Plasma and current drive parameter options for a megawatt range fusion neutron source

Kuteev, B. V.; Borisov, A.; Golikov, A.A.; Khripunov, V.I.; Lukash, V.E.; Popova, E.; Savrukhin, P. V.; Goncharov, P. R.; Sergeev, V. Yu.; Gryaznevich, M.

doi:10.1109/fusion.2009.5226382

Cited by 4 publications

(4 citation statements)

References 13 publications

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“…The highest level of neutron production reached so far, a rate of ∼10 18 n s −1 , corresponds to only 3 MW of DT fusion power. This means that relatively small devices with MW range of fusion power may be considered as the first fusion application for neutron production [3] instead of GW range devices typically developed for energy production.…”

Section: Introductionmentioning

confidence: 99%

Steady-state operation in compact tokamaks with copper coils

et al. 2011

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This paper considers a fast track to non-energy applications of nuclear fusion that is associated with the ‘fusion for neutrons’ (F4N) paradigm. Being a useful product accompanying energy, fusion neutrons are more valuable than the energy released in DT reactions and they are urgently needed for research purposes and to develop and validate modern technologies. In the near future neutron yield in fusion devices will become significantly larger than that of fission and accelerator sources. This paper describes a compact tokamak fusion neutron source based on a small spherical tokamak (FNS-ST) with a MW range of DT fusion power and considers the key physics issues of this device. The major and minor radii are ∼0.5 and ∼0.3 m with magnetic field ∼1.5 T, heating power less than 15 MW and plasma current 1–2 MA. The production rate of DT neutrons of (3–10) × 1017 n s−1 and their flux at the first wall of 0.2 MW m−2 ensure that the device is capable of fusion–fission demonstration experiments. The problems of major concern are discharge initiation, current drive, plasma—fast ion beam stability and high first wall and divertor loads. The conceptual design provides solutions to these problems and suggests the feasibility of the FNS-ST.

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Section: Introductionmentioning

confidence: 99%

Steady-state operation in compact tokamaks with copper coils

et al. 2011

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“…Nevertheless, such reactors with power in the range 10-50 MW are considered adequate for testing fusion nuclear technology components or driving sub-critical blankets for breeding [34]. While this paper addresses only the physics aspects of a compact fusion plasma core, the possibility of attaining the neutron flux required for contemporary neutron research and technologies using a low-power tokamak is demonstrated in a recent study [35] and references therein.…”

Section: Discussionmentioning

confidence: 99%

Physics performance analysis of low-power tokamak reactors

Ludwig¹,

Andrade²,

Gryaznevich³

et al. 2009

Nucl. Fusion

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Global models are useful in the analysis of fusion reactors due to the facility in computing and presenting the results in terms of comprehensive parameters. A general figure of merit, which encompasses all the relevant tokamak parameters, is introduced in this paper by a convenient normalization of the global power balance equation. In this way, different hypothetical tokamak reactors can be compared in terms of their figure-of-merit value. This criterion is applied to analyse the performance of both ITER-like reactors and a class of newly proposed low-power reactors.

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“…При концептуальном анализе источников термоядерных нейтронов на основе компактных токама-ков с низким аспектным отношением необходимо определить параметры разряда, обеспечивающие ста-ционарный режим с неиндуктивной генерацией тока [1]. Оптимальная система дополнительного нагрева должна обеспечивать пробой, подъём тока и его стационарное поддержание, что требует применения различных неиндуктивных методов как для создания оптимальных профилей давления плазмы с целью создания максимальной величины бутстреп-тока, так и для непосредственной генерации токов увлече-ния.…”

Section: Introductionunclassified

Choice of Parametres for Steady State Operation in a Compact Токамак

Golikov¹,

Kuteev²

2010

PAST-TF

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В работе обоснован выбор параметров стационарного разряда компактного токамака (большой радиус R = 0,47 м, малый радиус а = 0,27 м, магнитное поле 1,35 Тл), на основе которого проектируется источник нейтронов 14 МэВ. С помощью аналитической модели выполнены расчёты разрядного тока, складывающегося из бутстреп-тока и тока, генерируемого системами дополни-тельного нагрева. В условиях нагрева плазмы пучком дейтерия мощностью P до 15 МВт с энергией до 300 кэВ определены концентрации плазмы, обеспечивающие достижение разрядного тока до 3 МА. Показано, что в рабочих точках мощность синтеза на пучке P fusion находится на уровне единиц мегаватт, а коэффициент усиления мощности синтеза (Q fusion = P fusion /P) составляет около 0,5. Рассмотрены также возможности использования дополняющих нейтральную инжекцию высокочастотных методов генерации тока на основе электронных циклотронных волн (по схеме возбуждения в плазме бернштейновских волн), а также высших гармоник быстрых магнитозвуковых волн. Электронный циклотронный диапазон является эффективным для создания плазмы на начальной стадии разряда. Для подъёма тока на промежуточной стадии и поддержания тока в стационаре совместно с инжекцией пучка могут быть использованы обе схемы.Ключевые слова: токамак, параметры разряда, генерация тока, стационарный режим, мощность синтеза, подъём тока. CHOICE OF PARAMETRES FOR STEADY STATE OPERATION IN A COMPACT ТОКАМАК. A.A. GOLIKOV, B.V. KUTEEV.The choice of parameters for steady state operation of the compact tokamak as a 14 MEV neutron source (the major radius R = 0.47 m, minor radius a = 0.27 m, magnetic field -1.35 Т) is considered. An analytic model is developed for calculating the total plasma current composed of bootstrap current and that generated by auxiliary heating systems. In conditions of plasma heating by the neutral beam with energy of 300 keV and power P of 15 MW it was defined the range of plasma density providing a plasma current up to 3 МА. It is shown that within operation limits the fusion power p fusion produced by beam-plasma interaction maintains at a mw-level, and the power multiplication factor q fusion = p fusion /p is close to 0,5. The possibilities to use high frequency methods of plasma current generation based on electron cyclotron waves (including excitation of bernstein's waves in plasma), and the high harmonics of fast magnetosonic waves are considered in addition to neutral beam injection. The electron cyclotron waves are effective for the plasma start-up stage. Both schemes can be used together with neutral beam injection for plasma ramp -up at an intermediate stage and for plasma current generation in steady state operation.Key words: tokamak, parameters for plasmas discharge, current drive, steady state operation, fusion power, start-up stage. ВВЕДЕНИЕПри концептуальном анализе источников термоядерных нейтронов на основе компактных токама-ков с низким аспектным отношением необходимо определить параметры разряда, обеспечивающие ста-ционарный режим с неиндуктивной генерацией тока [1]. Оптимальная систе...

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Plasma and current drive parameter options for a megawatt range fusion neutron source

Cited by 4 publications

References 13 publications

Steady-state operation in compact tokamaks with copper coils

Steady-state operation in compact tokamaks with copper coils

Physics performance analysis of low-power tokamak reactors

Choice of Parametres for Steady State Operation in a Compact Токамак

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