VERIFICATION OF THE ENDF/B-VII.1 AND VIII.0 AMPX 1597-GROUP LIBRARIES FOR ADVANCED REACTOR ANALYSIS

von Kim, Kang Seog
Veröffentlicht in International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (2019 : Portland, Or.) International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M & C 2019) ; Volume 4 of 4 (2019)

SAMPLING-BASED UNCERTAINTY QUANTIFICATION OF THE SIX-GROUP KINETIC PARAMETERS

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

Molten Salt Reactor Fuel Depletion Tools in SCALE

von Betzler, Benjamin R.
Veröffentlicht in International Nuclear Fuel Cycle Conference (2019 : Seattle, Wash.) International Nuclear Fuel Cycle Conference (GLOBAL 2019) ; Volume 2 of 2 (2020)