Centro di Ateneo “Centro Ricerche Fusione”
c/o Consorzio RFX

             3 positions with open topic funded by

University of Padova and University of Napoli Federico II

Optimization of the negative ion source prototypes for the ITER injector.

(funded by ITER Organization through Consorzio RFX)

Neutral beams are used as main heating mechanism for fusion plasmas, with a major role also in future devices, including ITER. The next step in the research and development is the ITER neutral beams at the neutral beam test facility in Padova. This PhD position addresses the preparation of the next generation of neutral beam researchers in view of ITER.

In the recent operations of the prototype sources, it was shown that optimizing the negative ion production and acceleration concerns the role of caesium in negative ion production and the uniformity of the plasma in the extraction region. Experiments of negative ion beams at nominal acceleration energies revealed that modifications of the accelerator configuration are necessary to improve the beamlet optics; at the same time, the preparation of MITICA first campaign requires the mitigation of expected off-nominal conditions. The synergic use of source and beam diagnostics, integrating real-time analyses and visualization tools to steer the operation and provide the physical interpretation of source performance, are also necessary improvements. These topics shall be addressed by numerical and experimental techniques in order to promote the advancement of source operation and design enhancements.

      Contact person: prof. Emanuele Sartori
      emanuele.sartori@unipd.it

Engineering design and development for the ITER neutral beam injector prototypes

(funded by ITER Organization through Consorzio RFX)

Neutral beams are used as main heating mechanism for fusion plasmas, with a major role also in future devices, including ITER. The next step in the research and development is the ITER neutral beams at the neutral beam test facility in Padova. This PhD position addresses the preparation of the next generation of neutral beam researchers in view of ITER.

The challenges in the engineering design, and the technical aspects related to the operation of the experimental devices and the whole facility, concerns all engineering fields: electric, fluid dynamics, control engineering, and thermo-mechanics. The success of the first campaign of the full-size ITER neutral beam prototype depends on the integrated operation of auxiliary units as well as of the in-vacuum components. 

Examples of research activities include the optimization of RF operation strategies (from solid-state generators to driver design), the caesium evaporation devices and diagnostics, the voltage-holding optimization for MITICA source and bushing, the integrated control systems of MITICA, the mechanical and electrical improvements of the ion sources and accelerators of SPIDER and MITICA also considering the preparation of the beamline components for the installation and first use due for the next year.

     Contact person: dott. Diego Marcuzzi
     diego.marcuzzi@igi.cnr.it

Nuclear analyses via Monte Carlo methods and experiments to support the design and safety of the Divertor Tokamak Test and other experimental fusion machines

(funded by ENEA)

Neutronics plays a crucial role in fusion science. In the most promising reactions for future energy production, such as deuterium–deuterium (D–D) and deuterium–tritium (D–T), high-energy neutrons (2.45 MeV and 14.1 MeV, respectively) are produced. These neutrons escape the plasma and interact with surrounding structures, generating a range of effects that must be carefully managed. Such interactions strongly influence both technical and operational scenarios, often dictating the engineering solutions adopted and consequently impacting the design, cost, operation, and maintenance of fusion plants.

Radiation transport calculations and experimental activities are therefore essential for predicting and validating key neutronics parameters. In particular, accurate three-dimensional simulations are required to properly characterize the radiation environment and to account for phenomena such as neutron streaming through penetrations, radiation effects on electronic devices, radiation loads on machine structures and auxiliary components, and neutron induced activation on materials.

A detailed assessment of neutron and gamma fluxes within machine components is fundamental for their mechanical design. Moreover, precise mapping of radiation fields, both inside and outside the machine, is necessary to support maintenance planning and ensure operator safety.

Within this framework, both computational and experimental activities will be carried out in support of the Divertor Tokamak Test (DTT) and other fusion machine development and operation. Computational analyses will be performed using Monte Carlo radiation transport codes such as MCNP and emerging tools like OpenMC, coupled with appropriate nuclear data libraries. Experimental investigations will rely on established neutron and gamma detection techniques.

Contact person: dott. Andrea Colangeli
andrea.colangeli@enea.it