POD Analysis of the Shell-Side Local Flow in a Five-Rod Helical Coil Steam Generator

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

Differences in Experimental Friction Factors Across Two Model Helical Coil Steam Generators

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

High-Fidelity Simulation of Flow Induced Vibrations in Helical Steam Generators for Small Modular Reactors............................

von Merzari, Elia
Veröffentlicht in NURETH (17. : 2017 : Xi'an) 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-17) ; Volume 1 of 14 (2018)