Characterization of a new 4He scintillator detector prototype for the ITER Radial Neutron Camera

IF 1.9 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Fusion Engineering and Design Pub Date : 2025-03-10 DOI:10.1016/j.fusengdes.2025.114948

S. Cesaroni , D. Marocco , V. Anagnostopoulou , F. Belli , A. Colangeli , N. Fonnesu , S. Loreti , F. Moro , G. Pagano , E. Pirovano , F. Pompili , M. Pontesilli , A. Zimbal , B. Esposito

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Abstract

In ITER, the reconstruction of the neutron emissivity profile along radial Lines-Of-Sight (LOS) is performed with the Radial Neutron Camera (RNC) diagnostic system. Neutrons produced in the plasma core through D(d, n)³He and T(d, n)⁴He reactions are measured by the RNC Ex-Port subsystem using three different types of detectors located within modules positioned at the end of each LOS collimator: a plastic scintillator, a ⁴He gas scintillator and a single-crystal diamond matrix.

Considering plasma scenarios foreseen in ITER, measurements during full-power operations rely on the ⁴He scintillator detector. A new prototype of this device, specifically designed for the ITER RNC system, has been developed and experimentally characterized. This work presents the results of the measurements performed at the Physikalisch-Technische Bundesanstalt (PTB) Ion Accelerator Facility (PIAF) in Braunschweig, focusing on the detector's response to different neutron energies, and at ENEA Frascati Neutron Generator (FNG), where its performance under high neutron fluxes was studied. The new ⁴He scintillator detector prototype has proven to be suitable for its installation in the ITER RNC Ex-Port detector modules, and capable of reliable operation during the full-power scenarios of ITER operation.

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来源期刊

Fusion Engineering and Design 工程技术-核科学技术

CiteScore

3.50

自引率

23.50%

发文量

275

审稿时长

3.8 months

期刊介绍： The journal accepts papers about experiments (both plasma and technology), theory, models, methods, and designs in areas relating to technology, engineering, and applied science aspects of magnetic and inertial fusion energy. Specific areas of interest include: MFE and IFE design studies for experiments and reactors; fusion nuclear technologies and materials, including blankets and shields; analysis of reactor plasmas; plasma heating, fuelling, and vacuum systems; drivers, targets, and special technologies for IFE, controls and diagnostics; fuel cycle analysis and tritium reprocessing and handling; operations and remote maintenance of reactors; safety, decommissioning, and waste management; economic and environmental analysis of components and systems.