A description of the ITER's gas injection systems and current R&amp;D activities

Li, W.; Li, B.; Maruyama, S.; Jiang, Tao; Yang, Yu; Xia, Zhiyong; Zhang, Y.X.; Lü, Jie

doi:10.1016/j.fusengdes.2012.02.029

Cited by 10 publications

(5 citation statements)

References 4 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…where n G , I p , and a are in units of 10 20 m −3 , MA, and m, respectively. In addition to the fusion power, contour lines for the following ITER operational constraints [25,36,38] are plotted: i-the auxiliary heating systems saturate at 110 MW (solid pink), ii-the 100%D pellet injector saturates at 120 Pa m 3 s −1 (solid light blue), iii-the 10%D-90%T pellet injector saturates at 111 Pa m 3 s −1 (solid dark blue), ivthe gas fueling system saturates (reaches peak throughput) at 400 Pa m 3 s −1 (solid brown), v-the peak heat load on the divertor targets reaches the safety limit of 10 MW m −2 (solid red), and vi-the total plasma power exceeds the L-H power threshold such that the plasma is in H-mode (solid purple). The region in the temperature-density space where all six of the aforementioned constraints are satisfied is colored light green.…”

Section: Popcon Assessment Of Iter's Operable Spacementioning

confidence: 99%

Divertor-safe nonlinear burn control based on a SOLPS parameterized core-edge model for ITER

Graber,

Schuster

2024

Nucl. Fusion

View full text Add to dashboard Cite

For ITER operations, the range of desirable burning-plasma regimes with high fusion power output will be restricted by various operational constraints. These constraints include the saturation of ITER’s various heating and fueling actuators such as the neutral beam injectors, the ion and electron cyclotron heating systems, the gas puffing system, and the deuterium-tritium pellet injectors. In addition to these actuator constraints, the H-mode power threshold, divertor detachment, and the heat load on the divertor targets may apply limitations to ITER’s operational space. In this work, Plasma Operation Contour (POPCON) plots that map the aforementioned constraints to the temperature-density space are used to investigate which constraints are most limiting towards accessing regimes with high fusion power output. The presented POPCON plots are based on a control-oriented core-edge model that couples the nonlinear density and energy response models for the core-plasma region with SOLPS4.3 parameterizations for conditions in the edge-plasma regions (scrape-off-layer and divertor). Using this control-oriented core-edge model, a nonlinear burn controller, which aims to regulate the plasma temperature and density in the core-plasma region, is constructed in this work. This controller is augmented with an online optimization scheme that governs the control references such that the plasma can be guided towards regimes with high fusion powers while protecting the divertor targets from dangerously high heat loads. A closed-loop simulation study illustrates the capability of this burn control scheme.

show abstract

Section: Popcon Assessment Of Iter's Operable Spacementioning

confidence: 99%

Divertor-safe nonlinear burn control based on a SOLPS parameterized core-edge model for ITER

Graber,

Schuster

2024

Nucl. Fusion

View full text Add to dashboard Cite

show abstract

“…H 2 or He gas will be used for GDC prior to FP to prepare the walls for plasma operation, but this will not be controlled by the PCS. A combination of feedforward and feedback control of the GIS will allow triggering the SNUs at a chosen pre-fill pressure equilibrated in the vessel to achieve reproducible breakdown conditions, which are challenging in ITER due to the large VV volume (∼1700 m 3 ), low toroidal electric field and inherent delays due to the length of the gas lines (18-26 m) of order 0.5 s for H 2 [12]. The mass flow controlled (MFC) valves will be installed with two different throughputs with one in the range of 0.1-5 Pa m 3 s −1 and another in the range of 5-100 Pa m 3 s −1 .…”

Section: Kinetic Controlmentioning

confidence: 99%

ITER plasma control system final design and preparation for first plasma

et al. 2021

View full text Add to dashboard Cite

The ITER plasma control system (PCS) has successfully completed its final design for the first plasma (FP) and engineering operations (EOs) phase and plant system commissioning has begun as ITER prepares for this first operation phase. Commissioning of the essential plant systems will continue as each plant system is completed and made ready for operation. Tokamak assembly has begun with the base and lower cylinder of the cryostat and the lower most poloidal field (PF) coil installed in the tokamak pit. The first vacuum vessel (VV) sector and accompanying two toroidal field (TF) coils are being prepared for transfer to the pit. Once the tokamak is assembled, the cryostat top lid is closed and pump down begins, this will start approximately one year of integrated commissioning (IC) to prepare all of the relevant plant systems for FP operation. After a scheduled one month of plasma operation with the goal of achieving a plasma current > 100 kA for at least 100 ms, there will be about six months of EO to complete commissioning of the superconducting central solenoid, PF, and TF magnet systems to full current, without plasma, to complete this initial ITER operation phase. The PCS final design for FP will be described as well as the IC sequence of the main plant systems required for this operations phase. The plans for the FP operation campaign will be described, including specific challenges present on ITER due to large VV eddy currents, issues associated with electron cyclotron heating (ECH) assist, neutral pressure and impurities. This will be followed by the EO phase to commission full current operation of the superconducting magnets, possibly including plasma operation at full TF of 5.3 T to have improved conditions both for Ohmic plasma initiation and ECH absorption.

show abstract

“…The feasibility of meeting requirements on the response time and magnetic shielding by R&D are cov-YANG Yu et al: Conceptual Design of the ITER Gas Injection System ered in a description of ITER's gas injection systems and current R&D activities [3] .…”

Section: Gas Valve Boxmentioning

confidence: 99%

Conceptual Design of the ITER Gas Injection System

Yang¹,

Maruyama²,

Kiss³

et al. 2013

Plasma Sci. Technol.

Self Cite

View full text Add to dashboard Cite

A conceptual design review of the ITER gas injection system (GIS) function, safety, operation, and maintenance has recently been successfully completed. The GIS design can now continue to the preliminary design stage. This paper gives an overall description of the requirements and implementation at the concept design level. The designs of the sub-systems according to its breakdown structure are discussed against the corresponding requirements.

show abstract

A description of the ITER's gas injection systems and current R&D activities

Cited by 10 publications

References 4 publications

Divertor-safe nonlinear burn control based on a SOLPS parameterized core-edge model for ITER

Divertor-safe nonlinear burn control based on a SOLPS parameterized core-edge model for ITER

ITER plasma control system final design and preparation for first plasma

Conceptual Design of the ITER Gas Injection System

Contact Info

Product

Resources

About