ICONE29-93217 High-Precision Subchannel Model for Single and Two Phase Flow in PWR Rod Bundles With Mixing Grids

von Jiang, Li
Veröffentlicht in International Conference on Nuclear Engineering (29. : 2022 : Online) Proceedings of 2022 29th International Conference on Nuclear Engineering (ICONE 29) ; Volume 7, B (2022)

Transient Analysis Code Development for S-CO2 Brayton Cycle Based Reactor System

von Wu, Pan
Veröffentlicht in NURETH (17. : 2017 : Xi'an) 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-17) ; Volume 6 of 14 (2018)

3D Numerical Analysis on Thermal Stratification in Fast Reactor Upper Plenum by Modified RELAP5/MOD3.3 Code

von Lu, Tianyu
Veröffentlicht in NURETH (17. : 2017 : Xi'an) 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-17) ; Volume 12 of 14 (2018)

Influence Study Of Actuation Conditions of Passive Safety System on SGTR

von Yang, Zijiang
Veröffentlicht in NURETH (17. : 2017 : Xi'an) 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-17) ; Volume 10 of 14 (2018)

The Improved Spacer Grid Model and Its Application in Sub-Channel Analysis Code

von Dong, Siying
Veröffentlicht in NURETH (17. : 2017 : Xi'an) 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-17) ; Volume 5 of 14 (2018)

Development of LMFBR System Analysis Code NUSOL-LMR and Analysis of the Transient Accidents in CEFR

von Du, Peng
Veröffentlicht in NURETH (18. : 2019 : Portland, Or.) 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2019 (NURETH 2019) ; Volume 8 of 9 (2020)

Comparison of SGTR Accident for CPR1000 with Two Different Passive Residual Heat Removal Systems

von Wu, Yirui
Veröffentlicht in NURETH (17. : 2017 : Xi'an) 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-17) ; Volume 10 of 14 (2018)

ICONE29-92118 Performance Evaluation of Typical 3-Loop PWR With Annular Fuel Assemblies Under Typical Accidents

von Yang, Bowen
Veröffentlicht in International Conference on Nuclear Engineering (29. : 2022 : Online) Proceedings of 2022 29th International Conference on Nuclear Engineering (ICONE 29) ; Volume 7, A (2022)

A Bundle CHF Mechanism Model and Its Preliminary Verification Under PWR Conditions

von Liu, Yang
Veröffentlicht in NURETH (18. : 2019 : Portland, Or.) 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2019 (NURETH 2019) ; Volume 8 of 9 (2020)

ICONE29-92115 The Experimental Study on Critical Heat Flux in Vertical Eccentric Internally Heated Annuli

von Guo, Junliang
Veröffentlicht in International Conference on Nuclear Engineering (29. : 2022 : Online) Proceedings of 2022 29th International Conference on Nuclear Engineering (ICONE 29) ; Volume 7, A (2022)

ICONE28-64434 Eigenvalue Analysis of Well-Posedness of Two-Fluid Single Pressure Model With Virtual Mass Force and Interfacial Pressure

von Chao, Fei
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 (2021)

ICONE29-91764 Numerical Investigation of Melt Fragmentation in Sodium-Cooled Fast Reactor Based on Moving Particle Method

von Wang, Wenpeng
Veröffentlicht in International Conference on Nuclear Engineering (29. : 2022 : Online) Proceedings of 2022 29th International Conference on Nuclear Engineering (ICONE 29) ; Volume 8: Computational fluid dynamics (CFD) and applications (2022)

Comparison Of Different High-Resolution Spatial Discretization Schemes for Two-Fluid Seven-Equation Two-Pressure Model

von Chao, Fei
Veröffentlicht in NURETH (17. : 2017 : Xi'an) 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-17) ; Volume 10 of 14 (2018)

ICONE28-64367 Application of High Accuracy Numerical Methods for the Natural Circulation Problem

von Chao, Fei
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 (2021)

Simulation and Analysis of the Sodium-Cooled Fast Reactor Steam Generator

von Che, Zenan
Veröffentlicht in NURETH (18. : 2019 : Portland, Or.) 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2019 (NURETH 2019) ; Volume 4 of 9 (2020)

ICONE29-90825 Study on Developed Mechanism Model With R-134a CHF Experiment in Round Tubes

von Wu, Change
Veröffentlicht in International Conference on Nuclear Engineering (29. : 2022 : Online) Proceedings of 2022 29th International Conference on Nuclear Engineering (ICONE 29) ; Volume 7, A (2022)