Transient Subchannel Analvsis of BWR Fuel Thermal Hvdraulic Performance

von Hizoum, B.
Veröffentlicht in NURETH (18. : 2019 : Portland, Or.) 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2019 (NURETH 2019) ; Volume 5 of 9 (2020)

Application of the COBRAG Subchannel Code to Fuel Design

von Oh, S.
Veröffentlicht in NURETH (18. : 2019 : Portland, Or.) 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2019 (NURETH 2019) ; Volume 5 of 9 (2020)