The EU advanced dual coolant blanket concept

Norajitra, P.; Bühler, L.; Fischer, U.; Malang, S.; Reimann, G.; Schnauder, H.

doi:10.1016/s0920-3796(02)00107-2

Cited by 57 publications

(27 citation statements)

References 5 publications

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“…The liquid lithium lead (LiPb) breeder blanket concept has been explored extensively in the world as a design option of DEMO blankets for fusion power reactors due to their potential attractiveness of economy, safety and relatively mature technology base [1][2][3][4][5]. A series of LiPb blanket concepts based on the up-to-date fusion technology have been designed and assessed by the fusion design study (FDS) team in China [6][7][8][9][10].…”

Section: Introductionmentioning

confidence: 99%

Design analysis of the China dual-functional lithium lead (DFLL) test blanket module in ITER

2007

Fusion Engineering and Design

157

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Section: Introductionmentioning

confidence: 99%

Design analysis of the China dual-functional lithium lead (DFLL) test blanket module in ITER

2007

Fusion Engineering and Design

157

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“…12) Fusion power reactor design studies assume that SiC/SiC composites can be used in gas-cooled solidbreeding blankets [13][14][15][16] and helium/Pb-Li dual-coolant blankets. 17,18) Some of the dual-coolant blanket concepts, including the US-proposed Test Blanket Module (TBM) for the International Thermonuclear Experimental Reactor (ITER), utilize channel inserts made of SiC or SiC/SiC as an electrical and thermal insulator. 19) Among various processing techniques for matrix densification of SiC/SiC composites, chemical vapor infiltration (CVI) is the technique that produces reference materials for nuclear applications.…”

Section: Introductionmentioning

confidence: 99%

Mechanical Properties of Chemically Vapor-Infiltrated Silicon Carbide Structural Composites with Thin Carbon Interphases for Fusion and Advanced Fission Applications

et al. 2005

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Fast fracture properties of chemically vapor-infiltrated silicon carbide matrix composites with Hi-NicalonÔ Type-S near-stoichiometric silicon carbide fiber reinforcements and thin pyrolytic carbon interphase were studied. The primary emphasis was on preliminary assessment of the applicability of a very thin pyrolytic carbon interphase between fibers and matrices of silicon carbide composites for use in nuclear environments. It appears that the mechanical properties of the present composite system are not subject to strong interphase thickness effects, in contrast to those in conventional non-stoichiometric silicon carbide-based fiber composites. The interphase thickness effects are discussed from the viewpoints of residual thermal stress, fiber damage, and interfacial friction. A preliminary conclusion is that a thin pyrolytic carbon interphase is beneficial for fast fracture properties of stoichiometric silicon carbide composites.

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“…In different blanket concepts Li17Pb is foreseen as tritium breeder and neutron multiplier: in different blanket concepts, Helium Coolant Lithium-Lead (HCLL), Water Coolant Lithium Lead (WCLL), Dual Coolant (DCLL) etc being HCLL concept selected as EU Test Blanket Module (TBM) to be tested in ITER 2 . Much experimental and theoretical work has been done in the past years, covering many aspects of compatibility between PbLi and its environment.…”

Section: Interest Of Pb and LI In The Context Of Fusion Energymentioning

confidence: 99%

“…Heat capacity at constant volume, C v , can be calculated once the system is in equilibrium from energy fluctuations as: (2) But experimental heat capacity values are usually measured at constant pressure, C p . These two quantities are related by the well know relation C p -C v =VTα 2 /β T where α is the coefficient of thermal expansion and β T is the isothermal compressibility.…”

Section: Ivc Study Of Thermodynamical Propertiesmentioning

confidence: 99%