Published October 16, 2018 | Version v1
Report

Implementation of the Spherical Tokamak MEDUSA-CR: Stage 1

  • 1. Plasma Laboratory for Fusion Energy and Applications, Instituto Tecnológico de Costa Rica, Cartago (Costa Rica)

Description

Full text: The low aspect ratio Spherical Tokamak (ST) MEDUSA (Madison Education Small Aspect Ratio Tokamak) is currently being recommissioned at the Instituto Tecnológico de Costa Rica, after it was donated by the University of Wisconsin-Madison, USA. The main characteristics of this magnetic confinement device are described as follows. plasma major radius of Ro < 0.14 m, plasma minor radius a < 0.10 m, plasma vertical elongation 1.2, toroidal field at the geometric centre of the vessel Bt < 0.5 T, plasma current Ip < 40 kA, ne(0) < 2 x 1020/m3, central electron temperature Te(0) < 140 eV, discharge duration is < 3 ms, top and bottom rail limiters, and natural divertor D-shaped ohmic plasmas. Training students and researchers is the main goal as for ST MEDUSA-CR, to merge knowledge between physics and engineering in order to address relevant concepts for spherical and conventional tokamaks. Currently diverse topics are being addressed in the first engineering stage of the MEDUSACR. For the vacuum system design there has been developed a corresponding documentation process of the implementation and testing vacuum, also it is present a new design of the vacuum vessel made of stainless steel. The design of the new injection system, entirely developed to accomplish the spherical tokamak's requirements has been successfully tested. The electric current control of the coils presents a possible upgrade to converting ST MEDUSA-CR to AC mode. Additionally, a MHD equilibrium simulation for the original configuration of the device has been performed using a code named Fiesta; which was facilitated by Geoffrey Cunningham from Culham Centre for Fusion Energy (CCFE). (author)

Part of:
27th IAEA Fusion Energy Conference. Programme and Book of Abstracts

Additional details

Publishing Information

Imprint Title
27th IAEA Fusion Energy Conference. Programme and Book of Abstracts
Imprint Pagination
844 p.
Journal Page Range
p. 725
Report number
IAEA-CN--258

Conference

Title
27. IAEA Fusion Energy Conference
Acronym
FEC 2018
Dates
22-27 Oct 2018
Place
Ahmedabad (India)

INIS

Country of Publication
International Atomic Energy Agency (IAEA)
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
50057810
Subject category
S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
Resource subtype / Literary indicator
Conference
Descriptors DEI
ELECTRON TEMPERATURE; IMPLEMENTATION; MAGNETIC CONFINEMENT; MAGNETOHYDRODYNAMICS; PLASMA; SPHERICAL CONFIGURATION; STAINLESS STEELS; TOKAMAK DEVICES; VACUUM SYSTEMS
Descriptors DEC
ALLOYS; CARBON ADDITIONS; CLOSED PLASMA DEVICES; CONFIGURATION; CONFINEMENT; FLUID MECHANICS; HIGH ALLOY STEELS; HYDRODYNAMICS; IRON ALLOYS; IRON BASE ALLOYS; MECHANICS; PLASMA CONFINEMENT; STEELS; THERMONUCLEAR DEVICES; TRANSITION ELEMENT ALLOYS

Optional Information

Notes
4 refs.
Secondary number(s)
IAEA-CN--258-730