Quenching Experiment of Cr-Alloy Accident Tolerant Cladding Under Low and High Subcooling Conditions

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

CFD Analysis of Heat Transfer in Regular and Tight-Lattice Rod Bundles with the Twist-Vane Grid

von In, Wang Kee
Veröffentlicht in NURETH (17. : 2017 : Xi'an) 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-17) ; Volume 4 of 14 (2018)

Pool Boiling and Quenching Experiments with Cr-alloy Coated Accident Tolerant Cladding

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

meng gu zu tian wen li fa shi

von bo er zhi jin · wang qi ge
Veröffentlicht 20083

AJKFIuids2015-16706 Preliminary Investigation on Convective Heat Transfer of Rod Bundle Flow With Spacer Grid for Nuclear Fuel Assembly Application

von Lee, ChiYoung
Veröffentlicht in ASME/JSME/KSME Joint Fluids Engineering Conference (2015 : 2015) Proceedings of the ASME/JSME/KSME Joint Fluids Engineering Conference - 2015 ; Volume 1A (2016)