First-principles comparative study of UN and Zr corrosion (English)
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- Further information on Aagesen, Larry K.:
- https://orcid.org/0000-0003-4936-676X
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- Further information on Jaques, Brian J.:
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In:
Journal of Nuclear Materials
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523
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402-412
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2019
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ISSN:
- Article (Journal) / Electronic Resource
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Title:First-principles comparative study of UN and Zr corrosion
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Contributors:Sikorski, Ember L. ( author ) / da Silva, Thiago H. ( author ) / Aagesen, Larry K. ( author ) / Jaques, Brian J. ( author ) / Li, Lan ( author )
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Published in:Journal of Nuclear Materials ; 523 ; 402-412
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Publisher:
- New search for: Elsevier B.V.
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Publication date:2019-06-06
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Size:11 pages
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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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Source:
Table of contents – Volume 523
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.
- 1
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Heavy ion irradiation damage in Zr2AlC MAX phaseQarra, H.H. / Knowles, K.M. / Vickers, M.E. / Akhmadaliev, Sh. / Lambrinou, K. et al. | 2019
- 10
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Irradiation behavior of Cf/SiC composite with titanium carbide (TiC)-based interphaseWang, Ji / Wang, Kai / Pei, Xueliang / Li, Mian / Yuan, Qin / Zhu, Yabin / Yang, Yitao / Zhang, Chonghong / He, Liu / Du, Shiyu et al. | 2019
- 16
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Thermodynamic properties of praseodymium on the liquid cadmium electrode and evaluation of anodic dissolution behavior in LiCl-KCl eutecticYin, Taiqi / Liu, Yalan / Wang, Lin / Yan, Yongde / Wang, Guiling / Chai, Zhifang / Shi, Weiqun et al. | 2019
- 26
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Radiation response of Ti2AlC MAX phase coated Zircaloy-4 for accident tolerant fuel claddingGigax, Jonathan G. / Kennas, Miltiadis / Kim, Hyosim / Wang, Tianyao / Maier, Benjamin R. / Yeom, Hwasung / Johnson, Greg O. / Sridharan, Kumar / Shao, Lin et al. | 2019
- 33
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Insights into the plastic behavior of irradiated Ni-based alloy through in-situ TEM experiments: Formation and evolution of defect-free channelsKaoumi, D. / Jammot, V. et al. | 2019
- 43
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Supervised dictionary learning supported classifier with feature fusion scheme to noninvasively detect TRISO-particle defectsGuo, Man-shan / Yang, Xu / Zhang, Feng / Zhong, Yajuan / Lin, Jun et al. | 2019
- 51
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Experimental comparison of the (ODS)EUROFER steels implanted by helium ions and irradiated in spallation neutron targetKrsjak, V. / Degmova, J. / Veternikova, J. Simeg / Yao, C.F. / Dai, Y. et al. | 2019
- 56
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Determination of dose rate effects on Zircaloy oxidation using proton irradiation and oxygen transport modelingReyes, Michael / Wang, Peng / Was, Gary / Marian, Jaime et al. | 2019
- 66
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Stable lattice thermal expansion of ZIRLO™: High-temperature X-ray diffraction resultsYoun, Young-Sang / Park, Jeongmi / Lim, Sang Ho et al. | 2019
- 71
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Hydrogen distribution induced screw dislocation core spreading in tungstenWang, Yinan / Wang, Xiaoyang / Wu, Xiaoyu / Li, Qiulin / Li, Chengliang / Shu, Guogang / Xu, Ben / Liu, Wei et al. | 2019
- 80
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Microstructural characterization of the as-cast and annealed Pu-10Zr alloyAitkaliyeva, Assel / Adkins, Cynthia A. / Hirschhorn, Jacob / McKinney, Casey / Tonks, Michael R. / Di Lemma, Fidelma Giulia et al. | 2019
- 91
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Microstructural characteristics of plasma sprayed, electroplated, and co-rolled Zr diffusion barriers in hot isostatic pressed low enriched U-10 wt% Mo monolithic fuel platesNewell, R. / Mehta, A. / Park, Y.J. / Keiser, D.D. Jr. / Cole, J.I. / Sohn, Y.H. et al. | 2019
- 101
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Enthalpies of formation and phase stability relations of USi, U3Si5 and U3Si2Chung, Cheng-Kai / Guo, Xiaofeng / Wang, Gaoxue / Wilson, Tashiema L. / White, Joshua T. / Nelson, Andrew T. / Shelyug, Anna / Boukhalfa, Hakim / Yang, Ping / Batista, Enrique R. et al. | 2019
- 111
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Long-term stability of the microstructure of austenitic ODS steel rods produced with a carbon-containing process control agentGräning, Tim / Klimenkov, Michael / Rieth, Michael / Heintze, Cornelia / Möslang, Anton et al. | 2019
- 121
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DIONISIO 3.0: Comprehensive 3D nuclear fuel simulation through PCMI cohesive and PLENUM modelsGoldberg, Ezequiel / Loza Peralta, Matías E. / Soba, Alejandro et al. | 2019
- 135
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Bulk moduli and high pressure crystal structure of U3Si2Guo, Xiaofeng / Lü, Xujie / White, Joshua T. / Benmore, Chris J. / Nelson, Andrew T. / Roback, Robert C. / Xu, Hongwu et al. | 2019
- 143
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A study of constituent redistribution in U–Zr fuels using quantitative phase-field modeling and sensitivity analysisHirschhorn, Jacob / Tonks, Michael R. / Aitkaliyeva, Assel / Adkins, Cynthia et al. | 2019
- 157
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Thermodynamic modeling of the U-Nb-Zr ternary systemZhou, Peng / Peng, Yingbiao / Du, Yong / Zhang, Lei / Mo, Wenlin / Fa, Tao / Bai, Bin / Wang, Xiaolin et al. | 2019
- 172
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Oxidative passivation of Fe–Cr–Al steels in lead-bismuth eutectic under oxygen-controlled static conditions at 700° and 800 °CPopovic, M.P. / Bolind, A.M. / Aussat, Y. / Gubser, A.J. / Hosemann, P. et al. | 2019
- 182
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Radial microstructural evolution in low burnup fast reactor MOX fuelParrish, Riley J. / Liu, Xiang / Winston, Alexander / Harp, Jason M. / Aitkaliyeva, Assel et al. | 2019
- 189
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Predicting the onset of void swelling in irradiated metals with machine learningJin, Miaomiao / Cao, Penghui / Short, Michael P. et al. | 2019
- 198
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Effect of β-Irradiation on the structure of iron polyphosphate glassGoj, Paweł / Jeleń, Piotr / Marczewska, Barbara / Stoch, Paweł et al. | 2019
- 206
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Measurement and modeling of the gas permeability of high burnup pressurized water reactor fuel rodsMontgomery, Rose / Morris, Robert N. et al. | 2019
- 216
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Phase separation of molybdenum, cesium and selenium from the borosilicate glass containing simulated nuclear wastes under a CO2-rich heating atmosphereXu, Zhanglian / Xu, Weiguo / Lv, Ying / Wang, Sheng / Wang, Jie et al. | 2019
- 223
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Enhanced wear resistance of CrAl-coated cladding for accident-tolerant fuelLee, Young-Ho / Park, Jung-Hwan / Kim, Il-Hyun / Park, Dong-Jun / Jung, Yang-Il / Choi, Byoung-Kwon / Kim, Hyun-Gil et al. | 2019
- 231
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Morphology, crystal and metal/oxide interface structures of nanoparticles in Fe–15Cr–2W–0.5Ti–7Al–0.4Zr–0.5Y2O3 ODS steelDou, Peng / Sang, Wei / Kimura, Akihiko et al. | 2019
- 248
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Nondestructive evaluation of plastic damage in a RAFM steel considering the influence of loading historyHe, Manru / Matsumoto, Takanori / Takeda, Sho / Uchimoto, Tetsuya / Takagi, Toshiyuki / Miki, Hiroyuki / Chen, Hong-En / Xie, Shejuan / Chen, Zhenmao et al. | 2019
- 260
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HLMIF, a facility for investigating the synergistic effect of ion-irradiation and LBE corrosionYao, Cunfeng / Wang, Zhiguang / Zhang, Hongpeng / Chang, Hailong / Sheng, Yanbin / Shen, Tielong / Zhu, Yabin / Pang, Lilong / Cui, Minghuan / Wei, Kongfang et al. | 2019
- 268
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Electrochemical behavior of Th(IV) on the bismuth electrode in LiCl–KCl eutecticJiang, Shilin / Liu, Kui / Liu, Yalan / Yin, Taiqi / Chai, Zhifang / Shi, Weiqun et al. | 2019
- 276
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Stress corrosion crack growth rate of welded joint used for low-pressure rotor of nuclear turbine in oxygenated pure water at 180 °CChu, Tongjiao / Cui, Haichao / Tang, Xinhua / Lu, Fenggui et al. | 2019
- 291
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Influence of solidification structures on radiation-induced swelling in an additively-manufactured austenitic stainless steelMeric de Bellefon, G. / Bertsch, K.M. / Chancey, M.R. / Wang, Y.Q. / Thoma, D.J. et al. | 2019
- 299
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Evolution of the microstructural and mechanical properties of BAM-11 bulk metallic glass during ion irradiation and annealingBrechtl, J. / Agarwal, S. / Crespillo, M.L. / Yang, T. / Bei, H. / Zinkle, S.J. et al. | 2019
- 310
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Shadow corrosion: Experiments and modelingBarberis, P. / Skocic, M. / Kaczorowski, D. / Perche, D. / Wouters, Y. / Nowotka, K. et al. | 2019
- 320
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Crystal and metal/oxide interface structures of nanoparticles in Fe–16Cr–0.1Ti–0.35Y2O3 ODS steelDou, Peng / Qiu, Lanlan / Jiang, Shaomin / Kimura, Akihiko et al. | 2019
- 333
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Evolution of microstructures and hardening property of initial irradiated, post-irradiation annealed and re-irradiated Chinese-type low-Cu reactor pressure vessel steelShi, J.J. / Zhao, W.Z. / Wu, Y.C. / Liu, X.B. / Jiang, J. / Cao, X.Z. / Wang, B.Y. et al. | 2019
- 342
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The distribution and forming of tritium in two types of China reduced activation ferritic-martensitic steelsWang, Zhanlei / Xiang, Xin / Chen, Chang An / Yan, Jing / Song, Yaqi / Rao, Yongchu / Zhu, Kaigui et al. | 2019
- 347
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Strain localization in copper canister FSW welds for spent nuclear fuel disposalForsström, A. / Bossuyt, S. / Yagodzinskyy, Y. / Tsuzaki, K. / Hänninen, H. et al. | 2019
- 360
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Uranium dioxide - Molybdenum composite fuel pellets with enhanced thermal conductivity manufactured via spark plasma sinteringBuckley, J. / Turner, J.D. / Abram, T.J. et al. | 2019
- 369
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Temperature dependent He-enhanced damage and strain in He-implanted AlNJublot-Leclerc, S. / Pallier, F. / Delauche, L. / Declémy, A. et al. | 2019
- 378
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Inferring radiation-induced microstructural evolution in single-crystal niobium through changes in thermal transportFerry, Sara E. / Dennett, Cody A. / Woller, Kevin B. / Short, Michael P. et al. | 2019
- 383
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Effects of hydride rim on the ductility of Zircaloy-4 claddingKim, Ju-Seong / Kim, Ho-A / Kang, So-Young / Kim, Yong-Soo et al. | 2019
- 391
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Elastic moduli reduction in SiC-SiC tubular specimen after high heat flux neutron irradiation measured by resonant ultrasound spectroscopySingh, G. / Koyanagi, T. / Petrie, C. / Deck, C. / Terrani, K. / Arregui-Mena, J.D. / Katoh, Y. et al. | 2019
- 402
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First-principles comparative study of UN and Zr corrosionSikorski, Ember L. / da Silva, Thiago H. / Aagesen, Larry K. / Jaques, Brian J. / Li, Lan et al. | 2019
- 413
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A molecular dynamics study of the behavior of Xe in U3Si2Beeler, Benjamin / Andersson, David / Cooper, Michael WD. / Zhang, Yongfeng et al. | 2019
- 421
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Microstructure response of ferritic/martensitic steel HT9 after neutron irradiation: effect of doseZheng, Ce / Reese, Elaina R. / Field, Kevin G. / Marquis, Emmanuelle / Maloy, Stuart A. / Kaoumi, Djamel et al. | 2019
- 434
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Investigation of solute segregation behavior using a correlative EBSD/TKD/APT methodology in a 16MND5 weldZhang, Leifeng / Radiguet, Bertrand / Todeschini, Patrick / Domain, Christophe / Shen, Yang / Pareige, Philippe et al. | 2019
- 444
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Atomistic simulation of interaction of collision cascade with different types of grain boundaries in α-FeKedharnath, A. / Kapoor, Rajeev / Sarkar, Apu et al. | 2019
- 458
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Study on the mechanical properties and microstructure of Zr-2.5wt%Nb pressure tube materialAhn, Dong-Hyun / Lim, Sangyeob / Lee, Gyeong-Geun / Chun, Young-Bum et al. | 2019
- 472
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Inductive effect of phosphorus atoms on the formation of graphite-like clusters in silicon carbide during irradiationWang, Pengfei / Wang, Shuai / Li, Hongyun / Wang, Qing et al. | 2019
- 478
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Variance-based sensitivity analysis applied to the hydrogen migration and redistribution model in Bison. Part II: Uncertainty quantification and optimizationAly, Zineb / Casagranda, Albert / Pastore, Giovanni / Brown, Nicholas R. et al. | 2019
- 490
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Multi-glass investigation of Stage III glass dissolution behavior from 22 to 90 °C triggered by the addition of zeolite phasesParruzot, Benjamin / Ryan, Joseph V. / George, Jaime L. / Motkuri, Radha Kishan / Bonnett, Jeff F. / Seymour, Lorraine M. / Derewinski, Miroslaw A. et al. | 2019
- 502
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Defect evolution in Ni and NiCoCr by in situ 2.8 MeV Au irradiationWang, Xing / Barr, Christopher M. / Jin, Ke / Bei, Hongbin / Hattar, Khalid / Weber, William J. / Zhang, Yanwen / More, Karren L. et al. | 2019
- 510
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Ferritic-martensitic steels for fission and fusion applicationsCabet, C. / Dalle, F. / Gaganidze, E. / Henry, J. / Tanigawa, H. et al. | 2019
- 538
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Corrigendum to “Postirradiation examinations of low burnup U3Si2 fuel for light water reactor applications” J. Nucl. Mater. 518 (2019) 62-79Cappia, Fabiola / Harp, Jason M. et al. | 2019
- 539
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Corrigendum to “Post-irradiation examinations of UO2 composites as part of the Accident Tolerant Fuels Campaign” [J. Nucl. Mater. 517 (2019) 97–105]Cappia, Fabiola / Harp, Jason M. / McCoy, K. et al. | 2019
- 540
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Corrigendum to “Irradiation creep and growth of zirconium alloys: A critical review” [J. Nuclear Mater. 521 (2019) 167–244]Adamson, Ronald B. / Coleman, Christopher E. / Griffiths, Malcolm et al. | 2019
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Editorial Board| 2019