Journal of Nuclear Materials最新文献_第2页

Deuterium gas-driven permeation and retention in ZrC dispersion-strengthened W and pure W ZrC 分散强化 W 和纯 W 中氘气驱动的渗透和保留

IF 2.8 2区工程技术

Journal of Nuclear Materials Pub Date : 2024-11-19 DOI: 10.1016/j.jnucmat.2024.155529

Long Li , Ze Chen , Zeshi Gao , Yangyang Li , Zhe Liu , Wenyu Lin , Chao Yin , Shifeng Mao , Xudi Wang , Minyou Ye

{"title":"Deuterium gas-driven permeation and retention in ZrC dispersion-strengthened W and pure W","authors":"Long Li , Ze Chen , Zeshi Gao , Yangyang Li , Zhe Liu , Wenyu Lin , Chao Yin , Shifeng Mao , Xudi Wang , Minyou Ye","doi":"10.1016/j.jnucmat.2024.155529","DOIUrl":"10.1016/j.jnucmat.2024.155529","url":null,"abstract":"<div><div>ZrC dispersion-strengthened W (WZrC) exhibits high strength/ductility, low ductile-to-brittle transition temperature, and excellent thermal shock resistance, making it a promising candidate plasma-facing material for future fusion devices. However, the hydrogen isotope behaviors in WZrC are not well understood. In this study, experiments of deuterium gas-driven permeation (GDP) through 0.5 wt.% ZrC dispersion-strengthened W and pure W in the temperature range of 923–1123 K have been performed. The deuterium permeability of WZrC is close to pure W. In comparison, the deuterium diffusivity of WZrC is significantly lower than pure W in the experimental temperature range. Besides, thermal desorption spectroscopy (TDS) was used to investigate the deuterium retention properties of both W materials after static deuterium gas charging. The results reveal two deuterium desorption peaks with detrapping energies of 0.91 ± 0.09 eV and 1.07 ± 0.28 eV for WZrC, while one peak of 1.12 ± 0.31 eV for pure W. The deuterium retention of WZrC is approximately one order of magnitude higher than pure W. The study further discusses the impact of microstructural features on the transport and retention properties of deuterium in these materials.</div></div>","PeriodicalId":373,"journal":{"name":"Journal of Nuclear Materials","volume":"604 ","pages":"Article 155529"},"PeriodicalIF":2.8,"publicationDate":"2024-11-19","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142705993","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

Thermal evolution of helium bubbles in tungsten by GISAXS and TDS 通过 GISAXS 和 TDS 分析钨中氦气泡的热演化过程

IF 2.8 2区工程技术

Journal of Nuclear Materials Pub Date : 2024-11-19 DOI: 10.1016/j.jnucmat.2024.155524

Soon Han Bryan Teo , Matt Andrew Trevor Thompson , Nigel Kirby , Danielle Rose Hughes , Nour Hammoud , Aneeqa Khan , Hirohiko Tanaka , Noriyasu Ohno , Paul Mummery , Sarah Louise Harmer , Cormac Seamus Corr

{"title":"Thermal evolution of helium bubbles in tungsten by GISAXS and TDS","authors":"Soon Han Bryan Teo , Matt Andrew Trevor Thompson , Nigel Kirby , Danielle Rose Hughes , Nour Hammoud , Aneeqa Khan , Hirohiko Tanaka , Noriyasu Ohno , Paul Mummery , Sarah Louise Harmer , Cormac Seamus Corr","doi":"10.1016/j.jnucmat.2024.155524","DOIUrl":"10.1016/j.jnucmat.2024.155524","url":null,"abstract":"<div><div>Grazing-incidence small-angle x-ray scattering (GISAXS) and thermal desorption spectroscopy (TDS) were used to study the thermal evolution of helium (He) bubbles in tungsten (W). W samples were exposed to a low ion energy (∼20 eV, sheath accelerated) He plasma at two sample temperatures: 573 K (low-temperature) and 1050 K (high-temperature). They were then annealed to temperatures of 773 K, 873 K and 998 K. GISAXS analysis showed an increase in the median bubble radius of the high-temperature samples from 6.42 Å to 12.87 Å as a result of annealing to 998 K. No changes in the bubble radii distributions were observed for the low-temperature samples and the median radius remained at ∼4 Å even after annealing. TDS showed that the desorption behaviour of He in W has a dependence on the sample temperature during plasma irradiation. The higher-temperature sample experienced a maximum desorption rate that is an order of magnitude larger than the low-temperature sample. The desorption profile of the high-temperature sample spanned a wider temperature range, 500 K - 1500 K, than the low-temperature sample, 500 K - 750 K. The formation and thermal evolution of He bubbles in W have a clear dependence on sample temperature during plasma exposure. The differences in annealing behaviour observed in this work agree with prior in-situ TEM annealing experiments and help explain macroscopic plasma-material interaction effects such as recrystallisation suppression.</div></div>","PeriodicalId":373,"journal":{"name":"Journal of Nuclear Materials","volume":"604 ","pages":"Article 155524"},"PeriodicalIF":2.8,"publicationDate":"2024-11-19","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142705541","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":2,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"OA","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

Under the microscope: Reduced activation ferritic martensitic steel Eurofer-97 following ion-Irradiation and high-temperature high-pressure water exposure 显微镜下：离子辐照和高温高压水暴露后活化度降低的铁素体马氏体钢 Eurofer-97

IF 2.8 2区工程技术

Journal of Nuclear Materials Pub Date : 2024-11-17 DOI: 10.1016/j.jnucmat.2024.155527

Ronald N. Clark , David Kumar , Jonathan Hawes , Liam Hughes , Mariia Zimina , Robert Burrows , Jean-Charles Eloi , James Hargreaves , Kun Mo , Dong Liu , Elizabeth H. ParkerQuaife , Tomas Martin

{"title":"Under the microscope: Reduced activation ferritic martensitic steel Eurofer-97 following ion-Irradiation and high-temperature high-pressure water exposure","authors":"Ronald N. Clark , David Kumar , Jonathan Hawes , Liam Hughes , Mariia Zimina , Robert Burrows , Jean-Charles Eloi , James Hargreaves , Kun Mo , Dong Liu , Elizabeth H. ParkerQuaife , Tomas Martin","doi":"10.1016/j.jnucmat.2024.155527","DOIUrl":"10.1016/j.jnucmat.2024.155527","url":null,"abstract":"<div><div>This study is designed to characterise the microstructural behaviour of Eurofer-97 steel under ion irradiation and subsequent exposure to high-temperature high-pressure (HTHP) water. Eurofer-97, a ferritic-martensitic steel, has been developed to withstand the conditions of fusion reactors in the locations in contact with coolant with an elevated level of neutron flux, such as the breeder-wall blanket. The material has been studied after self-ion irradiation (using Fe ions) simulating the microstructural effects of neutron irradiation limited to the subsurface layer. The corrosion properties of the Eurofer-97 steel were studied by exposure to HTHP water up to 331°C. Advanced microstructural characterisation using scanning, transmission electron and focused ion beam microscopy was performed on the as-received microstructure and after ion irradiation. This was then characterised after exposure for 240 h in high-temperature water. Eurofer-97 had a dense, columnar Cr-rich inner oxide, followed by a Fe-rich outer oxide layer. In the irradiated condition the grain structure and oxide itself was less ordered. No appreciable difference in oxide thickness was identified between the irradiated and unirradiated specimens after this short exposure time.</div></div>","PeriodicalId":373,"journal":{"name":"Journal of Nuclear Materials","volume":"605 ","pages":"Article 155527"},"PeriodicalIF":2.8,"publicationDate":"2024-11-17","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142721126","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

Immobilization of TRPO waste by Na2O-B2O3-SiO2 matrix: Effects of Nd-containing crystals 用 Na2O-B2O3-SiO2 基质固定 TRPO 废物：含钕晶体的影响

IF 2.8 2区工程技术

Journal of Nuclear Materials Pub Date : 2024-11-17 DOI: 10.1016/j.jnucmat.2024.155528

Yang Li , Fen Luo , Jiahong Wang , Yu Gao , Gangchuan Ji , Xirui Lu

{"title":"Immobilization of TRPO waste by Na2O-B2O3-SiO2 matrix: Effects of Nd-containing crystals","authors":"Yang Li , Fen Luo , Jiahong Wang , Yu Gao , Gangchuan Ji , Xirui Lu","doi":"10.1016/j.jnucmat.2024.155528","DOIUrl":"10.1016/j.jnucmat.2024.155528","url":null,"abstract":"<div><div>This study used a ternary Na<sub>2</sub>O-B<sub>2</sub>O<sub>3</sub>-SiO<sub>2</sub> matrix to simulate the immobilization of complex TRPO waste. The study investigated the relationship between the solidified bodies with different TRPO waste contents and their solid solubility, FT-IR, Vickers hardness, and density. The study found that the maximum amount of TRPO waste that can be immobilized in the Na<sub>2</sub>O-B<sub>2</sub>O<sub>3</sub>-SiO<sub>2</sub> matrix was 20 <em>wt</em>.%. When the TRPO waste content ranged from 5-15 <em>wt</em>.%, it was primarily immobilized in the glassy phase. When the TRPO waste content exceeded 20 <em>wt</em>.%, the crystalline phases NdBO<sub>3</sub> and Na<sub>3</sub>Nd(BO<sub>3</sub>)<sub>2</sub>, which contain the main waste element Nd appeared. Samples containing 20 <em>wt</em>.% TRPO waste resulted in leaching of 10<sup>-6</sup> g·m<sup>-2</sup>·d<sup>-1</sup>. The presence of NdBO<sub>3</sub> and Na<sub>3</sub>Nd(BO<sub>3</sub>)<sub>2</sub> crystals resulted in a decrease in the Vickers hardness and density of the samples. The highest values for Vickers hardness and density were 6.77 GPa and 2.7 g<sup>-1</sup>cm<sup>-3</sup>, respectively. The borosilicate matrix utilized in this study has proven to be an effective immobilization of complex TRPO wastes and holds promise as a treatment matrix for TRPO wastes.</div></div>","PeriodicalId":373,"journal":{"name":"Journal of Nuclear Materials","volume":"604 ","pages":"Article 155528"},"PeriodicalIF":2.8,"publicationDate":"2024-11-17","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142706000","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 assessment of primary damage efficiency for fusion relevant elements

IF 2.8 2区工程技术

Journal of Nuclear Materials Pub Date : 2024-11-17 DOI: 10.1016/j.jnucmat.2024.155520

Hannah Agwunobi , Stefano Segantin , Michael Short

引用次数: 0

XPS post-mortem analysis of plasma-facing units extracted from WEST after the C3 (2018) and C4 (2019) campaigns 对 C3（2018 年）和 C4（2019 年）活动后从 WEST 提取的面向等离子体的单元进行 XPS 死后分析

IF 2.8 2区工程技术

Journal of Nuclear Materials Pub Date : 2024-11-15 DOI: 10.1016/j.jnucmat.2024.155525

Alexandru Marin , Ashrakat Saefan , Ezekial Unterberg , Chad M. Parish , Elodie Bernard , Mathilde Diez , Emmanuelle Tsitrone , Xing Wang , the WEST team

{"title":"XPS post-mortem analysis of plasma-facing units extracted from WEST after the C3 (2018) and C4 (2019) campaigns","authors":"Alexandru Marin , Ashrakat Saefan , Ezekial Unterberg , Chad M. Parish , Elodie Bernard , Mathilde Diez , Emmanuelle Tsitrone , Xing Wang , the WEST team","doi":"10.1016/j.jnucmat.2024.155525","DOIUrl":"10.1016/j.jnucmat.2024.155525","url":null,"abstract":"<div><div>Four monoblocks coming from one ITER-like plasma-facing unit from the Q3B sector of the lower divertor, named as monoblock (MB)3, MB9, MB20, and MB30, were exposed to the deuterium and helium plasma mixture during the C3 (2018) and C4 (2019) campaigns of the Tungsten Environment in Steady-state Tokamak (WEST), followed by a detailed ex-situ X-ray photoelectron spectroscopy investigation. The surface and in-depth chemistry of the tungsten monoblocks indicated the formation of a re-deposited mixture in the deposition-dominated area of the divertor, thicker than 218 and 172 nm for MB3 and MB9, respectively. The redeposition layer was dominated by a mixture of boron carbides accompanied by tungsten carbides in MB3, while in MB9, the redeposition layer was dominated by tungsten borides. The remaining two monoblocks, MB20 and MB30, were collected from the erosion region and showed similar chemical behavior with a blended mixture of oxidized and metallic tungsten followed by boron carbides within a 50 nm depth range. Boron fixation in the layers is an expected consequence of the boronizations used during the operation, but the chemical status of redeposited elements was characterized for the first time in this work.</div></div>","PeriodicalId":373,"journal":{"name":"Journal of Nuclear Materials","volume":"604 ","pages":"Article 155525"},"PeriodicalIF":2.8,"publicationDate":"2024-11-15","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142705992","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

Evaluation of radiation-induced amorphization of α-quartz in concrete aggregates using Raman spectroscopy 利用拉曼光谱评估辐射诱导的混凝土骨料中 α-石英的非晶化现象

IF 2.8 2区工程技术

Journal of Nuclear Materials Pub Date : 2024-11-15 DOI: 10.1016/j.jnucmat.2024.155523

Amr Meawad , Kenta Murakami , Takahiro Ohkubo , Osamu Kontani , Junji Etoh , Minh Do Thi , Claudia Aparicio , Chinthaka M. Silva , Ippei Maruyama

{"title":"Evaluation of radiation-induced amorphization of α-quartz in concrete aggregates using Raman spectroscopy","authors":"Amr Meawad , Kenta Murakami , Takahiro Ohkubo , Osamu Kontani , Junji Etoh , Minh Do Thi , Claudia Aparicio , Chinthaka M. Silva , Ippei Maruyama","doi":"10.1016/j.jnucmat.2024.155523","DOIUrl":"10.1016/j.jnucmat.2024.155523","url":null,"abstract":"<div><div>This study investigated the feasibility of Raman spectroscopy as a rapid and nondestructive chemical analysis tool for assessing radiation-induced amorphization in aggregate-forming minerals. Metachert and sandstone concrete aggregates, rich in quartz and containing additional minerals, such as albite and microcline in the case of sandstone, were exposed to various neutron fluence levels (1.2, 2.2, 7.0, and 14.3 × 10<sup>19</sup> n/cm², E ≥ 0.01 MeV) at ∼53.3°C. The Raman spectra of both the nonirradiated and irradiated samples were collected with a specific focus on quartz characterization. Concurrently, X-ray diffraction (XRD) refinement was employed to calculate the cell volume expansions of the studied mineral.</div><div>The crystal lattice defects in α-quartz induced by neutron irradiation cause changes in the Raman band attributes (band position, full width at half maximum, and relative intensity), and are also responsible for the growth of defect bands. The behavior of the most intense vibrational bands can be used to estimate the change in the cell volume of irradiated α-quartz in different rocks.</div><div>The data analysis presented in this study demonstrates a good correlation between the changes in the cell volume of quartz, as measured using XRD, and the Raman band attributes. This correlation enhances our understanding of structural alterations, emphasizing the potential of Raman spectroscopy as a reliable method for investigating the structural changes induced by the irradiation of minerals and highlighting its agreement with well-established XRD analyses.</div></div>","PeriodicalId":373,"journal":{"name":"Journal of Nuclear Materials","volume":"604 ","pages":"Article 155523"},"PeriodicalIF":2.8,"publicationDate":"2024-11-15","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142705540","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":2,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"OA","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

Optical vibrational spectroscopic signatures related to U3O8 production processes 与八氧化三铀生产过程有关的光学振动光谱特征

IF 2.8 2区工程技术

Journal of Nuclear Materials Pub Date : 2024-11-14 DOI: 10.1016/j.jnucmat.2024.155522

Jordan M. Roach , Andrew Miskowiec , Luther McDonald IV , Erik C. Abbott , Cody A. Nizinski , Ian J. Schwerdt , Tyler L. Spano

{"title":"Optical vibrational spectroscopic signatures related to U3O8 production processes","authors":"Jordan M. Roach , Andrew Miskowiec , Luther McDonald IV , Erik C. Abbott , Cody A. Nizinski , Ian J. Schwerdt , Tyler L. Spano","doi":"10.1016/j.jnucmat.2024.155522","DOIUrl":"10.1016/j.jnucmat.2024.155522","url":null,"abstract":"<div><div>Uranium ore concentrates are materials found early within the nuclear fuel cycle and contain high concentrations of uranium in an easily transported form, making the concentrates a likely target for illegal diversion. These concentrates are typically converted to U<sub>3</sub>O<sub>8</sub> for further processing and, therefore, may lose specific physicochemical characteristics in determining the materials’ source and processing history. In this work, we explore the Raman spectra of eight oxide samples produced from various uranium ore concentrates and processing pathways to examine the presence of spectroscopic signatures relating to each sample's process history. Samples produced from amine extraction and dialkylphosphoric acid extraction processes show unique characteristics due to high concentrations of α-UO<sub>3</sub>, whereas samples calcinated from metallic diuranates do not form pure α-U<sub>3</sub>O<sub>8</sub> because of metallic ion inclusions. Pure α-U<sub>3</sub>O<sub>8</sub> oxide samples are obtained through calcination of ammonium diuranate, ammonium uranyl carbonate, and metastudtite intermediates. The Raman spectra of these oxide samples show close agreement with pristine α-U<sub>3</sub>O<sub>8</sub> spectra. However, deviations from the pristine spectra are observed in the 300–460 cm<sup>−1</sup> spectral range. These deviations are unique identifying signatures that were likely created by lasting effects from the process history. Spectral center of mass calculations indicate grouping of samples based on processing history.</div></div>","PeriodicalId":373,"journal":{"name":"Journal of Nuclear Materials","volume":"604 ","pages":"Article 155522"},"PeriodicalIF":2.8,"publicationDate":"2024-11-14","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142705997","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

Additive manufactured ODS-FeCrAl steel achieves high corrosion resistance in lead-bismuth eutectic (LBE) 添加剂制造的 ODS-FeCrAl 钢在铅铋共晶（LBE）中实现了高抗腐蚀性能

IF 2.8 2区工程技术

Journal of Nuclear Materials Pub Date : 2024-11-12 DOI: 10.1016/j.jnucmat.2024.155516

Ji-Sheng Li, Yan-Fei Wang, Junjie Chai, Weijia Gong, Xian-Zong Wang

{"title":"Additive manufactured ODS-FeCrAl steel achieves high corrosion resistance in lead-bismuth eutectic (LBE)","authors":"Ji-Sheng Li, Yan-Fei Wang, Junjie Chai, Weijia Gong, Xian-Zong Wang","doi":"10.1016/j.jnucmat.2024.155516","DOIUrl":"10.1016/j.jnucmat.2024.155516","url":null,"abstract":"<div><div>Developing corrosion resistant alloys used in lead-bismuth eutectic (LBE) is essential for lead-cooled fast reactors (LFRs). In this work, additive manufacturing was applied to fabricate oxide dispersion-strengthened FeCrAl steels (ODS and Y-ODS), and the latter contains 1.5 wt.% Y<sub>2</sub>O<sub>3</sub> nanoparticles. After exposure in LBE at 450 °C for 1000 hours, both alloys generate a compact, uniform and stable Cr<sub>2</sub>O<sub>3</sub>/Al<sub>2</sub>O<sub>3</sub> protective oxide layer (below 200 nm). Benefits from the quick transient oxidation rate at the initial stage, the oxide layer realizes a slow oxidation kinetics and achieves high corrosion resistance to LBE attack. More importantly, the addition of Y<sub>2</sub>O<sub>3</sub> induce the formation of Y-Al-O-type oxide nanoparticles which provides an additional source of Al<sup>3+</sup> at the interface and promotes the growth of an internal oxide layer within Al<sub>2</sub>O<sub>3</sub>, and thus subsequently the oxides layer demonstrates remarkable stability. This study highlights the potential application of additive manufacturing in advanced materials for LFRs.</div></div>","PeriodicalId":373,"journal":{"name":"Journal of Nuclear Materials","volume":"604 ","pages":"Article 155516"},"PeriodicalIF":2.8,"publicationDate":"2024-11-12","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142652835","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

First-principles study of solute segregation and its effects on the cohesion of the Fe/Y2Ti2O7 interface in ferritic ODS alloy with He 铁素体 ODS 合金中溶质偏析及其对 Fe/Y2Ti2O7 与 He 界面内聚力影响的第一性原理研究

IF 2.8 2区工程技术

Journal of Nuclear Materials Pub Date : 2024-11-12 DOI: 10.1016/j.jnucmat.2024.155515

Ye Liu , Weibo Zhao , Shuang He , Zunmin Lin , Lin Zhang , Xu Chen , Oleg I. Gorbatov , Peinan Du , Ping Peng , Xuanhui Qu

{"title":"First-principles study of solute segregation and its effects on the cohesion of the Fe/Y2Ti2O7 interface in ferritic ODS alloy with He","authors":"Ye Liu , Weibo Zhao , Shuang He , Zunmin Lin , Lin Zhang , Xu Chen , Oleg I. Gorbatov , Peinan Du , Ping Peng , Xuanhui Qu","doi":"10.1016/j.jnucmat.2024.155515","DOIUrl":"10.1016/j.jnucmat.2024.155515","url":null,"abstract":"<div><div>The solute segregation and its effects on the cohesion of the Fe/Y₂Ti₂O₇ interface in ferritic oxide dispersion strengthened (ODS) alloy have been investigated using first-principles calculations. The computational results indicate that W, Cr, Al, Nb, Zr, and Hf are prone to segregate to the Fe/Y₂Ti₂O₇ interface and enhance the cohesive strength of the Fe/Y₂Ti₂O₇ interface, improving its stability. He atoms exhibit a strong tendency to segregate at the Fe/Y₂Ti₂O₇ interface, leading to embrittlement of the interface. Moreover, in the case of co-existing of W, Cr, Al, Nb, Zr, and Hf with He atoms, it is found that W, Cr, and Al increase the segregation energy of He at the Fe/Y₂Ti₂O₇ interface. This promotes the diffusion of He from the Fe/Y₂Ti₂O₇ interface into the bulk of the Y₂Ti₂O₇, thereby reducing He-induced embrittlement at the Fe/Y₂Ti₂O₇ interface. Finally, the electronic structures of the Fe/Y₂Ti₂O₇ interfaces with and without solute elements, as well as the interaction between metallic solutes and He, have been discussed in detail to reveal the mechanisms of alloying reduction effect on He-segregated embrittlement at the Fe/Y₂Ti₂O₇ interface. The results obtained from this work suggest that adjusting the alloying components in ODS alloys can improve the radiation resistance of the alloy, providing theoretical guidance for the design and optimization of ferritic ODS alloys.</div></div>","PeriodicalId":373,"journal":{"name":"Journal of Nuclear Materials","volume":"604 ","pages":"Article 155515"},"PeriodicalIF":2.8,"publicationDate":"2024-11-12","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142705991","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