Search results for "Reference design"
showing 6 items of 6 documents
Further improvements of the water-cooled Pb–17Li blanket
2001
Abstract The water-cooled lithium–lead (WCLL) blanket is based on reduced-activation ferritic–martensitic steel as the structural material, the liquid alloy Pb–17Li as breeder and neutron multiplier, and water at typical PWR conditions as coolant. It was developed for DEMO specifications and shall be tested in ITER. In 1999, a reactor parameter optimization was performed in the EU which yielded improved specifications of what could be an attractive fusion power plant. Compared to DEMO, such a power reactor would be different in lay-out, size and performance, thus requiring to better exploit the potential of the WCLL blanket concept in conjunction with a water-cooled divertor. Several new ap…
Key EU DEMO plant and building layout criteria
2021
Abstract An early attention to the layout of both plant site and its buildings is essential in a complex plant under preliminary design as DEMO in order to meet the assigned targets, namely i) the licensing requirements ii) a good availability in delivery electricity to the grid. The layout definition has to follow several criteria that become more complex and stringent for nuclear buildings, e.g. functional, maintenance, fire protection, safety, human factors, shielding, and remote handling. The criterion As Low As Reasonable Achievable, with respect to the dose to the staff, has to be applied in design, operation, maintenance and decommissioning phases. The tokamak building, where several…
Reference Design for Smart Collaborative Telehealth and Telecare Services Based on IoT Technologies
2015
The demographic development shows aging societies through-out the globe, leading to higher demands on the health and care systems due to age-related disabilities, chronic diseases, etc. Telehealth and telecare services for more efficient support of health and care providers are needed, which can be significantly improved by the continuous technological developments in areas such as sensor devices, Internet of Things (IoT), cloud services, and data analysis. This paper addresses the potential of selected emerging technologies to make eHealth systems smarter, more collaborative and more efficient. As a result of the analysis of the most promising technological trends, characteristics of futur…
Thermo-mechanical analysis of irradiation swelling and design optimization of the IFMIF target assembly with bayonet backplate
2017
Abstract The availability of a high flux neutron source for testing candidate materials under irradiation conditions, which will be typically encountered in future fusion power reactors (ITER, DEMO, FPR), is a fundamental step towards the development of fusion energy. To this purpose, the International Fusion Materials Irradiation Facility (IFMIF) represents the reference option to provide the fusion community with a DEMO-relevant neutron source capable of irradiating samples at a damage rate of up to 20 dpa/fpy (in steel) in a volume of 0.5 l. In the framework of the engineering design activities of IFMIF, ENEA is committed in the design of the lithium target assembly (TA) with removable (…
Status of a MIND type Neutrino Factory Far Detector
2013
A realistic simulation and analysis of a Magnetized Iron Neutrino Detector (MIND) has been developed for the purpose of understanding the potential sensitivity of such a facility. The status of the MIND simulation and reconstruction as discussed in the interim design report is reviewed here. Priorities for producing a more realistic simulation for a reference design report will be discussed, as will be the steps that have already been taken towards an improved simulation.
An enhanced, near-term HCPB design as driver blanket for the EU DEMO
2019
The Helium Cooled Pebble Bed (HCPB) breeding blanket is a candidate as driver blanket for the EU DEMO. The reference design of the HCPB is based on a cooling plate “sandwich” arrangement built in Multi-Module Segments. This architecture significantly improved the tritium breeding performance (TBR = 1.15) and the plant circulating power (≈130 MW) compared to the former ITER-like “beer-box”-like design (TBR<1.10, plant circulating power>200 MW). However, several issues remain with this design, in which (1) the still large power required per He circulator (beyond the state-of-the-art for these components) and (2) the large tritium inventory foreseen in Be have been identified as the most…