Validation and Benchmarking of CTF for Single- and Two-Phase Flow using VIPRE-01

von Zhao, Xingang
Veröffentlicht in NURETH (17. : 2017 : Xi'an) 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-17) ; Volume 11 of 14 (2018)

EVALUATION OF VERA-CS TRANSIENT CAPABILITY FOR ANALYZING THE AP1000® REACTOR CONTROL ROD EJECTION ACCIDENT

von Kucukboyaci, Vefa N.
Veröffentlicht in PHYSOR (2018 : Cancún) Reactor physics paving the way towards more efficient systems ; Volume 1 of 6 (2020)

WHOLE CORE CRUD-INDUCED POWER SHIFT SIMULATIONS USING VERA

von Collins, Benjamin
Veröffentlicht in PHYSOR (2018 : Cancún) Reactor physics paving the way towards more efficient systems ; Volume 6 of 6 (2020)