1 LOCA/LOFA Analyses for LiPb/FS System Carl Martin, Jake Blanchard Fusion Technology Institute University of Wisconsin - Madison ARIES-CS Project Meeting.

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ACT1 LOFA model updates and LOCA analyses

Presentation transcript:

1 LOCA/LOFA Analyses for LiPb/FS System Carl Martin, Jake Blanchard Fusion Technology Institute University of Wisconsin - Madison ARIES-CS Project Meeting November 4-5, 2004

2 LOCA/LOFA Analysis Update 1.Description of the thermal models, boundary conditions, and assumptions used for the LOCA/LOFA analyses. 2.Update of results presented previously to include plasma / nuclear heating for 3 seconds after loss of coolant. 3.LOCA/LOFA analysis with new Li/Pb afterheat data. 4.Modeling in progress to include support structure.

3 LiPb/FS/He Radial Build (Water Cooled Internal VV) SOL Vacuum Vessel FS Shield Gap Thickness (cm) FW Gap + Th. Insulator Winding Pack Plasma ≥  ≥ 149 cm | | Coil Case & Insulator Blanket (LiPb/FS/He) 47 Back Wall 9 1 Gap External Structure 18 These LOCA/LOFA analyses assume perfect insulation between the vacuum vessel ant the coil case, i.e. no heat loss. Also, no support structure in gaps included.

4 ANSYS FE Model and Boundary Conditions for Thermal Analyses BlanketShieldVacuum Vessel First Wall T init = 500 C LiPB T init = 625 C Back Wall T init = 450 C Shield T init = 450 C Vacuum Vessel T init = 100 C Gap Radius = 2.0 m Ferritic SteelBoronated Ferritic Steel LiPb H20H20H20H20H20H20 Adiabatic boundary at back of vacuum vessel Model is axisymmetric about plasma centerline and symmetric on sides Emissivity of 0.3 assumed across vacuum gaps and vacated cooling channels All analyses assume there is no helium in channels

5 Analyses without LiPb in Blanket Including Surface and Nuclear Heating BlanketShieldVacuum Vessel First Wall T init = 500 C Back Wall T init = 450 C Shield T init = 450 C Vacuum Vessel T init = 100 C Gap Radius = 2.0 m SiC liner Surface and nuclear heating continues for three seconds after loss of coolant First case assumes loss of all coolants – complete LOCA

6 Complete LOCA Thermal Response Long Term Response (10 Days) Short Term Effect of Surface Heating (600 sec.) Without coolant or heat loss, temperature continues to rise. Surface and nuclear heating have little long term effect. Long term temperature rise increases by 0.2 C. First peak temperature increases by 2.6 C. First peak (3.6 hr) Temperature spikes 100 C at 1 st wall due to surface heating at 3 sec.

7 LOCA in Blanket and Shield LOFA in Vacuum Vessel SiC liner BlanketShieldVacuum Vessel First Wall T init = 500 C Back Wall T init = 450 C Shield T init = 450 C Vacuum Vessel T init = 100 C Gap Radius = 2.0 m Natural convection to water in vacuum vessel assumed Heat transfer coefficient of 500 W/m 2 -C to 100 C water Surface and nuclear heating continues for three seconds water

8 Thermal Response for LOCA in Blanket/Shield and LOFA in Vacuum Vessel Peak temperature of 730 C occurs 3.6 hr after loss off coolant / flow and continues to drop with time. Addition of surface and nuclear heating increases peak by 2.5 C. Results not particularly sensitive to VV convection assumptions.

9 BlanketShieldVacuum Vessel First Wall T init = 500 C LiPB T init = 625 C Back Wall T init = 450 C Shield T init = 450 C Vacuum Vessel T init = 100 C Gap Radius = 2.0 m Ferritic SteelBoronated Ferritic Steel LiPb H20H20H20H20H20H20 Updated estimates of LiPb afterheat included. Heating levels much lower than previously assumed. Nuclear heating assumed for three seconds after loss of flow. Analysis repeating with (LOFA) and without water (LOCA) in vacuum vessel. Analyses Including the Static Presence of LiPb in the Blanket

10 Afterheat in Blanket Materials LiPb afterheat scaled from ARIES-AT data. Previously presented results (Sept.) had used heating for steel.

11 Thermal Results LOFA for LiPb and LOCA for He and Water Resulting temperatures slightly lower than complete LOCA.

12 Maximum temperature 17.8 C less than the case without LiPb. Thermal Results LOFA for LiPb and Water and LOCA for He

13 Support Structure Modeling Model to include heat loss through supporting leg and also structures in vacuum gaps. Potential to model noncircular cross-sections. Heat transfer from vacuum vessel to coils may also be included. Shield Blanket Vacuum Vessel Supporting Leg

14 Summary Peak temperatures are below 730 C for cases with LOFA in the vacuum vessel. Results not particularly sensitive to VV convection assumptions. Without heat removal (LOCA in VV), the temperatures continue to rise over time. The addition of surface and nuclear heating for three seconds after LOCA increased the peak temperature by 2.5 C. Models are being developed to include support structure and heat loss from vacuum vessel.