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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

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 2/7

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 3/7

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 4/7

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 monthsISLAFD meeting April 27-29, 2011 Princeton, New Jersey 5/7

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 heat

loads 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 6/7

• M. Narula: Fast flowing liquid lithium divertor concept for NSTX (Poster)

ISLAFD meeting April 27-29, 2011 Princeton, New Jersey 7/7

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).