The role of Cr, P, and N solutes on the irradiated microstructure of bcc Fe (English)
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In:
Journal of Nuclear Materials
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583
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2023
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ISSN:
- Article (Journal) / Electronic Resource
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Title:The role of Cr, P, and N solutes on the irradiated microstructure of bcc Fe
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Contributors:Warren, Patrick H. ( author ) / Clement, Caleb D. ( author ) / Yang, Chao ( author ) / Sen, Amrita ( author ) / Chen, Wei-Ying ( author ) / Wu, Yaqiao ( author ) / Wang, Ling ( author ) / Wharry, Janelle P. ( author )
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Published in:
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Publication date:2023-05-18
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ISSN:
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DOI:
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Type of media:Article (Journal)
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Type of material:Electronic Resource
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Language:English
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Keywords:
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Source:
Table of contents – Volume 583
The tables of contents are generated automatically and are based on the data records of the individual contributions available in the index of the TIB portal. The display of the Tables of Contents may therefore be incomplete.
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Irradiation performance of concentrated solid-solution alloys: Insight into defect behaviorsZhao, Yan / Li, Yaojun / Yang, Fan / Xie, Zhen / Wu, Xiaoyong / Wang, Yuexia et al. | 2023
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Molecular dynamics study of primary damage in the near-surface region in nickelFullarton, Michele / Nandipati, Giridhar / Senor, David J. / Casella, Andrew M. / Devanathan, Ram et al. | 2023
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Defect microstructure of a Ti64 alloy under TI2+ ion irradiation. Influence of dose and temperatureDoriot, Sylvie / Malaplate, Joël / Arnal, Benoît / Dalle, France et al. | 2023
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Determining the tensile strength of fuel surrogate TRISO-coated particle buffer, IPyC, and buffer-IPyC interlayer regionsMauseth, Tanner / Dunzik-Gougar, Mary Lou / Meher, Subhashish / van Rooyen, Isabella J et al. | 2023
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Effect of radiation damage on liquid Pb corrosion at the Fe/Pb solid-liquid interfaceZhang, Yange / Zhang, Jingdan / Li, Xiangyan / Xu, Yichun / Wu, Xuebang / Yang, Junfeng / Wang, Xianping / Liu, C.S. et al. | 2023
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Study of fusion boundary microstructure and local mismatch of SA508/alloy 52 dissimilar metal weld with butteringHytönen, N. / Ge, Y. / Que, Z. / Lindqvist, S. / Nevasmaa, P. / Virkkunen, I. / Efsing, P. et al. | 2023
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The cracking growth behavior of a sensitized Alloy 800H in supercritical waterSu, Haozhan / Huang, Tao / Wang, Jiamei / Zhang, Lefu / Chen, Kai et al. | 2023
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Understanding helium diffusion in iron: a multiscale modelling method based on the DFT and kinetic Monte Carlo, coupled to TEM and thermo-desorption spectroscopy experimentsOliveira Cavalcanti, Vinicius / Roques, Jérôme / Gentils, Aurélie / Horlait, Denis / Gilabert, Eric / Tassan-Got, Laurent et al. | 2023
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Mechanical properties of structural metallic alloys for nuclear applications deduced by small punch testMelkior, Thomas / Terentyev, Dmitry / Chang, ChihCheng / Bakaev, Alexander / Holmström, Stefan / Lebediev, S. / Paputsia, A. et al. | 2023
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The role of Cr, P, and N solutes on the irradiated microstructure of bcc FeWarren, Patrick H. / Clement, Caleb D. / Yang, Chao / Sen, Amrita / Chen, Wei-Ying / Wu, Yaqiao / Wang, Ling / Wharry, Janelle P. et al. | 2023
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Effects of tensile and compressive stresses on damage evolution law of nuclear graphiteYi, Yanan / Xing, Tongzhen / Liu, Guangyan / Sun, Libin / Shi, Li / Ma, Shaopeng et al. | 2023
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Effects of lattice and mass mismatch on primary radiation damage in W-Ta and W-Mo binary alloysWei, Guanying / Byggmästar, Jesper / Cui, Junzhi / Nordlund, Kai / Ren, Jingli / Djurabekova, Flyura et al. | 2023
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Initial stage of helium clustering in UN and PuNKuganathan, Navaratnarajah / Barron, Nicholas J. / Grimes, Robin W. et al. | 2023
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Oxidation behavior and microstructural evolution of Cr coatings prepared by multi-arc ion plating on Zry-4 in steam environments up to 1400 °CLiao, Haiyan / Huang, Weijiu / Ruan, Haibo / Zhang, Tengfei / Ning, Yi / Zhu, Pengzhou / Xu, Xiangkong / Xu, Meng / Yin, Shangyi / Su, Yongyao et al. | 2023
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Eutectic reaction and oxidation behavior of Cr-coated Zircaloy-4 accident-tolerant fuel cladding under various heating ratesKim, Dongju / Steinbrück, Martin / Grosse, Mirco / Tang, Chongchong / Lee, Youho et al. | 2023
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Radiation-induced alteration of sandstone concrete aggregateMaruyama, Ippei / Meawad, Amr / Kondo, Toshiaki / Sawada, Shohei / Halodova, Patricie / Fedorikova, Alica / Ohkubo, Takahiro / Murakami, Kenta / Igari, Takafumi / Rodriguez, Elena Tajuelo et al. | 2023
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The formation and migration of point defects and the thermodynamic behavior of TiD2 by first-principles calculationsZhou, Jintao / Chen, Heng / Zhou, Rulong / You, YuWei / Sun, Fei / Li, Dongdong et al. | 2023
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Microstructure and phase evolution in the U-10Zr fuel investigated by in situ TEM heating experiments.Di Lemma, Fidelma G. / Salvato, Daniele / Capriotti, Luca / Williams, Walter J. / Teng, Fei / Zhang, Yongfeng / Yao, Tiankai et al. | 2023
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Deuterium retention in helium-irradiated tungstenZhang, Hong / Zhang, Xuexi / Li, Yuhong / Wang, Peng / Qiao, Li et al. | 2023
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Simulation of radioactive fission gas release from defective PWR fuel rod using the MFPR/R mechanistic codeTarasov, V.I. / Ozrin, V.D. / Veshchunov, M.S. et al. | 2023
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Investigation of plate fuel performance under reactivity initiated accidents with developed multi-dimensional coupled methodXiang, Fengrui / He, Yanan / Wu, Yingwei / Niu, Yuhang / Qiu, Suizheng / Tang, Changbing / Wang, Kunpeng / Tian, Wenxi / Su, Guanghui et al. | 2023
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Integrated simulation of U-10Mo monolithic fuel swelling behaviorYe, Bei / Oaks, Aaron / Hu, Shenyang / Beeler, Benjamin / Rest, Jeff / Mei, Zhi-Gang / Yacout, Abdellatif et al. | 2023
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A prediction model for thermal conductivity of metallic nuclear fuel based on multiple machine learning modelsLu, Yong / Huang, Xiaoyi / Ren, Zhiyuan / Sun, Dan / Guo, Yihui / Liu, Xingjun / Wang, Cuiping et al. | 2023
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He clustering and role of vacancy in CuZr systemSarma, Dhrubanka / Saikia, Ujjal / Sahariah, Munima B. et al. | 2023
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A modified small punch testing scheme to investigate the circumferential mechanical behavior of nuclear fuel cladding tubesLai, Huan Sheng / Wang, Rongcheng / Zhong, Yuntao / Du, Peinan / Guo, Jinquan / Huang, Qifei et al. | 2023
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Characterization of surface coarse-grained structure and improved corrosion resistance for Zr-4 alloy at high temperatureGeng, Donghui / Deng, Jianxi / Liu, Leliang / Sun, Qiaoyan et al. | 2023
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Atomistic simulation study of the structure, segregation and stability of grain boundaries in the U-Zr metallic fuelCheik Njifon, Ibrahim / Torres, Edmanuel et al. | 2023
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A review of brannerite structured materials for nuclear waste managementZhang, Yingjie / Mir, Anamul H. et al. | 2023
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Effects of lead, bismuth and alloying elements on elastic anisotropy and fracture toughness of α-FeSun, L. / Gong, H.R. / Gong, X. / Gao, F. / Liang, C.P. et al. | 2023
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Statistical determination of stress threshold and survival analysis on IASCC initiation data of stainless steels in pressurized water reactor conditionsFalaakh, Dayu Fajrul / Myers, Patrick / Park, Jae Phil / Was, Gary S. / Bahn, Chi Bum et al. | 2023
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Recrystallization and grain growth of Zr-Nb-Sn alloy in 400–500 °C and effect on hydride embrittlementKim, Sangbum / Son, Donghyeon / Kang, Joo-Hee / Lee, Youho et al. | 2023
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Lithium titanate foam for tritium breeding applicationKhan, Nida / Sinha, Amit / Sudarsan, V et al. | 2023
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Atomistic investigation on radiation-induced segregation in W-Re alloy under cumulative flux irradiation: A hybrid simulation with MD and VC-SGC-MCZhang, Mengliang / Huang, Yun / Liu, Zhixiao / Sun, Jiayi / Gao, Fei / Zhou, Hong-Bo / Deng, Huiqiu et al. | 2023
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Long-term aqueous contamination of stainless steel in simulant nuclear reprocessing environmentsBarton, Daniel N. T. / Grebennikova, Tatiana / Denman, Anna E. / Carey, Thomas / Engelberg, Dirk L. / Sharrad, Clint A. et al. | 2023
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Microstructure-based crack formation in tungsten exposed to cyclic transient heatingWang, Yuanyuan / Wang, Hongzhi / Mi, Bo / Zhao, Jijun / Zhang, Chi et al. | 2023
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Editorial Board| 2023
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Single-size and cluster dynamics modeling of intra-granular fission gas bubbles in UOPastore, G. / Militello, N. / Blondel, S. / Wirth, B.D. et al. | 2023
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First-principles study on the corrosion-resistant of lead-bismuth to rough stainless steel surfaceLi, Yufei / Zhou, Runyu / Long, Xinglin / Gao, Tao / Chen, Changan et al. | 2023
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Near-infrared study of radiation damage in cerium dioxideCostantini, Jean-Marc / Guillaumet, Maxime / Lelong, Gérald / Seo, Pooreun / Yasuda, Kazuhiro et al. | 2023
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Alloy design and characterization of a recrystallized FeCrAl-ODS cladding for accident-tolerant BWR fuels: An overview of research activity in JapanUkai, S. / Sakamoto, K. / Ohtsuka, S. / Yamashita, S. / Kimura, A. et al. | 2023
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Ab initio modeling and thermodynamics of hydrated plutonium oxalatesLaCount, Michael D. / Meier, David E. / Ritzmann, Andrew M. / Muller, Scott E. / Clark, Richard A. / Buck, Edgar C. / Abrecht, David G. et al. | 2023
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Investigation of the thermal creep behaviour of non-irradiated Zr1%Nb cladding alloys between 623 and 1223KSklenicka, Vaclav / Kucharova, Kveta / Kral, Petr / Dvorak, Jiri / Kvapilova, Marie / Vrtilková, Vera / Krejcí, Jakub et al. | 2023
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The design and implementation of an in-situ mechanical loading apparatus used during proton-irradiationsMoore, B. / Topping, M. / Guo, R. / Feuerstake, T. / McDonald, C. / Daymond, M.R. et al. | 2023
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Diffusion study of uranium mononitride/zirconium carbide composite for space nuclear propulsionHamilton, Sarah / Jerred, Nathan D. / Scott, Randall / Bachhav, Mukesh / Yao, Tiankai / Miller, Victoria M. et al. | 2023