Fusion Engineering and Design最新文献

{"title":"Tritium release scenarios in the IRPR system of DEMO: Safety assessment and mitigation strategies","authors":"Samuele Meschini,&nbsp;Raffaella Testoni","doi":"10.1016/j.fusengdes.2025.115477","DOIUrl":"10.1016/j.fusengdes.2025.115477","url":null,"abstract":"<div><div>This study investigates potential tritium release scenarios in the Isotope Rebalancing and Protium Removal (IRPR) system of DEMO fuel cycle, focusing on failures in the Temperature Swing Absorption (TSA) unit, including its feed tank. Two accident cases are considered, based on the postulated initiating events identified by the FFMEA: (1) a guillotine break in the pipeline supplying the IRPR system and (2) a pipe rupture in the TSA unit. MELCOR 1.8.6 for fusion is used to simulate the dynamics of the gases (hydrogen, air, inert gases), the resulting pressurization of the enclosure volumes, and the accumulation of hydrogen isotopes. A parametric study evaluates the impact of design choices like feed tank configuration and glovebox volume, informing the design of the system to enhance safety. The analysis includes cases where safety systems such as detritiation or isolation fail to operate correctly. The findings support ongoing safety assessments for DEMO and inform strategies to improve safety in fusion power plants.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"222 ","pages":"Article 115477"},"PeriodicalIF":2.0,"publicationDate":"2025-10-11","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145267001","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":"On the evaluation of the DEMO WCLL Breeding Blanket sector thermal-hydraulic performances at a system level","authors":"Francesco Colliva ,&nbsp;Fabio Giannetti ,&nbsp;Antonio Trotta ,&nbsp;Alessandro Del Nevo ,&nbsp;Gianfranco Caruso ,&nbsp;Cristiano Ciurluini","doi":"10.1016/j.fusengdes.2025.115483","DOIUrl":"10.1016/j.fusengdes.2025.115483","url":null,"abstract":"<div><div>In the last years, an intense research activity has been carried out within the framework of the EUROfusion Consortium to optimize the layout of the EU-DEMO Breeding Blanket (BB). Two main concepts are currently under investigation: the Helium-Cooled Pebble Bed and the Water-Cooled Lead-Lithium, that is the option object of this work. This layout relies on pressurized water as coolant, liquid metal (i.e., lead-lithium) as breeder, neutron multiplier and tritium carrier, and reduced-activation ferritic/martensitic steel as structural material. In addition, a thin tungsten armor is used to protect the First Wall component. The overall BB is constituted by sixteen toroidal sectors. Each sector is composed by inboard (two) and outboard (three) segments, considering their radial position with respect to the plasma chamber. At its time, the segments consist in a stack of vertically-piled breeding cells, that are the system elementary units. Their layout differs according to the poloidal position and the segment they belong.</div><div>To obtain an affordable BB design, one of the key issues is assessing its thermal-hydraulic performances during operational and accidental conditions. For this, an analysis of the component transient behavior is needed to improve and refine the project. To achieve this goal, during the last year, the Nuclear Engineering Research Group of Sapienza University of Rome, in collaboration with ENEA, has developed a detailed model of the DEMO WCLL BB sector, including both the inboard and outboard segments. The rationale has been dividing the overall stack of cells belonging to each segment in poloidal sections. The number of these sections has been the object of a sensitivity study. The preliminary objective of this work is to have a dedicated BB sector model to evaluate its thermal-hydraulic performances at a system level during the DEMO normal operations, considering the pulsed plasma regime and the spatial distributions of the various loads insisting on this component. In addition, the developed input deck allowed to have insights into the BB behavior during accidental conditions, demonstrating the capability of the current design to effectively withstand such scenarios without exceeding safety margins. The level of detail adopted to prepare the BB model enabled to preliminary exclude the occurrence of local damaging phenomena, such as thermal crisis.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"222 ","pages":"Article 115483"},"PeriodicalIF":2.0,"publicationDate":"2025-10-11","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145267004","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":"Activation analysis of a compact Tokamak using Deuterium–Helium3 fuel","authors":"A. Morandi,&nbsp;D. Pettinari,&nbsp;M. Zucchetti","doi":"10.1016/j.fusengdes.2025.115491","DOIUrl":"10.1016/j.fusengdes.2025.115491","url":null,"abstract":"<div><div>Recent advancements in high-temperature superconducting (HTS) magnets have enabled tokamaks to reduce dimensions and operate with higher plasma parameters. This opens to the possibility of using advanced fuel mixtures such as Deuterium–<span><math><msup><mrow></mrow><mrow><mn>3</mn></mrow></msup></math></span>Helium (DHe3). Compared to traditional fuels, DHe3 offers the potential to reduce neutron-induced activation and minimize the presence of tritium in the fuel cycle.</div><div>In a fusion reactor that uses a 50% Deuterium–50% <span><math><msup><mrow></mrow><mrow><mn>3</mn></mrow></msup></math></span>Helium mixture, neutrons are produced solely in the Deuterium–Deuterium (DD) and Deuterium–Tritium (DT) side reactions, while Tritium can be produced during DD reactions and is therefore absent at the startup of the machine.</div><div>This study proposes a comprehensive neutronic and activation analysis of a compact, high-field tokamak employing DHe3 fuel. Using OpenMC, an open-source Monte Carlo code, the feasibility and performance of this fuel mixture within the confines of a compact fusion reactor will be investigated. The activation analysis will be limited to the First Wall, Blanket and inboard Toroidal Field coils, with some simplifications in the tokamak layout.</div><div>By analyzing neutron interactions and activation processes, as well as design modifications, we seek to assess the potential benefits and challenges associated with implementing DHe3 as fuel.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"222 ","pages":"Article 115491"},"PeriodicalIF":2.0,"publicationDate":"2025-10-11","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145267006","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":"Modeling-driven requirements for Error Field Control Coil application to initial JT-60SA plasmas","authors":"L. Pigatto ,&nbsp;G. Frello ,&nbsp;L. Garzotti ,&nbsp;Y.Q. Liu ,&nbsp;L. Novello ,&nbsp;M. Takechi ,&nbsp;E. Tomasina ,&nbsp;T. Bolzonella","doi":"10.1016/j.fusengdes.2025.115489","DOIUrl":"10.1016/j.fusengdes.2025.115489","url":null,"abstract":"<div><div>JT-60SA is a large superconducting tokamak built in Naka, Japan. After the successful achievement of its first MA-class plasma, the installation of several additional sub-systems, including a set of non-axisymmetric Error Field Correction Coils (EFCC), is ongoing. Optimization of future JT-60SA plasma scenarios will critically depend on the correct use of EFCC, including careful fulfillment of system specifications. In addition to that, preparation and risk mitigation of early ITER operations will greatly benefit from the experience gained by early EFCC application to JT-60SA experiments, in particular to optimize error field detection and control strategies. In this work, EFCC application in JT-60SA Initial Research Phase I perspective scenarios is modeled including plasma response. Impact of (Resonant) Magnetic Perturbations on the different plasma scenarios is assessed for both core and pedestal regions by the linear resistive MHD code MARS-F. The dominant core response to EFs is discussed case by case and compared to mode locking thresholds from literature. Typical current/voltage amplitudes and wave-forms are then compared to EFCC specifications in order to assess a safe operational space.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"222 ","pages":"Article 115489"},"PeriodicalIF":2.0,"publicationDate":"2025-10-11","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145267008","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":"Implementation of tritium transport in a gas-liquid contactor CFD simulation of tritium extraction from lead-lithium in ANSYS fluent","authors":"Anthony G. Bowers Jr. ,&nbsp;Subash L. Sharma ,&nbsp;Thomas F. Fuerst","doi":"10.1016/j.fusengdes.2025.115479","DOIUrl":"10.1016/j.fusengdes.2025.115479","url":null,"abstract":"<div><div>Modifications to the Computational Fluid Dynamic (CFD) software ANSYS Fluent were done to quantify and characterize tritium transport in gas-liquid contactors (GLCs). A double-slit, Ergun-like equation was employed for the porous media model, with Ergun coefficients validated with Sulzer’s Sulcol software. Tritium transport from PbLi within the GLC was verified against analytical models. The geometry of the CFD model was based on the MELODIE GLC experiment. The hydrodynamic CFD pressure drop results align well with Sulcol estimations and fall between the predictions of the analytical Delft-Olujić and Billet and Schultes models. In terms of mass transfer efficiency, traditional mass transfer models showed a significant deviation from experimental results when using varying values of H solubility in PbLi. A saturation phenomenon occurred when utilizing high solubility values for hydrogen in PbLi. A modified film theory mass transfer coefficient incorporating either the Delft-Olujić or Billet and Schultes wettability model yielded CFD-predicted extraction efficiencies that closely matched experimental measurements.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"222 ","pages":"Article 115479"},"PeriodicalIF":2.0,"publicationDate":"2025-10-10","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145267611","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 RAPTOR based control scheme at AUG and benchmarking its results with real time inputs against post-processed data","authors":"M. Reisner ,&nbsp;C. Contré ,&nbsp;F. Felici ,&nbsp;R. Fischer ,&nbsp;L. Giannone ,&nbsp;O. Kudláček ,&nbsp;F. Pastore ,&nbsp;C. Rapson ,&nbsp;O. Sauter ,&nbsp;W. Treutterer ,&nbsp;S. Van Mulders ,&nbsp;ASDEX Upgrade Team ,&nbsp;EUROfusion WPTE Team","doi":"10.1016/j.fusengdes.2025.115474","DOIUrl":"10.1016/j.fusengdes.2025.115474","url":null,"abstract":"<div><div>In the operation of fusion devices, rapid feedback control of plasma parameters is important due to the fast timescales of relevant physics processes. These parameters are often measured indirectly or through noisy diagnostics with limited resolution. To address this, we require models that can estimate these parameters in real time by integrating simple physics-based models with available measurements. This paper presents the integration of the RAPTOR (RApid Plasma TranspOrt simulatOR) code within the discharge control system (DCS) of ASDEX Upgrade (AUG). RAPTOR, combined with an extended Kalman filter (EKF), utilizes real-time electron cyclotron emission (ECE) measurements to enhance its accuracy. We provide an overview of RAPTOR, its integration with an EKF, and the impact of real-time data on its results. Our findings indicate that while the simple transport model we use in RAPTOR often matches the experimental electron temperatures only poorly, the EKF significantly enhances its accuracy, aligning well with experimental profiles. This integration allows effective feedback control of heat fluxes and temperature profiles in fusion devices. Additionally, through standalone simulations of RAPTOR without EKF, we assess to what extent RAPTOR results using real-time data could be improved.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"222 ","pages":"Article 115474"},"PeriodicalIF":2.0,"publicationDate":"2025-10-08","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145267009","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":"Neutron spectrometer based on a gas electron multiplier (GEM) detector for fusion reactors","authors":"M. Scholz ,&nbsp;U. Wiącek ,&nbsp;K. Drozdowicz ,&nbsp;A. Jardin ,&nbsp;U. Woźnicka ,&nbsp;K. Król ,&nbsp;A Kurowski ,&nbsp;A. Kulińska ,&nbsp;W. Dąbrowski ,&nbsp;B. Łach ,&nbsp;D. Mazon","doi":"10.1016/j.fusengdes.2025.115480","DOIUrl":"10.1016/j.fusengdes.2025.115480","url":null,"abstract":"<div><div>Neutron spectrometry is an important diagnostic method that will be used to determine the deuterium to tritium density ratio and the ion temperature in the core plasma of fusion reactors. In the case of ITER, the following spectrometric techniques are foreseen: Thin-foil Proton Recoil (TPR), diamond and time-of-flight detectors. The TPR spectrometer design for ITER includes a system of silicon detectors for the detection of protons resulting from the conversion of neutrons in a polyethylene converter. This arrangement has its drawbacks, one of which is limited resistance of silicon to radiation damage. Therefore, we propose using a Gas Electron Multiplier (GEM) type gas detector, which should have better resistance than silicon-based detectors. The concept and operating principle of a TPR neutron spectrometer based on GEM technology, so-called NS-GEM and intended for future fusion plasma spectrometry applications, is presented. The geometry of the detector and its feasibility study based on numerical calculations are discussed. In particular, the first results of experiments with a NS-GEM demonstrator on the IGN-14 neutron generator are shown.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"222 ","pages":"Article 115480"},"PeriodicalIF":2.0,"publicationDate":"2025-10-08","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145267003","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":"Design and analysis of a SF6 gas insulating HV-bushing for CRAFT NNBI","authors":"Yuchen Qu ,&nbsp;Zhimin Liu ,&nbsp;Caichao Jiang ,&nbsp;Jianglong Wei ,&nbsp;Bo Liu ,&nbsp;Yuanlai Xie ,&nbsp;Xu Wang","doi":"10.1016/j.fusengdes.2025.115468","DOIUrl":"10.1016/j.fusengdes.2025.115468","url":null,"abstract":"<div><div>The full-scale beam source of CRAFT NNBI is planned to adopt a vacuum-insulated ion source scheme to generate a 400<!--> <!-->keV negative hydrogen ion beam through two stages of -200<!--> <!-->kVacceleration voltage. A preliminary design has been developed for two stages of -400<!--> <!-->kVhigh-voltage bushings, which are intended for insulating and sealing connections between the SF6-insulated transmission line and the vacuum chamber. Vacuum-side insulation design has been conducted to analyze and improve the electric field strength of the vacuum-side cathode surface, anode surface, insulator surface, and triple point, meeting the standard requirements specified by the Japan Atomic Energy Agency for high-voltage bushings designed for ITER. The design includes the cooling water flow channels for the -200<!--> <!-->kVbushing section, considering the requirements for cooling water flow rate based on the thermal load of the accelerating electrode (AG) and temperature constraints, analyzing pressure drop in the channels and uniformity of flow distribution. Mechanical strength analysis of the bushing structure has been performed, considering the stress and deformation under 0.6<!--> <!-->MPa SF6 gas in the transmission line, 1<!--> <!-->MPa air between the insulating ceramic ring and fiber-reinforced polymer (FRP) ring and gravity loads.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"222 ","pages":"Article 115468"},"PeriodicalIF":2.0,"publicationDate":"2025-10-08","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145267610","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":"Design considerations for a TE28,12-mode 2-MW, 140-GHz gyrotron for the ECRH system at W7-X","authors":"Emmanouil Deliprimis ,&nbsp;Zisis C. Ioannidis ,&nbsp;Konstantinos A. Avramidis ,&nbsp;Tobias Ruess ,&nbsp;Stefan Illy ,&nbsp;John Jelonnek ,&nbsp;Manfred Thumm ,&nbsp;Ioannis G. Tigelis","doi":"10.1016/j.fusengdes.2025.115465","DOIUrl":"10.1016/j.fusengdes.2025.115465","url":null,"abstract":"<div><div>Following the recent upgrade of the Electron Cyclotron Resonance Heating (ECRH) system at the stellarator Wendelstein 7-X (W7-X) with a 1.5-MW, 140-GHz gyrotron (TH1507U), efforts are now focused on further advancing gyrotron technology by developing a 2-MW, 140-GHz Continuous Wave (CW) prototype. This paper proposes two RF and electron beam optics designs of a conventional-cavity 2-MW, 140-GHz gyrotron, operating with the TE_28,12 mode. Each design corresponds to different operating conditions, namely Low-Voltage High-Current (LVHC) and High-Voltage Low-Current (HVLC). The primary objective of the work is to leverage the existing infrastructure at W7-X while minimizing design modifications to the existing 1.5-MW gyrotron, therefore ensuring cost efficiency and increasing the possibility for a rapid implementation of the proposed designs. Given the significant (and challenging) space-charge depression associated with the TE_28,12 mode, several gyrotron startup scenarios are investigated thoroughly using the existing TH1507U diode Magnetron Injection Gun (MIG) as well as a new triode-type MIG design, which is based on the diode design. The findings of this study offer key insights into the design and operational challenges of future 2 MW-class gyrotrons operating at 140 GHz and beyond.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"222 ","pages":"Article 115465"},"PeriodicalIF":2.0,"publicationDate":"2025-10-07","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145267002","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":"Bridging open and proprietary control frameworks for fusion facilities: EPICS – Industrial SCADA integration in the CODAC system of IFMIF-DONES","authors":"Javier Cruz-Miranda ,&nbsp;Miguel Damas ,&nbsp;Eusebio N. Al-Soliman ,&nbsp;Javier Díaz ,&nbsp;Mauro Cappelli","doi":"10.1016/j.fusengdes.2025.115481","DOIUrl":"10.1016/j.fusengdes.2025.115481","url":null,"abstract":"<div><div>This paper presents an architectural approach for the Control, Data Access, and Communication (CODAC) system within the framework of the IFMIF-DONES (International Fusion Materials Irradiation Facility DEMO Oriented Neutron Source) control systems. This study focuses on the integration of the most widely adopted SCADA frameworks with state-of-the-art industrial automation standards in particle accelerator environments. The interoperability between EPICS and commercial control frameworks based on OPC UA is particularly emphasized, enabling a hybrid control ecosystem that leverages the strengths of both domains.The architecture enhances flexibility, scalability, and standardization across all systems and subsystems involved in supervision and control tasks. By facilitating seamless communication and modularity, it supports the use of both open-source and proprietary technologies while ensuring long-term maintainability and adaptability. The paper includes a review of comparable systems at other large-scale facilities, an evaluation of integration strategies, and a detailed discussion of the resulting CODAC architecture, highlighting its impact on the overall efficiency and interoperability of the IFMIF-DONES Central Instrumentation and Control Systems (CICS). This study aims to offer a complementary perspective on the control system architecture for IFMIF-DONES, exploring the potential integration of industrial SCADA frameworks alongside EPICS.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"222 ","pages":"Article 115481"},"PeriodicalIF":2.0,"publicationDate":"2025-10-07","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145267005","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}