Fusion Engineering and Design最新文献

{"title":"ITER-relevant experimental neutronic activities at JET during DTE3 and at the Frascati neutron generator","authors":"N. Fonnesu ,&nbsp;P. Beaumont ,&nbsp;T. Berry ,&nbsp;A. Colangeli ,&nbsp;F. Dacquait ,&nbsp;M. Damiano ,&nbsp;D. Flammini ,&nbsp;C.L. Grove ,&nbsp;X. Litaudon ,&nbsp;S. Loreti ,&nbsp;M. Lungaroni ,&nbsp;S. Mianowski ,&nbsp;F. Moro ,&nbsp;S. Noce ,&nbsp;J. Peric ,&nbsp;A. Previti ,&nbsp;V. Radulović ,&nbsp;R. Villari ,&nbsp;P. Zito ,&nbsp;JET Contributors","doi":"10.1016/j.fusengdes.2025.115297","DOIUrl":"10.1016/j.fusengdes.2025.115297","url":null,"abstract":"<div><div>The technological exploitation of deuterium-tritium (DT) campaigns at JET under EUROfusion work package PrIO (Preparation of ITER Operations) aimed at taking advantage of the ITER-relevant radiation fields to improve the knowledge of nuclear technology and safety and to develop and validate nuclear codes, data and measurement techniques through dedicated experiments. Among them, the shutdown dose rate (SDDR) measurement with a dosimetry system based on ion chambers for the validation of the numerical tools for the SDDR assessment in ITER, the on-line measurement of tritium production in the mock-up of the ITER HCPB-TBM (Helium Cooled Pebble Bed - Test Blanket Module) with a diamond detector to test some measurement systems capable of working in harsh environments as TBMs, and the first-of-a-kind experiment to measure the neutron-induced activation of cooling water in a tokamak during DT operation, to validate the multi-physics methodologies for water activation assessment in ITER. Moreover, as one of the main sources of radiological hazard in ITER is due to the Activated Corrosion Products (ACPs) circulating in the cooling system, an experiment is currently under design at the ENEA 14-MeV Frascati Neutron Generator (FNG) to prove the accuracy of the reference code in this matter for ITER (i.e., OSCAR-Fusion) under fusion relevant conditions. Finally, considering the importance of radiation-induced effects on electronics in ITER and future fusion machines, it is worth mentioning the development of a modular irradiation station at ENEA named GENeuSIS (General Experimental Neutron System Irradiation Station), to be installed at FNG and which aims at reproducing specific neutron and gamma energy spectra for studying the response of electronic devices and diagnostics.</div><div>The scope of the present work is to give an overview of the mentioned activities, mostly from an experimental point of view, to describe their status, achievements, criticalities emerged and the optimization of the next steps.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"219 ","pages":"Article 115297"},"PeriodicalIF":1.9,"publicationDate":"2025-06-26","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144490408","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":"Thermo-structural assessment of the limiter inboard first wall design of the Divertor Tokamak Test facility","authors":"Riccardo De Luca ,&nbsp;Maurizio Furno Palumbo ,&nbsp;Paolo Frosi ,&nbsp;Gabriele De Sano ,&nbsp;Matteo Iafrati ,&nbsp;Gian Mario Polli ,&nbsp;Bruno Riccardi ,&nbsp;Selanna Roccella","doi":"10.1016/j.fusengdes.2025.115281","DOIUrl":"10.1016/j.fusengdes.2025.115281","url":null,"abstract":"<div><div>The Divertor Tokamak Test facility (DTT) aims at investigating integrated power exhaust solutions that can be relevant for DEMO and future power plants. Such an ambitious goal imposes several constraints on the engineering design of the actively cooled plasma-facing components (PFCs) of DTT. For instance, the First Wall (FW) must withstand thermal and electromagnetic loads that arise during both normal and off-normal operations of various plasma scenarios. In particular, the Limiter Inboard FW (LIFW), covering 50 % of the IFW, has been designed to cope with plasma limited configurations, i.e. when the plasma interacts with the solid wall. Each module consists of seven long (2.3 m) coaxial pipes made of CuCrZr alloy. Owing to the high heat loads expected, the LIFW PFCs are based on the ITER-like W-monoblock design and the plasma-facing surface, protruding radially towards the plasma with respect to the standard IFW, has a toroidal shaping that helps distribute evenly the heat load. In the present work, the technological limits of the proposed LIFW design are assessed. Based on the hydraulic conditions of the cooling water, the maximum power that can be handled by the LIFW system is evaluated under the assumption of a safety margin from the critical heat flux (CHF). Moreover, the thermo-structural behavior of a LIFW unit is simulated in ANSYS under realistic boundary conditions. In this context, a parametric distribution of the thermal load is modelled as a function of the input power and the expected spatial-temporal evolution of the plasma “footprint”. Moreover, realistic kinematic boundary conditions, representative of the pinned supports, have been included in the structural integrity assessment of the pipe, carried out according to the ITER SDC-IC design criteria (design-by-analysis approach). Preliminary results suggest that the maximum peak heat flux that can be handled by the LIFW design falls in the range 5–8 MW/m². This range is compatible with the DTT “Day0” scenario, when, due to the lesser knowledge of machine control, the most critical limiter operations may occur. Nonetheless, studies on the full power scenarios confirmed that in the ramp-up phase the maximum conductive heat load shall be lower than 1 MW/m² therefore the calculated performances can be considered adequately safe. After the fabrication of small-scale mock-ups, the lifetime of such components will be assessed experimentally, by means of cyclic thermal fatigue high heat flux tests.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"219 ","pages":"Article 115281"},"PeriodicalIF":1.9,"publicationDate":"2025-06-26","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144481644","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 study on alternative magnetic layout (AML) for tokamaks reactors in the TRUST project framework","authors":"S. Carusotti ,&nbsp;R. Lombroni ,&nbsp;M. Scarpari ,&nbsp;M. Notazio ,&nbsp;A. Pizzuto ,&nbsp;F. Crisanti ,&nbsp;P. Fanelli ,&nbsp;G. Calabrò","doi":"10.1016/j.fusengdes.2025.115246","DOIUrl":"10.1016/j.fusengdes.2025.115246","url":null,"abstract":"<div><div>The main aim of this study is to explore a conceptual Alternative Magnetic Layout (AML) for the future nuclear fusion reactor based on the Tokamak concept. The proposed concept is eventually applied as a large down scaled study for the new academic tokamak Tuscia Research University Small Tokamak (TRUST), under construction at University of Tuscia (UNITUS). In this proposal the Central Solenoid (CS) placed around the Toroidal Field (TF) coils providing a relevant reduction in the reactor radial build. In order to compensate the increase of the toroidal filed on the coils, that it is intrinsic in such proposal, High Temperature Superconductor (HTS) material is foreseen for the TF coils. An overview of the proposed design and a possible plasma scenario is presented showing the AML advantages and disadvantages. The electromagnetic and structural characterizations for a preliminary design of the TF coils system is included in this paper to prove the engineering feasibility of the solution. Moreover, the involvement of the AML design in the TRUST project framework is presented. TRUST is a flexible and low-cost university-class experiment, to train the next generation of fusion engineers and physicists. Beyond its academic goal, TRUST is designed to allow easy replacement of the plasma facing components and testing innovative technologies (i.e., meta-materials) and materials including a feasible upgrade the magnetic system from copper to HTS.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"219 ","pages":"Article 115246"},"PeriodicalIF":1.9,"publicationDate":"2025-06-26","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144490409","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":"Variable-Depth Complementary Spiral cooling channel design for the steerable ECRH mirrors of DTT","authors":"Alfredo Pagliaro ,&nbsp;Francesco Braghin ,&nbsp;Alessandro Bruschi ,&nbsp;Daniele Busi ,&nbsp;Eliana De Marchi ,&nbsp;Francesco Fanale ,&nbsp;Gustavo Granucci ,&nbsp;Afra Romano ,&nbsp;Fabio Zanon","doi":"10.1016/j.fusengdes.2025.115276","DOIUrl":"10.1016/j.fusengdes.2025.115276","url":null,"abstract":"<div><div>The steerable launching mirrors, essential for directing microwave beams into the plasma, play a pivotal role in the Electron Cyclotron Resonance Heating (ECRH) system for the Divertor Tokamak Test (DTT) facility, currently under construction in Frascati, Italy. Due to the substantial heat and electromagnetic induced loads acting on the mirrors, implementing internal channels for active water cooling, together with a proper choice of the materials, is necessary to keep temperature and deformation under control. Three different channel configurations are studied. First, the single-channel spiral cooling path with a constant cross-section, defined in a previous design stage, has been examined. Then, a constant-depth complementary spiral geometry that increases heat exchange area has been defined and analyzed. Finally, a variable-depth complementary spiral channel is proposed and optimized to increase heat exchange efficiency. In all cases, single-channel geometries are considered to enhance safety and malfunctioning detectability. The study is based on Computational Fluid Dynamics simulations. In order to reduce electromagnetic loads on the mirrors in case of plasma disruption to a tolerable extent, a reduced electrical conductivity of the mirror bulk material with respect to pure copper is necessary: this requires the use of material different than copper alloys, which have in turn a lower thermal conductivity. In this case, high cooling efficiency is mandatory. With this goal in mind, first, the performances of the different configurations in terms of mirror temperature and pressure drop are compared considering a reference material with 100 W/(m⋅K) thermal conductivity. Then, the variable-depth configuration is tested for different and more realistic mirror materials. Finally, a comparison between the developed geometry and previous solutions is provided.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"219 ","pages":"Article 115276"},"PeriodicalIF":1.9,"publicationDate":"2025-06-26","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144481645","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":"Advance in the JT-60SA VUV divertor spectrometer design","authors":"A. Belpane ,&nbsp;W. Biel ,&nbsp;A. Fassina ,&nbsp;S. Soare ,&nbsp;F. Bombarda ,&nbsp;L. Carraro ,&nbsp;B. Zaniol ,&nbsp;M. Chernyshova ,&nbsp;I. Coffey ,&nbsp;K. Lawson ,&nbsp;S. Palomba ,&nbsp;F. Maierna ,&nbsp;A. Sartore ,&nbsp;M. Fincato ,&nbsp;L. Lotto ,&nbsp;M. Cavinato ,&nbsp;N. Hajnal ,&nbsp;G. Phillips ,&nbsp;S. Davis ,&nbsp;C. Sozzi ,&nbsp;M. Valisa","doi":"10.1016/j.fusengdes.2025.115271","DOIUrl":"10.1016/j.fusengdes.2025.115271","url":null,"abstract":"<div><div>The Vacuum Ultraviolet (VUV) Spectrometer designed to monitor the divertor region of JT-60SA is presented. JT-60SA is starting its activity in support of the exploitation of ITER and complementing it in resolving key physics and engineering issues for DEMO. The aim of the spectrometer is to characterize the contribution of impurities to the radiation emitted in the divertor region in different scenarios and to study the divertor physics including plasma detachment.</div><div>Positioned on an upper port with a vertical line of sight aiming at the divertor, the spectrometer is based on the double SPRED spectrometer originally employed on TEXTOR that has been refurbished with two new toroidal gratings specially designed to allow the 1D imaging detection and to cover the desired spectral range. The two channels of the instrument together cover a wavelength range from 10 nm to 125 nm in two ranges of 10–48 nm and 44–125 nm, with an overlapping region to perform the cross calibration. The wavelength resolution in the two ranges is 0.08 nm and 0.14 nm respectively, with a 50 μm wide entrance slit. Given the extended length of the JT-60SA port ducts, the system is equipped with a custom-designed optical relays based on gold-coated toroidal mirrors with possibility of remote control of the alignment. These mirrors focus the plasma emission at the divertor onto the two slits. The dispersed radiation is then recorded by two high sensitivity CCD detectors.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"219 ","pages":"Article 115271"},"PeriodicalIF":1.9,"publicationDate":"2025-06-25","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144480734","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":"Conceptual design proposal for the EU-DEMO electron cyclotron ex-vessel waveguide system with enhanced remote maintainability","authors":"Daniel Birlan ,&nbsp;Gabriele Benzoni ,&nbsp;William Brace ,&nbsp;Alessandro Bruschi ,&nbsp;Antonio Cammi ,&nbsp;René Chavan ,&nbsp;Fabien Crisinel ,&nbsp;Oliver Crofts ,&nbsp;Saul Garavaglia ,&nbsp;Timothy P. Goodman ,&nbsp;Jean-Philippe Hogge ,&nbsp;Cinta Lucia Marraco Borderas ,&nbsp;Avelino Mas Sanchez ,&nbsp;Changyang Li ,&nbsp;Janne Lyytinen ,&nbsp;Hannu Martikainen ,&nbsp;Aditya Sinha ,&nbsp;Peter Spaeh ,&nbsp;Marc Torrance ,&nbsp;Anna Unt ,&nbsp;Anastasia Xydou","doi":"10.1016/j.fusengdes.2025.115267","DOIUrl":"10.1016/j.fusengdes.2025.115267","url":null,"abstract":"<div><div>The EUropean DEMOnstration power plant (EU-DEMO) project, a EUROfusion initiative, seeks to advance fusion power technology by developing a reliable Electron Cyclotron (EC) heating and current drive system capable of delivering up to 130 MW of auxiliary heating power presently through six equatorial ports. This paper introduces an innovative alternative to the baseline ex-vessel waveguide (EW) system design, which could be major for effective EC operations. The proposed design reduces vacuum-sealed interfaces significantly — from 173 to seven — minimizing failure points and reducing the need for extensive monitoring in confined port spaces. Enhanced for remote maintainability, the design simplifies maintenance tasks and mitigates vacuum breach risks. The vacuum dimple-plated casing, acting as the primary confinement boundary, ensures nuclear safety and enables integration with current infrastructure, while addressing challenges like dynamic loads and vessel movements to maintain structural integrity. These advancements indicate that the modular and sealless waveguide approach offers a more reliable, maintainable solution.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"219 ","pages":"Article 115267"},"PeriodicalIF":1.9,"publicationDate":"2025-06-25","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144471328","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 and evaluation of a novel solid-state joint for long-scale fabrication of REBCO stacked strands","authors":"Haihong Wei,&nbsp;Pengyuan Li,&nbsp;Chao Huang,&nbsp;Teng Zhang,&nbsp;Linyu Sun,&nbsp;Rongrong Luo,&nbsp;Xiaoqiang Lai,&nbsp;Yunpeng Zhu","doi":"10.1016/j.fusengdes.2025.115296","DOIUrl":"10.1016/j.fusengdes.2025.115296","url":null,"abstract":"<div><div>Rare Earth Barium Copper Oxide (REBCO) tapes still presents considerable challenges, which restricts the development of long-scale conductors for high-field applications in fusion reactors. The integration of joints into the conductors is a promising solution. However, conventional joining techniques exhibit inherent limitations regarding electrical properties, thermal resistance, and economic efficiency. This study proposes a novel ultrasonic-assisted diffusion (UAD) method to facilitate solid-state bonding between copper-stabilized REBCO tapes within a markedly short duration. By employing a silver interlayer, the joint resistivity (<em>R_sj</em>) is reduced by one-third compared to solder joints, achieving a minimum value of 0.88 pΩ·m². Microscopic analysis reveals that the robust diffusion interfaces and intact tape structure are critical factors contributing to the superior electrical properties. The experimental results demonstrate that the introduction of UAD joints in stacked strands does not compromise the electrical or mechanical properties of the strands. Therefore, this simple joining method offers a straightforward and cost-effective approach for the development of long-scale HTS stacked cables utilizing commercial REBCO tapes.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"219 ","pages":"Article 115296"},"PeriodicalIF":1.9,"publicationDate":"2025-06-25","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144481642","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":"Characterization of MHD pressure losses in a mock-up of the WCLL Test Blanket Module","authors":"C. Courtessole,&nbsp;H.-J. Brinkmann,&nbsp;L. Bühler,&nbsp;C. Koehly,&nbsp;J. Roth","doi":"10.1016/j.fusengdes.2025.115216","DOIUrl":"10.1016/j.fusengdes.2025.115216","url":null,"abstract":"<div><div>Liquid metal magnetohydrodynamic (MHD) flows in a scaled mock-up of the water-cooled lead-lithium test blanket module (TBM) were investigated experimentally in the MEKKA laboratory at the Karlsruhe Institute of Technology. The test section faithfully replicates the complex geometry of the current TBM design where liquid metal is distributed to breeder units (BUs) through long electrically coupled manifolds oriented along the poloidal direction, orthogonally to the magnetic field direction. During the experiments, pressure was recorded at various points of the mock-up for several liquid metal flow rates and magnetic fields. The overall pressure drop of the mock-up was analyzed, along with the diverse contributions to the total pressure loss from different components, based on characteristic flow parameters. A correlation for the total MHD pressure drop in the WCLL TBM was derived.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"219 ","pages":"Article 115216"},"PeriodicalIF":1.9,"publicationDate":"2025-06-24","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144365638","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":"The role of specimen size and grain boundary characteristics in the yield strength of tungsten in microtensile tests","authors":"Tzu-Yi Chang ,&nbsp;Sebastian Lam ,&nbsp;David Frazer ,&nbsp;Fei Teng ,&nbsp;Yachun Wang ,&nbsp;Hanns Gietl ,&nbsp;Peter Hosemann ,&nbsp;Stephanie Pitts","doi":"10.1016/j.fusengdes.2025.115293","DOIUrl":"10.1016/j.fusengdes.2025.115293","url":null,"abstract":"<div><div>To effectively use the measured properties from small-scale tensile tests for bulk material performance predictions, it is essential to understand the threshold of specimen size-effect strengthening and the interaction between dislocations and microstructures within miniaturized specimens. This study uses pure tungsten to investigate the size effect in terms of specimen size, grain size, and grain boundary characteristics relative to the yield strength of tungsten at room temperature. We evaluate the transition from miniaturized specimen properties to bulk properties and the deformation behavior through small-scale tensile tests of three specimen sizes (large: 80 × 100 × 233 µm³; medium: 7 × 7 × 18 µm³; and small: 2 × 2 × 5 µm³). The testing results reveal that the small and medium specimens exhibit high yield strength with ductile behavior, while the large specimens exhibit brittle failure, consistent with the room temperature strength of tungsten, indicating bulk behavior. We further explore the specimen size-effect sensitivity to yield stress and the scaling relationship between yield strength and the number of grains involved in the deformation. A power-law relationship with the exponent value of approximately -0.5 was found in the yield strength–grain number scaling, implying the Hall-Petch like behavior. A minimum of 7–17 effective grain boundaries across the tensile gauge dimension is required to accurately measure bulk properties.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"219 ","pages":"Article 115293"},"PeriodicalIF":1.9,"publicationDate":"2025-06-24","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144365637","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":"Influence of thermal aging on the deuterium permeation and retention behavior in the CLAM Steel","authors":"Zongming Shao ,&nbsp;Hao Yang ,&nbsp;Siwei Zhang","doi":"10.1016/j.fusengdes.2025.115268","DOIUrl":"10.1016/j.fusengdes.2025.115268","url":null,"abstract":"<div><div>As one of the candidate structural materials for the fusion reactor, the properties of China Low Activation Martensitic (CLAM) steel gradually degrade during service at high temperature. While the effects of thermal aging on the mechanical properties of CLAM steel have been widely studied, the behavior of deuterium permeation and retention in CLAM steel after thermal aging is not yet well understood. In this study, the CLAM steel was exposed to 923 K for 8000 h. Subsequently, thermal desorption spectroscopy (TDS) and gas-driven permeation (GDP) experiments were performed to investigate the evolution of deuterium permeation and retention in CLAM steel following thermal aging. The results showed that the deuterium retention in CLAM steel decreased after thermal aging for 8000 h, while the deuterium permeability of aged CLAM steel increased. The further microstructural characterization reveals that dislocations, which serve as deuterium trapping sites, evolve into sub-grain boundaries during the thermal aging process. The grain boundaries, acting as rapid diffusion paths for deuterium atoms, lead to an increase in permeation and a decrease in retention.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"219 ","pages":"Article 115268"},"PeriodicalIF":1.9,"publicationDate":"2025-06-24","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144365635","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}