Résultats de la recherche - Miguel Mattar Neto
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Design considerations for rectangular bolted full face flanged joints for surface condensers
Publié 2022-10-01Accéder au texte intégralRectangular bolted full face flanged joints are widely used in surface condensers within the power generation industry including the nuclear one. In order to design these components, it is necessary to analyze the flanged joint from the point of view of structural strength and tightness. This work p...
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Simplified CFD model of coolant channels typical of a plate-type fuel element: an exhaustive verification of the simulations
Publié 2019-06-01Accéder au texte intégralThe use of parallel plate-type fuel assemblies is common in nuclear research reactors. One of the main problems of this fuel element configuration is the hydroelastic instability of the plates caused by the high flow velocities. The current work is focused on the hydrodynamic characterization of coo...
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Effect of Mounting Orientation on Testing Equipment on Elastic Compliance of Clamped SE(T) Specimens: an exploration
Publié 2022-10-01Accéder au texte intégralThe accurate evaluation of fracture mechanics properties is key to the safety of operation of high responsibility structures such as nuclear reactor components. This paper evaluates the impact of mounting orientation on the test machine of clamped SE(T) (SE(T)c) specimens on its compliance. The elas...
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Recommendation for linearization procedure in nuclear pressure vessel-nozzle intersections
Publié 2021-02-01Accéder au texte intégralThe pressure vessel design is a fundamental step during the construction of new pressurized water reactors (PWRs). In these facilities, several safety requirements are necessary to guarantee the protection of workers, community and environment against the release of radioactive materials. The Design...
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Pressure Vessels Structural Integrity Assessment Using Failure Analysis Diagrams
Publié 2025-02-01Accéder au texte intégralThere is much discussion today about the possibility of extending the lifetime of industrial plant components due to economic factors. Pressure vessels are among the most expensive components, and their replacement can significantly impact the operation of an entire plant. In this context, several...
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Encapsulated OSB Energy Absorption Potential: A Preliminary Analysis
Publié 2022-10-01Accéder au texte intégralThe transport of radioactive substances is, in many ways, necessary in the context of the nuclear fuel cycle that aims to generate energy or radioisotopes. In the event of a possible accident, the shock-absorbing parts reduce the mechanical stresses on the other components of the transport packaging...
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Development of the Reliability Assurance Program in a Brazilian nuclear power plant subsidized by a Reliability, Availability and Maintainability Model
Publié 2023-12-01Accéder au texte intégralThe main objective of this work is to present a methodology for the development of a Reliability Assurance Program (RAP) specific to a PWR experimental nuclear installation, through the analysis of the installation and the development of a preliminary RAP subsidized by a Reliability, Availability an...
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RMB experimental program on the hydrodynamical behavior of fuel assemblies
Publié 2021-02-01Accéder au texte intégralThe Brazilian Multipurpose Reactor - RMB is a 30 MW pool type research reactor, that uses Materials Testing Reactor - MTR type fuel assemblies. It has a 5x5 square array core with 23 fuel assemblies and two in-core irradiation positions, operating with upward flow and average velocities nearly 10 m/...
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Overview of the seismic probabilistic safety assessment applied to a nuclear installation located in a low seismicity zone
Publié 2021-07-01Accéder au texte intégralDeterministic and probabilistic nuclear safety analysis methodologies have been developed and updated based on operational experience, investigation of past incidents or accidents, and analysis of postulated initiating events in order to maintain the protection of workers, the public and the environ...
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Evaluation of “Safety Related” and “Important to Safety” terminology for safety classification of nuclear installation items in Brazil
Publié 2022-10-01Accéder au texte intégralIn general terms, safety demonstration of nuclear installations is carried out through an assessment of compliance with design criteria and safety requirements established in national and international codes and standards applicable to each type of installation. In addition, a safety analysis consis...
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Critical Velocity Experimental Assessment in Flat Plate Fuel Element for Nuclear Research Reactor
Publié 2022-09-01Accéder au texte intégralAluminum-coated plates, containing a uranium silicide (U3Si2) meat dispersed in an aluminum matrix, are commonly used in the fuel elements of Material Testing Reactors (MTRs). These fuel elements are typically comprised of narrow channels formed by parallel flat plates, which allow coolant flow to...
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Study on the Licensing Framework for Land Facilities Supporting Nuclear-powered Submarines in the United Kingdom
Publié 2025-02-01Accéder au texte intégralThis study examines nuclear regulation in the United Kingdom, focusing on licensing processes for land facilities supporting nuclear-powered submarines. It highlights the importance of these submarines for defense and maritime security, along with the need for specialized infrastructure to operate...
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