Search for reality of solid breeder blanket for DEMO

被引：41

作者：

Tobita, K. ^{[1
]}

Utoh, H. ^{[1
]}

Liu, C. ^{[1
]}

Tanigawa, H. ^{[1
]}

Tsuru, D. ^{[1
]}

Enoeda, M. ^{[1
]}

Yoshida, T. ^{[1
]}

Asakura, N. ^{[1
]}

机构：

[1] Japan Atom Energy Agcy, Naka, Ibaraki 3110193, Japan

来源：

FUSION ENGINEERING AND DESIGN | 2010年 / 85卷 / 7-9期

关键词：

DEMO; Blanket; TBR; Solid breeder; SlimCS; EFFECTIVE THERMAL-CONDUCTIVITY; PEBBLE BEDS; PLANT; REACTOR; DESIGN; JAERI;

D O I：

10.1016/j.fusengdes.2010.03.038

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：

For a tokamak fusion DEMO reactor with the fusion output of 2.95 GW, neutronic and thermal design of blanket is under way to find a feasible blanket concept. For the continuity with the Japanese ITER-TBM options, this study considered water-cooled blanket with solid breeding materials of Li ceramics (Li(4)SiO(4), Li(2)TiO(3) and Li(2)ZrO(3)) and Be multipliers (Be and Be(12)Ti). Based on a neutronics-heat coupled analysis, the tritium breeding ratio was evaluated so as to satisfy constraints of the operating temperature of <= 900 degrees C for Li ceramics and Be12Ti, and <= 600 degrees C for Be. Cooling water condition was assumed to be 23 MPa and 290-360 degrees C. The result indicates that surplus tritium production in lower neutron wall load (P(n)) blanket compensates a shortfall in higher P(n) blanket and thus the overall tritium production can marginally satisfy fuel self-sufficiency. (c) 2010 Elsevier B.V. All rights reserved.

引用

页码：1342 / 1347

页数：6

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