Pub Date : 2024-11-12DOI: 10.1016/j.nme.2024.101812
Huace Wu , Rongxing Yi , Anne Houben , Sebastijan Brezinsek , Marcin Rasinski , Cong Li , Gennady Sergienko , Yunfeng Liang , Timo Dittmar , Hongbin Ding
Boronization is used in present-devices as wall condition technique due to its effectiveness in reducing oxygen and other impurities in the vessel as well as improving plasma performance. The technique is also currently under consideration as wall conditioning method for the proposed full-tungsten (W) wall of the International Thermonuclear Experimental Reactor (ITER). However, the impact of the deposited Boron (B) layer thickness, and its homogeneity after the boronization process is uncertain as well as knowledge about the layer lifetime and improved conditions. In this study, an approach of the picosecond-laser-induced breakdown spectroscopy (ps-LIBS) is investigated to analyze the depth distribution of B-films on W-substrates by using three optical spectrometers in a vacuum environment. The depth distribution of two types of B-films on W-substrates with the thicknesses of 130 nm and 260 nm were sequentially measured under different laser spot sizes (varying the laser fluence). The B-films on the W-substrates were made by magnetron sputtering to simulate the thin B layers during the boronization. The measured average ablation rate of ps-LIBS shows a notable decrease with increasing laser spot size. Additionally, the spectral lines of B and W exhibit distinct intensity distributions under different spot sizes due to the different excitation thresholds of the B-films and the W-substrates. The interface between B-films and W-substrates, as well as the thickness of the B-films, were determined using the normalized intensity and intensity ratio method, respectively. The results from ps-LIBS measurements regarding the depth are in good agreement with those obtained through the Focused Ion Beam combined with Scanning Electron Microscopy (FIB-SEM) and Energy Dispersive X-ray Spectroscopy (EDS). These initial findings verify the feasibility to characterize the thickness and uniformity of thin B films in the order of 100 nm and below on W-substrates using ps-LIBS.
由于硼化技术能有效减少容器中的氧气和其他杂质，并能提高等离子体的性能，因此在目前的设备中被用作器壁调节技术。目前，国际热核聚变实验堆（ITER）正在考虑将这种技术作为拟建的全钨（W）壁的壁调节方法。然而，硼化过程后沉积硼（B）层厚度及其均匀性的影响，以及有关硼层寿命和改进条件的知识都是不确定的。本研究采用皮秒激光诱导击穿光谱（ps-LIBS）方法，在真空环境中使用三台光学光谱仪分析 W 基板上硼膜的深度分布。在不同激光光斑尺寸（改变激光能量）条件下，依次测量了 W 基片上厚度分别为 130 nm 和 260 nm 的两种 B 膜的深度分布。W 基片上的 B 膜是通过磁控溅射制造的，以模拟硼化过程中的薄 B 层。测得的 ps-LIBS 平均烧蚀率随着激光光斑尺寸的增大而明显下降。此外，由于硼薄膜和 W 基质的激发阈值不同，在不同光斑尺寸下，硼和 W 的光谱线呈现出不同的强度分布。利用归一化强度和强度比方法分别确定了 B 膜和 W 基底之间的界面以及 B 膜的厚度。ps-LIBS的深度测量结果与聚焦离子束结合扫描电子显微镜（FIB-SEM）和能量色散 X 射线光谱（EDS）获得的结果十分吻合。这些初步发现验证了利用 ps-LIBS 测定 W 基底上 100 纳米及以下 B 薄膜厚度和均匀性的可行性。
{"title":"Study of spectral features and depth distributions of boron layers on tungsten substrates by ps-LIBS in a vacuum environment","authors":"Huace Wu , Rongxing Yi , Anne Houben , Sebastijan Brezinsek , Marcin Rasinski , Cong Li , Gennady Sergienko , Yunfeng Liang , Timo Dittmar , Hongbin Ding","doi":"10.1016/j.nme.2024.101812","DOIUrl":"10.1016/j.nme.2024.101812","url":null,"abstract":"<div><div>Boronization is used in present-devices as wall condition technique due to its effectiveness in reducing oxygen and other impurities in the vessel as well as improving plasma performance. The technique is also currently under consideration as wall conditioning method for the proposed full-tungsten (W) wall of the International Thermonuclear Experimental Reactor (ITER). However, the impact of the deposited Boron (B) layer thickness, and its homogeneity after the boronization process is uncertain as well as knowledge about the layer lifetime and improved conditions. In this study, an approach of the picosecond-laser-induced breakdown spectroscopy (ps-LIBS) is investigated to analyze the depth distribution of B-films on W-substrates by using three optical spectrometers in a vacuum environment. The depth distribution of two types of B-films on W-substrates with the thicknesses of 130 nm and 260 nm were sequentially measured under different laser spot sizes (varying the laser fluence). The B-films on the W-substrates were made by magnetron sputtering to simulate the thin B layers during the boronization. The measured average ablation rate of ps-LIBS shows a notable decrease with increasing laser spot size. Additionally, the spectral lines of B and W exhibit distinct intensity distributions under different spot sizes due to the different excitation thresholds of the B-films and the W-substrates. The interface between B-films and W-substrates, as well as the thickness of the B-films, were determined using the normalized intensity and intensity ratio method, respectively. The results from ps-LIBS measurements regarding the depth are in good agreement with those obtained through the Focused Ion Beam combined with Scanning Electron Microscopy (FIB-SEM) and Energy Dispersive X-ray Spectroscopy (EDS). These initial findings verify the feasibility to characterize the thickness and uniformity of thin B films in the order of 100 nm and below on W-substrates using ps-LIBS.</div></div>","PeriodicalId":56004,"journal":{"name":"Nuclear Materials and Energy","volume":"41 ","pages":"Article 101812"},"PeriodicalIF":2.3,"publicationDate":"2024-11-12","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142653456","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}
Pub Date : 2024-11-12DOI: 10.1016/j.nme.2024.101813
Jun Hu , Xin Zhang , Yuhong Xu , Guangjiu Lei , Sanqiu Liu , Katsuyoshi Tsumori , Haruhisa Nakano , Masaki Osakabe , Mitsutaka Isobe , Shoichi Okamura , Akihiro Shimizu , Kunihiro Ogawa , Hiromi Takahashi , Heng Li , Zilin Cui , Yiqin Zhu , Xiaolong Li , Huaqing Zheng , Xiaoqiao Liu , Shaofei Geng , CFQS team
This study employs first-principles calculations to investigate the structural, electronic, and mechanical properties of La1-xMxB6 (M = Ba, Sr, Ca), focusing on the surface work function, elastic constants, bulk modulus, shear modulus, Young’s modulus, Debye temperature, and melting point. The results indicate that doping generally leads to a reduction in the surface work function, with La0.375Ba0.625B6 achieving a work function as low as 1.27 eV. The influence of doping concentration on the mechanical properties and anisotropy is analyzed, revealing that La1-xMxB6 and La0.5Sr0.5B6 exhibit oscillatory changes related to the layered structure of the dopants. Brittleness is assessed through the B/G ratio and Poisson’s ratio. Thermodynamic analysis shows that the melting points of these compounds exceed 2000 K. These findings provide useful references for choosing cesium-free electrode materials applied for plasma-facing applications in neutral beam injection.
{"title":"Theoretical investigation of structural, electronic, mechanical, surface work function and thermodynamic properties of La1-xMxB6 (M = Ba, Sr, Ca) compounds: Potential plasma grid materials in N-NBI system","authors":"Jun Hu , Xin Zhang , Yuhong Xu , Guangjiu Lei , Sanqiu Liu , Katsuyoshi Tsumori , Haruhisa Nakano , Masaki Osakabe , Mitsutaka Isobe , Shoichi Okamura , Akihiro Shimizu , Kunihiro Ogawa , Hiromi Takahashi , Heng Li , Zilin Cui , Yiqin Zhu , Xiaolong Li , Huaqing Zheng , Xiaoqiao Liu , Shaofei Geng , CFQS team","doi":"10.1016/j.nme.2024.101813","DOIUrl":"10.1016/j.nme.2024.101813","url":null,"abstract":"<div><div>This study employs first-principles calculations to investigate the structural, electronic, and mechanical properties of La<sub>1-x</sub>M<sub>x</sub>B<sub>6</sub> (M = Ba, Sr, Ca), focusing on the surface work function, elastic constants, bulk modulus, shear modulus, Young’s modulus, Debye temperature, and melting point. The results indicate that doping generally leads to a reduction in the surface work function, with La<sub>0.375</sub>Ba<sub>0.625</sub>B<sub>6</sub> achieving a work function as low as 1.27 eV. The influence of doping concentration on the mechanical properties and anisotropy is analyzed, revealing that La<sub>1-x</sub>M<sub>x</sub>B<sub>6</sub> and La<sub>0.5</sub>Sr<sub>0.5</sub>B<sub>6</sub> exhibit oscillatory changes related to the layered structure of the dopants. Brittleness is assessed through the B/G ratio and Poisson’s ratio. Thermodynamic analysis shows that the melting points of these compounds exceed 2000 K. These findings provide useful references for choosing cesium-free electrode materials applied for plasma-facing applications in neutral beam injection.</div></div>","PeriodicalId":56004,"journal":{"name":"Nuclear Materials and Energy","volume":"41 ","pages":"Article 101813"},"PeriodicalIF":2.3,"publicationDate":"2024-11-12","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142653455","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}
Pub Date : 2024-11-09DOI: 10.1016/j.nme.2024.101809
J.A. Snipes , L.R. Baylor , A. Bortolon , F. Effenberg , E.P. Gilson , A. Loarte , R. Lunsford , R. Maingi , S. Meitner , F. Nespoli , S. Maruyama , A. Nagy , Z. Sun , J. Ulreich , T. Wauters
As part of ITER’s consideration to change its first wall material from beryllium to tungsten, the ITER Organization has proposed studying the feasibility of real-time solid boron injection (SBI) into the plasma to coat the walls and divertor to supplement glow discharge boronization (GDB) [1]. Boron deposits getter oxygen and reduce sputtering of tungsten from plasma facing components (PFCs). Particularly in areas with significant plasma wall interactions, boron coatings are expected to be short-lived under high performance plasma conditions. The proposed SBI system aims to maintain boron layers in these areas to avoid excessive radiation from tungsten in the plasma as a risk mitigation to ensure ITER will be able to reach and sustain Q = 10 conditions. The system will be used sparingly, as redeposition of boron can lead to significant tritium retention, which must be minimized in ITER to comply with nuclear safety concerns. SBI is proposed to limit and precisely control the amount of boron injected in real-time during plasma operation. Here, some of the design requirements and initial concepts for an SBI system in ITER are presented based on previous results carried out with SBI systems on a number of tokamaks and stellarators around the world [2], [3], [4], [5], [6], [7], [8], [9], [10], [11], [12], [13], [14], [15], [16], [17], [18].
Previous results using SBI systems installed by PPPL have injected boron particles from 5 µm–2 mm diameter at calibrated rates of 2–200 mg/s in real-time during plasma operation on AUG [4], DIII-D [5], EAST [6], KSTAR [7], LHD [8], TFTR [9], WEST [10], and W7-X [11], [12], leading to improved wall conditions with reduced plasma impurity concentrations and radiated power and improved plasma performance. The boron is ionized in the plasma edge and then deposited on plasma-wetted surfaces. On AUG [4], EAST [6] and WEST [10] reduced tungsten sputtering sources were observed following several discharges with SBI. Extrapolation of these SBI results are presented to estimate the amount of boron needed for wall conditioning in ITER. Real-time SBI control requirements and plasma operation scenarios for ITER are also described.
{"title":"Initial design concepts for solid boron injection in ITER","authors":"J.A. Snipes , L.R. Baylor , A. Bortolon , F. Effenberg , E.P. Gilson , A. Loarte , R. Lunsford , R. Maingi , S. Meitner , F. Nespoli , S. Maruyama , A. Nagy , Z. Sun , J. Ulreich , T. Wauters","doi":"10.1016/j.nme.2024.101809","DOIUrl":"10.1016/j.nme.2024.101809","url":null,"abstract":"<div><div>As part of ITER’s consideration to change its first wall material from beryllium to tungsten, the ITER Organization has proposed studying the feasibility of real-time solid boron injection (SBI) into the plasma to coat the walls and divertor to supplement glow discharge boronization (GDB) <span><span>[1]</span></span>. Boron deposits getter oxygen and reduce sputtering of tungsten from plasma facing components (PFCs). Particularly in areas with significant plasma wall interactions, boron coatings are expected to be short-lived under high performance plasma conditions. The proposed SBI system aims to maintain boron layers in these areas to avoid excessive radiation from tungsten in the plasma as a risk mitigation to ensure ITER will be able to reach and sustain Q = 10 conditions. The system will be used sparingly, as redeposition of boron can lead to significant tritium retention, which must be minimized in ITER to comply with nuclear safety concerns. SBI is proposed to limit and precisely control the amount of boron injected in real-time during plasma operation. Here, some of the design requirements and initial concepts for an SBI system in ITER are presented based on previous results carried out with SBI systems on a number of tokamaks and stellarators around the world <span><span>[2]</span></span>, <span><span>[3]</span></span>, <span><span>[4]</span></span>, <span><span>[5]</span></span>, <span><span>[6]</span></span>, <span><span>[7]</span></span>, <span><span>[8]</span></span>, <span><span>[9]</span></span>, <span><span>[10]</span></span>, <span><span>[11]</span></span>, <span><span>[12]</span></span>, <span><span>[13]</span></span>, <span><span>[14]</span></span>, <span><span>[15]</span></span>, <span><span>[16]</span></span>, <span><span>[17]</span></span>, <span><span>[18]</span></span>.</div><div>Previous results using SBI systems installed by PPPL have injected boron particles from 5 µm–2 mm diameter at calibrated rates of 2–200 mg/s in real-time during plasma operation on AUG <span><span>[4]</span></span>, DIII-D <span><span>[5]</span></span>, EAST <span><span>[6]</span></span>, KSTAR <span><span>[7]</span></span>, LHD <span><span>[8]</span></span>, TFTR <span><span>[9]</span></span>, WEST <span><span>[10]</span></span>, and W7-X <span><span>[11]</span></span>, <span><span>[12]</span></span>, leading to improved wall conditions with reduced plasma impurity concentrations and radiated power and improved plasma performance. The boron is ionized in the plasma edge and then deposited on plasma-wetted surfaces. On AUG <span><span>[4]</span></span>, EAST <span><span>[6]</span></span> and WEST <span><span>[10]</span></span> reduced tungsten sputtering sources were observed following several discharges with SBI. Extrapolation of these SBI results are presented to estimate the amount of boron needed for wall conditioning in ITER. Real-time SBI control requirements and plasma operation scenarios for ITER are also described.</div></div>","PeriodicalId":56004,"journal":{"name":"Nuclear Materials and Energy","volume":"41 ","pages":"Article 101809"},"PeriodicalIF":2.3,"publicationDate":"2024-11-09","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142653451","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}
Pub Date : 2024-11-06DOI: 10.1016/j.nme.2024.101805
Ruihao Liao , Ke Xu , Yifan Liu , Zibo Gao , Shuo Jin , Linyun Liang , Guang-Hong Lu
Irradiation-induced cascade collisions produce numerous point defects within materials, which can severely deteriorate their thermo-mechanical properties and overall performance. We propose a computational scheme that combines molecular dynamic (MD) simulations with a denoising diffusion probabilistic model (DDPM) to rapidly and accurately predict the spatial coordinates of point defects at any given primary knock atom (PKA) energy, ranging from 0 to 100.0 keV. Importantly, this capability extends to PKA energies that are exclusive from the training data set, demonstrating the robustness and generalizability of the model. The proposed scheme has been thoroughly validated by several designed indicators, including the Fréchet inception distance, the number of point defects, the distance from vacancies and self-interstitial atoms (SIAs) to their respective centroids, the inter-centroid distance between the vacancies and SIAs, the probability density of clustered defect sizes, and the sub-cascade number. Compared to MD simulations, the DDPM can generate point defects at a specific PKA energy at least ten thousand times faster. By offering a rapid and reliable means to model defect distributions across various energy levels, the proposed scheme benefits the comprehension of the cascade process and provides a valuable database for both experimental investigations and large-scale simulations.
{"title":"Fast prediction of irradiation-induced cascade defects using denoising diffusion probabilistic model","authors":"Ruihao Liao , Ke Xu , Yifan Liu , Zibo Gao , Shuo Jin , Linyun Liang , Guang-Hong Lu","doi":"10.1016/j.nme.2024.101805","DOIUrl":"10.1016/j.nme.2024.101805","url":null,"abstract":"<div><div>Irradiation-induced cascade collisions produce numerous point defects within materials, which can severely deteriorate their thermo-mechanical properties and overall performance. We propose a computational scheme that combines molecular dynamic (MD) simulations with a denoising diffusion probabilistic model (DDPM) to rapidly and accurately predict the spatial coordinates of point defects at any given primary knock atom (PKA) energy, ranging from 0 to 100.0 keV. Importantly, this capability extends to PKA energies that are exclusive from the training data set, demonstrating the robustness and generalizability of the model. The proposed scheme has been thoroughly validated by several designed indicators, including the Fréchet inception distance, the number of point defects, the distance from vacancies and self-interstitial atoms (SIAs) to their respective centroids, the inter-centroid distance between the vacancies and SIAs, the probability density of clustered defect sizes, and the sub-cascade number. Compared to MD simulations, the DDPM can generate point defects at a specific PKA energy at least ten thousand times faster. By offering a rapid and reliable means to model defect distributions across various energy levels, the proposed scheme benefits the comprehension of the cascade process and provides a valuable database for both experimental investigations and large-scale simulations.</div></div>","PeriodicalId":56004,"journal":{"name":"Nuclear Materials and Energy","volume":"41 ","pages":"Article 101805"},"PeriodicalIF":2.3,"publicationDate":"2024-11-06","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142653452","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}
Pub Date : 2024-11-06DOI: 10.1016/j.nme.2024.101796
D. Nishijima , M.J. Baldwin , F. Chang , D. Hwangbo , G.R. Tynan
<div><div>D<sub>2</sub> molecular band emission observed at a wavelength range of <span><math><mrow><mi>λ</mi><mo>∼</mo><mn>557</mn><mo>−</mo><mn>643</mn><mspace></mspace><mi>nm</mi></mrow></math></span> is utilized to measure electron density, <span><math><msub><mrow><mi>n</mi></mrow><mrow><mi>e</mi></mrow></msub></math></span>, in D plasmas of the PISCES-A and PISCES-RF linear plasma devices. The D<sub>2</sub> band is divided at <span><math><mrow><mi>λ</mi><mo>=</mo><mn>593</mn><mspace></mspace><mi>nm</mi></mrow></math></span> to make an intensity ratio, D<span><math><msub><mrow></mrow><mrow><mi>2L</mi></mrow></msub></math></span> (<span><math><mrow><mo>∼</mo><mn>557</mn></mrow></math></span>–<span><math><mrow><mn>593</mn><mspace></mspace><mi>nm</mi></mrow></math></span>)/D<span><math><msub><mrow></mrow><mrow><mi>2R</mi></mrow></msub></math></span> (<span><math><mrow><mo>∼</mo><mn>593</mn></mrow></math></span>–<span><math><mrow><mn>643</mn><mspace></mspace><mi>nm</mi></mrow></math></span>), where D<span><math><msub><mrow></mrow><mrow><mi>2L</mi></mrow></msub></math></span> consists predominantly of the <span><math><mrow><mi>g</mi><msup><mrow><mspace></mspace></mrow><mrow><mn>3</mn></mrow></msup><msubsup><mrow><mi>Σ</mi></mrow><mrow><mi>g</mi></mrow><mrow><mo>+</mo></mrow></msubsup><mspace></mspace><mn>3</mn><mi>d</mi><mi>σ</mi></mrow></math></span>, <span><math><mrow><mi>h</mi><msup><mrow><mspace></mspace></mrow><mrow><mn>3</mn></mrow></msup><msubsup><mrow><mi>Σ</mi></mrow><mrow><mi>g</mi></mrow><mrow><mo>+</mo></mrow></msubsup><mspace></mspace><mn>3</mn><mi>s</mi><mi>σ</mi></mrow></math></span>, <span><math><mrow><mi>i</mi><msup><mrow><mspace></mspace></mrow><mrow><mn>3</mn></mrow></msup><msub><mrow><mi>Π</mi></mrow><mrow><mi>g</mi></mrow></msub><mspace></mspace><mn>3</mn><mi>d</mi><mi>π</mi></mrow></math></span>, <span><math><mrow><mi>j</mi><msup><mrow><mspace></mspace></mrow><mrow><mn>3</mn></mrow></msup><msub><mrow><mi>Δ</mi></mrow><mrow><mi>g</mi></mrow></msub><mspace></mspace><mn>3</mn><mi>d</mi><mi>δ</mi></mrow></math></span> <span><math><mo>→</mo></math></span> <span><math><mrow><mi>c</mi><msup><mrow><mspace></mspace></mrow><mrow><mn>3</mn></mrow></msup><msub><mrow><mi>Π</mi></mrow><mrow><mi>u</mi></mrow></msub><mspace></mspace><mn>2</mn><mi>p</mi><mi>π</mi></mrow></math></span> transitions, while D<span><math><msub><mrow></mrow><mrow><mi>2R</mi></mrow></msub></math></span> mainly includes the <span><math><mrow><mi>d</mi><msup><mrow><mspace></mspace></mrow><mrow><mn>3</mn></mrow></msup><msub><mrow><mi>Π</mi></mrow><mrow><mi>u</mi></mrow></msub><mspace></mspace><mn>3</mn><mi>p</mi><mi>π</mi></mrow></math></span> <span><math><mo>→</mo></math></span> <span><math><mrow><mi>a</mi><msup><mrow><mspace></mspace></mrow><mrow><mn>3</mn></mrow></msup><msubsup><mrow><mi>Σ</mi></mrow><mrow><mi>g</mi></mrow><mrow><mo>+</mo></mrow></msubsup><mspace></mspace><mn>2</mn><mi>s</mi><mi>σ</mi></mrow></math></span> Fulcher band emission. It is experimentally
{"title":"Utilization of D2 molecular band emission for electron density measurement","authors":"D. Nishijima , M.J. Baldwin , F. Chang , D. Hwangbo , G.R. Tynan","doi":"10.1016/j.nme.2024.101796","DOIUrl":"10.1016/j.nme.2024.101796","url":null,"abstract":"<div><div>D<sub>2</sub> molecular band emission observed at a wavelength range of <span><math><mrow><mi>λ</mi><mo>∼</mo><mn>557</mn><mo>−</mo><mn>643</mn><mspace></mspace><mi>nm</mi></mrow></math></span> is utilized to measure electron density, <span><math><msub><mrow><mi>n</mi></mrow><mrow><mi>e</mi></mrow></msub></math></span>, in D plasmas of the PISCES-A and PISCES-RF linear plasma devices. The D<sub>2</sub> band is divided at <span><math><mrow><mi>λ</mi><mo>=</mo><mn>593</mn><mspace></mspace><mi>nm</mi></mrow></math></span> to make an intensity ratio, D<span><math><msub><mrow></mrow><mrow><mi>2L</mi></mrow></msub></math></span> (<span><math><mrow><mo>∼</mo><mn>557</mn></mrow></math></span>–<span><math><mrow><mn>593</mn><mspace></mspace><mi>nm</mi></mrow></math></span>)/D<span><math><msub><mrow></mrow><mrow><mi>2R</mi></mrow></msub></math></span> (<span><math><mrow><mo>∼</mo><mn>593</mn></mrow></math></span>–<span><math><mrow><mn>643</mn><mspace></mspace><mi>nm</mi></mrow></math></span>), where D<span><math><msub><mrow></mrow><mrow><mi>2L</mi></mrow></msub></math></span> consists predominantly of the <span><math><mrow><mi>g</mi><msup><mrow><mspace></mspace></mrow><mrow><mn>3</mn></mrow></msup><msubsup><mrow><mi>Σ</mi></mrow><mrow><mi>g</mi></mrow><mrow><mo>+</mo></mrow></msubsup><mspace></mspace><mn>3</mn><mi>d</mi><mi>σ</mi></mrow></math></span>, <span><math><mrow><mi>h</mi><msup><mrow><mspace></mspace></mrow><mrow><mn>3</mn></mrow></msup><msubsup><mrow><mi>Σ</mi></mrow><mrow><mi>g</mi></mrow><mrow><mo>+</mo></mrow></msubsup><mspace></mspace><mn>3</mn><mi>s</mi><mi>σ</mi></mrow></math></span>, <span><math><mrow><mi>i</mi><msup><mrow><mspace></mspace></mrow><mrow><mn>3</mn></mrow></msup><msub><mrow><mi>Π</mi></mrow><mrow><mi>g</mi></mrow></msub><mspace></mspace><mn>3</mn><mi>d</mi><mi>π</mi></mrow></math></span>, <span><math><mrow><mi>j</mi><msup><mrow><mspace></mspace></mrow><mrow><mn>3</mn></mrow></msup><msub><mrow><mi>Δ</mi></mrow><mrow><mi>g</mi></mrow></msub><mspace></mspace><mn>3</mn><mi>d</mi><mi>δ</mi></mrow></math></span> <span><math><mo>→</mo></math></span> <span><math><mrow><mi>c</mi><msup><mrow><mspace></mspace></mrow><mrow><mn>3</mn></mrow></msup><msub><mrow><mi>Π</mi></mrow><mrow><mi>u</mi></mrow></msub><mspace></mspace><mn>2</mn><mi>p</mi><mi>π</mi></mrow></math></span> transitions, while D<span><math><msub><mrow></mrow><mrow><mi>2R</mi></mrow></msub></math></span> mainly includes the <span><math><mrow><mi>d</mi><msup><mrow><mspace></mspace></mrow><mrow><mn>3</mn></mrow></msup><msub><mrow><mi>Π</mi></mrow><mrow><mi>u</mi></mrow></msub><mspace></mspace><mn>3</mn><mi>p</mi><mi>π</mi></mrow></math></span> <span><math><mo>→</mo></math></span> <span><math><mrow><mi>a</mi><msup><mrow><mspace></mspace></mrow><mrow><mn>3</mn></mrow></msup><msubsup><mrow><mi>Σ</mi></mrow><mrow><mi>g</mi></mrow><mrow><mo>+</mo></mrow></msubsup><mspace></mspace><mn>2</mn><mi>s</mi><mi>σ</mi></mrow></math></span> Fulcher band emission. It is experimentally","PeriodicalId":56004,"journal":{"name":"Nuclear Materials and Energy","volume":"41 ","pages":"Article 101796"},"PeriodicalIF":2.3,"publicationDate":"2024-11-06","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142653099","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}
Pub Date : 2024-11-06DOI: 10.1016/j.nme.2024.101806
A. Huber , G. Sergienko , M. Groth , D. Keeling , M. Wischmeier , D. Douai , E. Lerche , C. Perez von Thun , S. Brezinsek , V. Huber , A. Boboc , M. Brix , I.S. Carvalho , A.V. Chankin , E. Delabie , I. Jepu , V. Kachkanov , V. Kiptily , K. Kirov , Ch. Linsmeier , M. Zlobinski
Analysis of comparable discharges fuelled by either deuterium or protium reveals a clear relationship between the isotope mass and the H-mode density limit. Notably, the density limit is significantly lower in protium, showing a reduction of up to 35 % compared to identical deuterium plasma conditions. Within mixed H-mode density limit (HDL) plasmas, the maximum achievable density, or H-mode density limit, decreases with increasing protium concentration, denoted as cH. For instance, the highest corresponding maximum Greenwald fraction (fGW) of about 1.02 was observed in the pulse with the lowest cH value of 4.4 %. This fGW decreases to 0.96 at cH = 48 %. The average atomic mass, , of the plasma species decreases in these pulses from the value of 1.96 (cH = 4.4 %) down to 1.52 (cH = 48 %). Interestingly, the maximum achievable density appears to be largely unaffected by the applied power value, regardless of whether deuterium or protium is used, as well as under mixed H/D fuelling conditions.
Additionally, the measured Greenwald fractions are agreed with a heuristic model based on the SOL pressure threshold of an MHD instability, as proposed by Goldston. This comparison, especially concerning the model’s dependence on isotopic mass, shows full consistency between the measured and predicted Greenwald fractions.
对以氘或氕为燃料的可比放电进行分析后发现，同位素质量与 H 模式密度极限之间存在明显的关系。值得注意的是，氕的密度极限明显降低，与相同的氘等离子体条件相比，降低幅度高达 35%。在混合 H 模式密度极限（HDL）等离子体中，可达到的最大密度或 H 模式密度极限会随着氕浓度（表示为 cH）的增加而降低。例如，在 cH 值最低（4.4%）的脉冲中观察到的相应最大格林瓦尔德分数（fGW）最高，约为 1.02。当 cH = 48 % 时，该 fGW 降至 0.96。在这些脉冲中，等离子体物种的平均原子质量 A¯ 从 1.96（cH = 4.4 %）下降到 1.52（cH = 48 %）。有趣的是，无论使用的是氘还是氕，以及在氢/氘混合燃料条件下，可达到的最大密度似乎基本不受应用功率值的影响。此外，测得的格林瓦尔德分数与戈德斯顿提出的基于 MHD 不稳定的 SOL 压力阈值的启发式模型一致。这种比较，特别是关于模型对同位素质量的依赖性的比较，表明测量和预测的格林瓦尔德分数完全一致。
{"title":"Investigation of H-mode density limit in mixed protium–deuterium plasmas at JET with ITER-like wall","authors":"A. Huber , G. Sergienko , M. Groth , D. Keeling , M. Wischmeier , D. Douai , E. Lerche , C. Perez von Thun , S. Brezinsek , V. Huber , A. Boboc , M. Brix , I.S. Carvalho , A.V. Chankin , E. Delabie , I. Jepu , V. Kachkanov , V. Kiptily , K. Kirov , Ch. Linsmeier , M. Zlobinski","doi":"10.1016/j.nme.2024.101806","DOIUrl":"10.1016/j.nme.2024.101806","url":null,"abstract":"<div><div>Analysis of comparable discharges fuelled by either deuterium or protium reveals a clear relationship between the isotope mass and the H-mode density limit. Notably, the density limit is significantly lower in protium, showing a reduction of up to 35 % compared to identical deuterium plasma conditions. Within mixed H-mode density limit (HDL) plasmas, the maximum achievable density, or H-mode density limit, decreases with increasing protium concentration, denoted as <em>c<sub>H</sub></em>. For instance, the highest corresponding maximum Greenwald fraction (<em>f<sub>GW</sub></em>) of about 1.02 was observed in the pulse with the lowest c<sub>H</sub> value of 4.4 %. This f<sub>GW</sub> decreases to 0.96 at <em>c<sub>H</sub></em> = 48 %. The average atomic mass, <span><math><mover><mrow><mi>A</mi></mrow><mrow><mo>¯</mo></mrow></mover></math></span>, of the plasma species decreases in these pulses from the value of 1.96 (<em>c<sub>H</sub></em> = 4.4 %) down to 1.52 (<em>c<sub>H</sub></em> = 48 %). Interestingly, the maximum achievable density appears to be largely unaffected by the applied power value, regardless of whether deuterium or protium is used, as well as under mixed H/D fuelling conditions.</div><div>Additionally, the measured Greenwald fractions are agreed with a heuristic model based on the SOL pressure threshold of an MHD instability, as proposed by Goldston. This comparison, especially concerning the model’s dependence on isotopic mass, shows full consistency between the measured and predicted Greenwald fractions.</div></div>","PeriodicalId":56004,"journal":{"name":"Nuclear Materials and Energy","volume":"41 ","pages":"Article 101806"},"PeriodicalIF":2.3,"publicationDate":"2024-11-06","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142653454","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}
Radiation transport simulations of the deuterium Lyman line series using EIRENE predict a factor of 2 increase of Balmer- emission in the JET-ILW low confinement divertor plasmas in high-recycling and detached conditions caused by the re-absorption of Lyman- emission. The photon tracing model in the EIRENE code is applied to SOLPS-ITER pure deuterium plasma solutions of JET-ILW to evaluate the contribution of Lyman- capture towards the population density of D() and, consequently, the Balmer- emission. The local population escape factors of Lyman- and Lyman- lines in the JET-ILW divertor show steep spatial gradients and indicate local regions with high opacity in high-recycling and detached conditions. The relative contribution of Lyman- capture towards the population density of D() is significant in high-recycling and detached conditions. This observation is further corroborated by line-integrated calculations using Balmer- diagnostic line-of-sights.
{"title":"Lyman line opacities in tokamak divertor plasmas under high-recycling and detached conditions","authors":"Ray Chandra , Detlev Reiter , Niels Horsten , Mathias Groth","doi":"10.1016/j.nme.2024.101794","DOIUrl":"10.1016/j.nme.2024.101794","url":null,"abstract":"<div><div>Radiation transport simulations of the deuterium Lyman line series using EIRENE predict a factor of 2 increase of Balmer-<span><math><mi>α</mi></math></span> emission in the JET-ILW low confinement divertor plasmas in high-recycling and detached conditions caused by the re-absorption of Lyman-<span><math><mi>β</mi></math></span> emission. The photon tracing model in the EIRENE code is applied to SOLPS-ITER pure deuterium plasma solutions of JET-ILW to evaluate the contribution of Lyman-<span><math><mi>β</mi></math></span> capture towards the population density of D(<span><math><mrow><mi>p</mi><mo>=</mo><mn>3</mn></mrow></math></span>) and, consequently, the Balmer-<span><math><mi>α</mi></math></span> emission. The local population escape factors of Lyman-<span><math><mi>α</mi></math></span> and Lyman-<span><math><mi>β</mi></math></span> lines in the JET-ILW divertor show steep spatial gradients and indicate local regions with high opacity in high-recycling and detached conditions. The relative contribution of Lyman-<span><math><mi>β</mi></math></span> capture towards the population density of D(<span><math><mrow><mi>p</mi><mo>=</mo><mn>3</mn></mrow></math></span>) is significant in high-recycling and detached conditions. This observation is further corroborated by line-integrated calculations using Balmer-<span><math><mi>α</mi></math></span> diagnostic line-of-sights.</div></div>","PeriodicalId":56004,"journal":{"name":"Nuclear Materials and Energy","volume":"41 ","pages":"Article 101794"},"PeriodicalIF":2.3,"publicationDate":"2024-11-06","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142653453","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}
Pub Date : 2024-11-04DOI: 10.1016/j.nme.2024.101803
M. Shoji , G. Kawamura , R. Smirnov , J. Romazanov , A. Kirschner , Y. Tanaka , S. Masuzaki , T. Kawate , F. Nespoli , R. Lunsford , E.P. Gilson , S. Brezinsek , N.A. Pablant
The toroidal distribution of boron deposition on plasma-facing components (PFCs) in boron powder injection using an impurity power dropper (IPD) was investigated by full-torus simulation and observations in a systematic plasma density-scan experiment. The images of the ablation of dropped boron powders observed with a visible CCD camera were consistently explained by the simulations of the ablation positions of the boron powders considering the size distribution. Simulations assuming full-torus boron deposition on the PFCs did not reproduce the observed intensity profile of boron emission lines for higher plasma densities. It indicated that the density of boron deposited on PFCs installed toroidally far from the IPD was low for higher plasma densities due to the change in the ablation positions of the boron powders toward the outboard side. The experimental results verified the previous full-torus simulation of the toroidal distribution of the boron deposition in both lower and higher plasma densities.
{"title":"Full-torus impurity transport simulation in boron powder injection experiments in the Large Helical Device","authors":"M. Shoji , G. Kawamura , R. Smirnov , J. Romazanov , A. Kirschner , Y. Tanaka , S. Masuzaki , T. Kawate , F. Nespoli , R. Lunsford , E.P. Gilson , S. Brezinsek , N.A. Pablant","doi":"10.1016/j.nme.2024.101803","DOIUrl":"10.1016/j.nme.2024.101803","url":null,"abstract":"<div><div>The toroidal distribution of boron deposition on plasma-facing components (PFCs) in boron powder injection using an impurity power dropper (IPD) was investigated by full-torus simulation and observations in a systematic plasma density-scan experiment. The images of the ablation of dropped boron powders observed with a visible CCD camera were consistently explained by the simulations of the ablation positions of the boron powders considering the size distribution. Simulations assuming full-torus boron deposition on the PFCs did not reproduce the observed intensity profile of boron emission lines for higher plasma densities. It indicated that the density of boron deposited on PFCs installed toroidally far from the IPD was low for higher plasma densities due to the change in the ablation positions of the boron powders toward the outboard side. The experimental results verified the previous full-torus simulation of the toroidal distribution of the boron deposition in both lower and higher plasma densities.</div></div>","PeriodicalId":56004,"journal":{"name":"Nuclear Materials and Energy","volume":"41 ","pages":"Article 101803"},"PeriodicalIF":2.3,"publicationDate":"2024-11-04","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142653098","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}
Pub Date : 2024-11-04DOI: 10.1016/j.nme.2024.101804
Xudong Wang , Rongyang Qiu , Yankun Dou , Yangchun Chen , Haipan Xiang , Peng Jiang , Xinfu He , Wen Yang , Guangdong Liu , Huiqiu Deng
Molybdenum-Rhenium (Mo-Re) alloys are considered core materials for advanced nuclear reactor components due to their excellent mechanical properties, machinability, and resistance to irradiation damage. However, irradiation-induced embrittlement and phase precipitation at high temperatures, along with transmutation nuclides, have hindered their broader application. To address this, we developed a Mo-Re interatomic potential using the Finnis-Sinclair formalism, facilitating molecular dynamics simulations to study primary irradiation damage. Systemically primary irradiation damage simulations for Mo and Mo-Re alloys have been performed. It’s found that there were more Frenkel-pair defects produced during the stage of thermal spike in Mo-Re alloys but fewer defects survived at the end of the cascade compared to Mo. In addition, the number of large-size interstitial clusters and dislocation loops was higher in Mo-Re alloys than in pure Mo with the same PKA energy. This is mainly attributed to the fact that Mo-Re alloys have lower thermal conductivity, while the binding energies of interstitial clusters and dislocation loops with sizes less than 100 in Mo-Re alloys are comparable to those of pure Mo, resulting in higher defect composites and larger defect sizes in Mo-Re alloys. These findings provide valuable insights into the primary damage mechanisms in Mo-Re alloys under irradiation, offering a foundation for developing kinetic models to simulate radiation-induced microstructural evolution.
{"title":"Molecular dynamic simulations of displacement cascades in molybdenum and molybdenum-rhenium alloys","authors":"Xudong Wang , Rongyang Qiu , Yankun Dou , Yangchun Chen , Haipan Xiang , Peng Jiang , Xinfu He , Wen Yang , Guangdong Liu , Huiqiu Deng","doi":"10.1016/j.nme.2024.101804","DOIUrl":"10.1016/j.nme.2024.101804","url":null,"abstract":"<div><div>Molybdenum-Rhenium (Mo-Re) alloys are considered core materials for advanced nuclear reactor components due to their excellent mechanical properties, machinability, and resistance to irradiation damage. However, irradiation-induced embrittlement and phase precipitation at high temperatures, along with transmutation nuclides, have hindered their broader application. To address this, we developed a Mo-Re interatomic potential using the Finnis-Sinclair formalism, facilitating molecular dynamics simulations to study primary irradiation damage. Systemically primary irradiation damage simulations for Mo and Mo-Re alloys have been performed. It’s found that there were more Frenkel-pair defects produced during the stage of thermal spike in Mo-Re alloys but fewer defects survived at the end of the cascade compared to Mo. In addition, the number of large-size interstitial clusters and dislocation loops was higher in Mo-Re alloys than in pure Mo with the same PKA energy. This is mainly attributed to the fact that Mo-Re alloys have lower thermal conductivity, while the binding energies of interstitial clusters and dislocation loops with sizes less than 100 in Mo-Re alloys are comparable to those of pure Mo, resulting in higher defect composites and larger defect sizes in Mo-Re alloys. These findings provide valuable insights into the primary damage mechanisms in Mo-Re alloys under irradiation, offering a foundation for developing kinetic models to simulate radiation-induced microstructural evolution.</div></div>","PeriodicalId":56004,"journal":{"name":"Nuclear Materials and Energy","volume":"41 ","pages":"Article 101804"},"PeriodicalIF":2.3,"publicationDate":"2024-11-04","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142593475","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}
Pub Date : 2024-11-03DOI: 10.1016/j.nme.2024.101802
A. Tonegawa , N. Okada , K. Miura , H. Natsume , K.N. Sato , K. Hoshino , Y. Hayashi , S. Masuzaki , S. Yamoto
For the first time, we have revealed the spatial structure of a detached plasma with electron–ion recombination (EIR) and molecular-activated recombination (MAR) in response to changes in ion temperature (Ti) and gas pressure. This was achieved using high-density sheet plasma generated by a linear divertor simulator (TPDsheet-ICR). The parallel-plate electrodes were positioned above and below the sheet plasma (∼1019 m−3). We varied the Ti from 3 to 7 eV using ion cyclotron resonance heating and investigated the parameters of the detached plasma near the target in the divergent field region. Plasma emission intensities at Balmer series (Hα and Hγ) and Fulcher band wavelengths (610 ± 10 nm) were measured with a high-speed camera equipped with an Arbaa prism. Additionally, a Langmuir probe measured the electron density and temperature of the plasma. Our results show that as the Ti increases, EIR generated near the plasma periphery disappears, while MAR gradually forms near the plasma center during the transition from detached to attached plasma. This transition occurs because the increase in Ti in the detached plasma transfers energy from ions to electrons, raising the high-energy component of the electrons, resulting in EIR disappearance and the onset of MAR.
我们首次揭示了具有电子-离子重组（EIR）和分子激活重组（MAR）的分离等离子体的空间结构对离子温度（Ti）和气体压力变化的响应。这是利用线性分流器模拟器（TPDsheet-ICR）产生的高密度片状等离子体实现的。平行板电极位于片状等离子体（1019 m-3）的上方和下方。我们利用离子回旋共振加热将钛从 3 eV 变为 7 eV，并研究了发散场区域目标附近分离等离子体的参数。等离子体在巴尔默波段（Hα 和 Hγ）和富尔彻波段（610 ± 10 nm）的发射强度是通过配备 Arbaa 棱镜的高速相机测量的。此外，朗缪尔探针还测量了等离子体的电子密度和温度。我们的结果表明，随着钛的增加，等离子体外围产生的 EIR 消失了，而 MAR 则在等离子体中心附近从分离等离子体过渡到附着等离子体的过程中逐渐形成。发生这种转变的原因是分离等离子体中 Ti 的增加将能量从离子转移到电子，从而提高了电子的高能分量，导致 EIR 消失和 MAR 开始出现。
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