Experimental results of multiple shattered pellet injection systems in KSTAR

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Abstract

Shattered pellet injection (SPI) is the technology chosen for the ITER Disruption Mitigation System and is explored at several fusion research devices, like DIII-D and JET and J-TEXT. The ITER disruption mitigation strategy relies on multiple injections to achieve RE (runaway electron) avoidance with optimum TQ (thermal quench), CQ (current quench) durations to adequately reduce wall loads. To demonstrate the feasibility of the multiple injection and to extrapolate to ITER, experiments with two identical injectors toroidally opposite to each other are needed urgently.

KSTAR (Korea Superconducting Tokamak Advanced Research) can be a unique testbed to study the plasma disruption mitigation for ITER. KSTAR has installed two identical injectors in 180 degrees of toroidal opposite positions in 2019. For this system, ORNL (Oak Ridge National Laboratory) provided the two injectors, the shatter tubes, and auxiliary systems. NFRI (National Fusion Research Institute) provided the infrastructure of a vacuum pumping system, control & data acquisition system, and installed additional diagnostic systems for SPI in collaboration with the ITER Organization. This paper describes the engineering achievements during installation on KSTAR and the initial results of single and multiple SPI experiments in the 2019 campaign.

Introduction

The mitigation of plasma disruption is one of the main challenges for future tokamak experiments. A large thermal load occurs during the thermal quench (TQ) and a large mechanical load occurs on the vacuum vessel and in-vessel components during the current quench (CQ). The impact of runaway electrons (RE) that can develop in the CQ on plasma facing components must be avoided. The disruption loads in ITER require a reliable and effective disruption mitigation strategy [1]. This strategy relies on the dissipation of thermal and magnetic energy through radiation and on the avoidance of RE formation through a massive increase in plasma density before the thermal quench.

The mitigation methods such as the gas injection, intact pellet injection, and solid particle injection have been studied for the mitigation of plasma disruptions. The ITER Disruption Mitigation System (DMS) will use Shattered Pellet Injection (SPI). The technology forms and accelerates large cryogenic pellets that are shattered into small fragments before entering the plasma to achieve high assimilation. The DMS of ITER can inject up to 24 pellets from three toroidal locations at the equatorial level [2]. For the validation of the ITER DMS design, the ITER Organization has established the DMS Task Force, a multi-year, multi-partner undertaking to enhance the physics and technology basis for the ITER DMS. The KSTAR SPI project is part of this programme.

Section snippets

Pellet injector

The KSTAR SPIs are based on a pipe-gun type injector [3] that uses a cryocooler to form a pellet in situ in a stainless steel (STS) barrel. The gases of D2, Ne, Ar are supplied into the STS barrel and then they start to freeze where the cold block is attached. (Fig. 1) The heaters of each barrel control the temperature to control the length of the pellets in the three different size barrels (∅ 4.5, 7, 8.5 mm). A fast propellant gas valve can release a pulse of high pressure (5 MPa) helium gas

Commissioning

The identical injector and shatter tubes provided by ORNL were tested at ORNL before delivery to KSTAR. The integrated commissioning of the first SPI was done with ORNL’s support in the early October 2019. The operational testing of each valve, gas manifold, injector cool-down, local and remote control by the PLC and the HMI program, and data acquisition were completed successfully [6] (Fig. 8).

One of the important checks performed was the flow of propellant gas to the vacuum vessel. We

Further work

For more recent experiments, the largest barrel of 8.5 mm diameter was replaced by a 7 mm barrel at each port. It can be quickly replaced in a day. It is possible to fire the same 7 mm pellets simultaneously from the same SPI. At a later stage, it will also be possible to make use of a mechanical punch to launch pure Ne and Ar pellets [7].

A dispersion interferometer is ready to measure the density from the SPI injection for the mitigation. A fast visible camera has been developed and we expect

Declaration of Competing Interest

The authors declare that they have no known competing financial interests or personal relationships that could have appeared to influence the work reported in this paper.

Acknowledgments

This study was supported by the Korean Ministry of Science and ICT under the Korea Superconducting Tokamak Advanced Research (KSTAR) Project. This work was supported by the Oak Ridge National Laboratory managed by UT-Battelle, LLC for the U.S. Department of Energy under Contract No. DE-AC05-00OR22725 and by the ITER Organization under Contracts IO/CT43-1830, 1909, 1918, 2034. The views and opinions expressed herein do not necessarily reflect those of the ITER Organization.

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