نوع مقاله : مقاله پژوهشی

نویسندگان

1 پژوهشکده‌ی پلاسما و گداخت هسته‌ای، پژوهشگاه علوم و فنون هسته‌ای، سازمان انرژی اتمی، صندوق پستی: 51113-14399، تهران - ایران

2 دانشکده‌ی فیزیک و مهندسی انرژی، دانشگاه صنعتی امیرکبیر، صندوق پستی: 4413-15875، تهران- ایران

چکیده

در این مقاله، با استفاده از نرم‌افزار کامسول به طراحی و شبیه­سازی یک منبع تولید یون براساس مولد پلاسمای چگال هلیکونی و سیستم استخراج‎کننده متناسب با آن جهت استفاده در طراحی سامانه گرمایش تزریق باریکه خنثی برای یک توکامک نمونه مانند توکامک دماوند پرداخته شده است. براساس محاسبات جهت افزایش دمای الکترونی پلاسمای این توکامک به 300 الکترون ولت و دمای یونی به 150 الکترون ولت، این توکامک نیازمند یک سامانه تزریق باریکه خنثی با انرژی 5/4 کیلوالکترون ولت، جریان 7/6 آمپر و توان 15/30 کیلووات می‌باشد. در این راستا در مدل‌سازی حاضر یک سیستم مولد پلاسمای هلیکونی با چگالی 1018×51/5 یک بر مترمکعب، دمای الکترونیپلاسما 8/2 الکترونولت و سیستم استخراج‌کننده‌ای با 280 حفره (قطر 5/3 میلی ­متر) و جریان باریکه یونی 7 آمپر، جهت استفاده در طراحی این سامانه گرمایشی، طراحی و شبیه‌سازی و ارایه شده است. هم­‌چنین در این طراحی تمامی مسایل نوری باریکه یونی از قبیل واگرایی، بار فضایی، و قطر باریکه که می‌‎تواند بر کیفیت باریکه تأثیر بگذارد، مورد بررسی قرار گرفته است.

کلیدواژه‌ها

عنوان مقاله [English]

Design of ion beam source for a sample tokamak neutral beam injection heating system

نویسندگان [English]

  • S. Fazelpour 1
  • A. Chakhmachi 1
  • H. Sadeghi 2

1 Plasma and Nuclear Fusion Research School, Nuclear Science and Technology Research Institute, AEOI, P.O.Box: 14399-51113, Tehran – Iran

2 Department of the Energy Engineering and Physics, Amirkabir University of Technology, P.O.Box: 15875-4413, Tehran – Iran

چکیده [English]

In this paper, the design and simulation of ion source based on a helicon plasma generator and its corresponding extraction system for design of the neutral beam injection heating system of a sample tokamak like Damavand tokamak using COMSOL software have been investigated. Based on our previous calculations, to increase the electron temperature of this tokamak to 300 eV and the ion temperature to 150 eV, it requires a neutral beam injection system with energy 4.5 KeV, 6.7 A current, and 30.15 kW power. In this regard, in the present model, a dense helicon plasma source with an electron density of 5.51×1018 m-3, an electron temperature of 2.8 eV and an extraction system with 280 holes (3.5 mm in diameter) and 7 A ion beam for this heating system were designed, simulated and presented. Also, in this design, all the optical issues of the ion beam such as divergence, space charge, and beam size which can affect the beam quality are investigated.

کلیدواژه‌ها [English]

  • NBI system
  • Ion source
  • Beam extraction
  • Tokamak
  • Space charge
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