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Session III-B Special Liquid Lithium Technology Session Summary

Session III-B Special Liquid Lithium Technology Session Summary. C. H. Skinner, session chair. Princeton Plasma Physics Laboratory. 2 nd International Symposium on Lithium Applications for Fusion Devices. April 27-29, 2011 Princeton, NJ, USA. Session III-B:.

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Session III-B Special Liquid Lithium Technology Session Summary

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  1. Session III-B Special Liquid Lithium Technology Session Summary C. H. Skinner, session chair Princeton Plasma Physics Laboratory 2nd International Symposium on Lithium Applications for Fusion Devices. April 27-29, 2011 Princeton, NJ, USA

  2. Session III-B: • F. Groeschel : The IFMIF Target Facility engineering design and the validation of key issues within the IFMIF-EVEDA Project • G.Miccichè: Status of the activities for the development of the remote handling techniques for the maintenance of IFMIF target assembly system • D. Bernardi: IFMIF Lithium Target • I. Lyublinski: Module of Lithium Divertor for KTM Tokamak • M. Narula: Fast flowing liquid lithium divertor concept for NSTX (Poster) B Rais et al., ISLAFD meeting April 27-29, 2011 Princeton, New Jersey

  3. F. Groeschel : The IFMIF Target Facility engineering design and the validation of key issues within the IFMIF-EVEDA Project • Summary: • Engineering design and validation tasks are closely linked • The proof of principle that stable flow and low impurity levels can be achieved would be an important step forward, but many other issues which may affect operability, performance and costs still have to be resolved until construction • Unfortunately we run out of time in the project which needs to be completed by 2013 ISLAFD meeting April 27-29, 2011 Princeton, New Jersey

  4. G.Miccichè: Status of the activities for the development of the remote handling techniques for the maintenance of IFMIF target assembly system • Summary: • The maintenance of the IFMIF TA system is a rather complex activity which requires a wide R&D program for the validation of the TA concepts, from the RH viewpoint, and of the RHEs and tools to be used; • The RH experimental activities are progressing even if the RH strategy has not fixed yet. However there are several common RH tasks that could help to take the final choice on the refurbishment approaches to be adopted. ( Qualification of the QDS system and final design of the RH for Test Modules for instance) • There are still several open points on the design of the RHEs and tools to be used (not described in the presentation): use of Rad Hard technology is mandatory ; viewing systems capable to withstand to the high dose rate expected in the test cell and in the other facilities as well. ISLAFD meeting April 27-29, 2011 Princeton, New Jersey

  5. D. Bernardi: IFMIF Lithium Target • Summary: • Main aspects of TA engineering design • TA mechanical design • Thermohydraulics • Neutronics • Thermomechanics • Lifetime assessment • Target Assembly Requirements: • Average heat flux 1 GW/m2 • Footprint area 100 cm2 (20 x 5 cm) • Jet width/thickness 260 / 25 mm • Li velocity 10-20 m/s • Damage rate on the BP 50-60 dpa/y • Erosion/corrosion rate 1 μm/y (nozzle and BP) • BP replacement frequency 11 months ISLAFD meeting April 27-29, 2011 Princeton, New Jersey

  6. I. Lyublinski: Module of Lithium Divertor for KTM Tokamak Summary: As a result of our Project realization the cooling module of lithium divertor for tokamak KTM will be designed and tested. The module with renewed lithium surface will be able to operate under specific heatloads of from 2 to 10 MW/m2, in quasi-stationary mode duration up to ~5 sec. At first stage, total power released from discharge under quasi-stationary mode will be about 1 MW. In the framework of the Project the technology will be developed and tested to assemble and mount lithium modules in tokamak, allowing for replacement of divertor components. After first tests and revision of the module design the issue of creation full-scale lithium divertor for tokamak KTM will be considered, total released power will be about 5 MW. ISLAFD meeting April 27-29, 2011 Princeton, New Jersey

  7. M. Narula: Fast flowing liquid lithium divertor concept for NSTX (Poster) • Summary: Concept proposed under ALPS (2004). • Film average inlet velocity ~ 10 m/s • Film average inlet thickness 2 mm • Film inclination (uphill) 21° Concept exploration with: • UCLA MTOR experiment with gallium • UCLA 3D incompressible MHD code HIMAG Result: Combined toroidal and surface normal field create a film with a non-uniform thickness in the toroidal direction (1-4 mm). ISLAFD meeting April 27-29, 2011 Princeton, New Jersey

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