C. Piron

ORCID: 0000-0002-4441-9781
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About
Contact & Profiles
Research Areas
  • Magnetic confinement fusion research
  • Fusion materials and technologies
  • Particle accelerators and beam dynamics
  • Superconducting Materials and Applications
  • Ionosphere and magnetosphere dynamics
  • Laser-Plasma Interactions and Diagnostics
  • Nuclear Physics and Applications
  • Laser-induced spectroscopy and plasma
  • Electron and X-Ray Spectroscopy Techniques
  • Plasma Diagnostics and Applications
  • Nuclear reactor physics and engineering
  • Silicon and Solar Cell Technologies
  • Radiation Therapy and Dosimetry

National Agency for New Technologies, Energy and Sustainable Economic Development
2015-2024

University of Padua
2015-2019

Disruptions caused by tearing modes (TMs) are considered to be one of the most critical roadblocks achieving reliable, steady-state operation tokamak fusion reactors. Here we have demonstrated a promising scheme avoid mode locking utilizing electro-magnetic (EM) torque produced with 3D coils that available in many tokamaks. In this scheme, EM is delivered toroidal phase shift between externally applied field and excited TM fields, compensating for momentum loss through interaction resistive...

10.1088/1741-4326/57/1/016035 article EN Nuclear Fusion 2016-11-25

Abstract External n = 1 magnetic fields are applied in RFX-mod and DIII-D low safety factor Tokamak plasmas to investigate their interaction with the internal MHD dynamics particular sawtooth instability. In these experiments cause a reduction of both amplitude period, leading an overall stabilizing effect on oscillations. sawteeth eventually disappear replaced by stationary m 1, helical equilibrium without increase disruptivity. However toroidal rotation is significantly reduced plasmas,...

10.1088/0029-5515/56/10/106012 article EN Nuclear Fusion 2016-08-11

We present experimental results of magnetic feedback control on the m = 2, n 1 tearing mode in RFX-mod operated as a circular ohmically heated tokamak. The suppression non-resonant resistive wall (RWM) q(a) < 2 plasmas is well-established result RFX-mod. counterpart, which develops > equilibrium, instead more difficult issue. In fact, disruption induced by growing amplitude can be prevented only when resonant surface q close to plasma edge, namely 2.5, and electron density does not exceed...

10.1088/0029-5515/55/4/043020 article EN Nuclear Fusion 2015-03-30

Abstract Since the 2018 IAEA FEC Conference, FTU operations have been devoted to several experiments covering a large range of topics, from investigation behaviour liquid tin limiter runaway electrons mitigation and control stabilization tearing modes by electron cyclotron heating pellet injection. Other involved spectroscopy heavy metal ions, density peaking in helium doped plasmas, assisted start-up temperature measurements high plasmas. The effectiveness laser induced breakdown system has...

10.1088/1741-4326/ac1802 article EN cc-by Nuclear Fusion 2021-07-27

The fully non-inductive sustainment of high normalized beta plasmas (β N ) is a crucial challenge for the steady-state operation tokamak reactor.In order to assess diculties facing such scenarios, regimes have been explored on Tokamak à Conguration Variable (TCV) using newly available 1 MW Neutral Beam Injection (NBI) system.The operating space extended towards that are closer those expected in JT-60SA and ITER, i.e. with signicant NBI Electron Cyclotron Resonance Heating Current Drive...

10.1088/1741-4326/ab2bb6 article EN Nuclear Fusion 2019-06-21

This work presents the first evidence of helical flow in RFX-mod q(a) < 2 tokamak plasmas. The pattern is characterized by presence convective cells with m = 1 and n periodicity poloidal toroidal directions, respectively. A similar deformation has been observed same device when operated as a reversed field pinch (RFP). In RFP plasmas, dynamic tailored innermost resonant 1, 7 tearing mode, which sustains magnetic configuration through dynamo mechanism (Bonomo et al 2011 Nucl. Fusion 51...

10.1088/1741-4326/aa5c5d article EN Nuclear Fusion 2017-03-31

Abstract In this work, L-mode analyses are performed in order to assess a modeling framework for the prediction of electron cyclotron resonant heating (ECRH) -assisted current ramp-up phases JT-60SA tokamak hybrid scenario #4-2. We compare two turbulence transport models, CDBM and TGLF, using integrated code CRONOS. Model validation is on basis an phase JET plasma, flat-top TCV (Tokamak configuration variable) plasma with applied ECRH. Parameter scans <?CDATA $Z_{\textrm{eff}}$?> <mml:math...

10.1088/1361-6587/abcba9 article EN Plasma Physics and Controlled Fusion 2020-11-18
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