Fusion Engineering and Design最新文献_第6页

Preliminary design of ITER PCS Provisioning System ITER pc供给系统初步设计

IF 2 3区工程技术

Fusion Engineering and Design Pub Date : 2025-07-31 DOI: 10.1016/j.fusengdes.2025.115348

Piotr Perek , Taehyun Tak , Woong-Ryol Lee , Anze Zagar , Dariusz Makowski , Domen Soklic , Peter Karlovsek

{"title":"Preliminary design of ITER PCS Provisioning System","authors":"Piotr Perek , Taehyun Tak , Woong-Ryol Lee , Anze Zagar , Dariusz Makowski , Domen Soklic , Peter Karlovsek","doi":"10.1016/j.fusengdes.2025.115348","DOIUrl":"10.1016/j.fusengdes.2025.115348","url":null,"abstract":"<div><div>The ITER Plasma Control System (PCS) will be a complex, distributed environment composed of several closely coupled subsystems responsible for real-time control of specific plasma parameters. All the required real-time functions will be implemented using a dedicated ITER Real-Time Framework (RTF) and deployed on many computational nodes. However, as with all the other ITER plant systems, PCS needs to be integrated and operated by the central supervisory systems responsible for machine configuration, pulse preparation and execution. On the other hand, the system engineers need to run the system in local operation mode (e.g. for development, testing, integration, etc.).</div><div>The PCS Provisioning System (PPS) is a conventional subsystem of PCS responsible for deploying, configuring and supervising the PCS real-time instances. It implements a system-level operational state machine supporting standalone operation mode and integrated synchronous operation managed by the central CODAC applications. It also ensures the interfacing with central configuration services and implements all the procedures required for processing and deploying the PCS configuration to real-time instances. PPS also serves as a gateway between PCS and other plant systems to share the PCS information with all the stakeholders. It also includes a PCS configuration database and implements other supplementary functions like integrating event logs from all real-time nodes, exception handling, and operator interface (OPI) required for PCS operators and engineers.</div><div>The paper presents the preliminary design of the PCS Provisioning System, including the requirements analysis, stakeholders and constraints, proposed architecture, components, interfaces and operating procedures defined for PCS operation and communication with external systems.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"220 ","pages":"Article 115348"},"PeriodicalIF":2.0,"publicationDate":"2025-07-31","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144739689","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}

引用次数: 0

Estimation of activated lithium and corrosion product contribution to the dose rate in IFMIF-DONES lithium loop cell IFMIF-DONES锂循环电池中活性锂和腐蚀产物对剂量率贡献的估计

IF 2 3区工程技术

Fusion Engineering and Design Pub Date : 2025-07-31 DOI: 10.1016/j.fusengdes.2025.115358

Andrius Tidikas, Gediminas Stankūnas, Benjaminas Togobickij

{"title":"Estimation of activated lithium and corrosion product contribution to the dose rate in IFMIF-DONES lithium loop cell","authors":"Andrius Tidikas, Gediminas Stankūnas, Benjaminas Togobickij","doi":"10.1016/j.fusengdes.2025.115358","DOIUrl":"10.1016/j.fusengdes.2025.115358","url":null,"abstract":"<div><div>To ensure the optimal design and maintenance of the IFMIF-DONES irradiation facility, it is imperative to conduct a thorough assessment of the lithium systems, given the presence of ionizing radiation sources. The flow of lithium within the target is impinged by the high-intensity continuous-wave (125 mA, 40 MeV) deuteron beam. The deuteron capture reaction in lithium leads to the production of the Beryllium-7 radioisotope and corresponding neutron emission. Beryllium-7 holds radiological importance due to its relevant half-life and subsequent decay gamma emission. Additionally, neutron emission, together with deuterons, results in the generation of various radioisotopes in the corrosion/erosion products of the structural materials, which are dispersed in the lithium flow.</div><div>In this study, we have used Be-7 and activated corrosion product estimates to assess the absorbed dose rates inside the lithium loop cell of IFMIF-DONES. High-efficiency Be-7 trapping in the lithium loop was considered with the assumption of a modest amount of Be-7 being dissolved homogeneously within the volume of lithium. For activated corrosion products, different quantities were used for the system components (heat exchanger, cold leg and cold trap). Gamma spectra and their evolution over one week were obtained using the FISPACT-2 code. Gamma photon transport calculations were performed with MCNP code. As a result, dose rate maps were created for the lithium rooms, photon leakage was assessed and hot zones were identified.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"220 ","pages":"Article 115358"},"PeriodicalIF":2.0,"publicationDate":"2025-07-31","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144749538","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}

引用次数: 0

An Extended Kalman Filter approach for tokamak plasma equilibrium reconstruction 托卡马克等离子体平衡重建的扩展卡尔曼滤波方法

IF 2 3区工程技术

Fusion Engineering and Design Pub Date : 2025-07-31 DOI: 10.1016/j.fusengdes.2025.115363

Luigi Emanuel di Grazia , Massimiliano Mattei , Alfredo Pironti

引用次数: 0

Optimisation of STEP poloidal field coils with superconducting coil constraints in STEP-Bluemira power plant design framework STEP- bluemira电厂设计框架中超导线圈约束的STEP极向场线圈优化

IF 2 3区工程技术

Fusion Engineering and Design Pub Date : 2025-07-30 DOI: 10.1016/j.fusengdes.2025.115357

Athoy Nilima , Matthew Bluteau , James Cook , Oliver Funk , Georgina Graham , Jonathan Matthews , Stuart I. Muldrew , Alexander J. Pearce , Dario Vaccaro

{"title":"Optimisation of STEP poloidal field coils with superconducting coil constraints in STEP-Bluemira power plant design framework","authors":"Athoy Nilima , Matthew Bluteau , James Cook , Oliver Funk , Georgina Graham , Jonathan Matthews , Stuart I. Muldrew , Alexander J. Pearce , Dario Vaccaro","doi":"10.1016/j.fusengdes.2025.115357","DOIUrl":"10.1016/j.fusengdes.2025.115357","url":null,"abstract":"<div><div>The Spherical Tokamak for Energy Production (STEP) programme aims to deliver a UK prototype fusion energy plant, targeting 2040, and a path to commercial viability of fusion. The conceptual design of such a prototype, meeting engineering and physics constraints, is complex due to the compact nature of spherical tokamaks. The STEP-Bluemira design framework addresses these challenges by providing optimisation tools that simplify the design process, enabling a rapid, integrated workflow for quick evaluation and improvement of design concepts. This work reports recent progress in the STEP-Bluemira power plant design framework, focusing on newly added capabilities for nested optimisation of poloidal field (PF) coil positions and currents with critical current constraints. A keep-in-zone module is introduced, that defines regions for PF coils based on spatial compatibility with the central solenoid, toroidal field coils, and other components. New methods for calculating critical current density for PF coils, based on superconducting properties and critical surface parameterisation, are also added. This paper highlights these advancements through a case study based on the STEP baseline design.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"220 ","pages":"Article 115357"},"PeriodicalIF":2.0,"publicationDate":"2025-07-30","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144724852","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}

引用次数: 0

Advanced electromagnetic-mechanical coupling analysis of superconducting magnets using an integrated multiphysics FE platform 基于集成多物理场有限元平台的超导磁体电磁-力学耦合分析

IF 2 3区工程技术

Fusion Engineering and Design Pub Date : 2025-07-30 DOI: 10.1016/j.fusengdes.2025.115373

Houyuan Zhang , Zhengnan Han , Canjie Xin , Hanxiao Guo , Yongjie Zhang , Guoxi Dai , Qiang Hu , Mingzhi Guan , Xingzhe Wang

{"title":"Advanced electromagnetic-mechanical coupling analysis of superconducting magnets using an integrated multiphysics FE platform","authors":"Houyuan Zhang , Zhengnan Han , Canjie Xin , Hanxiao Guo , Yongjie Zhang , Guoxi Dai , Qiang Hu , Mingzhi Guan , Xingzhe Wang","doi":"10.1016/j.fusengdes.2025.115373","DOIUrl":"10.1016/j.fusengdes.2025.115373","url":null,"abstract":"<div><div>High-field superconducting magnets, characterized by their high current densities and complex, compact configurations, are subjected to significant Lorentz forces. These forces induce pronounced mechanical deformation and stress within the superconducting coils, which can degrade magnetic field uniformity and threaten the operational safety and stability of the magnet, which is a coupled phenomenon referred to as electromagnetic-mechanical interaction. Effectively addressing these challenges, particularly in magnets with complex coil geometries, requires a robust approach for accurately characterizing and modeling such coupled effects. In this study, we developed a multiphysics coupling analysis platform that integrates finite element electromagnetic simulations (OPERA-3D) with mechanical simulations (ABAQUS). Seamless interoperability between these tools is achieved via Python scripting and a shared memory mechanism, enabling efficient, real-time data exchange and supporting parallel computational workflows to significantly enhance performance. Using this platform, we developed a finite element model of a superconducting magnet, which was subsequently validated against experimental measurements. The results demonstrate that the coupled modeling approach yields significantly improved agreement with experimental data compared to traditional one-way sequential simulations. Moreover, our analysis reveals that the differences between coupled and sequential models become more pronounced at higher current loads, offering valuable guidance for optimizing future magnet designs to mitigate electromagnetic-mechanical coupling effects.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"220 ","pages":"Article 115373"},"PeriodicalIF":2.0,"publicationDate":"2025-07-30","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144724853","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}

引用次数: 0

Development of First Wall Tool Base for ITER Blanket Remote Handling System ITER包层远程处理系统首个壁刀库的研制

IF 2 3区工程技术

Fusion Engineering and Design Pub Date : 2025-07-29 DOI: 10.1016/j.fusengdes.2025.115365

Takeyuki Tanaka, Kentaro Nakata, Yuto Noguchi, Nobukazu Takeda

{"title":"Development of First Wall Tool Base for ITER Blanket Remote Handling System","authors":"Takeyuki Tanaka, Kentaro Nakata, Yuto Noguchi, Nobukazu Takeda","doi":"10.1016/j.fusengdes.2025.115365","DOIUrl":"10.1016/j.fusengdes.2025.115365","url":null,"abstract":"<div><div>This paper reports on the development of a First Wall Tool Base (FW TB) for the Blanket Remote Handling System (BRHS), an essential system for the remote maintenance of the Blanket Modules (BMs) attached to the Vacuum Vessel (VV) of the ITER experimental fusion device. The BRHS is required due to the high levels of radiation environment inside the VV. To ensure the reliable performance of maintenance tasks, such as cutting and welding cooling water pipes passing through the BMs, we are developing a FW TB that positions maintenance tools with a high degree of precision. The FW TB can also withstand reaction forces during maintenance to retain precise positioning. We have completed the preliminary design of the Gripping Finger element and Tool Fixing element, primary components of the FW TB. We have confirmed that the FW TB layout remains compatible with a narrow in-vessel environment by means of changing the position of each FW TB element relative to 31 different FW BM variants. We have prototyped the Gripping Finger element and conducted two types of functional evaluation tests: a simulated load application test and a prolonged holding test. These tests have confirmed the achievement of these intended functional reliability of the Gripping Finger element in both of these respects.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"220 ","pages":"Article 115365"},"PeriodicalIF":2.0,"publicationDate":"2025-07-29","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144722352","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}

引用次数: 0

Design and thermal-hydraulic analysis for upper divertor of HL-3 tokamak HL-3型托卡马克上导流器设计及热水力分析

IF 2 3区工程技术

Fusion Engineering and Design Pub Date : 2025-07-29 DOI: 10.1016/j.fusengdes.2025.115370

Wenyu Huang, Yong Lu, Qiang Li, Kuancheng Liu, Pan Huang, Hailong Du

引用次数: 0

Time-resolved characterization of fusion neutron spectra via a liquid scintillation detection system in the HL-3 tokamak HL-3托卡马克中液体闪烁探测系统对聚变中子能谱的时间分辨表征

IF 2 3区工程技术

Fusion Engineering and Design Pub Date : 2025-07-29 DOI: 10.1016/j.fusengdes.2025.115339

J. Zhang , X.L. Chen , H.Y. Shen , J.L. Zhang , Y.S. Zhang , Y.X. Han , Q.L. Yang , Y.P. Zhang , Z.B. Shi , W. Chen

{"title":"Time-resolved characterization of fusion neutron spectra via a liquid scintillation detection system in the HL-3 tokamak","authors":"J. Zhang , X.L. Chen , H.Y. Shen , J.L. Zhang , Y.S. Zhang , Y.X. Han , Q.L. Yang , Y.P. Zhang , Z.B. Shi , W. Chen","doi":"10.1016/j.fusengdes.2025.115339","DOIUrl":"10.1016/j.fusengdes.2025.115339","url":null,"abstract":"<div><div>Measuring time-resolved neutron spectra in fusion neutron fields poses significant challenges. We present our recent advancements in time-resolved fusion neutron spectra measurements and analyses within the HL-3 tokamak for the first time. The measurements are executed using a liquid scintillation detector, which has the capacity to discriminate neutrons and <span><math><mi>γ</mi></math></span>-rays. Notably, the liquid scintillation detector directly acquires the pulse height spectra of recoil protons in the liquid scintillator, rather than the neutron spectra themselves. To convert the pulse height spectra of recoil protons into neutron spectra, Geant4 simulations are performed to compute the detector response matrix. Subsequently, the GRAVEL method is employed in the neutron spectrum unfolding process. As a result, the time-resolved neutron energy spectra can be obtained through time-resolved pulse amplitude spectra measurements. In this study, the optimal time-resolution for the neutron spectra is 100 ms. This indicates that the HL-3 tokamak is equipped with the ability to conduct research on the temporal evolution of neutron spectra and fast ion velocity distributions.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"220 ","pages":"Article 115339"},"PeriodicalIF":2.0,"publicationDate":"2025-07-29","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144722351","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}

引用次数: 0

Feasibility of an endoscope system for the ITER Dust Monitor ITER尘埃监测器内窥镜系统的可行性

IF 2 3区工程技术

Fusion Engineering and Design Pub Date : 2025-07-29 DOI: 10.1016/j.fusengdes.2025.115371

C. Seon , E. Veshchev , S. Sadakov , F. Costa , A. Ayrapetov , J. Catalan , C. Guillemaut , Y. An , J.M. Kim , F. Penzel , T. Wauters , Y.K. Kim , J.H. Bae , G. Vayakis

{"title":"Feasibility of an endoscope system for the ITER Dust Monitor","authors":"C. Seon , E. Veshchev , S. Sadakov , F. Costa , A. Ayrapetov , J. Catalan , C. Guillemaut , Y. An , J.M. Kim , F. Penzel , T. Wauters , Y.K. Kim , J.H. Bae , G. Vayakis","doi":"10.1016/j.fusengdes.2025.115371","DOIUrl":"10.1016/j.fusengdes.2025.115371","url":null,"abstract":"<div><div>The primary function of the ITER dust monitor system is to monitor the relative concentration and properties of generated mobilizable dust particles within the vacuum vessel due to plasma-wall interactions. It also contributes to survey the temporal variation of dust production for safety reasons. Given the challenging environmental conditions within ITER, the design objective of the dust monitoring device is to develop as a fully remote endoscope system with a dust collection unit and an integrated viewing function.</div><div>The operational system of the dust monitor endoscope comprises of driving rollers, a capsule replacement system employing a series of mechanical feedthroughs, and a storage box for collected samples. This paper primarily focuses on detailing the design of the operational system, including the configuration of in-vessel guide pipes. Each component, such as the rotary feedthrough and the imaging optic fiber, was chosen from commercially available options (COTS), with an emphasis on ensuring ease of maintenance.</div><div>The design of clamps for the in-vessel guide pipes was optimized taking into account both the heat load and the anticipated electromagnetic forces in this region. The heat load for these guide pipes was calculated using MCNP and Light-Tools software, and the summarized result is reported in this paper. To accommodate this heat load, specific clamps featuring a design with multiple elastic blades were developed to meet the functional requirement of maintaining the pipe temperature below 240 degrees Celsius, especially when containing dust particles with hydrogen isotopes.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"220 ","pages":"Article 115371"},"PeriodicalIF":2.0,"publicationDate":"2025-07-29","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144722348","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}

引用次数: 0

Parametric study of the thermal response of liquid tin-tungsten capillary porous systems exposed to high thermal loads 高热负荷下液态锡钨毛细管多孔系统热响应的参数化研究

IF 2 3区工程技术

Fusion Engineering and Design Pub Date : 2025-07-29 DOI: 10.1016/j.fusengdes.2025.115372

P. Fernandez-Mayo, E. Oyarzabal, I. Fernandez-Berceruelo

{"title":"Parametric study of the thermal response of liquid tin-tungsten capillary porous systems exposed to high thermal loads","authors":"P. Fernandez-Mayo, E. Oyarzabal, I. Fernandez-Berceruelo","doi":"10.1016/j.fusengdes.2025.115372","DOIUrl":"10.1016/j.fusengdes.2025.115372","url":null,"abstract":"<div><div>The behaviour of liquid metals in capillary porous systems (CPS) is critical for heat and particle exhaust of plasma-facing components, avoiding the problems of degradation and permanent damage of solid first-wall and divertor components in fusion reactors. This study presents a parametric investigation on the design and performance of a liquid tin-tungsten CPS exposed to high thermal loads. Through transient thermal simulations using finite element methods, the effects of geometry, liquid metal saturation degree, porosity and pore size on the CPS thermal behaviour are explored, using mixed thermal properties and random pore models. Our results show that these parameters significantly influence the surface temperature rise and temperature penetration range for both models. When considering the random porous model, different strategies have been adopted for small and large pore sizes, which affect the surface temperature. The numerical results have been compared with experimental measurements carried out in the OLMAT (<em>Optimisation of Liquid Metal Advanced Targets</em>) High Heat Flux facility to validate these models and evaluate their accuracy and limitations. It is found that these models are in good agreement with the experimental data during the thermal load exposure but need to be improved to simulate radiative cooling phases. This work offers a validated framework for future modelling studies and provides new insights into optimizing porous materials for efficient heat transfer in liquid metal-based systems, contributing to the design of enhanced performance solutions for plasma-facing components.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"220 ","pages":"Article 115372"},"PeriodicalIF":2.0,"publicationDate":"2025-07-29","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144724851","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}

引用次数: 0