Дисертації з теми "Nuclear reactor monitoring"
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Jahn, Gordon James. "Agent-based structural condition monitoring for nuclear reactor cores." Thesis, University of Strathclyde, 2011. http://oleg.lib.strath.ac.uk:80/R/?func=dbin-jump-full&object_id=17400.
Повний текст джерелаWallace, Christopher John. "Distributed data fusion for condition monitoring of graphite nuclear reactor cores." Thesis, University of Strathclyde, 2013. http://oleg.lib.strath.ac.uk:80/R/?func=dbin-jump-full&object_id=20607.
Повний текст джерелаROSSI, ROSA H. P. S. "Utilizacao de redes neurais na monitoracao da potencia do reator IEA-R1." reponame:Repositório Institucional do IPEN, 2001. http://repositorio.ipen.br:8080/xmlui/handle/123456789/10895.
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Dissertacao (Mestrado)
IPEN/D
Instituto de Pesquisas Energeticas e Nucleares - IPEN/CNEN-SP
Ertiame, A. M. S. "Monitoring and fault diagnosis for Chylla-Haase polymerization reactor." Thesis, Liverpool John Moores University, 2016. http://researchonline.ljmu.ac.uk/5001/.
Повний текст джерелаInzerillo, Santo. "Nonlinear estimation for condition monitoring of advanced gas-cooled nuclear reactor cores." Thesis, University of Strathclyde, 2012. http://oleg.lib.strath.ac.uk:80/R/?func=dbin-jump-full&object_id=19546.
Повний текст джерелаStewart, Christopher L. "Antineutrino-based safeguards for ultra-high burnup fast reactors." Diss., Georgia Institute of Technology, 2016. http://hdl.handle.net/1853/55024.
Повний текст джерелаNeighbour, Gareth Bryan. "Microstructural processes leading to fracture in nuclear graphites." Thesis, University of Bath, 1993. https://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.332601.
Повний текст джерелаBerglöf, Carl. "On measurement and monitoring of reactivity in subcritical reactor systems." Doctoral thesis, KTH, Reaktorfysik, 2010. http://urn.kb.se/resolve?urn=urn:nbn:se:kth:diva-12483.
Повний текст джерелаQC 20100621
FERREIRA, JUNIOR DECIO B. M. "Desenvolvimento de um sistema computacional para monitoracao dos parametros de reatividade e das oscilacoes axiais de xenonio do reator nuclear de Agra 1." reponame:Repositório Institucional do IPEN, 2001. http://repositorio.ipen.br:8080/xmlui/handle/123456789/10918.
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Dissertacao (Mestrado)
IPEN/D
Instituto de Pesquisas Energeticas e Nucleares - IPEN/CNEN-SP
MINDA, ELISE. "SENSITIVITY STUDIES ON NONDESTRUCTIVE EVALUATION (NDE) METHODS FOR MONITORING FATIGUE AND THERMAL EMBRITTLEMENT IN AUSTENITIC AND FERRITIC STEEL NUCLEAR REACTOR PLANT (NRP) COMPONENTS." University of Cincinnati / OhioLINK, 2007. http://rave.ohiolink.edu/etdc/view?acc_num=ucin1195611890.
Повний текст джерелаSingo, Thifhelimbilu Daphney. "Development of a high flux neutron radiation detection system for in-core temperature monitoring." Thesis, Stellenbosch : Stellenbosch University, 2012. http://hdl.handle.net/10019.1/19999.
Повний текст джерелаENGLISH ABSTRACT: The objective of this research was to develop a neutron detection system that incorporates a mass spectrometer to measure high neutron flux in a nuclear reactor environment. This system consists of slow and fast neutron detector elements for measuring fluxes in those energy regions respectively. The detector should further be capable of withstanding the harsh conditions associated with a high temperature reactor. This novel detector which was initially intended for use in the PBMR reactor has possible applications as an in-core neutron and indirect temperature-monitoring device in any of the HTGR. Simulations of a generic HTGR core model were performed in order to obtain the neutron energy spectrum with emphasis on the behavior of three energy regions, slow, intermediate and fast neutrons within the core at different temperatures. The slow neutron flux which has the characteristic of a Maxwell- Boltzmann distribution were found to shift to larger values of neutron flux at higher energies as the fuel temperature increased, while fast neutron flux spectra remained relatively constant. In addition, the results of the fit of the slow neutron flux with a modified Maxwell-Boltzmann equation confirmed that in the presence of the neutron source, leakage and absorption, the effective neutron temperatures is above the medium temperatures. From these results, it was clear that the detection system will need to monitor both slow and fast neutron flux. Placing neutron detectors inside the reactor core, that are sensitive to a particular energy range of slow and fast neutrons, would thus provide information about the change of temperature in the fuel and hence act as an in-core temperature monitor. A detection mechanism was developed that employs the neutron-induced break-up reaction of 6Li and 12C into α-particles. These materials make excellent neutron converters without interference due to γ-rays, as the contributions from 6Li(γ,np)4He and 12C(γ,3α) reactions are negligible. The mass spectrometer measures the 4He partial pressure as a function of time under high vacuum with the help of pressure gradient provided by a high-vacuum turbomolecular pump and a positive-displacement fore-vacuum pump connected in series. A cryogenic trap, which contains a molecular sieve made of pellets 1.6 mm in diameter, was also designed and manufactured to remove impurities which cause a background in the lighter mass region of the spectrum. The development and testing of the high flux neutron detection system were performed at the iThemba Laboratory for Accelerator Based Sciences (LABS), South Africa. These tests were carried out with a high energy proton beam at the D-line neutron facility, and with a fast neutron beam at the neutron radiation therapy facility. To test the principle and capability of the detection system in measuring high fluxes, a high intensity 66 MeV proton beam was used to produce a large yield of α-particles. This was done because the proton inelastic scattering cross-section with 12C nuclei is similar to that of neutrons, with a threshold energy of about 8 MeV for both reactions. Secondly, the secondary fast neutrons produced from the 9Be(p,n)9B reaction were also measured with the fast neutron detector. The response of this detection system during irradiation was found to be relatively fast, with a rise time of a few seconds. This is seen as a sharp increase in the partial pressure of 4He gas as the proton or neutron beam bombards the 12C material. It was found that the production of 4He with the proton beam was directly proportional to the beam intensity. The number of 4He atoms produced per second was deduced from the partial pressure observed during the irradiation period. With a neutron beam of 1010 s−1 irradiating the detector, the deduced number of 4He atoms was 109 s−1. When irradiation stops, the partial pressure drops exponentially. This response is attributed to a small quantity of 4He trapped in the present design. Overall, the measurements of 4He partial pressure produced during the tests with proton and fast neutron beams were successful and demonstrated proof of principle of the new detection technique. It was also found that this system has no upper neutron flux detection limit; it can be even higher than 1014 n·cm−2·s−1. The lifetime of this detection system in nuclear reactor environment is practically unlimited, as determined by the known ability of stainless steel to keeps its integrity under the high radiation levels. Hence, it is concluded that this high flux neutron detection system is excellent for neutron detection in the presence of high γ-radiation level and provides real-time flux measurements.
AFRIKAANSE OPSOMMING: Die doel van hierdie navorsing was om ’n neutrondetektorstelsel te ontwikkel wat hoë neutronvloed binne in ’n kernreaktor kan meet. Die stelsel bevat twee aparte detektorelemente sodat die termiese sowel as snelneutronvloed gemeet kan word. Die detektor moet verder in staat wees om die strawwe toestande, kenmerkend aan ’n hoë temperatuur reaktor, te kan weerstaan. Die innoverende detektorstelsel, oorspronklik geoormerk vir gebruik in die PBMR reaktor, het toepassingsmoontlikhede as in-kern neutron- sowel as indirekte temperatuurmonitor. Simulasies van ’n generiese model van ’n HTGR reaktorkern is uitgevoer ten einde die neutronenergiespektrum in die kern by verskillende temperature te bekom met klem op die gedrag van neutrone in drie energiegroepe: stadig (termies), intermediêr en snel (vinnig). Daar is bevind dat die stadige neutrone, wat ’n Maxwell-Boltzman verdeling toon, in intensiteit toeneem en dat die piek na hoër energie verskuif met toename in temperatuur, terwyl die vinnige neutronspektrum relatief onveranderd bly. ’n Passing van die stadige spektrum op ’n gemodifiseerde Maxwell-Boltzmann verdeling het bevestig dat die effektiewe neutrontemperatuur weens die teenwoordigheid van bronterme, verliese en absorpsie, hoër as die temperatuur van die medium is. Hierdie resultate maak dit duidelik dat die detektorstelsel beide die stadige sowel as die vinnige neutronvloed moet kan waarneem. Deur detektorelemente wat sensitief is vir die onderskeie spekrale gebiede in die reaktorhart te plaas, kan informasie bekom word wat tot in-kern temperatuur herleibaar is sodat die stelsel inderdaad as indirekte temperatuurmonitor kan dien. Die feit dat alfa-deeltjies geproduseer word in neutron-geïnduseerde opbreekreaksies van 6Li en 12C is as die basis van die nuwe opsporingsmeganisme aangewend. Hierdie materiale funksioneer uitstekend as neutron-selektiewe omsetters in die teenwoordigheid van gamma-strale aangesien laasgenoemde se bydraes tot helium produksie via die 6Li(γ,np)4He en 12C(γ,3α) reaksies, weglaatbaar is. Die massaspektrometer meet die tydgedrag van die 4He parsiële druk binne ’n hoogvakuum wat met behulp van ’n seriegeskakelde kombinasie van ’n turbomolekulêre en positiewe-verplasingsvoorpomp verkry word. ’n Koueval met ’n molekulêre sif, bestaande uit 1.6 mm diameter korrels, is ontwerp en vervaardig om onsuiwerhede te verwyder wat andersins as agtergrond by die ligter gedeelte van die massaspektrum sou wys. Die ontwikkeling en toetsing van die hoëvloed detektorstelsel is te iThembaLABS (iThemba Laboratories for Accelerator Based Sciences) gedoen. Dit is uitgevoer deur gebruik te maak van die hoë energie protonbundel van die D-lyn neutronfasiliteit asook van die bundel vinnige neutrone by die neutronterapiefasiliteit. Om die beginsel en vermoë te toets om by ’n hoë neutronvloed te kan meet, is van die intense 66 MeV protonbudel gebruik gemaak om ’n hoë opbrengs alfa-deeltjies te verkry. Dit is gedoen omdat die reaksiedeursnit vir onelastiese verstrooiing van protone vanaf 12C kerne soortgelyk is aan die van neutrone, met ’n drumpelenergie van 8 MeV vir beide reaksies. Tweedens is die sekondêre vinnige neutrone afkomstig van die 9Be(p,n)9B reaksie ook met die neutrondetektor gemeet. Daar is bevind dat die reaksietyd van die deteksiestelsel tydens bestraling relatief vinnig is, soos gekenmerk deur ’n stygtyd van etlike sekondes. Laasgenoemde manifesteer as ’n toename in die parsiële druk van die 4He sodra die proton- of neutronbundel op die 12C teiken inval. Daar is verder bevind dat die 4He produksie direk eweredig aan die bundelintensiteit is. Vir ’n neutronbundel van nagenoeg 1010 s−1, invallend op die neutrondetektor, is vanaf die gemete parsiële druk afgelei dat die produksie van 4He atome sowat 109 s−1 beloop. In die geheel beoordeel, was die meting van die 4He parsiële druk tydens die toetse met vinnige protone en neutrone suksesvol en het dit die nuwe meetbeginsel bevestig. Dit is verder bevind dat die meetstelsel nie ’n beperking op die boonste neutronvloed plaas nie, maar dat dit vloede van selfs hoër as 1014 s−1 kan hanteer. Die leeftyd van die detektorstelsel in die reaktor is prakties onbeperk en onderhewig aan die bevestigde integriteit van vlekvrystaal onder hoë bestraling. Die gevolgtrekking is dus dat die nuwe detektorstelsel uitstekend geskik is vir die in-tyd meting van ’n baie hoë vloed van neutrone ook in die teenwoordigheid van intense gammabestraling.
CARNEIRO, ALVARO L. G. "Desenvolvimento de sistema de monitoracao e diagnostico aplicado a valvulas moto-operadas utilizadas em centrais nucleares." reponame:Repositório Institucional do IPEN, 2003. http://repositorio.ipen.br:8080/xmlui/handle/123456789/11109.
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Tese (Doutoramento)
IPEN/T
Instituto de Pesquisas Energeticas e Nucleares - IPEN/CNEN-SP
PERRENOUD, HELENA G. "Modulo de extracao de eventos em assinaturas de potencia de valvulas moto-operadas, usando um sistema especialista para o sistema de diagnostico de MOV's utilizado em reatores nucleares." reponame:Repositório Institucional do IPEN, 2001. http://repositorio.ipen.br:8080/xmlui/handle/123456789/10967.
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Dissertacao (Mestrado)
IPEN/D
Instituto de Pesquisas Energeticas e Nucleares - IPEN/CNEN-SP
SANTOS, GEAN R. dos. "Algoritmo de colônia de formigas e redes neurais artificiais aplicados na monitoração e detecção de falhas em centrais nucleares." reponame:Repositório Institucional do IPEN, 2016. http://repositorio.ipen.br:8080/xmlui/handle/123456789/26798.
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Um desafio recorrente em processos produtivos é o desenvolvimento de sistemas de monitoração e diagnóstico. Esses sistemas ajudam na detecção de mudanças inesperadas e interrupções, prevenindo perdas e mitigando riscos. Redes Neurais Artificiais (RNA) têm sido largamente utilizadas na criação de sistemas de monitoração. Normalmente as RNA utilizadas para resolver este tipo de problema são criadas levando-se em conta apenas parâmetros como o número de entradas, saídas e quantidade de neurônios nas camadas escondidas. Assim, as redes resultantes geralmente possuem uma configuração onde há uma total conexão entre os neurônios de uma camada e os da camada seguinte, sem que haja melhorias em sua topologia. Este trabalho utiliza o algoritmo de Otimização por Colônia de Formigas (OCF) para criar redes neurais otimizadas. O algoritmo de busca OCF utiliza a técnica de retropropagação de erros para otimizar a topologia da rede neural sugerindo as melhores conexões entre os neurônios. A RNA resultante foi aplicada para monitorar variáveis do reator de pesquisas IEA-R1 do IPEN. Os resultados obtidos mostram que o algoritmo desenvolvido é capaz de melhorar o desempenho do modelo que estima o valor de variáveis do reator. Em testes com diferentes números de neurônios na camada escondida, utilizando como comparativos o erro quadrático médio, o erro absoluto médio e o coeficiente de correlação, o desempenho da RNA otimizada foi igual ou superior ao da tradicional.
Dissertação (Mestrado em Tecnologia Nuclear)
IPEN/D
Instituto de Pesquisas Energeticas e Nucleares - IPEN-CNEN/SP
Matlack, Kathryn H. "Nonlinear ultrasound for radiation damage detection." Diss., Georgia Institute of Technology, 2014. http://hdl.handle.net/1853/51965.
Повний текст джерелаLamotte, Maxime. "Etude du signal optique des chambres à fission et évaluation de son exploitation pour un système de mesure neutronique d'un réacteur de génération IV Development and first use of an experimental device for fission-induced spectrometry applied to neutron flux monitoring SCENA: A simulation tool for radiation-induced gas scintillation Simulation of heavy-ion slowing-down tracks with the SCENA code Design and irradiation test of an innovative optical ionization chamber technology Pulse-reactor core monitoring with an innovative optical neutron detector." Thesis, Université Grenoble Alpes, 2021. http://www.theses.fr/2021GRALI023.
Повний текст джерелаThis PhD thesis details the study of luminescence produced in gaseous detectors as fission chambers, to evaluate its use in 4th generation nuclear reactor power monitoring, as ASTRID.Energy deposition in the gas, from heavy-ions produced during nuclear fission in a fission chamber is usually used for its charge generation ability, that can be detected with electrodes. Such method has been used since the beginning of atomic era present disadvantages, and necessary improvements have been assessed.By estimating fission chamber gas excited states production, one can deduce intrinsic light emission, and its detection by appropriate photo-detectors. Use of an optical signal against an electric one improves dependability of a neutron flux monitoring system, immune to electromagnetic noise.Spectroscopic studies of a nuclear plasma in a self-designed analytical device allows observation of typical gas scintillation emission lines. Analysis of emission lines reinforce optical detection attraction, as pressure and gas composition can be monitored online.Alongside our experiments, a simulation code dedicated to heavy-ions induced cold-plasma excited levels population has been produced to optimise future detectors relying on optical emission. Typical times encountered for excited states generation and their position around an ionization track have been estimated.Several neutron detector prototypes based on the sole gas scintillation principle have been assessed in cold neutron beam lines of the Orphée reactor, to validate a proof of concept for neutron monitoring. Experiments on the Cabri reactor allowed quantification of detection limit, linearity and dynamic range of our system.The positive outcomes provided by these 3 lines of work validate the proof of concept of passive, on-line, and self-diagnosed neutron detection with high dependability in harsh environments
REIS, JUNIOR JOSE S. B. "Métodos e softwares para análise da produção científica e detecção de frentes emergentes de pesquisa." reponame:Repositório Institucional do IPEN, 2015. http://repositorio.ipen.br:8080/xmlui/handle/123456789/26929.
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O progresso de projetos anteriores salientou a necessidade de tratar o problema dos softwares para detecção, a partir de bases de dados de publicações científicas, de tendências emergentes de pesquisa e desenvolvimento. Evidenciou-se a carência de aplicações computacionais eficientes dedicadas a este propósito, que são artigos de grande utilidade para um melhor planejamento de programas de pesquisa e desenvolvimento em instituições. Foi realizada, então, uma revisão dos softwares atualmente disponíveis, para poder-se delinear claramente a oportunidade de desenvolver novas ferramentas. Como resultado, implementou-se um aplicativo chamado Citesnake, projetado especialmente para auxiliar a detecção e o estudo de tendências emergentes a partir da análise de redes de vários tipos, extraídas das bases de dados científicas. Através desta ferramenta computacional robusta e eficaz, foram conduzidas análises de frentes emergentes de pesquisa e desenvolvimento na área de Sistemas Geradores de Energia Nuclear de Geração IV, de forma que se pudesse evidenciar, dentre os tipos de reatores selecionados como os mais promissores pelo GIF - Generation IV International Forum, aqueles que mais se desenvolveram nos últimos dez anos e que se apresentam, atualmente, como os mais capazes de cumprir as promessas realizadas sobre os seus conceitos inovadores.
Dissertação (Mestrado em Tecnologia Nuclear)
IPEN/D
Instituto de Pesquisas Energéticas e Nucleares - IPEN-CNEN/SP
HIROMOTO, MARIA Y. K. "PSINCO-um programa para calculo da distribuicao de potencia e supervisao do nucleo de reatores nucleares, utilizando sinais de detetores tipo 'SPD'." reponame:Repositório Institucional do IPEN, 1998. http://repositorio.ipen.br:8080/xmlui/handle/123456789/10706.
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Dissertacao (Mestrado)
IPEN/D
Instituto de Pesquisas Energeticas e Nucleares - IPEN/CNEN-SP
Buljubasich, Gentiletti Lisandro. "Nuclear magnetic resonance as a tool for on-line catalytic reaction monitoring." Aachen Shaker, 2010. http://d-nb.info/100279109X/04.
Повний текст джерелаLeger, Robert P. "Analysis and monitoring of a CANDU nuclear power plant using multivariate statistical process control methods." Thesis, National Library of Canada = Bibliothèque nationale du Canada, 1999. http://www.collectionscanada.ca/obj/s4/f2/dsk1/tape8/PQDD_0032/NQ66218.pdf.
Повний текст джерелаBuljubasich, Gentiletti Lisandro [Verfasser]. "Nuclear Magnetic Resonance as a Tool for On-Line Catalytic Reaction Monitoring / Lisandro Buljubasich Gentiletti." Aachen : Shaker, 2010. http://d-nb.info/1120864194/34.
Повний текст джерелаBrockman, John Douglas. "Investigation of K₀ neutron activation analysis at MURR and investigation of the toenail as a biomonitor for Mg, Zn, Cu, Se and Hg." Diss., Columbia, Mo. : University of Missouri-Columbia, 2006. http://hdl.handle.net/10355/5890.
Повний текст джерелаThe entire dissertation/thesis text is included in the research.pdf file; the official abstract appears in the short.pdf file (which also appears in the research.pdf); a non-technical general description, or public abstract, appears in the public.pdf file. Title from title screen of research.pdf file (viewed on August 13, 2007) Vita. Includes bibliographical references.
Flaspoehler, Timothy Michael. "FW-CADIS variance reduction in MAVRIC shielding analysis of the VHTR." Thesis, Georgia Institute of Technology, 2012. http://hdl.handle.net/1853/45743.
Повний текст джерелаHsieh, Meng-Huan, and 謝孟寰. "A Study of Digital Neutron Monitoring System for Nuclear Reactor." Thesis, 2010. http://ndltd.ncl.edu.tw/handle/44029911357468037090.
Повний текст джерела國立清華大學
工程與系統科學系
99
Power monitoring system is one of the most important parts of nuclear planet. Due to the fact that the neutron flux in the reactor core is proportional to the reactor power, the wide range neutronmonitor system (WRNM) plays an important role in controlling and monitoring the situation of the reactor core. It can provide two main functions. First, it offers the information about the power variation; second, it provides the trip signals for the reactor protecting system in order to adjust the control rod. The classic WRNM systems were built by analog circuit system for the most parts. It is difficult to tune the parameters among different reactor system. Comparing to the analog cir-cuit system, the digital circuit system is flexible to redesign the parameters, providing a wide adaptability to different reactor systems; Moreover, analog circuit system is sensitive to the noise more than digital circuit system does, hence the readout could have errors for analog circuit system. Thanks to the rapid growing of IC technology, the efficiency of ADCs, the memory spaces of system, and the capability of realizing DSP algorithms becomes better and better these years. Using digital system to achieve the real-time processing as what can be done by classic analog system is possible for today’s WRNM. Therefore, the goal of our research is to evaluate the feasibility of digitizing the classic WRNM system, especially for the Campbell technique realization.
Lin, Ruey Iuan, and 林瑞淵. "Study of loose parts monitoring technique of nuclear reactor by neural network." Thesis, 1993. http://ndltd.ncl.edu.tw/handle/41670859805393344022.
Повний текст джерелаCronholm, Lillian Marie. "Reliability Engineering Approach to Probabilistic Proliferation Resistance Analysis of the Example Sodium Fast Reactor Fuel Cycle Facility." Thesis, 2011. http://hdl.handle.net/1969.1/ETD-TAMU-2011-08-9921.
Повний текст джерелаJorge, Pedro Filipe dos Santos. "Assessment of Low-field benchtop NMR applications in a pharmaceutical R&D laboratory." Master's thesis, 2022. http://hdl.handle.net/10362/131771.
Повний текст джерелаNa indústria farmacêutica, a monitorização de reações tornou-se uma parte importante no desenvolvimento e controlo de fármacos, quer em ambiente laboratorial de investigação e desenvolvimento (&D) quer a nível industrial. Este controlo é, usualmente, feito utilizando técnicas cromatográficas, contudo estas têm a desvantagens de serem técnicas destrutivas, demoradas e de custo monetário elevado. A espectroscopia de ressonância magnética nuclear (RMN) tem vindo a ser considerada uma possível alternativa a estas técnicas, contudo o custo de aquisição e de manutenção dos equipamentos tem sido o maior obstáculo para a sua utilização generalizada num ambiente industrial. Com o avanço no desenvolvimento de aparelhos de RMN de bancada, esta técnica tornou-se uma alternativa competitiva aos métodos analíticos tradicionais, oferecendo uma análise rápida, não destrutiva, mais económica e sustentável, aplicável tanto a sistemas simples como a sistemas moleculares mais complexos. O objetivo desta tese foi avaliar a viabilidade da utilização de aparelhos de RMN de bancada para monitorizar reações químicas em fluxo contínuo, num laboratório farmacêutico de I&D. Assim, para avaliar a resposta deste tipo de equipamentos para os problemas presentes na produção de fármacos e num ambiente laboratorial, foi feito um estudo da sensibilidade e da capacidade do instrumento, analisando parâmetros de reprodutibilidade e de validação (limite de deteção (LOD) e de quantificação (LOQ)). Posteriormente, usámos modelos de reações como prova de conceito para verificar a sua aplicação na monitorização online de reações. Estes estudos permitiram-nos concluir que os aparelhos de RMN de bancada podem ser uma mais-valia no estudo de reações em fluxo, obtendo informação quantitativa em tempo real, permitindo determinar a concentração de reagentes/produtos ao longo do tempo da reação de um modo rápido e com mínimo de manipulação. Os resultados permitiram construir um protocolo geral para o utilizador decidir se perante uma reação específica se este tipo de equipamento pode ser usado uma reação especifica e, em caso afirmativo, quais são as condições experimentais que devem ser abordadas durante a monitorização. A técnica de espectroscopia de RMN de bancada apresenta um enorme potencial de se tornar, no futuro, uma ferramenta comum e acessível para a monitorização de reações, tanto em ambiente industrial como em ambiente académico.