Evaluation of probabilistic safety margin of nuclear power plant based on optimized adaptive sampling method (English)
- New search for: Chen, Haoyin
- New search for: Wang, He
- New search for: Wang, Longcong
- New search for: Zhao, Qiang
- New search for: Chen, Haoyin
- New search for: Wang, He
- New search for: Wang, Longcong
- New search for: Zhao, Qiang
In:
Annals of Nuclear Energy
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201
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2024
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ISSN:
- Article (Journal) / Electronic Resource
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Title:Evaluation of probabilistic safety margin of nuclear power plant based on optimized adaptive sampling method
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Contributors:
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Published in:Annals of Nuclear Energy ; 201
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Publisher:
- New search for: Elsevier Ltd
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Publication date:2024-02-02
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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 201
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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Multi-input and multi-output shielding calculation agent model method based on improved neural network with Swish-NNTAGui, Long / Song, Yingming / Li, Xiaomeng / Yuan, Weiwei et al. | 2024
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Conceptual study of a new space nuclear propulsion system based on direct propulsion of fission fragmentsZhang, Dacai / Yu, Ganglin / Xiong, Minzhi / Zhang, Xirui / Zhong, Guanghui / Wang, Kan et al. | 2024
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An experimental study on the effect of coolant salinity on steam explosionDeng, Yucheng / Guo, Qiang / Xiang, Yan / Fang, Di / Komlev, Andrei / Bechta, Sevostian / Ma, Weimin et al. | 2024
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Stochastic model updating for analysis of a nuclear containment vessel under internal pressureSong, Meng-Yan / Wu, Yu-Xiao / Feng, De-Cheng / Jiang, Di / Zhang, Pei-Yao et al. | 2024
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Study on flow regime prediction model for water-cooled reactor core based on machine learning algorithmsMa, Yichao / Kong, Dexiang / Zhang, Jing / Wang, Mingjun / Tian, Wenxi / Wu, Yingwei / Su, G.H. / Qiu, Suizheng et al. | 2024
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Development of coarse mesh finite difference acceleration in the three-dimensional discrete-ordinates discontinuous finite element transport code TARSZhang, Hu / Zhang, Guangchun / Hu, Henglin et al. | 2024
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Editorial Board| 2024
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Numerical study on surface corrosion deposition of fuel elements and its influence on flow heat transferHou, Yandong / Chen, Tianbo / Li, Weichao / Gao, Chuntian / Chen, Bowen / Zhang, Chao / Xiang, Yan et al. | 2024
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Study of microstructure and properties of SiCf/SiC-Zr composite cladding prepared through PIPMeng, Ying / Qian, Yueqing / Feng, Haining / Gao, Yiming / Lu, Yongheng et al. | 2024
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An improved parallel Random Sequential Addition algorithm in RMC code for dispersion fuel analysisTan, Zhe Chuan / Feng, Zhi Yuan / Wang, Kan et al. | 2024
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Novel polynomial Abet data augmentation algorithm with GRU paradigm for nuclear power predictionKhan, Saifullah / Awan, Saeed Ehsan / Muhammad, Yasir / Jadoon, Ihtesham / Raja, Muhammad Asif Zahoor et al. | 2024
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Traditional machine learning methods in predicting the physics of subcritical systems in source-equilibriumGatchalian, Ronald Daryll E. / Tsvetkov, Pavel V. et al. | 2024
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Forward and inverse predictive transient models of TREAT using surrogate reactivity modelsJaradat, Mustafa K. / Schunert, Sebastian / Gleicher, Frederick N. / Labouré, Vincent M. / DeHart, Mark D. et al. | 2024
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Heaving motion effect on the transient thermodynamic characteristics of helical coil once-through steam generators in mixed ocean conditionsZhang, Chao / Li, Jiangping / Sun, Haoyu / Li, Weichao / Hou, Yandong / Xiang, Yan et al. | 2024
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Numerical simulation of typical abnormal operating conditions in the secondary circuit system of a Hua-long Pressurized Reactor nuclear power unitYang, Chen / Zhang, Qiang / Lu, Chuntian / Huang, Shanglong / Zhang, Tao / Zhang, Zonglong et al. | 2024
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Evaluation of probabilistic safety margin of nuclear power plant based on optimized adaptive sampling methodChen, Haoyin / Wang, He / Wang, Longcong / Zhao, Qiang et al. | 2024
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Investigation of the second-order nodal expansion method for the forward and adjoint neutron flux in the hexagonal geometryAbbasi Fashami, Sajjad / Zangian, Mahdi / Minuchehr, Abdolhamid / Zolfaghari, Ahmadreza et al. | 2024
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Enhancement in the safety and reliability of Pressurized Water reactors using Machine Learning approachZubair, Muhammad / Akram, Yumna et al. | 2024
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Numerical simulation investigations on the flow induced vibration of a nuclear fuel rod with relaxed clamping structuresJiao, Yongjun / Wang, Yihu / Li, Wei / Zheng, Meiyin / Zhang, Jing / Wu, Yingwei / Su, GuangHui / Qiu, Suizheng et al. | 2024
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The impact of gamma-irradiation on physical properties and membrane distillation performance of PTFE and PVDF hollow fiber membraneJia, Xuxiang / Lan, Lijun / Wang, Tianping / Wang, Yu / Ye, Chunsong et al. | 2024
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Impact of the extended computational domain at inlet and outlet on natural convection in a vertical rectangular channelJi, Yongan / Li, Changwei / Ding, Ming / Guo, Zehua / Sun, Zhongning et al. | 2024
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Experimental study of turbulent flow in lower plenum with flow skirt of reactor pressure vessel of pressurized water reactorQu, Wenhai / Xie, Hao / Wang, Hanyu / Xiong, Jinbiao et al. | 2024
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Empirical model of flow-accelerated corrosion at elbow of carbon steel pipeline based on dimensional analysisBao, Guozhi / Qin, Weiguang / Pan, Dailong / Si, Xiaodong et al. | 2024
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Steady and transient solutions of neutron diffusion equations via computational methods based on Hartley series and higher order finite difference schemesHamada, Yasser Mohamed et al. | 2024
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Numerical study on flow instability of parallel helical tubes under convective heating conditionLiu, Maolong / Shen, Cong / Xu, Ziyi / Zeng, Chen / Wang, Xiaowen / Liu, Limin / Gu, Hanyang et al. | 2024
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Numerical study of mixing vane spacer grid effect on subchannel mixing in a 5 × 5 rod bundleQu, Wenhai / Li, Yi et al. | 2024
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Bayesian update of fragility curves for equipment failure probability in seismic probabilistic safety assessment in nuclear power plantJiang, Hong / Peng, Changhong et al. | 2024
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Model order reduction of a once-through steam generator via dynamic mode decompositionXu, Yifan / Peng, Minjun / Cammi, Antonio / Introini, Carolina / Xia, Genglei et al. | 2024
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A study on the roll compaction of dry concentrated waste liquid for disposalLim, Sang-Hyun / Lee, Sang-Heon / Song, Jong-Soon / Kim, Ki-Hong et al. | 2024
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Sub-modeling numerical analysis on the radionuclide release from a transport cask submerged in the deep seaJeong, Guhyeon / Lee, Sanghoon et al. | 2024
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Next event estimation for neutron transport Monte Carlo simulations in moving objectsZhang, Huayang / Zhong, Bin / Xu, Longfei / Shen, Huayun / Li, Jinhong et al. | 2024
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Intelligent multi-severity nuclear accident identification under transferable operation conditionsXu, Song / Yao, Yuantao / Yong, Nuo / Xia, Dongqin / Ge, Daochuan / Yu, Jie et al. | 2024
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Spectrum features of the eigenvalue formulations in neutron transportAbrate, Nicolò / Dulla, Sandra / Ravetto, Piero / Saracco, Paolo et al. | 2024
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Intelligent Radiation: A review of Machine learning applications in nuclear and radiological sciencesJinia, Abbas J. / Clarke, Shaun D. / Moran, Jean M. / Pozzi, Sara A. et al. | 2024
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Development of friction factor and heat transfer correlation of liquid metal flow in helical tube bundlesShen, Cong / Liu, Maolong / Liu, Limin / Xu, Ziyi / Zeng, Chen / Liu, Li / Gu, Hanyang et al. | 2024
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Research on protection control strategy of pressurized water reactor nuclear power units for typical power system faultsWang, Haomin / Li, Muping / Sun, Peiwei / Wei, Xinyu et al. | 2024
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Numerical simulation prediction of critical heat flux for 5 × 5 rod bundle with multiple grid spacers and different cladding materialsLiu, Kexin / Li, Kejia / Mao, Yulong / Zhang, Rui / Ding, Ming / Cao, Xiaxin et al. | 2024
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Method of characteristics with a new Macro-track transport acceleration for complex general geometryJian, Guo / Guifeng, Zhu / Rui, Yan / Yang, Zou et al. | 2024