Log in

Relevant bibliographies by topics / Reactores de fisión nuclear / Dissertations / Theses

To see the other types of publications on this topic, follow the link: Reactores de fisión nuclear.

Dissertations / Theses on the topic 'Reactores de fisión nuclear'

Author: Grafiati

Published: 4 June 2021

Last updated: 1 February 2022

Create a spot-on reference in APA, MLA, Chicago, Harvard, and other styles

Select a source type:

Consult the top 50 dissertations / theses for your research on the topic 'Reactores de fisión nuclear.'

Next to every source in the list of references, there is an 'Add to bibliography' button. Press on it, and we will generate automatically the bibliographic reference to the chosen work in the citation style you need: APA, MLA, Harvard, Chicago, Vancouver, etc.

You can also download the full text of the academic publication as pdf and read online its abstract whenever available in the metadata.

Browse dissertations / theses on a wide variety of disciplines and organise your bibliography correctly.

1

García, Fajardo Laura. "DISEÑO CONCEPTUAL DE UN SISTEMA CONTROLADO POR UN ACELERADOR PARA TRANSMUTACIÓN DE RESIDUOS NUCLEARES Y APLICACIONES ENERGÉTICAS." Doctoral thesis, Universitat Politècnica de València, 2012. http://hdl.handle.net/10251/17654.

Full text

Abstract:

Las posibilidades de desarrollo de la energía nuclear aumentan considerablemente con el incremento de la demanda energética mundial. Sin embargo, el manejo de los residuos provenientes del combustible nuclear gastado de las plantas nucleares convencionales es actualmente uno de los principales problemas que enfrenta el uso de esta fuente de energía. El objetivo del presente trabajo consistió en realizar el diseño conceptual del TADSEA (Transmutation Advanced Device for Sustainable Energy Applications): un sistema controlado por un acelerador (ADS), de tipo lecho de bolas, refrigerado por helio

APA, Harvard, Vancouver, ISO, and other styles

2

Sánchez, Velasco Francisco Javier. "Experimental characterization of aerosol retention in the break stage of a dry steam generator in SGTR sequences." Doctoral thesis, Universitat Politècnica de València, 2008. http://hdl.handle.net/10251/3839.

Full text

Abstract:

En reactores de agua a presión, las secuencias de accidente severo con rotura de tubos del generador de vapor (conocidas por sus siglas en inglés SGTR, Steam Generator Tube Rupture) son dominantes del riesgo, a pesar de ser sucesos de muy baja probabilidad. Su importancia reside en la potencial liberación de radiactividad, en forma de aerosol, que supondrían desde el circuito primario al medio ambiente, sin intervención de la contención. Sin embargo, las partículas radioactivas podrían retenerse parcialmente en el secundario del generador de vapor aun cuando no quedara agua en el mismo. La aus

APA, Harvard, Vancouver, ISO, and other styles

3

Kingdon, David Ross. "Safety characteristics of a suspended-pellet fission reactor system." Thesis, National Library of Canada = Bibliothèque nationale du Canada, 1998. http://www.collectionscanada.ca/obj/s4/f2/dsk1/tape11/PQDD_0001/NQ42856.pdf.

Full text

APA, Harvard, Vancouver, ISO, and other styles

4

Stewart, Christopher L. "Investigation of fuel cycle for a sub-critical fusion-fission hybrid breeder reactor." Thesis, Georgia Institute of Technology, 2013. http://hdl.handle.net/1853/50407.

Full text

Abstract:

The SABR fusion-fission hybrid concept for a fast burner reactor, which combines the IFR-PRISM fast reactor technology and the ITER tokamak physics and fusion technology, is adapted for a fusion-fission hybrid reactor, designated SABrR. SABrR is a sodium-cooled 3000 MWth reactor fueled with U-Pu-10Zr. For the chosen fuel and core geometry, two configurations of neutron reflector and tritium breeding structures are investigated: one which emphasizes a high tritium production rate and the other which emphasizes a high fissile production rate. Neutronics calculations are performed using the ER

APA, Harvard, Vancouver, ISO, and other styles

5

Martin, Jerry Lynn. "DABLE--a facility for measuring fission product transport in gas-cooled reactors." Thesis, Massachusetts Institute of Technology, 1991. http://hdl.handle.net/1721.1/13906.

Full text

APA, Harvard, Vancouver, ISO, and other styles

6

Sweeney, David J. "Reactor power history from fission product signatures." Thesis, [College Station, Tex. : Texas A&M University, 2008. http://hdl.handle.net/1969.1/ETD-TAMU-3209.

Full text

APA, Harvard, Vancouver, ISO, and other styles

7

Presby, Andrew L. "Thermophotovoltaic energy conversion in space nuclear reactor power systems." Thesis, Monterey, Calif. : Naval Postgraduate School, 2004. http://edocs.nps.edu/npspubs/scholarly/theses/2004/Dec/04Dec%5FPresby.pdf.

Full text

Abstract:

Thesis (Astronautical Engineer and M. S. in Astronautical Engineering)--Naval Postgraduate School, December 2004.<br>Thesis Advisor(s): Gopinath, Ashok ; Michael, Sherif. "December 2004." Description based on title screen as viewed on March 13, 2009. Includes bibliographical references (p. 123-127). Also available in print.

APA, Harvard, Vancouver, ISO, and other styles

8

Mauer, Andrew N. "A superconducting fusion transmutation of waste reactor." Thesis, Georgia Institute of Technology, 2002. http://hdl.handle.net/1853/15970.

Full text

APA, Harvard, Vancouver, ISO, and other styles

9

Sommer, Christopher Michael. "Subcritical transmutation of spent nuclear fuel." Diss., Georgia Institute of Technology, 2011. http://hdl.handle.net/1853/41205.

Full text

Abstract:

A series of fuel cycle simulations were performed using CEA's reactor physics code ERANOS 2.0 to analyze the transmutation performance of the Subcritical Advanced Burner Reactor (SABR). SABR is a fusion-fission hybrid reactor that combines the leading sodium cooled fast reactor technology with the leading tokamak plasma technology based on ITER physics. Two general fuel cycles were considered for the SABR system. The first fuel cycle is one in which all of the transuranics from light water reactors are burned in SABR. The second fuel cycle is a minor actinide burning fuel cycle in which al

APA, Harvard, Vancouver, ISO, and other styles

10

Taylor, Neil Rutger. "Analysis of a High Temperature Fission Chamber Experiment for Next Generation Reactors." The Ohio State University, 2017. http://rave.ohiolink.edu/etdc/view?acc_num=osu1512048679402356.

Full text

APA, Harvard, Vancouver, ISO, and other styles

11

Dawson, Huw. "Friction stir welding of ODS steels for future generation nuclear reactors." Thesis, University of Manchester, 2018. https://www.research.manchester.ac.uk/portal/en/theses/friction-stir-welding-of-ods-steels-for-future-generation-nuclear-reactors(2603016f-6763-43d1-98ef-753e110b8791).html.

Full text

Abstract:

In this project, we have successfully joined MA956 Oxide Dispersion-Strengthened (ODS) steel plates using Friction Stir Welding (FSW). ODS steels are prime candidate materials for the fuel cladding in Generation IV nuclear fission reactors and as first wall components in nuclear fusion reactors. This is due to their exhibiting excellent high temperature strength and creep behaviour, together with enhanced resistance to radiationinduced void swelling. ODS steels are heavily reliant on a fine dispersion of (Y-Al-O) nanooxide particles to provide the aforementioned properties. This, however, make

APA, Harvard, Vancouver, ISO, and other styles

12

Di, Giuli Mirco <1976&gt. "Severe Accident Simulation of Small Modular Reactors." Doctoral thesis, Alma Mater Studiorum - Università di Bologna, 2015. http://amsdottorato.unibo.it/7079/.

Full text

Abstract:

Since the Three Mile Island Unit 2 (TMI-2), accident in 1979 which led to the meltdown of about one half of the reactor core and to limited releases of radioactive materials to the environment, an important international effort has been made on severe accident research. The present work aims to investigate the behaviour of a Small Modular Reactor during severe accident conditions. In order to perform these analyses, a SMR has been studied for the European reference severe accident analysis code ASTEC, developed by IRSN and GRS. In the thesis will be described in detail the IRIS Small Modular

APA, Harvard, Vancouver, ISO, and other styles

13

Reed, Mark Wilbert. "A fission-fusion hybrid reactor in steady-state L-mode tokamak configuration with natural uranium." Thesis, Massachusetts Institute of Technology, 2011. http://hdl.handle.net/1721.1/76535.

Full text

Abstract:

Thesis (S.M.)--Massachusetts Institute of Technology, Dept. of Nuclear Science and Engineering, 2011.<br>Cataloged from PDF version of thesis.<br>Includes bibliographical references (p. 215-218).<br>The most prevalent criticism of fission-fusion hybrids is simply that they are too exotic - that they would exacerbate the challenges of both fission and fusion. This is not really true. Intriguingly, hybrids could actually be more viable than stand-alone fusion reactors while mitigating many challenges of fission. This work develops a conceptual design for a fission-fusion hybrid reactor in steady

APA, Harvard, Vancouver, ISO, and other styles

14

Rosselli, Ruggero. "Sensitivity-uncertainty analyses on ZED-2 reactor criticality calculations with ENDF/B-VII.1 and recently measured 155,157Gd(n,γ) cross sections at n_TOF - CERN". Bachelor's thesis, Alma Mater Studiorum - Università di Bologna, 2021. http://amslaurea.unibo.it/22857/.

Full text

Abstract:

I veleni bruciabili sono una categoria di isotopi impiegata come dispositivo di sicurezza nei moderni reattori nucleari. Gli isotopi dispari del gadolinio 155Gd e 157Gd sono potenti veleni bruciabili, largamente impiegati in reattori di potenza di seconda e terza generazione. Le sezioni d'urto degli isotopi 155,157Gd sono state misurate più volte in passato, ma sembra esserci ulteriore margine di miglioramento. Inoltre, una conoscenza precisa delle sezioni d'urto dei due isotopi è richiesta per ragioni di sicurezza. Nel 2016, in risposta alla necessità di dati migliori, le sezioni d'urto di 15

APA, Harvard, Vancouver, ISO, and other styles

15

Xue, Sha. "Modeling and experiment of fission products release and interaction with coolant for defective fuel in Light Water Reactor(LWR)." The Ohio State University, 2017. http://rave.ohiolink.edu/etdc/view?acc_num=osu1492734885411167.

Full text

APA, Harvard, Vancouver, ISO, and other styles

16

Rossi, Fabiana <1982&gt. "Safety, Security And safeguards In GEN IV sodium fast reactors." Doctoral thesis, Alma Mater Studiorum - Università di Bologna, 2015. http://amsdottorato.unibo.it/6836/.

Full text

Abstract:

This work presents first a study of the national and international laws in the fields of safety, security and safeguards. The international treaties and the recommendations issued by the IAEA as well as the national regulations in force in France, the United States and Italy are analyzed. As a result of this, a comparison among them is presented. Given the interest of the Japan Atomic Energy Agency for the aspects of criminal penalties and monetary, also the Japanese case is analyzed. The main part of this work was held at the JAEA in the field of proliferation resistance (PR) and physical pr

APA, Harvard, Vancouver, ISO, and other styles

17

Skwarcan-Bidakowski, Alexander. "Nuclear reactor core model for the advancednuclear fuel cycle simulator FANCSEE. Advanceduse of Monte Carlo methods in nuclear reactorcalculations." Thesis, Institutionen för Reaktorfysik, 2017. http://urn.kb.se/resolve?urn=urn:nbn:se:uu:diva-324260.

Full text

Abstract:

A detailed reactor core modeling of the LOVIISA-2 PWR and FORSMARK-3BWR was performed in the Serpent 2 Continuous Energy Monte-Carlocode.Both models of the reactors were completed but the approximations ofthe atomic densities of nuclides present in the core differedsignificantly.In the LOVIISA-2 PWR, the predicted atomic density for the nuclidesapproximated by Chebyshev Rational Approximation method (CRAM)coincided with the corrected atomic density simulated by the Serpent2 program. In the case of FORSMARK-3 BWR, the atomic density fromCRAM poorly approximated the data returned by the simulati

APA, Harvard, Vancouver, ISO, and other styles

18

Ginestar, Peiro Damián. "Integración de la ecuación de la difusión neutrónica en geometrías multidimensionales. Aplicación a reactores nucleares. Cálculo de los Modos Lambda." Doctoral thesis, Universitat Politècnica de València, 2009. http://hdl.handle.net/10251/4268.

Full text

Abstract:

LA TESIS ESTA DEDICADA AL DESARROLLO DE METODOS PARA EL TRATAMIENTO DE DOS PROBLEMAS BASICOS DE LA FISICA DE REACTORES ENUCLEARES, EL CALCULO DE LOS MODOS LAMBDA ASOCIADOS A UNA CONFIGURACION ESTATICA DEL REACTOR NUCLEAR, Y LA INTEGRACION DE LA ECUACION DE LA DIFUSION NEUTRONICA DEPENDIENTE DEL TIEMPO. LA MEMORIA SE ESTRUCTURA EN SEIS CAPITULOS. EN EL PRIMERO SE INTRODUCEN LOS DOS PROBLEMAS A TRATAR. EN EL SEGUNDO, SE DESARROLLA UNA APROXIMACION ANALITICA PARA LA OBTENCION DE LOS MODOS LAMBDA DE UN REACTOR UNIDIMENSIONAL, Y LA GENERALIZACION DE ESTA METODOLOGIA PARA EL TRATAMIENTO DE PROBLEMAS

APA, Harvard, Vancouver, ISO, and other styles

19

Wolniewicz, Peter. "Development of a Methodology for Detecting Coolant Void in Lead-cooled Fast Reactors by Means of Neutron Measurements." Doctoral thesis, Uppsala universitet, Tillämpad kärnfysik, 2014. http://urn.kb.se/resolve?urn=urn:nbn:se:uu:diva-232252.

Full text

Abstract:

In a lead-cooled fast reactor (LFR), small bubbles (in the order of one mm or less) may enter the coolant from a leaking steam generator. If such a leakage is undetected the small bubbles may eventually coalesce into a larger bubble in local stagnation zones under the active core. If such a bubble or void releases and passes through the core, it could drive the reactor into prompt criticality. It is therefore desirable to be able to detect the initial stages of such void formation. In this thesis, a methodology to detect such leaks is presented together with a study on void-induced reactivity

APA, Harvard, Vancouver, ISO, and other styles

20

Dickinson, Shirley. "Infrared spectroscopic and mass spectrometric studies of high-temperature molecules relevant to severe nuclear reactor accidents." Thesis, University of Southampton, 1990. http://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.255768.

Full text

APA, Harvard, Vancouver, ISO, and other styles

21

Mireles, Omar R. (Omar Roberto). "Non-Nuclear Materials Compatibility Testing of Niobium - 1% Zirconium and 316 Stainless Steel for Space Fission Reactor Applications." Thesis, Georgia Institute of Technology, 2004. http://hdl.handle.net/1853/5267.

Full text

Abstract:

A new generation of compact and highly efficient power production and propulsion technologies are critically needed in enabling NASAs long-term goals. Nuclear fission power technologies as part of project Prometheus are in development to meet this need. Proposed reactor concepts utilize a combination of refractory metals and stainless steels. One such refractory alloy, Niobium 1% Zirconium (Nb-1Zr), will be used because of its strength at high temperatures, neutron absorption properties, and resistance to corrosion by liquid alkali metals. One potential problem in using Nb-1Zr is that it u

APA, Harvard, Vancouver, ISO, and other styles

22

Sánchez, Hernández Ana María. "Aportación a los Cálculos Neutrónicos y Termohidráulicos en 3D con Códigos de Mejor EStimación. Aplicación a Transitorios en Reactores Nucleares BWR y PWR." Doctoral thesis, Universitat Politècnica de València, 2012. http://hdl.handle.net/10251/18195.

Full text

Abstract:

El uso de códigos es una herramienta fundamental en Seguridad Nuclear para la simulación de diferentes situaciones en reactores de potencia. En particular, los códigos termohidráulicos de estimación óptima nos permiten simular de forma más realista los fenómenos que suceden en una central nuclear con la representación del circuito primario. A su vez los códigos neutrónicos de dinámica del núcleo, nos permiten una definición y simulación más precisa del núcleo. El uso de los códigos acoplados permite la optimización de las propiedades de los códigos separados, ya que se produce la transferenc

APA, Harvard, Vancouver, ISO, and other styles

23

Quintana, González Pablo Antonio. "Aspectos Termohidráulicos de la Generación Termonuclear en Chile." Tesis, Universidad de Chile, 2009. http://www.repositorio.uchile.cl/handle/2250/103510.

Full text

Abstract:

Se estudian aspectos de la generación nucleoeléctrica, a fin de establecer algunos conceptos a considerar para la posible incorporación de potencia nuclear a la matriz energética chilena. Un aumento de un 6% anual de la demanda energética nacional, crecientes dificultades de suministro de gas natural e hidroelectricidad, así como una reducida incidencia de las energías alterativas, motivan el interés por considerar la inclusión de energía nuclear en nuestra matriz energética a mediano o largo plazo. Se enfatiza en este estudio el aspecto termohidráulico de la recuperación de la energía generad

APA, Harvard, Vancouver, ISO, and other styles

24

Console, Camprini Patrizio <1984&gt. "Power Transient Analysis of Experimental Devices for Jules Horowitz Material Testing Reactor (JHR)." Doctoral thesis, Alma Mater Studiorum - Università di Bologna, 2013. http://amsdottorato.unibo.it/5689/.

Full text

Abstract:

The objective of this thesis is the power transient analysis concerning experimental devices placed within the reflector of Jules Horowitz Reactor (JHR). Since JHR material testing facility is designed to achieve 100 MW core thermal power, a large reflector hosts fissile material samples that are irradiated up to total relevant power of 3 MW. MADISON devices are expected to attain 130 kW, conversely ADELINE nominal power is of some 60 kW. In addition, MOLFI test samples are envisaged to reach 360 kW for what concerns LEU configuration and up to 650 kW according to HEU frame. Safety issues

APA, Harvard, Vancouver, ISO, and other styles

25

Terranova, Nicholas <1986&gt. "Covariance Evaluation for Nuclear Data of Interest to the Reactivity Loss Estimation of the Jules Horowitz Material Testing Reactor." Doctoral thesis, Alma Mater Studiorum - Università di Bologna, 2016. http://amsdottorato.unibo.it/7550/.

Full text

Abstract:

In modern nuclear technology, integral reactor parameter uncertainty evaluation plays a crucial role for both economic and safety purposes. Target accuracies for operating and future nuclear facilities can be obtained only if the available simulation tools, such that computational platforms and nuclear data, are precise enough to produce reduced biases and uncertainties on target reactor parameters. The quality of any engineering parameter uncertainty quantification analysis strongly depends on the reliability related to the covariance information contained in evaluated libraries. To propaga

APA, Harvard, Vancouver, ISO, and other styles

26

Ohmes, Martin Francis. "Deployment of a three-dimensional array of micro-pocket fission detector triads (MPFD[superscript]3) for real-time, in-core neutron flux measurements in the Kansas State University TRIGA Mark-II Nuclear Reactor." Diss., Kansas State University, 2012. http://hdl.handle.net/2097/13672.

Full text

Abstract:

Doctor of Philosophy<br>Department of Mechanical and Nuclear Engineering<br>Douglas S. McGregor<br>A Micro-Pocket Fission Detector (MPFD) is a miniaturized type of fission chamber developed for use inside a nuclear reactor. Their unique design allows them to be located between or even inside fuel pins while being built from materials which give them an operational lifetime comparable to or exceeding the life of the fuel. While other types of neutron detectors have been made for use inside a nuclear reactor, the MPFD is the first neutron detector which can survive sustained use inside a nuclea

APA, Harvard, Vancouver, ISO, and other styles

27

Medina, Calderón Richard. "Desarrollo de software para cálculo neutrónico en el reactor RP-10." Bachelor's thesis, Universidad Nacional Mayor de San Marcos, 2004. https://hdl.handle.net/20.500.12672/3204.

Full text

Abstract:

Se presenta el desarrollo del Software WIMCIT; el cual ha sido producido tomando como base el CPC[16] (Código para Cálculo de Reactores), que realiza la simulación, automatiza las entradas numéricas y genera el modelamiento matemático en formato estándar, para el código de cálculo neutrónico CITATION [11] del reactor nuclear peruano RP-10 en 2 y 3 dimensiones para varios grupos de energía. Dicho código se encarga de hallar la solución numérica de la ecuación de transporte en su aproximación de difusión, mediante el método de diferencias finitas y muestra sus salidas para un análisis posterior

APA, Harvard, Vancouver, ISO, and other styles

28

Masin, Federico. "Verificación estructural de la obra civil del reactor nuclear RA-0." Bachelor's thesis, Universidad Nacional de Córdoba. Facultad de Ciencias Exactas, Físicas y Naturales, 2017. http://hdl.handle.net/11086/5890.

Full text

Abstract:

Práctica Supervisada (IC)--FCEFN-UNC, 2017<br>Trata de la verificación estructural de la obra civil del Reactor RA-0, realizando un análisis de los sistemas de protección, tanto el biológico como el estructural, que posee el Reactor Nuclear RA-0 para garantizar que ante eventos extremos de gran magnitud las instalaciones del mismo no colapsarán ni se dañarán

APA, Harvard, Vancouver, ISO, and other styles

29

Muñoz, San Martín Eduardo Israel. "Modelación de la Transferencia de Calor en las Varillas de Combustible del Reactor Nuclear PWR." Tesis, Universidad de Chile, 2011. http://www.repositorio.uchile.cl/handle/2250/104223.

Full text

APA, Harvard, Vancouver, ISO, and other styles

30

Manríquez, Alegría Edison Bastián. "Caracterización hidráulica del elemento combustible RECH-1 mediante simulación numérica CFD." Tesis, Universidad de Chile, 2016. http://repositorio.uchile.cl/handle/2250/143452.

Full text

Abstract:

Ingeniero Civil Mecánico<br>La Agencia Internacional de Energía Atómica (IAEA por sus siglas en inglés) promueve el uso seguro y pacífico de la Energía Nuclear. La agencia funciona de manera cooperativa entre todos los Estados que la integran. Y en Chile la responsable es la Comisión Chilena de Energía Nuclear (CCHEN). En el país hay dos reactores de investigación, uno de ellos es el RECH-1, este corresponde a un reactor de investigación con una potencia de 5[MWt], es moderado y refrigerado con agua liviana y su combustible corresponde al tipo MTR (Material Testing Reactor) placas planas. El

APA, Harvard, Vancouver, ISO, and other styles

31

Grieveson, Eleanor M. "Irradiation effects on the deformation of oxide dispersion strengthened steels." Thesis, University of Oxford, 2015. https://ora.ox.ac.uk/objects/uuid:6234be04-02f3-44bd-9b11-cc915b2ecbee.

Full text

Abstract:

This study concerns four high performance structural alloys designed to withstand the extreme temperature and irradiation environment inside fusion and fission fast breeder reactors: two Reduced Activation Ferritic Martensitic (RAFM) steels (Fe-14wt&percnt;Cr and a European standard alloy EUROFER97) and two equivalent Oxide Dispersion Strengthened (ODS) steels (Fe-14wt&percnt;Cr ODS (CEA ODS) and EUROFER ODS). Neutron irradiation of the samples was impractical due to timescale and specific handling requirements for radioactive samples. Instead, ion implantation was used to simulate the helium

APA, Harvard, Vancouver, ISO, and other styles

32

Loza, Peñaran Miguel Angel. "Control dinámico de un reactor nuclear PWR utilizando software libre (SCICOS)." Bachelor's thesis, Universidad Nacional Mayor de San Marcos, 2009. https://hdl.handle.net/20.500.12672/15122.

Full text

Abstract:

Presenta en forma clara y sencilla el uso del software libre SCICOS para modelar la cinética y dinámica de un reactor nuclear PWR. Creemos que este trabajo puede servir para la enseñanza y fácil compresión del funcionamiento de un reactor nuclear que se estudia en el curso de física de reactores nucleares. Las ecuaciones diferenciales utilizadas en este modelo son de primer orden y de fácil compresión. El modelo utilizado es el de Cinética puntual que describe la población de los neutrones y de los núcleos precursores que finalmente determina la potencia del reactor nuclear PWR. El Modelo térm

APA, Harvard, Vancouver, ISO, and other styles

33

Gatsa, Oleksandr. "Development of acoustic sensors for the extension of measurements to high temperature in the experimental reactors." Thesis, Montpellier, 2018. http://www.theses.fr/2018MONTS092/document.

Full text

Abstract:

Ce travail de thèse porte sur l’étude et la réalisation d'une nouvelle génération de capteurs ultrasonore dédiés à la caractérisation des gaz de fission. Plus généralement, ces études concernent le développement de l’instrumentation du réacteur d’essai des matériaux Jules Horowitz (RJH), visant entre autre à effectuer le contrôle in situ de la composition du gaz libéré afin d’optimiser la durée de vie du combustible et le taux de combustion. La température de fonctionnement de ce nouveau réacteur devant se situer dans la plage entre 200 °C à 400 °C, la principale problématique concerne donc le

APA, Harvard, Vancouver, ISO, and other styles

34

Dufek, Jan. "Development of New Monte Carlo Methods in Reactor Physics : Criticality, Non-Linear Steady-State and Burnup Problems." Doctoral thesis, Stockholm : Skolan för teknikvetenskap, Kungliga Tekniska högskolan, 2009. http://urn.kb.se/resolve?urn=urn:nbn:se:kth:diva-10602.

Full text

APA, Harvard, Vancouver, ISO, and other styles

35

Mertens, Merlijn [Verfasser], S. [Akademischer Betreuer] Cottenier, J. M. [Akademischer Betreuer] Noterdaeme, and R. [Akademischer Betreuer] Stieglitz. "De productie en moleculaire verschijningsvorm van radiotoxisch Po-210 in kernfusie- en splijtingsreactoren = The Production and Molecular Occurrence of Radiotoxic Po-210 in Nuclear Fusion and Fission Reactors / Merlijn Mertens ; S. Cottenier, J.-M. Noterdaeme, R. Stieglitz." Karlsruhe : KIT-Bibliothek, 2019. http://d-nb.info/1201415179/34.

Full text

APA, Harvard, Vancouver, ISO, and other styles

36

Dahlfors, Marcus. "Studies of Accelerator-Driven Systems for Transmutation of Nuclear Waste." Doctoral thesis, Uppsala : Acta Universitatis Upsaliensis : Universitetsbiblioteket [distributör], 2006. http://urn.kb.se/resolve?urn=urn:nbn:se:uu:diva-6341.

Full text

APA, Harvard, Vancouver, ISO, and other styles

37

SUZUKI, KATIA N. "Estudos de tecnicas de concentracao da atividade de sup(99m)Tc eluido de geradores de sup(99)Mo/sup(99m)Tc tipo gel." reponame:Repositório Institucional do IPEN, 2009. http://repositorio.ipen.br:8080/xmlui/handle/123456789/9461.

Full text

Abstract:

Made available in DSpace on 2014-10-09T12:27:01Z (GMT). No. of bitstreams: 0<br>Made available in DSpace on 2014-10-09T13:56:47Z (GMT). No. of bitstreams: 0<br>Fundação de Amparo à Pesquisa do Estado de São Paulo (FAPESP)<br>Tese (Doutoramento)<br>IPEN/T<br>Instituto de Pesquisas Energeticas e Nucleares - IPEN-CNEN/SP<br>FAPESP:06/54851-8

APA, Harvard, Vancouver, ISO, and other styles

38

Pérez-Obiol, Castañeda Axel. "Non-mesonic weak decay of hypernuclei in effective field theory." Doctoral thesis, Universitat de Barcelona, 2014. http://hdl.handle.net/10803/144554.

Full text

Abstract:

In this thesis we have described the weak Lambda N to NN interaction, which is the main responsible for the decay of heavy hypernuclei, within the effective field theory (EFT) framework. The EFT is developed up to second order in “q”, where “q” is the transferred momentum between the interacting baryons. In particular, all the two-pion exchange diagrams entering at second order in the momentum expansion have been calculated. Numerical values for the leading order low-energy constants are obtained by two means. First, a fit to the hypernuclear decay observables for three light hypernuclei, 5

APA, Harvard, Vancouver, ISO, and other styles

39

Morato, Rafet Sergio. "Contributions to solve the Multi-group Neutron Transport equation with different Angular Approaches." Doctoral thesis, Universitat Politècnica de València, 2021. http://hdl.handle.net/10251/159271.

Full text

Abstract:

[ES] La forma más exacta de conocer el desplazamiento de los neutrones a través de un medio material se consigue resolviendo la Ecuación del Transporte Neutrónico. Tres diferentes aproximaciones de esta ecuación se han investigado en esta tesis: Ecuación del transporte neutrónico resuelta por el método de Ordenadas Discretas, Ecuación de la Difusión y Ecuación de Armónicos Esféricos Simplificados. Para resolver estás ecuaciones se estudian diferentes esquemas del Método de Diferencias Finitas. La solución a estas ecuaciones describe la población de neutrones y las reacciones ocasionadas den

APA, Harvard, Vancouver, ISO, and other styles

40

Hidalga, García-Bermejo Patricio. "Development and validation of a multi-scale and multi-physics methodology for the safety analysis of fast transients in Light Water Reactors." Doctoral thesis, Universitat Politècnica de València, 2021. http://hdl.handle.net/10251/160135.

Full text

Abstract:

[ES] La tecnología nuclear para el uso civil genera más preocupación por la seguridad que muchas otras tecnologías que se usan a diario. La Autoridad Nuclear define las bases de cómo debe realizarse la operación segura de una Central Nuclear. De acuerdo a las directrices establecidas por la Autoridad Nuclear, una Central Nuclear debe analizar una envolvente de escenarios hipotéticos y comprobar de manera determinista que los criterios de aceptación para dicho evento se cumplen. El Análisis Determinista de Seguridad utiliza herramientas de simulación que aplican la física conocida sobre el comp

APA, Harvard, Vancouver, ISO, and other styles

41

SARKIS, JORGE E. de S. "Aplicacao da tecnica de correlacao isotopica para determinacao da concentracao dos nuclideos AM-241 e AM234 em combustiveis nucleares irradiados." reponame:Repositório Institucional do IPEN, 1990. http://repositorio.ipen.br:8080/xmlui/handle/123456789/10228.

Full text

Abstract:

Made available in DSpace on 2014-10-09T12:36:16Z (GMT). No. of bitstreams: 0<br>Made available in DSpace on 2014-10-09T13:59:20Z (GMT). No. of bitstreams: 1 03766.pdf: 3809732 bytes, checksum: 161cbf8550f80b76813606d7f8abf4de (MD5)<br>Tese (Doutoramento)<br>IPEN/T<br>Instituto de Pesquisas Energeticas e Nucleares - IPEN/CNEN-SP

APA, Harvard, Vancouver, ISO, and other styles

42

Barci-Funel, Geneviève. "Etudes radiochimiques de nuclides de fission et transuraniens a longues vies dans des ecosystemes marins et terrestres." Nice, 1987. http://www.theses.fr/1987NICE4156.

Full text

Abstract:

Estimation de la pollution radioactive par les radionuclides artificiels a vie longue disperses dans l'environnement suite a des tests nucleaires dans l'atmosphere et suite aux rejets d'installations nucleaires ou aux accidents comme celui de tchernobyl.

APA, Harvard, Vancouver, ISO, and other styles

43

Matocha, Vítězslav. "Hodnocení bezpečnosti a spolehlivosti jaderného paliva pomocí in-core experimentů na výzkumných jaderných reaktorech." Master's thesis, Vysoké učení technické v Brně. Fakulta elektrotechniky a komunikačních technologií, 2014. http://www.nusl.cz/ntk/nusl-220677.

Full text

Abstract:

The aim of this master thesis is to show a connection among nuclear fuel safety, experiments led in research reactors and calculation codes. This thesis focuses on the calculation code Transuranus. There are represented four experiments, which were calculated in Transuranus. The fission gas release, elongation and growth of fuel were particularly monitored. Is is possible to set differences among versions v1m1j09 and v1m3j12 from achieved results, as well as the influence of selected Transuranus parameters on the results, so the thesis may bring new pieces of knowledge for improvement of safet

APA, Harvard, Vancouver, ISO, and other styles

44

Konarski, Piotr. "Thermo-chemical-mechanical modeling of nuclear fuel behavior : Impact of oxygen transport in the fuel on Pellet Cladding Interaction." Thesis, Lyon, 2019. http://www.theses.fr/2019LYSEI080.

Full text

Abstract:

L’objectif de cette thèse est d'étudier l'impact du transport de l’oxygène sur la thermochimie de l’interaction pastille-gaine. Pendant les rampes de puissance, le combustible nucléaire est exposé à des gradients de température élevés. Il subit des changements chimiques et structurels. Le gonflement du combustible entraîne un contact mécanique avec la gaine, provoquant des contraintes mécaniques élevées. Simultanément, des espèces chimiquement réactives sont libérées par le centre des pellets chauds et peuvent interagir avec la gaine. La combinaison de ces facteurs chimiques et mécaniques peut

APA, Harvard, Vancouver, ISO, and other styles

45

Bui, Van Minh. "La décroissance bêta des produits de fission pour la non-prolifération et la puissance résiduelle des réacteurs nucléaires." Phd thesis, Ecole des Mines de Nantes, 2012. http://tel.archives-ouvertes.fr/tel-00834225.

Full text

Abstract:

Aujourd'hui, l'énergie nucléaire représente une partie non-négligeable du marché énergétique mondial, très probablement vouée à croître dans les prochaines décennies. Les réacteurs du futur devront notamment répondre à des critères supplémentaires économiques mais surtout de sûreté, de non-prolifération, de gestion optimisée du combustible et d'une gestion responsable des déchets nucléaires. Dans le cadre de cette thèse, des études concernant la non-prolifération des armes nucléaires sont abordées, dans le cadre de la recherche et développement d'un nouvel outil potentiel de surveillance des r

APA, Harvard, Vancouver, ISO, and other styles

46

MURA, LUIS F. L. "Medidas de taxas de reacao nuclear e de indices espectrais ao longo do raio das pastilhas combustiveis do reator IPEN/MB-01." reponame:Repositório Institucional do IPEN, 2010. http://repositorio.ipen.br:8080/xmlui/handle/123456789/9617.

Full text

Abstract:

Made available in DSpace on 2014-10-09T12:28:43Z (GMT). No. of bitstreams: 0<br>Made available in DSpace on 2014-10-09T13:57:15Z (GMT). No. of bitstreams: 0<br>Dissertacao (Mestrado)<br>IPEN/D<br>Instituto de Pesquisas Energeticas e Nucleares - IPEN-CNEN/SP

APA, Harvard, Vancouver, ISO, and other styles

47

Lamotte, 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.

Full text

Abstract:

Cette thèse de doctorat expose l'étude la luminescence induite dans des capteurs à gaz de type chambre à fission, afin d'évaluer son utilisation pour le suivi de puissance des réacteurs nucléaires de quatrième génération comme ASTRID.Le dépôt d'énergie dans un gaz par des ions lourds produits lors de fissions nucléaires dans une chambre à fission est d'ordinaire exploité pour sa capacité à produire des charges libres, qui peuvent être détectées avec des électrodes. Cette méthode, utilisée depuis le début de l'ère atomique, n'est pas sans inconvénients, et des axes d'amélioration ont été claire

APA, Harvard, Vancouver, ISO, and other styles

48

Nibart, Vincent. "Projet PIAFE : transport d'ions exotiques de basse énergie sur longue distance." Université Joseph Fourier (Grenoble), 1996. http://www.theses.fr/1996GRE10019.

Full text

Abstract:

Le projet piafe consiste a produire des noyaux riches en neutrons par fission au sein d'une cible d'uranium placee pres du cur du reacteur de l'institut laue langevin, puis de transporter les produits de fission sous forme monochargee et a basse energie (inferieure a 30 kev) sur une distance de 400 m jusqu'au complexe accelerateur sara de l'institut des sciences nucleaires de grenoble. Une solution originale de guidage ayant ete proposee, l'objectif de cette these est de prouver la faisabilite d'un tel transport. Pour ceci, on s'est attache a etudier les effets sur le faisceau des defauts d'al

APA, Harvard, Vancouver, ISO, and other styles

49

Pham, thi Tam ngoc. "Caractérisation et modélisation du comportement thermodynamique du combustible RNR-Na sous irradiation." Thesis, Aix-Marseille, 2014. http://www.theses.fr/2014AIXM4044/document.

Full text

Abstract:

Au-dessus d'un taux de combustion seuil ≥ 7 at %, les produits de fission volatils Cs, I, et Te ou métalliques (Mo) sont partiellement relâchés hors du combustible et finissent par constituer une couche de composés de PF qui remplit progressivement le jeu existant entre la périphérie de la pastille et la surface interne de la gaine en acier inoxydable. Nous appelons cette couche JOG pour Joint Oxyde-Gaine. Mon sujet de thèse est axé sur l'étude thermodynamique du système (Cs, I, Te, Mo, O) + (U, Pu) ainsi que sur l'étude de la diffusion de ces produits de fission à travers le combustible vers

APA, Harvard, Vancouver, ISO, and other styles

50

Jurbandam, Linina. "Calculation of the fission q-value and spatial energy deposition in the safari-1 nuclear reactor." Thesis, 2018. https://hdl.handle.net/10539/26701.

Full text

Abstract:

A dissertation submitted to the Faculty of Science, University of the Witwatersrand, in fulﬁlment of the requirements for the degree of Master of Science, Johannesburg 2018<br>The calculation of reactor-speciﬁc ﬁssion Q-values is important for the safety analyses of nuclear reactors. The recoverable energy from the ﬁssion Q-value is used to normalise reactor quantities to the total power of the reactor. In this work, a detailed recoverable energy from ﬁssion Q-value and spatial heat deposition calculations are presented for the SAFARI-1 nuclear reactor. The ﬁssion Q-value is composed of the en

APA, Harvard, Vancouver, ISO, and other styles

We offer discounts on all premium plans for authors whose works are included in thematic literature selections. Contact us to get a unique promo code!