Nuclear Materials and Energy最新文献

{"title":"X-point radiation: From discovery to potential application in a future reactor","authors":"M. Bernert ,&nbsp;T.O.S.J. Bosman ,&nbsp;T. Lunt ,&nbsp;O. Pan ,&nbsp;B. Sieglin ,&nbsp;U. Stroth ,&nbsp;A. Kallenbach ,&nbsp;S. Wiesen ,&nbsp;M. Wischmeier ,&nbsp;G. Birkenmeier ,&nbsp;M. Cavedon ,&nbsp;B. Lipschultz ,&nbsp;C. Lowry ,&nbsp;N. Fedorczak ,&nbsp;P. Fox ,&nbsp;M. Lennholm ,&nbsp;H. Sun ,&nbsp;P. Jacquet ,&nbsp;K. Kirov ,&nbsp;N. Vianello ,&nbsp;F. Reimold","doi":"10.1016/j.nme.2025.101916","DOIUrl":"10.1016/j.nme.2025.101916","url":null,"abstract":"<div><div>Power exhaust is a crucial issue for future fusion reactors. Divertor detachment and the required power dissipation fractions of about 95% are foreseen to be achieved by impurity seeding. In a tokamak, at high seeding levels the radiation often concentrates in a small region inside the confined plasma near the X-point. In early observations the so-called X-point radiator (XPR) often led to back-transitions to L-mode or disruptions. In metal tokamaks or with higher available heating power, these regimes can be stabilized and are now established on AUG, JET, TCV, KSTAR and WEST.</div><div>The XPR is a cold, dense plasma inside the confined region in the vicinity of the X-point, that breaks the paradigm of poloidal symmetry of density and temperature on closed flux surfaces. On AUG, the poloidal extent of the XPR is a few centimeters and it is observed up to 15<!--> <span><math><mi>c</mi></math></span> <span><math><mi>m</mi></math></span> above the X-point. The long connection length in this region and the access of neutral particles from the divertor region facilitate the creation of the XPR, as predicted by an analytical model. Numerical simulations with SOLPS-ITER match the observations at AUG and TCV and allow predictions towards a power plant, where a lower impurity concentration is required to trigger an XPR. Since the XPR greatly reduces power and particle fluxes to the targets, simpler and more efficient divertor concepts, such as the compact radiative divertor, can be envisaged for future devices. A scenario with an XPR, however, comes at the cost of an increased impurity concentration and a potential reduction in confinement, which has to be further quantified.</div><div>The XPR location can be well detected by various diagnostics, enabling responsive real-time control, even through large transients like an LH transition. The active control helped to access a new regime of ELM suppression at AUG, which is now also observed at TCV and JET.</div><div>The observation of the XPR on multiple tokamaks, the demonstration of its active control, and the emergence of theoretical models that scale favourably towards fusion reactors have opened up a new phase of advanced power exhaust research.</div></div>","PeriodicalId":56004,"journal":{"name":"Nuclear Materials and Energy","volume":"43 ","pages":"Article 101916"},"PeriodicalIF":2.3,"publicationDate":"2025-03-25","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143739927","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":2,"RegionCategory":"物理与天体物理","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"OA","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Effects of alloying elements on the solubility, diffusivity, and permeability of hydrogen in TiC from first-principles calculation","authors":"Qian Wang ,&nbsp;Liang Chen ,&nbsp;Chaoping Liang","doi":"10.1016/j.nme.2025.101924","DOIUrl":"10.1016/j.nme.2025.101924","url":null,"abstract":"<div><div>First-principles calculations were utilized to explore the effects of Zr, Nb, Ta, and W on the solubility, diffusivity, and permeability of hydrogen in TiC. It is found that the trigonal site of H in TiC, which is encircled by three Ti atoms lying a {111} plane, has been identified as thermodynamically more stable. The addition of alloying elements will destroy the equilibrium distribution of the Ti-H interaction and reduce the structural stability of interstitial H. Furthermore, the solubility, diffusivity, and permeability of H in Ti₃₂C₃₂ and Ti₃₁MC₃₂ (M = Zr, Nb, Ta, and W) at finite temperatures are derived, and the results are discussed and compared with similar experiments in the literature. Drawing upon the influence of elemental alloying on H retention, we deeply understand experimental observations and provide experimentalists with a potentially valuable recommendation for controlling hydrogen permeability.</div></div>","PeriodicalId":56004,"journal":{"name":"Nuclear Materials and Energy","volume":"43 ","pages":"Article 101924"},"PeriodicalIF":2.3,"publicationDate":"2025-03-24","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143705325","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":2,"RegionCategory":"物理与天体物理","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"OA","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Oxidation behavior of pure W and W-0.5 wt% ZrC at 700 °C and 900 °C","authors":"Yongkui Wang ,&nbsp;Xiaochen Huang ,&nbsp;Changpeng Lv ,&nbsp;Zhong Wu ,&nbsp;Jinlong Ge ,&nbsp;Jianguo Ma ,&nbsp;Xueqi Zhang","doi":"10.1016/j.nme.2025.101922","DOIUrl":"10.1016/j.nme.2025.101922","url":null,"abstract":"<div><div>This study investigates the oxidative behavior of pure tungsten and a W-0.5 wt% ZrC alloy (WZC05), was examined. Both materials were fabricated via sintering and hot rolling. The alloys were exposed to air at 700 °C for 20 h and to air at 900 °C for 8 h to analyze surface morphology, oxidation resistance, and oxidation behavior of pure tungsten and WZC05. WZC05 exhibited a significantly smaller grain size than pure tungsten. At 700 °C, the “positive effect of grain size,” caused a higher oxidation rate in pure tungsten compared with that in WZC05. After air oxidation for 20 h at 700 °C, the thickness of the oxide layer on pure tungsten reached 320 μm, whereas that on WZC05 was only 202 μm. At 900 °C, the dense oxide layer was destroyed owing to the formation of volatile WO₃, resulting in similar oxidation rates for pure tungsten and WZC05. Scanning electron micrographs revealed that the oxidized tungsten materials had a layered structure.</div></div>","PeriodicalId":56004,"journal":{"name":"Nuclear Materials and Energy","volume":"43 ","pages":"Article 101922"},"PeriodicalIF":2.3,"publicationDate":"2025-03-20","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143704095","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":2,"RegionCategory":"物理与天体物理","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"OA","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Electron beam welding behavior in Eurofer subjected to the PbLi eutectic","authors":"T. Hernández ,&nbsp;M. Roldán ,&nbsp;F.J. Sánchez ,&nbsp;N. García-Rodríguez ,&nbsp;J. Patiño ,&nbsp;J. Navas ,&nbsp;E. Carella ,&nbsp;L. Serrador ,&nbsp;I. Rueda ,&nbsp;E. Abad ,&nbsp;R. San Martín","doi":"10.1016/j.nme.2025.101920","DOIUrl":"10.1016/j.nme.2025.101920","url":null,"abstract":"<div><div>The weldability of Eurofer steel and the behavior of weld beads under relevant fusion conditions are critical factors to assess for future designs, specifically in the context of the Water-Cooled Lithium Lead (WCLL) blanket concept. Here, the area corresponding to the breeder blanket will be in direct contact with the PbLi eutectic alloy, which will flow continuously at temperatures between 400 °C and 550 °C. In this study, electron beam welding was performed on 1.4 mm thick Eurofer plates. These welded samples were subsequently exposed to flowing PbLi in the CiCLo loop at CIEMAT, maintained at 450 °C for 1000 h.</div><div>Prior to corrosion testing, the microstructure of the samples was characterized to evaluate the fusion zone width, bonding coefficient, and the presence of any defects or brittle joints. Acicular delta ferrite was observed, attributed to the high temperatures during welding and rapid cooling afterward. The potential for improved corrosion resistance through normalization treatment post-welding was also assessed. Following PbLi exposure, the specimens underwent the same microstructural characterization.</div><div>The results showed a significant microstructural change in the HAZ, which caused an increase in hardness in the HAZ; this result occurred in both the as-welded and heat-treated materials. It should be noted that non-negligible amounts of lithium were found in the HAZ, which is evidence of the diffusion of lithium from the molten eutectic into the interior of the material.</div></div>","PeriodicalId":56004,"journal":{"name":"Nuclear Materials and Energy","volume":"43 ","pages":"Article 101920"},"PeriodicalIF":2.3,"publicationDate":"2025-03-15","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143679241","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":2,"RegionCategory":"物理与天体物理","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"OA","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Thermomechanical analysis for the theoretical optimization of W/Cu monoblocks with functionally graded interlayer","authors":"Yi Li ,&nbsp;Dahuan Zhu ,&nbsp;Chunyu He ,&nbsp;Zongxiao Guo ,&nbsp;Yang Wang ,&nbsp;Chuannan Xuan ,&nbsp;Baoguo Wang ,&nbsp;Junling Chen ,&nbsp;EAST Team","doi":"10.1016/j.nme.2025.101919","DOIUrl":"10.1016/j.nme.2025.101919","url":null,"abstract":"<div><div>In fusion devices, plasma-facing components (PFCs) play a critical role in withstanding severe thermal conditions resulting from cyclic high heat flux (HHF) loads. The International Thermonuclear Experimental Reactor (ITER) and next-generation fusion devices are expected to employ actively cooled tungsten/copper (W/Cu) monoblocks as divertor targets due to their excellent heat removal capabilities. Although ITER-like monoblocks utilize a soft Cu interlayer to alleviate stress, interface fatigue cracking still occurs under cyclic HHF loads. The issue of interface bonding between the W armor and heat sink has been a limiting factor for the long-term stable operation and structural integrity of these monoblocks. Functionally graded materials (FGMs) are regarded as an effective approach to address severe local stress concentration at the bonding interface. The number of layers, composition distribution, and thickness of the FGM layers are analyzed by evaluating the stress and strain after the loading and cooling phases in finite element simulations. The simulation results indicate that the graded interlayer can significantly reduce stress concentration at the interface, and a two-layer FGM (25 vol% and 66.7 vol% W) with each layer 0.6 mm thick can greatly mitigate both stress and strain. Such results provide important guidance for the development of graded W/Cu monoblocks for fusion applications.</div></div>","PeriodicalId":56004,"journal":{"name":"Nuclear Materials and Energy","volume":"43 ","pages":"Article 101919"},"PeriodicalIF":2.3,"publicationDate":"2025-03-13","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143644865","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":2,"RegionCategory":"物理与天体物理","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"OA","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Resistance to deuterium-induced blistering in laminated microstructure tungsten","authors":"Hanfeng Song ,&nbsp;Chao Qi ,&nbsp;Jiaguan Peng ,&nbsp;Pengcheng Guo ,&nbsp;Junyun Lai ,&nbsp;Long Cheng ,&nbsp;Yue Yuan ,&nbsp;Bo Wang ,&nbsp;Guang-Hong Lu","doi":"10.1016/j.nme.2025.101921","DOIUrl":"10.1016/j.nme.2025.101921","url":null,"abstract":"<div><div>Tungsten (W) is a promising candidate for plasma-facing materials in fusion reactors; however, its application is hindered by challenges such as blistering. This study proposes a laminated microstructure W design, developed by stacking warm-rolled W foils with thicknesses of 0.05 mm and 0.1 mm. The plasma-exposed surface exhibited a strong preferential [110] orientation, nanoscale grains, and grain boundaries oriented perpendicular to the surface, in addition to interlayer gaps between the foils. Laminated samples, composed of laminated microstructure W and 2.5 mm thick warm-rolled and recrystallized W bulks, were fabricated and exposed to deuterium plasma at a flux of 3 × 10²⁰ ions m^-2s⁻¹, with fluences of 1 × 10²⁵ ions m⁻² and 5 × 10²⁵ ions m⁻². The results demonstrated that the laminated microstructure W exhibits superior resistance to blistering. Furthermore, laminated W foils were successfully brazed onto a Cu substrate, validating the feasibility of manufacturing laminated W plasma-facing component (PFC). These findings indicate that laminated W-based PFC represent a promising design strategy for improving the irradiation tolerance of PFC under fusion reactor conditions.</div></div>","PeriodicalId":56004,"journal":{"name":"Nuclear Materials and Energy","volume":"43 ","pages":"Article 101921"},"PeriodicalIF":2.3,"publicationDate":"2025-03-13","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143629496","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":2,"RegionCategory":"物理与天体物理","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"OA","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"First ion temperature measurements in the MAST-U divertor via Retarding Field Energy Analyzer","authors":"Y. Damizia ,&nbsp;S. Elmore ,&nbsp;P. Ryan ,&nbsp;S. Allan ,&nbsp;F. Federici ,&nbsp;N. Osborne ,&nbsp;J.W. Bradley ,&nbsp;MAST-U Team","doi":"10.1016/j.nme.2025.101912","DOIUrl":"10.1016/j.nme.2025.101912","url":null,"abstract":"<div><div>This study presents the first ion temperature (<span><math><msub><mrow><mi>T</mi></mrow><mrow><mi>i</mi></mrow></msub></math></span>) measurements from the MAST-U divertor using a Retarding Field Energy Analyzer (RFEA). Embedded within the flat tile of the closed divertor chamber, the RFEA captures <span><math><msub><mrow><mi>T</mi></mrow><mrow><mi>i</mi></mrow></msub></math></span> profiles across various plasma scenarios, including transitions to the Super-X configuration. Measurements were conducted under steady-state and transient plasma conditions characterized by a plasma current (<span><math><msub><mrow><mi>I</mi></mrow><mrow><mi>p</mi></mrow></msub></math></span>) of 750 kA, electron density (<span><math><msub><mrow><mi>n</mi></mrow><mrow><mi>e</mi></mrow></msub></math></span>) between <span><math><mrow><mn>2</mn><mo>.</mo><mn>2</mn><mo>×</mo><mn>1</mn><msup><mrow><mn>0</mn></mrow><mrow><mn>19</mn></mrow></msup></mrow></math></span> and <span><math><mrow><mn>4</mn><mo>.</mo><mn>4</mn><mo>×</mo><mn>1</mn><msup><mrow><mn>0</mn></mrow><mrow><mn>19</mn></mrow></msup><mspace></mspace><msup><mrow><mtext>m</mtext></mrow><mrow><mo>−</mo><mn>3</mn></mrow></msup></mrow></math></span>, and Neutral Beam Injection (NBI) power ranging from 3.0 MW to 3.2 MW. The ion temperatures, peaking at approximately 17 eV in steady state, were compared with electron temperatures (<span><math><msub><mrow><mi>T</mi></mrow><mrow><mi>e</mi></mrow></msub></math></span>) obtained from Langmuir probes (LP) at identical radial positions. Preliminary findings reveal a <span><math><mrow><msub><mrow><mi>T</mi></mrow><mrow><mi>i</mi></mrow></msub><mo>/</mo><msub><mrow><mi>T</mi></mrow><mrow><mi>e</mi></mrow></msub></mrow></math></span> ratio ranging from 1 to 2.2. Additionally, high temporal resolution measurements (<span><math><mrow><mn>100</mn><mspace></mspace><mi>μ</mi><mi>s</mi></mrow></math></span>) captured the dynamics of Edge Localized Modes (ELMs), showing <span><math><msub><mrow><mi>T</mi></mrow><mrow><mi>i</mi></mrow></msub></math></span> peaks at 16 ±1.8 eV during ELM events, nearly three times higher than inter-ELM temperatures.</div></div>","PeriodicalId":56004,"journal":{"name":"Nuclear Materials and Energy","volume":"43 ","pages":"Article 101912"},"PeriodicalIF":2.3,"publicationDate":"2025-03-10","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143600969","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":2,"RegionCategory":"物理与天体物理","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"OA","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Reimplantation of supporting legs on EAST divertor by electron beam brazing","authors":"Yu Tian ,&nbsp;Yu-Ping Xu ,&nbsp;Chang Xu ,&nbsp;Wu-Qingliang Peng ,&nbsp;An-Bang Wu ,&nbsp;Jian-Ping Qu ,&nbsp;Fang-Yong Du ,&nbsp;Peng-Fei Zi ,&nbsp;Qiang Li ,&nbsp;Wan-Jing Wang ,&nbsp;Hai-Shan Zhou ,&nbsp;Guang-Nan Luo","doi":"10.1016/j.nme.2025.101918","DOIUrl":"10.1016/j.nme.2025.101918","url":null,"abstract":"<div><div>The supporting legs at the back of the ITER-like W/Cu monoblock in the upper divertor of the Experimental Advanced Superconducting Tokamak (EAST) were found fractured due to the influence of electromagnetic forces, vertical displacement events (VDEs) and its own weight. This study developed an electron beam brazing (EBB) technique for the reimplantation of supporting legs. Defect-free bonding between Inconel 625 (IN625) alloy and pure tungsten was obtained with the tensile strength exceeding 110 MPa. Microstructural analysis revealed a columnar grain structure on the tungsten side and finer grains on the IN625 side. Nanoindentation tests indicated that the brazed interface exhibited a lower average stiffness of 1660 μN/nm and a lower average hardness of 1.48 GPa, ensuring enhanced plasticity and improved load-bearing capacity. This work provides a novel proposal to reimplant supporting legs on divertor components by EBB in terms of achieving microstructural refinement and high strength.</div></div>","PeriodicalId":56004,"journal":{"name":"Nuclear Materials and Energy","volume":"43 ","pages":"Article 101918"},"PeriodicalIF":2.3,"publicationDate":"2025-03-10","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143600967","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":2,"RegionCategory":"物理与天体物理","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"OA","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Hermes-3 simulation of the low-n X-point mode driven by impurity in tokamak edge plasmas","authors":"Huayi Chang ,&nbsp;Benjamin Dudson ,&nbsp;Jizhong Sun ,&nbsp;Mike Kryjak ,&nbsp;Yang Ye ,&nbsp;Mao Li ,&nbsp;Weikang Wang","doi":"10.1016/j.nme.2025.101913","DOIUrl":"10.1016/j.nme.2025.101913","url":null,"abstract":"<div><div>Hermes-3, a multi-fluid plasma simulation tool is applied to investigate the low-n X-point mode driven by coupling between drift wave and impurity radiation condensation instability in tokamak edge plasmas. The radiation loss function of impurities under noncoronal equilibrium approximation is employed to better study the physics near the Scrape-Off Layer (SOL) in tokamaks. Firstly, the linear growth rates and frequencies of these instabilities are investigated in slab geometry for various impurities: He, Li, B, C, N, Ne, and Ar, over a broad range of impurity density and electron temperature. The results indicate that each impurity species presents varying excitation conditions for the low-n modes. While He and Li show limited ability to destabilize the modes, B, C, and N effectively initiate the instability at relatively low temperature. In contrast, Ne and Ar are more likely to destabilize the modes at higher temperature. It is found that for He, C, N and Ar, the low-frequency region is the one that tends to trigger instability. Subsequently, in the tokamak EAST geometry, the impact of impurity C near the X-point is analyzed with different toroidal mode numbers. The dominant mode of the low-n modes is found to be <span><math><mrow><mi>n</mi><mo>=</mo><mn>1</mn></mrow></math></span>, which is consistent with experimental observations. The study also explores the influence of impurity pressure on electron pressure, implying that there is a limit for impurity pressure to induce this mode.</div></div>","PeriodicalId":56004,"journal":{"name":"Nuclear Materials and Energy","volume":"43 ","pages":"Article 101913"},"PeriodicalIF":2.3,"publicationDate":"2025-03-07","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143600968","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":2,"RegionCategory":"物理与天体物理","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"OA","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Deuterium retention in pre-lithiated samples and Li–D co-deposits in the DIII-D tokamak","authors":"M. Morbey ,&nbsp;F. Effenberg ,&nbsp;S. Abe ,&nbsp;T. Abrams ,&nbsp;A. Bortolon ,&nbsp;R. Hood ,&nbsp;U. Losada ,&nbsp;A. Nagy ,&nbsp;J. Ren ,&nbsp;D.L. Rudakov ,&nbsp;M.J. Simmonds ,&nbsp;D. Truong ,&nbsp;T.W. Morgan","doi":"10.1016/j.nme.2025.101915","DOIUrl":"10.1016/j.nme.2025.101915","url":null,"abstract":"<div><div>Divertor designs involving liquid lithium have been proposed as an alternative to solid designs and wall conditioning techniques. However, Li affinity with tritium poses a risk for the fuel cycle. This study investigates deuterium retention in pre-lithiated samples and Li–D co-deposits in the DIII-D tokamak, making for the first time a direct comparison between Li–D co-deposits and pre-deposited Li films. Samples were exposed to H-mode plasmas in the far scrape-off layer (SOL), and Li powder was injected in-situ with the impurity powder dropper to study the uniformity of Li coatings, and the dependence of fuel retention on Li thickness. The results show that at temperatures below the melting point of lithium, deuterium retention is independent of the thickness of pre-deposited Li layers, with Li–D co-deposits being the primary factor for fuel retention. Both pre-deposited and in-situ deposited Li showed lower erosion than predicted by sputtering yield calculations. These results suggest that fuel retention in fusion reactors using lithium in the divertor will likely be dominated by co-deposits rather than in the divertor itself. If one desires to use Li to achieve flatter temperature profiles, operando Li injection is advantageous over pre-deposited Li films, at least at temperatures below the melting point of lithium.</div></div>","PeriodicalId":56004,"journal":{"name":"Nuclear Materials and Energy","volume":"43 ","pages":"Article 101915"},"PeriodicalIF":2.3,"publicationDate":"2025-03-07","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143628976","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":2,"RegionCategory":"物理与天体物理","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"OA","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}