Overview of the DEMO staged design approach in Europe

被引：205

作者：

Federici, G. ^{[1
]}

Bachmann, C. ^{[1
]}

Barucca, L. ^{[2
]}

Baylard, C. ^{[1
]}

Biel, W. ^{[3
]}

Boccaccini, L., V ^{[4
]}

Bustreo, C. ^{[5
]}

Ciattaglia, S. ^{[1
]}

Cismondi, F. ^{[1
]}

Corator, V ^{[6
]}

Day, C. ^{[4
]}

Diegele, E. ^{[1
]}

Franke, T. ^{[1
]}

Gaio, E. ^{[5
]}

Gliss, C. ^{[1
]}

Haertl, T. ^{[7
]}

Ibarra, A. ^{[8
]}

Holden, J. ^{[1
]}

Keech, G. ^{[1
]}

Kembleton, R. ^{[1
]}

Loving, A. ^{[9
]}

Maviglial, F. ^{[1
]}

Morris, J. ^{[9
]}

Meszaros, B. ^{[1
]}

Moscato, I ^{[10
]}

Pintsuk, G. ^{[3
]}

Sicciniol, M. ^{[1
]}

Taylor, N. ^{[9
]}

Tran, M. Q. ^{[11
]}

Vorpahl, C. ^{[1
]}

Walden, H. ^{[1
]}

You, J. H. ^{[7
]}

机构：

[1] EUROfus Consortium, Boltzmannstr 2, D-85748 Garching, Germany

[2] Ansaldo Nucl, Corso Perrone 25, I-16152 Genoa, Italy

[3] Forschungszentrum Julich, Julich, Germany

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

[5] Consorzio RFX, Cso Stati Uniti 4, I-35127 Padua, Italy

[6] ENEA, CR Frascati, I-00044 Rome, Italy

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

[8] CIEMAT, Avda Complutense 40, Madrid 28040, Spain

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

[10] Univ Palermo, Dipartimento Energia Ingn Informaz & Modelli Mate, Viale Sci, I-90128 Palermo, Italy

[11] Ecole Polytech Fed Lausanne, Swiss Plasma Ctr, Stn 13, CH-1015 Lausanne, Switzerland

来源：

NUCLEAR FUSION | 2019年 / 59卷 / 06期

关键词：

DEMO; fusion reactor; systems code; design integration; breeding blanket; divertor; TRITIUM BREEDING PERFORMANCE; FUSION POWER-PLANTS; DIVERTOR TARGETS; BLANKET DESIGN; EXHAUST-GASES; SYSTEMS CODE; HEAT-FLUX; EU; PROGRESS; TECHNOLOGIES;

D O I：

10.1088/1741-4326/ab1178

中图分类号：

O35 [流体力学]; O53 [等离子体物理学];

学科分类号：

070204 ; 080103 ; 080704 ;

摘要：

This paper describes the status of the pre-conceptual design activities in Europe to advance the technical basis of the design of a DEMOnstration Fusion Power Plant (DEMO) to come in operation around the middle of this century with the main aims of demonstrating the production of few hundred MWs of net electricity, the feasibility of operation with a closed- tritium fuel cycle, and maintenance systems capable of achieving adequate plant availability. This is expected to benefit as much as possible from the ITER experience, in terms of design, licensing, and construction. Emphasis is on an integrated design approach, based on system engineering, which provides a clear path for urgent R&D and addresses the main design integration issues by taking account critical systems interdependencies and inherent uncertainties of important design assumptions (physics and technology). A design readiness evaluation, together with a technology maturation and down selection strategy are planned through structured and transparent Gate Reviews. By embedding industry experience in the design from the beginning it will ensure that early attention is given to technology readiness and industrial feasibility, costs, maintenance, power conversion, nuclear safety and licensing aspects.

引用

页数：25

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