{"title":"CO2-laser Interferometer on the Large Helical Device","authors":"Kenji Tanaka, Tsuyoshi Akiyama, Toshiki Kinoshita, Hikona Sakai, Yuki Takemura, Hikaru Okuwada, Akira Uritani, Clive Michael","doi":"10.1007/s10894-026-00570-2","DOIUrl":"10.1007/s10894-026-00570-2","url":null,"abstract":"<div><p>This study reports the development of <span>(hbox {CO}_2)</span> laser interferometers for electron density measurements on the large helical device (LHD). Two types of interferometers using approximately 10 <span>(mu m)</span> are developed. One is an imaging two-color laser interferometer (I-TCI) for measuring density profiles and macroscopic fluctuations of MHD instabilities, and the other is a single channel phase-modulated dispersion interferometer (PMDI) designed for reliable density monitoring. The diagnostic principles, systems, and analysis techniques are outlined, and representative measurement results are presented. The I-TCI system was also designed to operate in the deuterium experiments performed on LHD from 2017 until 2022. Shielding against neutron and <span>(gamma)</span>-ray irradiation was necessary to prevent damage to the I-TCI detection system. Design strategies for neutron and <span>(gamma)</span>-ray shielding are presented in the appendices.</p></div>","PeriodicalId":634,"journal":{"name":"Journal of Fusion Energy","volume":"45 1","pages":""},"PeriodicalIF":2.1,"publicationDate":"2026-05-05","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://link.springer.com/content/pdf/10.1007/s10894-026-00570-2.pdf","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"147829388","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"OA","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Gaoyuan Liu, Junge Li, Xihao Chu, Jingjing Wang, Bing Wang, Bo Wang
{"title":"Suppression of MHD Effects in Liquid Metals through Solid Insulation Particle Doping","authors":"Gaoyuan Liu, Junge Li, Xihao Chu, Jingjing Wang, Bing Wang, Bo Wang","doi":"10.1007/s10894-026-00575-x","DOIUrl":"10.1007/s10894-026-00575-x","url":null,"abstract":"<div><p>Suppressing the magnetohydrodynamic (MHD) effect in the liquid tritium breeder is key to ensuring the safe and stable operation of the tritium breeding blanket in a fusion reactor.To address this issue, this study proposes a novel strategy for regulating the MHD effect by doping with solid insulating particles.Based on the finite element method, a three-dimensional rectangular duct MHD model is constructed, in which solid insulating Al₂O₃ particles are assumed to be uniformly distributed in the liquid lithium-lead alloy and interact with the velocity field and the electromagnetic field.By varying the particle quantity and the applied magnetic field strength, the effects of particles on the velocity field, electric potential distribution, and MHD pressure drop are simulated and analyzed.The results show that the introduction of solid insulating particles significantly optimizes the flow characteristics.Under a magnetic field of 2 T, the velocity reduction after adding 128 alumina particles with a diameter of 5 mm is 24.7%, which is substantially smaller than the 64.7% reduction observed without particles.Meanwhile, the dimensionless MHD pressure drop is reduced by 37.4% upon particle doping. Mechanism analysis reveals that the particle-induced micro-Hall effect is the primary mechanism for MHD suppression.The particle doping strategy proposed in this study provides a new theoretical basis and technical pathway for the optimal design of liquid tritium breeder blankets.</p></div>","PeriodicalId":634,"journal":{"name":"Journal of Fusion Energy","volume":"45 1","pages":""},"PeriodicalIF":2.1,"publicationDate":"2026-04-29","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"147797083","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
{"title":"Mechanical Property Evaluation of CSMC Armour and Helium Inlet under Steady-State Operation","authors":"Xianewei Wang, Wenlong Xu, Haikuo Zhao, Aihua Xu, Houxiang Han, Wentao Xie","doi":"10.1007/s10894-026-00576-w","DOIUrl":"10.1007/s10894-026-00576-w","url":null,"abstract":"<div>\u0000 \u0000 <p>This study evaluates the mechanical safety of the armour and helium inlet in the CFETR Central Solenoid Model Coil (CSMC). The analysis considers multi-physics coupling fields during steady-state operation. We adopted an electromagnetic-structural indirect coupling method consistent with ASME analytical design criteria and ITER magnet design specifications. A simplified electromagnetic model was first established in ANSYS Maxwell. We then used a current filament mapping approach to transfer the electromagnetic forces to the structural model. Static structural analysis was performed to obtain the stress distribution under multi-field coupling. The results, evaluated through stress linearization, show that the Nb<sub>3</sub>Sn armour and helium inlet meet the safety margins required by ASME and ITER standards. The NbTi armour also satisfies the design requirements, provided its yield strength is increased through cold work hardening. The simulation results indicate that the current CSMC design is adequate under the condition of multi-field coupling at steady operation state. These findings provide a technical reference for the engineering of the CFETR CSMC and the design of cooling interfaces for Cable-in-Conduit Conductors (CICC) in large-scale superconducting magnets.</p>\u0000 </div>","PeriodicalId":634,"journal":{"name":"Journal of Fusion Energy","volume":"45 1","pages":""},"PeriodicalIF":2.1,"publicationDate":"2026-04-28","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"147796946","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Shu Ito, Kiyomasa Watanabe, Yuki Takemura, Satoru Sakakibara
{"title":"Resistive Interchange Instability Response to External RMP, and its Parameter Dependence to Suppress the Instability","authors":"Shu Ito, Kiyomasa Watanabe, Yuki Takemura, Satoru Sakakibara","doi":"10.1007/s10894-026-00574-y","DOIUrl":"10.1007/s10894-026-00574-y","url":null,"abstract":"<div>\u0000 \u0000 <p>We derive an empirical scaling law for the external RMP (Resonant Magnetic Perturbation) amplitude required to completely suppress the resistive interchange MHD instabilities of m/<i>n</i> = 1/1 (m and n are the poloidal and toroidal mode numbers, respectively), which are typically observed in the Large Helical Device (LHD). We also derive the scaling law for the penetration threshold of the external RMP. Both scaling laws are found to have a strong dependence on the beta value and the normalized Larmor radius at the resonant rational surface. On the dependence on the collision parameters, the scaling laws for the external RMP amplitude to suppress the instability and the RMP penetration threshold show an inverse dependence. The above scaling laws suggest that it is easier to completely suppress the resistive interchange instability of the m/<i>n</i> = 1/1 mode in the LHD without degrading the plasma confinement performance due to the RMP penetration with a lower collision frequency, even with the same beta discharges.</p>\u0000 </div>","PeriodicalId":634,"journal":{"name":"Journal of Fusion Energy","volume":"45 1","pages":""},"PeriodicalIF":2.1,"publicationDate":"2026-04-20","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://link.springer.com/content/pdf/10.1007/s10894-026-00574-y.pdf","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"147738329","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"OA","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
{"title":"MHD Stability Analysis of High-Beta LHD Plasmas by Kinetic-MHD Hybrid Simulations with Kinetic Thermal and Energetic Ions","authors":"Masahiko Sato, Yasushi Todo","doi":"10.1007/s10894-026-00572-0","DOIUrl":"10.1007/s10894-026-00572-0","url":null,"abstract":"<div>\u0000 \u0000 <p>This paper revisits and extends previous simulation studies of pressure-driven magnetohydrodynamic (MHD) stability in high-beta plasmas in the Large Helical Device (LHD). In the conventional MHD model, resistive ballooning modes become unstable at low magnetic Reynolds numbers, while ideal interchange modes become unstable at high magnetic Reynolds numbers. Although these instabilities are initially destabilized in the peripheral region, their nonlinear development causes their impact to extend into the core region, ultimately resulting in core collapse. In contrast, kinetic-MHD hybrid simulations that include kinetic thermal and energetic ions demonstrate that the instabilities remain confined to the peripheral region, allowing high-beta plasmas to be sustained in agreement with experimental observations. These findings highlight the critical role of kinetic ions in accurately modeling the stability and confinement of high-beta plasmas in three-dimensional magnetic configurations.</p>\u0000 </div>","PeriodicalId":634,"journal":{"name":"Journal of Fusion Energy","volume":"45 1","pages":""},"PeriodicalIF":2.1,"publicationDate":"2026-04-18","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://link.springer.com/content/pdf/10.1007/s10894-026-00572-0.pdf","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"147737972","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"OA","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
{"title":"Experiments on Physics Issues in Burning Plasma: Isotope Mixing and Ion Collisionless Energy Transfer","authors":"Katsumi Ida, Mikirou Yoshinuma, Tatsuya Kobayashi, Kenichi Nagaoka, Kunihiro Ogawa, Tokihiko Tokuzawa, Hideo Nuga, Yuto Katoh, Motoki Nakata, Kenji Tanaka, Ryuichi Sakamoto, Gen Motojima, Suguru Masuzaki, Kotaro Yamasaki, Yutaka Fujiwara","doi":"10.1007/s10894-026-00573-z","DOIUrl":"10.1007/s10894-026-00573-z","url":null,"abstract":"<div>\u0000 \u0000 <p>Experiments on physics issues in burning plasma were conducted in the deuterium campaign of Large Helical Devices (LHD). One is an isotope mixing experiment, and the other is the collisionless energy transfer from energetic particles to bulk ions. The important finding for ion mixing in the LHD experiment is that the ITG turbulence (but not TEM turbulence) contributes to the isotope and ion mixing, which is beneficial for controlling the isotope ratio (deuterium and tritium) and helium ash exhaust. The experimental identification of energy transfer from energetic particles to bulk ions through Landau damping and transit-time damping suggests a possible ion-heating process for the ion-ITB plasma with (<span>(T_i/T_e> 1)</span>) through collisionless energy transfer from alpha particles to bulk ions through energetic particle-driven instability, so-called alpha channeling.</p>\u0000 </div>","PeriodicalId":634,"journal":{"name":"Journal of Fusion Energy","volume":"45 1","pages":""},"PeriodicalIF":2.1,"publicationDate":"2026-04-17","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://link.springer.com/content/pdf/10.1007/s10894-026-00573-z.pdf","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"147738224","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"OA","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
H. Takahashi, K. Nagaoka, M. Osakabe, H. Nakano, K. Mukai, T. Kobayashi, S. Murakami, M. Yokoyama, K. Tanaka, M. Yoshinuma, K. Ida, M. Kobayashi, G. Motojima, R. Seki, F. Warmer, Y. Yoshimura, M. Nakata, H. Yamaguchi, F. Nespoli, S. Masuzaki, H. Igami, R. Yanai, N. Kenmochi, T. Ii. Tsujimura, S. Kubo, T. Seki, K. Saito, H. Kasahara, S. Kamio, Y. Fujiwara, T. Oishi, Y. Kawamoto, M. Goto, I. Yamada, H. Funaba, A. Shimizu, T. Ido, T. Tokuzawa, N. B. Marushchenko, Y. Turkin, T. Morisaki
{"title":"Progress in Extending the High-Temperature Plasma Regime in the LHD","authors":"H. Takahashi, K. Nagaoka, M. Osakabe, H. Nakano, K. Mukai, T. Kobayashi, S. Murakami, M. Yokoyama, K. Tanaka, M. Yoshinuma, K. Ida, M. Kobayashi, G. Motojima, R. Seki, F. Warmer, Y. Yoshimura, M. Nakata, H. Yamaguchi, F. Nespoli, S. Masuzaki, H. Igami, R. Yanai, N. Kenmochi, T. Ii. Tsujimura, S. Kubo, T. Seki, K. Saito, H. Kasahara, S. Kamio, Y. Fujiwara, T. Oishi, Y. Kawamoto, M. Goto, I. Yamada, H. Funaba, A. Shimizu, T. Ido, T. Tokuzawa, N. B. Marushchenko, Y. Turkin, T. Morisaki","doi":"10.1007/s10894-026-00571-1","DOIUrl":"10.1007/s10894-026-00571-1","url":null,"abstract":"<div>\u0000 \u0000 <p>In this paper, we show the expansion of the high-temperature regime and related physical phenomena in the Large Helical Device (LHD). At the LHD, we have developed a high-temperature operational regime for both ion (<i>T</i><sub>i</sub>) and electron (<i>T</i><sub>e</sub>) temperatures through understanding the physical characteristics of high-temperature plasma, the enhancement of plasma heating, and the development of technical methods such as wall recycling control and impurity control. In particular, the formation of the ion internal transport barrier (i-ITB) and electron internal transport barrier (e-ITB) in the plasma core region is the key to improving plasma performance. In addition, the deuterium experiment that began in 2017 showed that, due to the isotope effect, the thermal transport of both ions and electrons is suppressed in deuterium plasma compared to light hydrogen plasma, and that a high central temperature can be achieved efficiently. Furthermore, the combination of neutral beam injection (NBI) and electron cyclotron heating (ECH) has extended the operating conditions that simultaneously maintain high <i>T</i><sub>i</sub> and <i>T</i><sub>e</sub>, and comprehensive research on plasma confinement characteristics with an eye to future fusion reactor conditions has progressed.</p>\u0000 </div>","PeriodicalId":634,"journal":{"name":"Journal of Fusion Energy","volume":"45 1","pages":""},"PeriodicalIF":2.1,"publicationDate":"2026-04-06","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://link.springer.com/content/pdf/10.1007/s10894-026-00571-1.pdf","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"147642459","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"OA","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Y. Narushima, Y. Takemura, S. Sakakibara, K. Y. Watanabe
{"title":"Dynamics of Magnetic Island and its Effect on Equilibrium in LHD Plasmas","authors":"Y. Narushima, Y. Takemura, S. Sakakibara, K. Y. Watanabe","doi":"10.1007/s10894-026-00569-9","DOIUrl":"10.1007/s10894-026-00569-9","url":null,"abstract":"<div>\u0000 \u0000 <p>The dynamics of magnetic islands in a magnetohydrodynamic equilibrium configuration of the Large Helical Device (LHD) are intriguing due to significant variations in their behaviour. When an externally perturbed magnetic field is applied to the configuration, plasma flow effects play a crucial role in modifying the shape of the magnetic islands. The response of these islands depends critically on the interplay between plasma viscosity and poloidal flow. Under certain conditions, magnetic islands either heal or grow spontaneously. Additionally, intermediate states are observed under specific conditions. The identification of these intermediate states fundamentally challenges the traditional understanding of magnetic island dynamics, which primarily focuses on binary outcomes. These intermediate states result from a delicate balance between electromagnetic and viscous torques, revealing a sophisticated mechanism underlying magnetic island behaviour. Investigating the isotopic effects on magnetic island behaviour based on these findings, we discovered that the boundary between magnetic island growth and healing differs for hydrogen (H) and deuterium (D) plasmas. Specifically, magnetic islands in D-plasma require higher beta values for healing and exhibit a significantly broader region of intermediate states compared to H-plasma, emphasizing the important role of the isotope effects in magnetic island behaviour. Furthermore, during detachment transitions, the growth and healing tendencies of magnetic islands show a clear correlation with the transition process, providing valuable insights into the interplay between external perturbation fields and plasma equilibrium. These findings offer critical insights into the physics of magnetic islands in helical plasmas, establishing a foundation for future advances in nuclear fusion research.</p>\u0000 </div>","PeriodicalId":634,"journal":{"name":"Journal of Fusion Energy","volume":"45 1","pages":""},"PeriodicalIF":2.1,"publicationDate":"2026-04-03","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://link.springer.com/content/pdf/10.1007/s10894-026-00569-9.pdf","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"147606592","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"OA","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Zhiqiang Cui, Zhengxiang Xu, Xiong Wu, Chen Zhang, Yueming Zhu, Yonghong Liu, Y. C. Francis Thio
{"title":"Nuclear Analysis of the DCLL Blanket for a Plasma-Jet-Driven Magneto-Inertial Fusion Reactor","authors":"Zhiqiang Cui, Zhengxiang Xu, Xiong Wu, Chen Zhang, Yueming Zhu, Yonghong Liu, Y. C. Francis Thio","doi":"10.1007/s10894-026-00567-x","DOIUrl":"10.1007/s10894-026-00567-x","url":null,"abstract":"<div><p>This study presents a conceptual design of a 200 MW plasma-jet-driven magneto-inertial fusion (PJMIF) reactor blanket, referring to fusion reactor technologies. The blanket employs a dual-coolant structure consisting of supercritical CO<sub>2</sub> and Li<sub>17</sub>Pb<sub>83</sub> liquid blanket. This paper is the first neutronics and nuclear thermal study of a dual-coolant lead-lithium (DCLL) blanket for a PJMIF reactor. A complete nuclear analysis of the DCLL is carried out with the TopMC Monte Carlo transport and activation code. Transient coupled models are established to calculate the temperature distribution and variations with the blanket. Key objectives include: (1) determining optimized geometric parameters, including LiPb/steel thickness and radial build; (2) quantifying nuclear heating distributions and peak power density; (3) assessing tritium breeding ratio (TBR) using LiPb enrichment sensitivity; and (4) evaluating radiation damage in the spherical first wall and plasma gun. This study summarizes the distribution pattern of DPA in the inner electrode during the normal operation of the reactor, providing data for assessing the plasma gun’s lifespan. The research findings indicate that the nuclear thermal coupling model can complete preliminary calculations and analysis. It is found that both tritium production and energy export from the blanket are influenced by the reactor cavity and the breeding zone size. Under the 200 MW operating conditions, it shows that a 3.8 m radius and a 65 cm breeding zone size best meet the requirements.</p></div>","PeriodicalId":634,"journal":{"name":"Journal of Fusion Energy","volume":"45 1","pages":""},"PeriodicalIF":2.1,"publicationDate":"2026-04-03","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"147606539","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
S. Kaldas, R. Rossi, I. Wyss, M. Gelfusa, P. Gaudio
{"title":"Developing Autoencoder Models for Multi-Diagnostic Electron Density Processing in Tokamaks within a Scientific Machine Learning Framework","authors":"S. Kaldas, R. Rossi, I. Wyss, M. Gelfusa, P. Gaudio","doi":"10.1007/s10894-026-00568-w","DOIUrl":"10.1007/s10894-026-00568-w","url":null,"abstract":"<div>\u0000 \u0000 <p>Accurate reconstruction of plasma measurements is crucial for real-time control in magnetic confinement fusion devices. Diagnostic systems in these devices provide essential insights for physics studies and operational safety, yet they face a harsh environment where strong magnetic fields, radiation and neutron flux often degrade data quality. Noise, outliers and sensor faults make real-time processing a major challenge, traditionally requiring ad-hoc algorithms for each diagnostic. In this work, we present a multi-diagnostic integration approach based on autoencoders within a Scientific Machine Learning framework, used to process electron density measurements, as one of the most critical parameters to maintain under control during operations. By combining complementary measurements, such as Thomson Scattering, interferometry and polarimetry measurements, our method learns correlations across diagnostics, improving accuracy and resilience to faulty data. We investigate unsupervised and supervised autoencoder configurations, using synthetic tokamak scenarios generated in a virtual environment. An increasing level of multi-diagnostic integration shows a reduction in reconstruction errors, and, beyond accuracy, the proposed methodology enables fast inference suitable for real-time control. This approach enables robust reconstruction of key plasma parameters, supporting advanced control strategies in present tokamaks and informing the design of intelligent diagnostic systems for next-generation devices.</p>\u0000 </div>","PeriodicalId":634,"journal":{"name":"Journal of Fusion Energy","volume":"45 1","pages":""},"PeriodicalIF":2.1,"publicationDate":"2026-03-30","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://link.springer.com/content/pdf/10.1007/s10894-026-00568-w.pdf","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"147606979","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"OA","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}