Nuclear Materials and Energy最新文献

{"title":"Water corrosion behavior of CLF-1 steel in Experimental Advanced Superconducting Tokamak (EAST) magnetic field environment","authors":"Shu-Feng Zhang ,&nbsp;Yi-Ming Lyu ,&nbsp;Ye Li ,&nbsp;Shang-Ming Chen ,&nbsp;Lei Peng ,&nbsp;Ming Wang ,&nbsp;Shan-Liang Zheng","doi":"10.1016/j.nme.2026.102158","DOIUrl":"10.1016/j.nme.2026.102158","url":null,"abstract":"<div><div>The magnetic field environment influences both the corrosion characteristics of metallic materials in water and the transport processes of corrosion products. Fusion reactor magnetic fields, characterized by their high strength and unique configuration, necessitate an evaluation of their impact on the corrosion of structural materials, particularly the piping materials in water-cooled blanket systems. Such evaluation is essential for investigating the generation, transport, and distribution mechanisms of activated corrosion products and for ensuring the safe operation of fusion reactors. In the absence of an operating fusion reactor, water corrosion experiments can be conducted within the magnetic field of a Tokamak device with a similar configuration to mimic and study these mechanisms. In this work, corrosion experiments were performed on CLF-1 steel in a solution of 1 wt% H₂O₂ + 0.1 wt% NaCl for durations of 2 h, 12 h, and 24 h under the magnetic field environment of the EAST (Experimental Advanced Superconducting Tokamak). Comparative experiments were conducted without a magnetic field. The localized corrosion of CLF-1 steel in solution and the general corrosion in pressurized water both fall under electrochemical corrosion. This model experiment will provide a reference for the study of corrosion products in fusion reactors. Analysis of the sample morphology and corrosion products composition revealed that under the EAST magnetic field, the corrosion products around corrosion pits tended to exhibit a nearly circular distribution on the sample surface, whereas in the absence of the field, the corrosion products showed a striated distribution. The magnetic field distribution at the C-port of the EAST device, where the samples were located, was simulated using ANSYS software. The simulation indicated that the magnetic field at the C-port is predominantly toroidal, and its direction during the corrosion experiments was nearly perpendicular to the sample surface. These results suggest that the Lorentz force and the magnetic gradient force induced by the EAST magnetic field alter the migration of ions and paramagnetic substances, respectively, thereby modifying the distribution characteristics of the corrosion products.</div></div>","PeriodicalId":56004,"journal":{"name":"Nuclear Materials and Energy","volume":"47 ","pages":"Article 102158"},"PeriodicalIF":2.7,"publicationDate":"2026-06-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"148230854","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":"Dissolution of unirradiated MOX fuel in the presence of magnetite and chukanovite","authors":"M. Saleh ,&nbsp;E. Darwish ,&nbsp;M. Hedberg ,&nbsp;P.L. Tam ,&nbsp;K. Spahiu ,&nbsp;C. Ekberg","doi":"10.1016/j.nme.2026.102148","DOIUrl":"10.1016/j.nme.2026.102148","url":null,"abstract":"<div><div>In all European concepts for deep geological repositories of spent nuclear fuel, massive canisters with cast iron inserts are designed to prevent early interaction between the spent nuclear fuel and groundwater. Should a canister breach occur, corrosion of the fuel would take place at repository depths of several hundred meters where the surrounding groundwater is generally anoxic. The radiation field surrounding the fuel alters local redox conditions through water radiolysis. Under such conditions, fuel corrosion is anticipated to proceed simultaneously with anoxic iron corrosion. When all iron is corroded, iron corrosion products will be present for very long times in the near field of a repository and thus buffer the redox conditions in the near field. By using a MOX fuel pellet with an extremely high alpha field, we can test the effects of iron corrosion products on fuel dissolution considering that the very old fuel they will contact in the repository has orders of magnitude lower alpha dose rates.</div><div>In this study, two leaching experiments were conducted on unirradiated MOX fuel pellets containing 10 wt% plutonium (specific alpha activity: 1.79 GBq/g) under an argon atmosphere in simulated granitic groundwater representative of the Forsmark site in Sweden. The experiments were performed in the presence of magnetite and synthesized chukanovite to assess their influence on the corrosion and leaching behaviour of the unirradiated MOX fuel. A strong inhibiting effect on fuel dissolution was noted for chukanovite, while magnetite could not counteract the radiolytic dissolution of the unirradiated MOX pellet.</div></div>","PeriodicalId":56004,"journal":{"name":"Nuclear Materials and Energy","volume":"47 ","pages":"Article 102148"},"PeriodicalIF":2.7,"publicationDate":"2026-06-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"148177746","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":"Change of the Bidirectional Reflectance Distribution Function for the Metal First Wall exposed in EAST","authors":"Yefan Zhu ,&nbsp;Rong Yan ,&nbsp;Chuannan Xuan ,&nbsp;Yuming Liu ,&nbsp;Zhaohui Wang ,&nbsp;Lei Mu ,&nbsp;Wei Zheng ,&nbsp;Shumei Xiao ,&nbsp;Zengjie Li ,&nbsp;Chunyu He ,&nbsp;Junling Chen ,&nbsp;Pengfei Zi","doi":"10.1016/j.nme.2026.102141","DOIUrl":"10.1016/j.nme.2026.102141","url":null,"abstract":"<div><div>Optical diagnostics is an important method for obtaining basic parameters and operational conditions of the plasma in the tokamak. The bidirectional reflectance distribution function (BRDF) of the wall will have a degradation during the plasma experiment, which will then affect the signal-to-noise ratio of optical diagnostics. Studying the BRDF change of the metal first wall could help to understand the change of wall reflection level and its possible influence on optical diagnostics. Two molybdenum-titanium-zirconium (TZM) first wall tiles with different levels of impurity deposition after exposure in EAST for one experimental campaign operation were analyzed. The surface morphology and elemental composition were characterized by scanning electron microscopy (SEM), energy-dispersive X-ray spectroscopy (EDS), and X-ray Photoelectron Spectroscopy (XPS). The BRDF value of the samples was also measured. The results show that after about 7426 plasma pulses, the peak BRDF value of the material decreased by about two orders of magnitude, and the BRDF curve exhibits asymmetry about the specular direction. The SEM observations showed that the microscopic spherical-like structures of the deposited layer are responsible for the shadowing and masking effects, thus accounting for the asymmetry observed in the BRDF curve. The EDS results indicated that the introduction of non-metallic components within the deposition layer will introduce the degradation of the BRDF value. These findings provide valuable references for analyzing wall reflectance behavior in EAST and other tokamaks.</div></div>","PeriodicalId":56004,"journal":{"name":"Nuclear Materials and Energy","volume":"47 ","pages":"Article 102141"},"PeriodicalIF":2.7,"publicationDate":"2026-06-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"148177693","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":"Analytical description of the creep rate of zirconium alloys under irradiation","authors":"Andrew Rusinko","doi":"10.1016/j.nme.2026.102149","DOIUrl":"10.1016/j.nme.2026.102149","url":null,"abstract":"<div><div>This paper presents a mathematical model for irradiation creep in zirconium alloys. The model is based on the Synthetic Theory of irreversible deformation. By analyzing the mechanisms governing time‑dependent deformation under irradiation at temperatures where thermal creep is only weakly expressed, a new term that accounts for the influence of flux on the steady‑state creep rate is introduced into the basic equations of the Synthetic Theory. As an example, diagrams are constructed for the steady‑state creep of a zirconium alloy as a function of applied stress at different temperatures and irradiation fluxes. The modeled curves, which agree well with the experimental data, show, in particular, that the irradiation creep rate is lower than the corresponding thermal creep rate at high stresses.</div></div>","PeriodicalId":56004,"journal":{"name":"Nuclear Materials and Energy","volume":"47 ","pages":"Article 102149"},"PeriodicalIF":2.7,"publicationDate":"2026-06-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"148177744","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":"Steam oxidation of 316Nb Stainless-Steel from 850°C to 1350°C: kinetics and thermodynamic analysis","authors":"M. Barrachin ,&nbsp;S. Guilbert ,&nbsp;L. Laborde ,&nbsp;P. Lacôte ,&nbsp;A. Viretto","doi":"10.1016/j.nme.2026.102144","DOIUrl":"10.1016/j.nme.2026.102144","url":null,"abstract":"<div><div>This paper presents a comprehensive study on the steam oxidation behaviour of 316Nb stainless steel at temperatures ranging from 850°C to 1350°C. The oxidation process formed complex, multilayered scales on the 316Nb samples. The outermost layer, primarily composed of iron oxides (magnetite and wüstite), was non-adherent and brittle. At temperatures above 1150°C, an intermediate layer containing oxygen, iron, and chromium was observed. The innermost layer exhibited a porous, fine-grained structure of oxidic particles embedded in a metallic Fe-Ni matrix. The oxidation kinetics can be approximated by a parabolic law after an initial incubation period, with 316Nb demonstrating superior resistance to steam oxidation compared to 304L stainless steel below 1200°C. Above this temperature, both alloys exhibited similar oxidation behaviour. A key insight from this study is the absence of catastrophic oxidation in 316Nb, despite its significant molybdenum content.</div></div>","PeriodicalId":56004,"journal":{"name":"Nuclear Materials and Energy","volume":"47 ","pages":"Article 102144"},"PeriodicalIF":2.7,"publicationDate":"2026-06-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"148177747","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":"Assessment of interatomic potentials for 1/2 <111> screw dislocation properties in tungsten and molybdenum","authors":"Wei-shu Yang ,&nbsp;Chang-jie Ding ,&nbsp;Zi-qiang Wang ,&nbsp;Xiao-lin Li ,&nbsp;Xiang-yan Li ,&nbsp;Yan-ge Zhang ,&nbsp;Yi-chun Xu ,&nbsp;C.S. Liu ,&nbsp;Xuebang Wu","doi":"10.1016/j.nme.2026.102151","DOIUrl":"10.1016/j.nme.2026.102151","url":null,"abstract":"<div><div>In this work, we systematically evaluated 27 W and 19 Mo interatomic potentials focusing on bulk and screw dislocation properties. The bulk properties primarily include: elastic constants, bulk modulus, shear modulus, Poisson’s ratio, and stacking fault energy; and the screw dislocation properties mainly consist of: differential displacement map of core structure, Peierls energy barrier, and Peierls stress. We identified six W potentials and three Mo potentials that are suitable for screw dislocation simulations. The computational efficiency of these selected potentials was subsequently benchmarked. Finally, considering both accuracy and computational efficiency, we employed three representative interatomic potentials to investigate the effect of temperature on screw dislocation motion. The critical resolved shear stress for dislocation motion decreases with increasing temperature and is accompanied by enhanced cross-slip propensity. This work offers a reference for selecting appropriate interatomic potentials in molecular dynamics simulations to investigate screw dislocation properties in W and Mo.</div></div>","PeriodicalId":56004,"journal":{"name":"Nuclear Materials and Energy","volume":"47 ","pages":"Article 102151"},"PeriodicalIF":2.7,"publicationDate":"2026-06-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"148177742","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":"Corrigendum to “Measurement of residual stresses in surrogate coated nuclear fuel particles using ring-core focussed ion beam digital image correlation” [Nucl. Mater. Energy 36 (2023) 101470]","authors":"Alexander J. Leide,&nbsp;Thomas A. Haynes,&nbsp;Nassia Tzelepi,&nbsp;John Payne,&nbsp;Matthew Jordan,&nbsp;Steven Knol,&nbsp;Jan A. Vreeling,&nbsp;Mark Davies,&nbsp;David T. Goddard,&nbsp;Manuel J. Pfeifenberger,&nbsp;Markus Alfreider,&nbsp;Daniel Kiener,&nbsp;Dong Liu","doi":"10.1016/j.nme.2026.102108","DOIUrl":"10.1016/j.nme.2026.102108","url":null,"abstract":"","PeriodicalId":56004,"journal":{"name":"Nuclear Materials and Energy","volume":"47 ","pages":"Article 102108"},"PeriodicalIF":2.8,"publicationDate":"2026-06-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"148539540","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":2,"RegionCategory":"物理与天体物理","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"OA","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Investigation of tensile behavior of additive manufacturing Z2CN19-10 steel via single-stress small punch test","authors":"Yaxin Li ,&nbsp;Rongcheng Wang ,&nbsp;Huan Sheng Lai ,&nbsp;Huanchun Wu ,&nbsp;Sixiong Zeng ,&nbsp;Quan Wen","doi":"10.1016/j.nme.2026.102155","DOIUrl":"10.1016/j.nme.2026.102155","url":null,"abstract":"<div><div>With the advancement of wire arc additive manufacturing (WAAM) technology, the use of WAAM materials has become increasingly widespread. However, these materials normally exhibit anisotropic characteristics, which pose significant challenges in the examination of their mechanical properties due to the limited volume of material available in some cases. Z2CN19-10 is newly developed to prevent corrosion cracking in nuclear power plants. This study investigated the tensile behavior of WAAM Z2CN19-10 steel using uniaxial tensile tests (UTTs), small punch tests (SPTs), and single-stress small punch tests (SS-SPTs). Additionally, the microstructure was characterized using metallographic microscopy (MM), scanning electron microscopy (SEM), and electron backscatter diffraction (EBSD). The UTT results indicated that WAAM Z2CN19-10 steel exhibited significantly anisotropic in tensile elongation. Relationships between UTT and SS-SPT results were established to determine the tensile properties of WAAM Z2CN19-10 steel via SS-SPTs. Fracture surface analysis revealed that the morphologies of UTT and SPT specimens displayed distinctly different characteristics, while similarities were observed between UTT and SS-SPT specimens.</div></div>","PeriodicalId":56004,"journal":{"name":"Nuclear Materials and Energy","volume":"47 ","pages":"Article 102155"},"PeriodicalIF":2.7,"publicationDate":"2026-06-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"148241469","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":"Experimental evaluation of magnetic shielding effectiveness in strong static magnetic fields","authors":"Th. Wegner,&nbsp;C. von Sehren,&nbsp;T. Przykopp,&nbsp;W7-X Team","doi":"10.1016/j.nme.2026.102147","DOIUrl":"10.1016/j.nme.2026.102147","url":null,"abstract":"<div><div>Magnetic shielding is crucial for the reliable operation of electronic and electromechanical components in environments with strong magnetic fields. In this work, the shielding performance of ferromagnetic materials is experimentally investigated for static magnetic fields in the range of 20 to 150<!--> <!-->mT. Motivated by the extension of the laser blow-off system at the Wendelstein 7-X stellarator, systematic measurements are carried out to examine the influence of material type, thickness and orientation relative to the external magnetic field. Cuboid-shaped enclosures made of pure iron and high-permeability metal with thicknesses between 3<!--> <!-->mm and 6<!--> <!-->mm are studied. Mu-metal provides superior shielding at low field strengths below approximately 70<!--> <!-->mT, while pure iron exhibits better performance at higher fields. Increasing material thickness and employing multiple layers enhance shielding effectiveness across the entire field range. Under optimized conditions, a reduction of the external magnetic field by up to 75% is achieved.</div></div>","PeriodicalId":56004,"journal":{"name":"Nuclear Materials and Energy","volume":"47 ","pages":"Article 102147"},"PeriodicalIF":2.7,"publicationDate":"2026-06-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"148177740","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":"Research on the migration behavior of corrosion products of CLF-1 steel in magnetic fields","authors":"Yuxin Xiao,&nbsp;Yi-Ming Lyu,&nbsp;Ye Li,&nbsp;Ning Liu,&nbsp;Jiejie Li,&nbsp;Shu-Feng Zhang,&nbsp;Shan-Liang Zheng","doi":"10.1016/j.nme.2026.102160","DOIUrl":"10.1016/j.nme.2026.102160","url":null,"abstract":"<div><div>CLF-1 steel, a candidate material for cooling water pipes in fusion reactors, is not only corroded by cooling water producing corrosion products (CPs), but is also exposed to strong magnetic fields during service. Activated corrosion products (ACPs) are formed when CPs are irradiated by neutrons. ACPs are among the most serious sources of radiation risk. Strong magnetic fields in fusion reactors may affect the migration behavior of these ACPs, making the safety assessment of fusion reactors more challenging. The aim of this work is therefore to investigate the migration behavior of the corrosion products of CLF-1 steel in magnetic fields. To obtain the corrosion products, corrosion experiments were performed in a solution of 1 wt% H₂O₂ and 0.1 wt% NaCl for 24 h. Migration experiments were performed on the corrosion products at different magnetic field strengths. The influence of magnetic fields on the migration behavior of corrosion products was experimentally observed for the first time. The XRD analysis reveals that the CPs are mixtures of multiple components. The same migration experiments were further performed for each of the main components of the corrosion products. The results indicate that, in the range of 200–1000 Gs, regarding quantity and migration distance of particles affected by the magnetic fields, Fe₃O₄ is the largest; in the range of 3000–8000 Gs, the quantity and migration distance of the particles affected by the magnetic fields, from highest to lowest, is FeCr₂O₄ &gt; CPs &gt; Fe₂O₃ &gt; Cr₂O₃, and the migration direction is mainly determined by the magnetic field gradient. In order to reveal the physical mechanism behind this phenomenon, the magnetic behaviors of corrosion products and the main components of the corrosion products were analyzed with a vibrating sample magnetometer. Analysis of the magnetization versus applied magnetic field curves indicates that the quantity and migration distance of the migrating particles affected by magnetic fields are positively correlated with their magnetization under the same magnetic field conditions. At 300 K, the magnetic response of the corrosion products exhibits weak ferromagnetism. The initial magnetic susceptibility of the corrosion products is higher than that of Fe₂O₃ and FeCr₂O₄ due to the presence of Fe₃O₄. In this study, the migration of reduced activation steel corrosion products affected by the magnetic fields was observed for the first time. Future work should further focus on the migration behavior of corrosion products in the actual magnetic fields of fusion reactors, which is important for the safety assessment of activated corrosion products in the fusion reactor environments.</div></div>","PeriodicalId":56004,"journal":{"name":"Nuclear Materials and Energy","volume":"47 ","pages":"Article 102160"},"PeriodicalIF":2.8,"publicationDate":"2026-06-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"148539539","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}