ICONE29-93350 Experimental Study on Condensation Heat Transfer Characteristics of Vertical Surface Chromium-Plated Tube With Condensate Gas

von Hou, Xiaofan
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)

ICONE29-93372 A Study on the Steady-State Flow Behavior of the Boiling-Driven Open Natural! Circulation System

von Hou, Xiaofan
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)

ICONE28-66338 Experimental Simulation of Transitions Between Forced Circulation and Natural Circulation With Nuclear Reactivity Feedback

von Chen, Hanying
Veröffentlicht in International Conference on Nuclear Engineering (28. : 2021 : Online) Proceedings of 2021 28th International Conference on Nuclear Engineering (ICONE 28) ; Volume 1: Operating plant challenges, successes, and lessons learned; nuclear plant engineering; advanced reactors and fusion; small modular and micro-reactors technologies and applications (2021)

ICONE29-90219 Automatic Scram Forecasting During Abnormal Conditions of Nuclear Power Plants Based on LSTM

von Chen, Hanying
Veröffentlicht in International Conference on Nuclear Engineering (29. : 2022 : Online) Proceedings of 2022 29th International Conference on Nuclear Engineering (ICONE 29) ; Volume 3: I & C, digital control, and influence of human factors (2022)

The Study of the Natural Circulation Influenced by Combined Earthquake Based on MATLAB

von Zhang, Yinxing
Veröffentlicht in NURETH (17. : 2017 : Xi'an) 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-17) ; Volume 13 of 14 (2018)

An Experimental Investigation on Flow Reversal Under Natural Circulation Flow Instability Conditions

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