Nuclear Materials and Energy最新文献

{"title":"Efficiency evaluation of fuel retention diagnostic in first wall by LID-QMS: Based on LIBS","authors":"Yiqin Wang ,&nbsp;Qingmei Xiao ,&nbsp;Yang Liu ,&nbsp;Shi Ye ,&nbsp;Feng Li ,&nbsp;Dongye Zhao","doi":"10.1016/j.nme.2025.101986","DOIUrl":"10.1016/j.nme.2025.101986","url":null,"abstract":"<div><div>Quantifying deuterium (D) retention in plasma-facing components (PFCs) with minimal material impact is critical for fusion reactor operation. This study employs laser-induced desorption coupled with quadrupole mass spectrometry (LID-QMS) for in situ D-retention analysis on HL-3 graphite tiles. As an auxiliary strategy, laser-induced breakdown spectroscopy (LIBS) is implemented under optimized low-fluence conditions to intermittently evaluate LID-QMS desorption efficiency during operation. Laboratory experiments demonstrate &gt; 80 % deuterium release in the first LID pulse (laser fluence &gt; 570 MW/m²), validated via cross-calibrated QMS measurements; LIBS provides rapid efficiency assessment by correlating D/H spectral results with QMS-resolved H, HD and D₂ desorption signals. The integrated LID-QMS-LIBS framework permits: real-time optimization of LID parameters during material analysis, direct efficiency validation without destructive sampling. This methodology is currently being implemented on HL-3 tokamak for in situ wall-D monitoring, demonstrating potential to replace ex situ post-mortem analysis in future fusion devices.</div></div>","PeriodicalId":56004,"journal":{"name":"Nuclear Materials and Energy","volume":"45 ","pages":"Article 101986"},"PeriodicalIF":2.7,"publicationDate":"2025-09-10","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145057400","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":2,"RegionCategory":"物理与天体物理","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Energetics and clustering properties of boron in tungsten and molybdenum: A comparative analysis from first-principles study","authors":"Peng Shao,&nbsp;Xiaowei Ma,&nbsp;Yunshan Xiong,&nbsp;Aoyu Mo,&nbsp;Haijun Li,&nbsp;Quan-Fu Han,&nbsp;Kun Jie Yang,&nbsp;Yue-Lin Liu","doi":"10.1016/j.nme.2025.101985","DOIUrl":"10.1016/j.nme.2025.101985","url":null,"abstract":"<div><div>Using first-principles calculations, we have systematically explored the geometric structures, electronic properties, diffusion behavior, and clustering with vacancies for impurity B (boron) in tungsten (W) and molybdenum (Mo). A single B atom prefers to occupy octerhedral interstitial position (oip) rather than tetrahedral interstitial position (tip) in bulk metals. B atoms can be easily captured by vacancies, and a single B atom prefers to occupy an oip next to vacancy center with a capturing energies of −2.67 and −2.51 eV in W and Mo, respectively. As the trapping progresses, at least 6B atoms can be captured by one vacancy, which is therefore regarded as the capturing center of B atoms to form B_nV clusters in both metals. For interstitial B and mono-vacancy, the most favorable diffusion pathways are oip → tip → oip and the &lt;111&gt; direction, respectively. At the same temperature, the diffusion coefficients of interstitial B and mono-vacancy in W are about 2–9 orders of magnitude lower than those in Mo, indicating that both interstitial B and mono-vacancy migrate much slower in W than in Mo. On the other hand, since the diffusion coefficient of interstitial B is significantly greater than that of mono-vacancy in both metals, the interstitial B migration is much easier than that of mono-vacancy. We therefore conclude that the B_nV formation mechanism can be attributed to that the relatively stable vacancies capture these relatively mobile interstitial B atoms in both metals.</div></div>","PeriodicalId":56004,"journal":{"name":"Nuclear Materials and Energy","volume":"45 ","pages":"Article 101985"},"PeriodicalIF":2.7,"publicationDate":"2025-09-10","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145061572","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":2,"RegionCategory":"物理与天体物理","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Investigating the stability and work function effects of Ba atoms adsorption on the Mo (110) surface","authors":"Yubo Ma ,&nbsp;Wei Li ,&nbsp;Jun Hu ,&nbsp;Xin Zhang ,&nbsp;Yuhong Xu ,&nbsp;Guangjiu Lei ,&nbsp;Shaofei Geng ,&nbsp;Haifeng Liu ,&nbsp;Xianqu Wang ,&nbsp;Jie Huang ,&nbsp;Hai Liu ,&nbsp;Jun Cheng ,&nbsp;Changjian Tang","doi":"10.1016/j.nme.2025.101984","DOIUrl":"10.1016/j.nme.2025.101984","url":null,"abstract":"<div><div>This study systematically investigates the effects of the stability and work function of barium (Ba) atoms adsorption on the Mo (110) surface using first-principles density functional (DFT) theory calculations. The results demonstrate that the long-bridge site represents the most stable adsorption configuration for Ba atoms on Mo (110) surface. As the Ba coverage increases, the work function initially decreases sharply and then increases slowly, reaching a minimum value of 2.25 eV at a coverage of 4/16 θ (3.35 × 10¹⁴ cm⁻²), which is markedly lower than the work function of 4.85 eV for the clean Mo (110) surface. This indicates that the adsorption of Ba atoms on the Mo (110) surface substantially reduces the work function. Theoretical analysis reveals a linear correlation between work function variations and dipole moment density changes, with charge redistribution induced by Ba adsorption dominating the total dipole moment modification. These results provide the reference for the research of the Cs-free alternative materials for neutral beam injection systems in fusion research.</div></div>","PeriodicalId":56004,"journal":{"name":"Nuclear Materials and Energy","volume":"45 ","pages":"Article 101984"},"PeriodicalIF":2.7,"publicationDate":"2025-09-09","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145050308","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":2,"RegionCategory":"物理与天体物理","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"High heat flux testing of wire-based laser metal deposition coated plasma-facing components","authors":"Jannik Tweer ,&nbsp;Thomas Derra ,&nbsp;Daniel Dorow-Gerspach ,&nbsp;Mauricio Gago ,&nbsp;Sascha Gierlings ,&nbsp;Stefan Gräfe ,&nbsp;Gerald Pintsuk ,&nbsp;Marius Wirtz ,&nbsp;Christian Linsmeier ,&nbsp;Thomas Bergs ,&nbsp;Ghaleb Natour","doi":"10.1016/j.nme.2025.101983","DOIUrl":"10.1016/j.nme.2025.101983","url":null,"abstract":"<div><div>The severe environment and loads acting on plasma-facing components (PFCs) of future fusion power plants cause inevitable erosion of their armor. In situ regeneration of tungsten (W) armored PFCs by local deposition of material would open up the possibility of damage healing and compensation of eroded material. The wire-based laser metal deposition (LMD-w) process fulfils the necessary requirements for use in the reactor vessel. Process development for the deposition of W on W substrate has already been carried out and it has been proven that thermal induced damage in the PFM can be healed this way. In this study, W armored PFCs were coated using LMD-w and tested under fusion–relevant thermal loads in the electron beam facility JUDITH 2. One respectively two stacked layers, each <strong>∼</strong>0.65 mm in height, were applied on the top surfaces of the W double tiles with surface areas of 28 × 12 mm² respectively, which are the characteristic dimensions for the plasma-facing surface of monoblocks. Some of the coated surfaces were also smoothed by laser remelting. In the electron beam facility JUDITH 2, the test components were exposed to steady state as well as combined steady state and transient thermal loads that are expected in the divertor area of the future DEMOnstration power plant. The coatings were tested with cyclic (200 and 1000 cycles) steady state thermal loading in the form of surface temperatures equivalent to heat fluxes on monoblock components of 10 MW m⁻² (∼1000 °C) and 15 MW m⁻² (∼1500 °C). To determine the performance of LMD-w layers under thermal loads that are expected during exposure to edged localized modes (ELMs), some layers were subjected to combined steady state and transient loading scenarios (0.13–0.55 GW m⁻², 10³ to 10⁵ pulses of 0.48 ms, 200–700 °C base-temperature). The temperature data obtained from the HHF experiments was processed and analyzed. Profile measurements on the coated surfaces before and after the high heat flux (HHF) exposure were used to investigate the influence of thermal stress on the deposited layers. Furthermore, cross-sectional micrographs of the test components were prepared and analyzed.</div></div>","PeriodicalId":56004,"journal":{"name":"Nuclear Materials and Energy","volume":"45 ","pages":"Article 101983"},"PeriodicalIF":2.7,"publicationDate":"2025-09-07","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145050311","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":2,"RegionCategory":"物理与天体物理","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Recrystallization, cracking, and erosion of dispersoid-strengthened tungsten materials during exposure to divertor plasmas","authors":"R.D. Kolasinski ,&nbsp;J.D. Coburn ,&nbsp;D.D. Truong ,&nbsp;J.G. Watkins ,&nbsp;T. Abrams ,&nbsp;Z.Z. Fang ,&nbsp;R. Hood ,&nbsp;R.E. Nygren ,&nbsp;A.W. Leonard ,&nbsp;J. Ren ,&nbsp;D.L. Rudakov ,&nbsp;J. Sugar ,&nbsp;C. Tsui ,&nbsp;H.Q. Wang ,&nbsp;J.A. Whaley ,&nbsp;I. Bykov ,&nbsp;A. Cruz ,&nbsp;F. Glass ,&nbsp;J. Herfindal ,&nbsp;C. Lasnier ,&nbsp;W. York","doi":"10.1016/j.nme.2025.101982","DOIUrl":"10.1016/j.nme.2025.101982","url":null,"abstract":"<div><div>In this study, we investigated the effects of combined intense particle and heat flux exposure on advanced tungsten plasma-facing materials within the DIII-D fusion facility. Our test matrix included two types of dispersoid-strengthened tungsten (containing either 100 nm diameter TiO₂ or Ni particles), along with high-purity polycrystalline tungsten as a reference. This experiment relied on a sample geometry angled at 15° relative to the divertor surface, thereby allowing the surfaces to intercept steady-state perpendicular heat fluxes (<span><math><mrow><msub><mi>q</mi><mo>⊥</mo></msub></mrow></math></span>) ranging from 10.1 to 19.6 MW/m². During each shot, the samples were exposed to 42 Hz edge-localized modes (ELMs), allowing us to test the material response to transient heating. We correlated the exposure conditions with extensive post-test surface composition analysis and microscopy to determine how the plasma modified each surface. The angled specimens closest to the strike point received the highest combined heat and particle flux and melted midway through the experiment. EBSD analysis revealed they were completely recrystallized throughout, with an average grain size &gt;100 µm. On the other hand, the specimens that received a lower steady state heat flux survived with more superficial surface damage. Whereas the high-purity polycrystalline tungsten exhibited a higher surface roughness, the dispersoid-strengthened material exhibited more extensive shallow inter-granular cracking. In addition, the surface was depleted of dispersoids following plasma exposure, possibly because of evaporation and/or sputtering. The results described here provide insights into the performance of these materials in a fusion environment which can guide further optimization for use in long-pulse devices.</div></div>","PeriodicalId":56004,"journal":{"name":"Nuclear Materials and Energy","volume":"45 ","pages":"Article 101982"},"PeriodicalIF":2.7,"publicationDate":"2025-09-05","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145057401","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":2,"RegionCategory":"物理与天体物理","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Influence of near-surface helium on the deuterium retention and uptake in tungsten","authors":"S. Markelj ,&nbsp;T. Schwarz-Selinger ,&nbsp;A. Šestan ,&nbsp;J. Zavašnik ,&nbsp;M. Kelemen","doi":"10.1016/j.nme.2025.101981","DOIUrl":"10.1016/j.nme.2025.101981","url":null,"abstract":"<div><div>The effect of near-surface helium (He) on deuterium (D) retention and uptake into the bulk of tungsten (W) was investigated. To quantify the He influence on D uptake, He was implanted close to the surface with 3 keV energy at different fluences and different temperatures. 20 MeV W irradiation was performed at room temperature after He implantation to create defects within the first 2.3 µm. Samples were then exposed to a low flux, low energy (300 eV/D) D ion beam at 450 <!--> <!-->K. The defects created by W ions trap penetrating D and make it hence possible to quantify D transport into depth below the He layer using ³He nuclear reaction analysis. Elastic recoil detection analysis enabled us to measure the D and He concentration depth profiles near the surface. Results show that D gets preferentially retained where He is implanted with D concentrations up to 10 at.%. At the same time D uptake beyond the He zone is reduced by a factor of 15 compared to a He-free W sample.</div></div>","PeriodicalId":56004,"journal":{"name":"Nuclear Materials and Energy","volume":"45 ","pages":"Article 101981"},"PeriodicalIF":2.7,"publicationDate":"2025-09-05","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145050310","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":2,"RegionCategory":"物理与天体物理","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Preparing LIBS for in-situ measurements in JET tokamak: system overview and co-deposited layer thicknesses","authors":"Jasper Ristkok ,&nbsp;Salvatore Almaviva ,&nbsp;Jari Likonen ,&nbsp;Juuso Karhunen ,&nbsp;Indrek Jõgi ,&nbsp;Peeter Paris ,&nbsp;Shweta Soni ,&nbsp;Pavel Veis ,&nbsp;Sahithya Atikukke ,&nbsp;Jelena Butikova ,&nbsp;Rongxing Yi ,&nbsp;Ionut Jepu ,&nbsp;Pawel Gasior ,&nbsp;Corneliu Porosnicu ,&nbsp;Mihaela Bojan ,&nbsp;Bianca Solomonea ,&nbsp;Sebastijan Brezinsek","doi":"10.1016/j.nme.2025.101968","DOIUrl":"10.1016/j.nme.2025.101968","url":null,"abstract":"<div><div>Laser-induced breakdown spectroscopy (LIBS) is a method for elemental composition analysis that has been proposed for fusion reactor safety diagnostics. A significant milestone in this development was the LIBS campaign conducted in 2024 at the Joint European Torus (JET), using a prototype LIBS enclosure, deployed with the MASCOT tele-manipulation arm. The work presented here prepared for the JET campaign by testing the LIBS enclosure.</div><div>Experiments were conducted at VTT Technical Research Centre of Finland, analyzing JET wall samples from the 2011–2016 ILW1–3 fusion campaigns, primarily from the divertor. The focus was on the analysis of co-deposited layers on the plasma-facing components containing hydrogen isotopes and elements from bulk layers: Be, W, Mo, CFC, and Inconel. Measurements were performed under atmospheric pressure air with an argon flow.</div><div>Optimal experimental conditions for the use of an Echelle spectrometer in subsequent JET LIBS campaign were identified, and the depth profiles of the surface layers are presented. The LIBS depth profiles defined distinct material layers. Ablating through the co-deposited layers required 1–870 laser shots (∼0.1–90 µm) on samples from different locations, with typical variations of 10–40 % on the same sample and the largest variation spanning 15–480 shots (∼1.5–50 µm).</div><div>The LIBS, Secondary Ion Mass Spectrometry (SIMS), and optical profilometry results showed good qualitative agreement. The ablation rate was ∼30–50 nm/shot for the W layers, ∼100–140 nm/shot for bulk Be limiters, and intermediate for the co-deposited layers. The insights gained in this study supported the preparation of the JET LIBS campaign.</div></div>","PeriodicalId":56004,"journal":{"name":"Nuclear Materials and Energy","volume":"44 ","pages":"Article 101968"},"PeriodicalIF":2.7,"publicationDate":"2025-09-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145048916","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":2,"RegionCategory":"物理与天体物理","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"The influence of variation in the ratio of components in two-phase lithium-containing ceramics on defect formation processes","authors":"Dmitriy.I. Shlimas ,&nbsp;Malik Kaliyekperov ,&nbsp;Ainash Zhumazhanova ,&nbsp;Artem L. Kozlovskiy ,&nbsp;Bakytzhan Zh. Burkhanov ,&nbsp;Gulnaz Zh. Moldabayeva ,&nbsp;Maxim V. Zdorovets","doi":"10.1016/j.nme.2025.101980","DOIUrl":"10.1016/j.nme.2025.101980","url":null,"abstract":"<div><div>The aim of this study is to determine the effect of changing the ratio of components in the composition of two-component xLi₂TiO₃ − (1-x)Li₂ZrO₃ ceramics on structural distortions and degradation of strength and thermal parameters under high-dose neutron irradiation. The assessment of structural changes was carried out using the electron paramagnetic resonance (EPR) method, which is one of the most accurate methods that allows for a quantitative and qualitative assessment of structural changes caused by irradiation, as well as determining the concentrations of various types of defects depending on the irradiation fluence. It was found that in the case of two-component lithium-containing ceramics, the resistance to accumulation of radiolysis products is due to the effects of the presence of interphase boundaries that inhibit the formation of radiolysis products. According to the qualitative assessment of the EPR spectra, it was established that in the case of two-component ceramics, the formation of HC₂ – centers occurs at higher irradiation fluences (above 5 × 10²⁰ neutron/cm²), while for one-component ceramics, the formation of radiolysis products is observed at irradiation fluences above 10¹⁹ neutron/cm². In this case, a comparative analysis of the concentrations of defects formed in the damaged layer and their evolution indicates an increase in resistance to defect formation processes due to a change in the ratio of components in the composition of two-component ceramics. The improved stability of two-component ceramics against disordering and defect accumulation is attributed to grain boundaries, which act as barriers to oxygen vacancy migration and defect clustering.</div></div>","PeriodicalId":56004,"journal":{"name":"Nuclear Materials and Energy","volume":"44 ","pages":"Article 101980"},"PeriodicalIF":2.7,"publicationDate":"2025-08-27","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144908450","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":2,"RegionCategory":"物理与天体物理","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Helium effect on temperature-displacement rate equivalence in radiation-induced swelling of iron: A study by improved stochastic cluster dynamics","authors":"Yi Hu ,&nbsp;Fangqing Qian ,&nbsp;Xiaolin Li ,&nbsp;He Tong ,&nbsp;Yange Zhang ,&nbsp;Yichun Xu ,&nbsp;Zhuoming Xie ,&nbsp;Rui Liu ,&nbsp;Xiang-Yan Li ,&nbsp;Xuebang Wu ,&nbsp;Xianping Wang ,&nbsp;C.S. Liu","doi":"10.1016/j.nme.2025.101977","DOIUrl":"10.1016/j.nme.2025.101977","url":null,"abstract":"<div><div>In nuclear energy systems, understanding material behavior (e.g., swelling) under irradiation is critical for ensuring long-term stability and safety. While direct neutron irradiation experiments pose significant challenges, ion irradiation serves as an alternative accelerating method for simulating neutron-induced damage. However, fundamental differences exist between neutron and ion irradiation in terms of substantial helium (He) induced by transmutation and significantly lower displacement rate in neutron irradiation than that of ion irradiation experiments. The equivalence between the two irradiation approaches in swelling, as well as the role of He, thus remains poorly understood. This study presents an optimized stochastic cluster dynamics (SCD) framework that combines dynamic rate table updating with a dual-regime strategy of pre-storing properties of small defect clusters while computing large clusters in real time, thereby resolving the persistent memory efficiency trade-off in conventional SCD approaches and meanwhile improving simulation efficiency for high-dose irradiation damage evolution (up to 10 dpa). By using the enhanced methodology, we systematically investigated the effects of temperature, displacement rate, He and vacancy migration energy barrier (<span><math><msubsup><mi>E</mi><mrow><mi>V</mi></mrow><mi>m</mi></msubsup></math></span>) on swelling behavior. The results reveal that these factors significantly influence swelling. Specifically, the swelling of pure iron initially increases and then decreases with rising temperature, with the peak swelling temperature positively correlated with the logarithm of the displacement rate. High displacement rates considerably widen the temperature range for swelling. Increasing the cluster resolution size (i.e., accounting for larger vacancy clusters in swelling calculations) shifts the peak swelling temperature to higher values, whereas higher irradiation doses reduce it. He-induced synergistic damage promotes the formation of large vacancy clusters, expanding the temperature range for swelling and meanwhile resulting in a higher swelling compared to pure displacement damage. Additionally, an increase in <span><math><msubsup><mi>E</mi><mrow><mi>V</mi></mrow><mi>m</mi></msubsup></math></span> (the migration energy of vacancies enhanced by helium and solute effects) leads to a higher peak swelling temperature and a reduced swelling. This study also explores the temperature shifts required to achieve equivalent irradiation damage at different displacement rates, providing insights into temperature selection criteria for ion irradiation equivalence in simulating neutron irradiation. The findings elucidate the mechanisms underlying swelling and establish a foundation for temperature control in neutron and ion irradiation equivalence.</div></div>","PeriodicalId":56004,"journal":{"name":"Nuclear Materials and Energy","volume":"44 ","pages":"Article 101977"},"PeriodicalIF":2.7,"publicationDate":"2025-08-20","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144893485","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":2,"RegionCategory":"物理与天体物理","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Preliminary numerical study on thermal impact of runaway electrons to limiter PFU in fusion reactor","authors":"Siyao Wang ,&nbsp;Xinyuan Qian ,&nbsp;Xuebing Peng","doi":"10.1016/j.nme.2025.101979","DOIUrl":"10.1016/j.nme.2025.101979","url":null,"abstract":"<div><div>Runaway electrons (RE) generated during unmitigated Major Disruptions (MDs) pose a significant threat to Plasma-Facing Components (PFCs) in fusion reactor. The highly energetic RE retain a large fraction of the plasma’s magnetic energy, and can penetrate the First Wall (FW), potentially damaging internal structures, even causing coolant leakage accidents. Understanding the interaction and damage mechanism between RE and FW will help design FW to resist RE impact. In this study, numerical simulations are conducted to investigate the thermal impact of RE on the FW of limiter based on thickened Monoblock structure under fusion reactor conditions, with particular focus on component damage in the RE beam peak region and the factors affecting the RE beam energy deposition. The results indicate that current plasma-facing units (PFUs) of limiter is highly susceptible to damage under the impact of runaway electron beam in fusion reactors. Nevertheless, by controlling the angle between the FW and the magnetic field lines and reducing the energy of the RE beam, the extent of damage to the limiter can be effectively controlled.</div></div>","PeriodicalId":56004,"journal":{"name":"Nuclear Materials and Energy","volume":"44 ","pages":"Article 101979"},"PeriodicalIF":2.7,"publicationDate":"2025-08-20","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144902501","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":2,"RegionCategory":"物理与天体物理","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}