Physics requirements on fuel throughput in ITER

Kukushkin, A.S.; Polevoi, A.; Pacher, H.D.; Pacher, G.W.; Pitts, R.A.

doi:10.1016/j.jnucmat.2010.08.050

Cited by 55 publications

(62 citation statements)

References 11 publications

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“…The pellet frequency is increased in 3 steps as seen in figure 1a. At the initial pellet rate 7.5 pel f Hz = the density changes only marginally. By doubling the pellet rate to 15 pel f Hz = the density increases and it is restored to pre-RMP values.…”

Section: Introductionmentioning

confidence: 91%

“…The numerical value of this parameter is controlled by the physics of transport mechanism. For example in case of convective ELMs, , / / is the fraction of heat flux transported by ELMs [7]. Therefore this parameter provides a useful constraint for the plasma pedestal temperature, in particular it shows that, for a given power and character of pedestal transport, the pedestal temperature is inversely proportional to the fuelling flux.…”

Section: Energy Confinementmentioning

confidence: 99%

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Pellet refuelling of particle loss due to ELM mitigation with RMPs in the ASDEX Upgrade tokamak at low collisionality

et al. 2016

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Abstract. The complete refuelling of the plasma density loss (pump-out) caused by mitigation of Edge Localised Modes (ELMs) is demonstrated on the ASDEX Upgrade tokamak. The plasma is refuelled by injection of frozen deuterium pellets and ELMs are mitigated by external resonant magnetic perturbations (RMPs). In this experiment relevant dimensionless parameters, such as relative pellet size, relative RMP amplitude and pedestal collisionality are kept at the ITER like values. Refuelling of density pump out of the size of /~30% n n ∆ requires a factor of two increase of nominal fuelling rate. Energy confinement and pedestal temperatures are not restored to pre-RMP values by pellet refuelling.

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Section: Introductionmentioning

confidence: 91%

Section: Energy Confinementmentioning

confidence: 99%

Pellet refuelling of particle loss due to ELM mitigation with RMPs in the ASDEX Upgrade tokamak at low collisionality

et al. 2016

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“…However, it should be noted that, following the H-mode transition, the plasma density and temperature increase. This density increase, which in ITER is more moderate than in present experiments due to the low core fuelling efficiency by recycling neutrals [36][37][38], together with the need to maintain a margin above the H-mode threshold in order to obtain high confinement H-mode plasmas implies that the power required to sustain high confinement H-mode plasmas is larger than the L-H power thresholds given in the estimates above. Indeed the requirements regarding the minimum density for unrestricted NBI heating of ITER plasmas with acceptable shine-through loads apply to the H-mode stationary phase and not to the L-H mode access phase.…”

Section: Access and Sustainment Of H-modesmentioning

confidence: 86%

Heating neutral beams for ITER: negative ion sources to tune fusion plasmas

et al. 2017

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Neutral beam injection (NBI) based on a negative ion source is one of the basic heating and current drive systems designed for ITER required to reach its goals of the operation with high fusion power, P fus ∼500 MW with fusion gain, Q=10 for 400 s in a baseline scenario, and P fus >250 MW, Q=5 operation for 3600 s in an advanced scenario. A total power of 33 MW from the two heating neutral beam (HNB) injectors is envisaged in the present scenario. The scope of the present paper is to provide an overview of the main aspects of the interaction of the HNBs with the ITER plasma. Various operational scenarios with different mixtures of the main ion species, He, H, DD and DT, foreseen at different phases of the ITER operation are considered.

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“…Кукушкин (Организация ИТЭР) представил доклад о физических требованиях к системе подачи топлива в ИТЭР [42]. Эта система будет выполнять пять функций:…”

Section: день четвёртыйunclassified

19th INTERNATIONAL CONFERENCE ON PLASMA SURFACE INTERACTIONS IN CONTROLLED FUSION DEVICES (PSI-19) (SAN DIEGO, USA, 24—28 MAY 2010)

Kolbasov¹

2010

PAST-TF

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Приводится краткий обзор наиболее интересных, по мнению автора, обзорных и приглашённых лекций и устных докладов, прочи-танных на конференции. Они были посвящены в основном нерешённым технологическим проблемам, связанным с сооружением международного термоядерного экспериментального реактора ИТЭР: применению вольфрамовых мишеней в диверторе, локаль-ным и переменным тепловым нагрузкам на первую стенку и дивертор, возможности уменьшить удержание трития в токамаках с углеродными мишенями дивертора, подавлению срывов плазмы и локализованных периферийных мод (ЛПМ).Ключевые слова: ИТЭР, токамак, дивертор, первая стенка, вольфрам. , 24-28 MAY 2010). B.N. KOLBASOV. The author presents a brief overview of the most interesting, in his opinion, review, invited and oral presentations delivered at the conference. They were addressed mainly to unsolved technological problems connected with the construction of International Thermonuclear Experimental Reactor ITER: application of tungsten divertor targets, local and transient heat loads on the first wall and divertor, ability to decrease tritium retention in tokamaks with carbon divertor targets, suppression of plasma disruptions and edge localized modes (ELMs). 19th INTERNATIONAL CONFERENCE ON PLASMA SURFACE INTERACTIONS IN CONTROLLED FUSION DEVICES (PSI-19) (SAN DIEGO, USA

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Physics requirements on fuel throughput in ITER

Cited by 55 publications

References 11 publications

Pellet refuelling of particle loss due to ELM mitigation with RMPs in the ASDEX Upgrade tokamak at low collisionality

Pellet refuelling of particle loss due to ELM mitigation with RMPs in the ASDEX Upgrade tokamak at low collisionality

Heating neutral beams for ITER: negative ion sources to tune fusion plasmas

19th INTERNATIONAL CONFERENCE ON PLASMA SURFACE INTERACTIONS IN CONTROLLED FUSION DEVICES (PSI-19) (SAN DIEGO, USA, 24—28 MAY 2010)

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