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Dissertations / Theses on the topic 'Fission products Analysis'

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Published: 4 June 2021
Last updated: 12 February 2022

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1

EL-HAJJE, REFAAT Safety Science Faculty of Science UNSW. "A SIMULTANEOUS MEASUREMENT OF THE ANGULAR DISTRIBUTION, MASS AND KINETIC ENERGY OF 235U AND 232Th FISSION FRAGMENTS." Awarded by:University of New South Wales. School of Safety Science, 2000. http://handle.unsw.edu.au/1959.4/17612.

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Simultaneous measurements of the angular distribution, mass distribution and average total kinetic energy of fission fragments produced by the neutron-induced fission of 235U and 232Th have been made using a gridded ionisation chamber. The neutron energy range used was thermal to 1.9 MeV for 235U and 1.4 to 1.7 MeV for 232Th. The following topics were investigated: the interdependence of the fission fragment angular and mass distribution; the anomalous behaviour of fragment anisotropy for 235U(n,f) at neutron energies En below 150 keV; the possible existence of a third symmetric mass peak for
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2

SATO, IVONE M. "Determinacao dos produtos de fissao em rejeito liquido de atividade alta por fluorescencia de raio-x .Correcao da interferencia espectral pela razao das intensidades." reponame:Repositório Institucional do IPEN, 1988. http://repositorio.ipen.br:8080/xmlui/handle/123456789/9888.

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3

Belhabib, Tayeb. "Comportement thermique des défauts lacunaires induits par l’hélium et les gaz de fission dans le dioxyde d’uranium." Thesis, Orléans, 2012. http://www.theses.fr/2012ORLE2071/document.

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Dans les nouvelles centrales nucléaires dites 4ème génération, comme d’ailleurs les anciennes, le dioxyde d’uranium devra opérer dans des milieux hostiles de températures et d’irradiation avec la présence des produits de fission (PF) et des particules alpha (α). Le fonctionnement dans ces conditions extrêmes induira des déplacements d’atomes et dégradera les propriétés thermiques et mécaniques du combustible UO2. La compréhension du comportement des défauts lacunaires, des PF et de l’hélium est cruciale pour prévoir le comportement du dioxyde d’uranium au sein de ces futures installations nucl
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4

Junior, Iberê Souza Ribeiro. "Determinação de fatores de interferência de produtos de fissão do urânio na Análise por Ativação Neutrônica." Universidade de São Paulo, 2014. http://www.teses.usp.br/teses/disponiveis/85/85131/tde-22092014-144404/.

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A análise por ativação com nêutrons é um método utilizado na determinação de diversos elementos em diferentes tipos de matrizes. Entretanto, quando a amostra contém altos teores de U ocorre o problema de interferência devido aos produtos de fissão do isótopo 235U. Um dos métodos de tratar este problema é fazer a correção usando fatores de interferência devido à fissão do U para os radionuclídeos utilizados nas análises dos elementos. No presente estudo foram determinados os valores dos fatores de interferência devido à fissão do U para os radioisótopos 141Ce, 143Ce,140La, 99Mo, 147Nd, 153Sm e
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5

GERALDO, BIANCA. "Utilização de métodos radioanalíticos para a determinação de isótopos de urânio, netúnio, plutônio, amerício e cúrio em rejeitos radioativos." reponame:Repositório Institucional do IPEN, 2012. http://repositorio.ipen.br:8080/xmlui/handle/123456789/9942.

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6

RIBEIRO, JUNIOR IBERE S. "Determinação de fatores de interferência de produtos de fissão do urânio na análise por ativação neutrônica." reponame:Repositório Institucional do IPEN, 2014. http://repositorio.ipen.br:8080/xmlui/handle/123456789/11801.

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Submitted by Claudinei Pracidelli (cpracide@ipen.br) on 2014-11-10T11:38:41Z No. of bitstreams: 0<br>Made available in DSpace on 2014-11-10T11:38:41Z (GMT). No. of bitstreams: 0<br>Dissertação (Mestrado em Tecnologia Nuclear)<br>IPEN/D<br>Instituto de Pesquisas Energeticas e Nucleares - IPEN-CNEN/SP
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7

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.

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8

Kennedy, William B. (William Blake) 1979. "Analysis of the MIT research reactor fission product and actinide radioactivity inventories." Thesis, Massachusetts Institute of Technology, 2004. http://hdl.handle.net/1721.1/32723.

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Thesis (S.B.)--Massachusetts Institute of Technology, Dept. of Physics, 2004.<br>MIT Institute Archives copy: leaves 92-111 bound in reverse order.<br>Includes bibliographical references (leaf 57).<br>The current analysis of the MITR core radioactivity inventory eliminates unnecessary assumptions made in previous estimates of the inventory, and revises the list of contributory isotopes to include all actinide and fission product isotopes necessary for a proper accident source term calculation. The result is a power-history-dependent inventory that increases with bum-up, and comprises 41 actini
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9

Halonen, Kimmo. "Gamma spectrum analysis of fission product release during accidental conditions: focus on ruthenium release during air ingress." Thesis, KTH, Fysik, 2012. http://urn.kb.se/resolve?urn=urn:nbn:se:kth:diva-103715.

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10

Belhabib, Tayeb. "Comportement thermique des défauts lacunaires induits par l'hélium et les gaz de fission dans le dioxyde d'uranium." Phd thesis, Université d'Orléans, 2012. http://tel.archives-ouvertes.fr/tel-00831705.

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Dans les nouvelles centrales nucléaires dites 4ème génération, comme d'ailleurs les anciennes, le dioxyde d'uranium devra opérer dans des milieux hostiles de températures et d'irradiation avec la présence des produits de fission (PF) et des particules alpha (α). Le fonctionnement dans ces conditions extrêmes induira des déplacements d'atomes et dégradera les propriétés thermiques et mécaniques du combustible UO2. La compréhension du comportement des défauts lacunaires, des PF et de l'hélium est cruciale pour prévoir le comportement du dioxyde d'uranium au sein de ces futures installations nucl
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11

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.

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12

TAKAHASHI, SERGIO Y. "Estudo comparativo da relacao custo beneficio dos metodos de producao de sup(99)Mo: Fissao de sup(235)U e reacao de captura neutronica no sup(98)Mo." reponame:Repositório Institucional do IPEN, 2004. http://repositorio.ipen.br:8080/xmlui/handle/123456789/11230.

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13

Grente, Lucie. "Structure des fragments de fission de masse A = 100 - 110 : mesures de temps de vie et analyses en champ moyen et au-delà." Thesis, Paris 11, 2014. http://www.theses.fr/2014PA112216/document.

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Les noyaux riches en neutrons de masse A=100-110 constituent une région de grand intérêt pour l'étude de la structure nucléaire loin de la stabilité. De précédentes études de cette région de masse ont déjà révélé la complexité de l'évolution de la collectivité et de la déformation dans les chaînes isotopiques de Zr, Mo, Ru et Pd. Afin d'étendre les données expérimentales sur la collectivité à des états de plus haut spin et à des noyaux plus riches en neutrons, des temps de vie d'états excités ont été mesurés dans des noyaux produits par une réaction de fusion-fission en cinématique inverse au
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14

Coulon, Romain. "Spectrométrie gamma haute résolution et hauts taux de comptage sur primaire de réacteur de type génération 4 au sodium liquide." Phd thesis, Université de Caen, 2010. http://tel.archives-ouvertes.fr/tel-00564868.

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Les réacteurs à neutrons rapides refroidis au sodium sont en développement en vue d'assurer une quatrième génération de réacteurs répondant à la demande énergétique, tout en assurant la préservation des ressources d'uranium par un fonctionnement en surgénérateur. L'objectif de la filière est également d'améliorer la gestion de la radiotoxicité des déchets produits par transmutation des actinides mineurs et de contrôler la non-prolifération par un fonctionnement en cycle fermé. Une instrumentation de surveillance et de contrôle de ce type de réacteur a été étudiée dans cette thèse. La spectromé
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15

Egnatuk, Christine Marie. "Identifying short-lived fission products by delayed gamma-ray emission." Thesis, 2009. http://hdl.handle.net/2152/ETD-UT-2009-12-530.

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samples were irradiated for approximately 45 minutes to allow for the saturation of fission products. The first method used the beam port shutter and allowed for longer counting and irradiation times, but was unsuitable for examining fission products with half-lives below 10 seconds. The on/off method used a cycle of equal irradiation and counting times of one minute. The second method is able to measure track the production of fission products with half-lives of less than 10 seconds. This method used a borated aluminum wheel beam chopper to stop the irradiation of the sample during counti
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16

Horne, Steven Michael. "Multispectral gamma-ray analysis using clover detectors with application to uranium fission product analysis." 2013. http://hdl.handle.net/2152/21557.

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A high-efficiency gamma-ray counting system has been built at Los Alamos National Laboratory for use in analyzing nuclear forensics samples. This system consists of two clover high-purity germanium detectors and is surrounded by a thallium-doped sodium iodide annulus. Special precautions have been taken to ensure the system has a low background. The system is connected to XIA Pixie-4 fast digitizers and collects data in list-mode. This work is split into two main parts. The first part describes the proper steps and techniques to initialize the settings of a detector system connected to fast di
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17

Lu, Christopher Hing. "Determination of fission product yields of 235U using gamma ray spectroscopy." 2012. http://hdl.handle.net/2152/19716.

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It is important to have a method of experimentally calculating fission product yields. Statistical calculations and simulations produce very large uncertainties. Experimental calculations, depending on the methods used, tend to produce lower uncertainties. This work set up a method to calculate fission product yields using gamma ray spectroscopy. In order to produce a method that was theoretically sound, a simulation was set up using OrigenArp to calculate theoretical concentrations of fission products from the irradiation of natural uranium. From these concentrations, the fission product yiel
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18

Weaver, Christopher Jordan. "Development of PYRAMDS (Python for Radioisotope Analysis and Multi-Detector Suppression) code used in fission product detection limit improvements with the DGF Pixie-4 digital spectrometer." Thesis, 2011. http://hdl.handle.net/2152/ETD-UT-2011-05-2711.

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The work presented here develops a gamma-ray spectral construction and analysis software tool that was used to analyze multi-detector data collected using a digital spectrometer with list mode capabilities. The tool was used to parse the output from three detectors and generate new spectra that the user chooses from post-processing suppression routines, such as simulated anticoincidence and coincidence spectra. Part of this research was also to characterize the improvements in the detection limits and the various detector efficiencies from this method as opposed to creating these spectra using
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