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Journal of Nuclear Materials
Journal Prestige (SJR): 1.104  Citation Impact (citeScore): 3 Number of Followers: 12  Hybrid journal (It can contain Open Access articles)ISSN (Print) 0022-3115 - ISSN (Online) 0022-3115 Published by Elsevier  [2974 journals]
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- Development of an interatomic potential for mixed Uranium-Americium oxides
and application to the determination of the structural and thermodynamic
properties of (U,Am)O2 with Americium contents below 50%-
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Abstract: Publication date: Available online 14 March 2023Source: Journal of Nuclear MaterialsAuthor(s): Baptiste LABONNE, Simon ORLAT, Marjorie BERTOLUS
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- Vacancy accumulation mechanism at iron grain boundaries: The influence of
grain boundary character and its coupling with grain size-
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Abstract: Publication date: Available online 14 March 2023Source: Journal of Nuclear MaterialsAuthor(s): Xiaolin Li, Changjie Ding, Yange Zhang, Yichun Xu, Xiangyan Li, Xianping Wang, Q.F. Fang, Xuebang Wu, C.S. Liu
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- Theoretical analysis of thermal annealing kinetics of radiation defects in
silica-
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Abstract: Publication date: Available online 13 March 2023Source: Journal of Nuclear MaterialsAuthor(s): Vladimir Kuzovkov, Eugene Kotomin, Rafael Vila
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- Structural, electronic, elastic and thermal properties of Cr-doped U3Si2:
A DFT study-
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Abstract: Publication date: Available online 12 March 2023Source: Journal of Nuclear MaterialsAuthor(s): Qiao Li, Nianxiang Qiu, Zhen Liu, Qing Huang, Peng An, Shiyu Du
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- Size effects on tensile properties of Chinese reactor pressure vessel
steels and its semi-empirical normalization-
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Abstract: Publication date: Available online 12 March 2023Source: Journal of Nuclear MaterialsAuthor(s): Shaochun Yin, Xuejiao Wang, Wenjiang Qiang, Junwei Qiao, Yucheng Wu
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- Microstructural Analysis of Tristructural Isotropic Particles in
High-Temperature Steam Mixed Gas Atmospheres-
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Abstract: Publication date: Available online 12 March 2023Source: Journal of Nuclear MaterialsAuthor(s): Katherine I. Montoya, Brian A. Brigham, Grant Helmreich, Jesse Werden, Tyler J. Gerczak, Elizabeth S. Sooby
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- Corrosion of 316L & 316H Stainless Steel in Molten LiF-NaF-KF (FLiNaK)
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Abstract: Publication date: Available online 12 March 2023Source: Journal of Nuclear MaterialsAuthor(s): William Doniger, Cody Falconer, Adrien Couet, Kumar Sridharan
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- Phase Transformations and Thermal Expansion Coefficients of Unirradiated
U-X wt.% Zr (X = 6, 10, 20, 30) Measured via Neutron Diffraction-
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Abstract: Publication date: Available online 11 March 2023Source: Journal of Nuclear MaterialsAuthor(s): W.J. Williams, S.C. Vogel, M.A. Okuniewski
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- First-principles study of Xe behavior in δ-UZr2
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Abstract: Publication date: Available online 11 March 2023Source: Journal of Nuclear MaterialsAuthor(s): Xiying He, Zhixiao Liu, Jinli Cao, Wangyu Hu, Xinfu He, Huiqiu Deng
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- Corrigendum to “Improved thermal stability and irradiation tolerance of
oxide dispersion strengthened chromium coatings” [Journal of Nuclear
Materials 577 (2023) 154328]-
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Abstract: Publication date: Available online 11 March 2023Source: Journal of Nuclear MaterialsAuthor(s): Yuhang Li, Ji Wang, Li Zhao, Cunfeng Yao, Peng Li, Feng Huang, Fanping Meng
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- Models for effective elastic constants of irradiated U-10Mo fuels with
distributed fission gas bubbles-
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Abstract: Publication date: Available online 10 March 2023Source: Journal of Nuclear MaterialsAuthor(s): Yong Li, Guochen Ding, Zhexiao Xie, Jing Zhang, Xiaobin Jian, Shurong Ding, Yuanming Li
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- Molecular dynamics study of grain boundary and radiation effects on
tritium population and diffusion in zirconium-
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Abstract: Publication date: Available online 9 March 2023Source: Journal of Nuclear MaterialsAuthor(s): M.E. Foster, X.W. Zhou
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- High Temperature Annealing of Irradiated Nuclear Grade Graphite
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Abstract: Publication date: Available online 9 March 2023Source: Journal of Nuclear MaterialsAuthor(s): Steve Johns, William E. Windes, David T. Rohrbaugh, David L. Cottle
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- Defect evolution under intense electronic energy deposition in uranium
dioxide-
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Abstract: Publication date: Available online 7 March 2023Source: Journal of Nuclear MaterialsAuthor(s): G. Gutierrez, H. Guessous, D. Gosset, M. Bricout, I. Monnet, F. Garrido, C. Onofri, G. Adroit, A. Debelle
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- Preliminary investigation of Cr-coated F82H: Evolution of microstructure
and mechanical properties at the F82H/Cr interface during solid-state
diffusion bonding above Ac1 temperature-
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Abstract: Publication date: May 2023Source: Journal of Nuclear Materials, Volume 578Author(s): Reuben Holmes, Bo Li, Lijuan Cui, Sho Kano, Huilong Yang, Hiroaki Abe
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- Fe ion irradiation effects on the precipitates of P92 steel after
thermomechanical treatment-
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Abstract: Publication date: Available online 4 March 2023Source: Journal of Nuclear MaterialsAuthor(s): Yinzhong Shen, Zhijun Fan, Jiazheng Wang
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- A comprehensive atomistic investigation on the cascade induced helium
bubble motion in bcc iron for neutron irradiated RAFM steels-
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Abstract: Publication date: Available online 4 March 2023Source: Journal of Nuclear MaterialsAuthor(s): Liuliu Li, Lei Peng, Jingyi Shi, Yeshang Hu, Yongjie Sun, Chaowei Hu
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- Modelling radiation-induced oxidative dissolution of UO2-based spent
nuclear fuel on the basis of the hydroxyl radical mediated surface
mechanism-
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Abstract: Publication date: Available online 2 March 2023Source: Journal of Nuclear MaterialsAuthor(s): N.L. Hansson, M. Jonsson, C. Ekberg, K. Spahiu
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- High-Energy Heavy Ion Irradiation of HOPG
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Abstract: Publication date: Available online 2 March 2023Source: Journal of Nuclear MaterialsAuthor(s): D. Iveković, P. Dubček, A. Gajović, T. Čižmar, B. Radatović, A.L. Brkić, M. Kralj, M. Karlušić
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- Effects of vapor hydration and radiation on the leaching behavior of
nuclear glass-
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Abstract: Publication date: Available online 2 March 2023Source: Journal of Nuclear MaterialsAuthor(s): Haohan Zhang, Tomo Suzuki-Muresan, Stéphane Gin, Guillaume Blain, Thierry Sauvage, Olivier Wendling, Johan Vandenborre, Abdesselam Abdelouas
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- Enhanced crud resistance of CrAl coated ATF claddings in simulated PWR
conditions-
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Abstract: Publication date: Available online 2 March 2023Source: Journal of Nuclear MaterialsAuthor(s): Sung Eun Kim, Dae Ho Kim, Jong Dae Hong, Jae-Yong Kim, Hyun-Gil Kim
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- Formation of Ni–Si clusters and Their Relationship with Dislocation
Loops in Irradiated Stainless Steels-
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Abstract: Publication date: Available online 2 March 2023Source: Journal of Nuclear MaterialsAuthor(s): Dongyue CHEN, Kenta MURAKAMI, Kenji DOHI, Kenji NISHIDA, Liang CHEN, Zhengcao LI, Naoto SEKIMURA
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- Early self-organization of fission gas bubble superlattice formation in
neutron-irradiated monolithic U-10Mo fuels-
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Abstract: Publication date: Available online 1 March 2023Source: Journal of Nuclear MaterialsAuthor(s): Charlyne Smith, Kaustubh Bawane, Dennis Keiser, Mukesh Bachhav, Brandon Miller, Daniele Salvato, Jian Gan, Jan-Fong Jue, Dong Choe, Paul Gilbreath, William Hanson
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- Corrosion Behavior of (Fe,Ni)–Gd Intermetallic Compounds in FeNi-based
neutron-absorbing steels-
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Abstract: Publication date: Available online 1 March 2023Source: Journal of Nuclear MaterialsAuthor(s): Heon-Young Ha, Tae-Ho Lee, Hyo-Haeng Jo, JinJong Lee, Jae Hoon Jang
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- Development of a hybrid model for fuel performance analysis of spherical
fuel elements under normal conditions-
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Abstract: Publication date: Available online 28 February 2023Source: Journal of Nuclear MaterialsAuthor(s): Yanan He, Chen Gu, Chaoqun Deng, Yingwei Wu, Guanghui Su, Wenxi Tian, Suizheng Qiu
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- Void swelling in additively manufactured 316L stainless steel with Hafnium
composition gradient under self-ion irradiation-
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Abstract: Publication date: Available online 28 February 2023Source: Journal of Nuclear MaterialsAuthor(s): Miao Song, Jingfan Yang, Xiang Liu, Laura R. Hawkins, Zhijie Jiao, Lingfeng He, Yongfeng Zhang, Daniel Schwen, Xiaoyuan Lou
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- Deuterium retention in W-Cr-Y alloy: Impact of the manufacturing method
and helium presence-
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Abstract: Publication date: Available online 26 February 2023Source: Journal of Nuclear MaterialsAuthor(s): Z. Harutyunyan, O.V. Ogorodnikova, Yu. Gasparyan, A. Umerenkova, Y. Wang, E. Sal, C. García-Rosales
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- Simulation of hydrogen diffusion along the axial direction in Zirconium
cladding tube during dry Storage-
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Abstract: Publication date: Available online 25 February 2023Source: Journal of Nuclear MaterialsAuthor(s): Chansoo Lee, Youho Lee
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- Oxidation susceptibility of UN Σ5(210) grain boundary with Al/Cr/Ni
dopant: a first-principles study-
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Abstract: Publication date: Available online 23 February 2023Source: Journal of Nuclear MaterialsAuthor(s): Yuanyuan Wang, Jiajun Zhao, Yuanhai Jiang, Liu Xi, Jijun Zhao
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- Prediction of Corrosion Defect Critical Size and Corrosion Failure
Assessment Study of SGTs-
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Abstract: Publication date: Available online 23 February 2023Source: Journal of Nuclear MaterialsAuthor(s): Weibing Wang, Shengnan Wang, Jiahong Zhu, Bo Wang, Bo Liang, Kun Cheng, Hongguo Hou, Meng Zhang, Ruifeng Tian
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- Irradiation-induced phases in an Fe ion irradiated CLAM steel
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Abstract: Publication date: Available online 21 February 2023Source: Journal of Nuclear MaterialsAuthor(s): Xiaochen Zhang, Yinzhong Shen, Mingming Zhang
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- Polycrystalline Diamond and Magnetron Sputtered Chromium as a Double
Coating for Accident-Tolerant Nuclear Fuel Tubes-
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Abstract: Publication date: Available online 21 February 2023Source: Journal of Nuclear MaterialsAuthor(s): Irena Kratochvílová, Lucie Celbová, Petr Ashcheulov, Jaromír Kopeček, Ladislav Klimša, Esther de Prado, Kateřina Aubrechtová Dragounová, Jakub Luštinec, Jan Macák, Petr Sajdl, Radek Škoda, Jiří Bulíř
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- First principles study of oxygen diffusion in plutonium dioxide,
sesquioxide, and their interface under activated conditions-
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Abstract: Publication date: Available online 19 February 2023Source: Journal of Nuclear MaterialsAuthor(s): Jun Tang, Jinfan Chen, Pengchuang Liu, Ruizhi Qiu
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- A multiscale and multiphysics framework to simulate radiation damage in
nano-crystalline materials-
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Abstract: Publication date: Available online 18 February 2023Source: Journal of Nuclear MaterialsAuthor(s): Mohamed Hendy, Mauricio Ponga
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- Post-irradiation examination of low burnup U3Si5 and UN-U3Si5 composite
fuels-
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Abstract: Publication date: Available online 18 February 2023Source: Journal of Nuclear MaterialsAuthor(s): William A. Hanson, Fabiola Cappia, Joshua T. White, Kenneth J. McClellan, Jason M. Harp
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- Development and formulation of physics based metallic fuel models and
comparison to integral irradiation data-
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Abstract: Publication date: Available online 18 February 2023Source: Journal of Nuclear MaterialsAuthor(s): Christopher Matthews, Stephen Novascone, Al Casagranda, Larry Aagesen, Cetin Unal, David Andersson
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- Surface microstructures and properties of oxide-reinforced FeCrAl matrix
composite coatings prepared by laser cladding on a ferritic-martensitic
steel-
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Abstract: Publication date: Available online 16 February 2023Source: Journal of Nuclear MaterialsAuthor(s): Jing Shen, Linjiang Chai, Hao Wang, Chuanmei Wang, Qian Yuan, Ning Guo, Jun Xiao, Xing Yin
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- Comparative study of fission product release of homogeneous and
heterogeneous high-burn up MOX fuel by Knudsen Effusion Mass Spectrometry
supported by EPMA, SEM/TEM and thermal diffusivity investigations-
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Abstract: Publication date: Available online 16 February 2023Source: Journal of Nuclear MaterialsAuthor(s): Jean-Yves Colle, Thierry Wiss, Oliver Dieste, Philipp Pöml, Dragos Staicu, Terje Tverberg, Stéphane Bremier, Rudy J.M. Konings, Vincenzo V. Rondinella, Takeshi Sonoda, Akihiro Sasahara, Shoichi Kitajima
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- Helium diffusion and bubble evolution in single-phase tungsten-based
W-Ta-Cr-V complex concentrated alloy-
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Abstract: Publication date: Available online 15 February 2023Source: Journal of Nuclear MaterialsAuthor(s): Yongzhi Shi, Zhenyu Jiang, Tongjun Xia, Wenjie Zhang, Peishu Yang, Xinyu Ren, Meiqi Wang, Lisha Liang, Xingzhong Cao, Kaigui Zhu
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- A Novel Protocol to Recycle Zirconium from Zirconium Alloy Cladding from
Used Nuclear Fuel Rods-
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Abstract: Publication date: Available online 14 February 2023Source: Journal of Nuclear MaterialsAuthor(s): Breanna K. Vestal, Jordan Travis, Austin Albert, Stephanie Bruffey, Joanna McFarlane, Emory D. Collins, Rodney D. Hunt, Craig E. Barnes
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- Uranium Nitride Stability in Aqueous Solutions under Anoxic and Oxidizing
Conditions – Expected Behaviour under Repository Conditions in
Comparison to Alternative Nuclear Fuel Materials-
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Abstract: Publication date: Available online 12 February 2023Source: Journal of Nuclear MaterialsAuthor(s): Sawsan El Jamal, Yulia Mishchenko, Mats Jonsson
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- In-situ TEM investigation of dislocation loop evolution in HR3 steel
during Fe+ ion irradiation-
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Abstract: Publication date: Available online 9 February 2023Source: Journal of Nuclear MaterialsAuthor(s): Jipeng Wang, Li Guo, Jinru Luo, Jiangfeng Song, Yan Shi, Chang'an Chen
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- DBTT and tensile properties of as-sintered tungsten alloys reinforced by
yttrium-zirconium oxide-
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Abstract: Publication date: Available online 6 February 2023Source: Journal of Nuclear MaterialsAuthor(s): Jiahao Ye, Liujie Xu, Yunchao Zhao, Zhou Li, Hua Yu, Shizhong Wei
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