Computation of JT-60SA TF coil temperature margin using the 4C code

被引：17

作者：

Bonifetto, R. ^{[1
]}

Domalapally, P. K. ^{[1
]}

Polli, G. M. ^{[2
]}

Richard, L. Savoldi ^{[1
]}

Turtu', S. ^{[2
]}

Villari, R. ^{[2
]}

Zanino, R. ^{[1
]}

机构：

[1] Politecn Torino, Dipartimento Energet, I-10129 Turin, Italy

[2] EURATOM, ENEA, I-00044 Frascati, Italy

来源：

FUSION ENGINEERING AND DESIGN | 2011年 / 86卷 / 6-8期

关键词：

Fusion reactors; Superconducting coils; Simulation; ITER; Thermal-Hydraulics; JT-60SA;

D O I：

10.1016/j.fusengdes.2011.02.068

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 recently developed 4C thermal-hydraulic code, currently under validation, is used to compute the temperature margin of the superconducting NbTi toroidal field coil of the ITER satellite tokamak JT-60SA, for the nominal burn operation of the machine. Repetitive conditions in the simulation are reached after two plasma pulses. For given (computed) thermal load distribution on winding and coil case due to nuclear heating only, helium temperature similar to 4.4 K at the winding inlet, reference strand, and the most recent conductor and winding layout, the computed minimum margin occurs in pancake #7 at the peak field location and turns out to be similar to 0.2-0.3 K above the design value of 1.2K. (C) 2011 Elsevier B.V. All rights reserved.

引用

页码：1493 / 1496

页数：4

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