DocumentCode :
1607478
Title :
Engineering issues to the stellerator of Costa Rica 1
Author :
Vargas, V.I. ; Mora, Javier ; Asenjo, J. ; Zamora, Erik ; Otarola, C. ; Carvajal-Godinez, J. ; Gonzalez-Gomez, J. ; Soto-Soto, C. ; Piedras, C. ; Barillas, L. ; Ribeiro, Cassio
Author_Institution :
Plasma Lab. for Fusion Energy & Applic., Cartago, Costa Rica
fYear :
2013
Firstpage :
1
Lastpage :
6
Abstract :
This paper aims at briefly describing the design and construction issues of the Stellarator of Costa Rica 1 (SCR-1). The SCR-1 is a small modular Stellarator for magnetic confinement of plasma developed by the Plasma Laboratory for Fusion Energy and Applications of the Instituto Tecnológico de Costa Rica (ITCR). SCR-1 will be a 2-field period small modular stellarator with an aspect ratio 4; low shear configuration with core and edge rotational transform equal to 0.32 and 0.28; it will hold plasma in a 6061-T6 aluminium torus shaped vacuum vessel with an minor plasma radius 54.11 mm, a volume of 13.76 liters (0.01 m3), and major radius R = 238 mm. Plasma will be confined in the volume by on axis magnetic field 43.8 mT generated by 12 modular coils with 6 turns each, carrying a current of 767.8 A per turn providing a total toroidal field (TF) current of 4.6 kA-turn per coil. The coils will be supplied by a bank of cell batteries of 120 V. Typical length of the plasma pulse will be between 4 s to 10 s. The SCR-1 plasmas will be heated by ECH second harmonic at 2.45 GHz with a plasma density cut-off value of 7.45×1016 m-3. Two magnetrons with a maximum output power of 2 kW and 3 kW will be used.
Keywords :
fusion reactor design; plasma boundary layers; plasma density; plasma flow; plasma radiofrequency heating; plasma toroidal confinement; stellarators; 6061-T6 aluminium torus shaped vacuum vessel; Costa Rica 1 stellarator; ECH second harmonic; Instituto Tecnologico de Costa Rica; Plasma Laboratory for Fusion Energy and Applications; SCR-1 design; axis magnetic field; cell batteries; edge rotational transform; magnetrons; major plasma radius; minor plasma radius; modular coils; plasma density cut-off value; plasma magnetic confinement; plasma pulse length; reactor core; shear configuration; toroidal field current; Coils; Heating; Magnetic resonance; Plasmas; Probes; Toroidal magnetic fields; Magnetic confinement; Stellerator; low shear configuration; small modular stellerator;
fLanguage :
English
Publisher :
ieee
Conference_Titel :
Fusion Engineering (SOFE), 2013 IEEE 25th Symposium on
Conference_Location :
San Francisco, CA
Print_ISBN :
978-1-4799-0169-2
Type :
conf
DOI :
10.1109/SOFE.2013.6635443
Filename :
6635443
Link To Document :
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