Design concept of K-DEMO for near-term implementation

Abstract

A Korean fusion energy development promotion law (FEDPL) was enacted in 2007. As a following step, a conceptual design study for a steady-state Korean fusion demonstration reactor (K-DEMO) was initiated in 2012. After the thorough 0D system analysis, the parameters of the main machine characterized by the major and minor radii of 6.8 and 2.1 m, respectively, were chosen for further study. The analyses of heating and current drives were performed for the development of the plasma operation scenarios. Preliminary results on lower hybrid and neutral beam current drive are included herein. A high performance Nb3Sn-based superconducting conductor is adopted, providing a peak magnetic field approaching 16 T with the magnetic field at the plasma centre above 7 T. Pressurized water is the prominent choice for the main coolant of K-DEMO when the balance of plant development details is considered. The blanket system adopts a ceramic pebble type breeder. Considering plasma performance, a double-null divertor is the reference configuration choice of K-DEMO. For a high availability operation, K-DEMO incorporates a design with vertical maintenance. A design concept for K-DEMO is presented together with the preliminary design parameters.

Impurity accumulation and performance of ITER and DEMO plasmas in the presence of transport barriers

“…The design parameters of K-DEMO used in simulations are R = 6.8 m, a = 2.1 m, I p = 12 MA, toroidal field of 7.4 T, κ = 2.0, and δ = 0.625 [23]. For Japanese DEMO, three different models are investigated; model A, model B and model C. The design parameters used in simulations can be seen in table 1 [24].…”

Pre-conceptual design study on K-DEMO ceramic breeder blanket

“…Instead, macroscopic material properties representing status of each pebble and temperature effect are employed [13][14][15]. 2 Neutron wall loading and heat flux onto the blanket first wall from plasma radiation were applied 2.9 MW/m 2 and 0.5 MW/m 2 , respectively. The promising coolant flow path for a blanket model 2 The configurations and the thermo-mechanical behavior of pebbles affect the material properties.…”

“…2 Neutron wall loading and heat flux onto the blanket first wall from plasma radiation were applied 2.9 MW/m 2 and 0.5 MW/m 2 , respectively. The promising coolant flow path for a blanket model 2 The configurations and the thermo-mechanical behavior of pebbles affect the material properties. The study on the non-linear behavior of the pebbles by discrete element method (DEM) is on-going and the result of this study will be able to be reported to a subsequent paper.…”

“…A pre-conceptual design study for the K-DEMO with a steady-state tokamak has been initiated, as a following activity of the FEDPL, with a unique two-phased development; to play the role of fusion nuclear component test facility in Phase I and to generate an order of 500 MW of net electricity in Phase II after upgrade. A selfsufficiency tritium fuel cycle is required to be demonstrated in both phases [1,2]. Based on a system analyses [1][2][3], key features of K-DEMO tokamak have been deduced: a major radius = 6.8 m, a minor radius = 2.1 m, B 0 = 7.4 T, and the up-down symmetric double-null divertor operation with Ä = 2.0 and ı = 0.625 in a steady-state operation.…”

“…A selfsufficiency tritium fuel cycle is required to be demonstrated in both phases [1,2]. Based on a system analyses [1][2][3], key features of K-DEMO tokamak have been deduced: a major radius = 6.8 m, a minor radius = 2.1 m, B 0 = 7.4 T, and the up-down symmetric double-null divertor operation with Ä = 2.0 and ı = 0.625 in a steady-state operation. The concepts of the major components of K-DEMO have been developed (see Fig.…”