Selected transport studies of a tokamak-based DEMO fusion reactor

被引：19

作者：

Fable, E. ^{[1
]}

Wenninger, R. ^{[1
,2
]}

Kemp, R. ^{[3
]}

机构：

[1] Max Planck Inst Plasma Phys, D-85748 Garching, Germany

[2] EUROfus Programme Management Unit, Boltzmannstr 2, D-85748 Garching, Germany

[3] Culham Sci Ctr, EURATOM CCFE Fus Assoc, Abingdon OX14 3DB, Oxon, England

来源：

NUCLEAR FUSION | 2017年 / 57卷 / 02期

关键词：

fusion reactor; tokamak; demo; transport; radiation; turbulence; ARBITRARY COLLISIONALITY; BOOTSTRAP CURRENT; SYSTEMS; PLASMA;

D O I：

10.1088/0029-5515/57/2/022015

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：

As a next-step in the tokamak-based fusion programme, the DEMO fusion reactor is foreseen to produce relevant output electricity, in the order of similar to 500 MW delivered to the network. The scenarios that are being presently investigated consist of a pulsed device, called DEMO1, and a steady-state device, called DEMO2. In this work, which is focused on the pulsed device DEMO1, scenarios are studied from the point of view of core transport, to assess plasma performance and limitations due to core microinstabilities. The role of radiated power, aspect ratio, and height of temperature pedestal are assessed as they impact both core energy and particle transport. Open issues in this framework are also discussed.

引用

页数：7

共 50 条

[41] The tritium extraction and removal system for the DCLL-DEMO fusion reactor [J].

Garcinuno, Belit ;

Rapisarda, David ;

Antunes, Rodrigo ;

Utili, Marco ;

Fernandez-Berceruelo, Ivan ;

Sanz, Javier ;

Ibarra, Angel .

NUCLEAR FUSION, 2018, 58 (09)

[42] NEUTRONIC ASSESSMENT OF CANDIDATE MATERIALS FOR TF COILS SHIELDING IN A DEMO FUSION REACTOR BASED ON A DCLL BLANKET [J].

Catalan, J. P. ;

Sanz, J. ;

Ogando, F. ;

Pampin, R. .

FUSION SCIENCE AND TECHNOLOGY, 2012, 62 (01) :190-195

[43] RESONANT MAGNETIC PERTURBATION FOR ELM SUPPRESSION WITH HELICAL FERRITIC STEEL INSERTS IN TOKAMAK DEMO REACTOR [J].

Takizuka, T. ;

Oyama, N. ;

Fukuda, T. .

FUSION SCIENCE AND TECHNOLOGY, 2013, 63 (1T) :64-69

[44] Design and simulation of a blanket module with high efficiency cooling system of tokamak focused on DEMO reactor [J].

Sadeghi, H. ;

Amrollahi, R. ;

Zare, M. ;

Fazelpour, S. .

NUCLEAR ENGINEERING AND TECHNOLOGY, 2020, 52 (02) :323-327

[45] Shutdown dose-rate assessment during the replacement of in-vessel components for a fusion DEMO reactor [J].

Someya, Youji ;

Utoh, Hiroyasu ;

Hiwatari, Ryoji ;

Tanigawa, Hisashi ;

Tobita, Kenji .

FUSION ENGINEERING AND DESIGN, 2017, 124 :615-618

[46] European DEMO Fusion Reactor: Design and Integration of the Breeding Blanket Feeding Pipes [J].

Mozzillo, Rocco ;

Vorpahl, Christian ;

Bachmann, Christian ;

Hernandez, Francisco A. ;

Del Nevo, Alessandro .

ENERGIES, 2023, 16 (13)

[47] Parametric study of S-CO2 cycles for the DEMO fusion reactor [J].

Stepanek, Jan ;

Entler, Slavomir ;

Syblik, Jan ;

Vesely, Ladislav ;

Dostal, Vaclav ;

Zacha, Pavel .

FUSION ENGINEERING AND DESIGN, 2020, 160

[48] A novel methodology to estimate the optimal cooling of the first wall in a DEMO fusion reactor [J].

Nogueron, Jose A. ;

Fernandez-Berceruelo, Ivan ;

Rapisarda, David .

INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER, 2025, 239

[49] Overview of the Mechanical Properties of Tungsten/Steel Brazed Joints for the DEMO Fusion Reactor [J].

Bachurina, Diana ;

Vorkel, Vladimir ;

Suchkov, Alexey ;

Gurova, Julia ;

Ivannikov, Alexander ;

Penyaz, Milena ;

Fedotov, Ivan ;

Sevryukov, Oleg ;

Kalin, Boris .

METALS, 2021, 11 (02) :1-11

[50] Status of Pb-16Li technologies for European DEMO fusion reactor [J].

Utili, M. ;

Bassini, S. ;

Boccaccini, L. ;

Buehler, L. ;

Cismondi, F. ;

Del Nevo, A. ;

Eboli, M. ;

DiFonzo, F. ;

Hernandez, T. ;

Wulf, S. ;

Kordac, M. ;

Martelli, D. ;

De Les Valls, E. Mas ;

Melichar, T. ;

Mistrangelo, C. ;

Tarantino, M. ;

Tincani, A. ;

Vala, L. .

FUSION ENGINEERING AND DESIGN, 2019, 146 :2676-2681

← 1 2 3 4 5 →