The paper describes a method for the identification of the plasma shape in a toroidal device for fusion experiments based on magnetic confinement. The method, developed for the RFX machine, makes use of the magnetic measurements and takes into account the electromagnetic effects of a conductive vacuum vessel and of a stabilizing shell. These effects are quite important in "fast" machines such as the RFPs of the present generation
The reversed-field pinch (RFP) is a device for magnetic confinement of fusion plasmas. The main obje...
The paper presents the results of the validation of the plasma contour identification code PLACID. T...
This thesis reports the work performed during the three years of my Ph.D. course at the Physics Depa...
The paper describes a method for the identification of the plasma shape in a toroidal device for the...
The paper presents the application and the first results of a plasma shape identification code used ...
The paper presents a method to identify the plasma magnetic contour in fusion machines, when eddy cu...
Abstract A method for the identification of the magnetic field configuration inside a RFP plasma,...
The paper deals with a method for the identification of the plasma magnetic contour in machines for ...
The paper proposes an approach for the identification of magnetic surfaces, and particularly of the ...
RFX is a magnetic confinement toroidal machine based on the Reversed Field Pinch (RFP) concept [1]. ...
In this paper we present a method to compute spatial and time evolution of electromagnetic forces in...
The plasma configuration in tokamaks is created and controlled by magnetic fields generated by the e...
The Magnetic Measurement System of the Reversed Field Pinch machine RFX for research on Thermonuclea...
This section describes the activity on the generalization of the CREATE_L model aimed at making it s...
A major refurbishment of the toroidal load assembly is under study to extend the operational space o...
The reversed-field pinch (RFP) is a device for magnetic confinement of fusion plasmas. The main obje...
The paper presents the results of the validation of the plasma contour identification code PLACID. T...
This thesis reports the work performed during the three years of my Ph.D. course at the Physics Depa...
The paper describes a method for the identification of the plasma shape in a toroidal device for the...
The paper presents the application and the first results of a plasma shape identification code used ...
The paper presents a method to identify the plasma magnetic contour in fusion machines, when eddy cu...
Abstract A method for the identification of the magnetic field configuration inside a RFP plasma,...
The paper deals with a method for the identification of the plasma magnetic contour in machines for ...
The paper proposes an approach for the identification of magnetic surfaces, and particularly of the ...
RFX is a magnetic confinement toroidal machine based on the Reversed Field Pinch (RFP) concept [1]. ...
In this paper we present a method to compute spatial and time evolution of electromagnetic forces in...
The plasma configuration in tokamaks is created and controlled by magnetic fields generated by the e...
The Magnetic Measurement System of the Reversed Field Pinch machine RFX for research on Thermonuclea...
This section describes the activity on the generalization of the CREATE_L model aimed at making it s...
A major refurbishment of the toroidal load assembly is under study to extend the operational space o...
The reversed-field pinch (RFP) is a device for magnetic confinement of fusion plasmas. The main obje...
The paper presents the results of the validation of the plasma contour identification code PLACID. T...
This thesis reports the work performed during the three years of my Ph.D. course at the Physics Depa...