Presentation is loading. Please wait.

Presentation is loading. Please wait.

Date of download: 9/26/2017 Copyright © ASME. All rights reserved.

Similar presentations


Presentation on theme: "Date of download: 9/26/2017 Copyright © ASME. All rights reserved."— Presentation transcript:

1 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): doi: / Figure Legend: MCNP model of the FQT test section

2 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): doi: / 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)

3 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): doi: / Figure Legend: Fuel centerline temperatures of the FQT fuel pins in 11 layers (2–12)

4 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): doi: / Figure Legend: Clad surface temperatures of the FQT fuel pins in 11 layers (2–12)

5 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): doi: / Figure Legend: Power profile calculated with GLOBUS for the LVR-15 reference core at different core arrangements

6 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): doi: / 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

7 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): doi: / 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

8 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): doi: / Figure Legend: Power curve of the FQT test section

9 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): doi: / Figure Legend: Coolant temperatures in the FQT primary loop

10 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): doi: / Figure Legend: Coolant pressures in the FQT primary loop

11 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): doi: / Figure Legend: Clad surface temperatures of the FQT fuel pins in six layers (2–12)

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): doi: / Figure Legend: Fuel centerline temperatures of the FQT fuel pins in six layers (2–12)

13 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): doi: / Figure Legend: Reactivity of the LVR-15 research reactor during ATWS

14 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): doi: / Figure Legend: Total power of the LVR-15 research reactor during ATWS

15 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): doi: / Figure Legend: Maximum fuel centerline temperatures of the FQT fuel pins during ATWS


Download ppt "Date of download: 9/26/2017 Copyright © ASME. All rights reserved."

Similar presentations


Ads by Google