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Thematische Bibliographien / Nuclear reaction codes / Dissertationen

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Dissertationen zum Thema „Nuclear reaction codes“

Autor: Grafiati

Veröffentlicht am 23. Juni 2021

Zuletzt aktualisiert am 29. Juli 2025

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1

MAI, LUIZ A. "Sistema de obtencao de um pre-projeto otimizado de um nucleo de um reator nuclear." reponame:Repositório Institucional do IPEN, 1988. http://repositorio.ipen.br:8080/xmlui/handle/123456789/9914.

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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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CARVALHO, LUIZ S. "Frequencia de danos no nucleo por blecaute em reator nuclear de concepcao avancada." reponame:Repositório Institucional do IPEN, 2004. http://repositorio.ipen.br:8080/xmlui/handle/123456789/11147.

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4

Laufer, Michael Robert. "Granular Dynamics in Pebble Bed Reactor Cores." Thesis, University of California, Berkeley, 2013. http://pqdtopen.proquest.com/#viewpdf?dispub=3593891.

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<p> This study focused on developing a better understanding of granular dynamics in pebble bed reactor cores through experimental work and computer simulations. The work completed includes analysis of pebble motion data from three scaled experiments based on the annular core of the Pebble Bed Fluoride Salt-Cooled High- Temperature Reactor (PB-FHR). The experiments are accompanied by the development of a new discrete element simulation code, GRECO, which is designed to offer a simple user interface and simplified two-dimensional system that can be used for iterative purposes in the preliminary

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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.

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A significant proportion of the UK energy needs are currently serviced by a fleet of ageing nuclear reactors. Ensuring that these reactors are operated safely is the highest priority and the structural health of their cores, that provide channels for control rods and coolant gas, is a key aspect. This thesis focuses on the application of structuralhealth monitoring to the graphite reactor cores used in the UK and presents a specification for the use of structural health monitoring (SHM) techniques already es- tablished in bridge and aircraft monitoring, with data obtained through existing reac

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Shuffler, Carter Alexander. "Optimization of hydride fueled pressurized water reactor cores." Thesis, Massachusetts Institute of Technology, 2004. http://hdl.handle.net/1721.1/33634.

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Thesis (S.M.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 2004.<br>Includes bibliographical references (leaf 173).<br>This thesis contributes to the Hydride Fuels Project, a collaborative effort between UC Berkeley and MIT aimed at investigating the potential benefits of hydride fuel use in light water reactors (LWRs). This pursuit involves implementing an appropriate methodology for design and optimization of hydride and oxide fueled cores. Core design is accomplished for a range of geometries via steady-state and transient thermal hydraulic analyses, which yield the

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Trant, Jarrod Michael. "Transient analysis of hydride fueled pressurized water reactor cores." Thesis, Massachusetts Institute of Technology, 2004. http://hdl.handle.net/1721.1/33632.

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Thesis (S.M.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 2004.<br>Includes bibliographical references (leaves 132-133).<br>This thesis contributes to the hydride nuclear fuel project led by U. C. Berkeley for which MIT is to perform the thermal hydraulic and economic analyses. A parametric study has been performed to determine the optimum combination of lattice pitch, rod diameter, and channel shape-further referred to as geometry-for maximizing power given specific transient conditions for pressurized water reactors (PWR) loaded with either U02 or UZrH1.6 fuel. Seve

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Alam, Syed Bahauddin. "The design of reactor cores for civil nuclear marine propulsion." Thesis, University of Cambridge, 2018. https://www.repository.cam.ac.uk/handle/1810/275650.

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Perhaps surprisingly, the largest experience in operating nuclear power plants has been in nuclear naval propulsion, particularly submarines. This accumulated experience may become the basis of a proposed new generation of compact nuclear power plant designs. In an effort to de-carbonise commercial freight shipping, there is growing interest in the possibility of using nuclear propulsion systems. Reactor cores for such an application would need to be fundamentally different from land-based power generation systems, which require regular refueling, and from reactors used in military submarines,

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PINTO, LETICIA N. "Experimentos de efeitos de reatividade no reator nuclear IPEN/MB-01." reponame:Repositório Institucional do IPEN, 2012. http://repositorio.ipen.br:8080/xmlui/handle/123456789/10099.

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SANTOS, DIOGO F. dos. "Caracterização dos campos neutrônicos obtidos por meio de armadilhas de nêutrons a partir da utilização de água pesada (D2O) no interior do núcleo do reator nuclear IPEN/MB-01." reponame:Repositório Institucional do IPEN, 2015. http://repositorio.ipen.br:8080/xmlui/handle/123456789/23825.

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Wallace, 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.

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Nuclear power stations worldwide are exceeding their originally specified design lives and with only limited construction of new generation underway, there is a desire to continue the operation of existing stations to ensure electricity supply. Continued operation of nuclear power stations with degrading and life-limiting components necessitates increased monitoring and inspection, particularly of the reactor cores, to ensure they are safe to operate. The monitoring of a large number of components and their related data sources is a distributed and time consuming process for the engineer given

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Inzerillo, 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.

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As the Advanced Gas-cooled Reactor (AGR) nuclear power stations are ageing, the nuclear core composed by graphite bricks can distort. The direct measurement of the core condition is costly and time-consuming, hence, alternative methods have been developed to provide the necessary information about the core condition. This thesis presents a model-based technique for condition monitoring of AGRs cores using measurements obtained during routine core refuelling process. It has been demonstrated that Fuel Grab Load Trace (FGLT) data gathered during refuelling operations provides, through the magnit

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Redd, Evan M. "X-10 reactor forensic analysis and evaluation using a suite of neutron transport codes." Thesis, Georgia Institute of Technology, 2015. http://hdl.handle.net/1853/53978.

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X-10, the genesis production reactor for the U.S. paved the way for all weapons material production. This feat offers a unique fundamental opportunity of nuclear forensic analysis and popular neutron code package evaluation. Production reactor nuclear forensic signatures and characteristics are emphasized throughout this work. These underlying production characteristics are reported and analyzed for potential in-core zone provenance and axial slug location coupled with how the nuclear data uncertainties affect these conclusions. Material attribution with respect to commercial versus military r

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Gong, Helin. "Data assimilation with reduced basis and noisy measurement : Applications to nuclear reactor cores." Thesis, Sorbonne université, 2018. http://www.theses.fr/2018SORUS189.

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Le but de la thèse est d'améliorer l'interprétation physique et numérique de l'information impliquée dans l'assimilation de données avec des stratégies de réduction de modèles modernes et efficaces pour les systèmes gouvernés par des EDPs. Plus précisément, l'accent mis sur la tâche d'assimilation des données est lié à l'estimation de l'état pour les problèmes stationnaires, en particulier l'estimation de l'état neutronique dans les applications aux réacteurs nucléaires. Dans la première partie de la thèse, nous analysons et adaptons les approches GEIM (Generalized Empirical Interpolation Meth

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Faure, Bastien. "Development of neutronic calculation schemes for heterogeneous sodium-cooled nuclear cores in the Apollo3 code : application to the ASTRID prototype." Thesis, Aix-Marseille, 2019. http://www.theses.fr/2019AIXM0289.

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Les réacteurs nucléaires refroidis au sodium offrent des perspectives intéressantes pour la filière nucléaire (utilisation optimale de l'uranium naturel, réduction de la radiotoxicité des déchets nucléaires). Cependant, la nécessité d’élever le niveau de sûreté de ces réacteurs aux standards du XXIe siècle a conduit à des designs de cœurs très hétérogènes.Ainsi, les objectifs de la thèse sont l’identification des principaux phénomènes physiques devant être pris en compte lors du calcul neutronique de cœurs hétérogènes en spectre rapide, ainsi que le développement de schémas de calcul adaptés d

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Schramm, Marcelo. "An algorithm for multi-group two-dimensional neutron diffusion kinetics in nuclear reactor cores." reponame:Biblioteca Digital de Teses e Dissertações da UFRGS, 2016. http://hdl.handle.net/10183/142510.

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O objetivo desta tese é introduzir uma nova metodologia para a cinética bidimensional multi- grupo de difusão de nêutrons em reatores nucleares. A metodologia apresentada usa uma aproximação polinomial em um domínio homogêneo retangular com condições de contornos não homogêneas. Como ela consiste em uma série de Taylor truncada, sua estimativa de erro varia de acordo com o tamanho do retângulo. Os coeficientes são obtidos principalmente pelas suas relações com o termo independente, que _e determinado pela equação diferencial. Estas relações são obtidas apenas pelas condições de contorno, e é d

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Frieß, Friederike Renate [Verfasser], Wolfgang [Akademischer Betreuer] Liebert, and Barbara [Akademischer Betreuer] Drossel. "Neutron-Physical Simulation of Fast Nuclear Reactor Cores / Friederike Renate Frieß ; Wolfgang Liebert, Barbara Drossel." Darmstadt : Universitäts- und Landesbibliothek Darmstadt, 2017. http://d-nb.info/1138212237/34.

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MURA, LUIZ E. C. "Caracterização dos campos neutrônicos obtidos por meio de armadilhas de nêutrons no interior do núcleo do reator nuclear IPEN/MB-01." reponame:Repositório Institucional do IPEN, 2011. http://repositorio.ipen.br:8080/xmlui/handle/123456789/9999.

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SILVEIRA, RENATO C. da. "Avaliacao da estabilidade estrutural de contencoes metalicas de centrais nucleares." reponame:Repositório Institucional do IPEN, 2000. http://repositorio.ipen.br:8080/xmlui/handle/123456789/10795.

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Helvenston, Edward M. (Edward March). "Analysis of in-core experiment activities for the MIT Research Reactor using the ORIGEN computer code." Thesis, Massachusetts Institute of Technology, 2006. http://hdl.handle.net/1721.1/41591.

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Thesis (S.B.)--Massachusetts Institute of Technology, Dept. of Nuclear Science and Engineering, 2006.<br>Includes bibliographical references (leaves 73-74).<br>The objective of this study is to devise a method for utilizing the ORIGEN-S computer code to calculate the activation products generated in in-core experimental assemblies at the MIT Research Reactor (MITR-II). ORIGEN-S is a nuclear depletion and decay analysis code. It accounts for all types of nuclear reactions and eliminates the need for selection of the dominant reactions that will occur in a given experiment, as must be done with

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Negm, Hani Hussein. "Studies on the Optimum Geometry for a Nuclear Resonance Fluorescence Detection System for Nuclear Security Applications." Kyoto University, 2014. http://hdl.handle.net/2433/193589.

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OLIVEIRA, JOSE R. de. "Programa computacional para estudo da estrategia de controle de um reator nuclear do tipo PWR." reponame:Repositório Institucional do IPEN, 2002. http://repositorio.ipen.br:8080/xmlui/handle/123456789/11060.

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Wang, Yunzhi (Yunzhi Diana). "Evaluation of the thermal-hydraulic operating limits of the HEU-LEU transition cores for the MIT Research Reactor." Thesis, Massachusetts Institute of Technology, 2009. http://hdl.handle.net/1721.1/54479.

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Thesis (S.M. and S.B.)--Massachusetts Institute of Technology, Dept. of Nuclear Science and Engineering, 2009.<br>Cataloged from PDF version of thesis.<br>Includes bibliographical references (p. 93-94).<br>The MIT Research Reactor (MITR) is in the process of conducting a design study to convert from High Enrichment Uranium (HEU) fuel to Low Enrichment Uranium (LEU) fuel. The currently selected LEU fuel design contains 18 plates per element, compared to the existing HEU design of 15 plates per element. A transitional conversion strategy, which consists of replacing three HEU elements with fresh

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STEFANI, GIOVANNI L. de. "Sobre a técnica de Rod Drop em medidas de reatividade integral em bancos de controle e segurança de reatores nucleares." reponame:Repositório Institucional do IPEN, 2013. http://repositorio.ipen.br:8080/xmlui/handle/123456789/10210.

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Hamzeh, Bahmani Hamed. "Development of novel techniques for the assessment of inter-laminar resistance in transformer and reactor cores." Thesis, Cardiff University, 2014. http://orca.cf.ac.uk/69860/.

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The main aim of this project is to investigate the influence of the inter-laminar short circuit faults on the performance of magnetic cores and develop a non-destructive method to detect these kinds of defects. The eddy current path in magnetic laminations which is magnetised by time varying magnetic field was modelled by an equivalent resistor network to calculate and predict the eddy current power losses in magnetic laminations. The model was validated over a wide range of magnetisation conditions. Based on the developed model, the influence of a wide range of magnetising frequency and peak

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BAPTISTA, FILHO BENEDITO D. "Redes neurais para controle de sistemas de reatores nucleares." reponame:Repositório Institucional do IPEN, 1998. http://repositorio.ipen.br:8080/xmlui/handle/123456789/10723.

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D'AMICO, Salvatore. "Integral approach to the safety design of the EU-DEMO Helium-Cooled Pebble Beds with reference to the associated relevant systems." Doctoral thesis, Università degli Studi di Palermo, 2020. http://hdl.handle.net/10447/395442.

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BRAGA, CLAUDIA C. "Analise de sensibilidade para modelagem semi-mecanistica de acidentes severos." reponame:Repositório Institucional do IPEN, 1994. http://repositorio.ipen.br:8080/xmlui/handle/123456789/10399.

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MUNIZ, RAFAEL O. R. "Análise neutrônica e especificação técnica para o combustível a dispersão UMo-Al com adição de veneno queimável." reponame:Repositório Institucional do IPEN, 2015. http://repositorio.ipen.br:8080/xmlui/handle/123456789/25671.

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CARNEIRO, ALVARO L. G. "Medida de distribuicao da densidade de potencia relativa do nucleo do reator IPEN/MB-01...vareta combustivel." reponame:Repositório Institucional do IPEN, 1996. http://repositorio.ipen.br:8080/xmlui/handle/123456789/10669.

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Rolfo, Stefano. "LES and Hybrid RANS/LES turbulence modelling in unstructured finite volume code and applications to nuclear reactor fuel bundle." Thesis, University of Manchester, 2010. https://www.research.manchester.ac.uk/portal/en/theses/les-and-hybrid-ransles-turbulence-modelling-in-unstructured-finite-volume-code-and-applications-to-nuclear-reactor-fuel-bundle(14e99c49-c1f5-442d-926e-2324a9701690).html.

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Rod bundle is a typical constitutive element of a very wide range of nuclear reactor designs. This thesis describes the investigation of such geometry with wall-resolved Large Eddy Simulation (LES). In order to alleviate the mesh constraint, imposed by the near wall resolution, the usage of embedded refinements and polyhedral meshes is analysed firstly with a inviscid laminar case (Taylor Green vortices) and secondly with a fully turbulent case (channel flow only with embedded refinement). The inviscid test case shows that the addition of embedded refinements decreases the conservation propert

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DOMINGOS, DOUGLAS B. "Calculos neutronicos, termo-hidrulicos e de seguranca de um dispositivo para irradiacao de miniplacas (DIM) de elementos combustiveis tipo dispersao." reponame:Repositório Institucional do IPEN, 2010. http://repositorio.ipen.br:8080/xmlui/handle/123456789/9510.

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Connolly, Kevin John. "A coarse mesh radiation transport method for reactor analysis in three dimensional hexagonal geometry." Diss., Georgia Institute of Technology, 2012. http://hdl.handle.net/1853/50149.

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A new whole-core transport method is described for 3-D hexagonal geometry. This is an extension of a stochastic-deterministic hybrid method which has previously been shown highly accurate and efficient for eigenvalue problems. Via Monte Carlo, it determines the solution to the transport equation in sub-regions of reactor cores, such as individual fuel elements or sections thereof, and uses those solutions to compose a library of response expansion coefficients. The information acquired allows the deterministic solution procedure to arrive at the whole core solution for the eigenvalue and the e

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CARLUCCIO, THIAGO. "Implementação e qualificação de metodologia de cálculos neutrônicos em reatores subcríticos acionados por fonte externa de nêutrons e aplicações." reponame:Repositório Institucional do IPEN, 2011. http://repositorio.ipen.br:8080/xmlui/handle/123456789/10033.

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Vaidya, Udyanth. "Uncertainty & Sensitivity Analysis of Nuclear Fuel Using Transuranus & Dakota." Thesis, KTH, Fysik, 2021. http://urn.kb.se/resolve?urn=urn:nbn:se:kth:diva-302565.

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With the initiative taken by the SUNRISE project (Sustainable Nuclear Energy Research in Sweden) to construct a Lead-cooled research reactor, this thesis intends to extend the knowledge within nuclear fuel development. By using integral iterative modelling and simulating techniques that mimic real-world phenomena, novel fuel materials like uranium nitride are assessed for future validation. The work deals with the fuel performance analysis of the SUNRISE LFR, employing the TRANSURANUS fuel performance code. This code contains a collection of model parameters that simulate the thermo-mechanica

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REIS, REGIS. "Análise do comportamento sob irradiação do combustível nuclear a altas queimas com os programas computacionais FRAPCON e FRAPTRAN." reponame:Repositório Institucional do IPEN, 2014. http://repositorio.ipen.br:8080/xmlui/handle/123456789/11797.

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ROSSI, LUBIANKA F. R. "Acoplamento entre os métodos diferencial e da teoria da perturbação para o cálculo dos coeficientes de sensibilidade em problemas de transmutação nuclear." reponame:Repositório Institucional do IPEN, 2014. http://repositorio.ipen.br:8080/xmlui/handle/123456789/23594.

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Leduc, Christian. "Modélisation de la condensation en film sur les parois d'une enceinte de réacteurs." Université Joseph Fourier (Grenoble ; 1971-2015), 1995. http://www.theses.fr/1995GRE10157.

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Un code enceinte, utilise dans les analyses de surete des centrales nucleaires, doit pouvoir predire les evolutions de la pression et des concentrations en vapeur, air et hydrogene dans l'enceinte de confinement d'un reacteur a eau pressurisee en situation accidentelle. La condensation de la vapeur sur les parois froides est un facteur essentiel de ces evolutions. Nous proposons un modele de condensation en film en presence de gaz incondensables. L'ecoulement du film est considere laminaire. Trois approches differentes sont abordees pour modeliser les transferts dans les couches limites: utili

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MURA, LUIS F. L. "Determinação experimental de taxas de reação no 238U e 235U ao longo do raio da pastilha de UO2 do reator IPEN/MB-01." reponame:Repositório Institucional do IPEN, 2015. http://repositorio.ipen.br:8080/xmlui/handle/123456789/25670.

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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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NUNES, BEATRIZ G. "Determinação exerimental de razões espectrais e do espectro de energia dos nêutrons no combustível do reator nuclear IPEN/MB-01." reponame:Repositório Institucional do IPEN, 2012. http://repositorio.ipen.br:8080/xmlui/handle/123456789/10069.

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PERROTTA, JOSE A. "Proposta de um nucleo de reator PWR avancado com caracteristicas adequadas para o conceito de seguranca passiva." reponame:Repositório Institucional do IPEN, 1999. http://repositorio.ipen.br:8080/xmlui/handle/123456789/10704.

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SILVESTRE, LARISSA J. B. "PCRELAP5 - Programa de cálculo para os dados de entrada do código RELAP5." reponame:Repositório Institucional do IPEN, 2016. http://repositorio.ipen.br:8080/xmlui/handle/123456789/26393.

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Trinh, Ngoc Duy. "Emission de neutrons par les réactions d'ions lourds (4,6-95 MeV/nucléon)." Thesis, Normandie, 2018. http://www.theses.fr/2018NORMC234/document.

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Les accélérateurs d’ions lourds sont un outil incontournable pour la recherche en physique nucléaire. Ils sont également utilisés pour diverses applications. Il est nécessaire de caractériser la production des neutrons secondaires dans les accélérateurs afin de garantir un fonctionnement sûr en toutes circonstances. Cependant, les données expérimentales sont très rares voire inexistantes. Pour certaines données, on note des divergences entre différentes publications. Des désaccords sont aussi observés entre les mesures et les calculs. Toutes ces raisons justifient le programme Thick Target Neu

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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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ALBUQUERQUE, LEVI B. de. "Categorizacao de tensoes em modelos de elementos finitos de conexoes bocal-vaso de pressao." reponame:Repositório Institucional do IPEN, 1999. http://repositorio.ipen.br:8080/xmlui/handle/123456789/10761.

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CRUZ, JULIO R. B. "Procedimento analitico para previsao do comportamento estrutural de componentes truncados." reponame:Repositório Institucional do IPEN, 1998. http://repositorio.ipen.br:8080/xmlui/handle/123456789/10665.

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HIRATA, DANIEL M. "Estimativa da frequencia de danos ao nucleo devido a perda de refrigerante primario e bloqueio de canal de refrigeracao do reator de pesquisas IEA-R1 do IPEN-CNEN/SP - APS nivel 1." reponame:Repositório Institucional do IPEN, 2009. http://repositorio.ipen.br:8080/xmlui/handle/123456789/9483.

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Gerardin, Delphine. "Développement de méthodes et d’outils numériques pour l’étude de la sûreté du réacteur à sels fondus MSFR." Thesis, Université Grenoble Alpes (ComUE), 2018. http://www.theses.fr/2018GREAI068/document.

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Les travaux réalisés pendant cette thèse portent sur l’étude de la sûreté du Molten Salt Fast Reactor (MSFR) et incluent à la fois des méthodes d’analyse de risques et des calculs déterministes de sûreté et de design. Ce travail s’inscrit dans le cadre du projet européen SAMOFAR.Le MSFR est un réacteur régénérateur à spectre neutronique rapide qui fonctionne en cycle thorium dans sa configuration de référence, établie en début du projet SAMOFAR. Il a été sélectionné par le Forum International Génération IV pour son potentiel prometteur. Comme tout réacteur nucléaire de quatrième génération, il

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CASTRO, ALFREDO J. A. de. "Análise experimental de velocidade crítica em elemento combustível tipo placa plana para reatores nucleares de pesquisa." reponame:Repositório Institucional do IPEN, 2017. http://repositorio.ipen.br:8080/xmlui/handle/123456789/28022.

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Submitted by Pedro Silva Filho (pfsilva@ipen.br) on 2017-11-17T17:27:31Z No. of bitstreams: 0<br>Made available in DSpace on 2017-11-17T17:27:31Z (GMT). No. of bitstreams: 0<br>Conselho Nacional de Desenvolvimento Científico e Tecnológico (CNPq)<br>Os elementos de combustível de um reator nuclear de pesquisa tipo MTR (\"Material Testing Reactor\") são, em sua grande maioria, formados por placas de combustível revestidas com alumínio contendo no cerne silicileto de urânio (U3Si2) disperso em matriz de alumínio. Essas placas possuem espessura da ordem de milímetros e comprimentos muito maiores

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