Pub Date : 2026-01-15DOI: 10.1016/j.fusengdes.2026.115630
Feng Zhang, Mei Huang, Gangyu Chen, He Wang, Wanxin Zheng, Jieqiong Wang, Guoyao Fan, Cheng Chen
As a crucial component of the electron cyclotron resonance heating (ECRH) system, the polarizer primarily serves to change the polarization characteristics of millimeter wave. In this study, an ultra-wideband polarization strategy based on two polarizers for the ECRH system is presented. By employing two identical sinusoidally grooved polarizers at a designated incident angle of 60°, it is possible to attain arbitrary polarization can be attained across an ultra-wideband frequency ranging from 99 GHz to 189 GHz. A ultra-wideband polarizer was devised and evaluated, and computational results indicate that the arbitrary polarization efficiency of the proposed method reaches at least 99.94%. According to this analysis, nearly every desired polarization state can be realized using the presented polarization strategy.
{"title":"Investigation of the ultra-wideband polarizer for high power millimeter wave system","authors":"Feng Zhang, Mei Huang, Gangyu Chen, He Wang, Wanxin Zheng, Jieqiong Wang, Guoyao Fan, Cheng Chen","doi":"10.1016/j.fusengdes.2026.115630","DOIUrl":"10.1016/j.fusengdes.2026.115630","url":null,"abstract":"<div><div>As a crucial component of the electron cyclotron resonance heating (ECRH) system, the polarizer primarily serves to change the polarization characteristics of millimeter wave. In this study, an ultra-wideband polarization strategy based on two polarizers for the ECRH system is presented. By employing two identical sinusoidally grooved polarizers at a designated incident angle of 60°, it is possible to attain arbitrary polarization can be attained across an ultra-wideband frequency ranging from 99 GHz to 189 GHz. A ultra-wideband polarizer was devised and evaluated, and computational results indicate that the arbitrary polarization efficiency of the proposed method reaches at least 99.94%. According to this analysis, nearly every desired polarization state can be realized using the presented polarization strategy.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"225 ","pages":"Article 115630"},"PeriodicalIF":2.0,"publicationDate":"2026-01-15","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145963133","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}
Pub Date : 2026-01-15DOI: 10.1016/j.fusengdes.2026.115629
Haixia Wang , Xuewei Fu , Zihui Yang , Qianchao Huo , Jie Yu
The China Fusion Engineering Test Reactor (CFETR) is a next-generation fusion reactor project independently designed and actively pursued by China. As the key radioactive source term of the CFETR, tritium safety is an important issue of nuclear safety. The tritium safety confinement system is one of the major systems in the CFETR tritium plant, and the study of tritium transport behavior in confinement system is of significant research interest. Supported by the National Key R&D Program, this study employs Unreal Engine (UE) as the 3D interactive simulation engine to construct a 3D simulation demonstration platform for tritium safety confinement of the CFETR. The Tokamak Exhaust Processing (TEP) System is selected as a representative case for simulation. Test results indicate that the platform enables smooth human-computer interaction, effectively visualizes tritium transport behavior under typical conditions, and provides an immersive 3D scene virtual roaming experience. Through dynamic demonstration of tritium transport under multiple conditions, the design principle of the CFETR tritium safety confinement system is effectively visualized, offering valuable insights for the future design of tritium confinement system in tritium plants.
{"title":"Development of 3D simulation demonstration platform for tritium safety confinement of China fusion engineering test reactor","authors":"Haixia Wang , Xuewei Fu , Zihui Yang , Qianchao Huo , Jie Yu","doi":"10.1016/j.fusengdes.2026.115629","DOIUrl":"10.1016/j.fusengdes.2026.115629","url":null,"abstract":"<div><div>The China Fusion Engineering Test Reactor (CFETR) is a next-generation fusion reactor project independently designed and actively pursued by China. As the key radioactive source term of the CFETR, tritium safety is an important issue of nuclear safety. The tritium safety confinement system is one of the major systems in the CFETR tritium plant, and the study of tritium transport behavior in confinement system is of significant research interest. Supported by the National Key R&D Program, this study employs Unreal Engine (UE) as the 3D interactive simulation engine to construct a 3D simulation demonstration platform for tritium safety confinement of the CFETR. The Tokamak Exhaust Processing (TEP) System is selected as a representative case for simulation. Test results indicate that the platform enables smooth human-computer interaction, effectively visualizes tritium transport behavior under typical conditions, and provides an immersive 3D scene virtual roaming experience. Through dynamic demonstration of tritium transport under multiple conditions, the design principle of the CFETR tritium safety confinement system is effectively visualized, offering valuable insights for the future design of tritium confinement system in tritium plants.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"225 ","pages":"Article 115629"},"PeriodicalIF":2.0,"publicationDate":"2026-01-15","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145981155","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}
Pub Date : 2026-01-15DOI: 10.1016/j.fusengdes.2026.115628
Qin Lei , Qiannan Yu , Jiaguan Peng , Yiwen Sun , Mengqi Zhang , Hanfeng Song , Hao Yin , Xiaolu Xiong , Sijie Hao , Yuhao Li , Xiuli Zhu , Lu Sun , Long Cheng , Yue Yuan , Guang-Hong Lu
The study of hydrogen isotopes (HIs) retention in fusion materials is crucial for the safe operation of fusion devices. This research developed the proximal probe thermal desorption mass spectrometry (PTDS) technique, a unique technique utilizing a probe to heat the specific micro-regions on the sample, to characterize lateral deuterium (D) retention in materials using deuterated tungsten. The temperature during the test was studied using an infrared camera, with the maximum probe tip temperature reaching approximately 2300 K and the temperature-affected region having a diameter of about 500 µm. PTDS testing of deuterated tungsten films prepared by magnetron sputtering revealed a uniform lateral distribution of D retention on the sample surface. Using PTDS, the estimated deuterium-to-tungsten (D/W) atomic ratio was approximately 0.146. PTDS testing of D plasma-exposed sample provided the lateral distribution characteristics of D retention, which were compared with the distribution of plasma flux showing consistent trends. Besides, D/W ratio in D plasma-exposed sample is about 6.40 × 10–5 as estimated based on thermal desorption spectroscopy (TDS) measurement, indicating that the detection capability of the device reached the order of ∼10–5. Furthermore, this technique is of potential in precise localization of measurement spots and future research will focus on enhancing the lateral spatial resolution and in situ application of PTDS on HIs transport studies during plasma exposure.
{"title":"Proximal probe thermal desorption mass spectrometry for mapping lateral hydrogen isotope retention in metals","authors":"Qin Lei , Qiannan Yu , Jiaguan Peng , Yiwen Sun , Mengqi Zhang , Hanfeng Song , Hao Yin , Xiaolu Xiong , Sijie Hao , Yuhao Li , Xiuli Zhu , Lu Sun , Long Cheng , Yue Yuan , Guang-Hong Lu","doi":"10.1016/j.fusengdes.2026.115628","DOIUrl":"10.1016/j.fusengdes.2026.115628","url":null,"abstract":"<div><div>The study of hydrogen isotopes (HIs) retention in fusion materials is crucial for the safe operation of fusion devices. This research developed the proximal probe thermal desorption mass spectrometry (PTDS) technique, a unique technique utilizing a probe to heat the specific micro-regions on the sample, to characterize lateral deuterium (D) retention in materials using deuterated tungsten. The temperature during the test was studied using an infrared camera, with the maximum probe tip temperature reaching approximately 2300 K and the temperature-affected region having a diameter of about 500 µm. PTDS testing of deuterated tungsten films prepared by magnetron sputtering revealed a uniform lateral distribution of D retention on the sample surface. Using PTDS, the estimated deuterium-to-tungsten (D/W) atomic ratio was approximately 0.146. PTDS testing of D plasma-exposed sample provided the lateral distribution characteristics of D retention, which were compared with the distribution of plasma flux showing consistent trends. Besides, D/W ratio in D plasma-exposed sample is about 6.40 × 10<sup>–5</sup> as estimated based on thermal desorption spectroscopy (TDS) measurement, indicating that the detection capability of the device reached the order of ∼10<sup>–5</sup>. Furthermore, this technique is of potential in precise localization of measurement spots and future research will focus on enhancing the lateral spatial resolution and <em>in situ</em> application of PTDS on HIs transport studies during plasma exposure.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"225 ","pages":"Article 115628"},"PeriodicalIF":2.0,"publicationDate":"2026-01-15","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145963131","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}
Pub Date : 2026-01-14DOI: 10.1016/j.fusengdes.2025.115610
Giacomo Cavuoti , Francesca Cau , José Lorenzo , Alfredo Portone
The aim of this paper is to present a fast method capable of computing thermo-hydraulic transients in solid components that are cooled (or heated) by incompressible forced flow with or without external heating sources. By coupling the heat conduction equation in the solid volume to the heat transfer to the forced flow we derive a linearized mapping between the vector of input (control) quantities u(t) such as mass flow and inlet temperature to the vector of nodal temperature T(t) in the solid domain. A comparison between the newly developed code, which is finite volume based and a standard finite element-based code such as ANSYS is presented. Despite the significant reduction in CPU time, the finite-volume code well approximates the solid temperature field computed by ANSYS for the two cases considered here, i.e. the fusion power operation and vacuum vessel baking operation.
{"title":"Linear model responses in forced flow cooling","authors":"Giacomo Cavuoti , Francesca Cau , José Lorenzo , Alfredo Portone","doi":"10.1016/j.fusengdes.2025.115610","DOIUrl":"10.1016/j.fusengdes.2025.115610","url":null,"abstract":"<div><div>The aim of this paper is to present a fast method capable of computing thermo-hydraulic transients in solid components that are cooled (or heated) by incompressible forced flow with or without external heating sources. By coupling the heat conduction equation in the solid volume to the heat transfer to the forced flow we derive a linearized mapping between the vector of input (control) quantities <strong>u</strong>(t) such as mass flow and inlet temperature to the vector of nodal temperature <strong>T</strong>(t) in the solid domain. A comparison between the newly developed code, which is finite volume based and a standard finite element-based code such as ANSYS is presented. Despite the significant reduction in CPU time, the finite-volume code well approximates the solid temperature field computed by ANSYS for the two cases considered here, i.e. the fusion power operation and vacuum vessel baking operation.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"225 ","pages":"Article 115610"},"PeriodicalIF":2.0,"publicationDate":"2026-01-14","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145963132","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}
The ADITYA tokamak, a medium-sized device with a limiter configuration is upgraded to ADITYA-U tokamak with divertor configuration for shaped plasma operation. Three pairs of divertor coils and two pairs of position control coils are introduced in ADITYA-U tokamak. The strategy was focused on optimising the available space for new magnetic field coils installation without relying on the active cooling arrangements. The primary challenge was to install the coil along with the bus bar without any joints while utilizing the same conductor. The demountable TF coils in ADITYA-U tokamak simplified the feasibility for the new coils. The physical and technical boundary conditions were met using copper-based continuous transposed conductor (CTC) for the in-situ coil winding. This simple design is low cost and offers winding flexibility while ensuring accurate coil dimensions. A detailed description of the assembly procedure and solution to different engineering challenges during the fabrication of the divertor and position control coils are presented in this paper.
{"title":"Strategies and solutions for engineering challenges during the assembly of divertor and position control coils in ADITYA-U tokamak","authors":"Rohit Kumar , Vaibhav Ranjan , Harshita Raj , Kumarpal Jadeja , Kaushal Patel , R.L. Tanna , J. Ghosh","doi":"10.1016/j.fusengdes.2026.115615","DOIUrl":"10.1016/j.fusengdes.2026.115615","url":null,"abstract":"<div><div>The ADITYA tokamak, a medium-sized device with a limiter configuration is upgraded to ADITYA-U tokamak with divertor configuration for shaped plasma operation. Three pairs of divertor coils and two pairs of position control coils are introduced in ADITYA-U tokamak. The strategy was focused on optimising the available space for new magnetic field coils installation without relying on the active cooling arrangements. The primary challenge was to install the coil along with the bus bar without any joints while utilizing the same conductor. The demountable TF coils in ADITYA-U tokamak simplified the feasibility for the new coils. The physical and technical boundary conditions were met using copper-based continuous transposed conductor (CTC) for the in-situ coil winding. This simple design is low cost and offers winding flexibility while ensuring accurate coil dimensions. A detailed description of the assembly procedure and solution to different engineering challenges during the fabrication of the divertor and position control coils are presented in this paper.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"224 ","pages":"Article 115615"},"PeriodicalIF":2.0,"publicationDate":"2026-01-13","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145977565","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}
Pub Date : 2026-01-12DOI: 10.1016/j.fusengdes.2026.115624
J.Q. Wang , Y.P. Zhang , Z.B. Wang , Y.X. Han , Z.H. Wang , J. Chen , Y. Yu , J. Zhang , C.Y. Zhao , H.Y. Shen , H. Duan , Q.L. Yang , H.B. Xu , HL-3 Team
A high spatiotemporal resolution hard X-ray (HXR) camera system has been designed for HL-3 tokamak for detecting fast electron bremsstrahlung and runaway electron profile imaging. By utilizing a combination of yttrium oxyorthosilicate (YSO) scintillator and silicon photomultipliers (SiPM), the system achieves a time resolution of up to 1 ms. Through the rational arrangement of scintillators, the camera can simultaneously detect 100 channels of hard X-rays, resulting in a spatial resolution of 2 cm for the camera. The system is dedicated to study the runaway electrons in the hard X-ray energy range of 20 to 200 keV. By improving the time resolution to 1 ms, it can be used to study power deposition in lower hybrid current drive (LHCD) and electron cyclotron resonance heating (ECRH), the generation of runaway seed populations in plasmas, and behavior of runaway electrons during plasma disruptions. The experimental results can present the evolution over time and the spatial distribution. This paper presents the system design, performance and typical diagnostic results.
{"title":"Design of a high spatiotemporal resolution hard X-ray camera system on the HL-3 tokamak","authors":"J.Q. Wang , Y.P. Zhang , Z.B. Wang , Y.X. Han , Z.H. Wang , J. Chen , Y. Yu , J. Zhang , C.Y. Zhao , H.Y. Shen , H. Duan , Q.L. Yang , H.B. Xu , HL-3 Team","doi":"10.1016/j.fusengdes.2026.115624","DOIUrl":"10.1016/j.fusengdes.2026.115624","url":null,"abstract":"<div><div>A high spatiotemporal resolution hard X-ray (HXR) camera system has been designed for HL-3 tokamak for detecting fast electron bremsstrahlung and runaway electron profile imaging. By utilizing a combination of yttrium oxyorthosilicate (YSO) scintillator and silicon photomultipliers (SiPM), the system achieves a time resolution of up to 1 ms. Through the rational arrangement of scintillators, the camera can simultaneously detect 100 channels of hard X-rays, resulting in a spatial resolution of 2 cm for the camera. The system is dedicated to study the runaway electrons in the hard X-ray energy range of 20 to 200 keV. By improving the time resolution to 1 ms, it can be used to study power deposition in lower hybrid current drive (LHCD) and electron cyclotron resonance heating (ECRH), the generation of runaway seed populations in plasmas, and behavior of runaway electrons during plasma disruptions. The experimental results can present the evolution over time and the spatial distribution. This paper presents the system design, performance and typical diagnostic results.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"224 ","pages":"Article 115624"},"PeriodicalIF":2.0,"publicationDate":"2026-01-12","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145977553","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}
Pub Date : 2026-01-10DOI: 10.1016/j.fusengdes.2026.115627
Matt Landreman , Humberto Torreblanca , Antoine Cerfon
In fusion reactor design, steels under consideration for the blanket are ferromagnetic, so the steel’s effect on the plasma physics must be examined. For efficient calculation of these fields, we can exploit the fact that the ferromagnetic material gives a small perturbation relative to the fields from the electromagnetic coils and plasma. Moreover the magnetization is saturated due to the strong fields in typical fusion systems. These approximations significantly reduce the nonlinearity of the problem, so the magnetic materials can be described by an array of point dipoles of known magnitude, oriented in the direction of the coil and plasma field. The approach is verified by comparison to finite-element calculations with commercial software and shown to be accurate. As no linear or nonlinear solve is required, only evaluation of Biot–Savart-type integrals, the method here is significantly simpler to implement than other methods, and extremely fast. The method is compatible with arbitrary CAD geometry, and also allows rapid computation of the magnetic forces. We demonstrate adding the ferromagnetic effects to free-boundary magnetohydrodynamic equilibrium calculations, assessing the effect on plasma physics properties such as confinement and stability. Moreover, it is straightforward to differentiate through the model to get the derivative of the field with respect to the electromagnet parameters. We thereby demonstrate gradient-based coil optimization for a quasi-isodynamic stellarator in which the field contribution from a ferromagnetic blanket is included. Even a significant steel volume is found to have little impact on the plasma physics properties, with the main effects being a slight destabilization of ballooning modes and a radial shift of the edge islands due to decrease in rotational transform. Both of these issues are corrected by the minor reoptimization of the coil shapes to account for the field from the steel.
{"title":"Efficient calculation of magnetic fields from ferromagnetic materials near strong electromagnets, and application to stellarator coil optimization","authors":"Matt Landreman , Humberto Torreblanca , Antoine Cerfon","doi":"10.1016/j.fusengdes.2026.115627","DOIUrl":"10.1016/j.fusengdes.2026.115627","url":null,"abstract":"<div><div>In fusion reactor design, steels under consideration for the blanket are ferromagnetic, so the steel’s effect on the plasma physics must be examined. For efficient calculation of these fields, we can exploit the fact that the ferromagnetic material gives a small perturbation relative to the fields from the electromagnetic coils and plasma. Moreover the magnetization is saturated due to the strong fields in typical fusion systems. These approximations significantly reduce the nonlinearity of the problem, so the magnetic materials can be described by an array of point dipoles of known magnitude, oriented in the direction of the coil and plasma field. The approach is verified by comparison to finite-element calculations with commercial software and shown to be accurate. As no linear or nonlinear solve is required, only evaluation of Biot–Savart-type integrals, the method here is significantly simpler to implement than other methods, and extremely fast. The method is compatible with arbitrary CAD geometry, and also allows rapid computation of the magnetic forces. We demonstrate adding the ferromagnetic effects to free-boundary magnetohydrodynamic equilibrium calculations, assessing the effect on plasma physics properties such as confinement and stability. Moreover, it is straightforward to differentiate through the model to get the derivative of the field with respect to the electromagnet parameters. We thereby demonstrate gradient-based coil optimization for a quasi-isodynamic stellarator in which the field contribution from a ferromagnetic blanket is included. Even a significant steel volume is found to have little impact on the plasma physics properties, with the main effects being a slight destabilization of ballooning modes and a radial shift of the edge islands due to decrease in rotational transform. Both of these issues are corrected by the minor reoptimization of the coil shapes to account for the field from the steel.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"224 ","pages":"Article 115627"},"PeriodicalIF":2.0,"publicationDate":"2026-01-10","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145939088","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}
Pub Date : 2026-01-09DOI: 10.1016/j.fusengdes.2025.115613
A. González Ganzábal , G.A. Rattá , T. Estrada , J. Martínez-Fernández , N. Panadero , Á. Cappa , B. López-Miranda , A. Baciero , F. Martín , D. Tafalla , B.P. Van Milligen , F. Medina , Á. de la Peña , S. Dormido-Canto , TJ-II team
Starting in 1997, the stellarator TJ-II has produced valuable scientific data crucial in the study of plasma physics and confinement. In this work, we present a stand-alone, comprehensive database that focuses on the statistical value of the TJ-II data. For this purpose, and comprising 4800 discharges, all the signals and parameters required to characterise the device before a discharge, and the diagnostics that better describe the produced plasma have been included in a database. All these different signals have been curated according to the needs of each signal and synchronised into a unified time frame of interest of 1 ms. Thus, this paper and the presented database fulfil two objectives: an introduction to several TJ-II key signals and diagnostics and a common framework for future works that rely on a strong, statistically tested database, such as the creation of models based on machine learning or data simulations.
{"title":"A comprehensive database of TJ-II signals and diagnostics for statistically based models","authors":"A. González Ganzábal , G.A. Rattá , T. Estrada , J. Martínez-Fernández , N. Panadero , Á. Cappa , B. López-Miranda , A. Baciero , F. Martín , D. Tafalla , B.P. Van Milligen , F. Medina , Á. de la Peña , S. Dormido-Canto , TJ-II team","doi":"10.1016/j.fusengdes.2025.115613","DOIUrl":"10.1016/j.fusengdes.2025.115613","url":null,"abstract":"<div><div>Starting in 1997, the stellarator TJ-II has produced valuable scientific data crucial in the study of plasma physics and confinement. In this work, we present a stand-alone, comprehensive database that focuses on the statistical value of the TJ-II data. For this purpose, and comprising 4800 discharges, all the signals and parameters required to characterise the device before a discharge, and the diagnostics that better describe the produced plasma have been included in a database. All these different signals have been curated according to the needs of each signal and synchronised into a unified time frame of interest of 1 ms. Thus, this paper and the presented database fulfil two objectives: an introduction to several TJ-II key signals and diagnostics and a common framework for future works that rely on a strong, statistically tested database, such as the creation of models based on machine learning or data simulations.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"224 ","pages":"Article 115613"},"PeriodicalIF":2.0,"publicationDate":"2026-01-09","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145939089","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}
Pub Date : 2026-01-09DOI: 10.1016/j.fusengdes.2025.115598
Troy Pederson , Himank Anand , Charlie Lasnier , Lennard Ceelen , Jun Ren , Keith Erickson , Ben Penaflor , John Ferron
In future tokamak reactors like ITER and the Fusion Pilot Plant (FPP), real-time feedback control of heat flux to the plasma-facing components (PFC) will be critical for steady-state operation. This work presents the first experimental demonstration of real-time divertor heat flux estimation with infrared thermography and feedback control with impurity seeding on the DIII-D tokamak. The flexible infrastructure of the Plasma Control System (PCS) on DIII-D makes this new capability possible. The PCS software runs on a gateway computer system, and five real-time compute nodes. An array of low latency streaming digitizers from d-TACQ Solutions connects to these real-time computers to collect and process data, and send commands to actuators during plasma discharges. This system handles the signal IO from the tokamak and allows the PCS to utilize the diagnostic data necessary to perform control in real-time. Feedback control on heat flux was accomplished by feeding infrared camera data from the “Infrared TV” (IRTV) camera to a custom-developed User Datagram Protocol (UDP) server. This server transmits infrared data to a newly developed PCS algorithm that estimates the heat flux to PFC. A proportional integral derivative (PID) controller minimizes the error between a heat flux reference and the real-time estimate by injecting nitrogen gas into the divertor.
{"title":"Preliminary proof-of-concept of real-time divertor heat flux control from infrared cameras with nitrogen injection in the DIII-D tokamak","authors":"Troy Pederson , Himank Anand , Charlie Lasnier , Lennard Ceelen , Jun Ren , Keith Erickson , Ben Penaflor , John Ferron","doi":"10.1016/j.fusengdes.2025.115598","DOIUrl":"10.1016/j.fusengdes.2025.115598","url":null,"abstract":"<div><div>In future tokamak reactors like ITER and the Fusion Pilot Plant (FPP), real-time feedback control of heat flux to the plasma-facing components (PFC) will be critical for steady-state operation. This work presents the first experimental demonstration of real-time divertor heat flux estimation with infrared thermography and feedback control with impurity seeding on the DIII-D tokamak. The flexible infrastructure of the Plasma Control System (PCS) on DIII-D makes this new capability possible. The PCS software runs on a gateway computer system, and five real-time compute nodes. An array of low latency streaming digitizers from <span>d</span>-TACQ Solutions connects to these real-time computers to collect and process data, and send commands to actuators during plasma discharges. This system handles the signal IO from the tokamak and allows the PCS to utilize the diagnostic data necessary to perform control in real-time. Feedback control on heat flux was accomplished by feeding infrared camera data from the “Infrared TV” (IRTV) camera to a custom-developed User Datagram Protocol (UDP) server. This server transmits infrared data to a newly developed PCS algorithm that estimates the heat flux to PFC. A proportional integral derivative (PID) controller minimizes the error between a heat flux reference and the real-time estimate by injecting nitrogen gas into the divertor.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"224 ","pages":"Article 115598"},"PeriodicalIF":2.0,"publicationDate":"2026-01-09","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145939617","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}
Pub Date : 2026-01-09DOI: 10.1016/j.fusengdes.2025.115612
Svitlana Rudchenko , Yiran Mao , Wolfgang Pantleon
Tungsten-based materials are considered as armor of plasma-facing components for future fusion reactors. To mitigate the brittleness of tungsten, tungsten fiber-reinforced tungsten composites (Wf/W) have been developed. Two types of Wf/W composites, with either continuous, aligned, potassium-doped tungsten wires in a dense tungsten matrix or randomly oriented, short fibers in a porous tungsten matrix are investigated. Both were fabricated using a powder metallurgical route facilitating field assisted sintering technology (FAST). Specimens are annealed at 1450 °C for different amounts of time up to two weeks to assess the thermal stability of the composites. Scanning electron microscopy and electron backscatter diffraction reveal major changes in the microstructure. After 4 hours of annealing initiation of recrystallization in the fibers concurrent to grain growth in the matrix is observed in both composites. Recrystallization commences at the outskirts of the fibers causing formation of a rim of small, recrystallized grains. Longer annealing increases the rim of recrystallized grains inwards into the fiber. After 3 days of annealing, all fibers are completely recrystallized, and the matrix is coarsened significantly by grain growth. While the short fibers can still be identified in the porous matrix after one week of annealing, matrix and continuous fibers cannot be distinguished any longer in the dense matrix. Short fibers with large, recrystallized grains can still be recognized after 2 weeks of annealing, while the porous matrix disintegrates by particle coarsening.
{"title":"Thermal stability of tungsten fiber-reinforced tungsten composites fabricated by powder metallurgy","authors":"Svitlana Rudchenko , Yiran Mao , Wolfgang Pantleon","doi":"10.1016/j.fusengdes.2025.115612","DOIUrl":"10.1016/j.fusengdes.2025.115612","url":null,"abstract":"<div><div>Tungsten-based materials are considered as armor of plasma-facing components for future fusion reactors. To mitigate the brittleness of tungsten, tungsten fiber-reinforced tungsten composites (W<sub>f</sub>/W) have been developed. Two types of W<sub>f</sub>/W composites, with either continuous, aligned, potassium-doped tungsten wires in a dense tungsten matrix or randomly oriented, short fibers in a porous tungsten matrix are investigated. Both were fabricated using a powder metallurgical route facilitating field assisted sintering technology (FAST). Specimens are annealed at 1450 °C for different amounts of time up to two weeks to assess the thermal stability of the composites. Scanning electron microscopy and electron backscatter diffraction reveal major changes in the microstructure. After 4 hours of annealing initiation of recrystallization in the fibers concurrent to grain growth in the matrix is observed in both composites. Recrystallization commences at the outskirts of the fibers causing formation of a rim of small, recrystallized grains. Longer annealing increases the rim of recrystallized grains inwards into the fiber. After 3 days of annealing, all fibers are completely recrystallized, and the matrix is coarsened significantly by grain growth. While the short fibers can still be identified in the porous matrix after one week of annealing, matrix and continuous fibers cannot be distinguished any longer in the dense matrix. Short fibers with large, recrystallized grains can still be recognized after 2 weeks of annealing, while the porous matrix disintegrates by particle coarsening.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"224 ","pages":"Article 115612"},"PeriodicalIF":2.0,"publicationDate":"2026-01-09","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145939618","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}
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