Topic FIP/P7-21 Progress of the CEA Contributions to the Broader Approach Projects

Size: px
Start display at page:

Download "Topic FIP/P7-21 Progress of the CEA Contributions to the Broader Approach Projects"

Transcription

1 Topic FIP/P7-21 Progress of the CEA Contributions to the Broader Approach Projects J.-C.Vallet 1, S.Chel 2, R. Gondé 1, F.Robin 3, O.Baulaigue 1, Ph.Brédy 2, J.David 5, P.Decool 1, G.Disset 2, H. Dzitko 2, L.Genini 2, G.Giruzzi 1, R.Gobin 2, F.Gougnaud 2, J-F.Gournay 2, J.Marroncle 2, C. Mayri 2, F.Michel 4, P.Nghiem 2, J.Noé 3, F.Orsini 2, M.Nusbaum 6, J.Beauvisage 7 ; A.Dorronsoro 8 ; P.Eymar-Vernein 9 ; H.Rocipon 10; M.Colombo CEA, IRFM, F St-Paul-lez-Durance, France, 6 ALSTOM, 3 Av. des trois chênes, F Belfort, France 2 CEA, IRFU, F Gif /Yvette, France, 7 Air Liquide, 2 rue Clémentière, F38360 Sassenage, France 3 CEA, DSM/DIR, F Gif/Yvette, France, 8 JEMA, Paseo del Circuito 10, E Lasarte-Oria, Spain 4 CEA, INAC, F Grenoble, France 9 SDMS, 761 route de Valence, F Saint-Romans, France 5 CEA, DEN/DPIE, F St-Paul-lez-Durance, France 10 ALSYOM, 12 Bd Renaudet, F Tarbes, France jean-claude.vallet@cea.fr 11 LGM, 655 rue P.S. Laplace, F Aix-en-Provence, France Abstract: This paper details the progress, achievement and status of the various CEA contributions to the Broader Approach projects: IFERC/CSC, IFMIF-EVEDA and STP/JT-60SA recorded since the 2012 IAEA conference. I) Introduction The Broader Approach, BA, Agreement to ITER was signed by Europe and Japan, in February 2007, for a first period of ten years. The Agreement comprises 3 projects: IFERC, the International Fusion Energy Research Center, including the Computational Simulation Center, CSC; IFMIF-EVEDA, Engineering Design and Validation of a 14MeV neutrons irradiation facility for material testing and STP, the ITER Satellite Tokamak Program with the JT-60SA project. CEA, in charge of the French commitments, as European Voluntary Contributor Designated by the French government, is participating to these projects, respectively in value for 85%, 33% and 42% of the EU contribution. The purpose of the BA is to support ITER operation and to contribute to DEMO design and studies. This report synthesizes progress and status of CEA contributions to the BA projects. Beyond its BA commitments, CEA is also involved in the development of the JT-60SA Research Plan and in the preparation of its Commissioning and Operation. II) Status of the CEA contribution to IFERC-CSC II-a) Helios status and upgrade The IFERC objectives are to promote DEMO Design R&D Activities, ITER Remote Experimentation, and to implement a Supercomputer Simulation Centre (CSC) for large scale simulation activities for fusion plasma experimental data analysis, ITER scenarios and performance simulations, and for DEMO Design. The IFERC centre, located at Rokkasho, Japan, is hosting the various IFERC facilities including the CSC. CEA provided the PetaFlops Class Helios supercomputer, the associated peripheral equipment and services for 5 years of operation including maintenance. According to schedule, the Helios supercomputer, designed and assembled by Bull Company, entered into operation in January Helios has a classical architecture with 4410 compute nodes federated by a fat-tree InfiniBand network. Each node contains 16 cores (2 Intel Sandy-Bridge processors with 8 cores each). The total computing power was PFlop/s Linpack which yield a 12 th place in the June 2012 Top 500 list. At the time, it was the largest supercomputer dedicated to a single scientific community. The Helios architecture was optimised and upgraded by Bull in 2014 on the basis of the feedback of the first two years of operation and following the recommendations made by a dedicated working group of making available for the fusion community additional nodes on Helios equipped with Intel Xeon Phi co-processors (fig.1); with the primary goal of preparing codes to the most promising architecture of future supercomputers. This upgraded has consisted in adding 5 racks equipped with 180 nodes fully integrated to the Helios configuration. Each node includes two Intel Xeon Phi 6110p co-processors (60 cores running at 1 GHz), two Intel Xeon E microprocessors (8 cores running at 2.1 GHz) and 48 GB of shared memory in addition to 8 GB of private memory per co-processor. In addition, programming environment tools for Intel Xeon Phi were installed (including Intel tools supporting

2 OpenMP3 and OpenMP4, Allinea DDT and MAP for debugging and optimisation). Moreover 90 additional nodes similar to the ones of the initial configuration were installed. In total, the aggregate peak performance of the Helios supercomputer resulting from these upgrades is PFlops (including PFlops for the Intel Xeon Phi partition). The Intel Xeon Phi racks were installed on site and accepted in January The acceptance tests included HP-Linpack for which the performance measured was TFlops. The new nodes were opened to user on February In order to promote the efficient usage of the new Intel Xeon Phi nodes, a set of support actions, supported by Bull and Intel, were undertaken. They include availability of full documentation on the Fig. 1: Architecture of a node based on Intel Xeon Phi CSC website, training sessions), monthly webinars on advanced topics including experience on code optimisation, optimisation of mini-apps derived from fusion codes. In addition, joint Europe and Japan seminars reporting the experience of Helios users on Intel Xeon Phi are planned in the future. So far, the use of the new nodes is mostly for code porting and optimisation. Their loads should increase when the native programming mode of the Intel Xeon will be fully available (end of 2014) and implemented in new generation codes. II-b) Utilisation of Helios and results Helios is currently used by more than 100 Japanese scientists and more than 300 European scientists. Almost all the users of the CSC are remote, even those in Japan. Allocation of computing resources to user s project is done by peer review, instituted in a joint setup, the Standing Committee (StC). Proposals are submitted for either fig.2 compute time per domain for EU and JA users helios supercomputer Cycle 1 Cycle 2 Cycle 3 Cycle 4 Compute period runs from-to Apr Oct 2012 Nov Oct 2013 Nov Nov Oct 2014 Oct 2015 Number of received Proposals total proposals asking (Mnodeh) 65,8 70,6 102,7 107,0 avg asking (Mnodeh) 1,1 0,9 0,8 0,8 overasking vs resource 1,8 2,0 2,9 3,0 table 1:Cycle characteristics Japanese or European party, reviewed and allocated so that 80% of available resources is allotted equally between the two on a common agreement. The remaining 10% + 10% are allotted on each party s specific criteria. With current utilisation of the computer around 85% and reaching regularly 90%, the total resources available for 2

3 StC allocation is around 35 million.nodes.hours (about 530 million.cores.hours for a more usual metric). The chosen metrics result from the choice of allocating only one job per node. From the 3 rd cycle (table1) a plateau is reached for proposal number and job characteristics. It corresponds to a mean size of 0.8 Mnodeh (14Mh) for a proposal. The computation time is still largely dominated by plasma turbulence computation, (fig.2), which has been historically the most compute-hungry discipline. Computation time for other scientific domains is more evenly distributed and shall grow in the future. Along with computation volume, another scientific relevant criterion is the number of papers issued at the end of each cycle. For example, the 2 nd cycle results gave rise to the publication of 120 reviewed-papers for the 82 selected projects. The repartition of those papers by scientific domain is more balanced than the allotted computation time and shows the interest for all of them (fig.3). A post-project evaluation is requested by the StC before allocating new project on following cycle. One of the highlights selected this year in the StC Scientific Report was related to the computation of the Density filaments and maximum power flux into the divertor in 7.5MA/2.65T ITER scenario in ELM due to n=12 ballooning mode 3 Fig.3 repartition per scientific domain of 120 scientific papers written as results of the 2 nd computation cycle. (fig.3) obtained with the JOREK code. Another result obtained with JOREK was related to the Mechanism of mitigation Edge Localized Modes (ELMs) by Resonant Magnetic Perturbations (RMPs) showing that RMPs non-linearly drive tearing-like modes replacing large ELMs crashes by continued MHD turbulence in the pedestal [1]. Aside StC activities for resources allocation and projects assessment the coherence of the remote scientific community of Helios users and operators is ensured by several communications and events: an annual seminar, scientific and compute-centric with focus on selected results and challenges, issues and solutions such as large jobs peculiarities in 2013 and on evolution of usage in 2014, a fig.4 Example of JOREK Results monthly newsletter for computing news only, a monthly webinar for HPC, helios and new MIC resources training, and an annual Xeon Phi workshop, the first held at the Maison de la Simulation in Saclay, France, last May. III) IFMIF-EVEDA activities and results The IFMIF-EVEDA project consists of design and validation activities aimed at providing the intermediate engineering design of the 14-MeV-neutron International Fusion Materials Irradiation Facility and validating the key technologies of the accelerator, lithium target, and test cell facilities. Sharing the work with the Japan Atomic Energy Agency JAEA, INFN Italy, CIEMAT Spain, and SCK CEN Belgium, CEA is committed in both the validation and the design of the accelerator facility. The 6 years studies of the IFMIF Intermediate Engineering Design were completed by mid [2] and the report (IIEDR) was adopted by the BA Steering Committee. In this report, details of each of the five IFMIF facilities (Accelerator, Li Target, Test Cells, Post-Irradiation and Examination Facility, Conventional) are defined. CEA was involved in the design of several systems of the accelerator facility (Injector, 40 MeV SRF Linac, HEBT, beam diagnostics), and participated in beam dynamics studies and cost assessment of the IFMIF construction, operation and decommissioning activities. In parallel, validation activities of critical components are progressing and achievements in the prototyping of accelerator sub-systems under CEA responsibility are presented in the next sections. III-a) Description of Accelerator Facility The IFMIF accelerator facility comprises 2 identical Linacs, each accelerating a cw 125-mA deuteron beam at the final energy of 40 MeV. A total beam power of 2x5MW is required to produce the high flux of neutrons ~10 17 n/s through break-up interactions of the D + beam with the Li target. As the accelerator facility shall reach unprecedented performances, a prototype of the low-energy part of the

4 Accelerator (LIPAc) comprising the injector, the radiofrequency quadrupole (RFQ), the matching section, the superconducting Linac (SRF Linac), and the 9 MeV transport line ended with the beam dump is being developed. Among these accelerator prototyping systems, CEA is in charge of the D + injector, the cryomodule and cryoplant of the SRF Linac, several beam diagnostics and is involved in the beam dynamics studies, the monitoring of accelerator control system, the procurement of RF power amplifiers as well as in the installation and commissioning of the LIPAc at Rokkasho. This crucial phase, which will be completed after demonstration of the operation of the LIPAc at full power, started in 2013 by the installation at Rokkasho of the D + injector and will continue with production of its first beams in pulsed mode, expected before end of III-b) Beam Dynamics Studies For the design of LIPAC components, taking into account the characteristics of this MW-class beam power accelerator and the threshold of beam losses (1W/m) allowing hands on maintenance, advanced beam dynamic studies were developed [3]. As assessment of adequacy of the human and accelerator protection systems was required too, these studies were performed in every possible beam operation situation that are: start from scratch, beam commissioning or tuning or exploration, routine operation, sudden failure. In a first step, start-to-end simulations, with 10 6 macroparticles, using input beam results from calculations of the ECR sources extraction system and 3D field map calculated by finite elements for most of LIPAc components, were carried out for 500 different sets of errors randomly distributed over the accelerator components. From the statistical analysis of the results the whole set of static and dynamic tolerances for every component are extracted [4]. In a second step, for each identified operation situation a specific protocol of beam dynamic simulations is applied. The results is a complete 'Catalogue of Losses' [5] allowing the identification of hot spots to be protected for each accelerator component, the definition of parameters, as the beam stop velocity or maximum beam power allowable, for each operation situation. More fundamental studies about the beam quality have also been undertaken, leading to a new approach where the optimization is performed by minimizing the beam halo size rather than the beam emittance, the latter describing mainly the beam core. This required a precise determination of the core-halo limit, obtained thanks to an in depth analysis [6]. With such an approach, risk of losses can be significantly reduced. The next steps will be mainly dedicated to beam commissioning at Rokkasho site of the successive sections of the accelerator until the overall ramp up to final beam power. For preparing these operations, detailed lists of beam tunings and measurements during each beam commissioning phase have been produced. III-c) SRF Linac Development The LIPAC SRF Linac is a full-scale and operational cryomodule for transporting and accelerating D + beams from 5 to 9 MeV. The cryomodule (Fig. 5) is a horizontal vacuum tank of ~6 m long which includes: 8 accelerating superconducting half wave resonators (HWRs), working at 175 MHz and at 4.45 K, 8 Power Couplers providing 70 cw kw to the cavities, and 8 Solenoid Packages as focusing elements, provided by CIEMAT. The LIPAc cryomodule design will be used as a reference for the IFMIF cryomodules, once the performance requirements will be experimentally demonstrated after beam operations at Rokkasho. After the design phase of the LIPAc cryomodule, officially ended up by the end of 2013 with the publication the engineering design report, most of activities are dedicated to the manufacturing of series components. The manufacturer for cavities is selected and the contract ready to be placed. As the HWRs are cooled down by liquid He, they shall be approved by Japanese Authorities before installation at Rokkasho. The licensing procedure of the HWR with the High Pressure Gas Safety Institute of Japan, KHK, is still ongoing. The Power Coupler design was shared in 2 parts: Fig. 5: General layout of the LIPAc SRF Linac the RF and preliminary thermomechanical design performed by CEA and then the detailed thermo-mechanical design carried out by the company CPI [7] in accordance with the detailed specification issued by CEA [8]. According to this design, two 4

5 couplers were fabricated and delivered to CIEMAT [9] for conditioning. Thanks to results qualifying the design and proving its robustness, the manufacturing of the series couplers was launched in June In parallel, the design of cryomodule components such as vacuum vessel, support frame, thermal screen, magnetic shield, phase separator, cryo-piping, tuning system, etc. was completed. Calls for proposals were issued in 2013 and some of the calls for tender for the critical parts as well. The company for manufacturing the vacuum tank and the thermal shield is selected; manufacturers for remaining components will be selected by the end of Meanwhile a dedicated test bench was devised. It will allow a full characterization of a jacketed and fully dressed cavity with coupler and tuning system in an environment as close as possible to the nominal operations (without beam), i.e. nominal RF power source, working point around 4K, HWR, coupler and tuner tested in the same position as in the cryomodule. Doing so, the RF, thermal and mechanical behavior of a cavity with its coupler and tuning system will be assessed 15 months before the first RF test of the fully assembled cryomodule, which is a strong mitigation in order to anticipate any problem. First results of this test bench are expected by mid III-d) Beam Diagnostics Status Several different types of diagnostics are required for monitoring and driving the LIPAc beam from the RFQ exit (5 MeV) to the beam dump (9 MeV). Among LIPAc beam instrumentation, the CEA is in charge of the beam loss and beam current monitors as well as the transverse beam profilers (Fig.6a), each demanding appropriate development due to the high beam intensity and power, high space charge and radioactive harsh environment [10]. From March 2013 to March 2014, acceptance tests carried out by CEA showed that every diagnostic fulfill requirements. The Beam Loss Monitor is made of LHCtype ionization chambers (IC) [11] providing a signal in less than 10 µs for emergency beam stop. In the energy range of the D + beam, only gammas and neutrons can escape the beam tube. As ICs are not sensitive detectors at low energy or for neutral particles, very tiny currents of few tens of pa are induced. A specific front-end electronics was necessary, based on integrators for beam monitoring and on discriminators generating a fast signal used to stop the beam. By adjusting the integration time and amplifiers, loss signal can be adapted to the optimal electronic range. This monitor was successfully tested with a 60 Co radiation source (Fig. 6b) and a current generator. Transverse beam profile based on ionization of the residual gas by beam particles was developed in a dedicated R&D program [12]. Figure 6: a) HEBT IPM (left) with frame made of 2 degraders, one electrode and one strip plate; b) Beam Loss Monitors (right) under calibration with a 60 Co radiation source. Within the area between 2 parallel plates, an electric field is applied which must be kept uniform to provide a linear response. To achieve this key point, degraders with various shapes and potentials were set for improving the electric field homogeneity and uniformity. Moreover, as the beam space charge induces distortions drifting the electron and ions trajectories, measured beam profile is widened. An iterative algorithm is implemented to correct this problem. During the acceptance tests with beam, uniformity of electric field was demonstrated, profile resolution better than 100 µm was achieved and good overlapping of beam profiles for different space charge was obtained with the algorithm. Industrial Current transformers (CTs) being available, 3 Alternating Current CTs, 1 Direct Current CT and 1 Fast CT have been ordered [13]. Adjustment of the design for the FCT-ACCT pair located at the exit of the RFQ was necessary because available room is small, drowned in a strong quadruple fringe field shielded with soft iron disks. Two Secondary Electron Emission Monitors with 2 grids of thin wires (SEM grids) identical to SPIRAL2 ones [14] were supplied to measure the beamlet passing through 2 perpendicular thin slits (100µm aperture). As consecutive wires are distant from 2 mm, steerers will be installed to increase the resolution allowing measurement of sub-millimeter profile widths by shifting the beamlet position. These diagnostics, including electronics, dedicated tools and cabling were shipped to Rokkasho during August

6 IV) Status of the CEA contribution to JT-60SA CEA procurements for JT-60SA include the manufacturing of 9 of the 18 Toroïdal Field, TF, Coils, the supporting structures of the Magnetic Field System, MFS, the Cryogenic System and 5 Superconducting Magnet Power Supplies, SCMPS, as well as the development, construction and operation of a Cold Test Facility, CTF, for the nominal testing of TF Coils. For Cryogenic System and SCMPS, installation, testing and commissioning at the JT-60SA site, Naka, Japan are also part of the CEA commitments. Specification definitions and tendering phases are completed. Industrial contracts have all been placed in between 2011 and 2013 and manufacturing is on-going in Europe. For insuring the compliance between specifications and manufacturing, a Quality Management System based on Configuration Management concepts was developed and applied with industrial partners. CEA also leads for EU the update of the Research Plan [15] and the preparation of the JT-60SA operation. IV-a) TF Coils, TFC Cold Test Facility, Magnet Structures and Magnet pre-assembly In July 2011, the contract for the TF coils manufacturing was awarded to ALSTOM. For insuring the accurate geometry of the coils, the chosen offer included the manufacturing of the winding pack using rigid jigs and thick impregnation mould, and the use of robots for the welding of coil casings. 2.5 years were needed to the manufacturer for performing the design, the manufacturing and the commissioning of the production line and to develop and validate with the support of CEA the qualification mockups associated to the most critical processes. Since December 2013, the TF coil manufacturing [16, 17] is started and 3 winding packs are being processed. The 1 rst coil (Fig.7) will be delivered to the CTF, mid At Saclay, the setup of the CTF [18] is nearly completed (Fig.8). It will be soon followed by an integrated commissioning including a nominal test at 25.7 ka using a superconducting shunt and a low current quench test using the W7X demo coil, aiming at qualifying the Magnet Safety System. The CTF will be ready beginning During 2014, the test program and the test procedure were validated. About 2 years are required to perform 18 cold tests. The MFS supporting structures are made of 2 main parts: the 18 Gravity Supports, GS, supporting the total weight of MFS and the Inner and Outer Intercoil Structures, IIS & OIS. OIS is a set of 18 components forming the outer vault of the TF coils assembly. These mechanical structures were optimized to reduce the cold mass and to withstand out-of-plane electromagnetic forces and seismic loads. An R&D Fig.7 1 rst TF Coil winding pack completed (June 2014) Fig.9 OIS structure, 1/3 mockup Fig.8 general view of the CTF hall with the cryostat, test Fig.10 Gravity support, components frames, valve box, refrigerator, power supply (Sept. 2014) for the 1 st GS. program, including the development of mockups aiming at qualifying the insulated bolted joint of the OIS, the IIS friction joint linking inner legs of TF coils [19] and the sliding coefficient of spherical bearings providing the required GS flexibility was conducted by CEA. In 2013, 2 contracts were placed to SDMS for OIS and to ALSYOM for GS. Both companies validated manufacturing and welding processes on down scale mockups. Now, manufacturing are on-going on time schedules compatible with the JT-60SA assembly. In addition, beginning 2014, CEA agreed to perform at 6

7 Saclay, the pre-assembly of TF coils with OIS, prior shipment to Naka. Tooling, work area, technical and quality procedures are being developed to be ready mid IV-b) Cryogenic System The Cryogenic System shall cool thermal shields at 80 K, HTS current leads at 50K, superconducting magnets at 4.5 K and cryopumps at 3.7 K and shall cope with the large pulsed heat loads generated by plasmas [20,21]. For solving these issues CEA specified an optimized cryogenic concept based on the feedback of a scale down dedicated mockup operated at Grenoble [22]. In November 2012, the manufacturing contract was awarded to Air Liquide after one year of intense tendering phase with 4 technical rounds and 2 intermediate offers. The solution proposed by Air Liquide uses 4 standard skids of compressors in parallel adapted for helium and equipped with frequency drive for the Warm Compression Station (WCS), a Refrigeration Cold Box (RCB) with 3 turbines and nitrogen precooling and an Auxiliary Cold Box (ACB) with a large liquid thermal buffer Fig.11 RCB during assembly at Air Liquide workshop (7 m 3 of liquid helium). For the WCS, each skid is composed of 2 compressors whose one equipped with frequency drive which offer flexibility and redundancy. The conceptual and detailed design was validated end For the main components (WCS, RCB, ACB), the manufacturing is almost finished and tests are planned from August to November 2014 before shipment to Naka. On-site installation and commissioning will start in April 2015 and last 18 months. IV-c) Magnet Power Supplies, SCMPS: CEA shall procure 2 SCMPS for Equilibrium Field Coils 2 & 5, EF2&5, rated ±1 kv / from -20 ka to +10 ka; 2 for EF3&4 coils, rated ±1 kv / ±20 ka and 1 for the 18 TF coils, rated ±80 V/+25.7 ka. Technical studies performed with F4E and ENEA were used as basis for the detailed specifications for European tendering. The contract was awarded in March 2013 to JEMA Energy Company, located at Lasarte-Oria, Spain, which provided recently power supplies for JET, W7X and MAST. The detailed design for EF3-4 was validated in August 2014 (Fig.12). SCMPS are AC/DC converters based on thyristor bridge technology (rectification from 6 to 24 pulses depending on configurations). They are interfaced with re-used installations such as electrical HV grid and transformers and will be connected to a new control system developed by JAEA. The proposal to realize complete functional tests, full power and load tests in JEMA s factory reduces technical risks during commissioning and acceptance tests in Japan. Furthermore, JEMA-POSEICO consortium is also procuring, for ENEA, the complementary part of the SCMPS (for EF1 & EF6 and Central Solenoid coils CS1 to CS4). This will allow a more homogeneous design and will also ease operation and Fig.12 SCMPS EF 2,3,4,5 layout maintenance activities. The manufacturing is now launched. Transportation to Japan should occur by the end The final acceptance of SCMPS is expected 2 nd half IV-d) JT-60SA Research and Operation plans: Since 2011, CEA is coordinating the EU contribution to the JT-60SA Research Unit in charge of both periodic update of the Research Plan [15] and managing the scientific collaboration for the preparation of the exploitation. In 2014, the latest activity conducted within the EUROfusion consortium was organized in 3 areas: Modelling, Sub-systems and Operation. For Modelling, CEA provides also the IRFM code suite (CRONOS & METIS) and co-chairs an EU-JA working group aiming at defining the top level requirements for Data Management in synergy with the Remote Experiment Centre (REC) developed within the IFERC project. CEA also joined a working group aiming at defining the 7

8 integrated commissioning and start-up of JT-60SA and at developing procedures for a safe operation of JT-60SA. V) Summary Every procurement to the BA in charge of CEA was subject to an extensive effort of optimization conducted with the BA partners during the conceptual design phase and of validation and qualification, defined by CEA, both at specification and manufacturing levels. This paper summarized results associated with this quality policy developed by CEA and detailed the achieved performances of the products either already delivered or being manufactured. For IFERC, as expected by the CSC project promoters, the Helios supercomputer became the focal point of a large and productive remote scientific community. Beyond the large number of scientific results already produced, the successful upgrade of Helios, performed by Bull in 2014, including the most up-to-date generation of INTEL processors, is also offering to fusion computation community the opportunity to access the most advanced programming mode for the next generation of HPC. For IFMIF/EVEDA, after the delivery of the D + injector at Rokkasho, in 2013, CEA completed the development and qualification of a set of high intensity beam diagnostics, as well as the studies of the SRF-Linac and associated Cryoplant. Preparation of the commissioning with beam of the injector, transportation of diagnostics to Rokkasho, tender process for cryoplant and SRF-Linac components are progressing, in such a way that operation at full intensity of the injector, installation of diagnostics on LIPAc and manufacturing of Cryoplant and SRF Cryomodule are expected for For JT-60SA, a tight follow up managed by CEA allows keeping on tracks every industrial contract. At Belfort, TF winding activities are running at full speed and impregnation activities are on schedule. At Sassenage, the cryogenic system is close to completion and will be shipped to Naka before the end of At Saclay, the CTF commissioning will started by the middle of fall 2014 with substantial margins regarding the TFC coils deliveries. TFC coil pre-assembly activities were also launched during the summer At Saint-Romans, industrial qualifications were completed and the manufacturing of the 1 rst OIS is in progress, as well as the manufacturing of components for GS assembly at Tarbes. At Lasarte-Oria, manufacturing of the SCMPS for EF3&4 started during summer 2014 and the detailed design for remaining SCMPS is in progress. Beyond its BA commitments, CEA is also actively participating to the preparation of the JT-60SA start-up and operation. The CEA implication in the BA projects represents in the present context a significant and fruitful investment for fusion researches in view of ITER and towards DEMO development. VI) References: [1] M.Bécoulet & al. This conference. [2] J. Knaster et al., Journal of Nuclear Physics, Vol. 453, 1 3, Oct. 2014, p [3] P. A. P. Nghiem et al., Nucl. Instrum. Methods Phys. Res. A, 654, (2011). [4] P. A. P. Nghiem et al., Laser Part. Beams 32, 109 (2014). [5] P. A. P. Nghiem et al., Laser Part. Beams 32, (2014. [6] P. A. P. Nghiem et al., Appl. Phys. Lett. 104, (2014). [7] Communications and Power Industries Palo Alto, California, USA [8] H.Jenhani et al, IPAC 10, Kyoto; MOPEC055 [9] D.Regidor et al, IPAC 11, San Sebastian; MOPC135. [10] J. Marroncle et al., in IBIC 2012 proceedings, Tsukuba (Japan), Oct [11] H. Stockner, PhD Thesis, Teschnische Universität Wien, 2007 [12] J. Egberts et al., in DIPAC2011 Proceedings, Hamburg (Germany) [13] Bergoz Instrumentation Saint-Genis Pouilly (France). [14] J.L. Vignet et al., DIPAC 09, Basel (Switzerland) [15] [16] P.Decool & al., this conference. [17] P.Decool & al., in Proc of the SOFT conf [18] W.Abdel Maksoud & al., in Proc of the SOFT conf [19] F.Nunio & al., IEEE Trans. on Appl. Supercond.,Vol.24, n 3.,2014 [20] F.Michel & al., ICEC conference proc [21] V.Lamaison & al., Adv. Cryogenic Eng. Vol.59A, 2014 [22] C.Hoa & al., Cryogenics, Vol.52, (7-9), p

ITER R&D Needs, Challenges, and the Way Forward

ITER R&D Needs, Challenges, and the Way Forward ITER R&D Needs, Challenges, and the Way Forward Bernard Bigot Director General ITER Organization, Cadarache, France Fusion Power Co-ordinating Committee Mtg, IO Headquarters, 24 Jan 2018 1 Context of ITER

More information

Recent Progress of JT-60SA Project H. Shirai 1, P. Barabaschi 2, Y. Kamada 3 and the JT-60SA

Recent Progress of JT-60SA Project H. Shirai 1, P. Barabaschi 2, Y. Kamada 3 and the JT-60SA Recent Progress of JT-60SA Project H. Shirai 1, P. Barabaschi 2, Y. Kamada 3 and the JT-60SA 1 JT-60SA Project Leader, 2 EU Project Manager, 3 JA Project Manager OV/3-3 IAEA Fusion Energy Conference 2016

More information

ITER Organization. Françoise Flament. Head of Procurement Arrangements & Contracts Division. Journée ITER/CEA 01/12/2010. Page 1

ITER Organization. Françoise Flament. Head of Procurement Arrangements & Contracts Division. Journée ITER/CEA 01/12/2010. Page 1 ITER Organization Françoise Flament Head of Procurement Arrangements & Contracts Division Page 1 1. Overview of the IO Procurement System 2. Business Opportunities 3. IO Procurement Processes and Procedures

More information

Vision of the Neutron Source for the post BA activities

Vision of the Neutron Source for the post BA activities 3rd IAEA DEMO Programme Workshop May 11-14, 2015, Hefei, China Vision of the Neutron Source for the post BA activities S. O hira1, K. Ochiai1, M. Sugimoto1, A. Kasugai1, K. Ushigusa1, J. Knaster2, Y. Okumura2,

More information

Studies of Impurity Seeding and Divertor Power Handling in Fusion Reactor

Studies of Impurity Seeding and Divertor Power Handling in Fusion Reactor 1 FIP/P8-11 Studies of Impurity Seeding and Divertor Power Handling in Fusion Reactor K. Hoshino 1, N. Asakura 1, K. Shimizu 2 and S. Tokunaga 1 1 Japan Atomic Energy Agency, Rokkasho, Aomori 039-3212

More information

The DAΦNE Cryogenic System

The DAΦNE Cryogenic System LABORATORI NAZIONALI DI FRASCATI SIS Pubblicazioni LNF 97/046 (IR) 19 Dicembre 1997 The DAΦNE Cryogenic System M. Modena INFN - Laboratori Nazionali di Frascati, P. O. Box 13, I-00044 Frascati (Roma),

More information

ITER Organization - Scientific Internships- 2016

ITER Organization - Scientific Internships- 2016 Human Resources Route de Vinon-sur-Verdon - CS 90 046-13067 St-Paul-Lez-Durance Cedex - France ITER Organization - Scientific Internships- Internship subject Start Non-linear MHD ELM simulations with fluid

More information

Design Progress and Analysis for ITER Thermal Shield

Design Progress and Analysis for ITER Thermal Shield 1 IT/P7-21 Design Progress and Analysis for ITER Thermal Shield W. Chung 1), K. W. Nam 1), C. H. Noh 1), B. C. Kim 1), J. W. Sa 1), Y. Utin 2), K. Ioki 2), N. I. Her 2), J. Yu 2), H. J. Ahn 1), K. J. Jung

More information

ITER TOKAMAK VACUUM VESSEL THERMAL SHIELD ADDITIONAL NEUTRAL SHIELDING

ITER TOKAMAK VACUUM VESSEL THERMAL SHIELD ADDITIONAL NEUTRAL SHIELDING Route de Vinon-sur-Verdon - CS 90 046-13067 St Paul Lez Durance Cedex - France ITER TOKAMAK VACUUM VESSEL THERMAL SHIELD ADDITIONAL NEUTRAL SHIELDING CALL FOR NOMINATION Ref. IO/CFN/14/11176/PMT SUMMARY

More information

Energy efficiency and saving potential analysis of the high intensity proton accelerator HIPA at PSI

Energy efficiency and saving potential analysis of the high intensity proton accelerator HIPA at PSI Journal of Physics: Conference Series PAPER OPEN ACCESS Energy efficiency and saving potential analysis of the high intensity proton accelerator HIPA at PSI To cite this article: A Kovach et al 2017 J.

More information

Recent Progress of JT-60SA Project

Recent Progress of JT-60SA Project Shirai DOI:10.1088/1741-4326/aa5d01 OV/3-3 Recent Progress of JT-60SA Project H. Shirai 1, P. Barabaschi 2, and Y. Kamada 1 1 Japan Atomic Energy Agency (JAEA), Naka, Japan 2 F4E: Fusion for Energy, ITER

More information

INFORMATION DAY. Fusion for Energy (F4E)

INFORMATION DAY. Fusion for Energy (F4E) INFORMATION DAY 26th November 2013, Zagreb Fusion for Energy (F4E) Part 2 Status of the ITER Project and Achievements Jesus Izquierdo Technical Coordination and Integration 1 THE ITER PROJECT MAIN SYSTEMS

More information

Status of XFEL Module Assembly at Saclay

Status of XFEL Module Assembly at Saclay Status of Module Assembly at Saclay O. Napoly, CEA-Saclay, IRFU/SACM 1 CEA contributes to the Cold Linac construction through Cavity String Assembly in Clean Room (WP9) and Module Assembly (WP3) Accelerator

More information

Progress of the Development of the IPP RF Negative Ion Source for the ITER Neutral Beam System

Progress of the Development of the IPP RF Negative Ion Source for the ITER Neutral Beam System IT/2-3Rc Progress of the Development of the IPP RF Negative Ion Source for the ITER Neutral Beam System P. Franzen, H. D. Falter, U. Fantz, W. Kraus, M. Berger, S. Christ, M. Fröschle, R. Gutser, B. Heinemann,

More information

Computational needs of fusion scientists David Coster

Computational needs of fusion scientists David Coster Computational needs of fusion scientists David Coster Max-Planck-Institut für Plasmaphysik Outline Why fusion Computational needs Laptops to Exaflops A few examples Some personal observations David Coster

More information

PROGRESS ON THE SECTOR MAGNETS FOR THE RIKEN SRC

PROGRESS ON THE SECTOR MAGNETS FOR THE RIKEN SRC PROGRESS ON THE SECTOR MAGNETS FOR THE RIKEN SRC A. Goto, H. Okuno, J. Ohnishi, N. Fukunishi, T. Mitsumoto, S. Fujishima, T. Tominaka, K. Ikegami, Y. Miyazawa, and Y. Yano, RIKEN, Wako, Saitama 351-0198,

More information

Fusion: the fundamental principle

Fusion: the fundamental principle The ITER Project The ITER Project The ITER Project aims to demonstrate the scientific and technological feasibility of fusion power for peaceful purposes. Iter project is an international cooperation between

More information

Fully Active Cooled In-vessel Components of EAST Tokamak

Fully Active Cooled In-vessel Components of EAST Tokamak 1 FTP/P1-30 Fully Active Cooled In-vessel Components of EAST Tokamak Y.T. Song, X. Ji, G. Shen, T.J. Xu, Z.B. Zhou, L. Cao, X.F. Liu, W.W. Xu, X.B. Peng, S.M. Wang, P, Zhang, N. Zhu, J.F. Wu, D.M. Gao,

More information

The ITER Blanket System Design Challenge

The ITER Blanket System Design Challenge The ITER Blanket System Design Challenge Presented by A. René Raffray Blanket Section Leader; Blanket Integrated Product Team Leader ITER Organization, Cadarache, France With contributions from B. Calcagno

More information

Accelerator Driven Systems. Dirk Vandeplassche, Luis Medeiros Romão

Accelerator Driven Systems. Dirk Vandeplassche, Luis Medeiros Romão Accelerator Driven Systems Dirk Vandeplassche, Luis Medeiros Romão IPAC'12, New Orleans (Louisiana) May 21, 2012 1 Overview 1. Introduction 2. The accelerator for ADS 3. Projects 4. Concluding remarks

More information

Tentative Translation

Tentative Translation Japan s Policy to promote R&D for a fusion DEMO reactor Decided on December 18, 2017 by Science and Technology Committee on Fusion Energy Subdivision on R&D Planning and Evaluation, Council for Science

More information

Development of Advanced Operation Scenarios in Weak Magnetic-Shear Regime on JT-60U

Development of Advanced Operation Scenarios in Weak Magnetic-Shear Regime on JT-60U EX/1-4Rc Development of Advanced Operation Scenarios in Weak Magnetic-Shear Regime on JT-60U T. Suzuki 1), N. Oyama 1), A. Isayama 1), Y. Sakamoto 1), T. Fujita 1), S. Ide 1), Y. Kamada 1), O. Naito 1),

More information

AIR LIQUIDE AND ITER WHEN THE EXPERTS IN CRYOGENICS FUSE THEIR ENERGIES

AIR LIQUIDE AND ITER WHEN THE EXPERTS IN CRYOGENICS FUSE THEIR ENERGIES AIR LIQUIDE AND WHEN THE EXPERTS IN FUSE THEIR ENERGIES , A UNIQUE PROJECT SEVEN INTERNATIONAL PARTNERS The magnitude of the scientific, technical and organizational challenge, plus the considerable resources

More information

Conceptual Design of Neutral Beam Injection System for EAST

Conceptual Design of Neutral Beam Injection System for EAST Conceptual Design of Neutral Beam Injection System for EAST HU Chundong (胡纯栋), NBI Team Institute of Plasma Physics, Chinese Academy of Sciences, Hefei 230031, China Abstract Neutral beam injection (NBI)

More information

Radiation Environment and Shielding Design Optimization at MEIC

Radiation Environment and Shielding Design Optimization at MEIC Radiation Environment and Shielding Design Optimization at MEIC Pavel Degtiarenko Radiation Physics Group Radiation Control Department, JLab October, 2015 Contents Brief review of MEIC Radiation Protection

More information

Concept Development of DEMO in Japan

Concept Development of DEMO in Japan US-JPN WS on Fusion Power Reactor 2014.3.13, UCSD Concept Development of DEMO in Japan JAEA Kenji Tobita 2/22 OUTLINE 1. Circumstances Surrounding DEMO 2. DEMO Design Activity 3. Safety Study 1. Circumstances

More information

Status of the FAIR plinac Accelerator Seminar C. Kleffner

Status of the FAIR plinac Accelerator Seminar C. Kleffner GSI Helmholtzzentrum für Schwerionenforschung GmbH Status of the FAIR plinac Accelerator Seminar 12. 10. 2017 C. Kleffner plinac - overview Beam Energy (MeV) 70 68 Design Current (ma) 70 Beam Pulse (µs)

More information

ITER: Another Way for the Nuclear Industry

ITER: Another Way for the Nuclear Industry ITER: Another Way for the Nuclear Industry Fusion for Energy, the European Domestic Agency for the ITER Project June 9th 2015 Anthony Courtial Market Intelligence & Supply Chain Analysis Outline 1. The

More information

Fusion for Energy The European Domestic Agency for ITER. F4E Contracts & Procurement Unit

Fusion for Energy The European Domestic Agency for ITER. F4E Contracts & Procurement Unit Fusion for Energy The European Domestic Agency for ITER F4E Contracts & Procurement Unit Market Policy Group Agenda 1. Fusion Energy 2. ITER 3. Europe in ITER: F4E Fusion for Energy 4. F4E Contractual

More information

Medical Isotope Production by Electron Accelerators. R.S. Orr University of Toronto

Medical Isotope Production by Electron Accelerators. R.S. Orr University of Toronto Medical Isotope Production by Electron Accelerators R.S. Orr University of Toronto Power Reactor Uranium Fission Chain reaction neutrons ANSTO's Open Pool Australian Lightwater (OPAL) Reactor is a state-of-the-art

More information

The Heat Rejection System of the ITER Reactor

The Heat Rejection System of the ITER Reactor The Heat Rejection System of the ITER Reactor G. Dell Orco, W. Curd, D. Gupta, L. Fan, K.P. Chang, I. Kuehn, A. Kumar* International Thermonuclear Experimental Reactor Organization (ITER-IO) 13108 Saint

More information

Scientific Status of ITER

Scientific Status of ITER Scientific Status of ITER D J Campbell ITER Organization, Cadarache Acknowledgements: Many colleagues in the ITER IO, ITER Members and ITPA Page 1 Summary of Presentation What are the main changes resulting

More information

Second stage cooling from a Cryomech PT415 cooler at second stage temperatures up to 300 K with cooling on the first-stage from 0 to 250 W

Second stage cooling from a Cryomech PT415 cooler at second stage temperatures up to 300 K with cooling on the first-stage from 0 to 250 W IOP Conference Series: Materials Science and Engineering PAPER OPEN ACCESS Second stage cooling from a Cryomech PT415 cooler at second stage temperatures up to 3 K with cooling on the first-stage from

More information

R&D required to place a test module on FNF (how does it compare to ITER TBM?) R&D required for base blanket

R&D required to place a test module on FNF (how does it compare to ITER TBM?) R&D required for base blanket Testing Strategy, Implications for R&D and Design What are the preferred blankets options for testing on FNF and what are the implications for R&D? Comparison of strategies for testing space allocation

More information

ITER ITA NEWSLETTER. No. 13, FEBRUARY 2004 INTERNATIONAL ATOMIC ENERGY AGENCY, VIENNA, AUSTRIA ISSN

ITER ITA NEWSLETTER. No. 13, FEBRUARY 2004 INTERNATIONAL ATOMIC ENERGY AGENCY, VIENNA, AUSTRIA ISSN ITER ITA NEWSLETTER No. 13, FEBRUARY 2004 INTERNATIONAL ATOMIC ENERGY AGENCY, VIENNA, AUSTRIA ISSN 1727 9852 COMMON MESSAGE FROM SECOND PREPARATORY MEETING FOR MINISTERIAL MEETING FOR ITER Delegations

More information

COREDIV modelling of JET ILW discharges with different impurity seeding: nitrogen, neon, argon and krypton*

COREDIV modelling of JET ILW discharges with different impurity seeding: nitrogen, neon, argon and krypton* NUKLEONIKA 17;(1): 7 doi: 1./nuka-17-1 ORIGINAL PAPER 17 Irena Ivanova-Stanik et al. This is an open access article distributed under the Creative Commons Attribution -NonCommercial-NoDerivatives. License

More information

Application of Infrared Thermography in NDT of Plasma-Facing Components for Tokamaks

Application of Infrared Thermography in NDT of Plasma-Facing Components for Tokamaks 17th World Conference on Nondestructive Testing, 25-28 Oct 2008, Shanghai, China Application of Infrared Thermography in NDT of Plasma-Facing Components for Tokamaks Pan QI, Qiang LI, Guang-Nan LUO Institute

More information

Design of Solid Breeder Test Blanket Modules in JAERI

Design of Solid Breeder Test Blanket Modules in JAERI Design of Solid Breeder Test Blanket Modules in JAERI Presented by: S. Suzuki, Blanket Engineering Lab., Japan Atomic Energy Research Institute, JAERI Contents 1. Outline of blanket development in JAERI

More information

Technical Specification for Qualification of magnet assembly procedures

Technical Specification for Qualification of magnet assembly procedures IDM UID R34F76 VERSION CREATED ON / VERSION / STATUS 09 Jul 2015 / 2.2 / Approved EXTERNAL REFERENCE / VERSION Call for Expert Documents Technical Specification for Qualification of magnet assembly procedures

More information

BEAM PARTICLE SOURCES RESEARCH AT UNIVERSIDAD AUTÓNOMA DE SINALOA

BEAM PARTICLE SOURCES RESEARCH AT UNIVERSIDAD AUTÓNOMA DE SINALOA BEAM PARTICLE SOURCES RESEARCH AT UNIVERSIDAD AUTÓNOMA DE SINALOA XXXI Reunión Anual de la División de Partículas y Campos de la SMF 24/5/2017 Cristhian Valerio Lizarraga,Carlos Duarte, Ildefonso Leon,

More information

The Development Path for Magnetic Fusion Energy

The Development Path for Magnetic Fusion Energy The Development Path for Magnetic Fusion Energy Rob Goldston Princeton Plasma Physics Laboratory Global Climate and Energy Project Workshop on Fusion Energy May 1, 2006 Fusion is an Attractive Long-term

More information

EU considerations on Design and Qualification of Plasma Facing Components for ITER

EU considerations on Design and Qualification of Plasma Facing Components for ITER EU considerations on Design and Qualification of Plasma Facing Components for ITER Patrick Lorenzetto, F4E Barcelona with inputs from B. Riccardi (F4E), V. Barabash and M. Merola (ITER IO) on Readiness

More information

Part. B Fusion for Energy. The European Joint Undertaking for ITER and the Development of Fusion Energy. Technical Activity Report

Part. B Fusion for Energy. The European Joint Undertaking for ITER and the Development of Fusion Energy. Technical Activity Report Part B Fusion for Energy The European Joint Undertaking for ITER and the Development of Fusion Energy Technical Activity Report 2007-2008 FUSION FOR ENERGY Technical Activity Report 2007-2008 Fusion for

More information

Radiation Resistant Insulation Systems for the ITER Toroidal Field Coils

Radiation Resistant Insulation Systems for the ITER Toroidal Field Coils Radiation Resistant Insulation Systems for the ITER Toroidal Field Coils R. Prokopec 1), K. Humer 1), R. K. Maix 1), H. Fillunger 1), H. W. Weber 1), J. Knaster 2), F. Savary 2) 1) Vienna University of

More information

European Experience In Transport / Storage Cask for Vitrified Residues

European Experience In Transport / Storage Cask for Vitrified Residues ABSTRACT European Experience In Transport / Storage Cask for Vitrified Residues L. Blachet, C. Otton, D. Sicard AREVA TN International Because of the evolution of burnup of spent fuel to be reprocessed,

More information

R&D of the ITER Correction Coil magnet system in China

R&D of the ITER Correction Coil magnet system in China 1 ITR/P1-52 R&D of the ITER Correction Coil magnet system in China J. Wei 1), S.S.Du 1), A.Foussat 2), X.W.Yu 1), L.P.Liu 1), S.Q.Han 1),X.F.Liu 1), W.Y.Wu 1), N.Dolgetta 2), P.Libeyre 2) 1) Institute

More information

EP-23. Advanced EP Concepts, AIAA Jared P. Squire, Mark D. Carter, Franklin R. Chang Diaz, Lawrence Dean, Matthew Giambusso, Jose Castro,

EP-23. Advanced EP Concepts, AIAA Jared P. Squire, Mark D. Carter, Franklin R. Chang Diaz, Lawrence Dean, Matthew Giambusso, Jose Castro, EP-23. Advanced EP Concepts, AIAA-2016-4950 Jared P. Squire, Mark D. Carter, Franklin R. Chang Diaz, Lawrence Dean, Matthew Giambusso, Jose Castro, Juan Del Valle Presented by Mark Carter 1.A review of

More information

Technical Summary for TCC0 Global overview of the scope for TCC0 contract

Technical Summary for TCC0 Global overview of the scope for TCC0 contract IDM UID V89YJN VERSION CREATED ON / VERSION / STATUS 06 Oct 2017 / 2.0 / Signed EXTERNAL REFERENCE / VERSION Technical Specification Technical Summary for TCC0 Global overview of the scope for TCC0 contract

More information

9. VACUUM TANK 9. VACUUM TANK

9. VACUUM TANK 9. VACUUM TANK 9. VACUUM TANK This system constitutes the external part of the solenoid cryostat. The vacuum tank, made of stainless steel, is cantilevered from the central ring of the barrel yoke. It houses and supports

More information

PPP&T Power Exhaust Studies

PPP&T Power Exhaust Studies PPP&T Power Exhaust Studies Leena Aho-Mantila VTT Technical Research Centre of Finland Visiting researcher at the Max-Planck- Institut für Plasmaphysik (IPP), Garching, Germany Euratom-TEKES Annual Seminar

More information

MEGAPIE experiment. EURISOL 2nd TOWN MEETING. January 24th and 25th, 2002 ITALY. Th. Kirchner

MEGAPIE experiment. EURISOL 2nd TOWN MEETING. January 24th and 25th, 2002 ITALY. Th. Kirchner EURISOL 2nd TOWN MEETING January 24th and 25th, 2002 ITALY Th. Kirchner Ecole des Mines de Nantes; 4 rue Alfred Kastler; BP 20722; 44307 Nantes cedex 03; FRANCE Thomas KIRCHNER, SUBATECH Context of the

More information

Status of ITER Buildings construction and next procurement steps

Status of ITER Buildings construction and next procurement steps Status of ITER Buildings construction and next procurement steps Laurent Schmieder Site, Buildings and Power Supplies Project Manager IBF/15 DIRECTORY IBF/15 March 25-27 March 25-27, 2015 Palais du Pharo

More information

ILC ASIAN DRAFT SCHEDULE

ILC ASIAN DRAFT SCHEDULE ILC ASIAN DRAFT SCHEDULE K Foraz, M Gastal & J Osborne Many thanks to all contributors Objectives and scope To provide a target baseline construction schedule for the 2 Asian sample sites Address remarks

More information

EU Contribution to ITER Remote Handling

EU Contribution to ITER Remote Handling EU Contribution to ITER Remote Handling Updates on technical and procurement status Carlo Damiani Project Manager Remote Handling Team Fusion for Energy 1 Outline Overview on ITER Remote Handling Situation

More information

Wisconsin Space Grant Consortium Graduate Fellowship Award and the NASA Space Technology Research Fellowship Program

Wisconsin Space Grant Consortium Graduate Fellowship Award and the NASA Space Technology Research Fellowship Program Recent Progress in Lunar Helium-3 Extraction Research Aaron D.S. Olson Engineering Physics Dept., University of Wisconsin-Madison 1 Abstract Research is ongoing to develop a prototype lunar volatiles extraction

More information

Gas Cooled Fast Reactors: recent advances and prospects

Gas Cooled Fast Reactors: recent advances and prospects Gas Cooled Fast Reactors: recent advances and prospects C. Poette a, P. Guedeney b, R. Stainsby c, K. Mikityuk d, S. Knol e a CEA, DEN, DER, F-13108 Saint-Paul lez Durance, CADARACHE, France. b CEA, DEN,

More information

ITER Research Needs. Report by David Campbell Plasma Operation Directorate

ITER Research Needs. Report by David Campbell Plasma Operation Directorate ITER Research Needs Report by David Campbell Plasma Operation Directorate Acknowledgements: Members of PO and CHD directorates, together with many experts in the international fusion community The views

More information

llilliiiillllllllilllllllllllllllllllllllil CERN AT, (CR, 94'36

llilliiiillllllllilllllllllllllllllllllllil CERN AT, (CR, 94'36 EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH CERN LIBRARIES, GENEVA llilliiiillllllllilllllllllllllllllllllllil CERN AT, (CR, 94'36 QERN-AT-94-36 ;.t W4?. Four 12 kw/4.5 K Cryoplants at CERN S. Claudet,

More information

Occupational Radiation Exposure (ORE) Dose Rate for TBM Replacement/Maintenance and Improving Estimates by 3-D Calculations

Occupational Radiation Exposure (ORE) Dose Rate for TBM Replacement/Maintenance and Improving Estimates by 3-D Calculations Occupational Radiation Exposure (ORE) Dose Rate for TBM Replacement/Maintenance and Improving Estimates by 3-D Calculations Mahmoud Youssef Mohamed Dagher UCLA With input from Brad Merrill (INL) FNST Meeting,

More information

Assessment and comparison of pulsed and steady-state tokamak power plants

Assessment and comparison of pulsed and steady-state tokamak power plants Assessment and comparison of pulsed and steady-state tokamak power plants Farrokh Najmabadi UC San Diego 21 st International Toki Conference, 28 Novemeber-1 December 2011 Toki, Japan Choice between steady-state

More information

The Australian Plasma Fusion Research Facility

The Australian Plasma Fusion Research Facility The Australian Plasma Fusion Research Facility NCRIS Progress Report 3: 1 st July to 31 st December 2014 This document is a brief report on the activities within Australian Plasma Fusion Research Facility

More information

THE ACCELERATOR PRODUCTION OF TRITIUM PROJECT

THE ACCELERATOR PRODUCTION OF TRITIUM PROJECT THE ACCELERATOR PRODUCTION OF TRITIUM PROJECT P. W. Lisowski, Los Alamos National Laboratory, Los Alamos NM 87545, USA Abstract Tritium is essential for U.S. nuclear weapons to function, but because it

More information

ITER-FEAT Vacuum Vessel and Blanket Design Features and Implications for the R&D Programme

ITER-FEAT Vacuum Vessel and Blanket Design Features and Implications for the R&D Programme ITER-FEAT Vacuum Vessel and Blanket Design Features and Implications for the R&D Programme K. Ioki 1), W. Daenner 2), K. Koizumi 3), V.Krylov 4), A. Cardella 1), F. Elio 1), M. Onozuka 1), ITER Joint Central

More information

El Séptimo Programa Marco de I+D de la Unión Europea Cómo tener éxito en las convocatorias 2013

El Séptimo Programa Marco de I+D de la Unión Europea Cómo tener éxito en las convocatorias 2013 El Séptimo Programa Marco de I+D de la Unión Europea Cómo tener éxito en las convocatorias 2013 Activity: Research and Development Title: Empresarios Agrupados: an innovative company Experience in the

More information

WM2015 Conference, March 15-19, 2015, Phoenix, Arizona, USA

WM2015 Conference, March 15-19, 2015, Phoenix, Arizona, USA An Integrated Equipment for Massive Segmentation and Packaging of Control Rod Guide Tubes 15161 Joseph Boucau*, Patrick Gobert** Sébastien Bonne *** * Westinghouse Electric Company, 43 rue de l Industrie,

More information

The Design and Construction of Miniature, High-Pressure, Penning Ionization Gauges for Alcator C-Mod

The Design and Construction of Miniature, High-Pressure, Penning Ionization Gauges for Alcator C-Mod PSFC/RR-15-12 The Design and Construction of Miniature, High-Pressure, Penning Ionization Gauges for Alcator C-Mod B. LaBombard MIT Plasma Science and Fusion Center, Cambridge, MA, USA. December, 2015

More information

Superconducting. magnets. The heart of NMR

Superconducting. magnets. The heart of NMR MARTIN TOWNSEND OXFORD INSTRUMENTS SUPERCONDUCTIVITY Superconducting The achievements of Oxford Instruments Superconductivity as a world leader in the research and development of superconducting magnets

More information

THE PROMISE OF FUSION ENERGY. General Atomics

THE PROMISE OF FUSION ENERGY. General Atomics THE PROMISE OF FUSION ENERGY General Atomics The following slide show is a compilation of slides from many previous similar slide shows that have been produced by different members of the fusion and plasma

More information

Best practices for preparing vessel internals segmentation projects

Best practices for preparing vessel internals segmentation projects Best practices for preparing vessel internals segmentation projects Joseph BOUCAU a*, Per SEGERUD b, Moisés SANCHEZ c a Westinghouse Electric Company, 43 rue de l Industrie, 1400 Nivelles, Belgium b Westinghouse

More information

JULES HOROWITZ REACTOR: RCC-MRx [1] APPLICABILITY FOR THE DESIGN PHASE OF EXPERIMENTAL DEVICES. S. GAY 1, S. GAILLOT 1

JULES HOROWITZ REACTOR: RCC-MRx [1] APPLICABILITY FOR THE DESIGN PHASE OF EXPERIMENTAL DEVICES. S. GAY 1, S. GAILLOT 1 JULES HOROWITZ REACTOR: RCC-MRx [1] APPLICABILITY FOR THE DESIGN PHASE OF EXPERIMENTAL DEVICES. S. GAY 1, S. GAILLOT 1 Abstract. 1) CEA, DEN, DTN, Nuclear Technology Department, CEA Cadarache. F-13108

More information

R. Prokopec, K. Humer, H. Fillunger, R. K. Maix, and H. W. Weber

R. Prokopec, K. Humer, H. Fillunger, R. K. Maix, and H. W. Weber PROPERTY CHANGES OF CYANATE ESTER / EPOXY INSULATION SYSTEMS CAUSED BY AN ITER-LIKE DOUBLE IMPREGNATION AND BY REACTOR IRRADIATION R. Prokopec, K. Humer, H. Fillunger, R. K. Maix, and H. W. Weber Atominstitut,

More information

Prediction of laser welding failure. on seat mechanisms simulation

Prediction of laser welding failure. on seat mechanisms simulation Prediction of laser welding failure on seat mechanisms simulation M. CHAUFFRAY*, G. DELATTRE*, L. GUERIN**, C. POUVREAU*** * Faurecia Automotive seating, Le pont de vère, 61100 Caligny ** Faurecia automotive

More information

COLD NEUTRON SOURCE AT CMRR

COLD NEUTRON SOURCE AT CMRR COLD NEUTRON SOURCE AT CMRR Hu Chunming Shen Wende, Dai Junlong, Liu Xiankun ( 1 ) Vadim Kouzminov, Victor Mityukhlyaev / 2 /, Anatoli Serebrov, Arcady Zakharov ( 3 ) ABSTRACT As an effective means to

More information

X-point Target Divertor Concept

X-point Target Divertor Concept X-point Target Divertor Concept and Alcator DX High Power Density Divertor Test Facility Presented by Brian LaBombard for the Alcator Team Alcator DX Contributed Oral C04.00002 Presented at the 55th Annual

More information

Energy consumption and savings potential of CLIC

Energy consumption and savings potential of CLIC Energy consumption and savings potential of CLIC Philippe Lebrun CERN, Geneva, Switzerland 55th ICFA Advanced Beam Dynamics Workshop on High Luminosity Circular e + e - Colliders Higgs Factory Beijing,

More information

What is Cryogenics? Cryogenics is the science and technology associated with generation of low temperature below 123 K.

What is Cryogenics? Cryogenics is the science and technology associated with generation of low temperature below 123 K. 1 1 What is Cryogenics? Kryo Very cold (frost) Genics to produce Cryogenics is the science and technology associated with generation of low temperature below 123 K. 2 Course outline This course is aimed

More information

Diagnostics for Studying Deposition and Erosion Processes in JET

Diagnostics for Studying Deposition and Erosion Processes in JET EFDA JET CP(04)06-10 P. Coad, H-G Esser, J. Likonen, M Mayer, G Neill, V Philipps, M. Rubel, J Vince and JET EFDA Contributors Diagnostics for Studying Deposition and Erosion Processes in JET . Diagnostics

More information

R&D Needs and Required Facilities for the Development of Fusion as an Energy Source

R&D Needs and Required Facilities for the Development of Fusion as an Energy Source R&D Needs and Required Facilities for the Development of Fusion as an Energy Source Report Report of the Fusion Facilities Review Panel Interested in European research? Research*eu is our monthly magazine

More information

High Power Operation of Cryogenic Yb:YAG. K. F. Wall, B. Pati, and P. F. Moulton Photonics West 2007 San Jose, CA January 23, 2007

High Power Operation of Cryogenic Yb:YAG. K. F. Wall, B. Pati, and P. F. Moulton Photonics West 2007 San Jose, CA January 23, 2007 High Power Operation of Cryogenic Yb:YAG K. F. Wall, B. Pati, and P. F. Moulton Photonics West 2007 San Jose, CA January 23, 2007 Outline Early work on cryogenic lasers MPS laser technology Recent program

More information

Microwave Plasma Processing

Microwave Plasma Processing Microwave Plasma Processing MUEGGE GMBH Hochstraße 4-6 64385 Reichelsheim Fon +49 (0) 6164-93 07 11 Fax +49 (0) 6164-93 07 93 info@muegge.de www.muegge.de Microwave Plasma Processing Microwave Plasma Technology:

More information

Application for Permission to Extend the Operating Period and Application for Approval of Construction Plans of Unit 3 at Mihama Nuclear Power Station

Application for Permission to Extend the Operating Period and Application for Approval of Construction Plans of Unit 3 at Mihama Nuclear Power Station November 26, 2015 The Kansai Electric Power Co., Inc. Application for Permission to Extend the Operating Period and Application for Approval of Construction Plans of Unit 3 at Mihama Nuclear Power Station

More information

Preliminary Design of ITER Component Cooling Water System and Heat Rejection System

Preliminary Design of ITER Component Cooling Water System and Heat Rejection System Preliminary Design of ITER Component Cooling Water System and Heat Rejection System A.G.A. Kumar 1, D.K. Gupta 1, N. Patel 1, G. Gohil 1, H. Patel 1, J. Dangi 1, L. Sharma 1, M. Jadhav 1, L. Teodoros 2,

More information

talk to experts Industrial-grade Magnetic Pulse (MP) and Electro-hydraulic (EH) systems for FORMING, WELDING, CRIMPING and EXPANSION

talk to experts Industrial-grade Magnetic Pulse (MP) and Electro-hydraulic (EH) systems for FORMING, WELDING, CRIMPING and EXPANSION talk to experts Industrial-grade Magnetic Pulse (MP) and Electro-hydraulic (EH) systems for FORMING, WELDING, CRIMPING and EXPANSION the company Bmax is the global leading provider of advanced metal processing

More information

Certification, Testing, Approval and R&D work on the Absorber Safety

Certification, Testing, Approval and R&D work on the Absorber Safety , Testing, Approval and R&D work on the Absorber Safety A discussion document prepared for the Safety Review rehearsal talk on Monday the 17 th of November 2003 1 and its scope needed? Design Material

More information

DECOMMISSIONING PROGRAMS AND TECHNOLOGY DEVELOPMENT IN JAPAN ATOMIC ENERGY RESEARCH INSTITUTE

DECOMMISSIONING PROGRAMS AND TECHNOLOGY DEVELOPMENT IN JAPAN ATOMIC ENERGY RESEARCH INSTITUTE DECOMMISSIONING PROGRAMS AND TECHNOLOGY DEVELOPMENT IN JAPAN ATOMIC ENERGY RESEARCH INSTITUTE Mitsugu Tanaka, Mimori Takeo, Takakuni Hirabayashi and Satoshi Yanagihara Japan Atomic Energy Research Institute

More information

CLIC Civil Engineering, Infrastructure and Siting Working Group, (CEIS) John Osborne Matthew Stuart CERN SMB-SE-FAS

CLIC Civil Engineering, Infrastructure and Siting Working Group, (CEIS) John Osborne Matthew Stuart CERN SMB-SE-FAS CLIC Civil Engineering, Infrastructure and Siting Working Group, (CEIS) John Osborne Matthew Stuart CERN SMB-SE-FAS 1 CEIS Working Group Civil Engineering, Infrastructure and Siting Core Disciplines: Civil

More information

WM2014 Conference, March 2 6, 2014, Phoenix, Arizona, USA

WM2014 Conference, March 2 6, 2014, Phoenix, Arizona, USA Reactor D&D: AREVA French and German Latest Experiences - 14458 (1) Stephan Krüger, AREVA GmbH, Kaiserleistr. 29, 63067 Offenbach, Germany; stephan.krueger@areva.com (2) Xavier de Brimont, AREVA NC, 1

More information

PROGRESS OF ITER FIRST WALL DESIGN ABSTRACT 1. INTRODUCTION

PROGRESS OF ITER FIRST WALL DESIGN ABSTRACT 1. INTRODUCTION PROGRESS OF ITER FIRST WALL DESIGN R. Mitteau(*), R. Raffray(*), P. Chappuis(*), M. Merola(*), D. Loesser(**) on behalf of the ITER Organization and the Blanket Integrated Product Team(1) (*) ITER Organization,

More information

55.E6 VSRS - Technical Summary for Design Development Service Contract

55.E6 VSRS - Technical Summary for Design Development Service Contract IDM UID VF32E5 VERSION CREATED ON / VERSION / STATUS 06 Oct 2017 / 1.1 / Approved EXTERNAL REFERENCE / VERSION Report 55.E6 VSRS - Technical Summary for Design Development Service Contract 55.E6 VSRS -

More information

Residual Stress Measurements Using Neutron Diffraction in Magnesium Alloy Laser Welded Joints

Residual Stress Measurements Using Neutron Diffraction in Magnesium Alloy Laser Welded Joints Residual Stress Measurements Using Neutron Diffraction in Magnesium Alloy Laser Welded Joints A. Fabre 1, J.-É. Masse 1, M. Ceretti 2 and L. Barrallier 1 1 MécaSurf Team, ENSAM - 2, cours des Arts et Métiers

More information

Vertically aligned 14 Tesla split-pair

Vertically aligned 14 Tesla split-pair Tel: +44 (0)20 8743 6049 Fax: +44 (0)20 8749 5315 Email: sales@cryogenic.co.uk Vertically aligned 14 Tesla split-pair magnet for X-ray Scattering Low-loss cryostat Goniometer mounted Beryllium windows

More information

Bonded Neo Magnetization Guide

Bonded Neo Magnetization Guide Bonded Neo Magnetization Guide 1 Presentation Outline 1. Magnetizing Systems 2. Fixture Design 3. Construction 4. Testing 5. Design Study 2 Magnetizing Systems A typical magnetizing system consists of

More information

Concepts and Features of ATMEA1 TM as the latest 1100 MWe-class 3-Loop PWR Plant

Concepts and Features of ATMEA1 TM as the latest 1100 MWe-class 3-Loop PWR Plant 8 Concepts and Features of ATMEA1 TM as the latest 1100 MWe-class 3-Loop PWR Plant KOZO TABUCHI *1 MASAYUKI TAKEDA *2 KAZUO TANAKA *2 JUNICHI IMAIZUMI *2 TAKASHI KANAGAWA *3 ATMEA1 TM is a 3-loop 1100

More information

EU DEMO Design Point Studies

EU DEMO Design Point Studies EU DEMO Design Point Studies R. Kemp 1, D. J. Ward 1, G. Federici 2, R. Wenninger 2,3 and J. Morris 1 1 CCFE, Culham Science Centre, Oxfordshire OX14 3DB, United Kingdom 2 EFDA PPPT, Boltzmannstr.2, Garching

More information

Maintenance Concept for Modular Blankets in Compact Stellarator Power Plants

Maintenance Concept for Modular Blankets in Compact Stellarator Power Plants Maintenance Concept for Modular Blankets in Compact Stellarator Power Plants Siegfried Malang With contributions of Laila A. EL-Guebaly Xueren Wang ARIES Meeting UCSD, San Diego, January 8-10, 2003 Overview

More information

CHARACTERIZATION OF TITANIUM ALLOYS FOR CRYOGENIC APPLICATIONS

CHARACTERIZATION OF TITANIUM ALLOYS FOR CRYOGENIC APPLICATIONS CHARACTERIZATION OF TITANIUM ALLOYS FOR CRYOGENIC APPLICATIONS M. Reytier, F. Kircher, B. Levesy CEA Saclay, DSM / DAPNIA / STCM Gif sur Yvette, 91191, France ABSTRACT Titanium alloys are employed in the

More information

Overview of ITER-FEAT The future international burning plasma experiment

Overview of ITER-FEAT The future international burning plasma experiment Overview of ITER-FEAT The future international burning plasma experiment R. Aymar a,v.a.chuyanov a,m.huguet b, Y. Shimomura b, ITER Joint Central Team, ITER Home Teams a ITER Garching Joint Work Site,

More information

Status of Research on Deposition of Superconducting Films for RF Accelerating Cavities

Status of Research on Deposition of Superconducting Films for RF Accelerating Cavities Status of Research on Deposition of Superconducting Films for RF Accelerating Cavities J. Langner, L. Catani*, A. Cianchi*, K. Czaus, R. Mirowski, R. Russo*, M.J. Sadowski, S. Tazzari*, F. Tazzioli***,

More information

LA-UR-99-2820 Approved for public release; distribution is unlimited. Title: STATUS OF THE ACCELERATOR PRODUCTION OF TRITIUM (APT) PROJECT Author(s): Submitted to: J. L. Anderson and P. W. Lisowski Los

More information

In-Process Monitoring and Adaptive Control in Micro Welding with a Single-Mode Fiber Laser.

In-Process Monitoring and Adaptive Control in Micro Welding with a Single-Mode Fiber Laser. Title Author(s) In-Process Monitoring and Adaptive Control in Micro Welding with a Single-Mode Fiber Laser KAWAHITO, Yousuke; KATAYAMA, Seiji Citation Transactions of JWRI. 38(2) P.5-P.11 Issue Date 2009-12

More information