optimization activities on design studies of LHD-type reactor FFHR

被引：33

作者：

Sagara, A. ^{[1
]}

Mitarai, O. ^{[2
]}

Tanaka, T. ^{[1
]}

Imagawa, S. ^{[1
]}

Kozaki, Y. ^{[1
]}

Kobayashi, M. ^{[1
]}

Morisaki, T. ^{[1
]}

Watanabe, T. ^{[1
]}

Takahata, K. ^{[1
]}

Tamura, H. ^{[1
]}

Yanagi, N. ^{[1
]}

Nishimura, K. ^{[1
]}

Chikaraishi, H. ^{[1
]}

Yamada, S. ^{[1
]}

Fukada, S. ^{[3
]}

Masuzaki, S. ^{[1
]}

Shishkin, A. ^{[4
]}

Igitkhanov, Y. ^{[5
]}

Goto, T. ^{[6
]}

Ogawa, Y. ^{[6
]}

Muroga, T. ^{[1
]}

Mito, T. ^{[1
]}

Motojima, O. ^{[1
]}

机构：

[1] Natl Inst Nat Sci, Natl Inst Fus Sci, Toki, Gifu 5095292, Japan

[2] Tokai Univ, Kumamoto 8628652, Japan

[3] Kyushu Univ, Fukuoka 8128581, Japan

[4] Kharkov Phys & Technol Inst, UA-108 Kharkov, Ukraine

[5] IPP EURATOM Ass, Max Planck Inst Plasmaphys, Greifswald, Germany

[6] Univ Tokyo, Chiba 2778568, Japan

来源：

FUSION ENGINEERING AND DESIGN | 2008年 / 83卷 / 10-12期

关键词：

Helical reactor; Blanket; COE; Nuclear heating; Superconducting magnet; Ignition;

D O I：

10.1016/j.fusengdes.2008.07.029

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：

Recent activities on optimizing the base design of the large helical device (LHD)-type helical reactor FFHR (force free helical reactor) are presented. Three candidates to secure the blanket space are proposed with the aim of reactor size optimization without deteriorating (x-heating efficiency and by taking cost analyses into account. In this way the key engineering aspects are investigated; from 3D blanket designs, it is demonstrated that the peaking factor of the neutron wall loading is 1.2-1.3 and a blanket covering ratio of over 90% is possible by proposing discrete pumping with a semi-closed shield (DPSS) concept. Helical blanket shaping along the divertor field lines is the next big issue. For large superconducting magnet systems under the maximum nuclear heating of 200w/m(3), cable-in-conduit conductor (CICC) and alternative conductor designs are proposed with a robust design of cryogenic support posts. For access to ignited plasmas, new methods are proposed, in which a long rise-up time over 300s reduces the heating power to 30 MW and a new proportional-integration-derivative (PID) control of the fueling can handle the thermally unstable plasma at high-density operation. This paper focuses on FFHR2m1, which is a modified version of FFHR. (C) 2008 Elsevier B.V. All rights reserved.

引用

页码：1690 / 1695

页数：6

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