Fusion Engineering and Design最新文献

{"title":"Non-destructive ultrasonic inspections of small-scale mock-ups provided with advanced tungsten armours for DEMO divertor target","authors":"Riccardo De Luca ,&nbsp;Emanuele Cacciotti ,&nbsp;Marco Cerocchi ,&nbsp;Francesco Crea ,&nbsp;Selanna Roccella ,&nbsp;Henri Greuner ,&nbsp;Katja Hunger ,&nbsp;Carsten Bonnekoh ,&nbsp;Andrei Galatanu ,&nbsp;Aljaž Iveković ,&nbsp;Petra Jenuš ,&nbsp;Marius Wirtz","doi":"10.1016/j.fusengdes.2025.115007","DOIUrl":"10.1016/j.fusengdes.2025.115007","url":null,"abstract":"<div><div>Within the framework of the EUROfusion Consortium, the Characterization of armour, heat sinks materials and joints sub-project of the Work Package Material (WP-MAT) has been dedicated to the development of different tungsten (W) monoblock mock-ups equipped with advanced materials for divertor target applications in the EU-DEMO fusion reactor. Assessing the status of the relevant joining interfaces of these mock-ups, not only after fabrication but throughout the whole component lifetime, plays a key role in the qualification process. At the ENEA Special Technologies Laboratory (TES), a number of facilities have been built to perform non-destructive inspections of plasma-facing components for fusion applications by ultrasonic testing (UT). The present work reports on the results of the UT inspections assessing the structural integrity of the relevant joining interfaces of three small-scale mock-ups provided with advanced W armour materials, specifically W-matrix with W₂C inclusions consolidated by Spark Plasma Sintering (SPS), K-doped rolled W and K-doped laminated W. The UT examinations are carried out after fabrication and after the high heat flux tests (HHFT) at the neutral beam facility GLADIS. All results confirm the high-quality joining achieved by HIP and HRP. During the HHF tests of mock-ups, after a few hundred HHFT cycles defects are detected at the joining interfaces, due to debonding, delamination and W material cracks mainly affecting the loaded zone. The ultrasonic pulse-echo technique provides not only the size and position of the defects in the plane orthogonal to the ultrasonic beam, but also their depth in the material. During the analysis, the probe is inserted inside the pipe and the mock-up is examined in a cylindrical configuration. The coupling medium (demineralized water) is poured only inside the pipe. The main inspection parameters and the piezoelectric probes are chosen to obtain the maximum resolution in accordance with the thickness and joining interfaces to be analyzed.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"215 ","pages":"Article 115007"},"PeriodicalIF":1.9,"publicationDate":"2025-03-30","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143734825","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"OA","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"A magnetohydrodynamic Method of Characteristics for the study of pressure transients in liquid metal piping systems","authors":"Lorenzo Melchiorri,&nbsp;Simone Siriano,&nbsp;Alessandro Tassone","doi":"10.1016/j.fusengdes.2025.114983","DOIUrl":"10.1016/j.fusengdes.2025.114983","url":null,"abstract":"<div><div>The Liquid Metal Breeding Blanket (LM-BB) represents a promising advancement in magnetic confinement fusion reactor technology. The lead-lithium eutectic alloy (PbLi) is employed both as a tritium breeder and, in certain designs, as the primary coolant. For the EU-DEMO reactor, alternative configurations such as the Helium-Cooled Lead Lithium and Water-Cooled Lead Lithium (WCLL) are considered. The blanket is required to endure high-energy neutron irradiation, significant thermal loads, and steep pressure gradients, which heighten the risk of coolant channel failures, known as In-box Loss of Coolant Accidents (In-box LOCA). These incidents involve the rapid release of high-pressure fluid into the PbLi channels, creating complex two-phase flow and substantial pressure shocks. LOCA scenarios are inherently three-dimensional and are significantly influenced by the fluid compressibility. The rapid pressurization of the liquid metal underscores the necessity for detailed knowledge of fluid thermodynamic states to accurately model shock transients. Additionally, magnetohydrodynamic (MHD) phenomena, arising from the interaction between the electrically conductive fluid and the strong magnetic field, need to be considered. The full impact of MHD effects on shock pressurization remains largely unexplored both experimentally and numerically.</div><div>This research aims to provide an in-depth assessment of MHD effects on simplified single-phase pressure transients. Liquid metal hammers are analysed using the method of characteristics, which has been modified to incorporate the electromagnetic force term, dependent on magnetic field intensity and the electrical conductivity of the fluid and pipe walls. The methodology is validated against hydrodynamic experimental data and compared with limited numerical results available in the literature. A parametric analysis has been conducted to simulate pressure transients under fusion-relevant conditions for the WCLL test blanket module. Although not fully representative of safety–critical in-box LOCA scenarios, these analyses provide valuable preliminary insights into MHD effects on pressure transients. Observations indicate that within a magnetic field range of <span><math><mrow><mn>1</mn><mo>≤</mo><mi>B</mi><mo>≤</mo><mn>4</mn></mrow></math></span> T, the magnetic field can significantly dampen pressure waves, reducing transient times by three orders of magnitude. Similar conclusions are drawn when varying the wall conductance ratio of the structures from <span><math><mrow><mn>0</mn><mo>≤</mo><mi>c</mi><mo>&lt;</mo><mn>20</mn></mrow></math></span>.</div><div>The method described in this study omits several underlying phenomena known to affect accidental scenarios. Nonetheless, the results presented offer the most advanced guidelines necessary for the development of more sophisticated tools.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"215 ","pages":"Article 114983"},"PeriodicalIF":1.9,"publicationDate":"2025-03-30","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143734826","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"OA","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Design and manufacture of the MITICA cryopump","authors":"J. Buckerfield ,&nbsp;R. Pearce ,&nbsp;A. Cobalt ,&nbsp;F. Chitu ,&nbsp;M. Dremel ,&nbsp;J.D. Dupuy ,&nbsp;L. Mora ,&nbsp;A. Rousseau ,&nbsp;J. Benet ,&nbsp;G. Kouzmenko ,&nbsp;S. Manfrin ,&nbsp;A. Rome ,&nbsp;A.S. Guichou","doi":"10.1016/j.fusengdes.2025.114991","DOIUrl":"10.1016/j.fusengdes.2025.114991","url":null,"abstract":"<div><div>A custom designed, open structure cryopump provides the required vacuum conditions for the MITICA experiment (Megavolt ITER Injector and Concept Advancement), a full-scale mockup of the ITER Heating Neutral Beam Injector located at the ITER Neutral Beam Test Facility (NBTF) in Padova, Italy. Upon connection to the cryoplant it will become the largest operating Neutral Beam cryopump in the world, designed to achieve the required pumping speeds of 4500 m³/s for H₂ and 3600 m³/s for D₂ operation. This paper presents the as-built design and manufacture of the pump, outlining the detailed design of each sub-system and the manufacture, assembly and testing processes that led to its successful delivery.</div><div>The MITICA cryopump consists of a pair of panels, each 8 m long, 3 m tall and weighing approximately 4 tons. These are comprised of a stainless steel frame supporting 32 pumping sections that are connected together to form two continuous cryogenic circuits, one operated at 4.5 K for cryosorption, the other at 80 K for thermal radiation shielding. Novel manufacturing techniques were developed for the individual cryopanels, including bespoke hydraulic expansion and charcoal coating processes to achieve the required cryopumping performance.</div><div>The delivery of the MITICA cryopump is a significant milestone in the development of the ITER Neutral Beam cryopumps, with the lessons learned during manufacture already being implemented in the ongoing design work. This paper therefore not only looks forward to the installation and commissioning of the delivered pump with the MITICA cryoplant but also beyond, towards the future procurement of similar cryopumps that will be installed on the ITER Heating and Diagnostic Neutral Beam Injectors.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"215 ","pages":"Article 114991"},"PeriodicalIF":1.9,"publicationDate":"2025-03-30","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143734824","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"The conceptual design of transporter & secondary containment structure of maintenance cask for CFETR and EU-DEMO blanket","authors":"Haoyin Wang ,&nbsp;Hongbin Huang ,&nbsp;Hongtao Pan ,&nbsp;Günter Janeschitz ,&nbsp;Christian Bachmann ,&nbsp;Yiming Wang ,&nbsp;Thomas Steinbacher ,&nbsp;Ping Su ,&nbsp;Yong Cheng ,&nbsp;Youmin Hu ,&nbsp;Bo Wu","doi":"10.1016/j.fusengdes.2025.114977","DOIUrl":"10.1016/j.fusengdes.2025.114977","url":null,"abstract":"<div><div>The currently devised maintenance scheme of tritium breeding blankets of both CFETR and EU-DEMO foresees that, after removal from the vacuum vessel of each banana-shaped segment, it is confined in a maintenance cask to prevent tritium and dust contamination of the reactor hall and the maintenance corridor, and then transferred to the hot cell. Because rubber seals of cask doors cannot retain dust and, in particular, tritium with 100 % efficiency, a double containment approach with a concept minimizing the volume where contamination spills can occur during docking and undocking processes has been considered, i.e. contamination spills shall be contained in as small a space as possible. In ITER, there is a cask and the port cells as contamination barrier, i.e. two barriers connected to detritiation and cleanable walls. In CFETR and EU-DEMO, the secondary containment structure, required to implement similar functionalities as ITER port cells with doors to open and close, has been designed with 16 cask containment cells and 16 turntables with revolving sealed doors arranged in an external ring corridor within which the cask operates. The maintenance cask is lifted, moved and deployed to its docking ports by the cask transporter, which runs on rails both on the floor and the top such as to provide stability against toppling in case of a seismic event. In addition, the cask transporter should have powerful crane to be able to handle casks up to 300 tones, and large wheels to cope with the small gaps in the rails at the turntables. This paper intends to present the conceptual design of both cask transporter and secondary containment structure developed by a collaborative joint CN and EU team for both CFETR and EU-DEMO that will face similar safety-related regulatory requirements.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"215 ","pages":"Article 114977"},"PeriodicalIF":1.9,"publicationDate":"2025-03-29","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143725589","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Robustness of the E×B MDC prototype design for gyrotrons","authors":"Benjamin Ell,&nbsp;Lukas Feuerstein,&nbsp;Gerd Gantenbein,&nbsp;Stefan Illy,&nbsp;Tobias Ruess,&nbsp;Tomasz Rzesnicki,&nbsp;Sebastian Stanculovic,&nbsp;Manfred Thumm,&nbsp;Jörg Weggen,&nbsp;Chuanren Wu,&nbsp;John Jelonnek","doi":"10.1016/j.fusengdes.2025.114979","DOIUrl":"10.1016/j.fusengdes.2025.114979","url":null,"abstract":"<div><div>The Short-Pulse (SP) <span><math><mi>E</mi></math></span> <span><math><mo>×</mo></math></span> <span><math><mi>B</mi></math></span> Multistage Depressed Collector (MDC) prototype developed and built at Karlsruhe Institute of Technology (KIT) is theoretically investigated for its robustness to manufacturing tolerances and non-optimized gyrotron operating scenarios. The tolerance analysis is done based on a parametric definition of the collector electrodes for the optimized gyrotron operation with the KIT 2<!--> <!-->MW 170<!--> <!-->GHz coaxial-cavity gyrotron. The six most dominant geometrical parameters are considered. The prototype design is then adapted to 5 different gyrotron configurations and operation modes, which include the Wendelstein 7-X (W7-X) Upgrade SP gyrotron for 140<!--> <!-->GHz and 105<!--> <!-->GHz operation, as well as the coaxial-cavity gyrotron in multi-frequency operation at 136<!--> <!-->GHz and 204<!--> <!-->GHz (in addition to the nominal operation at 170<!--> <!-->GHz) and operation at the second harmonic at 170<!--> <!-->GHz. The necessary modifications to the mechanical adaption, the magnetic configuration and electrode potentials are highlighted for promising MDC operation in all cases.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"215 ","pages":"Article 114979"},"PeriodicalIF":1.9,"publicationDate":"2025-03-29","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143734823","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Application of virtual fitting in the manufacturing of the ITER European vacuum vessel sectors","authors":"Alessandro Lo Bue ,&nbsp;Edoardo Pompa ,&nbsp;Miguel Gonzalez Fernandez ,&nbsp;Francesca Giovanna Lanzotti ,&nbsp;Gabriele D'Amico ,&nbsp;Boris Bellesia","doi":"10.1016/j.fusengdes.2025.114998","DOIUrl":"10.1016/j.fusengdes.2025.114998","url":null,"abstract":"<div><div>The Vacuum Vessel is one of the main systems of the ITER tokamak. The welded steel, torus-shaped vessel, houses the plasma and acts as a first safety containment barrier. It provides support for In-Vessel components and removes the heat generated during operation by mean of cooling water circulating through its walls. To ensure the functionality of the system, strict geometrical requirements have been defined on several features. The large scale of the component and the complexity of the manufacturing raised the need to develop metrology strategies that improve the awareness of the decision-making processes and minimize the risk of non-compliance of the final product. Virtual Fitting is a technique that enables to find the optimal way of assembling parts together considering their real shapes. By defining requirements to include in the analysis and their priority, an optimum can be found by least square minimization of the as-built data deviation from the nominal reference. The method has been deployed in one of the most critical stages of the Vacuum Vessel production, the assembly of the four poloidal segments composing the final sector. The analysis provided the actors involved several alignment scenarios, from which corrective actions have been derived, in terms of time, cost and quality. Firstly, this paper presents the principles of the Virtual Fitting technique, then the second part focuses on the application of the Vacuum Vessel European Sector #5.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"215 ","pages":"Article 114998"},"PeriodicalIF":1.9,"publicationDate":"2025-03-28","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143716182","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"ITER progresses into new baseline","authors":"Pietro Barabaschi,&nbsp;Arnaud Fossen,&nbsp;Alberto Loarte,&nbsp;Alain Becoulet,&nbsp;Laban Coblentz,&nbsp;ITER Contributors","doi":"10.1016/j.fusengdes.2025.114990","DOIUrl":"10.1016/j.fusengdes.2025.114990","url":null,"abstract":"<div><div>The ITER Project has gone through a period of transition, with progress continuing despite challenges, and is moving forward on the basis of a new project baseline. Repairs to key components—the vacuum vessel sectors and thermal shields—are progressing according to schedule. Progress has continued on construction, manufacturing, assembly, and system commissioning. Following more than a year of review, a new baseline proposal was submitted to the ITER Council in June 2024, and is now serving as the working reference schedule.</div><div>The discovery and analysis of geometric non-conformities in the bevel joints of several vacuum vessel sectors, as well as chloride corrosion cracking in the cooling pipes of the thermal shields, led to a slowdown in ITER tokamak assembly while repairs are carried out. In parallel, an assessment of root causes, including a thorough self-examination of project quality culture, was followed by a reorganization to prepare for the challenges ahead. Extensive discussions were held with the French nuclear safety authority (ASNR) to restore trust and evaluate strategies to enhance the safety demonstration accompanying ITER's licensing. Meanwhile, the power supply systems, the cryogenics plant, and several cooling water systems have completed installation and are largely commissioned. All poloidal and toroidal field coils have been delivered, as well as most of the central solenoid modules and many other major components.</div><div>The largest task over the past year has been to channel all these elements into a realistic, feasible updated project baseline. In the resulting proposal, the previously envisioned stages of assembly and operation are largely consolidated. Technical and operational risks are mitigated by replacing beryllium with tungsten for the first wall panels and incorporating the divertor, shield blocks, a sacrificial first wall, and other risk-reducing components into a more complete machine before initial operations, as well as fully testing some toroidal and poloidal field coils before their installation. The start of research operations (SRO) in 2034 will inaugurate a 27-month period of substantial experimentation with hydrogen and deuterium plasmas, to culminate in operating the tokamak with pulses of several tens of seconds at full magnetic energy and plasma current (15MA) in 2036. The SRO phase will largely demonstrate the integration of systems needed for industrial-scale fusion operations. The start of deuterium-tritium operations phase will be delayed by 4 years from the previous baseline, from 2035 to 2039.</div><div>Highlights from these areas (manufacturing, tokamak assembly, system commissioning), will be presented along with the updated baseline proposal and other aspects of project status.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"215 ","pages":"Article 114990"},"PeriodicalIF":1.9,"publicationDate":"2025-03-28","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143725590","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Structural analysis of DTT divertor PFU under electromagnetic and thermal loading","authors":"Patrik Tarfila ,&nbsp;Oriol Costa Garrido ,&nbsp;Boštjan Končar ,&nbsp;Francesco Giorgetti ,&nbsp;Selanna Roccella","doi":"10.1016/j.fusengdes.2025.114999","DOIUrl":"10.1016/j.fusengdes.2025.114999","url":null,"abstract":"<div><div>The plasma-facing units (PFU) of the Divertor Tokamak Test facility (DTT) are expected to withstand high heat fluxes as well as electromagnetic (EM) loads during normal and off-normal operations. As the design of the DTT divertor PFU moves forward, specific analyses of the component's real geometry under the expected loads are needed to verify its suitability. This paper presents structural analyses of the DTT divertor PFU under combined loads including EM, thermal and pressure loadings. A single PFU is analyzed under EM loads during the slow plasma Vertical Displacement Event (VDE), together with heat fluxes during single-null (SN) detached plasma configuration. A strategy for using a discrete vector field of EM loads as input data in the ABAQUS environment is described. Due to the rather large displacements obtained with EM loads and the original set of PFU supports, two additional supports are proposed and included in the analyses. The results with the additional supports show an improvement of the stresses and displacements. The analysis with combined loads reveals that the stresses in monoblocks, copper interlayer and weld regions are mainly driven by heat flux and pressure loads, while the EM loads are the source of higher (local) stresses in the CuCrZr pipe and supports.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"215 ","pages":"Article 114999"},"PeriodicalIF":1.9,"publicationDate":"2025-03-28","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143716294","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"OA","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Development of a laser sweeping system for precise positioning of Thomson measurement in KSTAR","authors":"Jong-ha Lee ,&nbsp;Ha Jin Kim ,&nbsp;Gheunhyung Park","doi":"10.1016/j.fusengdes.2025.114993","DOIUrl":"10.1016/j.fusengdes.2025.114993","url":null,"abstract":"<div><div>Thomson diagnostics are essential for diagnosing electron density (ne) and electron temperature (Te) profiles in most plasma machines. However, precise alignment of the laser path with the collection optics focus is crucial to obtain the Thomson signal. Misalignment can lead to inaccuracies in measuring the signal and may introduce errors in plasma parameters. Therefore, precise control of the laser beam position inside the vacuum vessel is necessary. Many researchers involved in Thomson diagnostics carefully adjust the laser beam path and position to ensure accurate measurements.</div><div>The KSTAR Thomson system traditionally aligned the laser beam with the collection optics focus manually using LED backlighting. However, this alignment process is challenging and time-consuming due to radiation in the vacuum vessel. To address this issue, a laser sweeping system was recently installed to enhance alignment accuracy and minimize working time in the vacuum vessel. This system includes a step motor installed on the last laser guiding mirror, enabling remote adjustment of the laser beam position from the diagnostics room.</div><div>The Rayleigh signal was measured while sweeping the laser in both the vertical and horizontal directions under a 40 mbar nitrogen gas condition. The obtained signal was analyzed using a three-pulse fitting method. The vertical and horizontal sweeping intervals were set to 20 steps. As a result, for vertical sweeping, both the core and edge regions showed peak signals around the +60 step region. For horizontal sweeping, the core region exhibited a peak at +60 steps, whereas for the edge region, the signal increased as the position moved below -60 steps. This indicates that the horizontal focal position of the edge lens is aligned more inward than initially expected. This study demonstrates that precise alignment can be achieved by horizontally and vertically sweeping the mirror from the laser injection side. And the purpose of laser sweeping in this study is to verify and correct slight misalignments that may occur after the baking process.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"215 ","pages":"Article 114993"},"PeriodicalIF":1.9,"publicationDate":"2025-03-28","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143725588","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"OA","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Preliminary thermo-structural analyses of the new DTT bolometric camera","authors":"V. D'Agostino ,&nbsp;A. Belpane ,&nbsp;S. Palomba ,&nbsp;E. Peluso ,&nbsp;I. Wyss ,&nbsp;B. Spolaore ,&nbsp;I. Regoli ,&nbsp;L. Gabellieri ,&nbsp;A. Murari ,&nbsp;G. Apruzzese ,&nbsp;M. Gelfusa","doi":"10.1016/j.fusengdes.2025.114981","DOIUrl":"10.1016/j.fusengdes.2025.114981","url":null,"abstract":"<div><div>The Divertor Tokamak Test (DTT) facility is currently under construction at the ENEA Frascati Research Centre, Italy, with the aim of studying divertor configurations in support to the design and construction of ITER and DEMO. In the context of monitoring the radiated power, it is crucial to measure the entire spectrum of electromagnetic radiation emitted by the plasma. This need is particularly relevant in the divertor region, especially in the specific case of DTT scientific programme. This work presents the preliminary thermal and structural analyses of the bolometric camera foreseen to be implemented in the tomographic diagnostic system, aimed at monitoring the emissivity of the plasma total radiated power. First, the design has been optimised, minimising the space occupied in the port by the arrays of metal foil bolometers, still ensuring the best possible coverage of the lines of sight (LoS) in the vessel and at the same time avoiding interferences with other devices. Then, the devised layout has been validated with thermo-mechanical simulations, focusing on the design of the active cooling system of the bolometers themselves, necessary to manage the thermal conditions of the wall, particularly baking, and the intense loads during machine operations. The results confirmed that, under the specific conditions of mirror polishing of components, the currently proposed layout is promising, but needs further optimisation.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"215 ","pages":"Article 114981"},"PeriodicalIF":1.9,"publicationDate":"2025-03-28","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143716295","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"OA","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}