Journal of Nuclear Materials最新文献_第2页

On a physics-based model of grain-boundary bubbles overpressurisation and its effects on fuel fragmentation 基于物理模型的颗粒边界气泡超压及其对燃料破碎的影响

IF 3.2 2区工程技术

Journal of Nuclear Materials Pub Date : 2025-09-15 DOI: 10.1016/j.jnucmat.2025.156116

Elisa Cappellari , Davide Pizzocri , Giovanni Zullo , Giovanni Nicodemo , Paul Van Uffelen , Arndt Schubert , Sophie Deanesi , Lelio Luzzi

{"title":"On a physics-based model of grain-boundary bubbles overpressurisation and its effects on fuel fragmentation","authors":"Elisa Cappellari , Davide Pizzocri , Giovanni Zullo , Giovanni Nicodemo , Paul Van Uffelen , Arndt Schubert , Sophie Deanesi , Lelio Luzzi","doi":"10.1016/j.jnucmat.2025.156116","DOIUrl":"10.1016/j.jnucmat.2025.156116","url":null,"abstract":"<div><div>Overpressurisation of gas-filled bubbles and pores is considered the main driver of oxide fuel fragmentation and fission gas release into the rod free volume of irradiated fuel during transients. In this framework, advanced modelling of fission gas behaviour is crucial to enhance the predictive capabilities of fuel performance codes. This study develops a physics-based model for fission gas release from grain boundaries in UO<sub>2</sub> fuel and implements it into SCIANTIX, an open-source code developed at Politecnico di Milano to simulate fission gas behaviour in nuclear fuels. The model first describes gas release through continuous bubble networks at the grain face, exploiting data from irradiated fuel. It then focuses on gas release from damaged grain boundaries, applying fracture mechanics to predict micro-cracking induced by bubble overpressurisation. Finite elements simulations are performed using ABAQUS software, in order to assess stress intensification as a function of bubble density, shape, and size. The model is assessed against three separate-effect experiment datasets, including annealing tests and grain-face observations via scanning electron microscopy, demonstrating promising predictive capabilities for gaseous swelling and fission gas release. This work provides a valuable tool for improving fission gas behaviour modelling through a physics-based approach and lays the groundwork for future extensions to the high burn-up structure, offering a framework for a more comprehensive description of fuel fragmentation.</div></div>","PeriodicalId":373,"journal":{"name":"Journal of Nuclear Materials","volume":"617 ","pages":"Article 156116"},"PeriodicalIF":3.2,"publicationDate":"2025-09-15","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145105138","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

Irradiation-induced grain boundary strengthening/embrittlement in bcc refractory high entropy alloy TiZrHfNbTa 辐照诱导bcc难熔高熵合金TiZrHfNbTa晶界强化/脆化

IF 3.2 2区工程技术

Journal of Nuclear Materials Pub Date : 2025-09-13 DOI: 10.1016/j.jnucmat.2025.156163

Chuanlong Xu, Peidong Li, Xiaobao Tian, Wentao Jiang, Qingyuan Wang, Haidong Fan

{"title":"Irradiation-induced grain boundary strengthening/embrittlement in bcc refractory high entropy alloy TiZrHfNbTa","authors":"Chuanlong Xu, Peidong Li, Xiaobao Tian, Wentao Jiang, Qingyuan Wang, Haidong Fan","doi":"10.1016/j.jnucmat.2025.156163","DOIUrl":"10.1016/j.jnucmat.2025.156163","url":null,"abstract":"<div><div>High entropy alloys (HEA) exhibit good mechanical performances and have potential applications in nuclear reactors. In this work, molecular dynamic (MD) simulation was performed to investigate the irradiation-induced grain boundary (GB) strengthening/embrittlement in refractory high entropy alloy (RHEA) TiZrHfNbTa and pure Ta. The distinct responses of low-angle symmetric tilt GB under tensile deformation were simulated. It was found that the irradiation-induced point defects have different influences on the GB fracture. Both the interstitials and vacancies can lead to GB embrittlement in pure Ta. For RHEA, only vacancies can lead to GB embrittlement while the interstitials can strengthen the GB conversely. By measuring the strengthening/embrittlement energy of interstitial and vacancy at GB, the different effects of point defects on GB fracture in pure Ta and RHEA were explained. This work confirmed that the TiZrHfNbTa RHEA shows better irradiation resistance than pure Ta in the perspective of GB behaviors, and provides new insights into understanding the GB regulation mechanism on mechanical properties, which are important for improving the irradiation effects in RHEA.</div></div>","PeriodicalId":373,"journal":{"name":"Journal of Nuclear Materials","volume":"617 ","pages":"Article 156163"},"PeriodicalIF":3.2,"publicationDate":"2025-09-13","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145105139","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

Molecular-dynamics study of diffusional creep in uranium mononitride 单氮化铀扩散蠕变的分子动力学研究

IF 3.2 2区工程技术

Journal of Nuclear Materials Pub Date : 2025-09-12 DOI: 10.1016/j.jnucmat.2025.156153

Mohamed AbdulHameed , Benjamin Beeler , Conor O.T. Galvin , Michael W.D. Cooper , Nermeen Elamrawy , Antoine Claisse

{"title":"Molecular-dynamics study of diffusional creep in uranium mononitride","authors":"Mohamed AbdulHameed , Benjamin Beeler , Conor O.T. Galvin , Michael W.D. Cooper , Nermeen Elamrawy , Antoine Claisse","doi":"10.1016/j.jnucmat.2025.156153","DOIUrl":"10.1016/j.jnucmat.2025.156153","url":null,"abstract":"<div><div>Uranium mononitride (UN) is a promising advanced nuclear fuel due to its high thermal conductivity and high fissile density. Yet, many aspects of its mechanical behavior and microstructural features are currently unknown. In this paper, molecular dynamics (MD) simulations are used to study UN's diffusional creep. Nanometer-sized polycrystals are used to simulate diffusional creep and to calculate an effective GB width. It is found that Nabarro-Herring creep is not dominant in the temperature range of 1700–2000 K and that the dominant diffusional creep mechanism is Coble creep with an activation energy of 2.28 ± 0.09 eV. A method is proposed to calculate the diffusional GB width and its temperature dependence in polycrystals. The effective GB width of UN is calculated as 2.69 ± 0.08 nm. This value fits very well with the prefactor of the phenomenological Coble creep formula. It is demonstrated that the most comprehensive thermal creep model for UN can be represented as the combination of our Coble creep model and the dislocation creep model proposed by Hayes et al.</div></div>","PeriodicalId":373,"journal":{"name":"Journal of Nuclear Materials","volume":"617 ","pages":"Article 156153"},"PeriodicalIF":3.2,"publicationDate":"2025-09-12","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145105201","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 intra- and intergranular hydride precipitation on phonon thermal transport behavior of zirconium: A molecular dynamics study 晶内和晶间氢化物沉淀对锆声子热输运行为的影响：分子动力学研究

IF 3.2 2区工程技术

Journal of Nuclear Materials Pub Date : 2025-09-12 DOI: 10.1016/j.jnucmat.2025.156162

Sanjay Patil, Avinash Parashar

{"title":"Effect of intra- and intergranular hydride precipitation on phonon thermal transport behavior of zirconium: A molecular dynamics study","authors":"Sanjay Patil, Avinash Parashar","doi":"10.1016/j.jnucmat.2025.156162","DOIUrl":"10.1016/j.jnucmat.2025.156162","url":null,"abstract":"<div><div>Hydride precipitation significantly influences the thermal properties of zirconium (Zr)-based components. In this study, non-equilibrium molecular dynamics simulations in conjunction with the Müller-Plathe algorithm were conducted to investigate the effects of hydride precipitates on thermal transport behaviour in Zr. The investigation addresses both intragranular and intergranular hydride precipitation, utilizing single-crystal and bicrystal Zr configurations, respectively. The phonon transport properties were characterized by temperature and kinetic energy profiles, Kapitza resistance, interfacial thermal conductance, partial density of states, and phonon participation ratio (PPR). The simulation results conclude that hydride precipitation acts as a phonon scattering center, impeding heat transport due to the mismatch in vibrational modes at the Zr-hydride interface. These effects were more pronounced at the high-energy grain boundary and with an increasing concentration of hydrogen in the hydride phases. Among the different hydride phases (γ, δ, and ε), the ε-hydride demonstrated the highest vibrational localization mode, as evidenced by its lower PPR values. The present study provides atomistic insights into phonon transport in Zr with hydride precipitation, which has important implications for improving thermal management in zirconium-based systems.</div></div>","PeriodicalId":373,"journal":{"name":"Journal of Nuclear Materials","volume":"617 ","pages":"Article 156162"},"PeriodicalIF":3.2,"publicationDate":"2025-09-12","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145105196","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}

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Reduction of the temperature threshold for tungsten fuzz growth by helium pre-irradiation 氦预辐照降低钨毛生长的温度阈值

IF 3.2 2区工程技术

Journal of Nuclear Materials Pub Date : 2025-09-10 DOI: 10.1016/j.jnucmat.2025.156134

Quan Shi , Shin Kajita , Noriyasu Ohno

引用次数: 0

Elemental gradient potential trap strategy for enhancing corrosion resistance of SiC in oxygenated and oxygen-free lead-bismuth corrosion 元素梯度电位阱策略提高SiC在含氧和无氧铅铋腐蚀中的耐蚀性

IF 3.2 2区工程技术

Journal of Nuclear Materials Pub Date : 2025-09-10 DOI: 10.1016/j.jnucmat.2025.156160

Jun Hui , Jiapeng Chen , Min Liu , Shuo Wang , Biao Wang

{"title":"Elemental gradient potential trap strategy for enhancing corrosion resistance of SiC in oxygenated and oxygen-free lead-bismuth corrosion","authors":"Jun Hui , Jiapeng Chen , Min Liu , Shuo Wang , Biao Wang","doi":"10.1016/j.jnucmat.2025.156160","DOIUrl":"10.1016/j.jnucmat.2025.156160","url":null,"abstract":"<div><div>SiC is a promising candidate for producing corrosion-resistant lead–bismuth cladding material for application in lead-cooled fast reactors because of its excellent properties, including high resistance to oxidation and thermal shock, high thermal conductivity, and low thermal expansion in flowing lead–bismuth material. The present study revealed the following. First, the binding behavior of Pb/Bi material on its free surface is mainly influenced by the shell energy; in the bulk, the core energy plays a larger role. Second, at the free surface of SiC, Si atoms partially lose their coordination and accumulate an electron energy of approximately 1.3 eV, leading to a 0.74 % decrease in the length of the Si–C bond, which enhances the local binding strength. By contrast, exposure of the C layer results in a loss of approximately 0.5 eV in the electron energy, which causes a 4.81 % contraction of the length of the Si–C bond. The charge depletion in the Si layer and bond contraction in the C layer contribute synergistically to corrosion resistance. Third, a gradient effect exists between the free surface and the bulk; surface elements tend to repel Pb/Bi, whereas bulk elements can either attract or repel Pb/Bi. Gradient doping at the free surface and in the bulk regions reduces Pb/Bi adsorption on the surface and modulates the Pb/Bi binding energy in the bulk, improving the overall corrosion resistance of SiC. This study provides essential theoretical support for the application of SiC as a cladding material in generation IV lead-cooled fast reactors. The proposed elemental gradient potential trapping (EGPT) strategy enhances the corrosion and irradiation resistance of SiC, thereby improving its overall performance in high-temperature environments where both irradiation and corrosion occur.</div></div>","PeriodicalId":373,"journal":{"name":"Journal of Nuclear Materials","volume":"617 ","pages":"Article 156160"},"PeriodicalIF":3.2,"publicationDate":"2025-09-10","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145045198","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

Effects of Ni on evolution of interstitials and dislocation loops under uniaxial tensile stress in Fe-Ni system Ni对Fe-Ni体系中单轴拉伸应力下间隙和位错环演变的影响

IF 3.2 2区工程技术

Journal of Nuclear Materials Pub Date : 2025-09-09 DOI: 10.1016/j.jnucmat.2025.156159

Shubin Li , Miaosen Yu , Wenxue Ma , Shenlu Yang , Luyao Cheng , Jinfu Li , Liang Chen , Ning Gao , Lingti Kong

{"title":"Effects of Ni on evolution of interstitials and dislocation loops under uniaxial tensile stress in Fe-Ni system","authors":"Shubin Li , Miaosen Yu , Wenxue Ma , Shenlu Yang , Luyao Cheng , Jinfu Li , Liang Chen , Ning Gao , Lingti Kong","doi":"10.1016/j.jnucmat.2025.156159","DOIUrl":"10.1016/j.jnucmat.2025.156159","url":null,"abstract":"<div><div>To understand the state of dislocation loops in iron (Fe)-based alloys under the application of external stress is important and necessary for elucidating their stress-induced preferential nucleation (SIPN), in which the regular arrangement of dislocation loops has been considered to play a key role. Different from previous studies, in this work, the coupled effects of Ni alloying and external stress on energy and kinetic evolution of the 1/2 < 111> loops in an Fe-Ni alloy were extensively studied through molecular dynamics (MD) simulations. The results indicate a suppression of such coupled effect on anisotropic distribution of loops formed after cascades. Further energy calculations imply that, compared to pure α-Fe, the normalized formation energy difference between dislocation loops with Burgers vector along the tensile and other directions is suppressed by Ni alloying. Similar trend is also observed in binding energy difference for an interstitial to bind with these loops. These results suggest that the preferential nucleation of loops can be suppressed by alloying atoms. Furthermore, from the viewpoint of energy barrier, more possible diffusion paths are explored under the coupled effect, revealing more possible rotations of 〈110〉 dumbbells and related 3D diffusion. The present work reveals that the effect of alloying elements in Fe-based alloy should be considered in employing the SIPN model to elucidate irradiation behavior of steels in nuclear reactors.</div></div>","PeriodicalId":373,"journal":{"name":"Journal of Nuclear Materials","volume":"617 ","pages":"Article 156159"},"PeriodicalIF":3.2,"publicationDate":"2025-09-09","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145045196","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

Research of tungsten-doped diamond: First-principles studies 掺钨金刚石的第一性原理研究

IF 3.2 2区工程技术

Journal of Nuclear Materials Pub Date : 2025-09-08 DOI: 10.1016/j.jnucmat.2025.156158

Hongfei Sha , Qijun Wang , Jinglin Huang , Xiang Sun , Gai Wu , Yansong Liu , Wei Shen

{"title":"Research of tungsten-doped diamond: First-principles studies","authors":"Hongfei Sha , Qijun Wang , Jinglin Huang , Xiang Sun , Gai Wu , Yansong Liu , Wei Shen","doi":"10.1016/j.jnucmat.2025.156158","DOIUrl":"10.1016/j.jnucmat.2025.156158","url":null,"abstract":"<div><div>Tungsten-doped high-density carbon (W-doped HDC) is a critical target material in nuclear fusion experiments. However, the microscopic structure of W-doped HDC remains insufficiently explored. Given that the diamond phase is a key component of HDC, the density functional theory (DFT) has been employed in this work to investigate the behavior of tungsten doping in diamond, providing insights into W incorporation in HDC. The key properties of tungsten in diamond, such as the formation energy in the bulk phase, the adsorption energy on the surface, the influence of nitrogen and oxygen elements on surface adsorption, the migration energy on the surface, and the formation energy in different carbon layers, are calculated. The significant atomic radius difference between tungsten and carbon causes substantial lattice mismatch, leading to high formation energy for tungsten doping in diamond bulk phase, which indicates doping difficulty. Additionally, the effect of carbon vacancies on tungsten doping is explored, and the results indicate that the suitable carbon vacancies can significantly reduce the formation energy, thus promoting tungsten doping in diamond.</div></div>","PeriodicalId":373,"journal":{"name":"Journal of Nuclear Materials","volume":"617 ","pages":"Article 156158"},"PeriodicalIF":3.2,"publicationDate":"2025-09-08","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145045200","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

Interaction of Cs and Sr with C–A–S–H and Carbonated C–A–S–H phases: Experimental study and thermodynamic modeling Cs和Sr与C-A-S-H和碳化C-A-S-H相的相互作用：实验研究和热力学模型

IF 3.2 2区工程技术

Journal of Nuclear Materials Pub Date : 2025-09-08 DOI: 10.1016/j.jnucmat.2025.156156

Sayuri Tomita , Kazuo Yamada , Go Igarashi , Yoshifumi Hosokawa , Ippei Maruyama

{"title":"Interaction of Cs and Sr with C–A–S–H and Carbonated C–A–S–H phases: Experimental study and thermodynamic modeling","authors":"Sayuri Tomita , Kazuo Yamada , Go Igarashi , Yoshifumi Hosokawa , Ippei Maruyama","doi":"10.1016/j.jnucmat.2025.156156","DOIUrl":"10.1016/j.jnucmat.2025.156156","url":null,"abstract":"<div><div>Understanding the retention mechanisms of radioactive cesium and strontium in cementitious materials is crucial for predicting contamination spread and designing effective barriers. This study investigates the adsorption behavior of Cs and Sr on calcium aluminosilicate hydrate (C–A–S–H) and its carbonated forms, revealing distinct retention mechanisms in these phases.</div><div>We found that in C–A–S–H, Cs and Sr adsorption occurs primarily through ion exchange with interlayer cations, with adsorption capacity increasing at lower Ca/Si ratios. In contrast, carbonation transforms C–A–S–H into CaCO<sub>3</sub> and an aluminosilicate gel with a three-dimensional network structure, significantly enhancing Cs and Sr retention through multiple mechanisms: ion exchange within the aluminosilicate framework, incorporation into the gel structure, and Sr substitution for Ca in carbonates.</div><div>Based on these findings, we developed a comprehensive thermodynamic model that successfully reproduces Cs and Sr adsorption behavior across various conditions by explicitly incorporating the aluminosilicate gel phase—a critical component overlooked in conventional models. This model provides a valuable tool for predicting radionuclide behavior in aging concrete barriers and supports the development of more effective containment strategies for radioactive waste.</div></div>","PeriodicalId":373,"journal":{"name":"Journal of Nuclear Materials","volume":"617 ","pages":"Article 156156"},"PeriodicalIF":3.2,"publicationDate":"2025-09-08","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145108675","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

Defect evolution in Fe using in-situ Fe-H-He triple-beam simultaneous irradiation under two orders of magnitude of dose rates with constant H/dpa and He/dpa ratios 在恒定H/dpa和He/dpa比值下，原位Fe-H-He三束同步辐照Fe的缺陷演化

IF 3.2 2区工程技术

Journal of Nuclear Materials Pub Date : 2025-09-08 DOI: 10.1016/j.jnucmat.2025.156157

Ziqi Cao , Yifan Ding , Qinghong Zhong , Mengjie Wu , Guang Ran

{"title":"Defect evolution in Fe using in-situ Fe-H-He triple-beam simultaneous irradiation under two orders of magnitude of dose rates with constant H/dpa and He/dpa ratios","authors":"Ziqi Cao , Yifan Ding , Qinghong Zhong , Mengjie Wu , Guang Ran","doi":"10.1016/j.jnucmat.2025.156157","DOIUrl":"10.1016/j.jnucmat.2025.156157","url":null,"abstract":"<div><div>The effectiveness and reliability of ion irradiation with high damage rates and without hydrogen and helium production to simulate neutron irradiation with low damage rates and with hydrogen and helium from nuclear reactions in the study of nuclear material irradiation damage has been questioned for a long time. In this work, the evolution of dislocation loops and helium bubbles in pure Fe was examined under Fe-H-He triple-beam simultaneous irradiation with two orders of magnitude (10<sup>−3</sup> dpa/s-10<sup>−5</sup> dpa/s) changes in the irradiation damage rate while maintaining constant hydrogen & helium-dose ratios (10 appm He/dpa and 45 appm H/dpa). The in-situ TEM analysis revealed the effect of dose rate on defect nucleation/growth: higher dose rates promote high density nucleation of dislocation loops and bubbles, but inhibit their growth. Lower dose rates, on the other hand, favour continuous growth of defects, leading to larger sizes and increased expansion rates. Based on experimental data, a comprehensive prediction equation for swelling ratio considering both dose rate and dose has been established. Additionally, irradiation hardening effects induced by loops demonstrate that high dose rates increase the density of <111> dislocation loops and inhibit their movement, thereby significantly improving material hardening. This study not only validates the feasibility of neutron damage simulation using triple-beam irradiation but also provides critical experimental support for predicting long-term service behaviour of nuclear materials.</div></div>","PeriodicalId":373,"journal":{"name":"Journal of Nuclear Materials","volume":"617 ","pages":"Article 156157"},"PeriodicalIF":3.2,"publicationDate":"2025-09-08","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145045137","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