Generic description of MITICA Beam Line Components and expected procurement activities

Transcription

1 MITICA Beam Line Components Ref.: F4E_D_25FLDW, v1.0 Generic description of MITICA Beam Line Components and expected procurement activities F4E_D_25FLDW, v1.0 Page 1/23

2 Table of Contents G1. INTRODUCTION AND BACKGROUND ITER HEATING AND CURRENT DRIVE NEUTRAL BEAM (HNB) SYSTEM OPERATING PRINCIPLE THE NEUTRAL BEAM TEST FACILITY (NBTF) MITICA BEAM LINE COMPONENTS (BLCS) - GENERIC DESCRIPTION OF THE HARDWARE..8 G2. OBJECTIVES AND SCOPE OF THE WORK...21 G3. INPUT DATA...22 G4. FUSION FOR ENERGY CONTACT PERSONS...22 F4E_D_25FLDW, v1.0 Page 2/23

3 PRELIMINARY REFERENCES AND APPLICABLE DOCUMENTS [1] Draft Technical Specification for the supply of the Beam Line Components for MITICA experiment [2] 3D CATIA models of the of the MITICA BLCs and of their interfaces [3] 2D drawings of the of the MITICA BLCs TERMS AND DEFINITIONS Term Definition Abbreviation Electrostatic Residual Ion Dump Fusion For Energy ITER International Organisation Megavolt ITER Injector & Concept Advancement MITICA Beam Line Components Neutraliser and Electron Dump Padova Research on Injector Megavolt Accelerated / Neutral Beam Test Facility Source for Production of Ion of Deuterium Extracted from Rf plasma Swirl Tube Element Supplier Beam Line Component which aim is to dump the residual ions following the passage of the beam in the NED The European Joint Undertaking for ITER and the Development of Fusion Energy (the European Union Domestic Agency) ITER is an organization established by seven parties through a Joint Implementation Agreement to build ITER Full scale Heating and Current Drive Neutral Beam Injector Components of the MITICA Neutral Beam that are in the line of the ion beam after the ion source Beam Line Component which aim is to neutralise the beam and protect the cryopumps against accelerated particles with diverging trajectories Test facility coordinating the Neutral Beam R&D activities. Full scale ion source Part of the Calorimeter assembly which intercepts the neutral beam Supplier that will be awarded the contract for the procurement of the BLCs ERID EU DA or F4E ITER MITICA BLCs NED PRIMA / NBTF SPIDER STE - F4E_D_25FLDW, v1.0 Page 3/23

4 G1. INTRODUCTION AND BACKGROUND 1.1 ITER HEATING AND CURRENT DRIVE NEUTRAL BEAM (HNB) SYSTEM The ITER project aims to build a fusion device, twice the size of the largest current devices, with the goal of demonstrating the scientific and technical feasibility of fusion power. In ITER, the plasma burning conditions will be obtained and controlled by additional Heating and Current Drive systems, including Ion Cyclotron (IC), Electron Cyclotron (EC) and Neutral Beam (NB) systems, whose aim is to inject energy into the plasma. Neutral Beam injectors are used to shoot uncharged high-energy particles into the plasma where, by way of collision, they transfer their energy to the plasma particles. Before injection, deuterium atoms must be accelerated outside of the tokamak to a kinetic energy of 1 Mega electron Volt (MeV). Only atoms with a positive or a negative charge can be accelerated by electric field. However, the process must then be reversed before injection into the fusion plasma; otherwise the electrically-charged ion would be deflected by the magnetic field of the plasma cage. The large plasma volume at ITER will impose new requirements on this proven method of injection: the particles will have to move three to four times faster than in previous systems in order to penetrate far enough into the plasma. At ITER a negatively-charged ion source has been selected. In ITER, two Heating and current drive Neutral Beam injectors (HNBs) are currently foreseen. The HNB system contributes to Q 10 operation heating the plasma and driving current for steady-state operation at Q 5. Each HNB will be able to deliver up to 16.7 MW power of neutral particles to the plasma, at 1MeV of energy (primarily to obtain deep enough penetration of the beam in the plasma and to drive current, and finally to maximise the power per injector) and with a pulse 3 600s long. Thus, the HNB system will provide a power of 33 MW from 2 injectors, which could be upgraded to 50 MW in total with a third injector. Figure Neutral Beam injection into plasma F4E_D_25FLDW, v1.0 Page 4/23

5 1.2 OPERATING PRINCIPLE Negative ions are generated in the ion source (or Beam Source) and are extracted and then accelerated through an electrostatic accelerator. The ions are neutralised in the neutraliser, which also adsorb the heat load coming from the co-accelerated electrons on the panels of the electron dump. Emerging from the neutraliser will be a neutral beam (60% of the original negative ion beam) and negative and positive ion beams, each with approximately 20% of the initial power/current. The charged beams are removed from the path of the neutral beam in a controlled manner by the Electrostatic Residual Ion Dump (ERID). This is obtained by electrostatic deflection of the charged beams onto a water-cooled collector system designed to accept the high power-density. The beam of neutral atoms is either injected into the ITER plasma or intercepted inside the injector by a calorimeter with movable panels which can accept the full neutral beam power. Figure Principle scheme of a neutral beam system Figure The ITER Heating Neutral Beam F4E_D_25FLDW, v1.0 Page 5/23

6 1.3 THE NEUTRAL BEAM TEST FACILITY (NBTF) The procurement of the ITER NB system presents several challenges. Indeed, even if the method is well proven and Neutral Beam injector are installed in several tokamak, these specifications are cumulatively (current x energy x pulse length) 3 orders of magnitude higher than the performance of existing devices. Therefore, a robust R&D program is necessary in order to complete the development and optimize the HNB operation, maximize the reliability of the injectors, develop technologies for the injectors, test key remote handling tools and procedures, improve availability of the NB injectors, test new concept to improve efficiency and achieve the required parameters within the tight constraints due to the ITER construction plan and the close integration of the HNB injectors with the ITER machine and tokamak building. Therefore the establishment of a dedicated full scale test facility is a necessary step towards the construction of the ITER injector and has become a centre piece of the HNB development strategy. This strategy is organized in the establishment of the Neutral Beam Test Facility PRIMA (Padova Research on Injector Megavolt Accelerated) at Padova (Italy). The PRIMA Test Facility is conducted by CONSORZIO RFX under European Management and Funding from Fusion for Energy (F4E). The laboratory that will host the prototype experimental injector is a complex of new buildings erected in the site of the National Council of Research (C.N.R.) of Padova in Corso Stati Uniti, 4. PRIMA identifies all the Neutral Beam R&D activities that will be realized in the framework of the international agreements with all the different actors. PRIMA activities foresee the construction, the installation and the exploitation of two experimental devices: SPIDER (Source for Production of Ion of Deuterium Extracted from Rf plasma) is the first experiment that will be hosted in the premises of the new test facility. SPIDER is a full scale ion source test facility in which will be conducted experiments that will allow developing the knowledge on negative ions and optimizing the maximization and uniformity of negative ion production. MITICA (Megavolt ITER Injector & Concept Advancement) is the second of the two experiments which will be hosted in the premises of the new test facility. MITICA is aiming at testing and qualifying at full scale Heating and Current Drive Neutral Beam Injector. MITICA will be the injector prototype of the two HNB injectors which will be installed in ITER. The injector will be developed in order to be able to emit a beam of neutral particles of deuterium accelerated up to 1 MeV. Figure Aerial view of the PRIMA site and PRIMA buildings F4E_D_25FLDW, v1.0 Page 6/23

7 Figure Integration of SPIDER, MITICA, auxiliary plants and power supplies in PRIMA facilities Figure MITICA experiment including the Beam Line Components F4E_D_25FLDW, v1.0 Page 7/23

8 1.4 MITICA Beam Line Components (BLCs) - Generic description of the hardware The supply of MITICA Beam Line Components includes one Neutraliser and Electron Dump (NED), one Electrostatic Residual Ion Dump (ERID), one Calorimeter and a number of Components Common Equipment (CCEs). Specific manufacturing, technical and material requirements for the BLCs Numerous heterogeneous joints are present in the BLCs. Deep drilling technology of CuCr1Zr plates for the walls of NED and ERID is necessary. Structural elements are made of AISI 304L and water piping is made of AISI 316L. Procured materials, design, and construction are compliant with ASME Boiler and Pressure Vessel Code Section VIII; component assemblies are manufactured in conformance with Pressure Equipment Directive 97/23/EC. High heat flux elements for the ERID panels and Calorimeter swirl tubes are made of CuCr1Zr alloy; the reference heat treatment is solution annealed at C for 1h, water quenched, then aged at C for 2 4 h. Ageing can be performed either before, during, or after the components are manufactured and welded. Competency requirements to main contractor are experience in vacuum technology and testing especially for water-vacuum barriers, assembly and metrology for coordinate tracking and recording during assembly, development of production drawings based on engineering design, project management with subcontractors. Several tests are required: qualification tests for pre-production prototypes and certificates/tests for the purchased materials; factory tests including dimensional checks, water proof tests, vacuum leak tests, electrical tests; assembly and acceptance on-site tests carried out in the MITICA assembly room. Various electron beam welds are necessary for the ERID and Calorimeter components. Adjustable Beds Each Beam Line Component is bolted on the vacuum vessel floor by means of an intermediate component (Adjustable Bed) providing adjustable features to align the components to the injector beam line. The three Adjustable Beds, which are made by welding of AISI 304L semi-finished products, have a mass of about 1 ton each. F4E_D_25FLDW, v1.0 Page 8/23

9 Neutraliser and Electron Dump (NED) The main function of the Neutralizer is to neutralize the beam consisting of negative deuterium/hydrogen ions as it emerges from the accelerator. This function is achieved by charge exchange reactions between the deuterium/hydrogen negative ion beam and deuterium/hydrogen atoms injected inside the Neutralizer. Figure Neutraliser and the electron dump The Neutralizer also provides a total thermal power measurement on itself by measuring temperature levels at several positions on the actively cooled panels and by measuring the total coolant flow rate. Thermal measurements for determining the angular misalignment in the horizontal direction and steering are foreseen; these thermal measurements and water temperature measurements are intended mostly for protection against overheating due to imprecision in the beam optics. Additional panels are placed out of the Neutraliser main cross-section, constituting the Electron Dump. These panels realise a protection against accelerated particles with diverging trajectories for the cryopumps, which are located at the side of the Beam Line Components and would be otherwise heated considerably. Thermal measurements for determining the beam angular misalignment in the horizontal direction and steering are foreseen; these thermal measurements and water temperature measurements are intended mostly for protection against overheating due to imprecision in the beam optics. The main function of the Electron Dump is to dump electrons power as they emerge from the accelerator and to protect the cryopump and other components from the electrons thermal load. This function is achieved by dumping the electrons onto water-cooled dumping panels or baffles to be designed for accepting high power density. The Electron Dump also provides a total thermal power measurement on itself by measuring temperature levels at several positions on the actively cooled elements and by evaluating the total coolant flow rate. The Neutralizer (see Figure 1-7 and Figure 1-8) is crossed by four vertical beam channels of rectangular cross-section, each approximately 3m long and 1.7 m high. The beam channels are delimited by five walls (one centre, two middle, and two side walls) that are formed each by three panels (front, middle and rear) made of OFHC copper with 2m height, 1.0 m length, and 40 mm or 37 mm or 34 mm thickness (9.2 tons of copper in total for 15 wall panels). The panels are water-cooled and the cooling channels pitch is constant along each panel. The faces of the front panels are protected by leading edge elements made of CuCr1Zr alloy (80 kg total mass) and with AISI 316L twisted tape inside the deep drilled 24mm channel. F4E_D_25FLDW, v1.0 Page 9/23

10 Figure CAD ISO view of the NED (Neutraliser and Electron Dump) Support Structure (SSAISI 304L) Neutraliser assembly Electron Dump (OF copper with junctions TP316L-Inconel 625 -OF copper) Panels with gas lines (OF copper and SS TP 316L with junctions TP316L-Inconel 625 -OF copper) Adjustable Bed (SSAISI 304L) Cooling pipework (SS TP 316L) Figure Sub-systems of the NED F4E_D_25FLDW, v1.0 Page 10/23

11 The 14 water-cooling channels (18mm ID and 1.8 m length) are double side deep drilled in each wall panel to form a serpentine pattern; copper plugs and tube inserts (AISI 316L with a Inconel adapter) are electron beam welded to the wall panels (50 m total length of the electron beam welded joints). The structural frame of the neutraliser has 2.4 tons total mass and it consists of AISI 304L side-plates and spacers that position, support, and align the wall panels along the beam line; spacers are braced into a stack by bolt studs. The panel inlet/outlet AISI 316L cooling tubes are joined to the corresponding manifolds by TIG welding. The main inlet and outlet water headers have bellows allowing compensation of manufacturing errors and component removal by cut&weld tool for the cooling lines. The gas feeding line for neutralisation is connected with two vertical channels, deep drilled in the two middle walls. The design of the welding joint with adaptor is similar to the one identified for the cooling channels. Each gas channel has five through-holes and nozzles positioned with 250mm vertical pitch. The main design parameters of the NED are summarised in the following table. Generic data Number of walls 5 Number of panels Panels dimensions [mm] Weight of panel Overall weight [kg] Overall dimensions [m] 3 panels per wall Total 15 panels 1000 (L) x 40/37/34 (W) x 1850 (H) Approximately 600kg per panel component assembly, 1000 adjustable bed 3.4 (L) x 2.1 (W) x 3.2 (H) Materials Support structure Cooling manifolds Wall panels Leading edge elements AISI 304L (about 3500kg) AISI 316L (about 300kg) OFHC copper (about 9000kg) CuCr1Zr alloy (about 80kg) Thermohydraulic Power load onto the panels [MW] 6 Inlet water temperature [ C] Outlet water temperature [ C] 88 Maximum coolant temperature [ C] 115 Inner diameter of panels cooling channels [mm] 18 Nominal diameter of main headers [mm] 200 Total flow rate [kg/s] 50 Inlet water pressure [bar] 20 Maximum allowable pressure according to PED [bar] 22 Table NED main parameters F4E_D_25FLDW, v1.0 Page 11/23

12 Electrostatic Residual Ion Dump (ERID) The Electrostatic Residual Ion Dump (ERID) uses an electrostatic field to deflect the ions that are dumped on the five ERID panels. The field is produced by applying zero potential to the odd panels (the two external and the central panels) and negative potential (- 20kV DC +/- to the two even panels. The ERID structure consists of five vertical dump walls, a support frame, manifolds and headers for the water cooling supply. The five walls (each 22mm thick) produce four channels crossed by the particle beam. Each wall is composed of 18 vertical Beam Stop Elements (BSEs) made of CuCr1Zr alloy (2.3 tons for the 5 walls). The BSEs have a rectangular cross-section (22mmx100mm) with four internal channels of 14mm in diameter for cooling water; the cooling channels are deep drilled from both ends. AISI 316L twisted tapes with a pitch of 50mm are inserted inside the cooling channels. Caps are EB welded at the ends of the BSEs to produce the cooling channels and AISI 316L stubs are also EB welded to the BSEs by interposing an Inconel 625 transition; the total length of EB welds is 65 m. To provide the necessary stiffness and accuracy of the panel assembly, tongue and groove features for positioning and restraining of adjacent BSEs are foreseen. Figure CAD ISO view of the ERID (Electrostatic Residual Ion Dump) F4E_D_25FLDW, v1.0 Page 12/23

13 Figure CAD rendering of the ERID with details of one beam stop element The BSEs are supported and positioned at the bottom between the two halves of a panel clamping bar. An upper clamping bar similarly clamps the BSEs top end but with gaps allowing free thermal expansion of the BSEs in the vertical direction. The wall assembly rest on two transverse bars and their support allows free axial thermal expansion. Panels biased at high voltage (HV) are connected to the transverse bars via cylindrical ceramic insulators (80mm in diameter, 80mm high). The insulators have metal end flanges for bolting and assembly. All insulators have electrostatic screening caps in order to prevent conductive layers produced by deposition of spattered material. HV potential is supplied to the biased panels with use of a connection bridge to the HV feedthrough on the wall of the vacuum vessel. The ERID frame provides the system stiffness and allows the walls installation in their relative positions with a total mass of 3.5 tons. The frame consists of two AISI 304L side plates, 20mm thick, the two lower transverse bars and the two upper transverse bars supported on four mounting brackets fastened to align the walls with reference to the beam line. The panel manifold is a single pipe DN 100 and the main headers are DN 200. Insulation distances between the HV biased and grounded manifolds are guaranteed by the arrangement in two different levels (see Figure 1-12). The inlet and outlet headers of the HV biased panels have ceramic insulating breaks with DN 130 mm. All the manifolds are made of AISI 316L. Single ply and welded end bellows are installed on the inlet and outlet headers to allow compensation of manufacturing errors and component removal by cut&weld tool for the cooling lines. A gas baffle is mounted on the frame at the ERID exit section to subdivide the injector volume, and therefore to achieve differential pumping for reduction of re-ionisation losses. F4E_D_25FLDW, v1.0 Page 13/23

14 Figure Cooling system sketch of the overall design F4E_D_25FLDW, v1.0 Page 14/23

15 The main design parameters of the ERID are summarised in the following table. Generic data Number of walls 5 Number of BSEs per panel 18 BSE dimensions [mm] Weight of BSE [kg] Overall weight [kg] Overall dimensions [m] 100 (L) x 40 (W) x 1900 (H) Approximately 40kg per BSE 6500kg component assembly, 1000kg adjustable bed 2.2 (L) x 2.1 (W) x 3.2 (H) Materials Support structure Cooling manifolds Wall BSEs Insulators AISI 304L (about 4600kg) AISI 316L (about kg 600kg) CuCr1Zr alloy (about 2300kg) High purity (99.9%) alumina Thermohydraulic Power load onto the panels [MW] 18 Approximately 2 per wall side Inlet coolant temperature [ C] Outlet coolant temperature [ C] 60 Maximum coolant temperature [ C] 140 Inner diameter of BSE cooling channels [mm] 14 Total flow rate [kg/s] 100 Inlet pressure [bar] 20 Maximum allowable pressure according to PED [bar] 22 Table ERID main parameters F4E_D_25FLDW, v1.0 Page 15/23

16 Calorimeter A moveable beam dump, the calorimeter, can be introduced into the beam path downstream of the ERID, allowing the injectors to be commissioned/conditioned and tested independently of the ITER plasma operation. In MITICA, although opening and closing capabilities will be built in the components, the calorimeter is the last component of the beam line and it will work only in the closed position. The general assembly of the calorimeter is shown in Figure The calorimeter consists of the following main parts: a fixed support structure mounted on the vacuum vessel pads via the support and alignment Ajustable Bed; two panels made of a vertical array of horizontal Swirl Tube Elements (STEs); the cooling manifolds and frame supporting each STE panel; hinges and rollers for panel rotation around a vertical axis; the main cooling headers including four bellows that provide a flexible connection for the angular displacement of the panels and two bellows allowing compensation of manufacturing errors and component removal by using the cut&weld tool on cooling lines; embedded instrumentation; an actuation mechanism providing panel movement and switches. Figure CAD ISO view of the Calorimeter F4E_D_25FLDW, v1.0 Page 16/23

17 Right panel Swirl tube back long Swirl tube back short Swirl tube front long Swirl tube front short Left panel Figure CAD rendering of the MITICA calorimeter with details of the swirl tubes arrangement Each calorimeter panel consists of an axial array of STEs, two manifolds for coolant inlet and outlet, an adjusting array supporting cooling fittings at the STE ends, and a clamping array supporting STEs at their omega shape. Each panel consists of 96 STEs, inclined by 2.8 degrees with respect to the horizontal axis. Each STE is made by a CuCrZr alloy circular tube with 20mm outer diameter, 2mm wall thickness, and provided with two AISI 316L tapes twisted with 50mm pitch. The STEs are bent in order to provide two straight parts to be exposed to the particle beam and bent regions to be supported at the manifolds ends, cooling fittings, and intermediate clamps. Assembly jigs will be used to install STEs before welding to the cooling manifolds and to check the position after welding. AISI 316L fittings with Inconel 625 interlayer will be EB welded to the CuCrZr STEs and to the cooling manifolds; the total EB welding length is about 25m. Each adjusting array supporting the cooling fittings at the STE ends rests on a roller that, during the opening/closing motion of the panel, slides on the chassis of the support structure. The left side panel is provided with an end stop. It dumps a part of the beam, leaking through gaps between STEs of the right and left panels when the calorimeter is in the closed position. This dump consists of an actively cooled plate made of OFHC copper. The joint of the AISI 361L tubes to the copper end stop is made through adaptors with Inconel 625 interlayer. The panels rotate around two vertical hinges at the entrance of the calorimeter assembly. The opening/closing of each panel requires a rotation of 5 degrees to move the panel far end by 300 mm. The hinges cylindrical bearings are attached to the upper and lower ends of the panel inlet manifolds. The aluminium bronze seats of the hinges are fixed to a bracket mounted on the fixed support structure. The coolant headers feeding each panel are connected to the corresponding manifolds, by bellows that can accommodate the required angular rotation for panel aperture/closure. The single ply and welded end bellows are installed horizontally allowing a relative rotation of their flanges, around the same vertical axis of the panel hinges. The fixed support structure consists of AISI 304L plates joined by welding, stiffened by ribs and tubular pillars. The carriages of the component support and alignment system, similar to those used for the NED and the ERID, are fastened to the frame of the support structure. F4E_D_25FLDW, v1.0 Page 17/23

18 Calorimeter actuator mechanism The opening/closing movement is provided by a pneumatic drive which is placed outside the vacuum vessel and double bellows are foreseen to satisfy safety requirements. The motion of the pneumatic drive shaft is transmitted to the panel frame through an actuation mechanism. The main design parameters of the calorimeter are summarised in the following table. Generic data Number of panels 2 Number of STEs per panel 96 Weight of panels [kg] Weight of CuCr1Zr tubes [kg] Overall weight [kg] Overall dimensions [m] Approximately 1400kg per panel Approximately 400kg per panel 5000kg component assembly, 1000kg adjustable bed 3.0 (L) x 2.1 (W) x 3.2 (H) Materials Support structure Cooling manifolds STEs AISI 304L (about 4500kg) AISI 316L (about 900kg) CuCr1Zr alloy (about 800kg) Thermohydraulic Power load onto the panels [MW] 18 Inlet coolant temperature [ C] Outlet coolant temperature [ C] 60 Maximum coolant temperature [ C] 120 Inner diameter of STEs [mm] 16 Outer diameter of STEs [mm] 20 Total flow rate [kg/s] 100 Inlet pressure [bar] 20 Maximum allowable pressure according to PED [bar] 22 F4E_D_25FLDW, v1.0 Page 18/23

19 Components Common Equipment (CCEs) Cutting-Welding Tools These tools will used to perform and test the following operations: bevelling of the tubes, squaring, automatic orbital welding, cutting, containment of dusts to prevent pollution of the surrounding environment like the vacuum vessel, and inspection. All these operations will be completed by the tool with minimal intervention of the operator. The tools will be used during the in-vessel installation and maintenance with high reproducibility of the process within the ranges of operation parameters. For the larger diameter tubes, the tool will also be required to allow the compression and extension of the bellows located in between the cutting sections, so that the joint surfaces can be aligned and closed. Cooling Bellows (axial expansion joints) Bellows will be positioned between the cut and weld sections of the cooling header and to connect the beam line components to the cooling feedthroughs of the vacuum vessel. A large clearance will be realised by removing cooling bellows before component lifting for maintenance out of the vessel. Cooling bellows will be compressed for removal and extended for alignment and closure of joint surfaces. The end flanges of the bellows assembly will be welded on bellows after component installation inside the vacuum vessel. Machine will be required on end flanges to adjust the length and the off axis position of the bellows assembly. Bellows Restraining Device During operation, the cooling bellows will be subject to the internal pressure of about 20 bar realising a large force which will open the end flanges apart. Bellows restraining devices will be installed to provide a rigid and adjustable structure which keeps constant the bellows axial length during operation. Figure Cooling bellows with bellows restraining device F4E_D_25FLDW, v1.0 Page 19/23

20 Lay shaft Four identical lay shafts will be used to bolt the components on the Adjustable Bed inside the vacuum vessel by applying the tightening torque required for bolting. The lay shaft ends will be designed to be compatible with all the three Beam Line Components. Figure Lay Shaft Lifting Frame In order to lift and move the components by using a crane, an interface based on container handling technology will be designed on the Beam Line Components and on the Adjustable Beds. The bottom part of the lifting frame will be interfaced with the Beam Line Components and the Adjustable Beds. The upper part of the lifting frame will be interfaced with the PRIMA crane. The lifting frame will be rigid to avoid any permanent deformation of the components. T-shaped wrenches Two T-shaped torque wrenches will have to be manufactured for the Beam Line Components. The torque wrenches will be designed to be handled and used by an operator for rotation of the foldable panel of Electron Dump and for tightening of screws bolting the Adjustable Beds on the vacuum vessel and the Beam Line Components on the Adjustable Beds. Figure T-shaped wrenches F4E_D_25FLDW, v1.0 Page 20/23

21 Diagnostic Instrumentation The Beam Line Components are equipped with different sensors: thermocouples, position switches, electrostatic probes, fiber optic strain gages, fiber optic transducers for temperature, fiber optic accelerometers. Sensors will be free issued by F4E to the Supplier for installation on the Beam Line Components. The Supplier shall: 1) Install the sensors on board of the Beam Line Components in the locations specified in the drawings and test them before and after installation. The assembly sequence of sensors and fixing of cables shall be developed by the Supplier. 2) Develop the routing of cable bundles and apply identification labels on each wire. The groups will be defined by F4E during the manufacturing design phase. 3) Procure and install all the features needed to lock in position the sensors as specified in the drawings. 4) Procure and install the fixing features for cables and the shielding braided sleeves containing the cable bundles. Component Neutraliser ERID Calorimeter Description Thermocouples, electrostatic probes, fiber optics Thermocouples, electrostatic probes, fiber optics Thermocouples, switches, contracts, fiber optics No of sensors F4E_D_25FLDW, v1.0 Page 21/23

22 G2. OBJECTIVES AND SCOPE OF THE WORK The supply consists of the procurement of the MITICA Beam Line Components and the associated services, in agreement with the Technical Specifications. The scope of the supply includes a first phase where the Supplier will develop the manufacturing design starting from the F4E technical specification, defining all the main manufacturing steps and procedures. The second phase consists on the manufacturing, pre-assembly and test at the factory of the MITICA Beam Line Components and the delivery, pre-assembly in the assembly room and test at PRIMA Site. The following services are foreseen to be included in the scope: Development of the Build to Print design for the prototypes Development of the Build to Print design for the parts/sub-assemblies which are detailed in the Technical Specifications Development of all the manufacturing drawings, including any individual part drawing not present in the tender package Procurement of all the materials, both raw materials and standard or off-the-shelf components Procurement and design, drawings and manufacturing of all the necessary tools and fixtures Construction, machining, handling, assembly and testing at the Supplier s workshop and at PRIMA site Manufacture of the components in agreement with all foreseen technical and quality requirements Cleaning and pre-assembly of the whole BLCs at Supplier s premises Testing at the Supplier s facilities Packaging and delivery of the BLCs to the PRIMA Site Pre-assembly of the BLCs in the assembly room at PRIMA Site Acceptance Tests on Site Procurement of any set of handling gear and appliances that may be necessary to handle the equipment safely and conveniently during its receipt and assembly at Site. These will become the property of F4E. Procurement of any special tool and special equipment necessary for the operation and maintenance of the equipment included in the Supply. These will become the property of F4E. Procurement of any set of testing tools and instruments needed to test the system. These will remain property of the Supplier Training of an assembly/maintenance staff on Site Preparation of a document in which decommissioning procedures and waste disposal rules are described Preparation of the complete set of management and technical documentation as described in detail in the specifications The supply includes spare parts of some sub-assemblies. Not included in the scope of supply: Installation of the BLCs inside the MITICA vacuum vessel Diagnostics instrumentation procurement F4E_D_25FLDW, v1.0 Page 22/23

23 G3. INPUT DATA Fusion for Energy will send to the selected Supplier, the necessary information for the satisfactory procurement of the equipment. This includes, but is not limited to, the following: Management Specification (Annex A) for the procurement of the MITICA BLCs Technical Specification (Annex B) for the procurement of the MITICA BLCs All related annexes and appendices 3D CATIA model of the of the MITICA BLCs and of their interfaces 2D drawings of the of the MITICA BLCs G4. FUSION FOR ENERGY CONTACT PERSONS Business Intelligence Contact: Name Telephone - Fax Benjamin Perier Tel: Benjamin.Perier@f4e.europa.eu F4E_D_25FLDW, v1.0 Page 23/23