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Fluorination of UO2, La2O3, and Y2O3 using ZrF4 使用 ZrF4 对二氧化铀、La2O3 和 Y2O3 进行氟化处理
Journal of Nuclear Materials Pub Date : 2024-02-01 DOI: 10.1016/j.jnucmat.2024.154971
Brenton Davis, Jinsuo Zhang
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引用次数: 0
Preparation of Li4SiO4 pebbles with high strength and inhibited lithium volatilization via lithium alginate 通过海藻酸锂制备具有高强度和抑制锂挥发的 Li4SiO4 卵石
Journal of Nuclear Materials Pub Date : 2024-02-01 DOI: 10.1016/j.jnucmat.2024.154973
Runze Geng, Jin Hu, Youwen Zhai, Juemin Yan, Kaijun Wang, Weijun Zhang, Qingming Chen, Xiang Liu, Kaizhao Wang
{"title":"Preparation of Li4SiO4 pebbles with high strength and inhibited lithium volatilization via lithium alginate","authors":"Runze Geng, Jin Hu, Youwen Zhai, Juemin Yan, Kaijun Wang, Weijun Zhang, Qingming Chen, Xiang Liu, Kaizhao Wang","doi":"10.1016/j.jnucmat.2024.154973","DOIUrl":"https://doi.org/10.1016/j.jnucmat.2024.154973","url":null,"abstract":"","PeriodicalId":506725,"journal":{"name":"Journal of Nuclear Materials","volume":"47 4","pages":""},"PeriodicalIF":0.0,"publicationDate":"2024-02-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"139889168","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
引用次数: 0
Spectroscopic and theoretical analyses of the reaction of SrO in molten chloride and fluoride salts 氧化锶在熔融氯化物和氟化物盐中反应的光谱和理论分析
Journal of Nuclear Materials Pub Date : 2024-02-01 DOI: 10.1016/j.jnucmat.2024.154962
Dokyu Kang, Choah Kwon, Wonseok Yang, Seok-Yeol Yoon, Yunu Lee, J. Amphlett, Sang-Eun Bae, Sangtae Kim, Sungyeol Choi
{"title":"Spectroscopic and theoretical analyses of the reaction of SrO in molten chloride and fluoride salts","authors":"Dokyu Kang, Choah Kwon, Wonseok Yang, Seok-Yeol Yoon, Yunu Lee, J. Amphlett, Sang-Eun Bae, Sangtae Kim, Sungyeol Choi","doi":"10.1016/j.jnucmat.2024.154962","DOIUrl":"https://doi.org/10.1016/j.jnucmat.2024.154962","url":null,"abstract":"","PeriodicalId":506725,"journal":{"name":"Journal of Nuclear Materials","volume":"22 22","pages":""},"PeriodicalIF":0.0,"publicationDate":"2024-02-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"139813416","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
引用次数: 0
Hydrogen Motion in Near Stoichiometric Yttrium Dihydride at Elevated Temperatures 高温下接近全化学计量的二氢化钇中的氢运动
Journal of Nuclear Materials Pub Date : 2024-02-01 DOI: 10.1016/j.jnucmat.2024.154972
Ercan Cakmak, M. N. Cinbiz, Aditya Sundar, Eugene Mamontov, Jianguo Yu, Xunxiang Hu, Kory D. Linton
{"title":"Hydrogen Motion in Near Stoichiometric Yttrium Dihydride at Elevated Temperatures","authors":"Ercan Cakmak, M. N. Cinbiz, Aditya Sundar, Eugene Mamontov, Jianguo Yu, Xunxiang Hu, Kory D. Linton","doi":"10.1016/j.jnucmat.2024.154972","DOIUrl":"https://doi.org/10.1016/j.jnucmat.2024.154972","url":null,"abstract":"","PeriodicalId":506725,"journal":{"name":"Journal of Nuclear Materials","volume":"19 9","pages":""},"PeriodicalIF":0.0,"publicationDate":"2024-02-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"139882881","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
引用次数: 0
Phase Field Modeling of Irradiation-induced Shrinkage Fracture in TRISO Fuel Particle 辐照诱发 TRISO 燃料粒子收缩断裂的相场建模
Journal of Nuclear Materials Pub Date : 2024-02-01 DOI: 10.1016/j.jnucmat.2024.154963
Jiatong Tan, Yingwei Wu, Qun Li, Ya-Kai He, Chunyu Yin
{"title":"Phase Field Modeling of Irradiation-induced Shrinkage Fracture in TRISO Fuel Particle","authors":"Jiatong Tan, Yingwei Wu, Qun Li, Ya-Kai He, Chunyu Yin","doi":"10.1016/j.jnucmat.2024.154963","DOIUrl":"https://doi.org/10.1016/j.jnucmat.2024.154963","url":null,"abstract":"","PeriodicalId":506725,"journal":{"name":"Journal of Nuclear Materials","volume":"32 6","pages":""},"PeriodicalIF":0.0,"publicationDate":"2024-02-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"139892690","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
引用次数: 0
Tungsten fiber-reinforced tungsten composites and their thermal stability 钨纤维增强钨复合材料及其热稳定性
Journal of Nuclear Materials Pub Date : 2024-02-01 DOI: 10.1016/j.jnucmat.2024.154951
D. A. H. Wartacz, Johann Riesch, K. Pantleon, W. Pantleon
{"title":"Tungsten fiber-reinforced tungsten composites and their thermal stability","authors":"D. A. H. Wartacz, Johann Riesch, K. Pantleon, W. Pantleon","doi":"10.1016/j.jnucmat.2024.154951","DOIUrl":"https://doi.org/10.1016/j.jnucmat.2024.154951","url":null,"abstract":"","PeriodicalId":506725,"journal":{"name":"Journal of Nuclear Materials","volume":"148 1","pages":""},"PeriodicalIF":0.0,"publicationDate":"2024-02-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"139877483","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","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 Sb-Nd and Te-Nd Phases within the U-Zr Fuel Matrix and Their Interactions with HT9 Alloy 评估 U-Zr 燃料基质中的 Sb-Nd 和 Te-Nd 相及其与 HT9 合金的相互作用
Journal of Nuclear Materials Pub Date : 2024-02-01 DOI: 10.1016/j.jnucmat.2024.154966
N. Jerred, Rabi Khanal, Michael T. Benson, Samrat Choudhury, I. Charit
{"title":"Evaluation of Sb-Nd and Te-Nd Phases within the U-Zr Fuel Matrix and Their Interactions with HT9 Alloy","authors":"N. Jerred, Rabi Khanal, Michael T. Benson, Samrat Choudhury, I. Charit","doi":"10.1016/j.jnucmat.2024.154966","DOIUrl":"https://doi.org/10.1016/j.jnucmat.2024.154966","url":null,"abstract":"","PeriodicalId":506725,"journal":{"name":"Journal of Nuclear Materials","volume":"132 ","pages":""},"PeriodicalIF":0.0,"publicationDate":"2024-02-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"139826052","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
引用次数: 0
Initial oxidation behavior of α-U and γ-U surfaces α-U 和 γ-U 表面的初始氧化行为
Journal of Nuclear Materials Pub Date : 2024-02-01 DOI: 10.1016/j.jnucmat.2024.154964
Houao Liu, Fuzhu Liu, H. Zong, Xiangdong Ding, Jun Sun
{"title":"Initial oxidation behavior of α-U and γ-U surfaces","authors":"Houao Liu, Fuzhu Liu, H. Zong, Xiangdong Ding, Jun Sun","doi":"10.1016/j.jnucmat.2024.154964","DOIUrl":"https://doi.org/10.1016/j.jnucmat.2024.154964","url":null,"abstract":"","PeriodicalId":506725,"journal":{"name":"Journal of Nuclear Materials","volume":"13 1","pages":""},"PeriodicalIF":0.0,"publicationDate":"2024-02-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"139879381","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
引用次数: 0
Application of the Immobilized Low-Activity Waste Glass Corrosion Model to the Static Dissolution of 24 Statistically-Designed Alkali-Borosilicate Waste Glasses 固定化低活性废玻璃腐蚀模型在 24 种统计设计的碱硼硅酸盐废玻璃静态溶解中的应用
Journal of Nuclear Materials Pub Date : 2024-02-01 DOI: 10.1016/j.jnucmat.2024.154968
S. Kerisit, J. Neeway, C. Lonergan, B. Parruzot, J. Crum, Richard C. Daniel, Gary L. Smith, R. Asmussen
{"title":"Application of the Immobilized Low-Activity Waste Glass Corrosion Model to the Static Dissolution of 24 Statistically-Designed Alkali-Borosilicate Waste Glasses","authors":"S. Kerisit, J. Neeway, C. Lonergan, B. Parruzot, J. Crum, Richard C. Daniel, Gary L. Smith, R. Asmussen","doi":"10.1016/j.jnucmat.2024.154968","DOIUrl":"https://doi.org/10.1016/j.jnucmat.2024.154968","url":null,"abstract":"","PeriodicalId":506725,"journal":{"name":"Journal of Nuclear Materials","volume":"18 1","pages":""},"PeriodicalIF":0.0,"publicationDate":"2024-02-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"139885183","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
引用次数: 0
Oxidation behavior of Zr-2.5Nb alloy exposed to steam in the temperature range of 600-1200°C 暴露于 600-1200°C 蒸汽中的 Zr-2.5Nb 合金的氧化行为
Journal of Nuclear Materials Pub Date : 2024-02-01 DOI: 10.1016/j.jnucmat.2024.154967
V. S. V. A. Krishna, Sai Karthik Nouduru, Kiran K. Mandapaka, Parag M. Ahmedabadi, G. Abraham, S. Shukla, S. Roychowdhury, V. Kain
{"title":"Oxidation behavior of Zr-2.5Nb alloy exposed to steam in the temperature range of 600-1200°C","authors":"V. S. V. A. Krishna, Sai Karthik Nouduru, Kiran K. Mandapaka, Parag M. Ahmedabadi, G. Abraham, S. Shukla, S. Roychowdhury, V. Kain","doi":"10.1016/j.jnucmat.2024.154967","DOIUrl":"https://doi.org/10.1016/j.jnucmat.2024.154967","url":null,"abstract":"","PeriodicalId":506725,"journal":{"name":"Journal of Nuclear Materials","volume":"7 1","pages":""},"PeriodicalIF":0.0,"publicationDate":"2024-02-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"139827136","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
引用次数: 0
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