Journal of Fusion Energy最新文献

Data-Driven Prediction of Tritium Transport Parameters for Fusion Reactor Fuel Cycle Modeling 聚变反应堆燃料循环建模中氚输运参数的数据驱动预测

IF 2.3 4区工程技术

Journal of Fusion Energy Pub Date : 2026-10-14 DOI: 10.1007/s10894-026-00606-7

Minxiang Shu, Wenxiang Jiang, Shenghan Cheng, Yu Li, Yang Yang, Zhilin Chen

{"title":"Data-Driven Prediction of Tritium Transport Parameters for Fusion Reactor Fuel Cycle Modeling","authors":"Minxiang Shu, Wenxiang Jiang, Shenghan Cheng, Yu Li, Yang Yang, Zhilin Chen","doi":"10.1007/s10894-026-00606-7","DOIUrl":"10.1007/s10894-026-00606-7","url":null,"abstract":"<div><p>Accurate tritium transport predictions are critical for fuel cycle optimization, tritium inventory control, and safety assessment in magnetic confinement fusion devices such as ITER and future DEMO reactors. However, inverse identification of diffusion and trapping parameters from experimental release measurements is often ill-posed due to sparse data, limited temperature coverage, or uncertain trapping characteristics. Here, we develop a data-driven inverse modeling framework based on deep neural networks (DNNs) to infer key parameters governing one-dimensional tritium transport in solids described by the McNabb-Foster diffusion-trapping model. Physically consistent synthetic datasets are generated by numerically solving coupled diffusion-trapping equations over a broad parameter space. Cumulative tritium release at multiple temperatures serves as the network input. Two prediction scenarios are examined: (i) known trapping parameters and (ii) unknown trapping parameters. In both cases, the DNNs accurately predict the diffusion pre-factor and activation energy, achieving average relative errors below 3.5%. Model interpretability is assessed using SHAP (SHapley Additive exPlanations) analysis, indicating that inversion is predominantly governed by high-temperature release behavior. The resulting transport parameters can provide physically informed inputs for fusion reactor fuel cycle simulations, enabling improved estimates of tritium retention, recycling, and plasma fueling efficiency. This work demonstrates a robust and efficient methodology for integrating experimentally accessible release data into reactor-scale tritium inventory assessments.</p></div>","PeriodicalId":634,"journal":{"name":"Journal of Fusion Energy","volume":"45 2","pages":""},"PeriodicalIF":2.3,"publicationDate":"2026-10-14","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"149189274","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}

引用次数: 0

Triton Burnup Detector in Large Helical Device 大型螺旋装置中的Triton燃耗探测器

IF 2.3 4区工程技术

Journal of Fusion Energy Pub Date : 2026-10-13 DOI: 10.1007/s10894-026-00603-w

Kunihiro Ogawa, Eiji Takada, Siriyaporn Sangaroon, LongYong Liao, Mitsutaka Isobe

引用次数: 0

Lithium Experimental Application Platform (LEAP) Part 1: Secondary-Containment Architecture and Downselection Framework for Flowing Liquid Lithium Fusion Systems 锂实验应用平台（LEAP）第1部分：流动液态锂聚变系统的二次安全壳结构和下行选择框架

IF 2.3 4区工程技术

Journal of Fusion Energy Pub Date : 2026-10-12 DOI: 10.1007/s10894-026-00602-x

Yufan Xu, Yoichi Momozaki, Michael Hvasta, Robert Kaita, Egemen Kolemen

{"title":"Lithium Experimental Application Platform (LEAP) Part 1: Secondary-Containment Architecture and Downselection Framework for Flowing Liquid Lithium Fusion Systems","authors":"Yufan Xu, Yoichi Momozaki, Michael Hvasta, Robert Kaita, Egemen Kolemen","doi":"10.1007/s10894-026-00602-x","DOIUrl":"10.1007/s10894-026-00602-x","url":null,"abstract":"<div><p>Plasma-facing components (PFCs) that incorporate flowing liquid lithium surfaces are a promising technology because they can provide a renewable interface, modify recycling, support power exhaust, and potentially connect PFCs with fuel recovery. The deployment of liquid lithium PFC technology, however, is constrained by lithium’s chemical reactivity, fire and aerosol hazards and the need for rapid experimental iteration. The Lithium Experimental Application Platform (LEAP), currently under construction at Princeton Plasma Physics Laboratory, is being developed to test liquid lithium PFCs and their integration with fusion devices. This paper is Part 1 of a two-part study and presents a hazard-complexity metric for selecting secondary-containment architectures for flowing liquid-lithium systems. The metric is used to compare six representative containment scenarios. Based on this analysis, LEAP uses a modular, room-sized argon glovebox as an inert secondary containment boundary for a staged flowing lithium program incorporating heating, diagnostics, magnetic field exposure, and future integration with fusion devices. The analysis indicates that an inert, airtight secondary enclosure without scrubbers around an enclosed lithium loop provides a practical balance between hazard reduction and facility complexity for the present LEAP design requirements. This architecture offers a practical approach to lithium PFC development and design principles applicable to other reactive or conductive liquid metal systems. Part 2 will address the design and engineering analysis of the LEAP lithium loop.</p></div>","PeriodicalId":634,"journal":{"name":"Journal of Fusion Energy","volume":"45 2","pages":""},"PeriodicalIF":2.3,"publicationDate":"2026-10-12","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"149189232","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}

引用次数: 0

Machine-Learning-Assisted Evaluation of the (^{241})Am(n,f) Cross Section in the 0.1–20 MeV Neutron Energy Range 0.1 - 20mev中子能量范围内(^{241}) Am（n,f）截面的机器学习辅助评价

IF 2.3 4区工程技术

Journal of Fusion Energy Pub Date : 2026-10-05 DOI: 10.1007/s10894-026-00601-y

Naima Amrani, Sihem Berbache, Sadiye M. Çakmak, Abdullah Aydin, Serkan Akkoyun

{"title":"Machine-Learning-Assisted Evaluation of the (^{241})Am(n,f) Cross Section in the 0.1–20 MeV Neutron Energy Range","authors":"Naima Amrani, Sihem Berbache, Sadiye M. Çakmak, Abdullah Aydin, Serkan Akkoyun","doi":"10.1007/s10894-026-00601-y","DOIUrl":"10.1007/s10894-026-00601-y","url":null,"abstract":"<div><p>Reliable <span>(^{241}textrm{Am}(n,f))</span> cross sections are essential for reactor design, transmutation performance, and nuclear data evaluation, yet significant discrepancies persist among experimental datasets, evaluated libraries, and theoretical models. This work provides a systematic assessment of the <span>(^{241}textrm{Am})</span> fission cross section in the fast-energy range by integrating EXFOR measurements, TALYS-2.0 calculations using five fission barrier formulations, evaluated libraries (ENDF/B-VIII.0 and TENDL-2019), and machine-learning-based predictions. A physically informed feature set including separation energies, deformation parameters, and fission barrier characteristics was used to train six regression models: CatBoost, Gradient Boosting Machine, Random Forest, Support Vector Regression, k-Nearest Neighbours, and XGBoost. GBM delivered the highest predictive accuracy and generalization, closely reproducing the experimental excitation function up to 20 MeV. TALYS results showed strong sensitivity to the barrier model. Comparative analysis demonstrates that advanced machine learning approaches can reduce high energy uncertainties and complement reaction model calculations. The findings highlight the value of data driven methodologies for improving nuclear data related to long-lived minor actinides and for supporting next generation fuel cycle and transmutation applications.</p></div>","PeriodicalId":634,"journal":{"name":"Journal of Fusion Energy","volume":"45 2","pages":""},"PeriodicalIF":2.3,"publicationDate":"2026-10-05","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"149132360","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}

引用次数: 0

Mechanical Analysis of Helium Inlet and Outlet Structures in the Central Solenoid of the Next-Generation Fully Superconducting Tokamak 新一代全超导托卡马克中央螺线管氦进出口结构的力学分析

IF 2.3 4区工程技术

Journal of Fusion Energy Pub Date : 2026-09-27 DOI: 10.1007/s10894-026-00600-z

Yi Yu, Houxiang Han, Yongsheng Wu, Huan Jin

引用次数: 0

Whole Plant Design, Integration, and Build 整个工厂的设计、集成和建造

IF 2.3 4区工程技术

Journal of Fusion Energy Pub Date : 2026-09-23 DOI: 10.1007/s10894-026-00598-4

J. Morris

引用次数: 0

Preliminary Thermal-hydraulic Analysis of Subcritical Fission Zone for Conceptual Test Blanket Module Driven by Fusion Neutrons 聚变中子驱动概念试验包层模块亚临界裂变区的初步热水力分析

IF 2.3 4区工程技术

Journal of Fusion Energy Pub Date : 2026-09-08 DOI: 10.1007/s10894-026-00599-3

Francesco Devia, Fabio Panza, Guglielmo Lomonaco, Seyed Kamal Mousavibalgehshiri

{"title":"Preliminary Thermal-hydraulic Analysis of Subcritical Fission Zone for Conceptual Test Blanket Module Driven by Fusion Neutrons","authors":"Francesco Devia, Fabio Panza, Guglielmo Lomonaco, Seyed Kamal Mousavibalgehshiri","doi":"10.1007/s10894-026-00599-3","DOIUrl":"10.1007/s10894-026-00599-3","url":null,"abstract":"<div><p>Developing fusion-fission hybrid systems offers a promising pathway to address critical challenges in energy generation and nuclear waste management. This study focuses on the thermal-hydraulic evaluation of a simplified Test Blanket Module (TBM) designed as a subcritical reactor driven by fusion neutrons. The primary objective is to assess the thermal and fluid dynamic performance of the module under steady-state conditions. The TBM is modelled as a subcritical assembly loaded with MOX fuel. Fast neutrons generated by a Reversed Field Pinch (RFP) provide adequate neutron flux to sustain fission reactions within the TBM. In the present study, the fluid dynamics analysis of the molten salt coolant flow, here a mixture of NaF and ZrF<sub>4</sub>, in a fission blanket coupled to the RFX-mod2 Reversed Field Pinch (RFP) device is carried out. Thermophysical properties of the molten salt composition are considered for temperature conditions between 500 and 900 °C. The current CFD model uses BOL fresh fuel thermophysical characteristics. The burnup value of 40 MWd/kg<sub>HM</sub> is considered a desired operational state for future depletion and EOL analyses, however burnup-dependent fuel property degradation is not explicitly accounted for in the current preliminary thermal-hydraulic calculation. Fuel compatibility is well maintained with AISI-316 steel cladding and coolant. To specify its thermal-hydraulic behaviour during normal operational conditions, the simulation has been conducted by the ANSYS-Fluent computational fluid dynamics code. Main assumptions and outcomes of this study are presented and critically discussed. The analysis results indicate that the temperature and power distribution within the module are within acceptable limits, and all components demonstrate good compatibility.</p></div>","PeriodicalId":634,"journal":{"name":"Journal of Fusion Energy","volume":"45 2","pages":""},"PeriodicalIF":2.3,"publicationDate":"2026-09-08","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"148926746","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}

引用次数: 0

Establishing a Coherent Qualification Pathway for Fusion Technologies 建立一个连贯的融合技术资格认证途径

IF 2.3 4区工程技术

Journal of Fusion Energy Pub Date : 2026-08-21 DOI: 10.1007/s10894-026-00597-5

Amanda Louise Allison

引用次数: 0

Development and Application of Collective Thomson Scattering Diagnostics for Energetic and Bulk Ion Measurements in the Large Helical Device 集体汤姆逊散射诊断在大型螺旋装置中高能和体离子测量中的发展和应用

IF 2.3 4区工程技术

Journal of Fusion Energy Pub Date : 2026-08-07 DOI: 10.1007/s10894-026-00595-7

Masaki Nishiura, Yuusuke Yamaguchi, Shin Kubo, Kenji Tanaka, Naoki Kenmochi, Ryoma Yanai, Ryosuke Seki, Hideo Nuga, Takashi Shimozuma, Yoshinori Tatematsu, Teruo Saito, Søren Bang Korsholm, Mirko Salewski, Dmitry Moseev

{"title":"Development and Application of Collective Thomson Scattering Diagnostics for Energetic and Bulk Ion Measurements in the Large Helical Device","authors":"Masaki Nishiura, Yuusuke Yamaguchi, Shin Kubo, Kenji Tanaka, Naoki Kenmochi, Ryoma Yanai, Ryosuke Seki, Hideo Nuga, Takashi Shimozuma, Yoshinori Tatematsu, Teruo Saito, Søren Bang Korsholm, Mirko Salewski, Dmitry Moseev","doi":"10.1007/s10894-026-00595-7","DOIUrl":"10.1007/s10894-026-00595-7","url":null,"abstract":"<div><p>To diagnose energetic and bulk ions in fusion plasmas, we have developed a millimeter-wave collective Thomson scattering (CTS) diagnostic system utilizing a megawatt-class gyrotron, originally designed for electron cyclotron heating (ECH), in the Large Helical Device (LHD). This paper presents CTS measurements of energetic and anisotropic ions produced by neutral beam injection (NBI), along with a method for analyzing CTS spectra. In addition, we report on the development of a 303 GHz gyrotron intended for CTS diagnostics, which enables lower background radiation levels and improved signal-to-noise ratio (SNR) in the detection of scattered signals.which is expected to reduce background radiation and improve the signal-to-noise ratio in CTS measurements. Furthermore, a high-performance notch filter has been developed to block stray radiation from the gyrotron beam within the vacuum vessel, preventing it from entering the receiver as noise. This type of notch filter is employed not only in CTS measurements but also in electron cyclotron emission (ECE) and correlation ECE diagnostics. This paper outlines these developments and their application to energetic ion diagnostics in LHD plasmas.</p></div>","PeriodicalId":634,"journal":{"name":"Journal of Fusion Energy","volume":"45 2","pages":""},"PeriodicalIF":2.3,"publicationDate":"2026-08-07","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://link.springer.com/content/pdf/10.1007/s10894-026-00595-7.pdf","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"148751422","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}

引用次数: 0

Numerical Optimization of Neon Soft X-ray Emission in a Spherical Plasma Focus Device with Lee Code 李码球形等离子体聚焦装置中氖软x射线发射的数值优化

IF 2.3 4区工程技术

Journal of Fusion Energy Pub Date : 2026-08-06 DOI: 10.1007/s10894-026-00596-6

M. I. Nayeem, M. A. Malek

{"title":"Numerical Optimization of Neon Soft X-ray Emission in a Spherical Plasma Focus Device with Lee Code","authors":"M. I. Nayeem, M. A. Malek","doi":"10.1007/s10894-026-00596-6","DOIUrl":"10.1007/s10894-026-00596-6","url":null,"abstract":"<div><p>A comprehensive numerical investigation was performed to optimize neon (Ne) soft X-ray emission (Y<sub>sxr</sub>) from a spherical plasma focus (SPF) device using the Lee code. As a prerequisite for predictive modeling, the code was benchmarked against the experimentally measured discharge current waveform of the 135 kJ SPF (N. V. Zavyalov et al., 2013). In this numerical study using ‘equivalent straight length’ technique referred to ‘shortcut’ simply fits a straight length equivalent to the curved run-down length of this SPF with the Lee code (for cylindrical electrodes), the computed current trace is first fitted to the measured one at 14.3 Torr deuterium-tritium (D-T) gas and the obtained best-fitted values of the model parameters are found as <span>(:{{f}_{m}=0.022,:f}_{c}=0.55,::{f}_{mr}=0.14,:{f}_{cr}=:0.72:)</span>. These values were then adopted in a systematic optimisation study of the pinch-plasma conditions. The simulations covered Ne fill pressures from 0.5 to 7 Torr, anode and cathode radii at fixed ratios of <span>(:b/a=1.8125)</span> and <span>(:b/a=1.41)</span>, and charging voltages from 15 to 30 kV. In all the cases, the plasma pinch temperature was constrained to the characteristic Ne emission window of (2.3–5) × 10<sup>6</sup> K. For each electrode geometry the code identified a unique combination of fill pressure and charging voltage that maximized Y<sub>sxr</sub>. At moderate electrode sizes and bank voltages of 25 kV the SPF is predicted to deliver peak Ne soft X-ray (SXR) yields exceeding 5 kJ per shot with efficiencies greater than 4%. In addition, our findings using the ‘shortcut’ method were compared to the results obtained by (Y. Ay, 2021) using the spherical magneto-hydrodynamic model where the cylindrical run-down section of the Lee code was modified to the spherical geometry. Indeed, both results overlap in some points, which is a validation of the ‘shortcut’. And thus, the Lee code was established as a robust and quantitative tool for the design and scaling of compact, high-performance Ne SXR sources.</p></div>","PeriodicalId":634,"journal":{"name":"Journal of Fusion Energy","volume":"45 2","pages":""},"PeriodicalIF":2.3,"publicationDate":"2026-08-06","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"148750852","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}

引用次数: 0