S. Gazzotti

ORCID: 0000-0001-8220-6552
Publications
Citations
Views
---
Saved
---
About
Contact & Profiles
Research Areas
  • Fusion materials and technologies
  • Magnetic confinement fusion research
  • Superconducting Materials and Applications
  • Nuclear Materials and Properties
  • Graphite, nuclear technology, radiation studies
  • Nuclear reactor physics and engineering
  • Space Exploration and Technology
  • Metallurgy and Material Forming
  • Electromagnetic Launch and Propulsion Technology
  • Industrial Engineering and Technologies
  • Laser-Plasma Interactions and Diagnostics
  • Mechanics and Biomechanics Studies
  • Human-Automation Interaction and Safety
  • Nuclear and radioactivity studies
  • Particle accelerators and beam dynamics
  • Material Properties and Applications

Commissariat à l'Énergie Atomique et aux Énergies Alternatives
2019-2024

CEA Cadarache
2019-2024

Institut de Recherche sur la Fusion par Confinement Magnétique
2016-2022

Port Cell (PC) rooms in the ITER tokamak building host devices required for Plugs operation and provide connection to services. During Plasma Operation State, Vacuum Vessel ports sealing interface provides vacuum tightness first confinement barrier as essential functions. When a Plug needs be replaced or maintained, this significant component must removed reinstalled. The general strategy has been reviewed resulting modification proposals address requirements static dynamic management of...

10.1016/j.fusengdes.2023.113670 article EN cc-by-nc-nd Fusion Engineering and Design 2023-04-05

The ITER Test Blanket Modules (TBMs) are installed and operated inside the vacuum vessel (VV) at equatorial ports located within port plugs (PP), each of them includes two TBMs. After plasma operation campaign, TBM research plan testing program requires replacement TBMs by new ones during long-term shutdown (LTM). a removal/reinstallation all test blanket system (TBS) equipment present in cell (PC), including those interspace called pipe forest (PF). TBS PC shall be designed so that...

10.1109/tps.2022.3212167 article EN IEEE Transactions on Plasma Science 2022-11-01

10.1016/j.fusengdes.2020.112000 article EN publisher-specific-oa Fusion Engineering and Design 2020-09-25

The objective of the ITER test blanket module (TBM) program is to provide experimental data on performance breeding blankets in integrated fusion nuclear environment. modules are installed and operated inside vacuum vessel (VV) at equatorial ports located within port plugs (PP), each PP includes two TBMs. After 18-month-long plasma operation campaign, TBM research plan testing requires replacement TBMs with new ones during long-term shutdown, called maintenance (LTM). a...

10.3390/jne4010022 article EN cc-by Journal of Nuclear Engineering 2023-03-17
Coming Soon ...