ICONE29-91535 Heating Start-Up Method and Demonstration for Full Natural Circulation Reactor

ICONE29-91535 Heating Start-Up Method and Demonstration for Full Natural Circulation Reactor

Gespeichert in:
Bibliographische Detailangaben
Veröffentlicht in:International Conference on Nuclear Engineering (29. : 2022 : Online) Proceedings of 2022 29th International Conference on Nuclear Engineering (ICONE 29) ; Volume 4: SMRS, advanced reactors, and fusion
1. Verfasser: Yu, Jianhui (VerfasserIn)
Weitere Verfasser: Tan, Wenji (VerfasserIn), Zhang, Xingliang (VerfasserIn)
Pages:2022 29
Format: UnknownFormat
Sprache:eng
Veröffentlicht: 2022
Schlagworte:
Tags: Tag hinzufügen
Keine Tags, Fügen Sie den ersten Tag hinzu!
Titel Jahr Verfasser
ICONE29-90511 Optimization of Core Parameters Based on Artificial Neural Network Surrogate Model 2022 Chen, Shu
ICONE29-90643 Modeling and Analysis of Tritium Fuel Cycle for Magnetic Confinement Fusion Reactor 2022 Xu, Jinggang
ICONE29-91505 Event Tree Analysis for Material Relocation on Core Catcher in a Sodium-Cooled Fast Reactor 2022 Yamano, Hidemasa
ICONE29-91511 Study on Radioactive Inventory, Accident Source Term and Offsite Dose Consequence of DHR400 Under Fuel Handling Accident and Core Damage Accident 2022 Wang, Fenglong
ICONE29-91546 Design and Comparison of Drainage Technology Scheme for Multi-Purpose Modular Small Reactor Science and Technology Demonstration Project 2022 Yujia, Mao
ICONE29-91857 Optimization in Heat Transfer Scheme for Load Rejection and Emergency Shutdown Conditions of Sodium Fast Reactor 2022 Yu, Yang
ICONE29-92077 The Research of the Customer Needs of a Type of Innovative Lead-Bismuth Fast Reactor Base on the TRIZ Method 2022 Yuan, Weiquan
ICONE29-92284 Numerical Analysis of Simple Heat Equation to Predict the Opening Time of the Freeze Plug in Moiten Salt Reactors 2022 IIham, Muhammad
ICONE29-92790 Research on Sensing Value Reconstruction Method of Small Modular Reactor Based on Improved Short-Term and Long-Term Memory Neural Network 2022 Cheng, Shouyu
ICONE29-92917 Thermal-Hydraulic Analysis of HL-2M Cooling Water System for Toroidal Field Coils 2022 Wang, Jiaqgi
ICONE29-93231 Structural Analysis of a Reactor Vessel in a Sodium-Cooled Fast Reactor Under Extremely High Temperature Conditions 2022 Yamano, Hidemasa
ICONE29-93407 Criticality Study of Spent Fuel Storage Rack of Ship-Based Small Modular Reactor 2022 Ye, Yaoxin
ICONE29-89180 Research on Deposition Performance of Fine Particles of Heat Pipe in Small Reactor 2022 Liu, Xiaofang
ICONE29-90528 Comprehensive Comparison and Analysis for Fast Reactors 2022 Yan, Zheng
ICONE29-90903 Pre-Conceptual Core Design of a Micro-LBE-Cooled Fast Reactor 2022 Yeoh, Eing Yee
ICONE29-91688 Evaluation of Detectability of Pump/Diagrid Link Rupture in Pool-Type Sodium- Cooled Fast Reactor 2022 Onoda, Yuichi
JICONE29-91821 Assessment of Passive Cooling Capability of the Westinghouse Lead Fast Reactor Under Station Blackout Conditions 2022 Tatli, Emre
ICONE29-92063 Study on Steady Operational Characteristics of Floating Nuclear Reactor Under Ocean Condition 2022 Cheng, Kun
ICONE29-92567 Simulation of One-Dimensional Nuclear-Pumped Laser Generation System Based or Modelica Language 2022 Tang, Xiang
ICONE29-92516 Study on Flow and Heat Transfer Performance of Space Reactor Radiator Water Heat Pipe 2022 Jiao, Suanghuf
Alle Artikel auflisten