Consistent integration in preparing the helium cooled lithium lead DEMO-2007 reactor

Li-Puma, A.; Bonnemason, J.; Cachon, L.; Duchateau, J.L.; Gabriel, Franck

doi:10.1016/j.fusengdes.2009.01.097

Cited by 21 publications

(5 citation statements)

References 39 publications

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“…where f neut = 0.8 is the fraction of the fusion power taken by the neutrons in a D-T reaction, and the following parameters are quoted from the European DEMO-2007 project [33]: η inj = 0.6 is the efficiency of the additional heating, M blanket = 1.18 is the energy gain of the blanket neutron multiplication, η nucl+inj = 93.6% is the efficiency with which P fus + P nucl−blanket + P inj is converted into useful heat, η th = 44% is the thermodynamic efficiency of the electric power generation, f pump = 21.4% is the fraction of the gross electric power P e1,g to run the blanket cooling system, and η pump = 91% is the fraction of pumping power P el,pump converted into useful heat. According to equations ( 3) and ( 4), and considering P fus = 1000 MW in the phase II of CFETR, the relation among Q, f recirc and P el,aux can be derived, which is plotted in figure 6.…”

Section: Relationships Among the Auxiliary Power Consumed By The Cryo...mentioning

confidence: 99%

Conceptual design of the cryogenic system and estimation of the recirculated power for CFETR

Liu

Qiu

et al. 2016

Nucl. Fusion

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The China Fusion Engineering Test Reactor (CFETR) is the next tokamak in China’s roadmap for realizing commercial fusion energy. The CFETR cryogenic system is crucial to creating and maintaining operational conditions for its superconducting magnet system and thermal shields. The preliminary conceptual design of the CFETR cryogenic system has been carried out with reference to that of ITER. It will provide an average capacity of 75 to 80 kW at 4.5 K and a peak capacity of 1300 kW at 80 K. The electric power consumption of the cryogenic system is estimated to be 24 MW, and the gross building area is about 7000 m2. The relationships among the auxiliary power consumed by the cryogenic system, the fusion power gain and the recirculated power of CFETR are discussed, with the suggestion that about 52% of the electric power produced by CFETR in phase II must be recirculated to run the fusion test reactor.

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Section: Relationships Among the Auxiliary Power Consumed By The Cryo...mentioning

confidence: 99%

Conceptual design of the cryogenic system and estimation of the recirculated power for CFETR

Liu

Qiu

et al. 2016

Nucl. Fusion

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“…The current blanket module treats only HCLL blankets. It is based on the HCLL design model described in [17]. The module computes the neutron flux from the fusion power provided by the plasma module.…”

Section: Blanket Modulementioning

confidence: 99%

DEMO reactor design using the new modular system code SYCOMORE

et al. 2015

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A demonstration power plant (DEMO) will be the next step for fusion energy following ITER. Some of the key design questions can be addressed by simulations using system codes. System codes aim to model the whole plant with all its subsystems and identify the impact of their interactions on the design choices. The SYCOMORE code is a modular system code developed to address key questions relevant to tokamak fusion reactor design. SYCOMORE is being developed within the European Integrated Tokamak Modelling framework and provides a global view (technology and physics) of the plant. It includes modules to address plasma physics, divertor physics, breeding blankets, shield design, magnet design and the power balance of plant. The code is coupled to an optimization framework which allows one to specify figures of merit and constraints to obtain optimized designs. Examples of pulsed and steady-state DEMO designs obtained using SYCOMORE are presented. Sensitivity to design assumptions is also studied, showing that the operational domain around working points can be narrow for some cases.

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“…This hypothesis led to overestimate the total tritium permeation rate into helium cooling system [14]. Some detailed studies [15], [16] based on Finite Element Method (FEM) models showed that the obtained velocity profiles of Pb-16Li coming from the Magneto Hydro Dynamic (MHD) effects lead tritium to create an effective boundary layer between the liquid metal bulk and the Cooling Plates walls characterizing a resistance to the tritium permeation into the Helium coolant.…”

Section: Mhd Effects On Tritium Distribution In Lithium-leadmentioning

confidence: 99%

Tritium permeation issues for helium-cooled breeding blankets

Franza

Boccaccini

Demange

et al. 2013

2013 IEEE 25th Symposium on Fusion Engineering (SOFE)

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Tritium permeation through Breeding Blanket and Steam Generator heat transfer areas is a crucial aspect for the design of the next generation DEMO fusion power plants. Tritium is generated inside the breeder, dissolves in and permeates through materials, thus leading to a potential hazard for the environment. For this reason it is important to carry out the tritium migration analysis for a specific DEMO blanket configuration in order to predict the released amount of tritium during the plant operation. Unfortunately, tritium assessments are often affected by several uncertainties implying very important modelling and parametric issues. In this study the main permeation issues are identified and possible solutions are discussed to face the modelling issues and the parametric uncertainties affecting the T migration assessments for the two DEMO helium-cooled breeding blankets, i.e.: 1) Helium-Cooled Pebble Beds (HCPB) and 2) Helium-Cooled Lithium-Lead (HCLL). For these two heliumcooled blanket concepts various tritium migration analyses will be carried out by means of the computational tool FUS-TPC in order to define proper and feasible tritium mitigation techniques which are needed to keep the tritium losses lower than the allowable environmental release (i.e. 20 Ci/d).

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Consistent integration in preparing the helium cooled lithium lead DEMO-2007 reactor

Cited by 21 publications

References 39 publications

Conceptual design of the cryogenic system and estimation of the recirculated power for CFETR

Conceptual design of the cryogenic system and estimation of the recirculated power for CFETR

DEMO reactor design using the new modular system code SYCOMORE

Tritium permeation issues for helium-cooled breeding blankets

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