San Sebastián de los Reyes, Spain
San Sebastián de los Reyes, Spain

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Farinas M.D.,Spanish National Research Council CSIC | Alvarez-Arenas T.E.G.,Spanish National Research Council CSIC | Aguado E.C.,TECNATOM | Merino M.G.,TECNATOM
IEEE International Ultrasonics Symposium, IUS | Year: 2013

The possibility to inspect laminates of prepreg carbon fiber reinforced polymer (CFRP) laminates during lay-up fabrication is studied. First ultrasonic properties of the uncured material are determined, this information is used to design an inspection system that is tested during the fabrication of laminates with up to 30 layers, following different compaction schemes and including some Teflon insertions to simulate the presence of delaminations. The paper shows that for the chosen selection of parameters (transducers sensitivity, centre frequency and mold configuration), the inspection is possible, opening a new field of application of air-coupled ultrasonic techniques. © 2013 IEEE.


Calleja J.A.,TECNATOM | Calleja J.A.,Polytechnic University of Mozambique | Gutierrez F.,Polytechnic University of Mozambique
Radioprotection | Year: 2011

Questions relating to the transport of radioactive materials are very much an issue of current interest due to the increasing mobility of the materials involved in the nuclear fuel cycle, commitment to the environment, the safety and protection of persons and the corresponding regulatory legal framework. The radiological impact associated with this type of transport was assessed by means of a new data-processing tool that may be of use and serve as complementary documentation to that included in transport regulations. Thus, by determining the level of radiation at a distance of one metre from the transport vehicle and by selecting a route, the associated impacts will be obtained, such as the affected populations, the dose received by the most highly exposed individual, the overall radiological impact, the doses received by the population along the route and the possible detriment to their health. The most important conclusion is that the emissions of ionising radiation from the transport of radioactive material by road in Spain are not significant as regards the generation of adverse effects on human health, and that their radiological impact may be considered negligible. © EDP Sciences, 2011.


Alonso P.T.,Tecnatom | Illobre L.F.,Tecnatom | Valdivia J.C.,Tecnatom | Hulsmans M.,European Commission
International Conference on Nuclear Engineering, Proceedings, ICONE | Year: 2014

Angra-1 Nuclear Power Station (Westinghouse PWR-600 MW, 2 loops) started commercial operation in 1985, being property of Eletronuclear, subsidiary of Eletrobras in Brazil. Angra-1 has been preparing the necessary measures to renew the operating license and to apply for a lifetime extension up to 60 years. Among the many activities to perform, there are some related to fulfilling the requirements of the Brazilian regulator, the CNEN. These include requirements related to Human Factors Engineering (HFE) that included the preparation of a Chapter 18 of HFE, to become part of the plant's Final Safety Analysis Report (FSAR). In the framework of the Instrument for Nuclear Safety Cooperation (INSC), created and funded by the European Union (EU) to enhance nuclear safety world-wide, cooperation activities between the EU and the Government of Brazil were set up in 2009. One of the INSC projects funded was to support the Brazilian nuclear operator of Angra-1 in the field of HFE. In 2010, the implementation of the project was awarded to a consortium lead by Tecnatom for performing a HFE Safety Evaluation to the plant and to provide support for preparing this Chapter 18. For this Project a specific methodology was developed for the execution of the Safety Evaluation. The methodology has been developed for evaluating - from the HFE viewpoint - a plant in operation, from the beginning of commercial operation until nowadays, including the design modifications performed to date. The obtained results have been used for developing the aforementioned Chapter 18. The main results of the Project Execution have been: 1. The developed methodology has made it possible to perform a comprehensive HFE evaluation of Angra-1, including the analysis of Post-TMI requirements, the design included in the current FSAR, the existing Angra-1 procedures and the verification of the current Main Control Room. 2. Technical support has been provided to Angra-1 for the preparation of Chapter 18 of the FSAR, following the structure of NUREG-0711, and using the results of the HFE Safety Evaluation. 3. An Action Plan has been developed for identifying and addressing in the future all those deficiencies found during the HFE Safety Evaluation, as well as those activities that are the consequence of the new FSAR Chapter 18. Copyright © 2014 by ASME.


Rejas L.,Tecnatom
International Congress on Advances in Nuclear Power Plants 2010, ICAPP 2010 | Year: 2010

According to NUREG-0800 ("Standard Review Plan ")andNUREG-0711 ("Human Factors Engineering Program Review Model"), the Human-System Interface (HSI) analysis and design should be performed following Human Factors Engineering (HFE) rules, that is, as a result of the NUREG-0711 elements related to Planning and Analysis, i.e. HFE program Management, Operating Experience Review (OER), Functional Requirements Analysis and Function Allocation (FRA&AOF), Task analysis (TA), Staffing and Qualification (S&Q), and Human Reliability Analysis (HRA). In modern Main Control Rooms (MCR), computerized and operated from software displays, an entire HFE analysis should be developedfor the complete set of operating and supervision displays. Conventional panels, such as Remote Shutdown panel, Back-up Panel, or any redundant panel, can be obtained, from an HFE point of view, as an integrated process in the HFE analysis. There are two main ways to perform the HFE analysis. The first one is to establish a list of functions obtained from all actions needed to mitigate all scenarios due to the Design Basis Accidents (DBA), Normal, and Abnormal Operation. From the hardware panel design point of view, this way is the most convenient because it can assign a function to each panel and then it can be designed without any interference. However, this way to work implies that the HFE team has to work independently of the actual design and the integration with the actual systems could carry out potential unresolved conflicts with the design team. The second one is based on the actual design. The HFE evaluation is performed on a systems function basis. So when a system is released by the design team, it can be evaluated by the HFE team. The HFE team could supply feedback to the design team in order to include the HFE issues in the next design revision. This way is very convenient because the HFE analysis is done at the same time as the design. However, all redundant panels with back-up function are left out of the design analysis. This paper shows the methodology for including the design, manufacturing and testing of all back-up panels in the HFE program. This paper also describes the proposed process according to the experience obtained due to this process has been implemented in new construction Nuclear power Plants around the world (USA NPPs, China NPPs and Taiwan NPPs).


Ballesteros A.,Tecnatom | Altstadt E.,Helmholtz Center Dresden
Strength of Materials | Year: 2013

This paper presents and describes key open issues which are being debated nowadays by experts in the field, and for which clarification is essential for a safe operation of the nuclear power plants during life extension. Notably: late blooming effects in low Cu steels; effects of Cu, Ni, Mn, and P on the irradiated microstructure and on hardening and embrittlement; use of material test reactor data for assessment in power reactors (including flux and spectrum effects); Master Curve versus Unified Curve and fracture toughness behavior of highly irradiated material; embrittlement in RPV zones out of the traditional beltline ("the expanding beltline"); embrittlement trend curves at high neutron fluence, where data are scarce; re-embrittlement after annealing. © 2013 Springer Science+Business Media New York.


Rejas L.,Tecnatom
7th International Topical Meeting on Nuclear Plant Instrumentation, Control, and Human-Machine Interface Technologies 2010, NPIC and HMIT 2010 | Year: 2010

The last years in the nuclear industry has started a modernization process in order to take advantage of the new digital technologies. In the modern Main Control Rooms (MCR) are being installed the new digital Distributed Control systems (DCS). In the advanced MCRs, the conventional controls and indicators are being replaced with software ones. The software capability involves a big increasing in the numbers of indicators (including alarms) and controls compare to the hardware ones. These signals supply very detail information that can be used in order to increase the plant availability and the safety operation. Using a sorted and filtered information, the operator can evaluate and detect in easy way, the plant malfunctions, accident diagnosis and the operator, so, basically the operator can avoid a quite significant human errors due to a misunderstanding or missing information. From Human Factors Engineering (HFE) Point of view, it is so not desirable the information excess as the defect of it. The crowd information available to the operator in the MCR for new constructions plans could be a risk factors because it can misunderstand to the operator and he could not be able to discriminate which information is essential which is superfluous, moreover when a plant is in a critical situation. Select and show what and which information has to be presented to the operator in each plant situation is the biggest goal. The High level displays (HLD) complement the System Operating Displays (SOD), HLD shows all needed information in order to obtain a plant group vision or a dedicate part of it. Operating displays (SOD and HLD) supply the information that the operator can demand in for the following reasons: System detail information during normal, surveillance or maintenance operation Information and control capabilities in order to perform any plant procedure; normal, surveillance, abnormal, or even emergency procedure. Monitoring the general plant status in order to avoid any misunderstanding any plant situation. This paper describes the method developed by Tecnatom for designing HLD based on HFE technologies (NUREG-0711 Rev. 2 and NUREG 0700 Rev. 2).


Trademark
Tecnatom | Date: 2011-01-04

Electronic instruments for use in remote inspection and measurement of industrial components using remote visual devices; optical inspection apparatus for industrial use; ultrasound inspection devices for non-medical, non-destructive testing; radiation measuring instruments; resistance measuring instruments; electronic indicator boards and electronic indicator panels; mechanical and electronic measuring machines for identifying and analyzing structural damage to buildings and industrial plants; scientific instruments, namely, electronic analyzers for measuring, testing and detecting contaminants and environmental pollutants; technical measuring, testing and checking apparatus and instruments for measuring, testing and checking the temperature, pressure, quantity and concentration of gas and liquids; testing and measuring equipment for use in testing the performance and efficiency of power plant equipment; calibration devices for calibrating optical emission spectrometers and atomic emission spectrometers; computer hardware and computer peripherals; computer component testing and calibrating equipment. Research and development in the field of engineering, aerospace engineering, railway construction and petrochemical industry and of energy production plants, and consultation in connection therewith; product research and development; design and testing for new product development; product safety testing; engineering services, namely, structural and fracture analysis; engineering services; environmental engineering services; material testing, technology supervision and inspections in the field of aerospace engineering, railway construction and petrochemical industry and of energy production plants; laboratory research in the field of nuclear and petrochemical energy; technology supervision and inspections in the field of product quality control; computer programming and software design; measurement evaluations in the field of radioactivity.


Trademark
Tecnatom | Date: 2010-08-31

Electronic instruments for use in remote inspection and measurement of industrial components using remote visual devices; optical inspection apparatus for industrial use; ultrasound inspection devices for non-medical, non-destructive testing; radiation measuring instruments; resistance measuring instruments; electronic indicator boards and electronic indicator panels; mechanical and electronic measuring machines for identifying and analyzing structural damage to buildings and industrial plants; scientific instruments, namely, electronic analyzers for measuring, testing and detecting contaminants and environmental pollutants; technical measuring, testing and checking apparatus and instruments for measuring, testing and checking the temperature, pressure, quantity and concentration of gas and liquids; testing and measuring equipment for use in testing the performance and efficiency of power plant equipment; calibration devices for calibrating optical emission spectrometers and atomic emission spectrometers; computer hardware and computer peripherals; computer component testing and calibrating equipment. Research and development in the field of engineering, aerospace engineering, railway construction and petrochemical industry and of energy production plants, and consultation in connection therewith; product research and development; design and testing for new product development; product safety testing; engineering services, namely, structural and fracture analysis; engineering services; environmental engineering services; material testing, technology supervision and inspections in the field of aerospace engineering, railway construction and petrochemical industry and of energy production plants; laboratory research in the field of nuclear and petrochemical energy; technology supervision and inspections in the field of product quality control; computer programming and software design; measurement evaluations in the field of radioactivity.


Trademark
Tecnatom | Date: 2014-07-18

Data collection, data conversion and broadcasting apparatus; electronic database recorded on computer media; data processors; computer programmers for data processing; data entry, data exit and data display terminals; data processing systems; interactive data transfer apparatus; electronic encryption apparatus; electronic data loggers and recorders; measuring instruments for performing non-destructive testing; apparatus for the reproduction of ultrasound image.


Trademark
Tecnatom | Date: 2016-02-18

Regulating and controlling apparatus and instruments, namely, scanners and laser scanners for industrial inspection and nuclear fuel rods control. Quality control for others; testing, monitoring and inspection of nuclear fuel rods; electronic scanning of nuclear rods.

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