Neutronic analysis of a dual He/LiPb coolant breeding blanket for DEMO

被引：8

作者：

Catalan, J. P. ^{[1
]}

Ogando, F. ^{[1
,3
]}

Sanz, J. ^{[1
,3
]}

Palermo, I. ^{[2
]}

Veredas, G. ^{[2
]}

Gomez-Ros, J. M. ^{[2
]}

Sedano, L. ^{[2
]}

机构：

[1] UNED, Dept Ingn Energet, Madrid 28040, Spain

[2] CIEMAT, E-28040 Madrid, Spain

[3] UPM, Inst Fus Nucl, Madrid, Spain

来源：

FUSION ENGINEERING AND DESIGN | 2011年 / 86卷 / 9-11期

关键词：

Blanket; Fusion; Neutronics; TBR; Shielding; Damage; ITER;

D O I：

10.1016/j.fusengdes.2011.03.030

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 conceptual design of a DEMO fusion reactor is being developed under the Spanish Breeding Blanket Technology Programme: TECNO_FUS based on a He/LiPb dual coolant blanket as reference design option. The following issues have been analyzed to address the demonstration of the neutronic reliability of this conceptual blanket design: power amplification capacity of the blanket, tritium breeding capability for fuel self-sufficiency, power deposition due to nuclear heating in superconducting coils and material damage (dpa, gas production) to estimate the operational life of the steel-made structural components in the blanket and vacuum vessel (VV). In order to optimize the shielding of the coils different combinations of water and steel have been considered for the gap of the VV. The used neutron source is based on an axisymmetric 20 fusion reaction profile for the given plasma equilibrium configuration. MCNPX has been used for transport calculations and ACAB has been used to handle gas production and damage energy cross sections. (C) 2011 Elsevier B.V. All rights reserved.

引用

页码：2293 / 2296

页数：4

共 11 条

[1] The ITER design [J].