Research frontier of tritium for fusion reactor – toward the DEMO reactor (8)
نویسندگان
چکیده
منابع مشابه
Design of the DEMO Fusion Reactor Following ITER
Runs of the NSTAB nonlinear stability code show there are many three-dimensional (3D) solutions of the advanced tokamak problem subject to axially symmetric boundary conditions. These numerical simulations based on mathematical equations in conservation form predict that the ITER international tokamak project will encounter persistent disruptions and edge localized mode (ELMS) crashes. Test par...
متن کاملHow the Demo Fusion Reactor Should Look If Iter Fails
Runs of the NSTAB equilibrium and stability code show there are many 3D solutions of the advanced tokamak problem subject to axially symmetric boundary conditions. These numerical simulations based on mathematical equations in conservation form predict that the ITER project will encounter pervasive disruptions and ELMs crashes. Test particle runs of the TRAN Monte Carlo code suggest that for qu...
متن کاملEffect on the Tritium Breeding Ratio for a distributed ICRF antenna in a DEMO reactor
The paper reports results of MCNP-5 calculations to assess the effect on the Tritium Breeding Ratio (TBR) when integrating a distributed Ion Cyclotron Range of Frequencies (ICRF) antenna in the blanket of DEMO fusion power reactor. The calculations consider different parameters such as the ICRF covering ratio and the type of breeding blanket including the Helium Cooled Pebble Bed (HCPB) and the...
متن کاملTokamak Reactor System Analysis Code for the Conceptual Development of Demo Reactor
The development strategy of nuclear fusion energy in the Korea National Basic Plan for the Development of Fusion Energy consists of several major programs. These are shown in Fig. 1, and include KSTAR for the study of a long-pulse, advanced tokamak operation, ITER for a burning plasma experiment, the DEMO reactor for the demonstration of producing net electricity from a fusion reactor, and a co...
متن کاملNumerical Simulation Analysis for the Divertor Plate of DEMO Reactor
The hydraulic simulation and structure coupled analysis were used to explore critical heat flux (CHF) margin of the W (tungsten) armour and the accommodation of the thermal stress between the cooling tube and the W armour. The t (wall thickness of the F82H tube) variation or as a constant were considered to analysis the heat removal capability of the cooling tube. It was found a nonlinear distr...
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ژورنال
عنوان ژورنال: Journal of the Atomic Energy Society of Japan
سال: 2019
ISSN: 1882-2606,2433-7285
DOI: 10.3327/jaesjb.61.2_138