Nuclear Materials and Energy最新文献

{"title":"Dependence of irradiation defects evolution on dose rate and PKA energy spectrum in tungsten","authors":"Wei Zhao ,&nbsp;Yu-Hao Li ,&nbsp;Hui-Zhi Ma ,&nbsp;Yu-Ze Niu ,&nbsp;Zhangcan Yang ,&nbsp;Dmitry Terentyev ,&nbsp;Hong-Bo Zhou ,&nbsp;Guang-Hong Lu","doi":"10.1016/j.nme.2025.101956","DOIUrl":"10.1016/j.nme.2025.101956","url":null,"abstract":"<div><div>Heavy-ion irradiation is considered as an effective method to study the performance of nuclear materials under neutron irradiation, while these two types of experiments show the striking difference in microstructure evolution and thermo-mechanical properties. In this work, taking tungsten (W) as an example, we systematically investigated how dose rate and primary knock-on atom (PKA) energy spectrum affect the evolution of displacement damages in materials using object kinetic Monte Carlo (OKMC) method. It is found that the increase of dose rate promotes the nucleation of vacancy clusters and dislocation loops but inhibits their growth, which is in agreement with the experimental results. This should be attributed to shortened evolution time, which suppresses the migration and dissociation of defects and promotes their nucleation, which can be compensated by the increase of temperature. Accordingly, a modified predictive model has been proposed to characterize the compensatory effect of temperature on different dose rates. However, different from the dose rate, the influence of PKA energy spectrum cannot be compensated by temperature variation, because the high-energy PKAs may generate large and stable defect clusters directly during collision cascade. These results clarify the influence of dose rate and PKA energy spectrum on the evolution of displacement defects in W, and provide valuable insights for assessing the performance of materials under neutron irradiation.</div></div>","PeriodicalId":56004,"journal":{"name":"Nuclear Materials and Energy","volume":"43 ","pages":"Article 101956"},"PeriodicalIF":2.3,"publicationDate":"2025-05-26","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144154802","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":"Oxidation behaviour of PM-C26M FeCrAl alloy in low-temperature steam 400 – 900 °C","authors":"Logan Joyce ,&nbsp;Rajnikant V. Umretiya ,&nbsp;Haozheng Qu ,&nbsp;Zhongxia Shang ,&nbsp;Yi Xie","doi":"10.1016/j.nme.2025.101953","DOIUrl":"10.1016/j.nme.2025.101953","url":null,"abstract":"<div><div>Iron-chromium-aluminum (FeCrAl) alloys are the primary candidate for serving as an accident tolerant fuel cladding, replacing zirconium (Zr)-based cladding. This preference stems from the high corrosion resistance under both operating and accident conditions in light water reactors (LWRs). To successfully implement this alloy as a cladding material in LWRs, the corrosion behavior under various conditions needs to be understood. While recent studies have focused on high-temperature steam conditions (&gt;1000 °C) and operating conditions (∼300 °C), there is a notable gap in research exploring the steam temperature range above 300 °C and below 1000 °C. This study specifically investigated the formation of oxide layers on powder metallurgy (PM)-C26M FeCrAl in steam at temperatures ranging from 400 °C – 900 °C. It was found that within the temperature range of 400 °C – 600 °C, a duplex oxide layer emerges, with Fe-oxide in the outer layer and Cr/Al-oxide in the inner layer. At 500 °C, the outer layer consists of α-Fe₂O₃ crystals with Cr/Al-oxides in the inner layer. The initial occurrence of a single oxide layer mostly comprised of alumina (Al₂O₃) is observed at 700 °C, remaining consistent from the 700 °C – 900 °C range. The Al₂O₃ layer is nanocrystalline, but not as thick or as uniform in composition as that observed in high-temperature steam environments. Notably, the Al₂O₃ layer has Fe, Cr, and molybdenum (Mo) precipitates dispersed throughout. Increasing the temperature decreases the presence of these precipitates in the oxide layer, and an increase in either temperature or time results in an increase in the thickness of Al₂O₃ layer.</div></div>","PeriodicalId":56004,"journal":{"name":"Nuclear Materials and Energy","volume":"43 ","pages":"Article 101953"},"PeriodicalIF":2.3,"publicationDate":"2025-05-23","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144134606","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":"Strength of a circumferential W/Cu/CuCrZr joint of ITER monoblock","authors":"K. Poleshchuk ,&nbsp;D. Terentyev ,&nbsp;F. Crea ,&nbsp;P. Gavila ,&nbsp;S. Roccella ,&nbsp;K. Verbeken","doi":"10.1016/j.nme.2025.101947","DOIUrl":"10.1016/j.nme.2025.101947","url":null,"abstract":"<div><div>A newly developed methodology for testing ITER monoblock was applied for the first time to measure the strength of a circumferential W/Cu/CuCrZr joint. An innovative anchor-shape configuration was used to machine tensile samples using ITER-specification W/Cu monoblocks, on which ITER-specification CuCrZr pipe was attached using hot radial pressing.</div><div>This contribution presents the results of mechanical testing and microstructural investigations of the abovementioned W/Cu/CuCrZr joints conducted at room temperature, as well as at the ITER operational conditions. It is found that depending on the test temperature, the fracture occurs in different locations corresponding to different damage modes. In some cases, the obtained ultimate tensile strength can be directly associated with the joint strength. However, the methodology emphasises the importance of correlating fracture location and detailed microstructural analysis of the fracture surface with the tensile test results. The findings reveal the dependencies of the joint strength and fracture mode on temperature, with a transition in failure modes observed at elevated temperatures. The results presented in this article are important for the interpretation of the effect of future neutron irradiation campaigns on W/Cu/CuCrZr joints.</div></div>","PeriodicalId":56004,"journal":{"name":"Nuclear Materials and Energy","volume":"43 ","pages":"Article 101947"},"PeriodicalIF":2.3,"publicationDate":"2025-05-20","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144138676","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":"SLM-printed EUROFER steel for fusion applications","authors":"Ramil Gaisin,&nbsp;Carsten Bonnekoh,&nbsp;Simon Bonk,&nbsp;Heiko Neuberger,&nbsp;Vladimir Chakin,&nbsp;Michael Rieth","doi":"10.1016/j.nme.2025.101951","DOIUrl":"10.1016/j.nme.2025.101951","url":null,"abstract":"<div><div>This study investigates selective laser melting (SLM) of atomized EUROFER97 powder for fusion applications, focusing on two fabrications and their resulting microstructure, tensile properties, impact toughness, and leak-tightness. Optimized powder preparation improved chemical composition and grain size after heat treatment, enhancing Charpy impact toughness with an upper shelf energy surpassing the EUROFER97 standard and a lower ductile-to-brittle transition temperature (−120 °C vs. −100 °C). Tensile properties, including yield and ultimate strength and elongation, were similar to the EUROFER97 reference material.</div><div>SLM-printed capsules demonstrated excellent leak-tightness, with helium leak rates well below ITER requirements, and burst tests confirmed ultimate strengths exceeding 700 MPa. These findings showcase potential of SLM for creating complex components for fusion reactor blankets with tailored mechanical properties.</div></div>","PeriodicalId":56004,"journal":{"name":"Nuclear Materials and Energy","volume":"43 ","pages":"Article 101951"},"PeriodicalIF":2.3,"publicationDate":"2025-05-15","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144115929","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 effects of W and Mo on the formation of early stage α’ solute clusters in ion-irradiated Fe-Cr-X (X = W/Mo) alloys","authors":"Rong Hu ,&nbsp;Yuhang Zhu ,&nbsp;Meiqing Chen ,&nbsp;Jing Xue","doi":"10.1016/j.nme.2025.101950","DOIUrl":"10.1016/j.nme.2025.101950","url":null,"abstract":"<div><div>Reduced activation ferritic-martensitic (RAFM) steels are known to suffer from 475 °C embrittlement, which is associated with the formation of Cr-enriched α’ phase, while dislocation loops also contribute to radiation hardening. The precipitation behavior in RAFM steels is highly complex, involving the formation of various types of precipitates as well as intricate interactions between different alloying elements. To date, only a limited number of studies have investigated the effects of minor alloying elements, such as Ni, Si, P, C and Al, under irradiation conditions. To enhance understanding of α’ phase formation in RAFM steels, this study conducted detailed experiments using Atom Probe Tomography (APT) on Fe-9Cr, Fe-9Cr-0.5 W and Fe-9Cr-0.5Mo alloys under self-ion irradiation to examine the effects of W and Mo additions. Ion irradiation was performed using sequential energies of 0.5 MeV, 1 MeV, and 2 MeV to achieve target maximum damage levels of 5 dpa and 10 dpa at 350 °C. Cr-enriched clusters were identified in these ion-irradiated samples. It was observed that W strongly suppresses the formation and evolution of Cr-enriched clusters due to its strong binding with vacancies, which reduces Cr diffusion. In contrast, Mo appears to promote the formation of Cr-enriched clusters and facilitates the growth of large clusters, possibly due to the positive interaction between Mo and Cr atoms.</div></div>","PeriodicalId":56004,"journal":{"name":"Nuclear Materials and Energy","volume":"43 ","pages":"Article 101950"},"PeriodicalIF":2.3,"publicationDate":"2025-05-14","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144070307","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":"Improved liquid lithium surfaces in the Lithium Tokamak Experiment-β","authors":"D.P. Boyle ,&nbsp;A. Maan ,&nbsp;R. Majeski ,&nbsp;E. Ostrowski ,&nbsp;S. Abe ,&nbsp;S. Banerjee ,&nbsp;W. Capecchi ,&nbsp;D.B. Elliott ,&nbsp;C. Hansen ,&nbsp;E. Jung ,&nbsp;P.E. Hughes ,&nbsp;S. Kubota ,&nbsp;M. Lampert ,&nbsp;R. Maingi ,&nbsp;A.G. McLean ,&nbsp;J.E. Menard ,&nbsp;J.J. Morales ,&nbsp;V.A. Soukhanovskii","doi":"10.1016/j.nme.2025.101949","DOIUrl":"10.1016/j.nme.2025.101949","url":null,"abstract":"<div><div>Advances in vacuum, surface, and lithium conditioning techniques throughout five years of continuous operations in LTX-β have produced mirror-like liquid lithium surfaces and demonstrated the feasibility of high-performance tokamak discharges fully surrounded by liquid metal without significant operational problems. Improvements in conditioning techniques and procedures, including many weeks of baking and accumulation of 70 g of Li, led to reduced residual gasses and clean Li surfaces − all while still maintaining enough operational flexibility for multiple in-vacuum diagnostic upgrades and calibrations. Coatings had a visibly clean appearance, with reflective liquid metal demonstrating good wetting and surface adhesion with films that were now macroscopically thick. Solidified Li showed large crystal grains, while surface science measurements observed reduced impurities in the lithium. Steadily improved plasma performance was achieved with liquid lithium, with discharges able to match solid Li in terms of evolution of I_p and n_e, including rapid density pumping indicating low recycling. There were indications of moderately increased Li impurity influx, though few significant disturbances by the large liquid surfaces on tokamak operations over hundreds of discharges. Liquid metal plasma facing components are a potential solution to the extreme heat and particle fluxes that could cause unacceptable damage to solid materials, while liquid lithium also has the potential for greatly increased confinement in the low-recycling regime. While many liquid metal approaches are possible, and numerous experiments have been conducted in test stands and small modules in fusion devices, LTX-β is the only tokamak operated while fully surrounded by liquid metal.</div></div>","PeriodicalId":56004,"journal":{"name":"Nuclear Materials and Energy","volume":"43 ","pages":"Article 101949"},"PeriodicalIF":2.3,"publicationDate":"2025-05-10","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144069265","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":"Exhaust assessment of a European Volumetric Neutron Source (EU-VNS) using SOLPS-ITER","authors":"S. Wiesen ,&nbsp;Ch. Bachmann ,&nbsp;M. Siccinio ,&nbsp;J. Boscary ,&nbsp;C. Bourdelle ,&nbsp;M. Coleman ,&nbsp;G. Federici ,&nbsp;F. Maviglia ,&nbsp;R. Neu","doi":"10.1016/j.nme.2025.101939","DOIUrl":"10.1016/j.nme.2025.101939","url":null,"abstract":"<div><div>EUROfusion considers a volumetric neutron source (EU-VNS) to generate a neutron wall load of about <span><math><mrow><mn>0</mn><mo>.</mo><mn>5</mn><mspace></mspace><mi>M</mi><mi>W</mi><mo>/</mo><msup><mrow><mi>m</mi></mrow><mrow><mn>2</mn></mrow></msup></mrow></math></span> to qualify tritium breeding blankets early in support of EU-DEMO that mitigates the risk of a late testing for required nuclear technology. The envisaged small-scale <span><math><mrow><mi>R</mi><mo>=</mo><mn>2</mn><mo>.</mo><mn>5</mn><mspace></mspace><mi>m</mi></mrow></math></span> D-beam/T-target driven fusion device (<span><math><mrow><msub><mrow><mi>P</mi></mrow><mrow><mi>f</mi><mi>u</mi><mi>s</mi></mrow></msub><mo>≈</mo><mn>30</mn><mspace></mspace><mi>M</mi><mi>W</mi></mrow></math></span>) must exhaust helium particles and dissipate sufficient energy from the large auxiliary power required (<span><math><mrow><msub><mrow><mi>P</mi></mrow><mrow><mi>a</mi><mi>u</mi><mi>x</mi></mrow></msub><mo>≈</mo><mn>50</mn><mspace></mspace><mi>M</mi><mi>W</mi></mrow></math></span>) entering in large parts the edge. A SOLPS-ITER assessment indicates that with argon seeding a finite divertor operational window exists allowing to avoid core dilution by helium and to reduce the peak heat-flux density below <span><math><mrow><mn>10</mn><mspace></mspace><mi>M</mi><mi>W</mi><mo>/</mo><msup><mrow><mi>m</mi></mrow><mrow><mn>2</mn></mrow></msup></mrow></math></span>. It is shown that an extra constraint of <span><math><mrow><msub><mrow><mi>Z</mi></mrow><mrow><mi>e</mi><mi>f</mi><mi>f</mi></mrow></msub><mo>&lt;</mo><mn>2</mn><mo>−</mo><mn>3</mn></mrow></math></span>, required to sustain good core performance to produce the required amount of fusion neutrons, can also be met if the Greenwald-fraction <span><math><mrow><msub><mrow><mi>f</mi></mrow><mrow><mi>G</mi><mi>W</mi></mrow></msub><mo>≈</mo><mn>0</mn><mo>.</mo><mn>5</mn></mrow></math></span> is maintained with total T-throughputs at about half the ITER value. It is reasoned that for a EU-VNS design study the exhaust operational window can be enlarged by choosing other seeding species like Krypton, refining the balance between pellet- to gas-fuelling, and integrated core-edge modelling.</div></div>","PeriodicalId":56004,"journal":{"name":"Nuclear Materials and Energy","volume":"43 ","pages":"Article 101939"},"PeriodicalIF":2.3,"publicationDate":"2025-05-09","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143934629","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":"First-principles study of beryllium thermodynamics and clustering mechanism in molybdenum: Effects of vacancies and self-interstitial atoms","authors":"Aoyu Mo ,&nbsp;Haijun Li ,&nbsp;Fuquan Guo ,&nbsp;Xiaowei Ma ,&nbsp;Yunshan Xiong ,&nbsp;Peng Shao ,&nbsp;Bo Li ,&nbsp;Kun Jie Yang ,&nbsp;Yue-Lin Liu ,&nbsp;Quan-Fu Han","doi":"10.1016/j.nme.2025.101948","DOIUrl":"10.1016/j.nme.2025.101948","url":null,"abstract":"<div><div>The clustering behavior of beryllium (Be) following plasma irradiation is of particular significance for molybdenum (Mo) in future fusion devices. Using first-principles calculations combined with thermodynamic models, the optimal configuration for Be clustering in Mo has been clearly determined, with a particular focus on the effects of vacancies and self-interstitials (SIAs). As the initial form of nucleation, the physical origin of Be-Be pair binding energy in Mo has been shown to be primarily dominated by the charge density at their location. Based on all of our computational results, a potential clustering mechanism for the formation of Be-rich regions in Mo is proposed: Be atoms first aggregate at interstitial sites, forming Be_n clusters. When the number of Be atoms reaches six, they form an approximately “octahedral” structure, displacing a central Mo atom and generating a Be₆V cluster and an SIA. They act as nucleation sites that continue to attract more Be atoms, growing into larger Be_nV and Be_n-SIA clusters. As the Be_n-SIA clusters expand, excess Be atoms displace more Mo atoms, creating additional SIAs and vacancies and further propagating the formation of Be_n-SIA and Be_nV clusters. This cascading process ultimately results in the development of Be-rich regions within Mo. Our results provide significant data support for advancing Mo as a primary mirror material and also offer valuable theoretical insights into the aggregation behavior of impurities in metals under irradiation conditions.</div></div>","PeriodicalId":56004,"journal":{"name":"Nuclear Materials and Energy","volume":"43 ","pages":"Article 101948"},"PeriodicalIF":2.3,"publicationDate":"2025-05-06","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144083796","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":"A first study of the complex-concentrated-alloy W38Ta36Cr15V11 in Pisces-RF high-flux deuterium plasma","authors":"M.T. Vigil ,&nbsp;S. Faulhaber ,&nbsp;M.I. Patino ,&nbsp;A. Založnik ,&nbsp;D. Nishijima ,&nbsp;M.J. Simmonds ,&nbsp;B. Schwendeman ,&nbsp;K. Vecchio ,&nbsp;G.R. Tynan ,&nbsp;M.J. Baldwin","doi":"10.1016/j.nme.2025.101943","DOIUrl":"10.1016/j.nme.2025.101943","url":null,"abstract":"<div><div>Bulk targets of W₃₈Ta₃₆Cr₁₅V₁₁ complex concentrated alloy (CCA) were produced by spark plasma sintering at the Vecchio materials research lab at the University of California–San Diego. Targets fabricated were reasonably dense, BCC phase, compositionally close in match to that of El-Atwani et al. (2019), and homogeneous, as measured by electron microscopy, energy dispersive x-ray microanalysis (EDX), EDX mapping, and x-ray diffraction. The targets were exposed to deuterium plasma of associated 100 eV ion fluences of <span><math><mrow><mn>2</mn><mo>×</mo><mn>1</mn><msup><mrow><mn>0</mn></mrow><mrow><mn>26</mn></mrow></msup></mrow></math></span> m⁻² at 523 K, 773 K and 1023 K in the <span>Pisces-RF</span> high-flux linear plasma device. Plasma exposure is found to produce surface compositional enrichment in W and Ta, as determined by Auger electron spectroscopy and EDX, that is caused by a depletion of surface Cr and V, the former being observed with optical emission spectroscopy in the target plasma. Accompanying the compositional change, transient grating spectroscopy analysis, taken pre- and post-plasma exposure on the 1023 K exposed target, revealed <span><math><mrow><mo>∼</mo><mn>30</mn><mtext>%</mtext></mrow></math></span> reduction in surface thermal diffusivity from <span><math><mrow><mn>9</mn><mo>.</mo><mn>4</mn><mo>×</mo><mn>1</mn><msup><mrow><mn>0</mn></mrow><mrow><mo>−</mo><mn>6</mn></mrow></msup></mrow></math></span> m²s⁻¹ to <span><math><mrow><mn>6</mn><mo>.</mo><mn>7</mn><mo>×</mo><mn>1</mn><msup><mrow><mn>0</mn></mrow><mrow><mo>−</mo><mn>6</mn></mrow></msup></mrow></math></span> m²s⁻¹. Lastly, D retention in the CCA targets was found to be characterized by a singular thermal release peak at <span><math><mrow><mo>∼</mo><mn>900</mn></mrow></math></span> K, and retention varied from <span><math><mrow><mn>2</mn><mo>×</mo><mn>1</mn><msup><mrow><mn>0</mn></mrow><mrow><mn>23</mn></mrow></msup></mrow></math></span> m⁻² to <span><math><mrow><mn>3</mn><mo>×</mo><mn>1</mn><msup><mrow><mn>0</mn></mrow><mrow><mn>20</mn></mrow></msup></mrow></math></span> m⁻² for exposure in the temperature range 523–1023 K, as measured by thermal desorption spectrometry. This level of D retention is found to be high relative to pure tungsten.</div></div>","PeriodicalId":56004,"journal":{"name":"Nuclear Materials and Energy","volume":"43 ","pages":"Article 101943"},"PeriodicalIF":2.3,"publicationDate":"2025-05-05","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143917316","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":"Machine learning-based hydrogen recycling model for predicting rovibrational distributions of released molecular hydrogen on tungsten materials via molecular dynamics simulations","authors":"Seiki Saito ,&nbsp;Masato Iida ,&nbsp;Hiroaki Nakamura ,&nbsp;Keiji Sawada ,&nbsp;Kazuo Hoshino ,&nbsp;Masahiro Kobayashi ,&nbsp;Masahiro Hasuo ,&nbsp;Yuki Homma ,&nbsp;Shohei Yamoto","doi":"10.1016/j.nme.2025.101942","DOIUrl":"10.1016/j.nme.2025.101942","url":null,"abstract":"<div><div>Understanding the hydrogen recycling process is crucial for comprehending the behavior of detached plasma in nuclear fusion devices. To achieve this, a molecular dynamics (MD) model is being developed to predict the distribution of translational energies and rovibrational states of hydrogen atoms and molecules released from the plasma-facing materials. Neutral transport simulations, utilizing distributions obtained from the MD model as boundary conditions, are also a powerful tool for analyzing the impact of recycled hydrogens on edge plasma. However, the MD model requires significant computational resources to obtain distributions under varying material and irradiation conditions such as material temperature and incident energy. Therefore, developing effective models that seamlessly integrate neutral transport simulation with hydrogen recycling models is crucial. Machine learning techniques are employed to develop predictive models capable of forecasting distributions of energies and rovibrational states of released hydrogen atoms and molecules. Furthermore, a model considering the incident energy distribution (shifted-Maxwellian) is developed by integrating the monochromatic distribution with the shifted-Maxwellian distribution.</div></div>","PeriodicalId":56004,"journal":{"name":"Nuclear Materials and Energy","volume":"43 ","pages":"Article 101942"},"PeriodicalIF":2.3,"publicationDate":"2025-05-04","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143927405","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}