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

被引:24
|
作者
Park, Jong Sung [1 ]
Kwon, Sungjin [1 ]
Im, Kihak [1 ]
Kim, Keeman [1 ]
Brown, Thomas [2 ]
Neilson, George [2 ]
机构
[1] Natl Fus Res Inst, Daejeon 305333, South Korea
[2] Princeton Plasma Phys Lab, Princeton, NJ 08543 USA
关键词
K-DEMO; Ceramic breeder blanket; TBR; Neutron shielding; Lithium ortho-silicate; Beryllide; ARIES-AT;
D O I
10.1016/j.fusengdes.2015.05.018
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
A pre-conceptual design study has been carried out for the Korean fusion demonstration reactor (K-DEMO) tokamak featured by high magnetic field (B-ro = 7.4T), R=6.8 m, a = 2.1 m, and a steady-state operation. The design concepts of the K-DEMO blanket system considering the cooling in-vessel components with pressurized water and a solid pebble breeder are described herein. The structure of the K-DEMO blanket is toroidally subdivided into 16 inboard and 32 outboard sectors, in order to allow the vertical maintenance. Each blanket module is composed of plasma-facing first wall, layers of breeding parts, shielding and manifolds. A ceramic breeder using Li4SiO4 pebbles with Be12Ti as neuron multiplier is employed for study. MCNP neutronic simulations and thermo-hydraulic analyses are interactively performed in order to satisfy two key aspects: achieving a global Tritium Breeding Ratio (TBR) > 1.05 and operating within the maximum allowable temperature ranges of materials. (C) 2015 Elsevier B.V. All rights reserved.
引用
收藏
页码:159 / 165
页数:7
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