Speaker
Gandolfo Alessandro Spagnuolo
(Institute for Neutron Physics and Reactor Technology (INR))
Description
The development of the fusion technology reliability involves, among other issues, the improvement of simulation tools to be used for the design of reactor key components, such as the Breeding Blanket (BB), where the engineering requirements and constraints are of nuclear, material and safety kind. For this reason, advanced simulation tools are needed. In the European DEMO project, several efforts are currently dedicated to the development of an integrated simulation-design tool for DEMO BB that is able to carry out a multi-physics analysis of such a component, allowing the characterization of BB design points which are consistent from the neutronic, thermal-hydraulic and thermo-mechanic points of view.
Within the framework of EUROfusion activities, a procedure, regarding the neutronics part, has been set-up to this end at Karlsruhe Institute of Technology (KIT).
The first step of this approach requires the definition of the reference geometry, coming from generic CAD files and to be converted into more suitable formats for neutronic analysis with Monte Carlo codes such as MCNP5/6. In this study, the neutronic model of Helium Cooled Pebble Bed (HCPB) slice in the equatorial outboard module has been used for the characterization of BB design points.
Therefore, the definition of proper boundary conditions has been pursued (i.e. angular distribution of neutron wall loading). For this reason, a 2D axial-symmetric neutronic model has been also developed to simulate all the reactor components that are radially and vertically based on reactor systems criteria and the materials are homogenized through the different regions.
The present work aims to summarize the research activity carried out and results obtained are herewith reported and critically discussed.
Furthermore, the strengths and weaknesses of this integrated coupling approach are highlighted and the potential developments, including the use of neutronic outcomes for CFD and thermo-mechanic analyses, are described as future steps.
Co-authors
Fabrizio Franza
(Institute for Neutron Physics and Reactor Technology (INR), Karlsruhe Institute of Technology (KIT), Eggenstein-Leopoldshafen, Germany)
Fischer Ulrich
(Institute for Neutron Physics and Reactor Technology (INR), Karlsruhe Institute of Technology (KIT), Eggenstein-Leopoldshafen, Germany)
Gandolfo Alessandro Spagnuolo
(Institute for Neutron Physics and Reactor Technology (INR), Karlsruhe Institute of Technology (KIT), Eggenstein-Leopoldshafen, Germany)
Lorenzo Virgilio Boccaccini
(Institute for Neutron Physics and Reactor Technology (INR), Karlsruhe Institute of Technology (KIT), Eggenstein-Leopoldshafen, Germany)
