SALIENT-03: Irradiation of Molten Salt Fuel in Ni-Based Alloy Capsules at the High Flux Reactor

von D’Agata, E.
Veröffentlicht in International Nuclear Fuel Cycle Conference (2019 : Seattle, Wash.) International Nuclear Fuel Cycle Conference (GLOBAL 2019) ; Volume 1 of 2 (2020)

Design and Safety Support Analyses of an in-pile Molten Salt Loop in the HFR with the SPECTRA Code

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

SALIENT-01: Preparation and Start of Irradiation of Thorium-Bearing Molten Fluoride Salt in Graphite Crucibles

von Hania, P. R.
Veröffentlicht in International Nuclear Fuel Cycle Conference (2019 : Seattle, Wash.) International Nuclear Fuel Cycle Conference (GLOBAL 2019) ; Volume 1 of 2 (2020)