Design and development of the Flibe blanket for helical-type fusion reactor FFHR

被引：59

作者：

Sagara, A ^{[1
]}

Yamanishi, H

Imagawa, S

Muroga, T

Uda, T

Noda, T

Takahashi, S

Fukumoto, K

Yamamoto, T

Matsui, H

Kohyama, A

Hasizume, H

Toda, S

Shimizu, A

Suzuki, A

Hosoya, Y

Tanaka, S

Terai, T

Sze, DK

Motojima, O

机构：

[1] Natl Inst Fus Sci, LHD Project, Res Operat Div, Toki 5095292, Japan

[2] Natl Res Inst Met, Tsukuba, Ibaraki 305, Japan

[3] Tohoku Univ, Inst Mat Res, Sendai, Miyagi 980, Japan

[4] Kyoto Univ, Inst Adv Energy, Uji 611, Japan

[5] Kyushu Univ, Kasuga, Fukuoka 816, Japan

[6] Univ Tokyo, Tokyo 113, Japan

[7] Argonne Natl Lab, Argonne, IL 60439 USA

来源：

FUSION ENGINEERING AND DESIGN | 2000年 / 49-50卷

关键词：

blanket design; Flibe blanket; helical-type fusion reactor FFHR;

D O I：

10.1016/S0920-3796(00)00360-4

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：

Blanket design is in progress in helical-type compact reactor FFHR-2. A localized blanket concept is proposed by selecting molten-salt Flibe as a self-cooling tritium breeder from the main reason of safety: low tritium solubility, low reactivity with air and water, low pressure operation, and low MHD resistance which is compatible with the high magnetic field design in force-free helical reactor (FFHR). Numerical results are presented on nuclear analyses using the MCNP-4B code, on thermal and stress analyses using the ABAQUS code, and heat exchange efficiency from Flibe to He. R&D programs on Flibe engineering are also in progress in material dipping-tests and in construction of molten salt loop. Preliminary results in these experiments are also presented. (C) 2000 Elsevier Science B.V. All rights reserved.

引用

页码：661 / 666

页数：6

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