Date of download: 9/26/2017 Copyright © ASME. All rights reserved. From: Control Rod Withdrawal Analysis of the Supercritical Water Reactor-Fuel Qualification Test Facility in the LVR-15 Research Reactor ASME J of Nuclear Rad Sci. 2015;2(1):011004-011004-5. doi:10.1115/1.4030933 Figure Legend: MCNP model of the FQT test section

Date of download: 9/26/2017 Copyright © ASME. All rights reserved. From: Control Rod Withdrawal Analysis of the Supercritical Water Reactor-Fuel Qualification Test Facility in the LVR-15 Research Reactor ASME J of Nuclear Rad Sci. 2015;2(1):011004-011004-5. doi:10.1115/1.4030933 Figure Legend: MCNP model of the LVR-15 core with numbered core arrangement: control rods (1–8), automatic rod (9), and safety rods (10–12)

Date of download: 9/26/2017 Copyright © ASME. All rights reserved. From: Control Rod Withdrawal Analysis of the Supercritical Water Reactor-Fuel Qualification Test Facility in the LVR-15 Research Reactor ASME J of Nuclear Rad Sci. 2015;2(1):011004-011004-5. doi:10.1115/1.4030933 Figure Legend: Fuel centerline temperatures of the FQT fuel pins in 11 layers (2–12)

Date of download: 9/26/2017 Copyright © ASME. All rights reserved. From: Control Rod Withdrawal Analysis of the Supercritical Water Reactor-Fuel Qualification Test Facility in the LVR-15 Research Reactor ASME J of Nuclear Rad Sci. 2015;2(1):011004-011004-5. doi:10.1115/1.4030933 Figure Legend: Clad surface temperatures of the FQT fuel pins in 11 layers (2–12)

Date of download: 9/26/2017 Copyright © ASME. All rights reserved. From: Control Rod Withdrawal Analysis of the Supercritical Water Reactor-Fuel Qualification Test Facility in the LVR-15 Research Reactor ASME J of Nuclear Rad Sci. 2015;2(1):011004-011004-5. doi:10.1115/1.4030933 Figure Legend: Power profile calculated with GLOBUS for the LVR-15 reference core at different core arrangements

Date of download: 9/26/2017 Copyright © ASME. All rights reserved. From: Control Rod Withdrawal Analysis of the Supercritical Water Reactor-Fuel Qualification Test Facility in the LVR-15 Research Reactor ASME J of Nuclear Rad Sci. 2015;2(1):011004-011004-5. doi:10.1115/1.4030933 Figure Legend: Predicted power profile in the FQT test-section. GLOBUS burn-up calculation for the LVR-15 reference core with 30% burnt IRT-4M assemblies next to the FQT section

Date of download: 9/26/2017 Copyright © ASME. All rights reserved. From: Control Rod Withdrawal Analysis of the Supercritical Water Reactor-Fuel Qualification Test Facility in the LVR-15 Research Reactor ASME J of Nuclear Rad Sci. 2015;2(1):011004-011004-5. doi:10.1115/1.4030933 Figure Legend: GLOBUS burn-up calculation for the LVR-15 reference core with 30% burnt IRT-4M assemblies next to the FQT section. Critical control rod positions in the LVR-15 core

Date of download: 9/26/2017 Copyright © ASME. All rights reserved. From: Control Rod Withdrawal Analysis of the Supercritical Water Reactor-Fuel Qualification Test Facility in the LVR-15 Research Reactor ASME J of Nuclear Rad Sci. 2015;2(1):011004-011004-5. doi:10.1115/1.4030933 Figure Legend: Power curve of the FQT test section

Date of download: 9/26/2017 Copyright © ASME. All rights reserved. From: Control Rod Withdrawal Analysis of the Supercritical Water Reactor-Fuel Qualification Test Facility in the LVR-15 Research Reactor ASME J of Nuclear Rad Sci. 2015;2(1):011004-011004-5. doi:10.1115/1.4030933 Figure Legend: Coolant temperatures in the FQT primary loop

Date of download: 9/26/2017 Copyright © ASME. All rights reserved. From: Control Rod Withdrawal Analysis of the Supercritical Water Reactor-Fuel Qualification Test Facility in the LVR-15 Research Reactor ASME J of Nuclear Rad Sci. 2015;2(1):011004-011004-5. doi:10.1115/1.4030933 Figure Legend: Coolant pressures in the FQT primary loop

Date of download: 9/26/2017 Copyright © ASME. All rights reserved. From: Control Rod Withdrawal Analysis of the Supercritical Water Reactor-Fuel Qualification Test Facility in the LVR-15 Research Reactor ASME J of Nuclear Rad Sci. 2015;2(1):011004-011004-5. doi:10.1115/1.4030933 Figure Legend: Clad surface temperatures of the FQT fuel pins in six layers (2–12)

Date of download: 9/26/2017 Copyright © ASME. All rights reserved. From: Control Rod Withdrawal Analysis of the Supercritical Water Reactor-Fuel Qualification Test Facility in the LVR-15 Research Reactor ASME J of Nuclear Rad Sci. 2015;2(1):011004-011004-5. doi:10.1115/1.4030933 Figure Legend: Fuel centerline temperatures of the FQT fuel pins in six layers (2–12)

Date of download: 9/26/2017 Copyright © ASME. All rights reserved. From: Control Rod Withdrawal Analysis of the Supercritical Water Reactor-Fuel Qualification Test Facility in the LVR-15 Research Reactor ASME J of Nuclear Rad Sci. 2015;2(1):011004-011004-5. doi:10.1115/1.4030933 Figure Legend: Reactivity of the LVR-15 research reactor during ATWS

Date of download: 9/26/2017 Copyright © ASME. All rights reserved. From: Control Rod Withdrawal Analysis of the Supercritical Water Reactor-Fuel Qualification Test Facility in the LVR-15 Research Reactor ASME J of Nuclear Rad Sci. 2015;2(1):011004-011004-5. doi:10.1115/1.4030933 Figure Legend: Total power of the LVR-15 research reactor during ATWS

Date of download: 9/26/2017 Copyright © ASME. All rights reserved. From: Control Rod Withdrawal Analysis of the Supercritical Water Reactor-Fuel Qualification Test Facility in the LVR-15 Research Reactor ASME J of Nuclear Rad Sci. 2015;2(1):011004-011004-5. doi:10.1115/1.4030933 Figure Legend: Maximum fuel centerline temperatures of the FQT fuel pins during ATWS