Nuclear Materials and Energy最新文献

{"title":"Boundary plasma studies for a spherical tokamak with lithium walls","authors":"A. Antony ,&nbsp;L. Carbajal ,&nbsp;T.D. Rognlien ,&nbsp;M.V. Umansky ,&nbsp;A. Froese ,&nbsp;S. Howard ,&nbsp;C. Ribeiro ,&nbsp;R. Ivanov ,&nbsp;C. Dunlea ,&nbsp;C.P. McNally","doi":"10.1016/j.nme.2025.101885","DOIUrl":"10.1016/j.nme.2025.101885","url":null,"abstract":"<div><div>Boundary plasma and plasma-material interactions are investigated for magnetised target fusion (MTF) applications. The General Fusion magnetised target fusion technology uses coaxial helicity injection (CHI) start-up which forms a spherical tokamak in a cavity with liquid lithium walls that will subsequently be compressed to fusion conditions Laberge, J. Fusion Energy (2019) The Plasma Injector 3 (PI3) experiment at General Fusion is a non-compressing experiment with solid lithium walls that studies the formation and quasi-steady state operation of a CHI spherical tokamak Carbajal et al. (2023). An explorative study is carried out for wall-limited versus diverted configurations for PI3 using the fluid edge transport code UEDGE. Experimental edge temperature and density profiles from triple Langmuir probes are used to establish realistic temperature and density profiles in UEDGE Rognlien et al. (1992) by adjusting the transport coefficients. In UEDGE, we model the wall-limited plasma via a thin limiter with various insertion depths. It is found that limiter depth and location are key parameters in determining radial profiles and sputtered lithium behaviour. Furthermore, it is found that the total sputtering of the limiter is significantly lower than the sputtering of the wall in some of the limiter configurations studied. Lithium ions and neutral behaviour are compared between limited and diverted configurations.</div></div>","PeriodicalId":56004,"journal":{"name":"Nuclear Materials and Energy","volume":"42 ","pages":"Article 101885"},"PeriodicalIF":2.3,"publicationDate":"2025-01-31","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143174235","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-principles calculations for the effect of irradiation-induced point defects on the hydrogen dissolution and diffusion in γ-Al2O3","authors":"Xin-Dong Pan ,&nbsp;Xiao-Chun Li ,&nbsp;Jing Wang ,&nbsp;Rongmei Yu ,&nbsp;Chunying Pu ,&nbsp;Hai-Shan Zhou ,&nbsp;Guang-Nan Luo","doi":"10.1016/j.nme.2025.101890","DOIUrl":"10.1016/j.nme.2025.101890","url":null,"abstract":"<div><div>FeAl/Al₂O₃ is considered the most promising candidate material for tritium permeation barrier (TPB) due to numerous advantages. γ-Al₂O₃ phase structure is commonly found in FeAl/Al₂O₃, and is crucial to its effectiveness. In fusion reactors, high-energy neutrons generate a large number of irradiation-induced defects, significantly affecting the performance of γ-Al₂O₃. The underlying mechanism is still unclear. This study focuses on the influence of irradiation-induced point defects on the dissolution and diffusion of H in γ-Al₂O₃ using first-principles theory. Our results show that the irradiation-induced point defect exhibit a strong ability to capture dissolved H atoms, leading to higher hydrogen retention. When dissolved H atoms are captured by vacancy-type defects, the diffusion barrier becomes so high that isolated vacancy-type irradiation-induced point defects can hinder the diffusion of H atoms. This in turn enhances the effectiveness of TPB in preventing H permeation. Furthermore, the impediment effect of Al vacancies on H diffusion in γ-Al₂O₃ is higher than that in α-Al₂O₃, whereas O vacancies have the opposite effect, impeding H diffusion in γ-Al₂O₃ less than in α-Al₂O₃. However, the diffusion barrier of O interstitial atoms and H as a bound entity is only 0.11 eV, which is even far lower than that in α-Al₂O₃ (0.44 eV). Therefore, O interstitial atoms can accelerate the diffusion process of H, which can reduce the efficiency of protection against H permeation through γ-Al₂O₃ TPB. The accelerating effect in γ-Al₂O₃ is higher than that in α-Al₂O₃. These findings provide valuable insights into the influence of irradiation-induced point defects on H behavior in γ-Al₂O₃, which is essential for improving the efficiency of FeAl/Al₂O₃ tritium permeation barriers.</div></div>","PeriodicalId":56004,"journal":{"name":"Nuclear Materials and Energy","volume":"42 ","pages":"Article 101890"},"PeriodicalIF":2.3,"publicationDate":"2025-01-30","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143173087","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":"Addressing the impact of Lyman opacity in inference of divertor plasma conditions with 2D spectroscopic camera analysis of Balmer emission during detachment in JET L-mode plasmas","authors":"J. Karhunen ,&nbsp;B. Lomanowski ,&nbsp;S. Aleiferis ,&nbsp;P. Carvalho ,&nbsp;M. Groth ,&nbsp;A. Holm ,&nbsp;K.D. Lawson ,&nbsp;A.G. Meigs ,&nbsp;A. Shaw ,&nbsp;V. Solokha ,&nbsp;JET Contributors ,&nbsp;EUROfusion Tokamak Exploitation Team","doi":"10.1016/j.nme.2025.101880","DOIUrl":"10.1016/j.nme.2025.101880","url":null,"abstract":"<div><div>The impact of re-absorption of the deuterium Lyman series emission was addressed in inferring divertor plasma conditions from Balmer series emission with 2D spectroscopic camera analysis during detachment in JET L-mode plasmas. The previously presented methodology was amended by modifying the standard photon emission coefficients and ionization and recombination rate coefficients of the ADAS database to consider the re-population of excited states due to Lyman opacity. This resulted in the estimate for the atomic density near the outer strike point to decrease by up to 75% at the onset of detachment at strike point temperatures of <span><math><mrow><msub><mrow><mi>T</mi></mrow><mrow><mi>e,osp</mi></mrow></msub><mo>≈</mo></mrow></math></span> 1.0–3.0 eV with respect to the strongly overestimated previously obtained values, whereas the estimated electron temperature and density were unaffected by the opacity correction within the scatter of the data and only a moderate reduction by up to 20% was observed in the estimate for the molecularly induced fraction of the Balmer emission. No noticeable change was seen in the ionization rate, calculated from the estimated outer strike point conditions, due to the decrease in the atomic density estimate compensating for the increased values of the opacity-corrected ADAS rate coefficients for ionization. In detached conditions at <span><math><mrow><msub><mrow><mi>T</mi></mrow><mrow><mi>e,osp</mi></mrow></msub><mo>≈</mo></mrow></math></span> 0.5–1.0 eV, 25%–35% lower recombination rates were provided by the opacity-corrected model. The observed effects on the experimental analysis were supported by a corresponding synthetic analysis based on EDGE2D-EIRENE simulations.</div></div>","PeriodicalId":56004,"journal":{"name":"Nuclear Materials and Energy","volume":"42 ","pages":"Article 101880"},"PeriodicalIF":2.3,"publicationDate":"2025-01-28","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143174244","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":"Tungsten erosion during L-mode discharges in the DIII-D SAS-VW divertor","authors":"G. Sinclair ,&nbsp;T. Abrams ,&nbsp;M.S. Parsons ,&nbsp;S.H. Messer ,&nbsp;J. Mateja ,&nbsp;S.A. Zamperini ,&nbsp;D.M. Thomas ,&nbsp;J.D. Elder ,&nbsp;R. Maurizio ,&nbsp;T. Odstrcil ,&nbsp;R.S. Wilcox ,&nbsp;J.L. Herfindal ,&nbsp;D.D. Truong ,&nbsp;J.G. Watkins ,&nbsp;A.G. McLean ,&nbsp;D.L. Rudakov ,&nbsp;J. Ren ,&nbsp;D. Donovan","doi":"10.1016/j.nme.2025.101884","DOIUrl":"10.1016/j.nme.2025.101884","url":null,"abstract":"<div><div>A series of L-mode plasma discharges was performed in the DIII-D tokamak to assess the impact of outer strike point (OSP) position and toroidal magnetic field direction on erosion and core contamination potential of the recently-installed, tungsten-coated Small Angle Slot (SAS-VW) divertor. In one discharge, in-slot emission spectroscopy measured an &lt; 48 % increase in the W gross erosion rate when the OSP was moved 3 cm outwards, away from the V-shaped vertex of the slot divertor. However, the effective W yield (erosion rate divided by the incident D flux) was, overall, insensitive to changes in OSP location. Consistently low estimates of the effective W yield based on measurements taken a few cm outwards from the vertex suggest potentially significant C surface contamination. No W emission signal was detected when orienting the toroidal magnetic field such that the ion B×∇B drift direction is pointed away from the X-point. However, measurements of W content in the plasma core for both toroidal magnetic field directions suggest the presence of additional, unmeasured sources of erosion. The difference in the measured core W density with OSP position is much greater than the difference in the measured erosion rates, which may suggest that the leakage of eroded impurities out of the divertor is governed primarily through the parallel ion temperature gradient and friction forces.</div></div>","PeriodicalId":56004,"journal":{"name":"Nuclear Materials and Energy","volume":"42 ","pages":"Article 101884"},"PeriodicalIF":2.3,"publicationDate":"2025-01-26","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143343830","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":"Integrated modelling of lithium transport and radiation under a liquid lithium divertor on EAST","authors":"Z.X. Wen ,&nbsp;Z.H. Gao ,&nbsp;B. Liu ,&nbsp;Z. Zhou ,&nbsp;Z.C. Lin ,&nbsp;Y. Feng ,&nbsp;S.Y. Dai","doi":"10.1016/j.nme.2025.101881","DOIUrl":"10.1016/j.nme.2025.101881","url":null,"abstract":"<div><div>The edge transport and core accumulation of lithium (Li) impurity under a liquid Li divertor on EAST have been investigated by the EMC3-EIRENE and STRAHL codes, respectively. At the edge region, the Li density distribution and power dissipation derived from divertor targets have been simulated by EMC3-EIRENE modeling. At the core region, the ONETWO and TGYRO codes are used to calculate the Li transport coefficients for STRAHL modeling, which is implemented through the OMFIT framework. At the core–edge transition region (<span><math><mrow><msub><mi>Ψ</mi><mi>N</mi></msub><mspace></mspace></mrow></math></span> = 0.95 ∼ 1.02, <span><math><mrow><msub><mi>Ψ</mi><mi>N</mi></msub></mrow></math></span> is the normalized poloidal flux coordinate), the representative distribution of <span><math><mrow><msup><mrow><mi>L</mi><mi>i</mi></mrow><mrow><mn>2</mn><mo>+</mo></mrow></msup></mrow></math></span> ion density is used for the comparison between EMC3-EIRENE and STRAHL modellings, which can achieve a reasonable agreement between two codes. On this basis, the Li-ion core density and radiation distributions have been analyzed by STRAHL modeling, which indicates there exist two radiation peaks located at the magnetic axis and <span><math><mrow><msub><mi>Ψ</mi><mi>N</mi></msub></mrow></math></span> = 1.01. The impacts of Li radiation on H-L back transition have been studied by Martin’s threshold power scaling law (Martin <em>et al</em> 2008<em>J Phys Conf Ser</em> 123 012033). The core radiation of lithium has a limited impact on the operation regime of EAST. Even for the maximum lithium effective sputtering coefficient of 0.1 used in the current study, it is still insufficient to cause H-L back transition.</div></div>","PeriodicalId":56004,"journal":{"name":"Nuclear Materials and Energy","volume":"42 ","pages":"Article 101881"},"PeriodicalIF":2.3,"publicationDate":"2025-01-25","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143173569","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":"Prediction of post-irradiation swelling rate of 316L stainless steel based on Variational Autoencoders and interpretable machine learning","authors":"Chengcheng Liu ,&nbsp;Hang Su","doi":"10.1016/j.nme.2025.101879","DOIUrl":"10.1016/j.nme.2025.101879","url":null,"abstract":"<div><div>In the field of materials science, accurately predicting the swelling rate of materials in irradiated environments is crucial for ensuring safety and reliability. This study aims to enhance the predictive accuracy of the swelling rate of irradiated 316L stainless steel, particularly in high-tech applications such as nuclear energy. By comparing various machine learning models, it was found that the Extreme Trees Regression (ETR) model performed best on the test set, achieving an R² of 0.79 and a Root Mean Square Error (RMSE) of 1.65 %. Although it demonstrated strong generalization capabilities, the limited data volume restricted its predictive accuracy. To address this issue, the study employed Variational Autoencoders (VAEs) for data augmentation, generating an additional 400 synthetic data points to expand the original dataset. This enhancement increased the R² on the test set to 0.91 and reduced the RMSE to 1.11 %. Following data augmentation, feature selection was conducted, resulting in Si, C, IrF, T, and Dd being identified as the optimal feature combination. SHapley Additive exPlanations (SHAP) was then utilized for interpretability analysis, revealing the significant effects of these features on the swelling rate. The findings provide essential insights for understanding and optimizing the swelling behavior of materials following irradiation.</div></div>","PeriodicalId":56004,"journal":{"name":"Nuclear Materials and Energy","volume":"42 ","pages":"Article 101879"},"PeriodicalIF":2.3,"publicationDate":"2025-01-23","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143173567","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":"A new method for preparing high-quality and fatigue-resistant divertor W/Cu joints","authors":"Nanyu Mou ,&nbsp;Qianqian Lin ,&nbsp;Mingchi Feng ,&nbsp;Shuai Huang ,&nbsp;Le Han ,&nbsp;Damao Yao","doi":"10.1016/j.nme.2025.101882","DOIUrl":"10.1016/j.nme.2025.101882","url":null,"abstract":"<div><div>Due to the insolubility between W and Cu and the inability to generate intermetallic compounds, connecting W and Cu poses a considerable challenge. In this study, a casting assisted vacuum hot pressing (VHP) method is adopted to join W and Cu, and the process parameters are optimized. The casting temperature is 1180 °C and the most suitable bonding parameters are a bonding temperature of 650 °C, a bonding pressure of 25 MPa and a bonding time of 90 min. The obtained W/Cu joint exhibits an average shear strength of 138.0 MPa and with no detectable defects on the interface. The effective bonding area of W/Cu joints exceed 98 %. The thermal conductivity of W/Cu prepared by casting assisted VHP is 347, 288, and 257 W/m·K at room temperature, 500 °C, and 900 °C, respectively, exceeding that of W/Cu prepared by casting assisted hot isostatic pressing (HIP) at the corresponding temperatures. The heat transfer performance and structural integrity of the prepared divertor mockup remain satisfactory after 1000 cycles at 20 MW/m², with a peak surface temperature of 725.7 ℃. The proposed method provides a new strategy for preparing high-performance and fatigue resistant W/Cu joints, to address the issues of low bonding performance as well as poor fatigue resistance.</div></div>","PeriodicalId":56004,"journal":{"name":"Nuclear Materials and Energy","volume":"42 ","pages":"Article 101882"},"PeriodicalIF":2.3,"publicationDate":"2025-01-23","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143173568","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":"Comparative studies of tungsten erosion and edge transport under partially detached divertor condition of CFETR with neon and argon seedings","authors":"Hui Wang ,&nbsp;Guoliang Xu ,&nbsp;Rui Ding ,&nbsp;Hang Si ,&nbsp;Guozhang Jia ,&nbsp;Jin Guo ,&nbsp;Jinheng Zhao ,&nbsp;Junling Chen","doi":"10.1016/j.nme.2025.101878","DOIUrl":"10.1016/j.nme.2025.101878","url":null,"abstract":"<div><div>Neon (Ne) and argon (Ar) impurity seedings are recognized as effective techniques for reducing the divertor heat load in high-power operations of future reactors like CFETR. However, their influence on tungsten (W) erosion and edge transport remains unclear. Based on previously published SOLPS-ITER simulation results ([H. Si et al 2022 Nucl. Fusion 62 026031]), this study investigates the effects of Ne and Ar seedings on the W source and edge transport under partially detached divertor conditions on CFETR by DIVIMP simulations. The transport processes of Ne and Ar impurities in the boundary plasma are evaluated, with Ar expected to have better compression. Under similar partial detachment divertor conditions with the same total radiation power loss, the W leakage ability from divertor to the core plasma is demonstrated to be similar for Ne and Ar seeding cases. However, the W density in the core plasma is approximately four times lower in the Ar seeding case compared to the Ne seeding case, primarily due to the smaller W source from the divertor target. Therefore, the Ar seeding is proved to be more beneficial for reducing the W source and core W concentration than the Ne seeding.</div></div>","PeriodicalId":56004,"journal":{"name":"Nuclear Materials and Energy","volume":"42 ","pages":"Article 101878"},"PeriodicalIF":2.3,"publicationDate":"2025-01-20","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143173099","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 study of neon retention and release behaviour from Be layers deposited under distinct temperature, pressure and ion energy conditions","authors":"P. Dinca ,&nbsp;C. Staicu ,&nbsp;B. Butoi ,&nbsp;B.G. Solomonea ,&nbsp;A. Anghel ,&nbsp;O.G. Pompilian ,&nbsp;G. Bulai ,&nbsp;V. Tiron","doi":"10.1016/j.nme.2025.101877","DOIUrl":"10.1016/j.nme.2025.101877","url":null,"abstract":"&lt;div&gt;&lt;div&gt;The purpose of this work is to carry out a systematic parametric study on neon (Ne) retention and release behaviour from Be/Ne layers co-deposited under ITER-relevant conditions, in terms of deposition temperature, gas pressure and ion energy. This study incorporates analyses of structural and morphological properties of Be/Ne coatings, along with Ne retention/release behaviour. A total of 27 batches of Be/Ne layers were deposited onto silicon (Si) and tungsten (W) substrates by adjusting to several selected values (&lt;em&gt;i&lt;/em&gt;) the working gas pressure (1 Pa, 2 Pa, 3 Pa), (&lt;em&gt;ii&lt;/em&gt;) the ion energy of the plasma species (30 eV, 100 eV, 200 eV) and (&lt;em&gt;iii&lt;/em&gt;) the substrate temperature during deposition (340 K, 473 K, 573 K). The chosen deposition method was the novel Bipolar-High Power Impulse Magnetron Sputtering (BP-HiPIMS) technique due to its high ionization degree of the plasma species and its versatility in controlling the ion flux and energy during the deposition process. For a more comprehensive understanding, of how plasma properties, coatings’ structure, retention and release behaviour of Ne from the deposited samples correlate to each other, plasma-diagnosis was performed. The influence of gas pressure and pulsing configuration on ion energy and flux was investigated. The coating’s morphology and microstructure were analysed by Scanning Electron Microscopy (SEM), Atomic Force Microscopy (AFM) and X-ray diffraction (XRD). The surface’s morphology of the Be-Ne layers deposited at 340 K indicates smooth layers, with surface roughness values independent of the working gas pressure and ion energy. SEM images of the layers produced at temperatures higher than 340 K suggest the formation of blister-like structures on their surface. Unsurprisingly, the crystalline structure is strongly dependent on the substrate temperature. Metallic Be crystalline phase is observed for layers deposited at 473 K and 573 K, while, for the lowest substrate temperature (340 K), the structure of the Be-Ne layers was found to be amorphous, regardless of the working gas pressure and/or ion energy used during the deposition process. Ne/Be ratio in the deposited layers was evaluated through Thermal Desorption Spectroscopy (TDS) measurements. The results show an increase in the Ne content in layers with the increase of working gas pressure and ion energy. Although the Ne inventory is released above 1000 K, the increase of substrate temperature during deposition changes the microstructure of the Be layer, leading to a significantly lower Ne retention. The empirical scaling equation was developed assuming that the Ne/Be ratio is proportional to the deposition rate of Be and the ion energy, obeying an Arrhenius-type temperature dependence. The resulting model accurately fits the experimental data obtained for the following conditions: substrate temperature 473 K ≤ T ≤ 573 K; deposition rate 0.04 nm/s ≤ r&lt;sub&gt;d&lt;/sub&gt; ≤ 0.12 nm/s; ion energy 30 eV &lt; &lt;em&gt;E&lt;","PeriodicalId":56004,"journal":{"name":"Nuclear Materials and Energy","volume":"42 ","pages":"Article 101877"},"PeriodicalIF":2.3,"publicationDate":"2025-01-19","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143173097","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":"Determination of tritium inventory in carbon divertor tiles used in deuterium plasma experiment by induction heating method","authors":"Masahiro Tanaka ,&nbsp;Hiromi Kato ,&nbsp;Naoyuki Suzuki ,&nbsp;Hiroki Chimura ,&nbsp;Hiroaki Yonezu ,&nbsp;Suguru Masuzaki","doi":"10.1016/j.nme.2025.101876","DOIUrl":"10.1016/j.nme.2025.101876","url":null,"abstract":"<div><div>The tritium inventory of the plasma-facing materials in a Large Helical Device (LHD) was analyzed using a thermal desorption system. In this study, we developed an induction heating system for the thermal desorption of tritium from carbon divertor tiles, which has several advantages, including a rapid temperature rise, internal heating via eddy currents, and heating with the original size and shape of the carbon tile. The apparatus was capable of heating a carbon divertor tile to a temperature greater than 1373 K over 20 min. Following a 12-h heating period at 1423 K, the tritium release rate from the carbon tile was 99.7 %. The chemical form of the tritium released from the divertor tiles was approximately 80 % molecular hydrogen, with the remaining tritium in the form of water vapor. The results of the tritium analysis of the divertor tiles suggest that the tritium distribution in the divertor region is not uniform, and that the flux varies from location to location in the LHD. To improve the accuracy of the tritium inventory analysis in an LHD vacuum vessel, it is essential to conduct a tritium inventory analysis of other plasma-facing materials.</div></div>","PeriodicalId":56004,"journal":{"name":"Nuclear Materials and Energy","volume":"42 ","pages":"Article 101876"},"PeriodicalIF":2.3,"publicationDate":"2025-01-18","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143173098","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}