Federico Scioscioli , Giulia Marcer , Alessandro Ciurlino , Stefano Colombi , Bruno Coriton , Andrea Dal Molin , Jan Dankowski , Giuseppe Gorini , Andrei Kovalev , Andrea Muraro , Massimo Nocente , Marica Rebai , Davide Rigamonti , Marco Tardocchi , Gabriele Croci
{"title":"Design and development status of the ITER Radial Gamma Ray Spectrometer","authors":"Federico Scioscioli , Giulia Marcer , Alessandro Ciurlino , Stefano Colombi , Bruno Coriton , Andrea Dal Molin , Jan Dankowski , Giuseppe Gorini , Andrei Kovalev , Andrea Muraro , Massimo Nocente , Marica Rebai , Davide Rigamonti , Marco Tardocchi , Gabriele Croci","doi":"10.1016/j.fusengdes.2025.115376","DOIUrl":null,"url":null,"abstract":"<div><div>The ITER Radial Gamma Ray Spectrometer (RGRS) is an ITER diagnostic located in the Equatorial Port 01 undergoing its Preliminary Design Review and foreseen for Phase DT1 (2041). RGRS is expected to measure the density profile and energy distribution of <span><math><mi>α</mi></math></span>-particles through reactions with <sup>10</sup>B, the current and maximum energy of runaway electrons through bremsstrahlung emissions, and fusion power via a radiative channel of the DT reaction. The diagnostic employs LaBr<sub>3</sub> scintillators coupled with PMTs along 4 radial lines of sight, with LiH attenuators to reduce the background due to direct neutrons and a heavily hydrogenated and borated concrete-like mixture for neutron shielding.</div><div>Performance assessments indicate RGRS can fulfil its functions regarding runaway electrons, while the feasibility of measuring <span><math><mi>α</mi></math></span>-particles is uncertain due to the intense gamma-ray background observed at JET. Further study is needed to confirm this measurement possibility. Additionally, while fusion power measurements appear possible, satisfying ITER requirements necessitates detailed knowledge of the gamma-ray-to-neutron branching-ratio of the DT reaction, which will be investigated through dedicated experiments, and possibly gamma-ray attenuators to reduce background.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"221 ","pages":"Article 115376"},"PeriodicalIF":2.0000,"publicationDate":"2025-08-16","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":null,"platform":"Semanticscholar","paperid":null,"PeriodicalName":"Fusion Engineering and Design","FirstCategoryId":"5","ListUrlMain":"https://www.sciencedirect.com/science/article/pii/S0920379625005721","RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"Q1","JCRName":"NUCLEAR SCIENCE & TECHNOLOGY","Score":null,"Total":0}
引用次数: 0
Abstract
The ITER Radial Gamma Ray Spectrometer (RGRS) is an ITER diagnostic located in the Equatorial Port 01 undergoing its Preliminary Design Review and foreseen for Phase DT1 (2041). RGRS is expected to measure the density profile and energy distribution of -particles through reactions with 10B, the current and maximum energy of runaway electrons through bremsstrahlung emissions, and fusion power via a radiative channel of the DT reaction. The diagnostic employs LaBr3 scintillators coupled with PMTs along 4 radial lines of sight, with LiH attenuators to reduce the background due to direct neutrons and a heavily hydrogenated and borated concrete-like mixture for neutron shielding.
Performance assessments indicate RGRS can fulfil its functions regarding runaway electrons, while the feasibility of measuring -particles is uncertain due to the intense gamma-ray background observed at JET. Further study is needed to confirm this measurement possibility. Additionally, while fusion power measurements appear possible, satisfying ITER requirements necessitates detailed knowledge of the gamma-ray-to-neutron branching-ratio of the DT reaction, which will be investigated through dedicated experiments, and possibly gamma-ray attenuators to reduce background.
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.