Cantabria, Spain
Cantabria, Spain

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Laarossi I.,University of Cantabria | Ruiz-Lombera R.,University of Cantabria | Quintela M.A.,University of Cantabria | Mirapeix J.,University of Cantabria | And 3 more authors.
Optics InfoBase Conference Papers | Year: 2016

An ultra-high temperature distributed sensor based on a Raman Optical-Time-Domain- Reflectometry (ROTDR) and multimode gold-coated fiber is experimentally validated in this paper. Distributed temperature measurements up to 600°C have been carried out.


Laarossi I.,University of Cantabria | Quintela M.A.,University of Cantabria | Ruiz-Lombera R.,University of Cantabria | Mirapeix J.,University of Cantabria | And 3 more authors.
Optics InfoBase Conference Papers | Year: 2016

A high temperature distributed sensor based on a Raman Optical-Time-Domain- Reflectometry (ROTDR) and a multimode silica fiber is experimentally checked in this paper. Distributed temperature measurements up to 450°C have been successfully carried out.


Grant
Agency: European Commission | Branch: H2020 | Program: MSCA-ITN-ETN | Phase: MSCA-ITN-2014-ETN | Award Amount: 3.70M | Year: 2015

The growth of cities, impacts of climate change and the massive cost of providing new infrastructure provide the impetus for this proposal entitled Training in Reducing Uncertainty in Structural Safety (TRUSS) which will maximize the potential of infrastructure that already exists. If flaws in a structure can be identified early, the cost of repair will be vastly reduced, and here an effective monitoring system would allow identifying the optimum time to repair as well as improving structural safety. But safety is difficult to quantify and requires a deep understanding of the uncertainty associated to measurements and models for the structure and the loads. TRUSS will gather this understanding by bringing together an intersectoral and multidisciplinary collaboration between 4 Universities, 11 Industry participants and 1 research institute from 6 European countries. The consortium will combine and share expertise to offer training at an advanced level as new concepts for monitoring, modelling and reliability analysis of structures are emerging all the time. TRUSS will make knowledge of structural safety grow by incorporating these emerging technologies (hi-tech monitoring and manufacturing, computing, etc.) into the training programme and it will support job creation by enabling a wider talent pool of skilled and accredited engineering graduates with business, entrepreneurship, communication, project management and other transferrable skills. The training programme will be structured into taught modules combined with original research supported by secondments that will expose 14 fellows to both academia and industry. While developing tools that will reduce uncertainty in structural safety and improve infrastructure management, TRUSS will lay the basis for an advanced doctoral programme that will qualify graduates for dealing with the challenges of an aging European infrastructure stock, thereby enhancing their career prospects in both industry and academia.


Koppe T.,Max Planck Institute for Plasma Physics (Greifswald) | Cardella A.,Max Planck Institute for Plasma Physics (Greifswald) | Missal B.,Max Planck Institute for Plasma Physics (Greifswald) | Hein B.,Max Planck Institute for Plasma Physics (Greifswald) | And 11 more authors.
Fusion Engineering and Design | Year: 2011

Wendelstein 7-X (W7-X) will be the world's largest superconducting helical advanced stellarator. This stellarator concept is deemed to be a desirable alternative for a future power plant like DEMO. The main advance of the static plasma is caused by the three dimensional shape of some of the main mechanical component inside the cryostat. The geometry of the plasma vessel is formed around the three dimensional shape of the plasma. The coils and their support structure are enclosed within the outer vessel. The space between the outer, the plasma vessel and the ports is called cryostat because the vacuum inside provides thermal insulation of the magnet system which is cooled down to 4 K. Due to the different thermal movements of both vessels and the support structure have to be supported separately. 10 cryo legs will bear the coil support structure. The plasma vessel supporting system is divided into two separate systems, allowing horizontal and vertical adjustments. This paper aims to give an overview of the main mechanical components of the cryostat. The authors delineate some disparate and special problems during the manufacturing of the components at the companies in Europe. It describes the current manufacturing and assembly. © 2011 Elsevier B.V. All Rights Reserved.


Grant
Agency: European Commission | Branch: FP7 | Program: BSG-SME | Phase: SME-1 | Award Amount: 1.37M | Year: 2011

The introduction of laser welding for the manufacturing of heat exchangers and steam generators can introduce some improvements in the manufacturing process such as the increase of the welding speed and of the quality level. Furthermore the automation of the process, involving the use of the laser welding technology, would permit to reduce the time between welding operations. Implementation of the laser welding process in industrial applications where orbital moving is needed involves the development of a special laser welding head. This is why a consortium of SMEs, consisting of companies with complementary expertises, have asked to LABOR, IWS-Fraunhofer and AIMEN to design and develop an orbital laser welding head for using in tube to sheet applications. The ORBITAL system consists in the design, development and construction of a new laser welding head adapted to the specific requirements of the orbital laser welding process and tailored for tube-to-sheet joints used in the production of heat exchangers. The system will be developed in order to enhance the characteristics of the laser welding process: high-speed welding, real-time control, easy automation, data exchange, accuracy. The ORBITAL laser welding system will be designed in order to satisfy the conditions of orbital welding applications, providing a good shielding gas atmosphere and a repeatable and robust positioning of the laser respect to the tubes to be welded thanks to a mechanical finger inserted in it. In order to achieve the objectives, it will be necessary to develop the three following technical aspects: an optical path in order to focus the laser on the workpiece, an electro-mechanical system in order to move and control the speed and path of laser beam around the tube circumference with a high positioning accuracy, and a control system that will be able to control the different parameters of the welding head and all the laser installation in order to perform the welding process.


Grant
Agency: European Commission | Branch: FP7 | Program: CP-IP | Phase: Fission-2008-2.2.1 | Award Amount: 11.87M | Year: 2009

The suggested Collaborative Project (CP) addresses key viability and performance issues to support the development of a fourth generation European Sodium Fast Reactor (ESFR). This innovative system is mainly developed for competitive electricity generation and offer interesting potential characteristics in terms of safety, environmental impact, resource utilisation and waste minimisation (e.g. potential for Minor Actinides management). The objectives of the CP-ESFR look for the improvement, vis--vis of current nuclear systems, of the safety level, the guarantee of a financial risk comparable to that of the other means of energy production and a flexible and robust management of the nuclear materials. The corresponding technical requirements in terms of Systems performance; Operation, maintenance and procedures; Safety design & analysis and licensing issues; Physical protection &Proliferation resistance; Functional requirements for provisions; Fuel cycle Constructability; Decommisioning; Systems economy are based among others - upon the results of the 6th FP Specific Support Action EISOFAR (Roadmap for a European Innovative SOdium cooled FAst Reactor). The schedule for this four years project fit with the principle for an industrial deployment of ESFR technology around 2040 with the preliminary deployment of a demonstrator by 2020-2025. Following the requirements above, and considering the context as it is described, the Collaborative Project is tentatively structured into six main technical sub projects (SPs): 1)Consistency and assessment & international relationships 2)Fuel, fuel element, core & fuel cycle 3)Safety and Security 4)Energy Conversion System Components & materials 5)Reactor system (including handling) 6)Education & training A specific Management activity will insure the whole consistency.


Grant
Agency: European Commission | Branch: FP7 | Program: CP | Phase: Fission-2007-4.1-02 | Award Amount: 3.42M | Year: 2009

The present proposal addresses the support to the Jules Horowitz Material testing reactor, a new research infrastructure of pan-European interest (Topic Fission-2007-4.1.2). In the EURATOM field of fission, the Jules Horowitz Reactor (JHR) appears to be an innovative project (FEUNMARR & ESFRI), firstly from the technical point of view as an up-to-date high performance material testing reactor (MTR), secondly through a funding and steering structure gathering several European research institutes and industrial companies. The overall JHR project that encompasses the JHR design and construction is generally designates as the JHR project. In the following JHR-CP designates the 7th FP Collaborative Project proposed as a contribution to the overall JHR project. The JHR-CP project will include several networking activities related to : - the management of the project, - the organizational aspects of the experimental processes attached to this experimental reactor, - the training, with the definition of academic and professional training related to the specific JHR experimentation and operation needs based on the best European practices. In the same way the JHR-CP project will include several Technical activities related to the JHR design and construction. Those activities are concerning more specifically : - the qualification programme of the critical components of the reactor, - the qualification tests of specific components, - the man machine interface principles definition, - the safety analysis and actions, the definition of some supports to JHR experimentation.


Grant
Agency: European Commission | Branch: H2020 | Program: IA | Phase: FOF-02-2016 | Award Amount: 7.26M | Year: 2016

COROMA project proposes to develop a cognitively enhanced robot that can execute multiple tasks for the manufacturing of metal and composite parts. COROMA will therefore provide the flexibility that European metalworking and advanced material manufacturing companies require to compete in the rapidly evolving global market. The main output of COROMA project will be a modular robotic system that will perform multitude of different manufacturing tasks in an autonomous way to adapt to the production requirements. The robot will be capable of performing drilling, trimming, deburring, polishing, sanding, non-destructive inspection and adaptive fixturing operations. Using a simple interface the robot will receive basic commands that require a minimum programming effort from the human operator. The robot will autonomously navigate in the workshop and will automatically perceive the manufacturing scene and locate the part that must be manufactured and even handle some of the required tools. Learning from previous experiences during displacement, tool grasping, part localisation and the manufacturing process itself, the robot will improve its performance. It will be able to interact with other machines in the shop floor and to work on a part even while other manufacturing operations are being performed by these other machines. Safe human-robot and machine-robot collaborations will be paramount and the robot will automatically react to the presence of both humans and other machines. The modularity of the COROMA robot will permit to customize it to meet specific requirements from different manufacturing companies. These challenges require a project consortium where the latest robotic technologies meet knowledge from manufacturing experts, including both industry and academia. COROMA project consortium presents a perfect balance between manufacturing and robotics sectors players.


Harding D.C.,Sandia National Laboratories | Quevedo D.G.,Equipos Nucleares SA
Packaging, Transport, Storage and Security of Radioactive Material | Year: 2014

Type B packages for the transportation of radioactive materials must remain 'essentially leak tight' under severe regulatory accident conditions, defined in the US Nuclear Regulatory Commission's 10 CFR 71·73 and the International Atomic Energy Agency's TS-R-1. The 9-m free drop test requirement onto an unyielding surface is performed in an orientation 'for which maximum damage is expected'. Analytical techniques are used to evaluate various possible impact orientations before testing, and historically these maximal damage orientations have been side, slap-down, end, and centre-ofgravity over corner. Other orientations are rarely considered. Sandia National Laboratories (SNL) was asked by Equipos NuclearesSA (ENSA) todesign, analyse, and test animpact limiter system for a newly designed rail cask. During the conceptual design process, SNL performed due diligence and evaluated a wide spectrum of possible impact orientations, in order to assure that peak cask body acceleration design goals were not exceeded. However, design of the impact limiter, including not only crush strength of constituent materials (which can be orientation and temperature dependent), but also the shape of the impact limiter, greatly affects peak acceleration response during 9-m drops in various orientations. Although many impact limiter design shapes resemble truncated right circular cylinders attached to each end of the cask, some tend to round the outer corners or truncate those corners with conical sections. SNL's original conceptual design followed a similar theme, intending to use polyurethane foam or aluminium honeycomb within a bevelled corner shaped cylindrical shell. Detailed finite element analyses indicated excellent impact resistance at regulatory cold temperatures in the stereotypically tested side, slap-down, end, and CGOC impact orientations. Shortly before proceeding to engineering design, a rarely-considered impact orientation of 45° from horizontal indicated that cask body acceleration levels jumped unexpectedly, exceeding the design goal due to insufficient crushable material protecting the sharp corner of the cask. A complete re-design of the impact limiter was necessary, and the lessons learned from this experience could have implications for future impact limiter designs, and possibly existing designs that may not have considered this atypical impact orientation during the design process. © 2014 Sandia National Laboratories.


Zheng G.,Equipos Nucleares S.A | Hossain S.,VEQTER Ltd. | Smith M.C.,University of Manchester | Smith D.J.,University of Bristol
American Society of Mechanical Engineers, Pressure Vessels and Piping Division (Publication) PVP | Year: 2014

A circular disc containing a partial ring weld has been devised to permit high levels of residual stress to be created in a relatively small specimen. The purpose of this research is to investigate the residual stress within the weld whilst developing a residual stress measurement method called the over-coring deep hole drilling (oDHD) method. The welding simulation, incremental deep hole drilling (iDHD) simulation and measurement and neutron diffraction were previously studied and reported in [1]. In this paper, the welding simulation results were mapped into a 3D model that included the necessary mesh and boundary conditions to simulate the process of residual measurement using the oDHD method. An experimental programme of residual stress measurement using the oDHD method was then conducted on a welded circular disc. The results from the oDHD simulation and measurement matched well with previous iDHD simulations on the original stress field in the ring weld, which also matched earlier neutron diffraction results. Copyright © 2014 by ASME.

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