Estimation of the error field due to winding manufacturing and assembly tolerances of the DTT SC magnet system

被引：2

作者：

Romanelli, G. ^{[1
]}

Giannini, L. ^{[1
]}

Martone, R. ^{[2
,3
]}

Ambrosino, R. ^{[2
,3
]}

Albanese, R. ^{[2
,3
]}

Zoboli, L. ^{[4
]}

Zumbolo, P. ^{[5
]}

Di Zenobio, A. ^{[1
]}

Turtu, S. ^{[1
]}

Muzzi, L. ^{[1
]}

della Corte, A. ^{[1
]}

机构：

[1] ENEA, Via Enrico Fermi 44, Frascati, Italy

[2] Univ Napoli Federico II, Consorzio CREATE, Naples, Italy

[3] DTT Scarl, Rome, Italy

[4] Univ Roma Tor Vergata, Via Cracovia 50, Rome, Italy

[5] Univ Padua, Via 8 Febbraio 2, Padua, Italy

来源：

FUSION ENGINEERING AND DESIGN | 2023年 / 192卷

关键词：

DTT; Tokamak; Error field; Correction coil; Plasma confinement;

D O I：

10.1016/j.fusengdes.2023.113588

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 Divertor Tokamak Test facility (DTT) currently under construction in Frascati, Italy, is an experimental fusion reactor part of the EUROfusion roadmap to fusion energy. Due to their non-ideal winding distribution and assembly and manufacturing tolerances, real magnets are responsible for what is referred to as Error Fields (EFs). In some cases, EFs above a certain level can be unacceptable for achieving the sought performance of the fusion reaction and the implementation of dedicated in-vessel correction coils may become a necessary requirement. This work describes an approach to verify the magnet winding disposition by computing the EFs caused by the non-ideal shape of the DTT superconducting (SC) magnets. The results here presented are a contribution to the other activities aimed at deriving and verifying the requirements for the in-vessel correction coils.

引用

页数：8

共 12 条

[1] The DTT device: Role and objectives [J].

Albanese, R. ;

Reimerdes, H. .

FUSION ENGINEERING AND DESIGN, 2017, 122 :285-287

[2]

Albanese R., 2022, 3D EFFECTS JOINTS FE

[3] Assessment of error field from solitary ferromagnetic elements located outside of ITER tokamak [J].

Amoskov, V. ;

Belov, A. ;

Belyakov, V. ;

Gribov, Yu. ;

Kukhtin, V. ;

Lamzin, E. ;

Maximenkova, N. ;

Sytchevsky, S. .

PLASMA DEVICES AND OPERATIONS, 2008, 16 (03) :171-179

[4] Estimation of error fields from ferromagnetic parts in ITER [J].

Bonito Oliva, A. ;

Chiariello, A. G. ;

Formisano, A. ;

Martone, R. ;

Portone, A. ;

Testoni, P. .

FUSION ENGINEERING AND DESIGN, 2013, 88 (9-10) :1576-1580

[5]

ENEA, 2019, DTT Divertor Tokamak Test Facility Interim Design Report the DTT Green Book

[6]

ENEA, 2015, DTT Divertor Tokamak Test facility Project Proposal

[7]

EUROfusion, 2018, EUROFUSION PROGRAMME

[8] Computation of the Biot-Savart line integral with higher-order convergence using straight segments [J].

McGreivy, N. ;

Zhu, C. ;

Gunderson, L. M. ;

Hudson, S. R. .

PHYSICS OF PLASMAS, 2021, 28 (08)

[9] Spectral asymmetry due to magnetic coordinates [J].

Park, Jong-Kyu ;

Boozer, Allen H. ;

Menard, Jonathan E. .

PHYSICS OF PLASMAS, 2008, 15 (06)

[10]

Spears B., 2011, JT60SA

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