V. Weinzettl , S. Vartanian , R. Dejarnac , M. Jerab , A. Havranek , F. Jaulmes , M. Dimitrova , D. Naydenkova , COMPASS team
{"title":"First partial pressure measurements using Optical Penning Gauge at the COMPASS tokamak","authors":"V. Weinzettl , S. Vartanian , R. Dejarnac , M. Jerab , A. Havranek , F. Jaulmes , M. Dimitrova , D. Naydenkova , COMPASS team","doi":"10.1016/j.fusengdes.2025.115033","DOIUrl":null,"url":null,"abstract":"<div><div>The Optical Penning Gauge for partial pressure measurements has been successfully implemented in the lower high-field side diagnostic port of the COMPASS tokamak, demonstrating a cost-effective way for resolving deuterium and helium and enabling measurements on timescales of about ten milliseconds. The procedure of its implementation is described in detail. Calibration data for deuterium and helium are discussed, including the effect of deuterium pressure on the helium channel. Time-resolved measurements of the working gas (deuterium) and the main gaseous impurity (helium) show, how helium, used for glow discharge conditioning and typically amounting to 5 - 10 % in the shots, is released from the surface of the tokamak vacuum vessel and the plasma-facing components during the subsequent shot. Behavior of both gases in L-mode, ELM-free and ELMy H-mode regimes and even just after the main (high-current high-temperature) discharge is exemplified. Surprisingly long low-current after-discharges (2 - 3 kA, about 100 ms), predominantly in helium, were observed with the Optical Penning Gauge and confirmed with other diagnostics. Simulations of the breakdown and burn-through phase for COMPASS using the DYON code are introduced, showing reasonable agreement with the measured data.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"216 ","pages":""},"PeriodicalIF":1.9000,"publicationDate":"2025-04-12","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/S0920379625002339","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 Optical Penning Gauge for partial pressure measurements has been successfully implemented in the lower high-field side diagnostic port of the COMPASS tokamak, demonstrating a cost-effective way for resolving deuterium and helium and enabling measurements on timescales of about ten milliseconds. The procedure of its implementation is described in detail. Calibration data for deuterium and helium are discussed, including the effect of deuterium pressure on the helium channel. Time-resolved measurements of the working gas (deuterium) and the main gaseous impurity (helium) show, how helium, used for glow discharge conditioning and typically amounting to 5 - 10 % in the shots, is released from the surface of the tokamak vacuum vessel and the plasma-facing components during the subsequent shot. Behavior of both gases in L-mode, ELM-free and ELMy H-mode regimes and even just after the main (high-current high-temperature) discharge is exemplified. Surprisingly long low-current after-discharges (2 - 3 kA, about 100 ms), predominantly in helium, were observed with the Optical Penning Gauge and confirmed with other diagnostics. Simulations of the breakdown and burn-through phase for COMPASS using the DYON code are introduced, showing reasonable agreement with the measured data.
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.