Nuclear Materials and Energy最新文献

{"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":"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":"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":"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}

{"title":"Tritium release performance of neutron-irradiated core–shell Li2TiO3-Li4SiO4 pebbles","authors":"Shouxi Gu ,&nbsp;Qiang Qi ,&nbsp;Fei Sun ,&nbsp;Yingchun Zhang ,&nbsp;Yasuhisa Oya ,&nbsp;Hai-Shan Zhou ,&nbsp;Guang-Nan Luo","doi":"10.1016/j.nme.2025.101917","DOIUrl":"10.1016/j.nme.2025.101917","url":null,"abstract":"<div><div>To enhance the mechanical strength of Li₄SiO₄ and reduce its sensitivity to carbon dioxide and water, advanced tritium breeder core–shell Li₂TiO₃-Li₄SiO₄ was designed and fabricated by graphite bed method. The 1:1 phase ratio between Li₂TiO₃ and Li₄SiO₄ was confirmed by X-ray diffraction (XRD) and Rietveld refinement. Scanning electron microscopy (SEM) revealed that submicron-sized Li₂TiO₃ grains aggregated at the grain boundaries of Li₄SiO₄. Micro-computed tomography (Micro-CT) distinctly illustrated the shell-structure and the three-dimensional distribution of internal pores, aligning with the original design requirements and expectations. Neutron irradiation and out-of-pile tritium release experiments were conducted to evaluate the tritium release performance. Temperature-programmed desorption tritium release spectra exhibited two distinct release peaks, occurring at approximately 312 and 478 °C. The corresponding desorption activation energies were calculated using varying heating rates, yielding values of 0.63 eV and 1.64 eV, respectively. Isothermal desorption experiments indicated that complete release of residual tritium can be achieved at temperatures exceeding 400 °C. The tritium release rate-controlling process was found to be primarily diffusion of tritium through the crystal, with an effective diffusivity of 3.73 × 10^-6exp(−1.35 eV/kT) m²/s.</div></div>","PeriodicalId":56004,"journal":{"name":"Nuclear Materials and Energy","volume":"43 ","pages":"Article 101917"},"PeriodicalIF":2.3,"publicationDate":"2025-03-06","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143592120","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 in operando transient grating spectroscopy measurements on tungsten during high flux plasma operation in PISCES-RF","authors":"M.J. Simmonds ,&nbsp;A. Založnik ,&nbsp;S. Moore ,&nbsp;D. Nishijima ,&nbsp;M.I. Patino ,&nbsp;B. Dacus ,&nbsp;A. Lanzrath ,&nbsp;M.P. Short ,&nbsp;K. Woller ,&nbsp;A. Wylie ,&nbsp;M.J. Baldwin ,&nbsp;G.R. Tynan","doi":"10.1016/j.nme.2025.101911","DOIUrl":"10.1016/j.nme.2025.101911","url":null,"abstract":"<div><div>This work details the construction and first in operando transient grating spectroscopy measurements conducted on PISCES-RF during plasma operation. A preliminary study on a tungsten sample with varied plasma species (Ar and D<span><math><msub><mrow></mrow><mrow><mn>2</mn></mrow></msub></math></span>), ion flux (4 × 10²¹ to 6 × 10²² ion/m<span><math><msup><mrow></mrow><mrow><mn>2</mn></mrow></msup></math></span>/s), ion energy (5 to 80 eV), and surface temperature (20 to 200 °C) is presented. Prior to plasma exposure, the thermal diffusivity and surface acoustic wave (SAW) speed, (6.9 ± 0.2)<span><math><mo>×</mo></math></span>10⁻⁵ m<span><math><msup><mrow></mrow><mrow><mn>2</mn></mrow></msup></math></span>/s and (2.66 ± 0.02) km/s, were measured in situ with a thermal grating period of 12.5 <span><math><mrow><mi>μ</mi><mtext>m</mtext></mrow></math></span>. During Ar plasma exposure, these two quantities vary according to the sample surface temperature. At low flux and varied ion energy, D<span><math><msub><mrow></mrow><mrow><mn>2</mn></mrow></msub></math></span> plasma exposure also results in thermal diffusivity and SAW speed varying with surface temperature alone. At high flux, D<span><math><msub><mrow></mrow><mrow><mn>2</mn></mrow></msub></math></span> plasma exposure results in no convincing change to the thermal diffusivity, but the SAW speed is reduced. After returning to 20 °C, post plasma exposures, the thermal diffusivity and SAW speed almost recover to the initial value prior to exposure.</div></div>","PeriodicalId":56004,"journal":{"name":"Nuclear Materials and Energy","volume":"43 ","pages":"Article 101911"},"PeriodicalIF":2.3,"publicationDate":"2025-03-05","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143592119","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":"The quasi-continuous exhaust regime in ASDEX Upgrade and JET","authors":"M. Faitsch ,&nbsp;M. Dunne ,&nbsp;E. Lerche ,&nbsp;P. Lomas ,&nbsp;I. Balboa ,&nbsp;P. Bilkova ,&nbsp;P. Bohm ,&nbsp;L. Gil ,&nbsp;G.F. Harrer ,&nbsp;A. Kappatou ,&nbsp;D. Kos ,&nbsp;B. Labit ,&nbsp;L. Radovanovic ,&nbsp;A. Redl ,&nbsp;O. Sauter ,&nbsp;S. Silburn ,&nbsp;E.R. Solano ,&nbsp;A. Tookey ,&nbsp;E. Viezzer ,&nbsp;E. Wolfrum ,&nbsp;U. Stroth","doi":"10.1016/j.nme.2025.101904","DOIUrl":"10.1016/j.nme.2025.101904","url":null,"abstract":"<div><div>The quasi-continuous exhaust (QCE) regime is a type-I ELM-free high confinement regime obtained at high plasma shaping and high separatrix density. A comparison with various ELM-free regimes in the literature is presented together with potential physics models for accessing the QCE regime. The regime was recently successfully ported from ASDEX Upgrade to JET. We present a first comparison between the achieved plasma conditions in the two tokamaks and an extrapolation towards ITER and EU-DEMO parameters. The step in size from ASDEX Upgrade to JET successfully lowered the pedestal top collisionality, demonstrating that the regime is not limited to high collisionality at the pedestal top but naturally operates at high density. The extrapolation to ITER and EU-DEMO parameters shows that they can reach the conditions in which ASDEX Upgrade and JET are operating in QCE without type-I ELMs applying previously proposed physics models.</div></div>","PeriodicalId":56004,"journal":{"name":"Nuclear Materials and Energy","volume":"42 ","pages":"Article 101904"},"PeriodicalIF":2.3,"publicationDate":"2025-03-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143510042","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":"Plasma heat load in the toroidal gaps of the ITER-like plasma facing units in WEST tokamak","authors":"Q. Tichit ,&nbsp;M.H. Aumeunier ,&nbsp;Y. Corre ,&nbsp;R. Dejarnac ,&nbsp;L. Dubus ,&nbsp;J. Gaspar ,&nbsp;J. Gerardin ,&nbsp;A. Grosjean ,&nbsp;J.P. Gunn ,&nbsp;A. Juven ,&nbsp;K. Krieger ,&nbsp;A. Podolník ,&nbsp;E. Tsitrone","doi":"10.1016/j.nme.2025.101899","DOIUrl":"10.1016/j.nme.2025.101899","url":null,"abstract":"<div><div>The heat load deposited in the toroidal gaps between two tungsten monoblocks remains an open problem to prepare safe and powerful experiments in ITER. An experiment has been carried out on the WEST tokamak aiming to study the power deposition on the toroidal surfaces with various monoblock and heat loading configurations. The very high spatial resolution (0.1 mm/px) infrared camera of WEST has been used to monitor the temperature distribution on the blocks. Few actively cooled ITER-like plasma facing units have been misaligned in the vertical and poloidal direction to maximize the heat loading and temperature on specific block areas. This paper shows the experimental results obtained during high power plasma experiment (4.5 MW injected power) performed with the outer strike line located precisely in the toroidal gap. The experimental IR images exhibit complex pattern with strong signal into the gap (greater than measured on the top surface) and shifted hot spot on the poloidal chamfer of the downstream component featuring poloidal misalignment (where optical hot spot are expected). Thermal and photonic modelling have been used to mimic the infrared thermal scene an try to provide a better understanding of the heat loading on the toroidal edge and on the optical hot spots. The importance of specular reflection is highlighted in the two cases because the reflective facets of the block facing each other.</div></div>","PeriodicalId":56004,"journal":{"name":"Nuclear Materials and Energy","volume":"42 ","pages":"Article 101899"},"PeriodicalIF":2.3,"publicationDate":"2025-03-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143520753","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}