Pub Date : 2026-02-04DOI: 10.1016/j.fusengdes.2026.115653
Yu-zhong Jin , You-yun Lian , Jian-bao Wang , Fan Feng , Cheng-ming Tu , Dong zhao , Hao Wang , Zong-jian Chai , Zi-jie Wang , Xiang Liu
Designed heat flux as 10 MW m−2 during stationary operation can be foreseen for ITER divertor tungsten, while the heat flux would be increased to even 20 MW m−2 for future fusion devices. Design of advanced divertor target structure with enhanced cooling ability and prolonged lifetime is a popular research direction at present. In this paper, a new divertor target structure that combines flat tile concept and monoblock concept has been proposed. Finite Element Method (FEM) has been used to compare the thermal response as well as the service lifetime between ITER-like divertor monoblock and the novel divertor structure. Low-cycle fatigue damage and thermal creep rupture has been considered during simulation. A linear rule criterion has been applied to roughly estimate the creep-fatigue interaction on the armor material. The results show the novel divertor structure owns better heat transfer capability and it is expected to own longer service lifetime than ITER-like monoblock. Furthermore, high heat flux experiments have been conducted to verify its heat removal ability and structural reliability.
{"title":"Novel divertor target structural design for extreme heat load: FEM Simulation and experimental validation","authors":"Yu-zhong Jin , You-yun Lian , Jian-bao Wang , Fan Feng , Cheng-ming Tu , Dong zhao , Hao Wang , Zong-jian Chai , Zi-jie Wang , Xiang Liu","doi":"10.1016/j.fusengdes.2026.115653","DOIUrl":"10.1016/j.fusengdes.2026.115653","url":null,"abstract":"<div><div>Designed heat flux as 10 MW m<sup>−2</sup> during stationary operation can be foreseen for ITER divertor tungsten, while the heat flux would be increased to even 20 MW m<sup>−2</sup> for future fusion devices. Design of advanced divertor target structure with enhanced cooling ability and prolonged lifetime is a popular research direction at present. In this paper, a new divertor target structure that combines flat tile concept and monoblock concept has been proposed. Finite Element Method (FEM) has been used to compare the thermal response as well as the service lifetime between ITER-like divertor monoblock and the novel divertor structure. Low-cycle fatigue damage and thermal creep rupture has been considered during simulation. A linear rule criterion has been applied to roughly estimate the creep-fatigue interaction on the armor material. The results show the novel divertor structure owns better heat transfer capability and it is expected to own longer service lifetime than ITER-like monoblock. Furthermore, high heat flux experiments have been conducted to verify its heat removal ability and structural reliability.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"225 ","pages":"Article 115653"},"PeriodicalIF":2.0,"publicationDate":"2026-02-04","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"146173790","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 : 2026-02-04DOI: 10.1016/j.fusengdes.2026.115654
Shunsuke Kenjo , Yoshiyuki Tsuji , Kai Masuda
One of the key challenges in Advanced Fusion Neutron Source (A-FNS) is to maintain the stable liquid Li target flow over the long-term operation. The laser-based distance meter using an optical frequency comb has been selected to detect the surface disturbance due to the nozzle degradation. However, the laser-based method can measure only wave crests/troughs where the incident laser is reflected. This study evaluated the frequency characteristics of the liquid Li flow surface by interpolating the irregular time series crest/trough data obtained in EVEDA Li Test Loop (ELTL) and performing Fast Fourier Transformation calculations. Linear and sine wave interpolation were performed, and the effect of the interpolation method was evaluated. This study revealed the frequency characteristics of the free surface liquid level fluctuations with the experimental results for the first time. Since a decrease in the spectra intensities due to the rough nozzle surface has been suggested by the calculations, the evaluations in temporal change of the energy spectra could quantitatively detect the nozzle degradation.
先进聚变中子源（A-FNS）的关键挑战之一是在长期运行中保持稳定的液态Li靶流。采用光学频率梳的激光测距仪检测喷嘴退化引起的表面扰动。然而，基于激光的方法只能测量入射激光反射的波峰/波谷。本研究通过插值EVEDA Li Test Loop （ELTL）中获得的不规则时间序列波峰/波谷数据，并进行快速傅里叶变换计算，评估了液体Li流表面的频率特性。分别进行了线性和正弦波插值，并对插值方法的效果进行了评价。本研究首次与实验结果结合，揭示了自由表面液位波动的频率特性。由于计算表明喷管表面粗糙会导致能谱强度下降，因此对能谱的时间变化进行评价可以定量地检测喷管的退化情况。
{"title":"Frequency characteristics of the liquid Li target flow surface in A-FNS","authors":"Shunsuke Kenjo , Yoshiyuki Tsuji , Kai Masuda","doi":"10.1016/j.fusengdes.2026.115654","DOIUrl":"10.1016/j.fusengdes.2026.115654","url":null,"abstract":"<div><div>One of the key challenges in Advanced Fusion Neutron Source (A-FNS) is to maintain the stable liquid Li target flow over the long-term operation. The laser-based distance meter using an optical frequency comb has been selected to detect the surface disturbance due to the nozzle degradation. However, the laser-based method can measure only wave crests/troughs where the incident laser is reflected. This study evaluated the frequency characteristics of the liquid Li flow surface by interpolating the irregular time series crest/trough data obtained in EVEDA Li Test Loop (ELTL) and performing Fast Fourier Transformation calculations. Linear and sine wave interpolation were performed, and the effect of the interpolation method was evaluated. This study revealed the frequency characteristics of the free surface liquid level fluctuations with the experimental results for the first time. Since a decrease in the spectra intensities due to the rough nozzle surface has been suggested by the calculations, the evaluations in temporal change of the energy spectra could quantitatively detect the nozzle degradation.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"225 ","pages":"Article 115654"},"PeriodicalIF":2.0,"publicationDate":"2026-02-04","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"146173791","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}
Control systems for experimental physics, such as the Plasma Control System (PCS), demand constant modification of control algorithms to test new theories. This need for agile development often conflicts with the critical requirement of maintaining data consistency across heterogeneous system components, such as user interfaces and databases. This paper introduces a lightweight, eXtensible Markup Language (XML)based, model-driven approach designed to resolve this conflict within the Lingshu PCS framework. At its core is a simple, human-readable data model that serves as the Single Source of Truth (SSoT) for all algorithm-related data. Coupled with a dedicated toolchain, our approach automates the generation of crucial engineering artifacts, including C++ code skeletons and user interface templates, directly from the model. This method ensures end-to-end data consistency, streamlines the development cycle, and provides a pragmatic, low-overhead approach tailored to the integration of control algorithms.
{"title":"Improving control integration in Plasma Control System with an XML-based model-driven approach","authors":"Z.M. Huang , Q.P. Yuan , R.R. Zhang , W.H. Ma , J.J. Huang , J.Q. Zhu , X.X. Li , W.Y. Rui , B.J. Xiao","doi":"10.1016/j.fusengdes.2026.115642","DOIUrl":"10.1016/j.fusengdes.2026.115642","url":null,"abstract":"<div><div>Control systems for experimental physics, such as the Plasma Control System (PCS), demand constant modification of control algorithms to test new theories. This need for agile development often conflicts with the critical requirement of maintaining data consistency across heterogeneous system components, such as user interfaces and databases. This paper introduces a lightweight, eXtensible Markup Language (XML)based, model-driven approach designed to resolve this conflict within the Lingshu PCS framework. At its core is a simple, human-readable data model that serves as the Single Source of Truth (SSoT) for all algorithm-related data. Coupled with a dedicated toolchain, our approach automates the generation of crucial engineering artifacts, including C++ code skeletons and user interface templates, directly from the model. This method ensures end-to-end data consistency, streamlines the development cycle, and provides a pragmatic, low-overhead approach tailored to the integration of control algorithms.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"225 ","pages":"Article 115642"},"PeriodicalIF":2.0,"publicationDate":"2026-02-02","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"146174232","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 : 2026-02-02DOI: 10.1016/j.fusengdes.2026.115655
Yang Yang , Yu Zhang , Liansheng Du , Xuwei Zhu , Junfei Pang , Yuxiang Tang , Yong Cheng
The double door system is a critical component of the remote maintenance cask system for fusion reactors, enabling the safe transfer of activated in-vessel components between the vacuum vessel and the hot cell. This paper presents the design, development, and experimental validation of a novel double door system. A full scale, fully functional double door prototype was constructed, featuring key design elements such as a rectangular door profile, irregular cross-section sealing ring, a purely mechanical port door and cask door coupling and locking mechanism, and an integrated door tilting system. The double door prototype was used to execute a comprehensive test campaign. This included validation of the complete motion sequence — docking, door unlocking, two door coupling, tilting, and reversal — and leak tightness testing according to ISO 10648-2 standards for all relevant sealed chambers. Experimental results confirmed reliable mechanical operation and demonstrated that all tested chambers met the Class 2 and Class 3 leak tightness requirement. The successful validation of both functional and sealing performance confirms the design’s effectiveness and provides a valuable reference for the engineering of transfer cask system in future fusion power plants.
{"title":"Design and verification of the double door system for fusion reactor remote maintenance casks","authors":"Yang Yang , Yu Zhang , Liansheng Du , Xuwei Zhu , Junfei Pang , Yuxiang Tang , Yong Cheng","doi":"10.1016/j.fusengdes.2026.115655","DOIUrl":"10.1016/j.fusengdes.2026.115655","url":null,"abstract":"<div><div>The double door system is a critical component of the remote maintenance cask system for fusion reactors, enabling the safe transfer of activated in-vessel components between the vacuum vessel and the hot cell. This paper presents the design, development, and experimental validation of a novel double door system. A full scale, fully functional double door prototype was constructed, featuring key design elements such as a rectangular door profile, irregular cross-section sealing ring, a purely mechanical port door and cask door coupling and locking mechanism, and an integrated door tilting system. The double door prototype was used to execute a comprehensive test campaign. This included validation of the complete motion sequence — docking, door unlocking, two door coupling, tilting, and reversal — and leak tightness testing according to ISO 10648-2 standards for all relevant sealed chambers. Experimental results confirmed reliable mechanical operation and demonstrated that all tested chambers met the Class 2 and Class 3 leak tightness requirement. The successful validation of both functional and sealing performance confirms the design’s effectiveness and provides a valuable reference for the engineering of transfer cask system in future fusion power plants.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"225 ","pages":"Article 115655"},"PeriodicalIF":2.0,"publicationDate":"2026-02-02","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"146173789","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 : 2026-01-29DOI: 10.1016/j.fusengdes.2026.115641
Wei Tong , Meng Xu , Hua Li , Zhenhan Li , Zhiquan Song , Peng Fu
Superconducting magnets in fusion devices are at the risk of quench during operation. Once quench occurs, the stored electromagnetic energy rapidly turns to Joule heat, potentially damaging the magnets severely. To protect these magnets, the Quench Protection System (QPS) employs high-power DC breaker to quickly interrupt the magnet current and transfer the quench energy, which relies on the LC circuit resonance to generate reverse pulsed current for creating a current zero-crossing point. This paper introduces the design and performance analysis of a high-current pulse inductor with toroidal helical structure. Its unique structure confines the magnetic field inside the coil, reducing interference and ensuring stability under pulse current. Targeting 20 μH inductance and 80 kA rated pulse current, the structural design of the inductor is performed firstly. Further, the Finite Element Method (FEM) is used to conduct a systematic simulation analysis of its electromagnetic, structural, and thermal performance. Finally, a prototype is also manufactured and subjected to LR parameter measurement and pulse high-current testing. Both simulation and test results show that the inductor has excellent magnetic confinement capability, outstanding structural stability, and reasonable temperature rise control ability.
{"title":"Design and performance analysis of a high-current pulse inductor for fusion magnet quench protection","authors":"Wei Tong , Meng Xu , Hua Li , Zhenhan Li , Zhiquan Song , Peng Fu","doi":"10.1016/j.fusengdes.2026.115641","DOIUrl":"10.1016/j.fusengdes.2026.115641","url":null,"abstract":"<div><div>Superconducting magnets in fusion devices are at the risk of quench during operation. Once quench occurs, the stored electromagnetic energy rapidly turns to Joule heat, potentially damaging the magnets severely. To protect these magnets, the Quench Protection System (QPS) employs high-power DC breaker to quickly interrupt the magnet current and transfer the quench energy, which relies on the LC circuit resonance to generate reverse pulsed current for creating a current zero-crossing point. This paper introduces the design and performance analysis of a high-current pulse inductor with toroidal helical structure. Its unique structure confines the magnetic field inside the coil, reducing interference and ensuring stability under pulse current. Targeting 20 μH inductance and 80 kA rated pulse current, the structural design of the inductor is performed firstly. Further, the Finite Element Method (FEM) is used to conduct a systematic simulation analysis of its electromagnetic, structural, and thermal performance. Finally, a prototype is also manufactured and subjected to LR parameter measurement and pulse high-current testing. Both simulation and test results show that the inductor has excellent magnetic confinement capability, outstanding structural stability, and reasonable temperature rise control ability.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"225 ","pages":"Article 115641"},"PeriodicalIF":2.0,"publicationDate":"2026-01-29","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"146079940","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 : 2026-01-29DOI: 10.1016/j.fusengdes.2026.115637
Yixuan He , Xiaofei Lu , Anyi Cheng , Qiyong Zhang , Yingqiu Zhu
Large-scale helium cryogenic systems are essential for sustaining the conditions of superconducting magnets in magnetically confined fusion devices, but their high energy demand remains a major challenge. The Auxiliary Cold Box (ACB), which connects helium refrigerators to cryogenic customers, typically consumes 30–50 % of the refrigeration capacity due to forced-flow cooling loops with subcooled helium. To evaluate potential improvements, three representative ACB process configurations are modeled and compared: (1) the Single-Bath Circulation Process, (2) the Dual-Bath Series Circulation Process, and (3) a proposed Dual-Bath Load Management Circulation Process. Their performance is assessed using Aspen HYSYS simulations with coefficient of performance (COP) evaluation and exergy analysis. Results show that, compared with the Dual-Bath Load Management process, the Single-Bath scheme requires 43 % more cold compressor power and 53 % higher heat exchanger exergy loss, while the Dual-Bath Series scheme requires 28 % more compressor power and 46 % higher exergy loss. These findings indicate that reducing heat-exchange temperature differences and alleviating the load on subcooled helium baths can substantially reduce energy consumption. This provides practical guidance for the design of efficient cryogenic subsystems in future fusion facilities.
{"title":"Thermodynamic process optimization of a forced flow cooling loops with subcooled helium for superconducting magnets based on exergy analysis","authors":"Yixuan He , Xiaofei Lu , Anyi Cheng , Qiyong Zhang , Yingqiu Zhu","doi":"10.1016/j.fusengdes.2026.115637","DOIUrl":"10.1016/j.fusengdes.2026.115637","url":null,"abstract":"<div><div>Large-scale helium cryogenic systems are essential for sustaining the conditions of superconducting magnets in magnetically confined fusion devices, but their high energy demand remains a major challenge. The Auxiliary Cold Box (ACB), which connects helium refrigerators to cryogenic customers, typically consumes 30–50 % of the refrigeration capacity due to forced-flow cooling loops with subcooled helium. To evaluate potential improvements, three representative ACB process configurations are modeled and compared: (1) the Single-Bath Circulation Process, (2) the Dual-Bath Series Circulation Process, and (3) a proposed Dual-Bath Load Management Circulation Process. Their performance is assessed using Aspen HYSYS simulations with coefficient of performance (COP) evaluation and exergy analysis. Results show that, compared with the Dual-Bath Load Management process, the Single-Bath scheme requires 43 % more cold compressor power and 53 % higher heat exchanger exergy loss, while the Dual-Bath Series scheme requires 28 % more compressor power and 46 % higher exergy loss. These findings indicate that reducing heat-exchange temperature differences and alleviating the load on subcooled helium baths can substantially reduce energy consumption. This provides practical guidance for the design of efficient cryogenic subsystems in future fusion facilities.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"225 ","pages":"Article 115637"},"PeriodicalIF":2.0,"publicationDate":"2026-01-29","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"146079944","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 : 2026-01-26DOI: 10.1016/j.fusengdes.2026.115640
Xin Zhang , Akihiro Shimizu , Takanori Murase , Yuhong Xu , Kazuki Nagahara , Sho Nakagawa , Hiroyuki Tanoue , Mamoru Shoji , Zilin Cui , Xiaolong Li , Huaqing Zheng , Kunihiro Ogawa , Hiromi Takahashi , Mitsutaka Isobe , Shoichi Okamura , Haifeng Liu , Xianqu Wang , Hai Liu , Jun Hu , Jun Cheng , Changjian Tang
The supersonic molecular beam injection (SMBI) technique has attracted considerable interest in magnetic confinement fusion because it offers an efficient fueling capability with relatively simple and economical hardware. As the key component of SMBI, the Laval nozzle largely determines the jet velocity, collimation, and thus the fueling performance. In this paper, we present an initial design of a Laval nozzle for the SMBI system on the Chinese First Quasi-axisymmetric Stellarator (CFQS). A reference gas flow rate for CFQS is estimated by scaling from well-diagnosed SMBI data from the Large Helical Device (LHD); the resulting value (∼12 Pa·m³/s) is used as an order-of-magnitude design input for nozzle sizing. To select a physically meaningful design Mach-number range, effective acceleration limits are discussed using a pressure-based criterion via the Knudsen number and a temperature-based criterion associated with hydrogen phase-change tendencies, and the clustering parameter is evaluated to quantify condensation/cluster-formation range under typical operating conditions. Using Foelsch’s method as an efficient analytical framework, the nozzle contour and key geometric parameters are obtained, and a baseline CFQS nozzle design is recommended (e.g., equal 7, is 5°, throat diameter 0.3 mm) considering both physical performance and engineering constraints, and an example engineering design diagram were presented. The present results provide a practical reference for the implementation and future optimization of the CFQS SMBI system.
{"title":"Initial design of a Laval nozzle for the supersonic molecular beam injection system on CFQS","authors":"Xin Zhang , Akihiro Shimizu , Takanori Murase , Yuhong Xu , Kazuki Nagahara , Sho Nakagawa , Hiroyuki Tanoue , Mamoru Shoji , Zilin Cui , Xiaolong Li , Huaqing Zheng , Kunihiro Ogawa , Hiromi Takahashi , Mitsutaka Isobe , Shoichi Okamura , Haifeng Liu , Xianqu Wang , Hai Liu , Jun Hu , Jun Cheng , Changjian Tang","doi":"10.1016/j.fusengdes.2026.115640","DOIUrl":"10.1016/j.fusengdes.2026.115640","url":null,"abstract":"<div><div>The supersonic molecular beam injection (SMBI) technique has attracted considerable interest in magnetic confinement fusion because it offers an efficient fueling capability with relatively simple and economical hardware. As the key component of SMBI, the Laval nozzle largely determines the jet velocity, collimation, and thus the fueling performance. In this paper, we present an initial design of a Laval nozzle for the SMBI system on the Chinese First Quasi-axisymmetric Stellarator (CFQS). A reference gas flow rate for CFQS is estimated by scaling from well-diagnosed SMBI data from the Large Helical Device (LHD); the resulting value (∼12 Pa·m³/s) is used as an order-of-magnitude design input for nozzle sizing. To select a physically meaningful design Mach-number range, effective acceleration limits are discussed using a pressure-based criterion via the Knudsen number and a temperature-based criterion associated with hydrogen phase-change tendencies, and the clustering parameter <span><math><msup><mrow><mstyle><mi>Γ</mi></mstyle></mrow><mo>*</mo></msup></math></span> is evaluated to quantify condensation/cluster-formation range under typical operating conditions. Using Foelsch’s method as an efficient analytical framework, the nozzle contour and key geometric parameters are obtained, and a baseline CFQS nozzle design is recommended (e.g., <span><math><msub><mi>M</mi><mi>t</mi></msub></math></span> equal 7, <span><math><msub><mi>θ</mi><mn>1</mn></msub></math></span> is 5°, throat diameter 0.3 mm) considering both physical performance and engineering constraints, and an example engineering design diagram were presented. The present results provide a practical reference for the implementation and future optimization of the CFQS SMBI system.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"225 ","pages":"Article 115640"},"PeriodicalIF":2.0,"publicationDate":"2026-01-26","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"146079945","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 : 2026-01-24DOI: 10.1016/j.fusengdes.2026.115632
Yi Yu , HouXiang Han
The Tail structure is a crucial component of high-temperature superconducting coils, providing both mechanical load transfer and reliable electrical connectivity between conductor leads. In this study, we designed and analyzed a Tail structure for a next-generation fully superconducting tokamak. We performed a coupled multi-physics analysis using finite element software to evaluate the mechanical performance of the proposed system under operational loads. The simulation revealed a maximum stress intensity of 1065.9 MPa, while linearized stress amplitudes remained within the allowable design limits, confirming adequate structural safety, and the minimum fatigue life of the structural components exceeds 127,000 cycles. We also developed and validated specialized welding fixtures through a series of welding experiments. All the welds successfully passed the quality inspections and met the technical specifications required for the procedure qualification, offering essential technical support for the construction of superconducting fusion devices.
{"title":"Mechanical analysis of tail structures in the next-generation fully superconducting tokamak CS HTS","authors":"Yi Yu , HouXiang Han","doi":"10.1016/j.fusengdes.2026.115632","DOIUrl":"10.1016/j.fusengdes.2026.115632","url":null,"abstract":"<div><div>The Tail structure is a crucial component of high-temperature superconducting coils, providing both mechanical load transfer and reliable electrical connectivity between conductor leads. In this study, we designed and analyzed a Tail structure for a next-generation fully superconducting tokamak. We performed a coupled multi-physics analysis using finite element software to evaluate the mechanical performance of the proposed system under operational loads. The simulation revealed a maximum stress intensity of 1065.9 MPa, while linearized stress amplitudes remained within the allowable design limits, confirming adequate structural safety, and the minimum fatigue life of the structural components exceeds 127,000 cycles. We also developed and validated specialized welding fixtures through a series of welding experiments. All the welds successfully passed the quality inspections and met the technical specifications required for the procedure qualification, offering essential technical support for the construction of superconducting fusion devices.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"225 ","pages":"Article 115632"},"PeriodicalIF":2.0,"publicationDate":"2026-01-24","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"146025383","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}
In-vessel diagnostic mirrors in fusion reactors are subjected to extreme thermal loads that can induce deformation and degrade optical performance. To address these challenges, this study investigates the application of powder-based Hot Isostatic Pressing (HIP) to fabricate complex internal cooling channels in the first mirror of the ITER divertor IR thermography system—a geometry not previously attempted using powder HIP. A prototype using gas-atomized stainless steel 316L powders was manufactured and HIP-processed at 1200°C for 4 hours. Dimensional changes were characterized through cross-sectional analysis and ultrasonic testing. Shrinkage rates were consistent, with pipe regions shrinking by 6-10%. The results demonstrate that powder HIP can reliably form integrated cooling channels, offering advantages in NDT (Non-destructive testing) and stress corrosion resistance. The method can also be applied to other diagnostic mirrors and in-vessel components with internal cooling channels in ITER and future fusion reactors.
{"title":"Application of powder HIP to the ITER IR thermography first mirror: Fabrication and evaluation of internal cooling channel deformation","authors":"Suguru TANAKA , Tomohiko USHIKI , Kimihiro IOKI , Hiroyuki TACHIBANA , Yoshihiko NUNOYA","doi":"10.1016/j.fusengdes.2026.115639","DOIUrl":"10.1016/j.fusengdes.2026.115639","url":null,"abstract":"<div><div>In-vessel diagnostic mirrors in fusion reactors are subjected to extreme thermal loads that can induce deformation and degrade optical performance. To address these challenges, this study investigates the application of powder-based Hot Isostatic Pressing (HIP) to fabricate complex internal cooling channels in the first mirror of the ITER divertor IR thermography system—a geometry not previously attempted using powder HIP. A prototype using gas-atomized stainless steel 316L powders was manufactured and HIP-processed at 1200°C for 4 hours. Dimensional changes were characterized through cross-sectional analysis and ultrasonic testing. Shrinkage rates were consistent, with pipe regions shrinking by 6-10%. The results demonstrate that powder HIP can reliably form integrated cooling channels, offering advantages in NDT (Non-destructive testing) and stress corrosion resistance. The method can also be applied to other diagnostic mirrors and in-vessel components with internal cooling channels in ITER and future fusion reactors.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"225 ","pages":"Article 115639"},"PeriodicalIF":2.0,"publicationDate":"2026-01-23","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"146025384","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 : 2026-01-23DOI: 10.1016/j.fusengdes.2026.115635
Chi Lei , Zhoujun Yang , Zhifeng Cheng , Nengchao Wang , Zezhi Yu , Zijian Xuan , Yan Guo , Siyu Zhu , J-TEXT Team
For magnetic confinement fusion, the measurement of hydrogen isotope ratios is of critical importance. It not only reflects the fuel ratio in future fusion reactors but also provides a quantitative analysis for investigating isotope effects on plasma confinement. In this paper, a spectral diagnostic system for measuring the ratio of hydrogen (H) and deuterium (D) at plasma edge has been developed on J-TEXT tokamak, based on the spectra of hydrogen isotope Balmer-alpha line radiation. To meet the requirement of spectra measurement for Hα (656.28 nm), Dα (656.10 nm) and Tα (656.04 nm), a high-resolution spectroscope with wavelength resolution of 0.0073 nm/pixel and time resolution of 5 ms is adopted for the diagnostic. An analysis module has been developed by employing a multi-parameter spectral shape-fitting algorithm and considering the Zeeman effect and Doppler broadening. The diagnostic has been applied in experiments, in which the H-D mixing ratio is affected by the wall conditions. The experimental results confirmed the excellent measurement ability of the high-resolution spectral diagnostic of the edge hydrogen isotope ratio developed for J-TEXT, which will provide the necessary H-D concentration information for the subsequent isotope experiments.
{"title":"Development of spectral diagnostic for edge hydrogen isotope ratio on J-TEXT","authors":"Chi Lei , Zhoujun Yang , Zhifeng Cheng , Nengchao Wang , Zezhi Yu , Zijian Xuan , Yan Guo , Siyu Zhu , J-TEXT Team","doi":"10.1016/j.fusengdes.2026.115635","DOIUrl":"10.1016/j.fusengdes.2026.115635","url":null,"abstract":"<div><div>For magnetic confinement fusion, the measurement of hydrogen isotope ratios is of critical importance. It not only reflects the fuel ratio in future fusion reactors but also provides a quantitative analysis for investigating isotope effects on plasma confinement. In this paper, a spectral diagnostic system for measuring the ratio of hydrogen (H) and deuterium (D) at plasma edge has been developed on J-TEXT tokamak, based on the spectra of hydrogen isotope Balmer-alpha line radiation. To meet the requirement of spectra measurement for Hα (656.28 nm), Dα (656.10 nm) and Tα (656.04 nm), a high-resolution spectroscope with wavelength resolution of 0.0073 nm/pixel and time resolution of 5 ms is adopted for the diagnostic. An analysis module has been developed by employing a multi-parameter spectral shape-fitting algorithm and considering the Zeeman effect and Doppler broadening. The diagnostic has been applied in experiments, in which the H-D mixing ratio is affected by the wall conditions. The experimental results confirmed the excellent measurement ability of the high-resolution spectral diagnostic of the edge hydrogen isotope ratio developed for J-TEXT, which will provide the necessary H-D concentration information for the subsequent isotope experiments.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"225 ","pages":"Article 115635"},"PeriodicalIF":2.0,"publicationDate":"2026-01-23","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"146025385","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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