Nuclear Materials and Energy最新文献

{"title":"Improved material mixing model in ERO2.0: Nonlinear effect of boron concentration on tungsten sputtering and influx from mixed tungsten-boron surfaces","authors":"H.A. Kumpulainen ,&nbsp;S. Brezinsek ,&nbsp;J. Romazanov ,&nbsp;A. Kirschner ,&nbsp;C. Baumann ,&nbsp;K. Schmid ,&nbsp;JET contributors","doi":"10.1016/j.nme.2026.102077","DOIUrl":"10.1016/j.nme.2026.102077","url":null,"abstract":"<div><div>An upgraded homogeneous mixing model for plasma-facing surfaces in ERO2.0 has been developed using a database of SDTrimSP mixed-material simulations, replacing earlier linear interpolation between pure-material sputtering yields. The SDTrimSP simulations predict nonlinear relationships between tungsten sputtering yield and low-Z surface concentration, in particular increased tungsten erosion by deuterium from tungsten-boron surfaces at low impact energies (<span><math><mo>&lt;</mo></math></span>300 eV). The updated model features parameterised analytic fit formulas for the sputtered energy and angular distributions, offering higher sampling resolution, significantly reduced memory requirements, and improved robustness against Monte Carlo noise compared to tabulated SDTrimSP outputs. As the first application of the model in an inter-ELM H-mode JET plasma scenario, ERO2.0 simulations predict that introducing a 10% B surface concentration on W divertor components reduces total W erosion by 7%, primarily due to B ions, but increases W erosion and influx from D atom impact by 5% at the outer divertor entrance.</div></div>","PeriodicalId":56004,"journal":{"name":"Nuclear Materials and Energy","volume":"46 ","pages":"Article 102077"},"PeriodicalIF":2.7,"publicationDate":"2026-03-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"146173719","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":"Deuterated ammonia formation, transport and dissociation in Ohmically-heated and nitrogen-seeded JET plasmas with low-recycling conditions at the divertor targets","authors":"R. Mäenpää ,&nbsp;M. Groth ,&nbsp;H. Kumpulainen ,&nbsp;A.G. Meigs ,&nbsp;E. Pawelec ,&nbsp;D. Reiter ,&nbsp;J. Romazanov ,&nbsp;S. Brezinsek ,&nbsp;A. Shaw ,&nbsp;JET Contributors ,&nbsp;EUROfusion Tokamak Exploitation Team","doi":"10.1016/j.nme.2026.102091","DOIUrl":"10.1016/j.nme.2026.102091","url":null,"abstract":"<div><div>A new deuterated ammonia ( <figure><img></figure> ) formation, transport and dissociation model implemented in the ERO2.0 Monte Carlo-code predicts a peak line-integrated deuterated imidogen radical (ND) band emission intensity 50% higher than measured by the vertically-viewing divertor spectrometer in low-recycling, Ohmically-heated and nitrogen-seeded Joint European Torus (JET) plasmas. By assuming a greater kinetic energy release (KER) of 10<!--> <!-->eV instead of 1<!--> <!-->eV upon the dissociation of <figure><img></figure> and its radicals, the model predicts a peak line-integrated ND band emission intensity 25% lower than measured. Together these predictions support the assumption of thermal re-release of incident nitrogen atoms and ions from the divertor targets as nitrogen molecules ( <figure><img></figure> ) and ND₃ in equal fractions.</div><div>Band emission from the ND radical has previously been measured in nitrogen-seeded divertor plasmas in the JET and ASDEX Upgrade tokamaks. The proposed model makes use of the AMMONX database for electron-impact dissociation and ionization rates of <figure><img></figure> molecules and its dissociation products, and recent computational estimates of the electron-impact excitation rates of the ND radical. The assumption of thermal re-release of incident nitrogen ions and atoms as <figure><img></figure> and <figure><img></figure> in equal fractions is also consistent with the maximum rates of ammonia production observed in measurements of tokamak divertor plasmas as well as with measurements performed in laboratory plasma devices with high surface fluxes of reactive hydrogen and nitrogen species.</div></div>","PeriodicalId":56004,"journal":{"name":"Nuclear Materials and Energy","volume":"46 ","pages":"Article 102091"},"PeriodicalIF":2.7,"publicationDate":"2026-03-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"147420281","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":"Erosion and redeposition patterns on divertor tiles after exposure in the first operational phase of WEST","authors":"M. Balden ,&nbsp;M. Diez ,&nbsp;A. Hakola ,&nbsp;M. Mayer ,&nbsp;E. Tsitrone ,&nbsp;the WEST Team","doi":"10.1016/j.nme.2026.102081","DOIUrl":"10.1016/j.nme.2026.102081","url":null,"abstract":"<div><div>Erosion and deposition patterns were obtained by ion beam analyses (Rutherford backscattering (RBS) and nuclear reaction analysis (NRA)) and scanning electron microscopy (SEM assisted by FIB cutting and EDX) on entire W-coated graphite divertor tiles exposed during the 1st operational phase of WEST (2017–2021) covering the campaigns C1 to C5.</div><div>The thicknesses of layers in regions with thick and thin deposition show a progression with plasma exposure duration in a non-linear manner. Very thick deposits exceeding 50 µm after C5 are observed on the high field side of the divertor after 7.3 h of plasma operation. These deposits peel off on sub-millimetre length scales, most probably triggered by arcing. The areal fraction altered by delamination exceeds 20%. The stratified layers are composed of a mixture of boron, carbon, oxygen and tungsten with minor additions of nitrogen, copper, iron (together with nickel) and silver. The deuterium concentration in the thick deposits is at most several atomic percent.</div><div>The tungsten net erosion at the inner and outer strike point areas exceeded already after the C3 campaign the 1–2 µm thickness of the W layer above the marker layer on the special plasma-facing units installed before phase 1 in 2016. The two-dimensional (poloidal and toroidal) net erosion patterns of 5 pairs of inner and outer W-coated standard graphite tiles were analysed to determine the effect of the magnetic ripple on the erosion. These data allow assessing the total net erosion volume around the torus for the complete phase 1 of WEST, resulting in an erosion volume of 1.4 and 1.1 cm³ for the inner and outer strike point areas, respectively. The maximal net erosion is found at the ripple maximum at the inner strike point area (8 µm erosion averaged over several mm², while erosion reaches microscopically up to 15 µm due to the microscopically inhomogeneous erosion pattern).</div></div>","PeriodicalId":56004,"journal":{"name":"Nuclear Materials and Energy","volume":"46 ","pages":"Article 102081"},"PeriodicalIF":2.7,"publicationDate":"2026-03-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"147420283","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":"Manufacturing and high heat flux testing of advanced target mock-ups for the EU-DEMO divertor target","authors":"P. Lorusso ,&nbsp;S. Roccella ,&nbsp;M. Di Bartolomeo ,&nbsp;E. Cacciotti ,&nbsp;M. Cerocchi ,&nbsp;R. De Luca ,&nbsp;E. Martelli ,&nbsp;L. Verdini ,&nbsp;K. Hunger ,&nbsp;P. Junghanns ,&nbsp;A. von Müller ,&nbsp;B. Böswirth ,&nbsp;H. Greuner ,&nbsp;J. Riesch ,&nbsp;J.H. You","doi":"10.1016/j.nme.2025.102045","DOIUrl":"10.1016/j.nme.2025.102045","url":null,"abstract":"<div><div>Among the R&amp;D tasks undertaken for the technological development of plasma facing components, a research activity has been undertaken under the framework of the EUROfusion consortium to pursue the consolidation and verification of the current target concepts envisioned for DEMO, i.e., the ITER-like baseline concept and the back-up concept with tungsten-fiber-reinforced copper (Wf-Cu) pipes. Focus has been addressed on the back-up solution (Wf-Cu pipes) finding alternative technological solutions for monoblock-pipe joining in order to reduce the use of materials having high activation and/or degradation under neutron irradiation. Among the brazing alloys tested for the monoblock/Wf-Cu pipe joint, the Gemco commercial alloy has been selected as the most suitable, thanks to its good joining capability and low content of nickel, which suffers high neutron activation. However, the use of Wf-Cu pipes instead of standard CuCrZr ones complicates the joining. One reason could be that the lower thermal expansion coefficient of W compared to Cu affects the overall expansion behaviour of the tube, making it difficult to fill the gap between the surfaces to be joined (necessary for the assembly) during the brazing process. The present paper describes the manufacturing activities which led to the fabrication of small mock-ups. In particular, fabrication, testing at High Heat Flux (HHF) conditions and analyses of a small mock-up are presented. Non-destructive examinations by ultrasonic testing have been performed pre- and post-HHF tests to assess the structural integrity of the mock-up and the reliability of the joining. Furthermore, microscopic examinations at different magnifications have been carried out to highlight microstructural modifications, recrystallization, and potential defect propagation due to thermal cycling.</div></div>","PeriodicalId":56004,"journal":{"name":"Nuclear Materials and Energy","volume":"46 ","pages":"Article 102045"},"PeriodicalIF":2.7,"publicationDate":"2026-03-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145738858","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":"Elemental analysis of divertor marker tiles exposed during the 2018 (C3), 2019 (C4) and 2020 (C5) WEST campaigns","authors":"R. Mateus ,&nbsp;N. Catarino ,&nbsp;E. Alves ,&nbsp;M. Diez ,&nbsp;E. Bernard ,&nbsp;E. Tsitrone ,&nbsp;M. Balden ,&nbsp;M. Mayer ,&nbsp;J. Likonen ,&nbsp;A. Hakola ,&nbsp;the WEST team","doi":"10.1016/j.nme.2025.102050","DOIUrl":"10.1016/j.nme.2025.102050","url":null,"abstract":"<div><div>Erosion marker tiles mounted in the lower divertor of WEST were exposed during Phase 1 of plasma operations to evaluate poloidal erosion and re-deposition profiles on the tiles. Previous analyses performed to the exposed tiles have shown distinct erosion- or deposition-dominated patterns on them. Afterwards, core-drilled disks cut from the tiles were sent to different laboratories for further and detailed analysis. The present work relates the main results achieved from five characteristic regions of the tiles after completion of the C3, C4, and C5 experimental campaigns on WEST. SIMS and complementary IBA measurements were carried out and the corresponding elemental depth profiles strongly agree, confirming the main earlier conclusions. Deposits are composed of ²H, B, C, O, Mo and W, mainly. Low amounts of Cr, Fe, Ni and Cu were identified as additional metallic impurities. The research confirmed the locations of thin deposition zones nearby the inner and outer divertor limits: at the inner region, the deposition of B and C is particularly enhanced after C4 and C5. Strong erosion zones are located at the inner and outer strike point (ISP and OSP, respectively) areas: only a small erosion occurred after C3, which evolved after C4; nevertheless, the deposition of B and C is enhanced at the OSP edge after C5 nearby the thin deposition zone. Thick deposits appear in the neighborhood of ISP, towards the high field side, and evolve significantly after C4. The amount of O follows the deposition of B. Low retained amounts of ²H were quantified.</div></div>","PeriodicalId":56004,"journal":{"name":"Nuclear Materials and Energy","volume":"46 ","pages":"Article 102050"},"PeriodicalIF":2.7,"publicationDate":"2026-03-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145791720","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":"Effect of spatially non-uniform boronization on plasma restart in WEST","authors":"A. Gallo ,&nbsp;P. Manas ,&nbsp;T. Wauters ,&nbsp;M. Diez ,&nbsp;E. Geulin ,&nbsp;E. Hodille ,&nbsp;J. Gaspar ,&nbsp;N. Rivals ,&nbsp;P. Puglia ,&nbsp;Ph. Moreau ,&nbsp;D. Douai ,&nbsp;T. Alarcon ,&nbsp;V. Anzallo ,&nbsp;E. Caprin ,&nbsp;M. De Combarieu ,&nbsp;F.P. Pellissier ,&nbsp;P. Devynck ,&nbsp;C. Guillemaut ,&nbsp;C. Desgranges ,&nbsp;B. Guillermin ,&nbsp;A. Hakola","doi":"10.1016/j.nme.2025.102042","DOIUrl":"10.1016/j.nme.2025.102042","url":null,"abstract":"<div><div>The recent ITER re-baseline with the adoption of a full-W wall calls for mandatory boronization studies. ITER pulses will be inboard limited on the W tiles of the central column for several seconds during the current ramp up phase. Our first question of this study is: <em>will it be possible to efficiently start plasma operations in a full-W ITER without any boronization?</em> In particular, throughout the start of research operations (SRO), ITER will be equipped with an asymmetric boronization system as glow anodes in the equatorial plane will not be uniformly distributed in the toroidal direction due to the limited availability of ports. According to recent simulations, such arrangement of the glow anodes could lead to a strongly non-uniform B layer with depleted regions. Our second question hence is: <em>should a boronization be needed to start plasma operations in ITER, would a non-uniform B layer be enough?</em> In November 2024, we attempted to restart WEST plasma operations without boronization after a vent and after installing new bulk W limiter tiles. In about 4 days of operation corresponding to 74 pulse attempts, we reached a maximum pulse duration of 1.55 s and a maximum plasma current of 600 kA. Plasmas were cold and dense, mostly detached from the inboard limiter and dominated by light impurities with radiated power fractions close to unity. No runaway electron beams were observed but the restart without boronization was not timely. We then carried out the first WEST boronization utilizing only 3 out of 6 diborane (B₂D₆) inlets (half torus), to deposit a non-uniform B layer. Repeatable, 10 s long, ohmic limiter pulses were immediately achieved with radiated power fractions between 50 % and 70 %. Through a separate experiment in February 2025, we achieved matching pulses before and after a second non-uniform boronization to better characterize its effects: the radiated fraction initially dropped by 22 % with the reduction mainly occurring in the central plasma and well correlating with lower UV signals for O, N and W. These effects almost vanished by the end of the first day after the non-uniform boronization corresponding to a cumulated injected energy of 0.7 GJ.</div></div>","PeriodicalId":56004,"journal":{"name":"Nuclear Materials and Energy","volume":"46 ","pages":"Article 102042"},"PeriodicalIF":2.7,"publicationDate":"2026-03-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145791722","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 actively cooled graphite- and tungsten-armoured JT-60SA flat tile divertor mock-ups","authors":"Daniel Dickes ,&nbsp;Bernd Böswirth ,&nbsp;Katja Hunger ,&nbsp;Gabriel Peyron ,&nbsp;Quentin Tichit ,&nbsp;Marianne Richou ,&nbsp;Johann Riesch ,&nbsp;Mehdi Firdaouss ,&nbsp;Valerio Tomarchio ,&nbsp;Rudolf Neu","doi":"10.1016/j.nme.2026.102067","DOIUrl":"10.1016/j.nme.2026.102067","url":null,"abstract":"<div><div>During the process of developing actively cooled divertor plasma-facing components for JT-60SA, a fusion experiment in Japan built within the framework of the “Broader Approach Agreement” between the European Union and Japan, three small-scale divertor mock-ups have been manufactured. The mock-ups follow the flat-tile design, i.e., have plasma-facing armour tiles joined to an actively cooled heat sink. One mock-up has tungsten (W) armour tiles, and two mock-ups have carbon (C) armour tiles, with the heat sink material being the molybdenum alloy TZM. The joining was realized via diffusion bonding with a titanium interlayer. In this work, the thermo-mechanical behaviour of the mock-ups is assessed with the high heat flux test facility GLADIS in order to qualify the joining technology. This includes screening tests up to a heat flux of 15 <!--> <!-->MW/m² and cyclic loading with a heat flux of 10 <!--> <!-->MW/m² for 10 <!--> <!-->s. During high heat flux testing, pyrometer and thermocouple temperature measurements, digital camera images, and thermographic imaging were used to monitor the mock-ups. In addition, comparative infrared thermography tests and visual characterizations before and after high heat flux testing were performed, including the preparation of cross-sections for scanning electron microscopy. Debonding of the armour tiles did not occur during high heat flux testing, indicating that the diffusion bonding process is suitable. However, this work outlines challenges like a potentially decreasing heat removal capability of the TZM heat sink during cyclic loading or the occurrence of detrimental deep cracking in the case of W armour tiles.</div></div>","PeriodicalId":56004,"journal":{"name":"Nuclear Materials and Energy","volume":"46 ","pages":"Article 102067"},"PeriodicalIF":2.7,"publicationDate":"2026-03-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"146023235","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":"Review on ASDEX Upgrade operation with tungsten plasma facing components","authors":"R. Neu,&nbsp;C. Angioni,&nbsp;V. Bobkov,&nbsp;R. Dux,&nbsp;J. Hobirk,&nbsp;A. Kallenbach,&nbsp;K. Krieger,&nbsp;T. Pütterich,&nbsp;V. Rohde,&nbsp;K. Schmid","doi":"10.1016/j.nme.2026.102063","DOIUrl":"10.1016/j.nme.2026.102063","url":null,"abstract":"<div><div>With the decision of ITER to start its operation with tungsten as plasma facing material also for the main chamber plasma facing components, the interest in the consequences of the use of W was strongly increased. Although many investigations had already been carried out in the all-W ASDEX Upgrade, EAST and WEST tokamak experiments, the ITER decision raised many new questions. To provide a robust foundation for addressing these questions, this paper reviews the tungsten related investigations carried out in ASDEX Upgrade over the last three decades in order to summarize the results achieved so far and to provide a comprehensive list of references for more detailed reading. Further to conclude from this material which results can be used directly for the full-W ITER, where further work is needed and possibly rewarding and which areas are difficult to be researched in AUG and other present-day devices.</div></div>","PeriodicalId":56004,"journal":{"name":"Nuclear Materials and Energy","volume":"46 ","pages":"Article 102063"},"PeriodicalIF":2.7,"publicationDate":"2026-03-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"146023237","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":"Neon retention in tungsten, boron and mixed thin-films under the effects of thermal annealing studied by isotopic tracing","authors":"D.N. Gautam ,&nbsp;D. Primetzhofer ,&nbsp;M. Rubel ,&nbsp;E. Pitthan","doi":"10.1016/j.nme.2025.102053","DOIUrl":"10.1016/j.nme.2025.102053","url":null,"abstract":"<div><div>The retention of two neon isotopes, ²⁰Ne and ²²Ne, was studied by ion beam analysis (IBA) for thin-films of mixed W and B as well as for pure W and B layers grown on silicon-and tungsten-substrates by means of magnetron sputter deposition. Each isotope was implanted to a fluence of 3 × 10¹⁶ at./cm² but at different energies (35–190 keV) to obtain deposition profiles closer to the surface and deeper into the film, depending on isotope and thin-film composition. Thermal annealing in combination with IBA was used to investigate the Ne-retention in a range of temperatures between RT and 1000 °C. Time-of-flight elastic recoil detection analysis was employed to monitor the retention and depth profiles of the Ne isotopes. Both Ne-isotopes remain at their original implantation depth, thus not indicating diffusion, intermixing or desorption for the full range of temperatures and for all studied compositions.</div></div>","PeriodicalId":56004,"journal":{"name":"Nuclear Materials and Energy","volume":"46 ","pages":"Article 102053"},"PeriodicalIF":2.7,"publicationDate":"2026-03-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145926683","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":"Charpy impact properties of EUROFER97-3 after neutron irradiation at 330 °C and 540 °C to damage doses of 21–23 dpa","authors":"Vladimir Chakin,&nbsp;Carsten Bonnekoh,&nbsp;Ramil Gaisin,&nbsp;Rainer Ziegler,&nbsp;Michael Duerrschnabel,&nbsp;Michael Klimenkov,&nbsp;Bronislava Gorr,&nbsp;Michael Rieth","doi":"10.1016/j.nme.2026.102079","DOIUrl":"10.1016/j.nme.2026.102079","url":null,"abstract":"<div><div>The reduced activation ferritic-martensitic (RAFM) EUROFER97-3 steel of two heat treatments (EUROFER97-3_1100/700 and EUROFER97-3_980/780) after irradiation in the BOR-60 fast reactor at temperatures of 330 °C and 540 °C, with damage doses ranging from 21.6 to 22.8 dpa showed big differences in the Charpy impact properties depending on the irradiation temperature. Significant drop in the upper shelf energy (USE) and shift of the ductile–brittle transition temperature (DBTT) occurred after irradiation at 330 °C. However, irradiation at 540 °C resulted in only minor changes in the USE and DBTT compared to the unirradiated reference state. Probably, these changes are attributed of the formation of radiation-induced defects and evolution in the phase structure.</div></div>","PeriodicalId":56004,"journal":{"name":"Nuclear Materials and Energy","volume":"46 ","pages":"Article 102079"},"PeriodicalIF":2.7,"publicationDate":"2026-03-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"146173716","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}