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Lecture

Development and Validation of a Computational Tool for Fusion Reactor System

Monday, 26 June 2017, 11:00-13:00
KIT Campus Nord, INR, Bau 521, 2. OG, Raum 302

Abstract:

Fusion systems codes are vital computational tools for the assessment of the key design parameters of a fusion power plant. The main goal is to capture the key physics and technology aspects, pushing the solution to comply with physics and engineering requirements and constraints. Although most of currently existing system codes provide reliable results they appear in some case to be quite simplified, especially with respect the modelling sophistication. In light of this frame, a systems code development activity is being carried out at INR since beginning of 2013, whose main goals are to develop advanced models for fusion systems analyses and thus to allow tackling certain key physics and engineering issues, normally difficult to handle with ?canonical? fusion systems codes.
The key modules developed and integrated so far include:
- Reactor radial-poloidal build-up, for the characterization of space allocation for the main re-actor physical components.
- Core plasma physics to evaluate the key power, current and magnetic equilibrium features.
- Magnetic equilibrium and confinement, including a solver for the poloidal field coils current to operate in order to achieve some target magnetic configuration.
- Wall loading, for the characterization of the peak heat fluxes on blanket and divertor plasma facing components coming from fusion neutrons, plasma radiation and charged particles.
- Neutronics, to assess tritium breeding, nuclear shielding and nuclear heating capabilities of the breeding blanket.
- Poloidal and toroidal field coils design, including a wide spectrum evaluation of such vital components which spans from an engineering evaluation of superconductive properties to a complete electromagnetic and structural characterization.
- Power flow, performing an integral energy balance for the whole power plant with the ultimate to goal to determine the plant performances and efficiencies.
A preliminary version of the code has been recently obtained and the majority of all the key models have been coherently integrated into a unique computational environment. It is currently possible therefore to produce already some reactor design, imposing for instance some target requirements (e.g. on net electric power) taking into account of some prescribed engineering constraints (such as peak heat fluxes on blanket and divertor).
The key features on the main modules will be illustrated, together with some applicative examples on DEMO design configurations produced as per runs of this newly developed fusion reactor systems analysis tool.

Speaker
Fabrizio Franza

KIT-CN, INR
Organizer