M. Scholz , U. Wiącek , K. Drozdowicz , A. Jardin , U. Woźnicka , K. Król , A Kurowski , A. Kulińska , W. Dąbrowski , B. Łach , D. Mazon
{"title":"基于气体电子倍增器(GEM)探测器的核聚变反应堆中子谱仪","authors":"M. Scholz , U. Wiącek , K. Drozdowicz , A. Jardin , U. Woźnicka , K. Król , A Kurowski , A. Kulińska , W. Dąbrowski , B. Łach , D. Mazon","doi":"10.1016/j.fusengdes.2025.115480","DOIUrl":null,"url":null,"abstract":"<div><div>Neutron spectrometry is an important diagnostic method that will be used to determine the deuterium to tritium density ratio and the ion temperature in the core plasma of fusion reactors. In the case of ITER, the following spectrometric techniques are foreseen: Thin-foil Proton Recoil (TPR), diamond and time-of-flight detectors. The TPR spectrometer design for ITER includes a system of silicon detectors for the detection of protons resulting from the conversion of neutrons in a polyethylene converter. This arrangement has its drawbacks, one of which is limited resistance of silicon to radiation damage. Therefore, we propose using a Gas Electron Multiplier (GEM) type gas detector, which should have better resistance than silicon-based detectors. The concept and operating principle of a TPR neutron spectrometer based on GEM technology, so-called NS-GEM and intended for future fusion plasma spectrometry applications, is presented. The geometry of the detector and its feasibility study based on numerical calculations are discussed. In particular, the first results of experiments with a NS-GEM demonstrator on the IGN-14 neutron generator are shown.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"222 ","pages":"Article 115480"},"PeriodicalIF":2.0000,"publicationDate":"2025-10-08","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":"{\"title\":\"Neutron spectrometer based on a gas electron multiplier (GEM) detector for fusion reactors\",\"authors\":\"M. Scholz , U. Wiącek , K. Drozdowicz , A. Jardin , U. Woźnicka , K. Król , A Kurowski , A. Kulińska , W. Dąbrowski , B. Łach , D. Mazon\",\"doi\":\"10.1016/j.fusengdes.2025.115480\",\"DOIUrl\":null,\"url\":null,\"abstract\":\"<div><div>Neutron spectrometry is an important diagnostic method that will be used to determine the deuterium to tritium density ratio and the ion temperature in the core plasma of fusion reactors. In the case of ITER, the following spectrometric techniques are foreseen: Thin-foil Proton Recoil (TPR), diamond and time-of-flight detectors. The TPR spectrometer design for ITER includes a system of silicon detectors for the detection of protons resulting from the conversion of neutrons in a polyethylene converter. This arrangement has its drawbacks, one of which is limited resistance of silicon to radiation damage. Therefore, we propose using a Gas Electron Multiplier (GEM) type gas detector, which should have better resistance than silicon-based detectors. The concept and operating principle of a TPR neutron spectrometer based on GEM technology, so-called NS-GEM and intended for future fusion plasma spectrometry applications, is presented. The geometry of the detector and its feasibility study based on numerical calculations are discussed. In particular, the first results of experiments with a NS-GEM demonstrator on the IGN-14 neutron generator are shown.</div></div>\",\"PeriodicalId\":55133,\"journal\":{\"name\":\"Fusion Engineering and Design\",\"volume\":\"222 \",\"pages\":\"Article 115480\"},\"PeriodicalIF\":2.0000,\"publicationDate\":\"2025-10-08\",\"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/S0920379625006763\",\"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}","platform":"Semanticscholar","paperid":null,"PeriodicalName":"Fusion Engineering and Design","FirstCategoryId":"5","ListUrlMain":"https://www.sciencedirect.com/science/article/pii/S0920379625006763","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}
Neutron spectrometer based on a gas electron multiplier (GEM) detector for fusion reactors
Neutron spectrometry is an important diagnostic method that will be used to determine the deuterium to tritium density ratio and the ion temperature in the core plasma of fusion reactors. In the case of ITER, the following spectrometric techniques are foreseen: Thin-foil Proton Recoil (TPR), diamond and time-of-flight detectors. The TPR spectrometer design for ITER includes a system of silicon detectors for the detection of protons resulting from the conversion of neutrons in a polyethylene converter. This arrangement has its drawbacks, one of which is limited resistance of silicon to radiation damage. Therefore, we propose using a Gas Electron Multiplier (GEM) type gas detector, which should have better resistance than silicon-based detectors. The concept and operating principle of a TPR neutron spectrometer based on GEM technology, so-called NS-GEM and intended for future fusion plasma spectrometry applications, is presented. The geometry of the detector and its feasibility study based on numerical calculations are discussed. In particular, the first results of experiments with a NS-GEM demonstrator on the IGN-14 neutron generator are shown.
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.