Conceptual analysis of a tokamak reactor with lithium dust jet

@article{Kuteev2010ConceptualAO,
  title={Conceptual analysis of a tokamak reactor with lithium dust jet},
  author={Boris V. Kuteev and V Yu Sergeev and Sergey V. Krylov and V. G. Skokov and Viktor M. Timokhin},
  journal={Nuclear Fusion},
  year={2010},
  volume={50},
  pages={075001}
}
The steady-state operation of tokamak reactors requires radiating a substantial part of the fusion energy dissipated in plasma to make more uniform the heat loads onto the first wall and to reduce the erosion of the divertor plates. One of the approaches to realize this goal uses injection of lithium dust jet into the scrape-off layer (SOL). A quantitative conceptual analysis of the reactor parameters with lithium dust jet injection is presented here. The effects of the lithium on the core and… 

Modelling of lithium transport and its influence on the edge plasma parameters in T-15MD tokamak

A possible application of a lithium emitter-collector scheme to the T-15MD tokamak is considered. 2D simulations with the SOLPS4.3 code package indicate that the outer midplane is the optimal

A Simple Hybrid Model for SOL, Pedestal and Core Tokamak Plasmas

In this paper, the divertor heat flux density profile is being discussed. The simple robust model, dealing with core, pedestal and edge plasmas was improved. The model was applied to the ITER basic

Issues of a Compact Tokamak Fusion Neutron Source

The paper describes a concept of a compact tokamak fusion neutron source based on a small spherical tokamak (FNS-ST) with MW-range of the DT-fusion power and considers key physics issues of this

Concept of the divertor of a fusion neutron source based on a spherical tokamak

A concept of the divertor and the technology for organizing the edge plasma in a fusion neutron source based on a spherical tokamak (FNS-ST) are described. The experimental data on the

Plasma and current drive parameter options for a megawatt range fusion neutron source

Tokamak-based MW-range fusion neutron sources are needed for the development of innovative neutron technologies, mainly for the control of sub-critical active zones of fast nuclear reactors, for

Computational and theoretical studies of metallic dust transport in Tokamaks

The plasma facing surfaces of the ITER are going to contain beryllium for the first wall and tungsten for the divertors [1–3]. To test their benefits for the future operations, the JET [1–3] is now

References

SHOWING 1-10 OF 32 REFERENCES

Chapter 4: Power and particle control

The ability to exhaust the plasma power loss from a large tokamak onto material walls surrounding the plasma has been perceived to be a large obstacle to the successful production of a fusion power

Study of discharge quenching in the T-10 tokamak by injecting high-Z impurity pellets

The problem of the fast quenching of a discharge in tokamaks by injecting high-Z impurity pellets is considered. Results are presented from experiments in the T-10 tokamak, in which a substantial

Studies of the impurity pellet ablation in the high-temperature plasma of magnetic confinement devices

The ablation of impurity pellets in tokamak and stellarator plasmas is investigated. Different mechanisms for shielding the heat fluxes from the surrounding plasma to the pellet surface are

Experiments with lithium limiter on T-11M tokamak and applications of the lithium capillary-pore system in future fusion reactor devices

The paper is an overview of recent results of Li limiter testing in T-11M tokamak. The lithium limiter is based on the capillary-pore system (CPS) concept. The Li erosion process and deuterium (D2)

From JET to the reactor

In the past, JET results have been prominent in defining ITER. Only absolute performances matter in a reactor, and these have to be already optimised, JET can still increase the fusion power and

Chapter 2: Plasma confinement and transport

The understanding and predictive capability of transport physics and plasma confinement is reviewed from the perspective of achieving reactor-scale burning plasmas in the ITER tokamak, for both core

Chapter 9: ITER contributions for Demo plasma development

The chapter summarizes the physics issues of the demonstration toroidal fusion power plant (Demo) that can be addressed by ITER operation. These include burning plasma specific issues, i.e. energetic

Chapter 2: Plasma confinement and transport

  • ITER Physics Expert Group on Confinement and TransITER Physics Expert Group on Confinement ModellingITER Physics Basis Editors
  • Physics
  • 1999
Physics knowledge in plasma confinement and transport relevant to design of a reactor-scale tokamak is reviewed and methodologies for projecting confinement properties to ITER are provided.

Chapter 4: Power and particle control

Progress, since the ITER Physics Basis publication (ITER Physics Basis Editors et al 1999 Nucl. Fusion 39 2137–2664), in understanding the processes that will determine the properties of the plasma