Fusion Engineering and Design最新文献

{"title":"An optimal flange assembly pose evaluation method based on the PSO-HPO algorithm","authors":"Xin Song,&nbsp;Dong Gao,&nbsp;Zhiqi Wang,&nbsp;Junran Liang,&nbsp;Congsheng Feng","doi":"10.1016/j.fusengdes.2026.115663","DOIUrl":"10.1016/j.fusengdes.2026.115663","url":null,"abstract":"<div><div>The assembly accuracy of flanges mounted on the spherical shell holes directly affects the overall assembly quality and performance in laser inertial confinement fusion (LICF) systems. In the flange assembly process, manufacturing errors in both the flange mounting holes and the flange body make it difficult to accurately evaluate the optimal assembly pose of flanges. To solve this problem, this study proposes an evaluation method for determining the optimal flange assembly. In this method, a pose evaluation model of flange assembly is developed, and the regulation mechanism derived from the Hunter Prey Optimization (HPO) algorithm is integrated into the Particle Swarm Optimization (PSO) framework. The objective is to minimize alignment deviations and determine the optimal flange assembly pose. First, key measurement points (MPs) on both the flange mounting holes and the flange surface are acquired to characterize the manufacturing errors and determine the actual initial pose of the flange. Based on these identified deviations and the assembly accuracy requirements, a set of assembly constraints is formulated. A pose evaluation model is then constructed, aiming to minimize the overall assembly error under these constraints. Subsequently, the proposed PSO<img>HPO algorithm is used to determine the optimal pose parameters of the flange. Finally, a simulation case of flange pose adjustment demonstrates that the proposed algorithm substantially outperforms the singular value decomposition(SVD) and conventional PSO algorithm in terms of pose estimation accuracy. Specifically, the proposed method reduces the flange’s collinearity error by 78.86 % and coplanar error by 58.66 %. All constraint errors derived from the pose evaluation model are within the prescribed design tolerances, thereby ensuring higher assembly precision.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"225 ","pages":"Article 115663"},"PeriodicalIF":2.0,"publicationDate":"2026-04-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"146174229","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Improving control integration in Plasma Control System with an XML-based model-driven approach","authors":"Z.M. Huang ,&nbsp;Q.P. Yuan ,&nbsp;R.R. Zhang ,&nbsp;W.H. Ma ,&nbsp;J.J. Huang ,&nbsp;J.Q. Zhu ,&nbsp;X.X. Li ,&nbsp;W.Y. Rui ,&nbsp;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":"2026-04-01","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}

{"title":"Application of powder HIP to the ITER IR thermography first mirror: Fabrication and evaluation of internal cooling channel deformation","authors":"Suguru TANAKA ,&nbsp;Tomohiko USHIKI ,&nbsp;Kimihiro IOKI ,&nbsp;Hiroyuki TACHIBANA ,&nbsp;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":"2026-04-01","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}

{"title":"Frequency characteristics of the liquid Li target flow surface in A-FNS","authors":"Shunsuke Kenjo ,&nbsp;Yoshiyuki Tsuji ,&nbsp;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":"2026-04-01","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}

{"title":"Preliminary neutronic and thermal analysis of Inertial Fusion Energy systems with a focus on thick liquid wall concepts","authors":"Nahom Habtemariam ,&nbsp;Eric Cervi ,&nbsp;Robert Earley ,&nbsp;Kirk Flippo ,&nbsp;Travis Hallam ,&nbsp;Susana Reyes ,&nbsp;Carlo Fiorina","doi":"10.1016/j.fusengdes.2026.115659","DOIUrl":"10.1016/j.fusengdes.2026.115659","url":null,"abstract":"<div><div>This paper provides an assessment of the neutronic behavior of Inertial Fusion Energy systems using the Serpent 2 Monte Carlo code. The study explores different types of reactor concepts, including dry-wall and thick liquid wall systems. In particular, it characterizes the tritium breeding and energy multiplication performance, as well as the effect of long-term irradiation on structural materials. For this purpose, the displacement per atom (DPA) and the gas production rate in structural materials are calculated. A simplified geometry with varying geometrical parameters is used as a representation for the different kinds of devices. Additionally, the case of the HYLIFE-II concept is used to assess modeling inaccuracies arising from certain approximations. A comparison between the simplified geometry and a realistic one is performed, thanks to Serpent’s capability to run transport calculations on unstructured meshes. The study then addresses the impact of these discrepancies on the temperature distribution in the first wall using the GeN-Foam code for conjugate heat transfer analysis. The results highlight the necessity to consider the heterogeneous nature of the liquid wall, as simplified models tend to underestimate radiation damage metrics and heat loads.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"225 ","pages":"Article 115659"},"PeriodicalIF":2.0,"publicationDate":"2026-04-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"146173795","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Tritium depth distribution measurement by using chemical etching and surface washing technique for structural material of the ICF target chamber","authors":"Jingquan Xia ,&nbsp;Zhilin Chen ,&nbsp;Yang Yang ,&nbsp;Zhu An","doi":"10.1016/j.fusengdes.2026.115634","DOIUrl":"10.1016/j.fusengdes.2026.115634","url":null,"abstract":"<div><div>The tritium depth distribution in the structural material (i.e., the 5083 aluminum alloy (Al5083)) of the inertial confinement fusion (ICF) target chamber is a key basis for evaluating radiation protection and environmental hazards. Given the characteristic of shallow tritium ion implantation depth in the Al5083, this study aimed to establish a high-resolution measurement method. A method for measuring the tritium depth distribution in Al5083 was established by coupling the ZnCl₂ surface washing (SW) method and the layer-by-layer chemical etching (LLCE) method. Firstly, the effects of etchant type, acid-to-water ratio, temperature, and etching period on measurement resolution in the LLCE method were systematically investigated, and the depth resolution was controlled within 30–50 nm, meeting the requirement for high-resolution measurement of shallowly implanted tritium. Secondly, the reliability of two correction methods for liquid scintillation counting (LSC) measurement of tritium-containing zinc solution was verified using the internal standard method. It was confirmed that the SW method can accurately separate and quantitatively determine the total amount of surface-adsorbed tritium in the Al5083, providing a key method to distinguish between surface-adsorbed tritium and bulk-retained tritium. Experiments on tritium-loaded Al5083 sample by implantation with an average incident energy of 7.5 keV and a fluence of 4.5 × 10¹² ions/cm² showed that the surface-adsorbed tritium accounts for 1.8% of the total tritium amount with a high concentration (∼10⁸ Bq/cm³), and 80% of the tritium in the bulk is distributed within 200 nm of the surface. The standardized measurement method established in this study provides reliable technical support for evaluating the retention and migration of tritium in the structural material of the ICF device.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"225 ","pages":"Article 115634"},"PeriodicalIF":2.0,"publicationDate":"2026-04-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"146025284","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Development of 3D simulation demonstration platform for tritium safety confinement of China fusion engineering test reactor","authors":"Haixia Wang ,&nbsp;Xuewei Fu ,&nbsp;Zihui Yang ,&nbsp;Qianchao Huo ,&nbsp;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&amp;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":"2026-04-01","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}

{"title":"Thermodynamic process optimization of a forced flow cooling loops with subcooled helium for superconducting magnets based on exergy analysis","authors":"Yixuan He ,&nbsp;Xiaofei Lu ,&nbsp;Anyi Cheng ,&nbsp;Qiyong Zhang ,&nbsp;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":"2026-04-01","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}

{"title":"Proximal probe thermal desorption mass spectrometry for mapping lateral hydrogen isotope retention in metals","authors":"Qin Lei ,&nbsp;Qiannan Yu ,&nbsp;Jiaguan Peng ,&nbsp;Yiwen Sun ,&nbsp;Mengqi Zhang ,&nbsp;Hanfeng Song ,&nbsp;Hao Yin ,&nbsp;Xiaolu Xiong ,&nbsp;Sijie Hao ,&nbsp;Yuhao Li ,&nbsp;Xiuli Zhu ,&nbsp;Lu Sun ,&nbsp;Long Cheng ,&nbsp;Yue Yuan ,&nbsp;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^–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 <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":"2026-04-01","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}

{"title":"Initial design of a Laval nozzle for the supersonic molecular beam injection system on CFQS","authors":"Xin Zhang ,&nbsp;Akihiro Shimizu ,&nbsp;Takanori Murase ,&nbsp;Yuhong Xu ,&nbsp;Kazuki Nagahara ,&nbsp;Sho Nakagawa ,&nbsp;Hiroyuki Tanoue ,&nbsp;Mamoru Shoji ,&nbsp;Zilin Cui ,&nbsp;Xiaolong Li ,&nbsp;Huaqing Zheng ,&nbsp;Kunihiro Ogawa ,&nbsp;Hiromi Takahashi ,&nbsp;Mitsutaka Isobe ,&nbsp;Shoichi Okamura ,&nbsp;Haifeng Liu ,&nbsp;Xianqu Wang ,&nbsp;Hai Liu ,&nbsp;Jun Hu ,&nbsp;Jun Cheng ,&nbsp;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":"2026-04-01","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}