A5002408766- Fusion materials and technologies
- Nuclear Materials and Properties
- Nuclear reactor physics and engineering
- Superconducting Materials and Applications
- Magnetic confinement fusion research
- Nuclear Physics and Applications
- Rocket and propulsion systems research
- Nuclear and radioactivity studies
- Spacecraft and Cryogenic Technologies
- Advanced ceramic materials synthesis
- Heat transfer and supercritical fluids
- Particle accelerators and beam dynamics
- Advanced materials and composites
- Powder Metallurgy Techniques and Materials
- Rheology and Fluid Dynamics Studies
- High Temperature Alloys and Creep
- Additive Manufacturing Materials and Processes
- Rare-earth and actinide compounds
- Radio Wave Propagation Studies
- Numerical methods in engineering
- Granular flow and fluidized beds
- Vibration Control and Rheological Fluids
- Advancements in Photolithography Techniques
- Advanced MEMS and NEMS Technologies
- Composite Material Mechanics
IberEspacio (Spain)
2024
Iberdrola (Spain)
2024
Karlsruhe Institute of Technology
2014-2023
Illinois Institute of Technology
2015-2021
National University of Distance Education
2019
Culham Science Centre
2019
New Mexico Institute of Mining and Technology
2017
The Helium Cooled Pebble Bed (HCPB) Breeding Blanket (BB) is one of the 4 BB concepts being investigated in EU for their possible implementation DEMO. During 2014 former "beer-box" concept based on ITER's HCPB Test Module suffered several design changes so as to meet different counteracting nuclear, thermohydraulic and thermomechanical requirements. These studies evidenced that too rigid tight TBR requirements imposed DEMO (i.e. ≥ 1.10). Additionally, complex manifold system with unbalanced...
The scope of the EUFOfusion Work Package Breeding Blanket is to develop a blanket concept for EU DEMO reactor; this includes segments inside Vacuum Vessel and related Tritium Extraction/Removal Systems. In Pre-Concept Design (PCD) Phase, two concepts have been selected as candidates; solid liquid breeder cooled with helium water, respectively. design these systems has adapted plant developed in PCD Phase performances assessed. A large R&D programme implemented evaluate different technologies...
In the framework of EUROfusion's Power Plant Physics and Technology, working package breeding blanket (BB) aims at investigating four different BB concepts for an EU demonstration fusion reactor (DEMO). One these is helium-cooled pebble bed (HCPB) BB, which based on use beds lithiated ternary compounds Be or beryllides as tritium breeder multiplier materials, respectively, EUROFER97 structural steel He coolant. This paper giving overview HCPB Research Development (R&D) being developed KIT,...
The helium-cooled pebble bed (HCPB) blanket is one of the two concepts proposed as a driver for European Union Demonstration Fusion Power Reactor (EU DEMO). In contrast to past conceptual design studies, in frame current Plant Physics and Technology EUROfusion Consortium, ongoing EU DEMO preconceptual activities have adopted holistic integrated (i.e., systems engineering) approach. As consequence this new approach, many interfaces requirements been identified, some them driving blankets....
Significant design efforts were undertaken during the Pre-Concept Design (PCD) phase of European DEMO program to optimize helium cooled pebble bed (HCPB) breeding blanket. A gate review was conducted for entire at conclusion PCD phase. This article presents a summary evolution and rationale behind HCPB blanket concept DEMO. The main performance metrics, including nuclear, thermal hydraulics, mechanical, tritium permeation behaviors, are reported. These figures demonstrate that is highly...
Currently, for the EU DEMO, two Breeding Blankets (BBs) have been selected as potential candidates integration in reactor. They are Water Cooled Lithium Lead and Helium Pebble Bed BB concepts. The variants together with associated ancillary systems drive design of overall plant. Therefore, a holistic investigation issues derived by installation its has performed. related to water activation due 16N 17N isotopes impact on primary heat transfer investigated providing guidelines dedicated...
The EU conducted the pre-conceptual design (PCD) phase of demonstration reactor (DEMO) during 2014–2020 under framework EUROfusion consortium. current strategy DEMO is to bridge breeding blanket (BB) technology gaps between ITER and a commercial fusion power plant (FPP) by playing role “Component Test Facility” for BB. Within this strategy, so-called driver blanket, with nearly full in-vessel surface coverage, will aim at achieving high-level stakeholder requirements tritium self-sufficiency...