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Dinamica e controle de um gerador de vapor do tipo passo-unicoGOMES, ARIVALDO V. 09 October 2014 (has links)
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Transformadas de Wavelets e logica Fuzzi na inspecao por Eddy-Current em tubos de geradores de vapor de centrais nuclearesLOPEZ, LUIZ A.N.M. 09 October 2014 (has links)
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Modelagem computacional de caldeiras de recuperação termica / Computational model of heat recovery steam generatorsGomes, Ricardo Antonio do Espirito Santo 13 August 2018 (has links)
Orientador: Jorge Isaias Llagostera Beltran / Dissertação (mestrado) - Universidade Estadual de Campinas, Faculdade de Engenharia Mecanica / Made available in DSpace on 2018-08-13T22:38:51Z (GMT). No. of bitstreams: 1
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Previous issue date: 2005 / Resumo: Este trabalho faz a análise de caldeiras de recuperação térmica aquotubular no ponto de projeto e fora de projeto, seja ela parte integrante de uma central termoeléctrica de ciclo combinado ou de plantas de cogeração. Os mecanismos de troca de calor, que conduzem à produção de vapor na caldeira, encontram-se parametrizados num sistema matemático baseado nas leis fundamentais da termodinâmica e da transferência de calor, aplicado a um programa computacional. O programa foi desenvolvido no ambiente do software Engineering Equation Solver -EES. Quatro configurações básicas foram estudadas, considerando caldeiras com um e dois níveis de pressão e a variação de parâmetros relevantes. O modelo computacional desenvolvido, caracteriza-se pela sua flexibilidade já que os fatores geométricos da caldeira não precisão ser avaliados. Eventos operacionais como a queima auxiliar e o controle da temperatura do vapor, também podem ser avaliados, para todas as configurações disponíveis. Através das estruturas com dois níveis de pressão é possível evidenciar como a energia recuperada pode ser maximizada redistribuindo as superfícies de aquecimento. Esta analise é realiza para diversos casos, simulada com dados publicados, para sistemas reais e sistemas em estudo, contemplando desta forma cenários operacionais, que poderão esta de acordo com a realidade de qualquer unidade industrial / Abstract: The objective of this work was to model thermal recovery water tube boilers in the design and off-design point, either it has left integrant of a thermoelectric central office of agreed cycle or cogeneration plants. The heat exchange mechanisms, that lead to the steam production in the boiler, meet parameterizations in a based mathematical system in the thermodynamics and the heat transference basic laws, applied to a computational program. The program was developed in the environment of software Engineering Equation Solver - EES. Four basic configurations had been studied, considering boilers with one and two pressure levels and the excellent parameter variation. The developed computational model is characterized for its flexibility, since the steam generators geometric factors no is evaluated. Operational events as the burning auxiliary and the control of the temperature of the steam also can be evaluated for all the available configurations. Through the structures with two levels of pressure it is possible evidences as the recouped energy can be maximized reconfiguring the heating surfaces. This analyzes is carries through for diverse cases, simulated with data published, for real systems and systems in study, contemplating of this form operational scenes, that will be able this in accordance with the reality of any industrial unit / Mestrado / Termica e Fluidos / Mestre em Engenharia Mecânica
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Evaluation of Safety Transients in Helical Coil Steam Generators with RELAP5-3D Code / Safety Transients in Helical Coil Steam GeneratorsAlkan, Cahit January 2022 (has links)
Around the world, countries are increasingly considering carbon-free energy generation
options as the threat of climate change grows. Small modular reactor designs,
promising such carbon-free energy generation, are thriving worldwide with novel and
innovative technologies that improve safety as well as economic performance. Canada
is also considering small modular reactors (SMRs) as a means of achieving net zero
carbon emissions by 2050.
Some of these reactor designs utilize pressurized water for cooling and moderator.
Reactors with pressurized water have been subjected to steam generator tube ruptures
in the past, and a detailed investigation into the possible consequences of such incidents
in SMRs should be conducted.
In this research, a model for one of the newer designs, the NuScale Integrated Small
Modular Reactor, was developed with the RELAP5-3D code for assessing safety related
transients. The NuScale Small Modular Reactor incorporates helical coil steam
generators within its reactor pressure vessel, which are more efficient in terms of heat
transfer than the U-tube steam generators that are widely used in nuclear reactors.
In the first part of the research, a detailed model is created and used to obtain steady
state conditions with parameters collected from NuScale’s Final Safety Analysis Report
(FSAR). The Steam Generator Tube Rupture event is analyzed in the second part
of the work. Slight differences in the broken and intact steam generator pressures as
well as decay heat removal system flow rates are seen in the comparison of reference
values and calculated results. Among the reasons for those differences could be that
the correlations used by the RELAP5-3D code for heat transfer coefficient and pressure
drop in the helical coil steam generators are different than those of the NuScale proprietary
code NRELAP5, with which the analyses have been performed in the FSAR.
Also, post-dryout heat transfer at the exit of helical coil steam generators and evaporator
sections could cause differences in the outlet conditions of the steam, resulting in
different mass flow rates as well.
The final section of the research simulates a comparable but more severe tube rupture
incident without the availability of decay heat removal systems in order to assess
the reactor’s emergency core cooling system reaction. Passive decay heat removal systems
are crucial components for removing heat after reactor shutdown through heat
exchangers that are submerged in the reactor pool and connected to steam generators
by a closed loop. The containment pressures, the containment wall temperatures, and
the peak fuel clad temperatures are considered to be the key design constraints that
must be observed.
Future work on this subject could include modifying the source code, adding specific
correlations for helical coil steam generators, and comparing the results, as well
as quantifying uncertainties in the SGTR event. Main parameters in the quantification
of uncertainties would be reactor power, single phase and two-phase discharge coefficients
from the break, trip signals and delays as well as break size and location. / Thesis / Master of Applied Science (MASc)
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An experimental study of an inherently-safe, natural circulating, flash-tube type system for a nuclear reactor steam supply conceptLoubser, Karl Albie 12 1900 (has links)
Thesis (MEng) -- Stellenbosch University, 2014. / ENGLISH ABSTRACT: This project investigates aspects of a novel inherently safe nuclear power steam
supply system as safety is of paramount importance. The system envisaged has
unique features namely: a) a two-phase flow flash-tube type natural circulating
primary loop (also the secondary radioactive particle containment); b) a twophase
flow thermosyphon heat pipe type heat exchanger secondary loop is
used to transfer heat from the primary loop to the steam generators, thereby
physically separating the two flow streams from one another; c) a natural
convection air cooled condenser for the removal of the reactor’s residual heat;
d) a unique core using TRISO type fuel (acting as the primary radioactive
particle containment) with life of at least 8.9 years; e) a steel containment vessel
acting as a tertiary radioactive product containment; f) a concrete containing
structure with air vents to allow air to pass over the main steel containment
vessel for cooling purposes in the case of an emergency, and for the removal of
parasitic heat during operation.
In particular the primary and secondary loops of the proposed system are
investigated. This is done by design, construction and testing of a small scale
experimental set-up of the primary and secondary loops as well as the development
of theoretical models for the two loops. A literature survey focusing on
nuclear technology, thermosyphon loops, natural circulating loop instabilities,
heat pipes, and two-phase flow modelling is presented to give a brief overview
of the technologies as well as tools used in the work undertaken.
Observations of the inside flow behaviour of the primary loop experimental
set-up were made possible by windows providing many insights into the inner
workings, such as plume formation and geysering. The transient response of
the secondary heat pipe loop start-up is also investigated.
A thermal resistance theoretical model was developed for the secondary
loop using heat transfer formulae from theory as well as experimentally semiempirical
correlated formula. Different states of operation of the secondary
loop were observed during testing with the theoretical model of the condensing regime correlating well, two-phase regime correlating acceptably and liquid
regime correlating poorly to experimental results and thus were modelled using
an experimentally determined overall heat transfer coefficient. The secondary
loop model of the liquid regime is coupled with the primary loop theoretical
model to predict the system’s performance.
A homogeneous, one-dimensional, simple theoretical model for the primary
loop was derived and computer simulated. The results did not compare well
with experimental results for single phase flow and failed to capture the onset
of two-phase flow. The assumptions of one dimensional model with a unidirectional
flow, a hydrostatic pressure problem, a constant volumetric flow rate
and the inability of the implementation of the code to handle expansion are
noted as some of the flaws in the theoretical model.
The following recommendations are made: a more advanced design of the
pressuriser should be incorporated into the experiment; the secondary loop’s
theoretical model should be characterised under a broader set of operating
conditions; the computer program can be used as the basis for further research
and implementation of alternative solution algorithms and models. / AFRIKKANSE OPSOMMING: Hierdie projek ondersoek aspekte van ’n ongewone, essensieel veilige kernkrag
stoomtoevoer-stelsel, omdat veiligheid van kardinale belang is. Die stelsel wat
voorgestel is, het unieke eienskappe, naamlik: a) ’n twee-fasevloei flits-buistipe
natuurlik sirkulerende primêre lus (wat ook die sekondêre inperking van
radioaktiewe materiaal bevat); b) ’n twee-fasevloei termo-heweleffek sekondêre
lus hitte-pyp hitte-uitruiler word gebruik om die hitte vanaf die primêre lus
oor te dra na die stoomkragopwekkers en daardeur word die twee strome se
vloei fisies geskei van mekaar; c) ’n natuurlike konveksie lugverkoelde kondensor
word gebruik vir die verwydering van die reaktors se oortollige hitte; d) ’n
unieke kern gebruik TRISO-tipe brandstof (wat as die primêre inperking van
radioaktiewe materiaal optree) met ’n lewe van minstens 8.9 jaar; e) ’n inperkingshouer
van staal wat optree as ’n tersiêre radioaktiewe produkhouer; f) ’n
betonstruktuur met lugventilasie om toe te laat dat lug oor die hoof staalhouer
vloei vir verkoeling in ’n noodgeval, en vir die verwydering van parasitiese hitte
tydens werking.
Hoofsaaklik word die primêre en sekondêre lusse van die voorgestelde stelsel
ondersoek. Dit word gedoen deur die ontwerp, konstruksie en die toets
van ’n eksperimentele opstelling van die primêre en sekondêre lusse op klein
skaal, sowel as die ontwikkeling van teoretiese modelle vir die twee lusse. ’n Literatuurstudie
wat fokus op kerntegnologie, termo-heweleffeklusse, natuurlik
sirkulerende lus instabiliteit, hitte-pype, en twee-fase vloeimodellering word
aangebied om ’n kort oorsig te gee van die tegnologie, sowel as gereedskap
gebruik in die werk wat onderneem is.
Om die interne vloeigedrag van die primêre lus se eksperimentele opstelling
waar te neem, word daar gebruik gemaak van vensters wat dien as ’n manier
om die innerlike werking van die proses soos pluimvorming en die kook van die water in die warmwaterkolom te toon. Die oorgangsreaksie van die sekondêre
hittepyplus aanvangs is ook ondersoek.
’n Teoretiese termiese weerstandmodel is ontwikkel vir die sekondêre lus
met behulp van hitte-oordragformules waarvoor hitte-oordragteorie gebruik
is, wat met eksperimentele semi-empiriese formules gekorreleer is. Verskillende
toestande van die sekondêre lus se werking is waargeneem gedurende die toetse.
Die teoretiese model het goed met die kondensasiestaat gekorreleer, terwyl by
die twee-fasewerkswyse aanvaarbare korrellasies aangetref is en die uiteindelike
vloeitoestand swakker gekorrelleer het met eksperimentele resultate en dus
gemodelleer is met behulp van die NTU-effektiwiteitsmetode. Die sekondêre
lusmodel van die vloeistoftoestand is gekoppel met die primêre lus teoretiese
model om die werking van die stelsels te voorspel.
’n Homogene een-dimensionele eenvoudige teoretiese model van die primêre
lus is afgelei en ’n rekenaar simulasie is uitgevoer. Die resultate vergelyk nie
goed met die eksperimentele resultate vir enkelfasevloei en kon nie die aanvang
van twee-fasevloei beskryf nie. Die aannemings van ’n een-dimensionele
model met eenrigting vloei, ’n hidrostatiese druk probleem, ’n konstant volumetries
vloeitempo en die onvermoë van die implementering van die kode
om uitbreiding te hanteer is bekend as ’n paar van die foute in die teoretiese
model.
Die volgende aanbevelings word gemaak: ’n meer gevorderde ontwerp van
drukreëlaar moet in die eksperiment ingesluit word; die sekondêre lus se teoretiese
model moet gekenmerk word onder ’n wyer stel bedryfsomstandighede,
en die rekenaar program kan gebruik word as die basis vir verdere navorsing
en die implementering van alternatiewe algoritmes en modelle.
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Análise de defeitos em tubos de geradores de vapor de usinas nucleares utilizando a transformada de Hilbert-Huang em sinais de inspeção por correntes parasitas / Defects diagnosis of nuclear power plant steam generator tubes using the Hilbert-Huang transform in eddy current testing signalsFORMIGONI, ANDRE L. 09 October 2014 (has links)
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Analise de integridade estrutural de tubos de geradores de vapor deteriorados por corrosao sob tensao pelo primario na regiao de transicao de expansao junto ao espelhoSILVEIRA, HELVECIO C.K. da 09 October 2014 (has links)
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Concepção e análise técnico-econômica da recuperação de calor em sistemas de despoeiramento de aciarias elétricas para geração de vapor superaquecido / Design and technical-economical analysis of the heat recovery in dedusting systems of electric steel mill for the generation of superheated steamSilva Júnior, Cesar Augusto Arezo [UNESP] 16 December 2016 (has links)
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Previous issue date: 2016-12-16 / As usinas siderúrgicas caracterizam-se, sob o ponto de vista energético, pela grande intensidade de energia empregada em processos de redução do minério de ferro, fusão das matérias-primas e refino do aço líquido obtido. Quanto aos processos utilizados para a produção de aço, destacam-se o emprego de duas rotas tecnológicas: usinas integradas e semi-integradas (mini-mills). As usinas integradas possibilitam a redução do minério de ferro até ferro-gusa e, a partir deste, a obtenção do aço. As mini-mills caracterizam-se pelo emprego de sucatas metálicas, ferro-gusa ou ferro esponja como matérias-primas e pela obtenção, como produtos, de diferentes tipos de aço. Na operação de refino do aço líquido produzido comumente é necessário o emprego de desgaseificadores a vácuo para remoção de contaminantes e, consequentemente, atendimento às especificações do produto acabado. Com isso, as mini-mills demandam potência elétrica para os processos de fusão do aço e vapor superaquecido para obtenção de vácuo nos ejetores do processo de desgaseificação. Para atendimento a legislações ambientais, sistemas de despoeiramento devem ser aplicados às aciarias, disponibilizando grandes vazões de gases quentes provenientes do forno elétrico. A operação do sistema de despoeiramento indica expressivo potencial para recuperação de calor em processos siderúrgicos. Na presente dissertação propõe-se a coleta e análise de dados de operação do sistema de despoeiramento de um forno elétrico a arco de uma mini-mill brasileira, visando concepção e análise técnica-econômica de uma central de cogeração associada à recuperação de calor destes gases do sistema de despoeiramento / The steel industry can be characterized by its high demand of energy in the process of reduction and production of pig iron and steel. For the production of steel the following routes can be highlighted: integrated plants and mini-mills. Integrated plants are used for production steel from iron ore, allowing the reduction of iron ore until pig iron, and pig iron to steel. Mini-mills are used for production of steel through metallic scraps and pig iron. In a mini-mill, the transformation of metallic scraps and pig iron to steel is reached in melting shop areas. The melting shop areas adopt vacuum degassers as a commonly equipment to remove contaminants of liquid steel and consequently reach requirements of finished products. As a consequence, in a melting shop, electricity is applied in electric arc furnaces and overheated steam is applied in vacuum degassers. According to environmental restrictions these melting shops are integrated with dust collectors. The dust collected in electric arc furnaces has great amount of energy and can express a high potential to heat recovering systems. The present dissertation has purpose in collect and analyzes data from an electric arc furnace with a dust collector in a Brazilian mini-mill for developing a thermal-economic analysis of a cogeneration plant integrated in this mini-mill.
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Análise de defeitos em tubos de geradores de vapor de usinas nucleares utilizando a transformada de Hilbert-Huang em sinais de inspeção por correntes parasitas / Defects diagnosis of nuclear power plant steam generator tubes using the Hilbert-Huang transform in eddy current testing signalsFORMIGONI, ANDRE L. 09 October 2014 (has links)
Made available in DSpace on 2014-10-09T12:35:10Z (GMT). No. of bitstreams: 0 / Made available in DSpace on 2014-10-09T14:00:55Z (GMT). No. of bitstreams: 0 / Os tubos de Geradores de Vapor em Reatores Nucleares do tipo PWR são submetidos a diferentes níveis de tensões e carregamento em altas temperaturas, reduzindo sua vida útil devido o surgimento de defeitos e corrosão. A inspeção por Correntes Parasitas é um ensaio não destrutivo usado para diagnosticar defeitos de corrosão e descontinuidades na superfície externa e interna em tubos de trocadores de calor. Esses tubos estão sujeitos a danos por diferentes mecanismos de degradação mecânica e química, tais como trincas por fadiga e corrosão sob tensão. Os sinais de inspeção por Correntes Parasitas são afetados por diferentes ruídos dificultando sua análise pelo inspetor. Esse trabalho apresenta os resultados da análise dos sinais de Correntes Parasitas usando a Transformada de Hilbert-Huang (THH) funcionando como filtro de ruídos (De-noising), como uma técnica alternativa de processamento e análise de sinais. A Transformada de Hilbert-Huang teve esse nome atribuído pela agência espacial norte-americana (NASA) para o resultado da reunião de dois processos, um método de decomposição empiricamente modal (Empirical Mode Decomposition EMD), seguido da análise espectral de Hilbert (Hilbert Spectral Analysis HSA). Os sinais de inspeção por correntes parasitas possuem características de transiente, não estacionário e não linear. A transformada de Hilbert-Huang aplicada neste trabalho forneceu dois recursos alternativos em processamento de sinais; o pré-processamento que funcionou como filtro de ruídos, e outro de análise de sinais, responsável pela identificação das características tempo-frequência-energia do sinal. / Dissertação (Mestrado) / IPEN/D / Instituto de Pesquisas Energeticas e Nucleares - IPEN-CNEN/SP
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Analise de integridade estrutural de tubos de geradores de vapor deteriorados por corrosao sob tensao pelo primario na regiao de transicao de expansao junto ao espelhoSILVEIRA, HELVECIO C.K. da 09 October 2014 (has links)
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