 19

20 Equipment for MOX fuel production plant Rods final inspection and sorting Rods decontamination Filters pre-clogging Powders storage and handling Rods handling carriage 20

21 Incineration and cementing unit for very low level waste - Shipyard in Severodvinsk, Russia Factory assembly Incinerator Station for preparation of cement and bentonite Pushrod system for ashes Bicarbonate injection station Station for introduction of ashes, cement, bentonite and water Ceramic filter 21

22 AGATE, CEA Cadarache : Glove boxes of samples-taking, pneumatic transfer and distribution of pitchers SCOPE OF PROJECT : Integration of part of the process of the Advanced Management Workshop and Effluent Treatment, Design, manufacturing, installation on site, testing and commissioning of a set of four glove boxes (calculated earthquake) automated sample-taking, connected by a network of pneumatic transfert, Integration of all automated mechanical elements and control systems, Supply and installation of sorbonnes. 22

23 Equipment for French DCN Shielded shell Mass 70 tons Tooling K15 Mass 90 tons 23

24 CEA Design, manufacture, assembly and tests of a loading and unloading platform for type B casks CEA Valduc Collimator Docking for drums with the holding and the sealing of the lid EDF Design, manufacture, assembly and tests of a radioactive waste cementation unit 24 CEA Remote intervention for cutting in a contaminated environment CEA Specific device used for transfer, control and reconditioning of waste containers from storage pit

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26 Photo credit : P.Stroppa / CEA Design, manufacture and assembly Designer and manufacturer of hot cells since the 60s, ROBATEL Industries still develops new techniques and improves its skills in the field of design and manufacture of hot cells. Atalante 2 26

27 Design, manufacture and assembly Last references 2002 / cells for IRE, Belgium Hot cells for the nuclear center of Morocco Hot cells for SCK CEN, Belgium Hot cell for Cyceron Supply of 1,800 tons of lead shielding for the CEA Saclay (PELECI) Hot cells for SCK CEN, Belgium Hot cells of LECA, CEA Cadarache 27

28 Design, manufacture and assembly Last references 2007 / Pharmaceutic cell Cis Bio (IBA) Neutron cell (PNT7 Robatel) CEA Saclay Cell for microprobe Karlsruhe ALGETA cell on SCK plant IRE (renovating) AREVA MED cell ANSTO cell Cadecol cell (CEA) 28

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30 Study, manufacture, assembly MELOX MELOX MELOX CEA CEA CEA CEA COGEMA ZWILAG 30

31 Photo credit : P.Dumas / CEA Study and manufacture of internal equipment MELOX AREVA NC CEA IRSN ALL FILL (GB) 31

32 Glove boxes dedicated to a US MOX plant 32 Separating Hoppers Glove Boxes

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34 Design & approval Starting with the first French reactor ZOE : 60 years of experience Design and acquisition of 78 approvals of type B transportation casks, Design of many casks: type A, IP2, Extension of approvals, Elaboration of special arrangements. Underwater Transportation of a 1300 MW PWR fuel assembly Shuttle for vitrified HLW ORIGINAL TECHNICAL PATENTED : Neutron-absorbing and thermal protections: compounds ROBATEL no 9, 10, 21, 22, PNT7, PNT3, «Thermal switch» protection, Tightness by triple seals, Transport frame. R52 R62 R

35 Scale models - drop and fire tests Design and manufacture of scale models, Drop tests carried out on our In-house approved drop test facility, Performance of fire tests (800 C/1 472 F, 30 min). 9 meters drop test of a scale model of a type B cask: Movies of the falls using high speed cameras Instrumentation of test specimens (accelerometers...) 9 meters drop test of a scale model of a type B cask: ROBATEL drop test facility approved by the French nuclear safety authority (ASN) 35

36 Design & manufacture Over 1000 casks 36

37 R68 cask Transportation of concrete shells for EDF (type B cask) Stowage Specificities: Very sturdy containment system (100 mm of stainless steel) Very large loading capacities (2 150 L / kg) Main package dimensions: Height: H mm (7,4 ) Diameter: Ø mm (8,0 ) Gross weight: kg ( lbs) R68 Drop test specimen Radiological protections: Side (steel) : de 100 à 120 mm (3,9 to 4,7 ) Upper/lower sides (steel): 130 mm (5,1 ) Others protections: (thermal) R68 Drop tests Loading capacities: Cavity height: H 1320 mm (4,3 ) Cavity diameter: Ø mm (4,7 ) Cavity Volume: L Maximum payload: kg ( lbs) Compound ROBATEL PNT7 30 mm (1,2 ) Approvals: UN Type B(U) : ADR Applications: Transportation of activated and contaminated waste type filter or metal, packaged in concrete shells type C1 or C4 Transport mode: road Maximum activity: Maximum γ activity: 120 A2 31 TBq (Co 60 equivalent)

38 R72 cask Spent fuel rods transportation (type B cask) Main package dimensions: Radiological protections: (lead equivalent) Length: L mm (20,5 ) Diameter: Ø mm (5,51 ) Gross weight: kg ( lbs) Side: > 180 mm (7,0 ) Front: > 300 mm (11,8 ) Rear: > 290 mm (11,4 ) Loading capacities: Others protections: (neutron / thermal) Cavity length: L mm (17,5 ) Cavity diameter: Ø 140 mm (5,5 ) Compound ROBATEL PNT7 210 mm (8,3 ) PEHD Cavity volume: 80 L Approvals: (France + Validations abroad) Maximum payload: 650 kg (1 430 lbs) UN Type B(M) Fissile : ADR + RID Applications: Transportation of 10 highly irradiated spent fuel rods for R&D needs: Rods types: UO 2 or MOX, Rods from PWR 900, 1300 or 1450 MW, Compatibility with EPR rods. International transports from the PWR facilities to the research laboratories: France, Italy, Switzerland, Germany, Sweden, Denmark, Spain Spent fuel rods: UO 2 MOX Number of rods : 10 Burn-up : 100 GWd/tHM Cooling time: 6 month U 235 enrichment: 10% 1,5% Pu rate: - 15% Transport modes: road or rail.

39 R72 cask Spent fuel rods transportation (type B cask) Specificities of the cask: Double sealed enclosure controlled and resistant to accidental events: Cask s cavity closed and sealed by 2 closure lids (front and rear), Independent internal canister: closed by a sealed shielded plug, Loadings/unloadings allowed under water: By immersion in a pool, By interfacing to a sas under a pool, Loadings/unloadings in vertical or horizontal positions allowed, Has a transport frame allowing it to tilt, Has all the tools specifically dedicated to its operation. Drain port Front shock absorber Cask body Front sealed closure lid Canister sealed & shielded plug Front Rear Trrunions for handling and tipping Tightness flange Sealed canister Basket (capacity : 10 PWR rods) Stowage element Rear sealed closure lid Rear shock absorber

40 Transport frame of the R73 cask R73 cask Transportation of activated/contaminated metallic waste from EDF NPPs dismantling (type B cask) Main package dimensions: Radiological protections: (lead equivalent) Height: H mm (7,8 ) Diameter : Ø mm (7,3 ) Gross weight: kg ( lbs) Side: > 220 mm (8,6 ) Upper side: > 270 mm (10,6 ) Lower side: > 185 mm (7,3 ) Loading capacities: Others protections: (thermal) Cavity height: H 935 mm (3 ) Compound ROBATEL PNT7 30 mm (1,2 ) Cavity diameter: Ø mm (3,4 ) Cavity Volume: 790 L Maximum payload: kg (4 970 lbs) Approvals: UN Type B(U) : ADR + RID packagings manufactured Applications : Transport of metallic activated and contaminated waste (HLW and ILW) from the dismantling of the Nuclear Power Plants (1 rst generation), Transport modes: road or rail, Maximum activity: Maximum γ activity: A2 / TBq, TBq / 1 TBq/kg (Co 60 equivalent).

41 R73 cask Transportation of activated/contaminated metallic waste from EDF NPPs dismantling (type B cask) Handling devices for the upper shock absorber Upper shock absorber Depressurisation plug Tightness control plug Sealed closure lid Specificities of the cask: Handling device for the shielded plug Secondary shielded plug Very high loading capacity ( kg (4 970 lbs) / 790 L), Able to load the waste «in bulk», Metallic basket Very important shielding, Presence of a secondary shielded plug equipped with seals under the closure lid which ensures : the protection against the radiations and, the containment of the activity, even at the opening of the lid, Upper shock absorber fastening support Handling devices of the cask Cask body Lower shock absorber fastening support Has a specifically designed transport frame equipped with certified ISO corners, Lower shock absorber Has all the tools specifically dedicated to its operation

42 R74 cask Design, approval, manufacturing of 2 type B(U) casks R74 for wastes transportation Scotland (Dounreay) / Belgium (SCK) Main package dimensions: Radiological protections: (lead equivalent) Height: H mm (7,3 ) Diamter : Ø mm (9,0 ) Gross weight: kg ( lbs) Side: > 85 mm (3,4 ) Upper side: > 105 mm (4,2 ) Lower side: > 120 mm (4,7 ) Loading capacities: Others protections: (thermal) Cavity height: H mm (4,4 ) Compound ROBATEL PNT7 > 30 mm (1,2 ) Cavity diameter: Ø mm (5,9 ) Cavity volume: L Maximum payload: kg (9 430 lbs) Approvals: UN Type B(U) : ADR + RID + IMDG Applications: Cimented waste from the reprocessing of spent fuel, Very large loading capacities ( 3 drums of 500L), Transport modes: road, rail and maritime, Transport frame equipped with certified ISO corners to facilitate the transportation. Content: Maximum activity : 80 TBq / 320 A2, Maximum g activité: 75 TBq (Cs 137 equivalent).

43 R75 cask Design, approval and manufacturing of a type B cask for the transportation of 5 cluster guides for EDF UTO Applications: Transport of 5 irradiated cluster guides: Activated and contaminated metallic pieces, From 900, 1300 or 1450 MW PWRs, Optimized shielding relative to the specific activation profile of the cluster guides, Loadings / unloadings performed under water in vertical position, Transport frame equipped with certified ISO corners allowing the tipping of the cask in vertical position. Main package dimensions: Radiological protections: (lead equivalent) Transport mode: road, Total activity: 13 A2, Maximum γ activity: (Co 60 equivalent ) 10 TBq, 80 GBq/kg. Length: L mm (15,6 ) Diameter: Ø mm (6,7 ) Gross weight: kg ( lbs) Loading capacities: Cavity length: L mm (14,9 ) Cavity diameter: Ø 880 mm (2,9 ) Cavity volume: L Maximum payload: kg (4 905 lbs) Side: Front zone: > 62 mm (2,4 ) Rear zone: > 130 mm (5,1 ) Front: > 170 mm (6,7 ) Rear: > 145 mm (5,7 ) Others protections : (thermal) Compound ROBATEL PNT7 35 to 103 mm Approvals: UN Type B(U) : ADR 43 43

44 R76 cask Design, approval and manufacturing of 4 Type B casks for the transportation of waste drums for CEA Cadarache Main package dimensions: Radiological protections: (lead equivalent) Height: H mm (7,3 ) Diameter : Ø mm (7,3 ) Gross weight: kg ( lbs) Side: > 185 mm (7,3 ) Upper side: > 200 mm (7,9 ) Lower side: > 300 mm (11,8 ) Loading capacities: Others protections: (thermal) Cavity height: H 655 mm (2,15 ) Compound ROBATEL PNT3 38 mm (1,5 ) Cavity diameter: Ø mm (3,60 ) Applications: Cavity volume: 620 L Maximum payload: > 920 kg (2 030 lbs) Approvals: UN Type B(M) Fissile : ADR Content: Maximum activity: A2 / 100 A2/kg Maximum γ activity: 125 TBq (Co 60 equivalent) Fissile material: 210 g Transports by road of 2 to 5 technological waste drums (HLW & ILW): Contaminated and activated waste / Materials: metallic, minéral and organic, 60 to 200 L drums Modular internal fittings (metallic baskets, shielded plugs ), Very sturdy containment system: Withstands an hydrogen internal explosion*, Large loading capacities and important shielding + Secondary shielded plugs: Protection retained even when loading/unloading the drums. * (shown by explosions experimental testing)

45 R77s cask AREVA NC Design and manufacturing of a site cask for the transportation of 4 drums of alpha wastes Gross weight: Maximum payload: kg (7 720 lbs) 725 kg (1 600 lbs) 45 45

46 RT100 cask WCS (USA) Design, approval and manufacturing of 4 type B casks for the transportation of class B & C waste Gross weight: Maximum payload: kg ( lbs) kg ( lbs) 46

47 RTG32s / RTG33s casks EDF UTO Design and manufacture of 9 casks to store 32 or 33 clusters guides Gross weight: kg ( lbs) RA03 cask EDF CIDEN Design and manufacture of a cask for the transportation of the lid of the vessel of Chooz A reactor Gross weight: kg ( lbs) 47 47

48 R69s cask CABRI, IRSN Cadarache Transportation package for R&D spent fuel Approvals: Transport on Site Class 3 Fissile Main properties of the cask: Length: L mm (27,6 ) Diameter: Ø mm (7,9 ) Gross weight: kg ( lbs) Maximum payload: kg ( lbs) Transfert cask: Loading / Transfert / Unloading of an experimental device containing one spent fuel rod from the CABRI research reactor (UO 2 or MOX, Burn-up 90 GWd/tHM,Cooling time 24 month, Length: 560 mm (22 )), Protections: Radiological / Containment, Transportation overpack: Transport on site of the transfert cask loaded with the experimental device, Internal stowage systems, Protections: - Radiological, Transportation hull - Mécanical, (or overpack) - Thermal, - Containment. Transfert cask (and internal stowage devices) Maximum activities: A2 ( A2/kg) Fissile material: 35 g Protections: (radiological / neutron / thermal) Steel: 50 mm (1,6 ) Lead: 95 mm (3,7 ) Compounds ROBATEL : PNT3 et PNT7

49 Crédit photo : CEA Other recent references: CEA Design of type B cask for liquid radwaste EDF 30B and 48Y Casks (2010) (UF 6 transportation) CEA Design and manufacture of cask for contaminated glove boxes transportation EDF Design and approval of a type B cask for the transportation of concrete shells

50 Other recent references: EDF CIDEN Design and certification of casks family for the Superphénix s PNL transport, storage and disposal : Manufacture of 58 casks CEA: R64 Type B cask: transport of neutron sources CEA: Phénix cask CEA: Pégase container

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52 Compound ROBATEL no. 9 TM and no. 10 TM With a binder based on plaster, these neutron materials can be used for any protection which does not support any thermal or any particular mechanical constraints. It is always placed in metal casing, hermetically closed so that it maintains its optimal characteristics. In this case, access to the interior of the casing at the time of implementation should be as broad as possible. In the absence of containment, it should take account of the gradual loss of the free water by drying. This type of material was subject to irradiation tests until a fluence of 1, thermal neutrons/cm². No apparent degradation was observed. Chemical composition: boron, calcium, carbon, hydrogen, oxygen, sulfur, miscellaneous. Density : 1,15 to 1,25 g/cm³. Material approved by : CEA, AREVA, EDF. Wall CP9 (PPB) 52

53 Compound ROBATEL no. 21 TM and no. 22 TM Neutrophage materials made of a base of polyester resin. They have independent properties to any containment. They are generally molded to the shape and size desired and can be, if necessary, machined. They enable to make protection with a high mechanical strength and good heat resistance. This type of material was subjected to irradiation testing until an integrated flux of 1, thermal neutrons/cm². No apparent degradation was observed. Chemical composition: aluminum, boron, calcium, carbon, chlorine, hydrogen, oxygen, miscellaneous. Density : 1,20 to 1,30 g/cm³. Material approved by : CEA, AREVA, EDF. Facilities for 26 reactors in France, 1 in Korea, 1 in South Africa and 22 in China. 53

54 Compound ROBATEL PNT7 TM (Thermal Neutron Protection no. 7) and PNT3 TM These neutron-absorbing materials are as fine mortar and may be used for any protection subjected to thermal and mechanical stresses. They are preferably introduced in metal boxes, closed tightly so that they retain its optimum characteristics. In the absence of containment, it should take account of the gradual loss of the free water by drying. The crude mortar exactly reproduces the surface of the mold. Its ease of decontamination can be improved by applying a surface coating. This material is classified M0. Chemical composition: aluminum, boron, calcium, iron, hydrogen, oxygen, miscellaneous. Density : 1,75 to 1,95 g/cm³. Material approved by : CEA, AREVA, EDF, US Department of Energy. 54

55 NEUTRON AND GAMMA PROTECTIONS EPR TAISHAN 1&2 Design, calculation and manufacturing of neutron and gamma protections for the two EPRs to China. 55

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57 Over 1200 tons produced since 2000 Design, manufacture, shop and site assembly Lead shielded door IRSN Shielded hatch installed at Chernobyl Shielded hatch Belgoprocess 57

58 Recently manufactured : Shielded hatch (7 tons) for Chernobyl Motorized shielding (50 tons) for the anti-neutron protection of a cyclotron (Milan, Italy) 58 Hatch in hot cell CEA Saclay STELLA building Motorized doors for BELGOPROCESS (Belgium)

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60 Stainless steel and metal working MATERIALS Stainless steel: austenitic, superaustenitic, refractory, Aluminum and alloys, Titanium and alloys, Nickel and alloys (Monel, Inconel, Hastelloy ). CODES CARRIED OUT CODAP, ASME, RCC-M, RCC-MR, RCC-MX. Lid for Phénix (RCCM-R) 65 ton sleeves for nuclear fuel loading pools, DCN 16T forged device - CEA 60

61 Stainless steel and metal working OPERATING MODES QUALIFICATION References : NF EN 288.3, ASME, RCCM Number of reports : over 180, stainless steel : 304L, 316L heavy steel : U45N, UB6, C22 carbon steel : S235, A42 FP copper and alloys, borated stainless. MAIN WELDING PROCESSES TIG, Arc welding, Semi-automatic, filled wire, Semi-automatic, MIG and pulsed MIG, Automatic, submerged arc. Decontamination room EDF Fuel storage basket 61

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63 63 63 FENOSOL TM Rigid foam for filling, impact absorption, fire protection, insulation and many other applications. Shock absorber In partnership with the FENOSOL TM is a rigid phenolic foam. It is subject to continuous quality control under the ISO 9001(2000 version) Quality System, FENOSOL TM is used in the preparation of special containers for the transport of hazardous products for nuclear and defence industry purposes. It provides good mechanical protection and thermal insulation and is fire resistant. FENOSOL TM ADVANTAGES : Can be moulded or injected ; suitable for creating complex shapes and for filling largesized holes as well as small gaps, Available in a wide range of densities, Rigid, lightweight and strong, Very high mechanical strength in compression, Low, steady thermal conductivity makes for good insulation, Excellent fire resistance (category M1 fire rating), Negligible emissions (category F1 fumes rating), CFC and HCFC free for protection of environment.

64 Plastic boilermaking Filtration pilot Suction hood AREVA DESIGN AND MANUFACTURE OF COMPONENTS MADE OF : PVC, Polycarbonate, Perspex, Polypropylene, Polyethylene, Polyester resin, Corian. Ventilation shafts 64 Perspex gloves box Corian gloves box PVC gloves box Polycarbonate gloves box

65 Foundry Machining of Lead 3 ICPE lead foundry : Genas, Marcoule, La Hague, 2 ICPE allowed to cast lead from the nuclear industry, A capacity of several thousand tons per year, Parts of a few kilograms to more than 20 tons, An experience of more than 50 years in techniques of lead implementations for the nuclear industry. Pieces of large size Shielding on site Brick Machined slab Pipework protection 65

66 Dismantling ROBATEL Industries offers its customers a large range of dismantling services approved by the CEA (CAEAR approval related to studies, design and field work). Relying on its significant experience feedback ROBATEL Industries is in a position to display unavoidable changes in studies, manufacture and servicing. 66

67 Loading casks (fuel rods) on EDF plants Outline of proposed services Intervention crane with mobile protection Maintenance and refurbishment of hot cells, Annual maintenance contracts with AREVA & CEA, Loading of casks in pools and unloading, Maintenance of casks : regulatory maintenance of type B casks, repair of casks on site and in our workshops, tightness testing before transportation and assistance to loading. Tightness testing and maintenance of glove boxes, Pipe testing, Supply and assembly of biological protections, Installation of lock-chambers, Management and disposal of radioactive waste, Supply of spare parts and assembly in controlled area. 67

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