VEST

The main objectives of VEST are to study spherical tokamak plasmas, wave heating and high beta operations, as well as divertor concepts, including Super-X divertor configuration.

Quoted verbatim from the IAEA World Survey of Fusion Devices, not paraphrased.

Operator

Seoul National University

Type

Fusion device

Approach

Tokamak

Country

KR

Status

Operating

Built

2013

Ownership

public