Progress in studying the fretting wear/corrosion of nuclear steam generator tubes (English)
- New search for: Guo, Xianglong
- New search for: Lai, Ping
- New search for: Li, Ling
- New search for: Tang, Lichen
- New search for: Zhang, Lefu
- New search for: Guo, Xianglong
- New search for: Lai, Ping
- New search for: Li, Ling
- New search for: Tang, Lichen
- New search for: Zhang, Lefu
In:
Annals of Nuclear Energy
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144
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2020
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ISSN:
- Article (Journal) / Electronic Resource
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Title:Progress in studying the fretting wear/corrosion of nuclear steam generator tubes
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Contributors:Guo, Xianglong ( author ) / Lai, Ping ( author ) / Li, Ling ( author ) / Tang, Lichen ( author ) / Zhang, Lefu ( author )
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Published in:Annals of Nuclear Energy ; 144
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Publisher:
- New search for: Elsevier Ltd
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Publication date:2020-04-20
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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 144
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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Development and testing of a coupled SuperMC and SUBCHANFLOW code for LWR simulationsYu, Louhanrong / Wang, Lei / Liu, Chao / Wu, Bin / Song, Jing / Wu, Yican et al. | 2020
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Investigation of a fast partial defect detection method for safeguarding PWR spent fuel assembliesLee, Haneol / Yim, Man-Sung et al. | 2020
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A three-dimensional PWR-core pin-by-pin analysis code NECP-Bamboo2.0Li, Yunzhao / Yang, Wen / Wang, Sicheng / Wu, Hongchun / Cao, Liangzhi et al. | 2020
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Three-dimensional numerical study on the effect of sidewall crust thermal resistance on transient MCCI by improved MPS methodCai, Qinghang / Zhu, Dahuan / Chen, Ronghua / Deng, Jian / Li, Yonglin / Dong, Chunhui / Tian, Wenxi / Qiu, Suizheng / Su, G.H. et al. | 2020
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Potential fuel cycle performance of floating small modular light water reactors of Russian originHernandez, Richard / Brown, Nicholas R. et al. | 2020
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Review on separation mechanism of corrugated plate separatorChen, Bowen / Wang, Bo / Mao, Feng / Ke, Bingzheng / Wen, Jiming / Tian, Ruifeng / Lu, Chuan et al. | 2020
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On the performance of nanofluids in APR 1400 PLUS7 assembly: NeutronicsKhuwaileh, Bassam A. / Al-Hamadi, Fatima I. / Hartanto, Donny / Said, Zafar / Ali, Muataz et al. | 2020
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Research on the software reliability quantitative evaluation of nuclear power plant digital control system based on non-homogeneous poisson process modelZhang, Qing / Ma, Quan / Liu, Mingxing / Zhong, Ke / Xu, Biao / Wu, Liyin et al. | 2020
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X2 VVER-1000 benchmark revision: Fresh HZP core state and the reference Monte Carlo solutionBilodid, Yuri / Fridman, Emil / Lötsch, Thomas et al. | 2020
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Design of a two-degree-of-freedom controller for nuclear reactor power control of pressurized water reactorWan, Jiashuang / Zhao, Fuyu et al. | 2020
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Point reactor kinetics equations from P1 approximation of the transport equationsEspinosa-Paredes, G. / Suescún-Díaz, D. et al. | 2020
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Review on sensors to measure control rod position for nuclear reactorHu, Guang / Zhang, Huang / Liu, Qianfeng et al. | 2020
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Extension and validation of aerosol wash-down model on inclined wallWang, Fangnian / Cheng, Xu et al. | 2020
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Fission product releases from thoria and urania fuels under reactor accident conditions: Hot cell experiment #6 (HCE6)Dickson, Raymond S. / Bell, J. Stuart / O'Connor, Robert F. / Sheedy, Jeffrey / Peplinskie, Randy T. / Gauthier, Mark D. et al. | 2020
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approach on the electronic and thermal properties of hypostoichiometricKaloni, T.P. / Onder, N. / Pencer, J. / Torres, E. et al. | 2020
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Dynamic sensitivity and uncertainty analysis of a small lead cooled reactorReale Hernandez, Cuauhtemoc / Wallenius, Janne / Luxat, John et al. | 2020
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Sensitivity study on criticality safety analysis of multiple misloading within the spent fuel storage caskAlrawash, Saed / Boravy, Muth / Yoo, Seung Uk / Han, Hyuk / Kim, Soon Young / Park, Moon-ghu / Park, Chang Je et al. | 2020
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Numerical prediction of a single phase Pressurized Thermal Shock scenario for crack assessment in an Reactor Pressure Vessel wallUitslag-Doolaard, H.J. / Stefanini, L. / Shams, A. / Blom, F.J. et al. | 2020
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Uncertainty & sensitivity analyses for LOCA simulation of PHEBUS experiment FPT-1 using a modified SUNSET codeFoad, B. / Hassan, M. / Takeda, T. et al. | 2020
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Effects of newly developed entrainment model for a thermal hydraulic system code (SPACE) based on breakup of large droplets in refloodYoon, Seung Hyun / Kim, Kyung Doo / Heo, Jaeseok / You, Byung-Hyun / Ha, Kwiseok et al. | 2020
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Study on the soil evaluation methodology of on and offsite Kori Unit 1Byon, Jihyang / Park, Sangjune / Ahn, Seokyoung et al. | 2020
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Reaction rate analyses of high-energy neutrons by injection of 100 MeV protons onto lead–bismuth targetPyeon, Cheol Ho / Yamanaka, Masao / Lee, Bongsoo et al. | 2020
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Numerical study on fluidelastic instability of tube bundles in two-phase flow considering the effect of tube boundary constraintLai, Jiang / Sun, Lei / Gao, Lixia / Tan, Tiancai / Li, Pengzhou et al. | 2020
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Improvement and validation of the heat transfer model for the containment module in the RCS-containment integral system codeGe, Li / Yang, Zijiang / Li, Huaqi / Shan, Jianqiang et al. | 2020
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Improvement of CINDER library for PWR burnup calculationsTavakkoli, Ehsan / Zangian, Mahdi / Minuchehr, Abdolhamid / Zolfaghari, Ahmadreza et al. | 2020
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Jeffery David Lewins 1930–2019| 2020
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Editorial Board| 2020
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Simulation investigation on flashing-induced instabilities in a natural circulation systemZhao, Yanan / Peng, Minjun / Xu, Yifan / Xia, Genglei et al. | 2020
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Statistical characterization of NPP transients: Application to PWR LBLOCAFernández-Cosials, Kevin / Queral, Cesar / Zugazagoitia, Eneko / Magán, Javier / Sanchez-Torrijos, Jorge / Sánchez-Espinoza, Victor Hugo / Posada, José María et al. | 2020
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Development and application of MOQUICO code to study molten corium-concrete interactionXu, Zhichun / Zhang, Yapei / Lin, Bo / Luo, Simin / Zhou, Yukun / Su, G.H. / Tian, Wenxi / Qiu, Suizheng et al. | 2020
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Experimental and numerical studies on two-phase flow instability behavior of a parallel helically coiled systemWang, Minglu / Zheng, Mingguang / Yan, Jinquan / Lin, Shaoxuan / Xiao, Yao et al. | 2020
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Safety aspects of spent fuel management in nuclear power plants during transition to decommissioningLiu, Ru-Feng / Chen, Chia-Kuan / Yang, Pei-Ying et al. | 2020
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Progress in studying the fretting wear/corrosion of nuclear steam generator tubesGuo, Xianglong / Lai, Ping / Li, Ling / Tang, Lichen / Zhang, Lefu et al. | 2020
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Numerical study on the uncertainty reduction for thermal power estimation of an open pool research reactor with natural convection core coolingKim, Hyunjong / Kim, In-Guk / Jung, Minkyu / Seo, Kyoung-Woo / Kim, Seong-Hoon et al. | 2020
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Reliability assessment of passive systems using artificial neural network based response surface methodologySolanki, R.B. / Kulkarni, Harshavardhan D. / Singh, Suneet / Varde, P.V. / Verma, A.K. et al. | 2020
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The EQL0D fuel cycle procedure and its application to the transition to equilibrium of selected molten salt reactor designsHombourger, Boris / Křepel, Jiří / Pautz, Andreas et al. | 2020
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Development of Core Monitoring System for a Nuclear Power Plant using Artificial Neural Network TechniqueSaeed, Asim / Rashid, Atif et al. | 2020
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Investigation on fluidelastic instability of tube bundles considering the effect of slip ratio of air-water two-phase flowLai, Jiang / Zhang, Dan / Sun, Lei / Gao, Lixia / Tan, Tiancai / Li, Pengzhou et al. | 2020
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Research on level 1 PSA and risk-informed design for ACP100Deng, Jian / Xu, Youyou / Qiu, Zhifang / Zhang, Hang / Wu, Lingjun / Wang, Xiaoji / Peng, Huanhuan / Du, Zhengyu et al. | 2020
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Numerical analysis of the effect of horizontal distance between a water mist nozzle and ignition source on reduction in heat release rateLee, Jaiho / Moon, Jongseol et al. | 2020
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Conceptual design and analysis of a megawatt power level heat pipe cooled space reactor power systemZhang, Wenwen / Zhang, Dalin / Wang, Chenglong / Tian, Wenxi / Qiu, Suizheng / Su, G.H. et al. | 2020
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Numerical study on the effect of dissymmetry heating on flow instability of supercritical water in two parallel channelsLiu, Jialun / Li, Huixiong / Lei, Xianliang / Feng, Zongrui / Hao, Yun et al. | 2020
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A comprehensive theoretical assessment of potential ‘tramp uranium’ isotopic evolution in BWR reactorsVasiliev, Alexander / Grimm, Peter / Ferroukhi, Hakim / Pecchia, Marco / Ledergerber, Guido et al. | 2020
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Symmetries of the approximation to the Boltzmann neutron transport equationPittman, Emily R. / Schmidt, Emma M. / Ramsey, Scott D. et al. | 2020
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Numerical study of natural convection effects on effective thermal conductivity in a pebble bedBu, Shanshan / Li, Zhenzhong / Ma, Zaiyong / Sun, Wan / Zhang, Luteng / Chen, Deqi et al. | 2020
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A dynamic model of xenon behavior in the Molten Salt Reactor ExperimentPrice, Terry / Chvala, Ondrej / Bereznai, George et al. | 2020
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A new hexagonal-Z nodal SN method in SARAX code systemWang, Yongping / Xu, Zhitao / Zheng, Youqi / Wu, Hongchun et al. | 2020
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Design and exergy evaluation of a novel parabolic trough solar-nuclear combined systemWang, Gang / Yin, Junhui et al. | 2020
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Disengagement of dispersed cerium oxalate from nitric-oxalic acid medium in a batch settler: Measurements and CFD simulationsPanda, Saroj K. / Vishnu Anand, P. / Aashranth, B. / Pandey, N.K. et al. | 2020
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Optimization of light water reactor High Level Waste disposal scenario in the situation of delayed reprocessing with existing and demonstrated technologyFukaya, Yuji et al. | 2020
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Multi-physics numerical analysis of the fuel-addition transients in the liquid-fuel molten salt reactorWan, Chenghui / Hu, Tianliang / Cao, Liangzhi et al. | 2020
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Code development and analysis of heat pipe cooled passive residual heat removal system of Molten salt reactorWang, Chenglong / Duan, Qianni / Liu, Minghao / Zhang, Dalin / Qiu, Suizheng / Su, G.H. / Tian, Wenxi et al. | 2020
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Development and verification of heat production and radiation damage energy production cross section module in the nuclear data processing code NECP-AtlasYin, Wen / Zu, Tiejun / Cao, Liangzhi / Wu, Hongchun et al. | 2020
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Simulation and uncertainty analysis of main steam line break accident on an integral test facilityYang, Ye / Yang, Jun / Deng, Chengcheng / Ishii, Mamoru et al. | 2020
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Estimation of the likelihood of severe accident management decision-making using a fuzzy logic modelSuh, Young A / Kim, Jaewhan et al. | 2020