Development of the safety code AINA for the European DEMO designs

Abstract In order to evaluate plasma evolution and in-vessel components strains, a safety code called AINA has been developing during the last ten years for different fusion reactors designs. This work describes the new AINA code which is being adapted for the four European DEMO designs (HCPB, DCLL, HCLL and WCLL) after an in-depth critical analysis of the former AINA versions with the purpose of performing a proper, reliable, versatile and flexible tool for the future safety studies. At this point, a new 0D plasma dynamics approach and a 1D finite-difference thermal model for the DEMO HCPB configuration and the divertor have been developed. By means of the feedback among both blocks, a preliminary safety analysis is carrying out checking the integrity of in-vessel components both when a plasma perturbation induces a Loss Of Plasma Control (LOPC) and a thermo-hydraulic accident takes place in the Plasma Facing Components (PFCs) or in the Vacuum Vessel such as a Loss Of Coolant Accident (LOCA). Initial results show deficiencies in the Blanket design which may be extremely significant when some of the described unexpected scenarios takes place leading the reactor to a melting episode.

[1]  José Carlos,et al.  Development of AINA code for the study of loss of plasma control events in ITER and DEMO, and contribution to the systems study of DEMO , 2016 .

[2]  Rowan,et al.  Strong nonlocal effects in a tokamak perturbative transport experiment. , 1995, Physical review letters.

[4]  J. Bohdansky,et al.  Few collisions approach for threshold sputtering , 1985 .

[5]  Joachim Roth,et al.  Revised formulae for sputtering data , 1995 .

[6]  W. D. Wilson,et al.  Calculations of nuclear stopping, ranges, and straggling in the low-energy region , 1977 .

[7]  T. Okazaki,et al.  Development of time dependent safety analysis code for plasma anomaly events in fusion reactors , 1997 .

[8]  V. Parail,et al.  Transient heat transport studies using laser ablated impurity injection in JET , 1998 .

[9]  Javier Dies,et al.  Revisiting the analysis of passive plasma shutdown during an ex-vessel loss of coolant accident in ITER blanket , 2015 .

[11]  Javier Dies,et al.  Safety studies of plasma-wall events with AINA code for Japanese DEMO , 2016 .

[12]  J. Rivas,et al.  Safety studies: Review of loss of plasma control transients in ITER with AINA 3.0 code , 2013 .

[13]  W. Horton,et al.  Impurity transport studies in the Texas Experimental Tokamak (TEXT) , 1994 .

[14]  A. Kukushkin,et al.  Material erosion at the vessel walls of future fusion devices , 2003 .

[15]  J. Dies,et al.  Upgrading of Plasma Wall Interaction Model for Tokamak Transient Modeling Code AINA 2.0, Used in Safety Studies of ITER Plasma Instability Events , 2011 .

[16]  W. Fundamenski,et al.  Multi-machine comparison of drift fluid dimensionless parameters , 2011 .