Standard Fuel Block Test to Validate Core Thermo-Fluid Analysis Code for Prismatic Gas-Cooled Reactor

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