Multi-scale Thermal Hydraulic Analysis of the EBR-II Loss of Flow Tests SHRT-17 and SHRT-45R

von Stempniewicz, M. M.
Veröffentlicht in NURETH (17. : 2017 : Xi'an) 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-17) ; Volume 9 of 14 (2018)

A New Method to Simulate Circulating Liquid Fuel Systems 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)

Analysis of the DVI Line Break Accident of the Westinghouse SMR with SPECTRA, MELCOR and RELAP System Codes

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

GEMINI+ Design Options for HTGR Fitting the Requirements for Cogeneration Use in Europe

von Lavarenne, J.
Veröffentlicht in International Nuclear Fuel Cycle Conference (2019 : Seattle, Wash.) International Nuclear Fuel Cycle Conference (GLOBAL 2019) ; Volume 2 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)