Get Publication AlertsNew fusion research delivered to your inbox.
G. Bongiovì, I. Catanzaro, D. Bernardi, F.S. Nitti, P. Chiovaro, E. Vallone, J. Maestre, S. Basile, P.A. Di Maio
Katarzyna Mikszuta-Michalik, Daniele Marocco, Basilio Esposito, Marco Riva, Gianluca Pucella
A tomography code based on the Minimum Fisher Regularisation method with a geometry description based on the field of view has been applied to reconstruct the neutron emissivity profiles from measurements performed in 2021 during the second JET deuterium-tritium campaign (DTE2). The Neutron Profile Monitor Upgrade installed at JET offers a unique opportunity for investigating the neutron emissivity in a full poloidal cross-section with unprecedented time resolution (~1 ms), thanks to the availability of digital data reprocessing and the high neutron emission that enables milisecond line-integrated raw data with low statistical error. Measurements of 14.1 MeV neutrons provided by the Bicron BC418 plastic scintillators installed in the JET neutron camera have been used.The analysis focuses on the effect of sawtooth crashes on the neutron emission profiles. Tomography results were compared with 1D reconstructions using two different methods and 10 ms time resolution. The use of the neutron camera data sampled at 1 ms enables the observation of hollowing of the neutron emissivity profiles during the sawtooth crash and their subsequent flattening.
Francesco Devia, Fabio Panza, Guglielmo Lomonaco, Seyed Kamal Mousavibalgehshiri
Ion Evangelos Evangelos Stamatelatos, Marilia Savva, Theodora Vasilopoulou, K Mergia, S Messoloras, Steven Bradnam, Chantal Shand, Lee William Packer, Zamir Ghani, Paola Batistoni, et al.
The VERDI detector is a passive neutron detector using the multi-foil activation technique to measure neutron fluence in extreme fusion conditions. It features a low-activation capsule that contains a defined concentration of metallic elements. The robustness of the detector is ensured by the capsule material, while neutron detection relies on activation of the metallic elements. Post-irradiation gamma spectrometry combined with computational unfolding enables reconstruction of the neutron fluence and energy spectrum. This study reviews the development of the VERDI detector and reports the first deployment of VERDI detectors in an operational Deuterium-Tritium (D-T) fusion environment in the Long-Term Irradiation Station (LTIS) of JET tokamak during the DTE2 campaign, featuring a neutron spectrum representative of future fusion devices such as ITER and DEMO. The results provide benchmarks for validating neutronic simulations and nuclear data, supporting the design optimization and safety assessment of future fusion power plants.
Francesco Colliva, Cristiano Ciurluini, Bruno Gonfiotti, Amelia Tincani, Fabio Giannetti
Martin Felix Dentan, Soilihi Moindjie, Matteo Cecchetto, Jean-Luc Autran, Ruben Garcia Alia, Richard Naish, John Waterhouse, Alan R Horton, Xavier L Litaudon, Fernanda Rimini, et al.
We measured SEEs in 40 nm and 65 nm SRAMs exposed to the D–T fusion neutron environment of the JET tokamak during the DTE-3 campaign (September–October 2023), while also characterizing the neutron spectrum seen by the devices. Using consolidated JET neutron production data, the measured SEE rates show good agreement with predictions based on the measured spectra and independently determined SRAM sensitivity parameters from thermal and monoenergetic neutron tests. These results extend the validation of our spectrum-based SEE prediction methodology, previously demonstrated in a D–D fusion neutron environment in 2021, to a D–T fusion neutron field. The novelty of this work is therefore the first experimental validation of this complete prediction approach in a D–T fusion environment, using real-time neutron spectrometry and independent device sensitivity data, rather than a new SEE model. The experiments also show that a local B₄C shield reduces the bit-flip rate by absorbing thermal neutrons, and we discuss the conditions under which such shielding can improve electronics reliability in tokamak and accelerator neutron environments.
Tommaso Glingler, Gianfranco Caruso, Danilo Nicola Dongiovanni, Salvatore d’Amico, Italo Ricapito, Paul Wouters, Francesca Fantini, Joelle Elbez-Uzan, Sandrine Rosanvallon, Matteo D'Onorio
The planned experimental activities of the ITER Test Blanket Module program will be a key step in understanding the physics and technologies required for tritium breeding blankets, which are essential for achieving tritium self-sufficiency in a demonstration fusion power reactor. The ITER Test Blanket Module program foresees the installation and operation of different breeding blanket concepts, such as the Water-Cooled Lithium Lead and the Helium-Cooled Pebble Bed, to demonstrate tritium breeding, high-grade heat extraction, and integrated system operation under ITER conditions. The objective of this paper is to provide an overview of the thermal-hydraulic analyses performed in the frame of EUROfusion, for the Water Cooled Lead Lithium Test Blanket Module, with emphasis on the main phenomena occurring during representative accident sequences. The main figure of merit is that the structural integrity of confinement barriers is preserved. Accident scenarios were analyzed using MELCOR version 1.8.6 for fusion applications. The main sequences considered, were identified through an extensive failure mode and effect analysis, include ex-vessel Loss of Coolant Accident and Loss of Heat Sink. The results highlight the robustness of the current design.
Gustavo Granucci, Silvio Ceccuzzi, Afra Romano, Andrea Murari, Gian Luca Ravera, Piero Agostinetti, Sofia Bertolami, Falk Braunmüller, Alessandro Bruschi, Daniele Busi, et al.
This paper reports the main design keys and the challenging issues of the Heating and Current Drive System (HCD) of the Divert Tokamak Test (DTT) facility that is under construction at ENEA site in Frascati with the aim to perform studies on the power exhaust in a flexible and easily modifiable environment. The selected HCD systems for DTT are those with the most consolidated technology and expected to be relevant for the future reactor. The status of each system is reported, both in terms of design and procurement, which are well advanced for the system required in the first phase of the DTT exploitation: electron and ion cyclotron resonant heating. The third system is neutral beam injector, based on negative ion acceleration, which will be installed in DTT in a second phase, after the first five years of operation. The full heating power will be reached with the doubling of the radiofrequency power to reach the 45 MW at plasma needed to test the divertor with a power density at reactor level.
Francesco Marino, Andrea Zoppoli, Andrea Fimiani, Francesca Giovanna Lanzotti, Andrea Reale, Giuseppe Di Gironimo
M. Damiano, R. Villari, A. Colangeli, D. Flammini, N. Fonnesu, P. Gaudio, M. Lungaroni, F. Moro, S. Noce, A. Previti, et al.
Nils Holstein, Wolfgang Krauss, Jürgen Konys, Francesco Saverio Nitti, Belit Garcinuño, Jorge Maestre
G. Mongiardini, C. Ciurluini, B. Gonfiotti, A. Vannoni, N. Badodi, P. Arena, M. Eboli, F. Giannetti, A. Del Nevo
Gerardo Giruzzi, P Martin, Clemente Angioni, Sebastijan Brezinsek, Flavio Crisanti, Giacomo Dose, Matteo Valerio Falessi, Paolo Innocente, Paola Mantica, Eric Nardon, et al.
The Divertor Tokamak Test facility (DTT) is a device presently under construction at the ENEA site in Frascati (Italy) in the framework of a joint public/private partnership. It has been designed as a superconducting tokamak with breakeven class performance, with the main objective of developing credible solutions for heat and particle exhaust, a key challenge in view of future fusion reactors. This needs to be addressed in a core-edge integrated approach, to assess the compatibility of exhaust solutions with reactor relevant core performance. In this paper, an overview is provided of the DTT research plan, recently developed by an international team. It covers the DTT programmatic objectives, research strategy and expected scientific contributions connected with the device characteristics, not only in the key area of heat exhaust and edge plasma physics, but also on other subjects of high fusion relevance, such as MHD stability in high performance scenarios, transport and turbulence, energetic particle physics, validation of advanced theoretical developments, as well as tests of technological solutions for reactor relevant components.
S. Noce, G. Bailey, L. Butt, Y.-L. Chiu, A. Colangeli, F. Dacquait, M. Damiano, D. Flammini, N. Fonnesu, M.R. Gilbert, et al.
S. Coda, C. Piron, I. Voitsekhovitch, M. Agostini, F. Auriemma, L. Cordaro, A. Mele, M. Podestà, S. Garavaglia, A. Jardin, et al.
An extended experimental effort is underway on the TCV tokamak to develop scenarios compatible with long-pulse operation, featuring mostly non-inductively driven current—preferably with a large fraction of bootstrap current. A closely related goal is to achieve good plasma performance, typically measured through the normalized beta β N . This work is part of a broader endeavor involving several European tokamaks, under the auspices of the Tokamak Exploitation Work Package (WPTE) of EUROfusion, and aimed in part at preparing advanced scenarios for the new JT-60SA tokamak, which is the largest such device ever operated and has these scenarios at the core of its mission. This paper reports on the encouraging progress achieved in the last campaign, featuring an extensive set of discharges sustained over multiple current relaxation times ( T pulse ≫ τ R ) with zero flux contribution from the central solenoid (CS), and approaching stationary conditions with β N ∼ 2 and ion temperature ( T i ) rising towards the same order of magnitude as the electron temperature ( T e ). Auxiliary power currently appears to be a key limitation. With increased heating being added in 2027, there is now a realistic prospect of TCV reaching a fully stationary, high- β N , fully non-inductive neutral-beam injection-heated scenario. In the process of exploring the boundaries of this scenario, the hot-electron ( T e ≫ T i ) internal-transport-barrier (ITB) regime was also revisited and temperatures of 12 keV were recorded (a record for TCV non-inductive discharges). Additionally, a fully CS-free current ramp-up, starting only 30 ms after breakdown and displaying robustly negative central magnetic shear, has also been demonstrated, with a smooth continuation into the flat-top, non-inductive, advanced-scenario phase. This scenario, which is accompanied by an electron ITB of varying strength, is also a promising step towards a possible spherical-tokamak power plant. Finally, central-solenoid-free operation in the X -point target divertor configuration has been achieved, with a view to attempting detachment in a closed divertor geometry.
I. Ivanova-Stanik, A. Chomiczewska, G. Telesca, E. Kowalska-Strzęciwilk, L. Garzotti, G. Pucella, D. Van Eester, R. Zagorski, V.K. Zotta
This work consists of integrated numerical modelling applied to JET high-current, high-power baseline pulses with 92% tritium + 8% hydrogen with tungsten divertor and beryllium wall in corner configuration. These simulations are performed using the COREDIV code, which self-consistently solves one-dimensional radial transport equations for the plasma and impurities in the core region, coupled with two-dimensional multi-fluid transport in the scrape-off layer. It should be noted that the simulations are ‘semi-interpretative’, in the sense that transport coefficients are tuned in order to match experimental data: profile of the radiation, Ni concentration, radiation in SOL and Z eff . The simulations suggest that, within the assumptions of the COREDIV model and the available experimental constraints, the observed increase in core plasma radiation can be most consistently reproduced by changes in impurity transport rather than by an increase in the impurity source. The simulations show that sputtering of tungsten due to tritium is negligible. The Be is the main source of sputtering and the dominant contribution to tungsten sputtering comes from Be 2+ .
Emma Piozin, Mathieu Monteremand, Julien Cigna, Paolo Rossi, Jeong-Ha You
G. Grapow, M. Molinari, V. Narcisi, A. Santucci, M. D'Onorio
Gabriele Puglisi, Gabriele Manduchi, Luca Boncagni, Arturo Buscarino, Fabio Zanon
© 2019-2026 Triple Product Inc. Content available under CC BY-NC 4.0. Terms of Use
