Interfacial Condensation Heat Transfer For Countercurrent Steam-Water Stratified Flow In A Circular Pipe

von CHUN, M. H.
Veröffentlicht in International Topical Meeting on Nuclear Reactor Thermal Hydraulics (9 : 1999 : San Francisco, Calif.) Ninth International Topical Meeting on Nuclear Reactor Thermal Hydraulics 1999 (NURETH-9) ; Volume 4 of 5 (2022)

MARS-KS Code Assessment on LOCA Test in Pressurized Water Loop Facility of PHWR

von Yu, S. O.
Veröffentlicht in NURETH (18. : 2019 : Portland, Or.) 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2019 (NURETH 2019) ; Volume 7 of 9 (2020)