Suppression Pool Thermal-Hydraulics Preliminary Analysis of Fukushima Daiichi Unit-2 Using Pool-3D Module of SAMPSON Code

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

Preliminary Ex-Vessel Sensitivity Study of Fukushima Dai-ichi Unit 1 Using DSA1 and CVPA Coupling Modules of the Sampson Code

von Giuli, Mirco Di
Veröffentlicht in NURETH (17. : 2017 : Xi'an) 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-17) ; Volume 12 of 14 (2018)