Journal of Nuclear Materials最新文献

Effects of temperature and trace elements on the mechanical properties and dissolution-diffusion characteristics of CoCrFeNi in liquid LBE: Atomic insights from molecular dynamics 温度和微量元素对CoCrFeNi在液态LBE中力学性能和溶解扩散特性的影响：来自分子动力学的原子观察

IF 2.8 2区工程技术

Journal of Nuclear Materials Pub Date : 2025-04-29 DOI: 10.1016/j.jnucmat.2025.155861

Wenrui Wang, Weihan Li, Lu Xie, Zijian Jia, Zexin Chen

{"title":"Effects of temperature and trace elements on the mechanical properties and dissolution-diffusion characteristics of CoCrFeNi in liquid LBE: Atomic insights from molecular dynamics","authors":"Wenrui Wang, Weihan Li, Lu Xie, Zijian Jia, Zexin Chen","doi":"10.1016/j.jnucmat.2025.155861","DOIUrl":"10.1016/j.jnucmat.2025.155861","url":null,"abstract":"<div><div>CoCrFeNi high-entropy alloys (HEAs) represent promising structural materials for Generation IV lead-bismuth cooled reactors, and it is crucial to study the effect of the liquid lead-bismuth eutectic (LBE) environment on their mechanical properties and their dissolution process. This study employs molecular dynamics simulations to systematically investigate the effects of temperature and trace elements on the mechanical properties of the HEAs under different environments and the dissolution and diffusion process of the HEAs in liquid LBE. Results demonstrate that elevated temperatures (300–873 K) induce lattice defect proliferation and dislocation activation, leading to substantial reductions in Young’s modulus (23.3 %), yield strength (47.1 %), and ultimate tensile strength (33.3 %) compared to ambient conditions. Enhanced atomic thermal motion at high temperatures accelerates the dissolution of matrix elements (Fe>Cr>Ni>Co) and LBE atom penetration (Pb/Bi), synergistically exacerbating corrosion-induced mechanical deterioration. Microalloying effects reveal that Mo addition enhances the strength and stiffness of CoCrFeNi HEAs, while the addition of Al leads to a decrease in the tensile strength of HEAs, and Mo-Ti co-doping maximizes the strain modulation capability. Diffusion analyses identify Fe atoms as exhibiting the highest degree of diffusion, while the Al atoms exhibit the lowest degree of diffusion in liquid LBE. The addition of the Mo element slows down the infiltration process of liquid LBE, and (CoCrFeNi)<sub>97</sub>Mo<sub>3</sub> HEAs exhibit higher tensile strength in liquid LBE compared to Al and Ti elements. Our research results may provide some references for the application of structural materials in fourth-generation lead-bismuth reactors.</div></div>","PeriodicalId":373,"journal":{"name":"Journal of Nuclear Materials","volume":"613 ","pages":"Article 155861"},"PeriodicalIF":2.8,"publicationDate":"2025-04-29","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143894519","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":2,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

Structure-thermal properties relationship of borosilicate glasses containing MoO3 含MoO3硼硅酸盐玻璃的结构-热性能关系

IF 2.8 2区工程技术

Journal of Nuclear Materials Pub Date : 2025-04-28 DOI: 10.1016/j.jnucmat.2025.155857

Xingquan Zhang , Yifan Xiong , Sijia Yu , Jingyu Yuan , Kui Zheng , Zhu Cui , Yongchang Zhu , Jichuan Huo

{"title":"Structure-thermal properties relationship of borosilicate glasses containing MoO3","authors":"Xingquan Zhang , Yifan Xiong , Sijia Yu , Jingyu Yuan , Kui Zheng , Zhu Cui , Yongchang Zhu , Jichuan Huo","doi":"10.1016/j.jnucmat.2025.155857","DOIUrl":"10.1016/j.jnucmat.2025.155857","url":null,"abstract":"<div><div>The effect of MoO<sub>3</sub> incorporation on structure and thermal properties (e.g., thermal diffusivity, heat capacity, and thermal conductivity) of a borosilicate glass with a composition of 59.76 SiO<sub>2</sub>–14.46B<sub>2</sub>O<sub>3</sub>–2.90 Al<sub>2</sub>O<sub>3</sub>–11.46 Na<sub>2</sub>O-11.42 CaO (mol%) was investigated systematically. MoO<sub>3</sub> incorporation induced phase separation and crystallization of CaMoO<sub>4</sub> and Na<sub>2</sub>MoO<sub>4</sub> in borosilicate glass. CaMoO<sub>4</sub> phases with grain size of about 200 nm in diameter were homogenously dispersed in the glass matrix, while, Na<sub>2</sub>MoO<sub>4</sub> as a second phase formed on the surface. In addition, MoO<sub>3</sub> incorporation resulted in re-polymerization of the glass network. These structural changes have obvious influence on thermal properties. MoO<sub>3</sub> additions up to 6 wt% decreased thermal diffusivity by 7.5 %, heat capacity by 27.8 % and thermal conductivity by 30.2 %. Correlations between the structure, microstructure and thermal properties were proposed. It is speculated that the decrease of thermal conductivity mainly results from the decrease of mean free path of phonons caused by interface scattering. The understanding of the linkages between structure, microstructure, and thermal properties should provide insights for the design of borosilicate glass compositions for vitrification of MoO<sub>3</sub>-rich high-level waste.</div></div>","PeriodicalId":373,"journal":{"name":"Journal of Nuclear Materials","volume":"613 ","pages":"Article 155857"},"PeriodicalIF":2.8,"publicationDate":"2025-04-28","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143891949","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":2,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

Annealing-induced microstructure and mechanical property evolution of helium-irradiated Cr coatings 氦辐照Cr涂层退火组织及力学性能演变

IF 2.8 2区工程技术

Journal of Nuclear Materials Pub Date : 2025-04-24 DOI: 10.1016/j.jnucmat.2025.155854

Qining Zheng , Shuqin Wen , Mingju Chen , Ce Zheng , Guanghai Bai , Jinshan Li , Biao Chen

{"title":"Annealing-induced microstructure and mechanical property evolution of helium-irradiated Cr coatings","authors":"Qining Zheng , Shuqin Wen , Mingju Chen , Ce Zheng , Guanghai Bai , Jinshan Li , Biao Chen","doi":"10.1016/j.jnucmat.2025.155854","DOIUrl":"10.1016/j.jnucmat.2025.155854","url":null,"abstract":"<div><div>Post-irradiation annealing (PIA) is a highly effective approach for investigating the impacts of irradiation temperature. In this work, annealing at 350–800 °C was conducted on helium ion irradiated (300 keV, 6.85 × 10¹⁵ ions/cm²) chromium coatings, and the impact of annealing temperature on irradiation defects and mechanical properties of chromium was investigated. A critical temperature threshold of 700 °C (0.45 <em>T<sub>m</sub></em>) was identified, beyond which helium bubbles exhibited a pronounced transition in coarsening behavior: gradual growth below 700 °C transitioned to rapid coarsening dominated by migration-coalescence mechanisms at higher temperatures. Concurrently, grain boundaries emerged as preferential defect sinks, facilitating bubble nucleation and growth. The swelling rate of the coating is primarily governed by bubble size and increases with temperature. Dislocation loops displayed coevolution with helium bubbles, mirroring temperature-dependent growth trends. Irradiation hardening primarily originated from dislocation pinning by both loops and bubbles. Depth-resolved nanoindentation analysis via the Nix-Gao model quantified intrinsic hardness gradients, revealing deviations from theoretical predictions attributed to unaccounted defects below 2 nm and grain-coarsening effects.</div></div>","PeriodicalId":373,"journal":{"name":"Journal of Nuclear Materials","volume":"613 ","pages":"Article 155854"},"PeriodicalIF":2.8,"publicationDate":"2025-04-24","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143894606","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":2,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

Synergies between H and He in advanced F/M steels for fusion reactors and spallation target 核聚变反应堆用先进F/M钢和散裂靶中H和He的协同作用

IF 2.8 2区工程技术

Journal of Nuclear Materials Pub Date : 2025-04-23 DOI: 10.1016/j.jnucmat.2025.155849

Yiqihui Lan , Peng Jin , Minghuan Cui , Jing Li , Dongsheng Li , Yushan Yang , Zeyuan Chen , Yuhan Zhai , Wenhui Zhang , Yucheng Feng , Liangting Sun , Tielong Shen , Zhiguang Wang

{"title":"Synergies between H and He in advanced F/M steels for fusion reactors and spallation target","authors":"Yiqihui Lan , Peng Jin , Minghuan Cui , Jing Li , Dongsheng Li , Yushan Yang , Zeyuan Chen , Yuhan Zhai , Wenhui Zhang , Yucheng Feng , Liangting Sun , Tielong Shen , Zhiguang Wang","doi":"10.1016/j.jnucmat.2025.155849","DOIUrl":"10.1016/j.jnucmat.2025.155849","url":null,"abstract":"<div><div>A comparative study was conducted to investigate the synergistic effects of H and He on the microstructure evolution, irradiation swelling, and hardening of two candidate ferritic/martensitic steels (SIMP and T91) for fusion reactors and spallation target. Ion irradiation experiments were carried out using mixed H<sub>2</sub><sup>+</sup>/He<sup>2+</sup> beams with doses of 4 × 10<sup>17</sup> H<sub>2</sub><sup>+</sup>/cm<sup>2</sup> and 1 × 10<sup>17</sup> He<sup>2+</sup>/cm<sup>2</sup>, at irradiation temperatures of RT, 300 °C, and 500 °C. The results reveal that at low temperatures, H and He interacted to form stable H<img>He-vacancy clusters, promoting uniform cavity nucleation. As the temperature increases, the cavities were more heterogeneously distributed, particularly at grain boundaries (GBs) and dislocations. Notably, SIMP exhibited superior resistance to irradiation swelling compared to T91, likely due to its finer microstructure and higher silicon content. The study also shows that the hardening of SIMP was more pronounced than T91, correlating with larger size and higher density of dislocation loops (DLs). The irradiation hardening decreased with increasing temperature. These findings reveal a temperature-sensitive synergy between H and He, emphasizing its significance for material design in fusion and spallation environments.</div></div>","PeriodicalId":373,"journal":{"name":"Journal of Nuclear Materials","volume":"613 ","pages":"Article 155849"},"PeriodicalIF":2.8,"publicationDate":"2025-04-23","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143894605","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":2,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

Swelling and Fission Gas Release of U-10Mo and U-17Mo Following Neutron Irradiation at 250 – 500°C 250 ~ 500℃中子辐照后U-10Mo和U-17Mo的膨胀和裂变气体释放

IF 2.8 2区工程技术

Journal of Nuclear Materials Pub Date : 2025-04-23 DOI: 10.1016/j.jnucmat.2025.155851

Peter Doyle , Jacob Gorton , Kara Godsey , Annabelle Le Coq , Jason Harp , Matthew Jones , Stephanie Curlin , Andrew Nelson

{"title":"Swelling and Fission Gas Release of U-10Mo and U-17Mo Following Neutron Irradiation at 250 – 500°C","authors":"Peter Doyle , Jacob Gorton , Kara Godsey , Annabelle Le Coq , Jason Harp , Matthew Jones , Stephanie Curlin , Andrew Nelson","doi":"10.1016/j.jnucmat.2025.155851","DOIUrl":"10.1016/j.jnucmat.2025.155851","url":null,"abstract":"<div><div>The performance of metallic fuel alloys, U-10Mo and U-17Mo, was examined using the MiniFuel test system in the High Flux Isotope Reactor. Approximately 0.8 mm thick disks were irradiated at target temperatures of 250°C, 350°C, 450°C, and 500°C up to three different fission densities, culminating at a maximum fission density of 6.8×10<sup>20</sup> cm<sup>−3</sup>. Fission rates decayed from 3 – 6 × 10<sup>13</sup> cm<sup>−3</sup>s<sup>−1</sup> to 2 – 4 × 10<sup>13</sup> cm<sup>−3</sup>s<sup>−1</sup> over the course of the longest, eight cycle, irradiation as the <sup>235</sup>U was consumed and the <sup>239</sup>Pu concentration accumulated. Actual irradiation temperature on the last day of irradiation was measured via dilatometry using the SiC passive thermometry recovered from the MiniFuel subcapsules and compared favorably with the thermal calculations using as-built geometry and test conditions. Furthermore, average simulated temperatures were within 50°C of the target temperatures, except for the 500°C irradiation, for which the temperature variation was 62°C, 32°C, and 90°C in the in two, four, and eight cycle irradiations, respectively. Fission gas release (FGR) measurements showed no release above recoil for any U-17Mo fuels or for the U-10Mo fuel irradiated at 250°C. Significant (40%–80%) FGR was found for the medium- to highest-burnup U-10Mo samples irradiated at target temperatures 350°C–500°C. Significant FGR correlated with sample thickness swelling, which was as high as 13%–35% for high-release samples and below 7% for all other (low–gas release) samples.</div></div>","PeriodicalId":373,"journal":{"name":"Journal of Nuclear Materials","volume":"612 ","pages":"Article 155851"},"PeriodicalIF":2.8,"publicationDate":"2025-04-23","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143879143","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":2,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

Effect of neighbouring rods in cladding deformation and rupture opening size during loss of coolant accidents 失冷事故中相邻棒对包层变形和破裂口尺寸的影响

IF 2.8 2区工程技术

Journal of Nuclear Materials Pub Date : 2025-04-22 DOI: 10.1016/j.jnucmat.2025.155848

Cristina Dominguez, Tatiana Taurines, Georges Repetto

{"title":"Effect of neighbouring rods in cladding deformation and rupture opening size during loss of coolant accidents","authors":"Cristina Dominguez, Tatiana Taurines, Georges Repetto","doi":"10.1016/j.jnucmat.2025.155848","DOIUrl":"10.1016/j.jnucmat.2025.155848","url":null,"abstract":"<div><div>The COCAGNE experiments aim to study the deformation and burst of fuel cladding under Loss-Of-Coolant-Accident (LOCA) conditions in a “multi-rod” configuration. This configuration enables the study of cladding ballooning in situations of contact/blockage between peripheral rods, burst conditions with various azimuthal temperature gradients, or after contact. The main objective is to measure online the three-dimensional mechanical behaviour of pressurised rods surrounded by structures simulating four neighbouring fuel rods, under a geometrically and thermally representative environment.</div><div>Twenty-three ramp tests were conducted on single-sided or double-sided pre-oxidised Zircaloy-4 claddings at heating rates between 1 and 10 °C/s and pressures from 2 to 10 MPa. The effect of temperature differences between the test rod and the guards simulating surrounding rods was also investigated.</div><div>The presence of the neighbouring rods affects the size and shape of balloons and burst openings. In “multi-rod” tests, deformation is constrained by the guards resulting in maximal strains up to 50 % lower compared to single-rod tests. Additionally, the formed balloon adapts to the available space between the guards leading to square shapes. Moreover, cladding thermal profiles are relatively flat in single-rod tests, but they become uneven in the presence of guards, leading to greater axial temperature gradients and shorter balloons in multi-rod tests. Nevertheless, under certain conditions, ballooning can extend axially producing ballons nearly 100 mm long.</div><div>Additionally, an internal pre-oxide layer significantly reduces burst strain by up to three times and opening dimensions by over 75 %.</div></div>","PeriodicalId":373,"journal":{"name":"Journal of Nuclear Materials","volume":"612 ","pages":"Article 155848"},"PeriodicalIF":2.8,"publicationDate":"2025-04-22","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143877295","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":2,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

Surface damage evolution during helium plasma irradiation of W-Y2O3 composite materials in different grain orientations 不同晶粒取向W-Y2O3复合材料在氦等离子体辐照下的表面损伤演变

IF 2.8 2区工程技术

Journal of Nuclear Materials Pub Date : 2025-04-21 DOI: 10.1016/j.jnucmat.2025.155840

Zhen Liu , Guo-Qing Wei , Wei Ye , Gang Yao , Yi-Fan Zhang , Lai-Ma Luo , Yu-Cheng Wu

{"title":"Surface damage evolution during helium plasma irradiation of W-Y2O3 composite materials in different grain orientations","authors":"Zhen Liu , Guo-Qing Wei , Wei Ye , Gang Yao , Yi-Fan Zhang , Lai-Ma Luo , Yu-Cheng Wu","doi":"10.1016/j.jnucmat.2025.155840","DOIUrl":"10.1016/j.jnucmat.2025.155840","url":null,"abstract":"<div><div>Tungsten (W) is the preferred material for first walls. In this study, a linear plasma device was employed to irradiate two surfaces of a W-Y<sub>2</sub>O<sub>3</sub> (WYO) composite rod with low-energy helium plasma, with one surface perpendicular and the other parallel to the rod’s axial direction. The evolution of surface damage on WYO due to plasma irradiation was characterized by scanning electron microscopy, while the effect of grain orientation on irradiation damage resistance was analyzed through electron backscatter diffraction and white light interferometry. Results reveal that under varying irradiation doses, the surface of polycrystalline W exhibits three distinct morphologies: wavy, pyramidal, and step-like structures. A comparison of the two surfaces shows that the extent of irradiation damage is highly dependent on grain orientation. Specifically, grains oriented along the [101] direction demonstrate the strongest resistance to irradiation damage, whereas those with a [111] orientation exhibit the weakest resistance. Further analysis suggests that differences in atomic binding energies on various crystal planes, along with the channeling effect of adjacent planes, may significantly influence the observed surface morphologies.</div></div>","PeriodicalId":373,"journal":{"name":"Journal of Nuclear Materials","volume":"612 ","pages":"Article 155840"},"PeriodicalIF":2.8,"publicationDate":"2025-04-21","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143873903","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":2,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

Damage behavior of He-irradiated sintered SiC at high temperatures he辐照烧结SiC的高温损伤行为

IF 2.8 2区工程技术

Journal of Nuclear Materials Pub Date : 2025-04-21 DOI: 10.1016/j.jnucmat.2025.155839

Jintao Zhang , Zhongzheng Wu , Jiale Huang , Jun Li , Haiyuan Wei , Tongmin Zhang , Tomas Polcar , Nabil Daghbouj , Bingsheng Li

{"title":"Damage behavior of He-irradiated sintered SiC at high temperatures","authors":"Jintao Zhang , Zhongzheng Wu , Jiale Huang , Jun Li , Haiyuan Wei , Tongmin Zhang , Tomas Polcar , Nabil Daghbouj , Bingsheng Li","doi":"10.1016/j.jnucmat.2025.155839","DOIUrl":"10.1016/j.jnucmat.2025.155839","url":null,"abstract":"<div><div>Understanding the effects of high-temperature helium (He) irradiation on the damage behavior of sintered silicon carbide (SiC) is crucial for assessing the material's stability in advanced nuclear reactors. In this study, we investigate the impact of 230 keV He ions on SiC at temperatures of 800 °C and 1000 °C, utilizing three different irradiation fluences: 2 × 10<sup>16</sup>/cm<sup>2</sup>, 4 × 10<sup>16</sup>/cm<sup>2</sup>, and 1.6 × 10<sup>17</sup>/cm<sup>2</sup>. Raman spectroscopy and transmission electron microscopy were employed to analyze various damage features, including irradiation-induced lattice strain, platelet formation, dislocation loops, and helium bubbles. Our findings indicate that over-pressurized platelets predominantly formed on the (0001) plane, with a limited number of dislocation loops detected nearby. In contrast, numerous black spot defects were observed near grain boundaries, where platelets were absent. This variation in defect distribution underscores the unique damage behavior associated with high-temperature He irradiation. The insights gained from this study are essential for understanding the structural changes and integrity of SiC materials under conditions relevant to nuclear reactor applications.</div></div>","PeriodicalId":373,"journal":{"name":"Journal of Nuclear Materials","volume":"612 ","pages":"Article 155839"},"PeriodicalIF":2.8,"publicationDate":"2025-04-21","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143860188","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":2,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

Radiation response of inconel-Cu multimetallic layered composites: Role of alloy chemistry inconel-Cu多层复合材料的辐射响应：合金化学的作用

IF 2.8 2区工程技术

Journal of Nuclear Materials Pub Date : 2025-04-19 DOI: 10.1016/j.jnucmat.2025.155837

Rajesh Ramesh , Daniel Schwen , Sara Neshani , Keivan Davami , Kasra Momeni

{"title":"Radiation response of inconel-Cu multimetallic layered composites: Role of alloy chemistry","authors":"Rajesh Ramesh , Daniel Schwen , Sara Neshani , Keivan Davami , Kasra Momeni","doi":"10.1016/j.jnucmat.2025.155837","DOIUrl":"10.1016/j.jnucmat.2025.155837","url":null,"abstract":"<div><div>The reliability and longevity of fusion reactors' current drive systems are essential for sustained operation under high neutron fluence, requiring materials that maintain high strength and conductivity while resisting high irradiation doses. Here, we investigate the stability and structural integrity of under irradiation using Molecular Dynamics simulations. The mechanochemistry of the constituent elements and their role in the radiation resistance is investigated by considering five variants of Inconel, i.e., Incoloy 800H (Ni<sub>32</sub>Cr<sub>21</sub>Fe<sub>47</sub>), Inconel 625 (Ni<sub>72</sub>Cr<sub>23</sub>Fe<sub>5</sub>), Inconel 690 (Ni<sub>58</sub>Cr<sub>31</sub>Fe<sub>11</sub>), Inconel 718 (Ni<sub>55</sub>Cr<sub>21</sub>Fe<sub>24</sub>), and Inconel X-750 (Ni<sub>77</sub>Cr<sub>14</sub>Fe<sub>9</sub>). We revealed three linear, exponential, and plateau stages in the relationship between Frenkel Pair (FP) defect density and radiation damage. Furthermore, our results indicate a high Fe concentration reduces diffusivity between the two metallic layers, while a high concentration of Cr, with its low migration energy barrier, increases diffusivity. Among considered composites, the Incoloy 800H (Ni<sub>32</sub>Cr<sub>21</sub>Fe<sub>47</sub>) shows the highest radiation resistance. FP defect clustering planes are revealed in both Inconel and Cu, while the formation of Stacking Faults (SF) and Lomer-Cottrell (LC) locks are also observed on the Inconel side; we revealed that the shear stress determines the orientation of the FP defect clustering planes.</div></div>","PeriodicalId":373,"journal":{"name":"Journal of Nuclear Materials","volume":"612 ","pages":"Article 155837"},"PeriodicalIF":2.8,"publicationDate":"2025-04-19","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143860187","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":2,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

Temperature effect on cavity evolution by triple-beam irradiation 三束辐照对腔体演化的温度效应

IF 2.8 2区工程技术

Journal of Nuclear Materials Pub Date : 2025-04-19 DOI: 10.1016/j.jnucmat.2025.155838

Junjie Cao , Liping Guo , Yiheng Chen , Wenbin Lin , Rui Yan , Zixiao Wang , Yunxiang Long

{"title":"Temperature effect on cavity evolution by triple-beam irradiation","authors":"Junjie Cao , Liping Guo , Yiheng Chen , Wenbin Lin , Rui Yan , Zixiao Wang , Yunxiang Long","doi":"10.1016/j.jnucmat.2025.155838","DOIUrl":"10.1016/j.jnucmat.2025.155838","url":null,"abstract":"<div><div>To understand the synergistic effects of irradiation damage and transmuted helium and hydrogen in reduced-activation ferritic/martensitic (RAFM) steels irradiated by fusion neutrons, China low-activation martensitic (CLAM) steel was subjected to Fe+H+He triple-beam simultaneous irradiation under controlled conditions. The experiments were conducted at three temperatures of 350 °C, 450 °C and 550 °C, with irradiation doses of 11 dpa, 22 dpa and 33 dpa applied at each temperature, maintaining the He ratio of 11 appm/dpa and H ratio of 44 appm/dpa. At 350 °C, the increase in swelling was attributed to an increase in the number density of helium bubbles. At 450 °C, the helium bubble density saturated between 11 and 22 dpa, transitioning to cavities growing under bias-driven mechanisms, ultimately resulting in the formation of the largest voids. At 550 °C, the high temperature suppressed the number density of cavities, while thermal emission limited the void growth rate. With increasing doses, the size distribution gradually transitioned from unimodal to multimodal due to helium bubble-to-void transformation and the influence of size on growth rates, a phenomenon more pronounced at higher temperatures. At the three temperatures of 350 °C, 450 °C and 550 °C, CLAM steel experienced irradiation hardening, minimal changes, and irradiation softening, respectively, with hardness variations closely related to irradiation swelling. The results revealed the evolution of irradiation-induced defects and swelling under the synergistic effect among irradiation damage, helium and hydrogen.</div></div>","PeriodicalId":373,"journal":{"name":"Journal of Nuclear Materials","volume":"612 ","pages":"Article 155838"},"PeriodicalIF":2.8,"publicationDate":"2025-04-19","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143864790","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":2,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0