ICONE29-89241 Validation of NUIT for Decay Heat Predictions of PWR Spent Fuel Assemblies

ICONE29-89241 Validation of NUIT for Decay Heat Predictions of PWR Spent Fuel Assemblies

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 2: Nuclear fuel and material, reactor physics and transport theory, fuel cycle technology
1. Verfasser: Li, Jian (VerfasserIn)
Weitere Verfasser: Li, Ruihan (VerfasserIn), She, Ding (VerfasserIn), Liang, Jin’gang (VerfasserIn), Shi, Lei (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
ICONE29-90325 Microstructural Evolution of SiC-Coated C/C Composites Under Argon Ion Irradiation 2022 Xie, Xiangmin
ICONE29-90718 Effect of Surface Treatment on the Corrosion Behavior of Stainless Steels in High- Temperature Supercritical Carbon Dioxide 2022 Liu, Zhu
ICONE29-90736 Hydrogenation of Zircaloy-4 in a Defective Fuel Pellet for Pressurized Water Reactors 2022 Enivweru, Doctor
ICONE29-90802 Preparation Method of ORIGEN2 Library for High Temperature Gas-Cooled Reactors 2022 Simanullang, Irwan Liapto
ICONE29-90835 The Wear and General Corrosion Properties of Low-Temperature Plasma Nitrided 17- 4PH Stainless Steel With a Work-Hardened Sublayer 2022 Han, Zhongli
ICONE29-90902 Study on Selection Method of Shielding Nuclides in Nuclear Reactor Based on Non- Dominated Sorting 2022 Li, Rui
ICONE29-91399 Development and Verification of Multigroup Cross Section Generation Module GroupXS in AXSP 2022 Hu, Kui
ICONE29-91726 Numerical Simulation of Reactor Neutron Noise Based on Discrete Ordinate Finite Element Method 2022 Yuan, Baoxin
ICONE29-91817 Multiphysics Thermo-Mechanical Behavior Modeling for Annular Uranium-Plutonium Mixed Oxide Fuels in a Lead-Cooled Fast Reactor 2022 Cal, Yutai
ICONE29-91804 Numerical Simulation Analysis of Silicon Carbide Whiskers Doped Uranium Dioxide Composite Fuel for High Thermal Conductivity 2022 Lu, Linyuan
ICONE29-92210 Research Progress of Neutron Shielding Materials 2022 Chang, Bing
ICONE29-92757 Research on Establishing Efficient Scheduling System of Spent Fuel From Chinese Nuclear Power Plants 2022 Su, Jiqiang
ICONE29-93196 Study on Synthesis of the Organophosphorus Functionalized MCM-41 And its Adsorption Property for Dy(Ill) 2022 Mao, Cong
ICONE29-93351 PWR Spent Fuel Dry Storage Loading Pattern and Safety Evaluation 2022 Wen, Li
ICONE29-88944 A Bi-Layered Three-Dimensional Mechanical Modeling of the Cladding and Its Creep Deformation Analysis 2022 Zhang, Ming
ICONE29-90557 Automation of High-Fidelity Modeling of PWR Fuel Rods and Verification 2022 Chunyu, Zhang
ICONE29-90755 Research on Cracked Fuel Relocation of Dual-Cooled Annular Fuel Element Under Normal and LOCA Conditions 2022 Deng, Yangbin
ICONE29-92625 Structural Design and Dynamic Analysis of the Heat Exchanger Used in Nuclear Fuel Test Loop 2022 Gang, Huang
ICONE29-92858 Effects of Stoichiometry and High-Temperature Annealing on Zirconium Carbide Coating Layer in TRISO Particles 2022 Cheng, Xinyu
ICONE29-92971 Study on Separation of Palladium From High Level Liquid Waste by Potassium Manganese Ferrocyanide 2022 Qi, Tianming
Alle Artikel auflisten