MAST Upgrade Divertor Facility: A Test Bed for Novel Divertor Solutions
暂无分享,去创建一个
D. Moulton | N. R. Walkden | A. Kirk | F. Militello | B. Lipschultz | A. Kirk | J. Harrison | D. Moulton | N. Walkden | F. Militello | William Morris | J. R. Harrison | B. Lipschultz | W. Morris | B. Lipschultz
[1] F. Wagner. A study of the perpendicular particle transport properties in the scrape-off layer of ASDEX , 1985 .
[2] M. Mattei,et al. A procedure for the design of snowflake magnetic configurations in tokamaks , 2014 .
[3] F. Maviglia,et al. DEMO exhaust challenges beyond ITER , 2015 .
[4] Laila A. El-Guebaly,et al. Fusion nuclear science facilities and pilot plants based on the spherical tokamak , 2016 .
[5] Overview of recent physics results from MAST , 2016, 1611.06047.
[6] T. Eich,et al. Inter-ELM power decay length for JET and ASDEX upgrade: measurement and comparison with heuristic drift-based model. , 2011, Physical review letters.
[7] D. Coster,et al. Using SOLPS to confirm the importance of total flux expansion in Super-X divertors , 2017 .
[8] Llion Evans. Approaches for the Qualification of Exhaust Solutions for DEMO-class Devices , 2016 .
[9] Y. Ogawa,et al. “Multi-layer” one-dimensional model for stability analysis on partially detached divertor plasmas , 2011 .
[10] G. Fishpool,et al. MAST-upgrade divertor facility and assessing performance of long-legged divertors , 2013 .
[11] A. Kirk,et al. Quiescence near the X-point of MAST measured by high speed visible imaging , 2017, 1706.06318.
[12] E. Surrey,et al. Assessing Component Suitability and Optimizing Fusion Plant Design—Alternative Approaches to TRLs , 2018, IEEE Transactions on Plasma Science.
[13] C. Fuchs,et al. Integrated Data Analysis of Profile Diagnostics at ASDEX Upgrade , 2010 .
[14] F. Militello,et al. On the relation between non-exponential scrape off layer profiles and the dynamics of filaments , 2016, 1606.04262.
[15] R. Goldston,et al. A new scaling for divertor detachment , 2017 .
[16] J. Contributors,et al. High density operation for reactor-relevant power exhaust , 2015 .
[17] M. Gadomska,et al. Overview of EU DEMO design and R&D activities , 2014 .
[18] D. N. Hill,et al. Effect of changes in separatrix magnetic geometry on divertor behaviour in DIII-D , 2013 .
[19] J. Harrison,et al. Filamentary transport in the private flux region in MAST , 2015 .
[20] Shahram Sarkani,et al. A Comprehensive Review and Analysis of Maturity Assessment Approaches for Improved Decision Support to Achieve Efficient Defense Acquisition , 2009 .
[21] R. Sharples,et al. Coherence imaging of scrape-off-layer and divertor impurity flows in the Mega Amp Spherical Tokamak (invited). , 2014, The Review of scientific instruments.
[22] F. Militello,et al. Scrape off layer profiles interpreted with filament dynamics , 2016, 1604.08790.
[23] Graham Naylor,et al. MAST Upgrade – Construction Status , 2015 .
[24] G. Matthews,et al. Interpretation of scrape-off layer profile evolution and first-wall ion flux statistics on JET using a stochastic framework based on fillamentary motion , 2017, 1706.01239.
[25] N. R. Walkden,et al. L-mode filament characteristics on MAST as a function of plasma current measured using visible imaging , 2016, 1602.03021.
[26] M. Umansky. Attainment of a stable, fully detached plasma state in innovative divertor configurations. , 2016 .
[27] Joseph A. Fernandez. Contextual role of TRLs and MRLs in technology management. , 2010 .
[28] J. P. Goedbloed,et al. Generalized ballooning and sheath instabilities in the scrape-off layer of divertor tokamaks , 1997 .
[29] Robert J. Goldston,et al. Heuristic drift-based model of the power scrape-off width in low-gas-puff H-mode tokamaks , 2011 .
[30] J. Schweinzer,et al. Impurity seeding for tokamak power exhaust: from present devices via ITER to DEMO , 2013 .
[31] M. Reinke. Heat flux mitigation by impurity seeding in high-field tokamaks , 2017 .
[32] C. Challis,et al. MAST Accomplishments and Upgrade for Fusion Next-Steps , 2014, IEEE Transactions on Plasma Science.
[33] T. Eich,et al. Filament structures at the plasma edge on MAST , 2006 .
[34] B. Lipschultz,et al. Sensitivity of detachment extent to magnetic configuration and external parameters , 2016 .
[35] Wayne Arter,et al. A CAD-Based Tool for Calculating Power Deposition on Tokamak Plasma-Facing Components , 2014, IEEE Transactions on Plasma Science.
[36] A. Kirk,et al. L-mode and inter-ELM divertor particle and heat flux width scaling on MAST , 2013, 1306.6777.
[37] V. Parail,et al. Gyrokinetic projection of the divertor heat-flux width from present tokamaks to ITER , 2017, 1701.05507.
[38] A. Loarte,et al. Status and physics basis of the ITER divertor , 2009 .
[39] Shuichi Takamura,et al. Chapter 4: Power and particle control , 2007 .
[40] P. J. Knight,et al. Conceptual design of a component test facility based on the spherical tokamak , 2008 .
[41] J. Contributors,et al. Power exhaust by SOL and pedestal radiation at ASDEX Upgrade and JET , 2017 .
[42] M. Wischmeier,et al. SOLPS analysis of the MAST-U divertor with the effect of heating power and pumping on the access to detachment in the Super-x configuration , 2015 .
[43] P. Valanju,et al. Pedestal transport in H-mode plasmas for fusion gain , 2017 .
[44] J. Harrison,et al. The appearance and propagation of filaments in the private flux region in Mega Amp Spherical Tokamak , 2015 .