Progress in the engineering design and assessment of the European DEMO first wall and divertor plasma facing components

被引：84

作者：

Barrett, Thomas R. ^{[1
]}

Ellwood, G. ^{[1
]}

Perez, G. ^{[1
]}

Kovari, M. ^{[1
]}

Fursdon, M. ^{[1
]}

Domptail, F. ^{[1
]}

Kirk, S. ^{[1
]}

McIntosh, S. C. ^{[1
]}

Roberts, S. ^{[1
]}

Zheng, S. ^{[1
]}

Boccaccini, L. V. ^{[2
]}

You, J. -H. ^{[3
]}

Bachmann, C. ^{[4
]}

Reiser, J. ^{[5
]}

Rieth, M. ^{[5
]}

Visca, E. ^{[6
]}

Mazzone, G. ^{[6
]}

Arbeiter, F. ^{[2
]}

Domalapally, P. K. ^{[7
]}

机构：

[1] CCFE, Culham Sci Ctr, Abingdon OX14 3DB, Oxon, England

[2] KIT, INR, Hermann von Helmholtz Pl 1, D-76344 Eggenstein Leopoldshafen, Germany

[3] Max Planck Inst Plasma Phys, Boltzmannstr 2, D-85748 Garching, Germany

[4] EUROfusion, PPPT, Boltzmann Str 2, D-85748 Garching, Germany

[5] KIT, IAM, Hermann von Helmholtz Pl 1, D-76344 Eggenstein Leopoldshafen, Germany

[6] ENEA, Unita Tecn Fus, ENEA CR Frascati, Via E Fermi 45, I-00044 Frascati, Italy

[7] Res Ctr Rez, Hlavni 130, Husinec Rez 25068, Czech Republic

来源：

FUSION ENGINEERING AND DESIGN | 2016年 / 109卷

基金：

英国工程与自然科学研究理事会;

关键词：

EUROfusion; DEMO; Plasma-facing component; Design; RESEARCH-AND-DEVELOPMENT; LITHIUM LEAD BLANKET; EUROFER;

D O I：

10.1016/j.fusengdes.2016.01.052

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：

The European DEMO power reactor is currently under conceptual design within the EUROfusion Consortium. One of the most critical activities is the engineering of the plasma-facing components (PFCs) covering the plasma chamber wall, which must operate reliably in an extreme environment of neutron irradiation and surface heat and particle flux, while also allowing sufficient neutron transmission to the tritium breeding blankets. A systems approach using advanced numerical analysis is vital to realising viable solutions for these first wall and divertor PFCs. Here, we present the system requirements and describe bespoke thermo-mechanical and thermo-hydraulic assessment procedures which have been used as tools for design. The current first wall and divertor designs are overviewed along with supporting analyses. The PFC solutions employed will necessarily vary around the wall, depending on local conditions, and must be designed in an integrated manner by analysis and physical testing. (C) 2016 EURATOM/CCFE Fusion Association. Published by Elsevier B.V. All rights reserved.

引用

页码：917 / 924

页数：8

共 22 条

[1] Development of the Helium Cooled Lithium Lead blanket for DEMO [J].

Aiello, G. ;

Aubert, J. ;

Jonqueres, N. ;

Puma, A. Li ;

Morin, A. ;

Rampal, G. .

FUSION ENGINEERING AND DESIGN, 2014, 89 (7-8) :1444-1450

[2]

[Anonymous], 2012, G74MA8010528W02 ITER

[3]

Arbeiter F., 2015, ISFNT 12

[4] Optimization of the first wall for the DEMO water cooled lithium lead blanket [J].

Aubert, Julien ;

Aiello, Giacomo ;

Bachmann, Christian ;

Di Maio, Pietro Alessandro ;

Giammusso, Rosario ;

Li Puma, Antonella ;

Morin, Alexandre ;

Tincani, Amelia .

FUSION ENGINEERING AND DESIGN, 2015, 98-99 :1206-1210

[5] Enhancing the DEMO divertor target by interlayer engineering [J].

Barrett, T. R. ;

McIntosh, S. C. ;

Fursdon, M. ;

Hancock, D. ;

Timmis, W. ;

Coleman, M. ;

Rieth, M. ;

Reiser, J. .

FUSION ENGINEERING AND DESIGN, 2015, 98-99 :1216-1220

[6]

Boccaccini L.V., 2015, ISFNT 12

[7]

Coleman M., 2015, ISFNT 12

[8]

Crofts O., 2015, ISFNT 12

[9]

Domalapally P. K., 2015, ISFNT 12

[10] Overview of EU DEMO design and R&D activities [J].

Federici, G. ;

Kemp, R. ;

Ward, D. ;

Bachmann, C. ;

Franke, T. ;

Gonzalez, S. ;

Lowry, C. ;

Gadomska, M. ;

Harman, J. ;

Meszaros, B. ;

Morlock, C. ;

Romanelli, F. ;

Wenninger, R. .

FUSION ENGINEERING AND DESIGN, 2014, 89 (7-8) :882-889

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