Economic goals and requirements for competitive fusion energy

Miller, R.L.

doi:10.1016/s0920-3796(98)00120-3

Cited by 12 publications

(6 citation statements)

References 20 publications

(15 reference statements)

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“…In the design of Demo-CREST, current ramp-up is mainly supported by CS coils, as mentioned in section 2. In equation (2), it is assumed that all the available magnetic flux can be used for plasma current ramp-up; however, the ramp-up scenario should be constructed under the constraints of plasma equilibrium, CS and PF coil capacity, transition from limiter to divertor configuration, plasma performance and so on. In this section, the precise analysis for plasma equilibrium and ramp-up scenario with the two-dimensional plasma equilibrium code TOSCA [31] is carried out in order to ensure consistency between the plasma current ramp-up scenario and engineering constraints.…”

Section: Plasma Equilibrium Analysis and Current Ramp-up Scenariomentioning

confidence: 99%

“…By using this two-point model, the total radiation power required to achieve q div 10 MW m −2 for each operation point (from OP1 to OP4) of Demo-CREST is investigated, and the results together with the ITER and CREST results are plotted in figure 12. In this figure, the upstream SOL density of Demo-CREST is assumed to be 2 3 of the core plasma density, which is somewhat mitigated compared to that of ITER and CREST. In the Demo-CREST operation, the total radiation power has to be increased step by step, and that of OP4 for Demo-CREST finally becomes a little larger than that of CREST.…”

Section: Operation Condition For the Sol-divertor Plasmamentioning

confidence: 99%

“…It is time to begin practical discussions on how to introduce fusion energy smoothly into the world energy market. The potential of fusion energy as a long-term energy source has been investigated for tokamak-type fusion power plants [1][2][3]. Tokimatsu et al [1] investigated the relationship between the introduction year and the breakeven cost of electricity (COE) for fusion energy under the constraint of CO 2 concentration in a long-term world energy scenario.…”

Section: Introductionmentioning

confidence: 99%

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Demonstration tokamak fusion power plant for early realization of net electric power generation

et al. 2005

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A demonstration tokamak fusion power plant Demo-CREST is proposed as the device for early realization of net electric power generation by fusion energy. The plasma configuration for Demo-CREST is optimized to satisfy the electric breakeven condition (the condition for net electric power, ) with the plasma performance of the ITER reference operation mode. This optimization method is considered to be suitable for the design of a demonstration power plant for early realization of net electric power generation, because the demonstration power plant has to ensure the net electric generation. Plasma performance should also be more reliably achieved than in past design studies. For the plasma performance planned in the present ITER programme, net electric power from 0 to 500 MW is possible with Demo-CREST under the following engineering conditions: maximum magnetic field 16 T, thermal efficiency 30%, NBI system efficiency 50% and NBI current drive power restricted to 200 MW. By replacing the blanket system with one of higher thermal efficiency, a net electric power of about 1000 MW is also possible so that the performance of the commercial plant with Demo-CREST can also be studied from the economic point of view. The development path from the experimental reactor ‘ITER’ to the commercial plant ‘CREST’ through the demonstration power plant ‘Demo-CREST’ is proposed as an example of the fast track concept.

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Section: Plasma Equilibrium Analysis and Current Ramp-up Scenariomentioning

confidence: 99%

Section: Operation Condition For the Sol-divertor Plasmamentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

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Demonstration tokamak fusion power plant for early realization of net electric power generation

et al. 2005

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“…Moreover, it should be noted that the economic break-even conditions discussed here are not suffi cient conditions. Several economic analyses on fusion power plants have been carried out [13][14][15]. For example, Okano et al carried out an economic comparison of fusion power plant with other energy sources including future innovative technologies, e.g., a fast breeding reactor, a light water reactor based on uranium from sea water, a fossil fuel plant with CO 2 control, a geothermal energy plant, a wind power plant, an ocean thermal energy conversion plant, and a solar power plant, as shown in Fig.…”

Section: How To Clarify Forthcoming Break-even Conditions ?mentioning

confidence: 99%

Forthcoming Break-Even Conditions of Tokamak Plasma Performance for Fusion Energy Development

Hiwatari

Okano

Asaoka

et al. 2005

J. Plasma Fusion Res.

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The present study reveals forthcoming break-even conditions of tokamak plasma performance for the fusion energy development. The fi rst condition is the electric break-even condition, which means that the gross electric power generation is equal to the circulating power in a power plant. This is required for fusion energy to be recognized as a suitable candidate for an alternative energy source. As for the plasma performance (normalized beta value β N , confi nement improvement factor for H-mode HH, the ratio of plasma density to Greenwald density fn GW ), the electric break-even condition requires the simultaneous achievement of 1.2 < β N < 2.7, 0.8 < HH, and 0.3 < fn GW < 1.1 under the conditions of a maximum magnetic fi eld on the TF coil B tmax = 16 T, thermal effi ciency η e = 30%, and current drive power P NBI < 200 MW. It should be noted that the relatively moderate conditions of β N ~ 1.8, HH ~ 1.0, and fn GW ~ 0.9, which correspond to the ITER reference operation parameters, have a strong potential to achieve the electric break-even condition. The second condition is the economic break-even condition, which is required for fusion energy to be selected as an alternative energy source in the energy market. By using a long-term world energy scenario, a break-even price for introduction of fusion energy in the year 2050 is estimated to lie between 65 mill/kWh and 135 mill/kWh under the constraint of 550 ppm CO 2 concentration in the atmosphere. In the present study, this break-even price is applied to the economic break-even condition. However, because this break-even price is based on the present energy scenario including uncertainties, the economic break-even condition discussed here should not be considered the suffi cient condition, but a necessary condition. Under the conditions of B tmax = 16 T, η e = 40%, plant availability 60%, and a radial build with/without CS coil, the economic break-even condition requires β N ~ 5.0 for 65 mill/kWh of lower break-even price case. Finally, the present study reveals that the demonstration of steady-state operation with β N ~ 3.0 in the ITER project leads to the upper region of the break-even price in the present world energy scenario, which implies that it is necessary to improve the plasma performance beyond that of the ITER advanced plasma operation. keywords: fusion power plant, plasma performance, tokamak, break-even condition

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“…The ARIES-RS design was guided by the toplevel requirements discussed in Section 2 and Table 1 [13,[21][22][23][24]. A high performance plasma core operating in the reversed-shear mode is chosen (see Fig.…”

Section: Aries-rsmentioning

confidence: 99%