Date of download: 10/2/2017 Copyright © ASME. All rights reserved. From: Development of a Thermal-Hydraulic Analysis Code and Transient Analysis for a Fluoride-Salt-Cooled High-Temperature Test Reactor ASME J of Nuclear Rad Sci. 2015;1(1):011007-011007-7. doi:10.1115/1.4026394 Figure Legend: TMSR-SF cross-sectional view

Date of download: 10/2/2017 Copyright © ASME. All rights reserved. From: Development of a Thermal-Hydraulic Analysis Code and Transient Analysis for a Fluoride-Salt-Cooled High-Temperature Test Reactor ASME J of Nuclear Rad Sci. 2015;1(1):011007-011007-7. doi:10.1115/1.4026394 Figure Legend: Model of TMSR-SF fuel pebble

Date of download: 10/2/2017 Copyright © ASME. All rights reserved. From: Development of a Thermal-Hydraulic Analysis Code and Transient Analysis for a Fluoride-Salt-Cooled High-Temperature Test Reactor ASME J of Nuclear Rad Sci. 2015;1(1):011007-011007-7. doi:10.1115/1.4026394 Figure Legend: Relative power and mass flow rate in the UOC accident

Date of download: 10/2/2017 Copyright © ASME. All rights reserved. From: Development of a Thermal-Hydraulic Analysis Code and Transient Analysis for a Fluoride-Salt-Cooled High-Temperature Test Reactor ASME J of Nuclear Rad Sci. 2015;1(1):011007-011007-7. doi:10.1115/1.4026394 Figure Legend: Temperatures in the UOC accident

Date of download: 10/2/2017 Copyright © ASME. All rights reserved. From: Development of a Thermal-Hydraulic Analysis Code and Transient Analysis for a Fluoride-Salt-Cooled High-Temperature Test Reactor ASME J of Nuclear Rad Sci. 2015;1(1):011007-011007-7. doi:10.1115/1.4026394 Figure Legend: Temperature reactivity feedback in the UOC accident

Date of download: 10/2/2017 Copyright © ASME. All rights reserved. From: Development of a Thermal-Hydraulic Analysis Code and Transient Analysis for a Fluoride-Salt-Cooled High-Temperature Test Reactor ASME J of Nuclear Rad Sci. 2015;1(1):011007-011007-7. doi:10.1115/1.4026394 Figure Legend: Relative power and flow in the UTOP accident

Date of download: 10/2/2017 Copyright © ASME. All rights reserved. From: Development of a Thermal-Hydraulic Analysis Code and Transient Analysis for a Fluoride-Salt-Cooled High-Temperature Test Reactor ASME J of Nuclear Rad Sci. 2015;1(1):011007-011007-7. doi:10.1115/1.4026394 Figure Legend: Temperatures in the UTOP accident

Date of download: 10/2/2017 Copyright © ASME. All rights reserved. From: Development of a Thermal-Hydraulic Analysis Code and Transient Analysis for a Fluoride-Salt-Cooled High-Temperature Test Reactor ASME J of Nuclear Rad Sci. 2015;1(1):011007-011007-7. doi:10.1115/1.4026394 Figure Legend: Temperature reactivity feedback in the UTOP accident

Date of download: 10/2/2017 Copyright © ASME. All rights reserved. From: Development of a Thermal-Hydraulic Analysis Code and Transient Analysis for a Fluoride-Salt-Cooled High-Temperature Test Reactor ASME J of Nuclear Rad Sci. 2015;1(1):011007-011007-7. doi:10.1115/1.4026394 Figure Legend: Relative power and flow in the ULOF accident

Date of download: 10/2/2017 Copyright © ASME. All rights reserved. From: Development of a Thermal-Hydraulic Analysis Code and Transient Analysis for a Fluoride-Salt-Cooled High-Temperature Test Reactor ASME J of Nuclear Rad Sci. 2015;1(1):011007-011007-7. doi:10.1115/1.4026394 Figure Legend: Temperatures in the ULOF accident

Date of download: 10/2/2017 Copyright © ASME. All rights reserved. From: Development of a Thermal-Hydraulic Analysis Code and Transient Analysis for a Fluoride-Salt-Cooled High-Temperature Test Reactor ASME J of Nuclear Rad Sci. 2015;1(1):011007-011007-7. doi:10.1115/1.4026394 Figure Legend: Temperature reactivity feedback in the ULOF accident