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AINA Safety Code, A Review of Loss of Plasma Control Transients in ITER: Sudden Increase in Fuelling Rate, Sudden Increase of Auxiliary Heating

J. Dies et al.

Fusion Science and Technology / Volume 56 / Number 1 / July 2009 / Pages 31-37

ITER / Eighteenth Topical Meeting on the Technology of Fusion Energy (Part 1)

In this contribution, two ITER loss of plasma control events are investigated. The first one is a failure of pumps and/or pellet injection system which fuel the plasma, producing an overfuelling event. The second examines an increase of external heating during the steady state operation of ITER. For both events, initial simulation parameters are scanned in order to find out which could lead to highest fusion power.

Extensive simulation work has been done with AINA-1.0 (July-2007), the safety code developed by Fusion Energy Engineering Laboratory (FEEL-UPC) on the basis of SAFALY. AINA is a hybrid code comprising a zero-dimensional plasma dynamics and radial and poloidal thermal analyses of in-vessel components, and is intended to the quantitative investigation of plasma events in nuclear fusion reactors such as ITER.

FEEL-UPC research group has been developing AINA code since 2004. AINA code brings significant improvements in relation to the original SAFALY code, and FEEL-UPC aims to continue improving it in the near future, with new models for plasma wall interactions, blanket thermal analysis, and plasma edge and core.

 
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