Accuracy and convergence of coupled finite-volume/Monte Carlo codes for plasma edge simulations of nuclear fusion reactors

The plasma and neutral transport in the plasma edge of a nuclear fusion reactor is usually simulated using coupled finite volume (FV)/Monte Carlo (MC) codes. However, under conditions of future reactors like ITER and DEMO, convergence issues become apparent. This paper examines the convergence behaviour and the numerical error contributions with a simplified FV/MC model for three coupling techniques: Correlated Sampling, Random Noise and Robbins Monro. Also, practical procedures to estimate the errors in complex codes are proposed. Moreover, first results with more complex models show that an order of magnitude speedup can be achieved without any loss in accuracy by making use of averaging in the Random Noise coupling technique.

[1]  H. Robbins A Stochastic Approximation Method , 1951 .

[2]  H. Cramér Mathematical methods of statistics , 1947 .

[3]  D. Coster,et al.  Experimental studies and modeling of complete H-mode divertor detachment in ASDEX Upgrade , 2015 .

[4]  H. H. Bruun,et al.  Hot-Wire Anemometry: Principles and Signal Analysis , 1996 .

[5]  D. Harting,et al.  Preliminary Comparison of the Conventional and Quasi‐Snowflake Divertor Configurations with the 2D Code EDGE2D/EIRENE in the FAST Tokamak , 2014 .

[6]  Martine Baelmans,et al.  Accuracy and Convergence of Coupled Finite-Volume / Monte-Carlo Codes for Plasma Edge Simulations , 2016 .

[7]  H. H. Bruun Hot-wire anemometry , 1995 .

[8]  Martine Baelmans,et al.  The new SOLPS-ITER code package , 2015 .

[9]  D. Coster,et al.  Effect of the tokamak size in edge transport modelling and implications for DEMO , 2007 .

[10]  M. Kendall Probability and Statistical Inference , 1956, Nature.

[11]  P. J. Green,et al.  Probability and Statistical Inference , 1978 .

[12]  P. Roache Perspective: A Method for Uniform Reporting of Grid Refinement Studies , 1994 .

[13]  Vladislav Kotov,et al.  Consequences of a reduction of the upstream power SOL width in ITER , 2013 .

[14]  D. Reiter,et al.  The EIRENE and B2-EIRENE Codes , 2005 .

[15]  A. S. Kukushkin,et al.  Finalizing the ITER divertor design: The key role of SOLPS modeling , 2011 .

[16]  R. R. Coveyou Monte Carlo Principles and Neutron Transport Problems , 1971 .