2006
DOI: 10.1016/j.fusengdes.2005.06.356
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Advanced power core system for the ARIES-AT power plant

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Cited by 25 publications
(20 citation statements)
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“…Based on the progress in the recent experiments and the associated theoretical studies of magnetic confinement fusion, and in the studies of fusion power plant concepts, such as US ARIES, EU PPCS, and the Japanese SSTR series fusion reactor concepts [8][9][10][11][12], as well as ITER, the core plasma parameters of FDS-II are initially designated and optimized by the SYSCODE [13], a coupled physics-engineering/cost-benefit computer system code, which was developed by the FDS team itself. With a major radius of 6 m and a minor radius of 2 m, the fusion power for FDS-II is ∼2.5 GW with 1 GW of electrical power, and the power gain Q reaches 30.…”
Section: Plasma Core and Reactor Configurationmentioning
confidence: 99%
“…Based on the progress in the recent experiments and the associated theoretical studies of magnetic confinement fusion, and in the studies of fusion power plant concepts, such as US ARIES, EU PPCS, and the Japanese SSTR series fusion reactor concepts [8][9][10][11][12], as well as ITER, the core plasma parameters of FDS-II are initially designated and optimized by the SYSCODE [13], a coupled physics-engineering/cost-benefit computer system code, which was developed by the FDS team itself. With a major radius of 6 m and a minor radius of 2 m, the fusion power for FDS-II is ∼2.5 GW with 1 GW of electrical power, and the power gain Q reaches 30.…”
Section: Plasma Core and Reactor Configurationmentioning
confidence: 99%
“…The thermal power collected within the Pb-17Li coolant is transferred to a high efficiency helium gas turbine which utilizes Brayton cycle 9 . The gross electric power output from the Brayton cycle is reduced by the amount needed to operate the blanket and divertor coolant pumps, current drives and various auxiliary functions, such as maintaining the cryogenic temperatures of the magnets, etc.…”
Section: Iib Power Flowmentioning
confidence: 99%
“…The steady state plasma physics for advanced tokamaks is modeled by an algorithm that was originally developed in order to examine the high field compact tokamak burning plasmas for the design study "Fusion Ignition Research Experiment" (FIRE) 8 . The power core and energy conversion systems are modeled based on the ARIES-AT design 9 . The magnetic confinement model resembles the one used for the ARIES-AT in geometry, while the material composition is modified in order to utilize a less advanced technology and a more realistic costing.…”
Section: Introductionmentioning
confidence: 99%
“…A self-cooled Pb-17Li blanket with SiC f /SiC composite as structural material, based on the ARIES-AT blanket design [3] is maintained as a back-up option. It allows for high operation temperature and high performance (with a power cycle efficiency ∼55-60%) but carries a higher development risk mostly due to SiC f /SiC material development.…”
Section: Blanketmentioning
confidence: 99%