Neural-network-based reconstruction of spent-fuel radioactive distribution in nuclear waste cask (English)
- New search for: Liu, Zhihao
- New search for: Wu, Ying
- New search for: Chen, Hui
- New search for: Li, Yudan
- New search for: Liu, Zhihao
- New search for: Wu, Ying
- New search for: Chen, Hui
- New search for: Li, Yudan
In:
Annals of Nuclear Energy
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197
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2023
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ISSN:
- Article (Journal) / Electronic Resource
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Title:Neural-network-based reconstruction of spent-fuel radioactive distribution in nuclear waste cask
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Contributors:
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Published in:Annals of Nuclear Energy ; 197
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Publisher:
- New search for: Elsevier Ltd
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Publication date:2023-11-23
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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 197
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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Time-dependent leakage model for the identification of defective fuel assemblies of VVER-type nuclear reactors. Part 2: Expediting the solution and applications to a nuclear power plantKristóf Szarvas, Csongor / Radócz, Gábor / Gerényi, Anita / Szabados, György / Pintér, Tamás / Rozmanitz, Péter / Kirchknopf, Péter / Szalóki, Imre et al. | 2023
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Fragility evaluation of nuclear containment structure subjected to earthquake and subsequent internal pressureJin, Song / Jiang, Di / Wang, Dongmei / Wang, Shaojie / Wang, Zhen et al. | 2023
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Integration of Level 3 probabilistic risk assessment for nuclear power plants with transportation simulation considering earthquake hazardsShimada, Kazumasa / Sakurahara, Tatsuya / Farshadmanesh, Pegah / Reihani, Seyed / Mohaghegh, Zahra et al. | 2023
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Inverse method study based on Characteristic Statistic Algorithm (CSA) with application in estimating core states parametersQian, Zhang / ZhiHong, Liu / Jing, Zhao et al. | 2023
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Study on reduction of pressure oscillation in low-velocity steam jet condensationCao, An / Hua, Yongzhen / Sun, Zhongning / Meng, Zhaoming / Guo, Zehua / Zhang, Nan et al. | 2023
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CFD assessment of RANS turbulence modeling for solidification in internal flows against experiments and higher fidelity LBM-LES phase change modelFreile, Ramiro / Tano, Mauricio E. / Ragusa, Jean C. et al. | 2023
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Prediction of state transitions in 3D core dynamics and xenon transients based on dynamic mode decompositionLi, Wenhuai / Peng, Sitao / Li, Jinggang / He, Qingyun / Wang, Tao / Zhang, Yijun / Lu, Haoliang / Wang, Ting / Ding, Peng et al. | 2023
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On the need for multi-dimensional models for the safety analysis of (fast-spectrum) Molten Salt ReactorsHabtemariam, Nahom / Fiorina, Carlo / Lorenzi, Stefano / Cammi, Antonio et al. | 2023
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Preliminary analysis of maximum hypothetical accident for a solid core space nuclear reactor power systemLi, Ge / Huaqi, Li / Jianqiang, Shan / Xinbiao, Jiang et al. | 2023
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Preliminary conceptual design with neutronics and thermal-hydraulics assessments of FuSTARZhou, Xingguang / Zhang, Dalin / Li, Xinyu / Lv, Xindi / Jiang, Dianqiang / Tian, Wenxi / Qiu, Suizheng et al. | 2023
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Numerical analysis of fluid force on orifice structure of valve disc for nuclear globe valveZhang, Ao / Li, Qingye / Zong, Chaoyong / Liu, Fuwen / Xue, Tianhang / Xiao, Jian / Song, Xueguan et al. | 2023
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Towards modelling defective fuel rods in TRANSURANUS: Benchmark and assessment of gaseous and volatile radioactive fission product releaseGiaccardi, L. / Cherubini, M. / Zullo, G. / Pizzocri, D. / Magni, A. / Luzzi, L. et al. | 2023
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A new strategy for validating transient neutronic solver using the measurement data during the dynamic rod worth measurement processBai, Jiahe / Zhang, Shengbin / Wang, Kunpeng / Wan, Chenghui / Wu, Hongchun et al. | 2023
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A numerical investigation of subcooled flow boiling heat transfer in twisted elliptical tubesDi, Xichao / Zhou, Meihui / Tao, Ping / Zhou, Jianqiu et al. | 2023
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Gas phase interactions between tellurium and organic material in severe nuclear accident scenariosPasi, Anna-Elina / Kärkelä, Teemu / Börjesson Sandén, Fredrik / Tapper, Unto / Kajolinna, Tuula / Ekberg, Christian et al. | 2023
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Experimental investigation of thermal stratification development in boiling water reactor suppression pools during reactor core isolation cooling system operationKeesling, Dallin / Kirkland, Karen et al. | 2023
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Estimation of weight window parameters based on recursive Monte Carlo approach for reactor shielding problemsYadav, Pratibha / Rachamin, Reuven / Konheiser, Jörg / Baier, Silvio et al. | 2023
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Health state identification of circulating seawater pump-unit in nuclear power plant based on multi-virtual vibration source fusion in the presence of strong data imbalanceLiu, Song / Xiong, Xin / Huang, Yuanyuan / Chang, Zhengke / He, Jun / Yang, Shixi et al. | 2023
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Heat transfer in the argon space of pool-type sodium-cooled fast reactor: Numerical simulation and experimental validationLu, Daogang / Feng, Jiaqi / Yu, Zongyu / Wang, Han / Zhang, Yuhao et al. | 2023
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Nuclear material accountancy using momentum-informed muon scattering tomographyBae, JungHyun / Montgomery, Rose / Chatzidakis, Stylianos et al. | 2023
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A critical heat flux model for IVR-ERVC application based on the experimental observationGang, Wang / Bo, Kuang / Yu, Zhao / Shilei, Han / Pengfei, Liu / Jieming, Hou et al. | 2023
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A simulation study of tritium distribution in a 10WM(e) thorium-based molten salt reactorZeng, You-shi / Zhang, Qin / Deng, Ke / Liu, Wei et al. | 2023
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The deterministic neutron transport calculation for the HTR-PM by the three-dimensional method of characteristics code ARCHERZhu, Kaijie / Dou, Qinrong / Zhang, Han / Kong, Boran / Liu, Zhaoyuan / Guo, Jiong / Li, Fu et al. | 2023
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Angular distribution uncertainty influence in a large sodium-cooled fast reactor with mixed-oxide fuelRyzhkov, Alexander A. / Tikhomirov, Georgy V. / Ternovykh, Mikhail Yu. et al. | 2023
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A predictor–corrector Monte Carlo method for thermal radiative transfer equationsShi, Yi / Xie, Hui et al. | 2023
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CFD analysis of coolant mixing in VVER-1000/V320 reactor pressure vesselBöttcher, M. / Bernard, O. / Mas, A. / Sanchez, V. / Nop, R. / Belaunde, F. / Bourcier, C. / Ruban, D. / Hashymov, A. / Halim, O. et al. | 2023
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Development of cyber risk analysis framework for core computational system of TRIGA reactor using graded approachVechgama, Wasin / Dararutana, Chotika / Pechrak, Anantachai / Wetchagarun, Saensuk / Sasawattakul, Watcha / Silva, Kampanart et al. | 2023
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State space modelling development of Micro-High-Temperature Gas-Cooled reactor with helium Brayton cycleQiu, Leilei / Fan, Sui / Liao, Shengyong / Sun, Peiwei / Wei, Xinyu et al. | 2023
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Accuracy analysis of RANS turbulent models on predicting thermal stratification in the SUPERCAVNA facilityLi, Wenbo / Bai, Yunqing / Zhang, Shuai / Li, Yang / Jin, Ming / Li, Chunjing et al. | 2023
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Neural-network-based reconstruction of spent-fuel radioactive distribution in nuclear waste caskLiu, Zhihao / Wu, Ying / Chen, Hui / Li, Yudan et al. | 2023
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Editorial Board| 2024
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Numerical simulation of tritium extraction from liquid PbLi by gas–liquid contactorJiang, Kecheng / Yang, Jinzhao / Zhao, Xueli / Chen, Lei / Gou, Fujun / Liu, Songlin et al. | 2023