Development of a SCDAP/RELAPS Model for the Simulation of the Helical-Coiled Once-Through Steam Generators

von Xu, Ziyi
Veröffentlicht in NURETH (18. : 2019 : Portland, Or.) 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2019 (NURETH 2019) ; Volume 6 of 9 (2020)

ICONE29-91911 Numerical Investigations of the LBE Flow and Heat Transfer Characteristics in the Helical-Coiled Tube Bundle

von Shen, Cong
Veröffentlicht in International Conference on Nuclear Engineering (29. : 2022 : Online) Proceedings of 2022 29th International Conference on Nuclear Engineering (ICONE 29) ; Volume 15: Student paper competition (2022)

ICONE29-93035 Development of a 1d Code for Heat Transfer Characteristics of Helical-Coiled Once- Through Steam Generators

von Liu, Maolong
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)

Surface Wettability Measurements of Fecral Alloys Under LWR Environments

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