Tauro: a ceramic composite structural material self-cooled Pb—17Li breeder blanket concept

Ramírez, Aldas; Caso, Aldo; Giancarli, L.; Bars, N. Le; Chaumat, Gilles; Salavy, J.-F.; Szczepanski, J.

doi:10.1016/s0022-3115(96)00147-x

Cited by 30 publications

(3 citation statements)

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“…The results of detailed analyses are given in [1,8]. In summary, the 1 D-geometry neutronic analysis has shown that this blanket has a sufficient margin for reaching Tritium breeding self-sufficiency.…”

Section: Blanket Performancesmentioning

confidence: 99%

“…When F is much less than one, the Hartmann layers are the main conductors of the return current, and therefore the wall conductivity has no effect on the flow. Using values from Pérez Ramirez [1] and Coen et al [6], the maximum wall conductivity can be estimated corresponding to F = 1 as | w, max =500 V − 1 m − 1 (for comparison, martensitic steel electrical conductivity at 300°C is approximately 1.3× 10 6 V − 1 m − 1 ). Electrical conductivity measurements on the Cerasep ® N3-1 will have to be performed in order to verify this point, also taking into account that neutron irradiation tends to increase the electrical conductivity of insulators.…”

Section: Mhd Analysis For the Pb-17li Front Channelmentioning

confidence: 99%

“…For several years, a self-cooled-type breeding blanket using Pb-17Li as liquid metal for cooling and tritium breeding, and SiC/SiC composites as structural material has been proposed by CEA [1,2]. The main objective for this blanket, the TAURO blanket, is to permit, at least in principle, FPR passive safety due to the very low energy stored in such a system, limiting the amount of radioactive material release during severe accidents.…”

Section: Introductionmentioning

confidence: 99%

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Design requirements for SiC/SiC composites structural material in fusion power reactor blankets

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This paper recalls the main features of the TAURO blanket, a self-cooled Pb-17Li concept using SiC/SiC composites as structural material, developed for FPR. The objective of this design activity is to compare the characteristics of present-day industrial SiC-SiC composites with those required for a fusion power reactor blanket and to evaluate the main needs of further R&D. The performed analyses indicated that the TAURO blanket would need the availability of SiC/SiC composites approximately 10 mm thick with a thermal conductivity through the thickness of approximately 15 Wm − 1 K − 1 at 1000°C and a low electrical conductivity. A preliminary MHD analysis has indicated that the electrical conductivity should not be greater than 500 V − 1 m − 1 . Irradiation effects should be included in these figures. Under these conditions, the calculated pressure drop due to the high Pb-17Li velocity (approximately 1 m s − 1 ) is much lower then 0.1 MPa. The characteristics and data base of the recently developed 3D-SiC/SiC composite, Cerasep ® N3-1, are reported and discussed in relation to the identified blanket design requirements. The progress on joining techniques is briefly reported. For the time being, the best results have been obtained using Si-based brazing systems initially developed for SiC ceramics and whose major issue is the higher porosity of the SiC/SiC composites.

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Section: Blanket Performancesmentioning

confidence: 99%

Section: Mhd Analysis For the Pb-17li Front Channelmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

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