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Related papers: Conceptual Design of In-Vessel Divertor Coils in D…

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The Divertor Tokamak Test (DTT) facility, construction starting at Frascati, Italy, is designed to test different solutions for divertor in view of DEMO. A preliminary analysis of the error fields (EFs) assumed a simplified model of rigid…

The Divertor Tokamak Test (DTT) is a new experimental facility whose construction is starting in Frascati, Rome, Italy; its main goals are improving the understanding of plasma-wall interactions and supporting the development of ITER and…

Designing superconducting coils for a tokamak fusion device is a highly coupled, non-linear design problem. The coils have many disparate engineering requirements from structural to power electronics, as well strict limits placed on the…

Plasma Physics · Physics 2025-12-19 Nathan Welch , Chris Marsden

It is found that the X-Divertor (XD) configuration [1-3] can be made with the conventional PF coil set on ITER[4], where all PF coils are outside the TF coils. Desirable configurations are possible where the PF currents are below the…

Plasma Physics · Physics 2015-06-18 Brent Covele , Prashant Valanju , Mike Kotschenreuther , Swadesh Mahajan

The background magnetic geometry at the edge of a tokamak plasma has to be designed in order to mitigate the particle and energy looses essentially due to turbulent transport. The Divertor-Tokamak-Test (DTT) facility under construction at…

Plasma Physics · Physics 2024-08-01 F. Cianfrani , G. Montani

One of the main challenges concerning next generation tokamaks (such as DEMO) will be the development of a heat and power exhaust system able to withstand the large loads expected in the divertor region. A dedicated Divertor Tokamak Test…

Plasma Physics · Physics 2023-04-19 E. Acampora , R. Ambrosino , A. Castaldo , R. Iervolino

This work introduces the design analysis simulation and a standard MEMS fabrication process for a three dimensional microcoil with a magnetic core and a digital switch configuration using a completely integrated fully MEMS compatible…

Systems and Control · Electrical Eng. & Systems 2022-12-21 Abdelhameed Sharaf , S. M. Eladl , A. Nasr , Mohamed Serry

The ITER tokamak will be operating with 5 microwave diagnostic systems. While they rely on different physics, they share a common need: transmitting low and high power microwave in the range of 12 GHz to 1000 GHz(different bandwidths for…

A new optimized quasihelically symmetric configuration is described that has the desir-able properties of improved energetic particle confinement, reduced turbulent transportby 3D shaping, and non-resonant divertor capabilities. The…

Developing HTS dipole inserts producing fields larger than 5 T within 15 T Nb3Sn outserts is necessary to generate 20 T or higher fields for future high energy colliders. Dipole inserts based on the cos-theta coil geometry with various…

Accelerator Physics · Physics 2022-10-27 Emanuela Barzi

A potentially important feature in a divertor design for a high-power tokamak is an extended and expanded divertor leg. The upgrade to MAST will allow a wide range of such divertor leg geometries to be produced, and hence will allow the…

We present the field-line modeling, design and construction of a prototype circular-coil tokamak-torsatron hybrid called Proto-CIRCUS. The device has a major radius R = 16 cm and minor radius a < 5 cm. The six "toroidal field" coils are…

Plasma Physics · Physics 2014-10-10 A. W. Clark , M. Doumet , K. C. Hammond , Y. Kornbluth , D. A. Spong , R. Sweeney , F. A. Volpe

In this work we present a study on the viability and practicality of installing a Doppler reflectometer (DR) system in the JT-60SA advanced tokamak. First, we discuss its scientific scope in the context of the JT-60SA research plan. We…

Plasma Physics · Physics 2026-01-16 D. Carralero , T. Happel , T. Estrada , T. Tokuzawa , J. Martínez , E. de la Luna , A. Cappa , J. García

Simulating gas flow within the divertor, which is a crucial component in nuclear fusion reactors, is essential for assessing and enhancing its design and performance. Traditional methods, such as the direct simulation Monte Carlo and the…

Plasma Physics · Physics 2024-09-11 Wei Li , Yanbing Zhang , Jianan Zeng , Lei Wu

With edge plasma code SOLS-ITER, we study four Snowflake (SF) configurations for an ITER-size tokamak, with toroidal magnetic field BT=5T, major radius R=5m and plasma current Ip=10MA. Our aim is to provide insights on SF divertor design…

Plasma Physics · Physics 2025-09-03 H. S. Wu , F. Subba , M. R. K. Wigram , O. Pan , R. Lo Frano , A. Pucciarelli , R. Zanino

Power exhaust is one of the major challenges for a future fusion device. Applying a non-axisymmetric external magnetic perturbation is one technique that is studied in order to mitigate or suppress large edge localized modes which accompany…

In-situ, two-dimensional (2D) Langmuir probe measurements across a large part of the TCV divertor are reported in L-mode discharges with and without divertor baffles. This provides detailed insights into time averaged profiles, particle…

In stellarators, achieving effective divertor configurations is challenging due to the three-dimensional nature of the magnetic fields, which often leads to chaotic field lines and fuzzy separatrices. This work presents a novel approach to…

Plasma Physics · Physics 2025-11-03 Todd Elder , Matt Landremann , Christoper B. Smiet , Robert Davies

Turbofan engine performance depends highly on the characteristics and conditions of the inlet flow. Swirl distortions, caused by non-uniformities in flows arising from boundary layer or ground/fuselage vortex ingestion are of concern and…

Fluid Dynamics · Physics 2019-03-27 Tamara Guimarães , K. Todd Lowe , Walter F. O'Brien

Direct Torque Control (DTC) is well known as an effective control technique for high performance drives in a wide variety of industrial applications and conventional DTC technique uses two constant reference value: torque and stator flux.…

Systems and Control · Computer Science 2012-12-04 Fatih Korkmaz , M. Faruk Cakir , Yilmaz Korkmaz , Ismail Topaloglu
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