Date of download: 10/13/2017 Copyright © ASME. All rights reserved. From: Expected Safety Performance of the Supercritical Water Reactor Fuel Qualification Test ASME J of Nuclear Rad Sci. 2015;2(1):011005-011005-9. doi:10.1115/1.4030917 Figure Legend: Cross sections of the pressure tube for the fuel qualification test: left, heated test section; right, recuperator section

Date of download: 10/13/2017 Copyright © ASME. All rights reserved. From: Expected Safety Performance of the Supercritical Water Reactor Fuel Qualification Test ASME J of Nuclear Rad Sci. 2015;2(1):011005-011005-9. doi:10.1115/1.4030917 Figure Legend: Sketch of the fuel qualification test loop and its safety systems [3]

Date of download: 10/13/2017 Copyright © ASME. All rights reserved. From: Expected Safety Performance of the Supercritical Water Reactor Fuel Qualification Test ASME J of Nuclear Rad Sci. 2015;2(1):011005-011005-9. doi:10.1115/1.4030917 Figure Legend: Coolant pressure, mass flow rates, and temperatures in the test section after a sudden break of the emergency cooling line L3 [3]

Date of download: 10/13/2017 Copyright © ASME. All rights reserved. From: Expected Safety Performance of the Supercritical Water Reactor Fuel Qualification Test ASME J of Nuclear Rad Sci. 2015;2(1):011005-011005-9. doi:10.1115/1.4030917 Figure Legend: Coolant pressure (left), mass flow rates in supply lines of the safety system, and pressure in the test section (right) after a sudden break of the feed line L1, close to the headpiece of the pressure tube [3]

Date of download: 10/13/2017 Copyright © ASME. All rights reserved. From: Expected Safety Performance of the Supercritical Water Reactor Fuel Qualification Test ASME J of Nuclear Rad Sci. 2015;2(1):011005-011005-9. doi:10.1115/1.4030917 Figure Legend: Power, mass flow rate, pressure, and coolant temperature in the test section after a trip of the recirculation pump HCC [3]

Date of download: 10/13/2017 Copyright © ASME. All rights reserved. From: Expected Safety Performance of the Supercritical Water Reactor Fuel Qualification Test ASME J of Nuclear Rad Sci. 2015;2(1):011005-011005-9. doi:10.1115/1.4030917 Figure Legend: Water temperatures inside depressurization tank BN and inside emergency reservoir HN1 as well as flow rate through pump HC3 (left). Coolant temperatures along the fuel rods over the total simulation period of 500,000 s (right) [3].

Date of download: 10/13/2017 Copyright © ASME. All rights reserved. From: Expected Safety Performance of the Supercritical Water Reactor Fuel Qualification Test ASME J of Nuclear Rad Sci. 2015;2(1):011005-011005-9. doi:10.1115/1.4030917 Figure Legend: Original (left) and modified attachment (right) of the pressure tube [8]

Date of download: 10/13/2017 Copyright © ASME. All rights reserved. From: Expected Safety Performance of the Supercritical Water Reactor Fuel Qualification Test ASME J of Nuclear Rad Sci. 2015;2(1):011005-011005-9. doi:10.1115/1.4030917 Figure Legend: Simulation of a 30-mm square fragment, total length 60 mm (dry), 70 mm (dry), and 60 mm (surrounded by water). Gray value indicates plastic strain [8].

Date of download: 10/13/2017 Copyright © ASME. All rights reserved. From: Expected Safety Performance of the Supercritical Water Reactor Fuel Qualification Test ASME J of Nuclear Rad Sci. 2015;2(1):011005-011005-9. doi:10.1115/1.4030917 Figure Legend: Lengthwise split of the pressure tube: dry (left) and surrounded by water (right, water invisible). Gray value indicates plastic strain [8].

Date of download: 10/13/2017 Copyright © ASME. All rights reserved. From: Expected Safety Performance of the Supercritical Water Reactor Fuel Qualification Test ASME J of Nuclear Rad Sci. 2015;2(1):011005-011005-9. doi:10.1115/1.4030917 Figure Legend: Coolant temperatures along the fuel rods for the first 600 s (left) and cladding temperatures during the total simulation time of 200 min (right). Inlet and outlet denote the lower and upper end of the assembly box. Segments 1–4 are in between [3].

Date of download: 10/13/2017 Copyright © ASME. All rights reserved. From: Expected Safety Performance of the Supercritical Water Reactor Fuel Qualification Test ASME J of Nuclear Rad Sci. 2015;2(1):011005-011005-9. doi:10.1115/1.4030917 Figure Legend: Progression of heating power (left) and rod centerline temperature (right) used as a basis for the source-term evaluation (right) [3]

Date of download: 10/13/2017 Copyright © ASME. All rights reserved. From: Expected Safety Performance of the Supercritical Water Reactor Fuel Qualification Test ASME J of Nuclear Rad Sci. 2015;2(1):011005-011005-9. doi:10.1115/1.4030917 Figure Legend: Source term of iodine-131: fuel rod centerline temperature and I-131 release per time step and total release with converted effective dose [3]

Date of download: 10/13/2017 Copyright © ASME. All rights reserved. From: Expected Safety Performance of the Supercritical Water Reactor Fuel Qualification Test ASME J of Nuclear Rad Sci. 2015;2(1):011005-011005-9. doi:10.1115/1.4030917 Figure Legend: Steam temperature predicted for the accident postulated in Section 3.2. Channel numbers refer to Fig. 1.