Fusion Engineering and Design最新文献_第2页

An optimal flange assembly pose evaluation method based on the PSO-HPO algorithm 基于PSO-HPO算法的法兰装配位姿最优评价方法

IF 2 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Fusion Engineering and Design

Pub Date : 2026-04-01 Epub Date: 2026-02-12 DOI: 10.1016/j.fusengdes.2026.115663

Xin Song, Dong Gao, Zhiqi Wang, Junran Liang, Congsheng Feng

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 PSOHPO 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.

在激光惯性约束聚变（LICF）系统中，安装在球壳孔上的法兰的装配精度直接影响系统的整体装配质量和性能。在法兰装配过程中，由于法兰安装孔和法兰本体的制造误差，难以准确评估法兰的最佳装配姿态。为了解决这一问题，本研究提出了一种确定最佳法兰组合的评价方法。该方法建立了翼缘装配的位姿评估模型，并将猎人-猎物优化（HPO）算法导出的调节机制整合到粒子群优化（PSO）框架中。目标是尽量减少对中偏差，并确定最佳的法兰装配姿势。首先，获取法兰安装孔和法兰表面的关键测量点（MPs），以表征制造误差并确定法兰的实际初始位姿。基于这些识别的偏差和装配精度要求，制定了一套装配约束。然后构建姿态评估模型，以最小化这些约束下的整体装配误差。然后，利用所提出的PSOHPO算法确定翼缘的最优位姿参数。最后，通过翼缘位姿调整的仿真实例表明，该算法在位姿估计精度上明显优于奇异值分解（SVD）和传统粒子群算法。具体而言，该方法可使法兰共线误差减小78.86%，共面误差减小58.66%。由位姿评估模型得到的约束误差均在规定的设计公差范围内，从而保证了较高的装配精度。

{"title":"An optimal flange assembly pose evaluation method based on the PSO-HPO algorithm","authors":"Xin Song, Dong Gao, Zhiqi Wang, Junran Liang, 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}

引用次数: 0

Improving control integration in Plasma Control System with an XML-based model-driven approach 利用基于xml的模型驱动方法改进等离子体控制系统中的控制集成

IF 2 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Fusion Engineering and Design

Pub Date : 2026-04-01 Epub Date: 2026-02-02 DOI: 10.1016/j.fusengdes.2026.115642

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

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.

实验物理的控制系统，如等离子体控制系统（PCS），需要不断修改控制算法来测试新的理论。敏捷开发的这种需求经常与跨异构系统组件（如用户界面和数据库）维护数据一致性的关键需求相冲突。本文介绍了一种轻量级的、基于可扩展标记语言（XML）的、模型驱动的方法，旨在解决灵书PCS框架中的这一冲突。其核心是一个简单的、人类可读的数据模型，作为所有算法相关数据的单一真相来源（SSoT）。与专用的工具链相结合，我们的方法可以直接从模型中自动生成关键的工程工件，包括c++代码框架和用户界面模板。这种方法确保了端到端的数据一致性，简化了开发周期，并为控制算法的集成提供了一种实用的、低开销的方法。

{"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":"2026-04-01","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}

引用次数: 0

Application of powder HIP to the ITER IR thermography first mirror: Fabrication and evaluation of internal cooling channel deformation 粉末HIP在ITER红外热成像第一镜中的应用：内部冷却通道变形的制备与评价

IF 2 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Fusion Engineering and Design

Pub Date : 2026-04-01 Epub Date: 2026-01-23 DOI: 10.1016/j.fusengdes.2026.115639

Suguru TANAKA , Tomohiko USHIKI , Kimihiro IOKI , Hiroyuki TACHIBANA , Yoshihiko NUNOYA

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.

核聚变反应堆的容器内诊断镜受到极端热载荷的影响，会引起变形并降低光学性能。为了解决这些挑战，本研究研究了基于粉末的热等静压（HIP）在ITER转向器红外热成像系统的第一个反射镜中制造复杂的内部冷却通道的应用，这是一种以前未尝试使用粉末HIP的几何形状。制造了一个使用雾化不锈钢316L粉末的原型，并在1200°C下hip - processing 4小时。通过截面分析和超声检测表征尺寸变化。收缩率一致，管道区域收缩6-10%。结果表明，粉末HIP能够可靠地形成完整的冷却通道，在无损检测和抗应力腐蚀方面具有优势。该方法也可以应用于ITER和未来核聚变反应堆中其他具有内部冷却通道的诊断镜和容器组件。

{"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":"2026-04-01","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}

引用次数: 0

Frequency characteristics of the liquid Li target flow surface in A-FNS A-FNS中液体Li靶流表面的频率特性

IF 2 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Fusion Engineering and Design

Pub Date : 2026-04-01 Epub Date: 2026-02-04 DOI: 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":"2026-04-01","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}

引用次数: 0

Preliminary neutronic and thermal analysis of Inertial Fusion Energy systems with a focus on thick liquid wall concepts 惯性聚变能系统的初步中子和热分析，重点是厚液壁概念

IF 2 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Fusion Engineering and Design

Pub Date : 2026-04-01 Epub Date: 2026-02-10 DOI: 10.1016/j.fusengdes.2026.115659

Nahom Habtemariam , Eric Cervi , Robert Earley , Kirk Flippo , Travis Hallam , Susana Reyes , Carlo Fiorina

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.

本文利用Serpent 2蒙特卡罗代码对惯性聚变能系统的中子行为进行了评估。该研究探讨了不同类型的反应器概念，包括干壁和厚液壁系统。特别地，它描述了氚的增殖和能量倍增性能，以及长期辐照对结构材料的影响。为此，计算了结构材料中的原子位移（DPA）和产气速率。用不同几何参数的简化几何来表示不同类型的器件。此外，HYLIFE-II概念的案例用于评估由某些近似值引起的建模不准确性。由于Serpent能够在非结构化网格上运行传输计算，因此可以将简化的几何形状与现实的几何形状进行比较。然后，该研究使用GeN-Foam代码进行共轭传热分析，解决了这些差异对第一壁温度分布的影响。研究结果强调了考虑液壁非均匀性的必要性，因为简化的模型往往低估了辐射损伤指标和热负荷。

{"title":"Preliminary neutronic and thermal analysis of Inertial Fusion Energy systems with a focus on thick liquid wall concepts","authors":"Nahom Habtemariam , Eric Cervi , Robert Earley , Kirk Flippo , Travis Hallam , Susana Reyes , 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}

引用次数: 0

Tritium depth distribution measurement by using chemical etching and surface washing technique for structural material of the ICF target chamber 利用化学蚀刻和表面清洗技术测量ICF靶室结构材料的氚深度分布

IF 2 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Fusion Engineering and Design

Pub Date : 2026-04-01 Epub Date: 2026-01-19 DOI: 10.1016/j.fusengdes.2026.115634

Jingquan Xia , Zhilin Chen , Yang Yang , Zhu An

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.

惯性约束聚变（ICF）靶室结构材料（即5083铝合金（Al5083））中的氚深度分布是评价辐射防护和环境危害的重要依据。鉴于Al5083中氚离子注入深度较浅的特点，本研究旨在建立一种高分辨率的测量方法。采用ZnCl2表面洗涤（SW）法和逐层化学蚀刻（LLCE）法，建立了一种测量Al5083中氚深度分布的方法。首先，系统研究了LLCE法中蚀刻剂类型、酸水比、温度、蚀刻周期对测量分辨率的影响，将深度分辨率控制在30 ~ 50 nm，满足浅注入氚的高分辨率测量要求。其次，用内标法验证了两种含氚锌溶液液体闪烁计数（LSC）测量校正方法的可靠性。结果表明，该方法能够准确地分离和定量测定Al5083中表面吸附氚的总量，为区分表面吸附氚和体积保留氚提供了关键方法。在平均入射能量为7.5 keV、注入量为4.5 × 10¹²离子/cm²的负载氚Al5083样品上进行的实验表明，表面吸附的氚占总氚量的1.8%，浓度较高（~ 108 Bq/cm3），体体中80%的氚分布在距表面200 nm的范围内。本研究建立的标准化测量方法为评估氚在ICF器件结构材料中的滞留和迁移提供了可靠的技术支持。

{"title":"Tritium depth distribution measurement by using chemical etching and surface washing technique for structural material of the ICF target chamber","authors":"Jingquan Xia , Zhilin Chen , Yang Yang , 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 ZnCl<sub>2</sub> 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 (∼10<sup>8</sup> Bq/cm<sup>3</sup>), 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}

引用次数: 0

Development of 3D simulation demonstration platform for tritium safety confinement of China fusion engineering test reactor 中国核聚变工程试验堆氚安全约束三维仿真演示平台的研制

IF 2 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Fusion Engineering and Design

Pub Date : 2026-04-01 Epub Date: 2026-01-15 DOI: 10.1016/j.fusengdes.2026.115629

Haixia Wang , Xuewei Fu , Zihui Yang , Qianchao Huo , Jie Yu

The China Fusion Engineering Test Reactor (CFETR) is a next-generation fusion reactor project independently designed and actively pursued by China. As the key radioactive source term of the CFETR, tritium safety is an important issue of nuclear safety. The tritium safety confinement system is one of the major systems in the CFETR tritium plant, and the study of tritium transport behavior in confinement system is of significant research interest. Supported by the National Key R&D Program, this study employs Unreal Engine (UE) as the 3D interactive simulation engine to construct a 3D simulation demonstration platform for tritium safety confinement of the CFETR. The Tokamak Exhaust Processing (TEP) System is selected as a representative case for simulation. Test results indicate that the platform enables smooth human-computer interaction, effectively visualizes tritium transport behavior under typical conditions, and provides an immersive 3D scene virtual roaming experience. Through dynamic demonstration of tritium transport under multiple conditions, the design principle of the CFETR tritium safety confinement system is effectively visualized, offering valuable insights for the future design of tritium confinement system in tritium plants.

中国聚变工程试验堆（CFETR）是中国自主设计并积极推进的新一代聚变反应堆项目。氚作为CFETR的关键放射源项，其安全性是核安全的重要问题。氚安全约束系统是CFETR氚厂的主要系统之一，对约束系统中氚输运行为的研究具有重要的研究意义。本研究在国家重点研发计划的支持下，采用虚幻引擎（UE）作为三维交互仿真引擎，构建了CFETR氚安全约束的三维仿真演示平台。选取托卡马克排气处理（TEP）系统作为仿真的代表案例。测试结果表明，该平台实现了流畅的人机交互，有效地可视化了典型条件下氚的输运行为，提供了沉浸式3D场景虚拟漫游体验。通过多种条件下氚输运的动态演示，有效地可视化了CFETR氚安全约束系统的设计原理，为今后氚厂氚约束系统的设计提供了有价值的见解。

{"title":"Development of 3D simulation demonstration platform for tritium safety confinement of China fusion engineering test reactor","authors":"Haixia Wang , Xuewei Fu , Zihui Yang , Qianchao Huo , Jie Yu","doi":"10.1016/j.fusengdes.2026.115629","DOIUrl":"10.1016/j.fusengdes.2026.115629","url":null,"abstract":"<div><div>The China Fusion Engineering Test Reactor (CFETR) is a next-generation fusion reactor project independently designed and actively pursued by China. As the key radioactive source term of the CFETR, tritium safety is an important issue of nuclear safety. The tritium safety confinement system is one of the major systems in the CFETR tritium plant, and the study of tritium transport behavior in confinement system is of significant research interest. Supported by the National Key R&D Program, this study employs Unreal Engine (UE) as the 3D interactive simulation engine to construct a 3D simulation demonstration platform for tritium safety confinement of the CFETR. The Tokamak Exhaust Processing (TEP) System is selected as a representative case for simulation. Test results indicate that the platform enables smooth human-computer interaction, effectively visualizes tritium transport behavior under typical conditions, and provides an immersive 3D scene virtual roaming experience. Through dynamic demonstration of tritium transport under multiple conditions, the design principle of the CFETR tritium safety confinement system is effectively visualized, offering valuable insights for the future design of tritium confinement system in tritium plants.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"225 ","pages":"Article 115629"},"PeriodicalIF":2.0,"publicationDate":"2026-04-01","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}

引用次数: 0

Thermodynamic process optimization of a forced flow cooling loops with subcooled helium for superconducting magnets based on exergy analysis 基于火用分析的超导磁体过冷氦强制流动冷却回路热力学过程优化

IF 2 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Fusion Engineering and Design

Pub Date : 2026-04-01 Epub Date: 2026-01-29 DOI: 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.

大型氦低温系统对于维持磁约束聚变装置中超导磁体的状态至关重要，但其高能量需求仍然是一个主要挑战。辅助冷箱（ACB）将氦气制冷机与低温客户连接起来，由于过冷氦气的强制流动冷却回路，通常会消耗30 - 50%的制冷能力。为了评估潜在的改进，对三种代表性的ACB工艺配置进行了建模和比较：(1)单浴循环工艺，(2)双浴系列循环工艺，(3)拟议的双浴负荷管理循环工艺。使用Aspen HYSYS模拟、性能系数（COP）评估和火用分析来评估它们的性能。结果表明，与双槽负荷管理过程相比，单槽负荷管理方案需要增加43%的冷压缩机功率和53%的换热器火用损失，双槽负荷管理方案需要增加28%的压缩机功率和46%的换热器火用损失。上述结果表明，减小换热温差和减轻过冷氦浴负荷可以显著降低能耗。这为未来核聚变设施中高效低温子系统的设计提供了实践指导。

{"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":"2026-04-01","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}

引用次数: 0

Proximal probe thermal desorption mass spectrometry for mapping lateral hydrogen isotope retention in metals 近端探针热解吸质谱法测定金属中氢同位素的横向保留

IF 2 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Fusion Engineering and Design

Pub Date : 2026-04-01 Epub Date: 2026-01-15 DOI: 10.1016/j.fusengdes.2026.115628

Qin Lei , Qiannan Yu , Jiaguan Peng , Yiwen Sun , Mengqi Zhang , Hanfeng Song , Hao Yin , Xiaolu Xiong , Sijie Hao , Yuhao Li , Xiuli Zhu , Lu Sun , Long Cheng , Yue Yuan , Guang-Hong Lu

The study of hydrogen isotopes (HIs) retention in fusion materials is crucial for the safe operation of fusion devices. This research developed the proximal probe thermal desorption mass spectrometry (PTDS) technique, a unique technique utilizing a probe to heat the specific micro-regions on the sample, to characterize lateral deuterium (D) retention in materials using deuterated tungsten. The temperature during the test was studied using an infrared camera, with the maximum probe tip temperature reaching approximately 2300 K and the temperature-affected region having a diameter of about 500 µm. PTDS testing of deuterated tungsten films prepared by magnetron sputtering revealed a uniform lateral distribution of D retention on the sample surface. Using PTDS, the estimated deuterium-to-tungsten (D/W) atomic ratio was approximately 0.146. PTDS testing of D plasma-exposed sample provided the lateral distribution characteristics of D retention, which were compared with the distribution of plasma flux showing consistent trends. Besides, D/W ratio in D plasma-exposed sample is about 6.40 × 10^–5 as estimated based on thermal desorption spectroscopy (TDS) measurement, indicating that the detection capability of the device reached the order of ∼10^–5. Furthermore, this technique is of potential in precise localization of measurement spots and future research will focus on enhancing the lateral spatial resolution and in situ application of PTDS on HIs transport studies during plasma exposure.

氢同位素在核聚变材料中的保留研究对核聚变装置的安全运行至关重要。本研究开发了近端探针热解吸质谱（PTDS）技术，这是一种利用探针加热样品上特定微区域的独特技术，用于表征氘化钨材料中的侧向氘(D)保留。使用红外摄像机对测试过程中的温度进行了研究，测头最高温度约为2300 K，温度影响区直径约为500µm。对磁控溅射制备的氘化钨薄膜进行PTDS测试，发现样品表面有均匀的横向D保留分布。使用PTDS，估计氘与钨（D/W）原子比约为0.146。D等离子体暴露样品的PTDS检测提供了D潴留的横向分布特征，与等离子体通量分布相比较，显示出一致的趋势。此外，通过热解吸光谱（TDS）测量，D等离子体暴露样品的D/W比约为6.40 × 10-5，表明该器件的检测能力达到了~ 10-5的量级。此外，该技术在测量点的精确定位方面具有潜力，未来的研究将集中在提高横向空间分辨率和原位应用PTDS在等离子体暴露过程中的he输运研究上。

{"title":"Proximal probe thermal desorption mass spectrometry for mapping lateral hydrogen isotope retention in metals","authors":"Qin Lei , Qiannan Yu , Jiaguan Peng , Yiwen Sun , Mengqi Zhang , Hanfeng Song , Hao Yin , Xiaolu Xiong , Sijie Hao , Yuhao Li , Xiuli Zhu , Lu Sun , Long Cheng , Yue Yuan , Guang-Hong Lu","doi":"10.1016/j.fusengdes.2026.115628","DOIUrl":"10.1016/j.fusengdes.2026.115628","url":null,"abstract":"<div><div>The study of hydrogen isotopes (HIs) retention in fusion materials is crucial for the safe operation of fusion devices. This research developed the proximal probe thermal desorption mass spectrometry (PTDS) technique, a unique technique utilizing a probe to heat the specific micro-regions on the sample, to characterize lateral deuterium (D) retention in materials using deuterated tungsten. The temperature during the test was studied using an infrared camera, with the maximum probe tip temperature reaching approximately 2300 K and the temperature-affected region having a diameter of about 500 µm. PTDS testing of deuterated tungsten films prepared by magnetron sputtering revealed a uniform lateral distribution of D retention on the sample surface. Using PTDS, the estimated deuterium-to-tungsten (D/W) atomic ratio was approximately 0.146. PTDS testing of D plasma-exposed sample provided the lateral distribution characteristics of D retention, which were compared with the distribution of plasma flux showing consistent trends. Besides, D/W ratio in D plasma-exposed sample is about 6.40 × 10<sup>–5</sup> as estimated based on thermal desorption spectroscopy (TDS) measurement, indicating that the detection capability of the device reached the order of ∼10<sup>–5</sup>. Furthermore, this technique is of potential in precise localization of measurement spots and future research will focus on enhancing the lateral spatial resolution and <em>in situ</em> application of PTDS on HIs transport studies during plasma exposure.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"225 ","pages":"Article 115628"},"PeriodicalIF":2.0,"publicationDate":"2026-04-01","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}

引用次数: 0

Initial design of a Laval nozzle for the supersonic molecular beam injection system on CFQS CFQS超声速分子束喷射系统拉瓦尔喷嘴的初步设计

IF 2 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Fusion Engineering and Design

Pub Date : 2026-04-01 Epub Date: 2026-01-26 DOI: 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

Γ^{*}

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.,

M_{t}

equal 7,

θ_{1}

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.

超声速分子束注入（SMBI）技术在磁约束聚变领域引起了人们极大的兴趣，因为它能以相对简单和经济的硬件提供高效的燃料。作为SMBI的关键部件，拉瓦尔喷嘴在很大程度上决定了射流速度、准直度，从而决定了加油性能。本文介绍了中国第一颗拟轴对称仿星器（CFQS） SMBI系统的拉瓦尔喷嘴的初步设计。CFQS的参考气体流量是通过对大型螺旋装置（LHD）中诊断良好的SMBI数据进行缩放来估算的；结果值（~ 12 Pa·m³/s）用作喷嘴尺寸的数量级设计输入。为了选择物理上有意义的设计马赫数范围，使用基于Knudsen数的压力标准和与氢相变趋势相关的基于温度的标准来讨论有效加速度限制，并评估聚类参数Γ*以量化典型操作条件下的凝结/簇形成范围。采用Foelsch方法作为有效的分析框架，得到了喷管外形和关键几何参数，综合考虑物理性能和工程约束条件，推荐了CFQS喷管的基准设计（如Mt = 7, θ1 = 5°，喉道直径0.3 mm），并给出了工程实例设计简图。本研究结果为CFQS SMBI系统的实施和未来的优化提供了实用参考。

{"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":"2026-04-01","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}

引用次数: 0