Remaining Issues in System Thermal Hydraulics How the Fonesys and CONUSAF Networks Can Help Find Solutions?

von Bestion, D.
Veröffentlicht in NURETH (18. : 2019 : Portland, Or.) 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2019 (NURETH 2019) ; Volume 6 of 9 (2020)

A General Method Of Predicting Critical Heat Flux (CHF) In Advanced Water-Cooled Reactors (AWCRs)

von GROENEVELD, D. C.
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)

Critical Flow Prediction by System Codes—Recent Analyses Made Within The FONESYS Network

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