ICONE28-65776 Research on Application of Additive Manufacturing Technology In Nuclear Fuel Assembly Field

ICONE28-65776 Research on Application of Additive Manufacturing Technology In Nuclear Fuel Assembly Field

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Veröffentlicht in:International Conference on Nuclear Engineering (28. : 2021 : Online) Proceedings of 2021 28th International Conference on Nuclear Engineering (ICONE 28) ; Volume 2: Nuclear fuels, research, and fuel cycle; nuclear codes and standards; thermal-hydraulics
1. Verfasser: Li, Hua (VerfasserIn)
Weitere Verfasser: Yue, Ti (VerfasserIn), Zhu, Fawen (VerfasserIn), Peng, Yuan (VerfasserIn), Li, Yun (VerfasserIn), Huang, Chunlan (VerfasserIn), Zhang, Youjia (VerfasserIn)
Pages:2021 28
Format: UnknownFormat
Sprache:eng
Veröffentlicht: 2021
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Titel Jahr Verfasser
ICONE28-63101 Steady-State Performance Analysis of a Dual-Cladding Design for Accident Tolerance Fuel 2021 Deng, Qianliang
ICONE28-64154 Sensitivity Study on TRISO Fuel Failure Probability Evaluation for HTGR 2021 Li, Jian
ICONE28-64684 Experimental Study on Edge Blockage Accidents in a Narrow Rectangular Channel 2021 Yuan, Dongdong
ICONE28-65840 Evaluation of Interface Stresses and Cladding-Cladding Delamination Failures In U-Mo Fuel Plates ICONE28-66589 . ; 2021 Ozaltun, Hakan
ICONE28-64692 Research on Quality Assurance of Raw Materials for Nuclear Power Equipment 2021 Pu, Chenghao
ICONE28-60406 Void Fraction Measurement and Prediction of Two-Phase Boiling Flows in a Tubular Test Section 2021 Liu, Qingging
ICONE28-63380 Core Thermal-Hydraulic Analysis During Dipped-Type Direct Heat Exchanger Operation in Natural Circulation Conditions 2021 Hamase, Erina
ICONE28-63381 Numerical Simulation of Vortex Shedding Downstream of a Thermoacoustic Engine Stack 2021 Qiao, Bowen
ICONE28-64252 Aerosol Removal by a Heat Exchanger of Passive Containment Cooling System 2021 Liang, Yangyang
ICONE28-64169 Codes and Methods Improvements for VVER Comprehensive Safety Assessment: The CAMIVVER H2020 Project 2021 Verrier, Denis
ICONE28-64434 Eigenvalue Analysis of Well-Posedness of Two-Fluid Single Pressure Model With Virtual Mass Force and Interfacial Pressure 2021 Chao, Fei
ICONE28-64607 A Numerical Study of Supersonic Film Cooling With Discrete Holes 2021 Ni, Hang
ICONE28-65575 Design of a Novel Test Section for the Lead Fast Reactors Development: The CIRCE-THETIS Facility 2021 Lorusso, Pjerdomenico
ICONE28-65596 Study on Water Cooler Performance for High Temperature Helium Experimental System 2021 Hu, Qingxiang
ICONE28-66257 Applicability Assessment of Accident Analysis Codes and Determination of Testing Facility for Validation of the CAP 1400 2021 Cai, Xiaoyu
ICONE28-61765 Development of Cesium Trap Material for Coated Fuel Particles in High Temperature Gas-Cooled Reactors 2021 Sasaki, K.
ICONE28-63354 Study on the Applicability of Typical Valve Failure Data to Non-Reactor Nuclear Fuel Cycle Front-End Facilities 2021 Lyu, Dan
ICONE28-64250 Feasibility Study of Disassembly Technologies of Fast Reactor Fuel Assembly 2021 Nishikawa, Hidetsugu
ICONE28-65563 Modeling of Irradiation-Induced Thermo-Mechanical Coupling Behavior in Metal Matrix Microencapsulated Fuel 2021 Wei, Hongyang
ICONE28-64761 Study on Aging Management of Operating Nuclear Power Plants in China 2021 Liang, Li
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