On Heat Loading, Novel Divertors, and Fusion Reactors
نویسندگان
چکیده
It is shown that the limited thermal power handling capacity of the standard divertors (used in current as well as projected tokamaks) forces extremely high (∼ 95%) radiation fractions fRad in tokamak fusion reactors [1–3] with heating powers considerably larger than ITER-FEAT [4]. Independent of how the radiation may be apportioned between the scrape off layer (SOL) and the core, these enormous values of fRad have profound and deleterious consequences on the core confinement and stability to the extent that a high power hypothetical fusion reactor operating with the standard divertor (SD) is not likely to meet the daunting confinement requirements. Even operation in modes that have an internal transport barriers (ITBs) [5, 6] is not expected to lead to a dependable fusion power reactor with acceptable economics. The core confinement and stability problems caused by high fRad are shown to be adequately addressed by X-Divertors (XD) which, through a flaring of the field lines near the divertor plates, considerably enhance the divertor thermal capacity. The use of this new class of divertors will lower the bar on confinement sufficiently that confinement at the level of the routinely found H-mode [7] could be enough for a fusion reactor. A possible class of experiments that could lay the foundation for an efficient and attractive path to practical fusion power is suggested.
منابع مشابه
Component Testing and Materials Development for Fusion Applications Using Materials Test Reactors
Fusion power plant operation will strongly depend on the economy and reliability of crucial components, such as first wall modules, tritium breeding blankets and divertors. Their operating temperature shall be high to accomplish high plant efficiency. The materials properties and component fabrication routes shall also assure long reliable operation to minimize plant outage. The components must...
متن کاملSimulation of plasma–neutral dynamics for radiation cooling
An advanced heat removal scenario is required to handle the high input power of magnetic fusion reactors. The concepts of gas target and radiative divertors have been explored. A set of self-consistently coupled fluid equations for plasma and neutrals is suitable for this system because of the sophisticated equations for neutrals. The transfer of plasma momentum to neutrals, which is crucial in...
متن کاملAn Overview of Georgia Tech Studies on the Fluid Dynamics Aspects of Liquid Protection Schemes for Fusion Reactors
This paper provides an overview of experimental and numerical studies conducted at Georgia Tech to assess the fluid dynamics aspects of liquid protection schemes for fusion energy reactors. The problems described here include: (1) Dynamics of slab jets for thick liquid protection, including the effect of nozzle design, flow conditioning, and boundary layer cutting on jet surface smoothness; (2)...
متن کاملCFD Simulation of Porosity and Particle Diameter Influence on Wall-to-Bed Heat Transfer in Trickle Bed Reactors
Wall-to-bed (or wall-to-fluid) heat transfer issues in trickle bed reactors (TBR) has an important impact on operation and efficiency in this category of reactors. In this study, the hydrodynamic and thermal behavior of trickle bed reactors was simulated by means of computational fluid dynamics (CFD) technique. The multiphase behavior of trickle bed reactor was studied by the implementation of ...
متن کاملUWFDM-1394 Structural Materials Damage in Fusion and Fission Systems
Calculations were performed to quantify the damage parameters in the leading candidate structural and plasma facing materials when used in magnetic and inertial confinement fusion systems and when irradiated in fission reactors. The structural materials considered are ferritic steel, austenitic steel, vanadium alloy and SiC/SiC composite. Plasma facing materials included beryllium, tungsten, an...
متن کامل