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Panel Discussion ISLA-2011 April 27-29, 2011 Session VII. Panel Discussion “ Is lithium PFC viable in magnetic fusion reactors such as ITER?” [11:00 –

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Presentation on theme: "Panel Discussion ISLA-2011 April 27-29, 2011 Session VII. Panel Discussion “ Is lithium PFC viable in magnetic fusion reactors such as ITER?” [11:00 –"— Presentation transcript:

1 Panel Discussion ISLA-2011 April 27-29, 2011 Session VII. Panel Discussion “ Is lithium PFC viable in magnetic fusion reactors such as ITER?” [11:00 – 12:30] Panel Members: R. Goldston (ITER/Reactor), F. Groeschel (IFMIF), Y. Hirooka (IFE), S. Mirnov (Innovative Ideas), G. Mazzitelli (Tokamaks), M. Ono (Chair), D. Ruzic (LiMIT), F. L. Tabarés (non-tokamak), A. Ying (TBM) 11:00 – 11:45: Comments from Panel Members 11:45 – 12:30: Panel Discussion 1

2 Panel Discussion ISLA-2011 April 27-29, 2011 1. Handling Divertor High Heat Flux 2. Removal of D, T, Impurities 3. Divertor Steady-State Heat Removal 4. Liquid Lithium Flow in Magnetic Field 5. Long Term Lithium Corrosion 6. Flowing Liquid Lithium Safety 7. Compatibility with Hot Wall 2 Issues for Lithium Reactor Applications

3 Panel Discussion ISLA-2011 April 27-29, 2011 First Wall / Blanket At 500°C – 700°C? Lithium is not likely to be on this surface. 000000000000 Core Reacting Plasma Core Reacting Plasma Edge Plasma Scrape Off Layer Flowing Liquid Lithium Divertor Tray (LLDT) 200°C – 400°C LL Circulation Pump LL Purificati on and Cooling System D, T, Impurities Cooling line Divertor Heat and Particle Flux ~ 400°C ~ 200°C Flowing Liquid Lithium System LLDT Flowing Liquid Lithium Divertor Tray an Ultimate Solution? Necessary “Ingredients” are Coming Together?!

4 Panel Discussion ISLA-2011 April 27-29, 2011 1. Handling Divertor High Heat Flux 2. Removal of D, T, Impurities 3. Divertor Steady-State Heat Removal 4. Liquid Lithium Flow in Magnetic Field 5. Long Term Lithium Corrosion 6. Flowing Liquid Lithium Safety 7. Compatibility with Hot Wall 4 Issues for Lithium Reactor Applications

5 Panel Discussion ISLA-2011 April 27-29, 2011 Heat Flux Questions: Liquid lithium appears to handle high heat flux well. CDX-U, LiMIT, LLL, Goh Lithium reduces divertor heat flux? NSTX Can liquid lithium carry out necessary steady-state heat flux? IFMIF experience? Can liquid lithium divertor handle ultra high transient heat flux such as the ELM heat flux issue? Transient 100 MW/m 2 Partial lithium vaporization. Vaporization necessary ultimately? (e.g., Nagayama) Can Liquid Lithium Surface Handle High Heat Flux? Promising Properties of Liquid Lithium Liquid Lithium Properties: Light 0.534 g / cc High heat capacity (4.22 J/g K) Low viscosity < 0.5 water above 400°C Low Melting Point of 180.4°C High Boiling Point of 1342°C Low vapor pressure at high T Very large vaporization energy ~ 23 kJ / g (J.E. Selle, ORNL) Flowing LLDT 200°C - 600°C? Divertor Heat and Particle Flux

6 Panel Discussion ISLA-2011 April 27-29, 2011 1. Handling Divertor High Heat Flux 2. Removal of D, T, Impurities 3. Divertor Steady-State Heat Removal 4. Liquid Lithium Flow in Magnetic Field 5. Long Term Lithium Corrosion 6. Flowing Liquid Lithium Safety 7. Compatibility with Hot Wall 6 Issues for Lithium Reactor Applications

7 Panel Discussion ISLA-2011 April 27-29, 2011 Can D, T, Impurities Removed via LLD System IFMIF Experience? LL Circulation Pump LL Purification and Cooling System D, T, Impurities Cooling line Divertor Heat and Particle Flux ~ 600°C ~ 200°C Flowing LLDT 200°C - 600°C D,T, Impurity Removal Questions and Issues: Argon bubble removal of hydrogen? M. Kondo IFMIF EVEDA – O,N, T <10 weppm in real time. Cold trap, nitrogen trap, hydrogen trap, IFMIF – local loop idea for impurity removal seems quite practical.

8 Panel Discussion ISLA-2011 April 27-29, 2011 1. Handling Divertor High Heat Flux 2. Removal of D, T, Impurities 3. Divertor Steady-State Heat Removal 4. Liquid Lithium Flow in Magnetic Field 5. Long Term Lithium Corrosion 6. Flowing Liquid Lithium Safety 7. Compatibility with Hot Wall 8 Issues for Lithium Reactor Applications

9 Panel Discussion ISLA-2011 April 27-29, 2011 Can Liquid Lithium Remove Steady-State Divertor Power? IFMIF Experience? LL Circulation Pump LL Purification and Cooling System D, T, Impurities Cooling line Divertor Heat and Particle Flux ~ 600°C ~ 200°C Flowing LLDT 200°C - 600°C Steady-State Heat Removal Questions and Issues: 130 l /s, 4.5 ton, 250 – 350°C, 10 MW, IFMIF EVEDA (F. Groeschel) Liquid Lithium Properties: High heat capacity (4.22 J/g K) Low viscosity at high T

10 Panel Discussion ISLA-2011 April 27-29, 2011 1. Handling Divertor High Heat Flux 2. Removal of D, T, Impurities 3. Divertor Steady-State Heat Removal 4. Liquid Lithium Flow in Magnetic Field 5. Long Term Lithium Corrosion 6. Flowing Liquid Lithium Safety 7. Compatibility with Hot Wall 10 Issues for Lithium Reactor Applications

11 Panel Discussion ISLA-2011 April 27-29, 2011 Can Liquid Lithium Circulated within Magnetic Field? Blanket Module Experience, Thermo-Electric Effect? LL Circulation Pump LL Purification and Cooling System D, T, Impurities Cooling line Divertor Heat and Particle Flux ~ 600°C ~ 200°C Flowing LLDT 200°C - 600°C Liquid Lithium Circulation in B Questions and Issues: TBM - MHD forces dominate viscous and inertial forces for the PbLi flow in magnetic field. Modeling and Experiment (R&D) needed. A. Yoing T-E effect must be taken into account - could greatly help the flow (D. Ruzic) L. Zakharov ‘s comment on flow issues.

12 Panel Discussion ISLA-2011 April 27-29, 2011 1. Handling Divertor High Heat Flux 2. Removal of D, T, Impurities 3. Divertor Steady-State Heat Removal 4. Liquid Lithium Flow in Magnetic Field 5. Long Term Lithium Corrosion 6. Flowing Liquid Lithium Safety 7. Compatibility with Hot Wall 12 Issues for Lithium Reactor Applications

13 Panel Discussion ISLA-2011 April 27-29, 2011 First Wall / Blanket At 500°C – 700°C? Lithium is not likely to be on this surface. 000000000000 Core Reacting Plasma Core Reacting Plasma Edge Plasma Scrape Off Layer Flowing Liquid Lithium Divertor Tray (LLDT) 200°C – 400°C Longer Term Lithium Corrosion Lithium Corrosion Questions and Issues: TBM material – corrosion rate – Er 2 O 3 coationg is effecting against lithium. O, N impurities are corrosive. C impurity is OK. ( M. Kondo)

14 Panel Discussion ISLA-2011 April 27-29, 2011 1. Handling Divertor High Heat Flux 2. Removal of D, T, Impurities 3. Divertor Steady-State Heat Removal 4. Liquid Lithium Flow in Magnetic Field 5. Long Term Lithium Corrosion 6. Flowing Liquid Lithium Safety 7. Compatibility with Hot Wall 14 Issues for Lithium Reactor Applications

15 Panel Discussion ISLA-2011 April 27-29, 2011 Can Flowing Hot Liquid Lithium System Be Safe? IFMIF Experience? How to Avoid Contact with Water / Air? LL Circulation Pump LL Purification and Cooling System D, T, Impurities Cooling line Divertor Heat and Particle Flux ~ 600°C ~ 200°C Flowing LLDT 200°C - 600°C Liquid Lithium Safety Questions and Issues:

16 Panel Discussion ISLA-2011 April 27-29, 2011 1. Handling Divertor High Heat Flux 2. Removal of D, T, Impurities 3. Divertor Steady-State Heat Removal 4. Liquid Lithium Flow in Magnetic Field 5. Long Term Lithium Corrosion 6. Flowing Liquid Lithium Safety 7. Compatibility with Hot Wall 16 Issues for Lithium Reactor Applications

17 Panel Discussion ISLA-2011 April 27-29, 2011 First Wall / Blanket At 500°C – 700°C? Lithium is not likely to be on this surface. 000000000000 Core Reacting Plasma Core Reacting Plasma Edge Plasma Scrape Off Layer Flowing Liquid Lithium Divertor Tray (LLDT) 200°C – 400°C Is Lithium Utilization Compatible with Hot First Wall? Hot Wall Questions and Issues: Avoid lithium contamination of first wall? Perhaps lithium dust, jet, evaporation etc., into the main chamber may be fine with hot wall? Would lithium and its compound eventually end up in the colder divertor area?

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