Design of the Water-Cooled Ceramic Breeder blanket for CFETR

Liu, Songlin; Chen, Lei; Ma, Xuebin; Cheng, Xiaoman; Lu, Peng; Lei, Mingzhun; Jiang, Kecheng; Zhao, Xin; Wang, Xu‐Jia; Huang, Kai; Wu, Qianying; Wang, Wenjia; Yu, Yi; Ling, Qixin

doi:10.1016/j.fusengdes.2022.113059

Cited by 16 publications

(13 citation statements)

References 26 publications

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“…The geometric architecture and thermal hydraulic design of this solid-type Pb x Li y blanket are derived from the latest design of the water-cooled ceramic breeding blanket (WCCB), which has been comprehensively researched by our group and has been evolved into two versions in view of the optimization of the multi-physical fields [8,22]. As shown in figure 2, the CFETR blanket includes 16 sectors at toroidal angles of 22.5 • , and each sector includes three outboard segments and two inboard segments.…”

Section: Blanket Architecturementioning

confidence: 99%

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Conceptual design of solid-type Pb _x Li _y eutectic alloy breeding blanket for CFETR

Jiang

Wu²,

Chen³

et al. 2023

Nucl. Fusion

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As a key component of the Chinese Fusion Engineering and Test Reactor (CFETR), the blanket is responsible for tritium breeding, neutron shielding and energy conversion. Blankets can be classified into solid and liquidaccording to the form of tritium breeder. Among them, the solid blanket utilizes the pebble beds as both the tritium breeder and neutron multiplier, and it has been a popular scheme due to its advantages, such as good material compatibility and non-magnetohydrodynamic effects. However, it usually adopts beryllium or an alloy (i.e. Be and Be12Ti) for multiplying neutrons, causing a very high cost of the solid blanket due to the scarcity of natural resources of beryllium, and this hinders its development. In this paper, a novel solid blanket utilizing a PbLi eutectic alloy was proposed to make up the above deficiency. Pb83Li17 is usually applied in a liquid blanket due to its lowmelting point. However, this kind of alloy can have a higher melting point by adjusting the atomic ratio of Pb/Li, and thus it can be used in the solid blanket both for the tritium breeder and neutron multiplier. Based on the blanket modular design of CFETR, the optimization of the radial layouts, the atomic ratio of Pb/Li and the packed structure of the pebble beds are studied through neutronic and thermal hydraulic analysis. The results indicate that the solid-type Pb x Li y can satisfy the requirement of tritium self-sufficiency, and the global tritium breeding ratio is larger than 1.0. In addition, the cooling system design can retain the maximum temperature of Pb x Li y at a lower level without melting. Overall, this kind of solid-type Pb x Li y blanket is feasible from the perspective of neutronic and thermal hydraulics, and it avoids using beryllium; thus, the cost is highly reduced.

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Section: Blanket Architecturementioning

confidence: 99%

“…It can be classified into solid and liquid blankets in view of the breeder material state. In the solid blanket design [7][8][9][10], lithium-containing ceramic pebbles (i.e. Li 2 TiO 3 and Li 4 SiO 4 ) are used as the tritium breeder, and an elementary beryllium or alloy (i.e.…”

Section: Introductionmentioning

confidence: 99%

Conceptual design of solid-type Pb _x Li _y eutectic alloy breeding blanket for CFETR

Jiang

Wu²,

Chen³

et al. 2023

Nucl. Fusion

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“…From all these designs and options, experts will decide which TBMs will be used in ITER with a view to their future implementation in DEMO. Because of this, a vast amount of reviews can be found regarding each of them [ 65 , 66 , 67 , 68 , 69 , 70 , 71 , 72 ].…”

Section: Structural Materialsmentioning

confidence: 99%

Materials to Be Used in Future Magnetic Confinement Fusion Reactors: A Review

Alba¹,

Rodríguez²,

Cerdeira³

2022

Materials

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This paper presents the roadmap of the main materials to be used for ITER and DEMO class reactors as well as an overview of the most relevant innovations that have been made in recent years. The main idea in the EUROfusion development program for the FW (first wall) is the use of low-activation materials. Thus far, several candidates have been proposed: RAFM and ODS steels, SiC/SiC ceramic composites and vanadium alloys. In turn, the most relevant diagnostic systems and PFMs (plasma-facing materials) will be described, all accompanied by the corresponding justification for the selection of the materials as well as their main characteristics. Finally, an outlook will be provided on future material development activities to be carried out during the next phase of the conceptual design for DEMO, which is highly dependent on the success of the IFMIF-DONES facility, whose design, operation and objectives are also described in this paper.

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“…This assigns the blanket responsibilities of breeding tritium to make up the tritium consumed in the fusion reactor, extracting energy for electricity generation as well as shielding neutrons for environment protection. There are two candidate blankets for CFETR, including the solid blankets including the Helium Cooled Ceramic Breeder blanket [6] and Water Cooled Ceramic Breeder blanket [7]. The related researches have been performed comprehensively, such as neutronics, thermal hydraulics, mechanics, manufacture and integration, et al However, as the beryllium is adopted as neutron multiplier, the blanket cost is too high due to the beryllium scarcity of natural resources.…”

Section: Introductionmentioning

confidence: 99%

Thermal hydraulic assessment on the full banana model of COOL blanket for CFETR

Jiang,

Chen,

Chen

et al. 2024

Nucl. Fusion

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The Supercritical Carbon Dioxide (S-CO2) cOoled Lithium-Lead (COOL) blanket is under development for Chinese Fusion Engineering and Test Reactor. The thermal hydraulic assessment plays an important role for the comprehensive performance evaluation on the fusion blanket among the multi-physics fields. As the fusion reactor will enter into the engineering construction stage, it is important to study the thermal hydraulics performance on basis of the full model. Because it can accurately check the heat removal capability and thermoelectricity conversion efficiency, as well as provide essential input for the other physical fields. In this demand-driven, the analyses and optimization on the cooling system are put into priority on basis of the full banana model, including the manifold design and inlet/outlet pipes locations. Finally, the coolant pressure drop is highly reduced and the mass flow distribution becomes much more uniformly. For the S-CO2, 82.3% of the total mass flow rate is distributed into the key component first wall, and this is beneficial to face the high radiation heat flux. Besides, under different level of heat flux, the required total mass flow rate and pressure drop are obtained on premise that the coolant has enough ability to safely remove the heat away. For the Lead–Lithium (PbLi), the distribution of mass flow rate is designed as ‘ladder’ shape to adapt the unevenly spatial distributed nuclear heat along the radial direction, and the ratio is 8:2:1. Furthermore, the first law of thermodynamics is adopted for the trade-off analysis, which converts the total pressure drop of the two coolants into the pumping power, and it occupies only 1.3% of the total thermal power. This provides accurate and valuable data for the primary and secondary loop design, as well as the economic assessment on the fusion reactor. Finally, the Two Dimensional thermal hydraulic model containing the detailed layouts of different materials is used to study the coupling heat transfer effects between PbLi and S-CO2, as well as the MagnetoHydroDynamics (MHD) effects. The boundary conditions are derived from the results of full banana model, and the results show that the temperature of all materials is not exceeding the upper limits.

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Design of the Water-Cooled Ceramic Breeder blanket for CFETR

Cited by 16 publications

References 26 publications

Conceptual design of solid-type Pb _x Li _y eutectic alloy breeding blanket for CFETR

Conceptual design of solid-type Pb _x Li _y eutectic alloy breeding blanket for CFETR

Materials to Be Used in Future Magnetic Confinement Fusion Reactors: A Review

Thermal hydraulic assessment on the full banana model of COOL blanket for CFETR

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Design of the Water-Cooled Ceramic Breeder blanket for CFETR

Cited by 16 publications

References 26 publications

Conceptual design of solid-type Pb x Li y eutectic alloy breeding blanket for CFETR

Conceptual design of solid-type Pb x Li y eutectic alloy breeding blanket for CFETR

Materials to Be Used in Future Magnetic Confinement Fusion Reactors: A Review

Thermal hydraulic assessment on the full banana model of COOL blanket for CFETR

Contact Info

Product

Resources

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Conceptual design of solid-type Pb _x Li _y eutectic alloy breeding blanket for CFETR

Conceptual design of solid-type Pb _x Li _y eutectic alloy breeding blanket for CFETR