O processo de sinterização de pastilhas de UO2-Er2O3 tem sido investigado devido à sua importância na indústria nuclear e ao comportamento complexo durante a sinterização. O presente estudo contempla o desenvolvimento de combustíveis nucleares para reatores de potência visando aumentar a sua eficiência no núcleo do reator por meio da elevação da taxa de queima. O érbio é indicado para ciclos mais longos, significando menos paradas para troca de combustível e menos rejeitos. Neste trabalho foi estudado o uso de óxido de érbio variando as concentrações na faixa de 1-9,8%, o qual foi adicionado ao pó de UO2 e ao lubrificante sólido ADS por meio de mistura mecânica, visando verificar a taxa de densificação e um possível bloqueio de sinterização. Os pós foram compactados e as pastilhas foram sinterizadas a 1700°C sob atmosfera de H2. Os resultados demonstram um característico bloqueio da sinterização no sistema UO2-Er2O3, porém de forma mais discreta do que no sistema UO2-Gd2O3, o qual ocorre no intervalo de temperatura de 1500 a 1700°C, retardando a densificação. Os ensaios dilatométricos indicam uma retração de 21,87% quando utilizado o Er2O3 a 1% de concentração em massa. Essa retração é maior do que as encontradas com concentrações superiores ou mesmo sem adição do veneno queimável, nos fornecendo um melhor grau de incorporação do elemento érbio, resultando em pastilhas com densidade adequada para uso como combustível nuclear. / The sintering process of UO2-Er2O3 pellets has been investigated because of its importance in the nuclear industry and the complex behavior during sintering. The present study includes the development of nuclear fuel for power reactor in order to increase the efficiency of the fuel through longer refueling intervals. The erbium is indicated for longer cycles, which means less stops to refueling and less waste. In this work, it was studied the use of erbium oxide by varying the concentrations in the range of 1-9.8%, which was added to UO2 powder through mechanical mixing, aiming to check the rate of densification and a possible sintering blockage. The powders were pressed and sintered at 1700°C under hydrogen atmosphere. The results show a sintering blockade in the UO2-Er2O3 system that occurs in the range of 1500-1700°C temperature. Dilatometric tests indicate a retraction of 21.87% when used Er2O3 at 1% mass concentration. This retraction is greater than is observed with higher concentrations or even without the addition of the burnable poison, providing us with a better degree of incorporation of the element erbium, resulting in pellets with density suitable for use as nuclear fuel.

Este trabalho apresenta a análise neutrônica do combustível a dispersão de UMo-Al em relação ao aumento da densidade de urânio e faz uma comparação com o combustível de U3Si2-Al. Neste estudo, a densidade de urânio do U3Si2-Al é variada de 3,0 à 5,5 gU/cm3 e a do UMo-Al entre 4,0 à 7,5 gU/cm3 e com a porcentagem em massa de molibdênio com 7 e 10 %. Neste trabalho também é proposta a aplicação de veneno queimável metálico no cerne do combustível de UMo-Al, uma vez que este combustível é metálico e é analisada a utilização de gadolínio (Gd) e európio (Eu) como veneno queimável. A utilização do Gd como veneno queimável foi analisada com o fator de multiplicação infinito (k∞) através do programa celular HRC desenvolvido pelo IPEN e composto pelos códigos HAMMERTECHNION para a analise de célula, ROLAIDS para o cálculo de auto blindagem dos actinídeos e CINDER-2 empregado para a fissão e transmutação dos actinídeos. O núcleo do reator simulado foi similar ao do RMB (Reator Multipropósito Brasileiro) composto por um arranjo de 5x5 posições com 23 elementos combustíveis e dois blocos de alumínio. Para o európio, foram utilizados os programas SERPENT e CITATION. Os cálculos de queima foram realizados considerando uma potência de 30 MW durante três ciclos do RMB de 97 dias. Os resultados obtidos mostram que a porcentagem em massa do molibdênio têm uma grande influência no comportamento neutrônico devido a seção de choque de absorção do molibdênio ser considerável. Portanto, foi escolhida a porcentagem de 7 % de Mo para os estudos com veneno queimável. Para o núcleo proposto, o európio mostrou-se melhor, pois apresenta uma queima mais gradual que o gadolínio. Foi realizada uma simulação com o programa SERPENT com adição de 6 % de silício, o que mostrou que a adição de Si não causa mudança significativa no ciclo de operação do reator. Para validação da metodologia de cálculo, foi elaborada uma especificação técnica e fabricadas 12 miniplacas combustíveis de UMo-Al sem veneno queimável. As miniplacas foram irradiadas no núcleo do reator IPEN/MB-01, em quatro configurações de núcleo, para obtenção da reatividade inserida. Os resultados simulados obtidos para a inserção de reatividade pelas miniplacas nos diversos núcleos analisados apresentaram alta concordância com os resultados experimentais. / This work presents the neutronic analysis of the UMo-Al dispersion fuel concerning uranium density increase and shows comparisons relatively to the U3Si2-Al fuel. The U3Si2-Al uranium density varied from 3.0 to 5.5 gU/cm3 while that of UMo-Al fuel varied from 4.0 to 7.5 gU/cm3. The molybdenum mass content in the former case varies from 7 to 10 % in mass. Here, it is also proposed the utilization of burnable poison nuclides in the UMo-Al fuel meat. Since the fuel is metallic, gadolinium and europium were chosen as candidates to cope with this task. A recently developed cell code at IPEN (HRC) composed of the coupling of the codes HAMMER-TECHNION for the cell analysis, ROLAIDS for the actinide self-shielding calculations and CINDER-2 for the actinide and fission transmutation was employed for the neutronic analyses of UMo-Al. The simulated reactor core was similar to the one of RMB (Brazilian Multipurpose Reactor) composed of an array of 5x5 positions with 23 fuel elements and 2 aluminum blocks. A second analysis of the europium case employed the SERPENTE and CITATION codes. The burnup calculations were performed considering a power of 30 MW during three cycles of RMB 97 days. The analyses revealed that the molybdenum content has a great impact in the core reactivity due to its high absorption cross section. A value of 7 % was found adequate for the molybdenum mass content. The analyses also reveal that europium is a better burnable poison than gadolinium for the core cycle length and power level under consideration. It was realized a simulation with the computer code SERPENT with addition of 6 % silicon in UMo-Al fuel. The silicon does not change significantly the reactor operation cycle. To validate the calculation methodology it was developed a technical specification and fabricated 12 UMo-Al fuel miniplates without burnable poison. The miniplates were irradiated in the IPEN-MB/01 reactor core for four core configurations, in order to obtain the inserted reactivity. The simulated results for the reactivity insertion by the fuel miniplates in the analyzed cores showed high agreement with the experimental results.

O processo de sinterização de pastilhas de UO2-Er2O3 tem sido investigado devido à sua importância na indústria nuclear e ao comportamento complexo durante a sinterização. O presente estudo contempla o desenvolvimento de combustíveis nucleares para reatores de potência visando aumentar a sua eficiência no núcleo do reator por meio da elevação da taxa de queima. O érbio é indicado para ciclos mais longos, significando menos paradas para troca de combustível e menos rejeitos. Neste trabalho foi estudado o uso de óxido de érbio variando as concentrações na faixa de 1-9,8%, o qual foi adicionado ao pó de UO2 e ao lubrificante sólido ADS por meio de mistura mecânica, visando verificar a taxa de densificação e um possível bloqueio de sinterização. Os pós foram compactados e as pastilhas foram sinterizadas a 1700°C sob atmosfera de H2. Os resultados demonstram um característico bloqueio da sinterização no sistema UO2-Er2O3, porém de forma mais discreta do que no sistema UO2-Gd2O3, o qual ocorre no intervalo de temperatura de 1500 a 1700°C, retardando a densificação. Os ensaios dilatométricos indicam uma retração de 21,87% quando utilizado o Er2O3 a 1% de concentração em massa. Essa retração é maior do que as encontradas com concentrações superiores ou mesmo sem adição do veneno queimável, nos fornecendo um melhor grau de incorporação do elemento érbio, resultando em pastilhas com densidade adequada para uso como combustível nuclear. / The sintering process of UO2-Er2O3 pellets has been investigated because of its importance in the nuclear industry and the complex behavior during sintering. The present study includes the development of nuclear fuel for power reactor in order to increase the efficiency of the fuel through longer refueling intervals. The erbium is indicated for longer cycles, which means less stops to refueling and less waste. In this work, it was studied the use of erbium oxide by varying the concentrations in the range of 1-9.8%, which was added to UO2 powder through mechanical mixing, aiming to check the rate of densification and a possible sintering blockage. The powders were pressed and sintered at 1700°C under hydrogen atmosphere. The results show a sintering blockade in the UO2-Er2O3 system that occurs in the range of 1500-1700°C temperature. Dilatometric tests indicate a retraction of 21.87% when used Er2O3 at 1% mass concentration. This retraction is greater than is observed with higher concentrations or even without the addition of the burnable poison, providing us with a better degree of incorporation of the element erbium, resulting in pellets with density suitable for use as nuclear fuel.

In the deep burn research of Very High Temperature Reactor (VHTR), it is desired to make an accurate estimation of absorption cross sections and absorption rates in burnable poison (BP) pins. However, in traditional methods, multi-group cross sections are generated from single bundle calculations with specular reflection boundary condition, in which the energy spectral effect in the core environment is not taken into account. This approximation introduces errors to the absorption cross sections especially for BPs neighboring reflectors and control rods. In order to correct the BP absorption cross sections in whole core diffusion calculations, energy spectrum reconstruction (ESR) methods have been developed to reconstruct the fine group spectrum (and in-core continuous energy spectrum). Then, using the reconstructed spectrum as boundary condition, a BP pin cell local transport calculation serves an imbedded module within the whole core diffusion code to iteratively correct the BP absorption cross sections for improved results. The ESR methods were tested in a 2D prismatic High Temperature Reactor (HTR) problem. The reconstructed fine-group spectra have shown good agreement with the reference spectra. Comparing with the cross sections calculated by single block calculation with specular reflection boundary conditions, the BP absorption cross sections are effectively improved by ESR methods. A preliminary study was also performed to extend the ESR methods to a 2D Pebble Bed Reactor (PBR) problem. The results demonstrate that the ESR can reproduce the energy spectra on the fuel-outer reflector interface accurately.

Este trabalho apresenta a análise neutrônica do combustível a dispersão de UMo-Al em relação ao aumento da densidade de urânio e faz uma comparação com o combustível de U3Si2-Al. Neste estudo, a densidade de urânio do U3Si2-Al é variada de 3,0 à 5,5 gU/cm3 e a do UMo-Al entre 4,0 à 7,5 gU/cm3 e com a porcentagem em massa de molibdênio com 7 e 10 %. Neste trabalho também é proposta a aplicação de veneno queimável metálico no cerne do combustível de UMo-Al, uma vez que este combustível é metálico e é analisada a utilização de gadolínio (Gd) e európio (Eu) como veneno queimável. A utilização do Gd como veneno queimável foi analisada com o fator de multiplicação infinito (k∞) através do programa celular HRC desenvolvido pelo IPEN e composto pelos códigos HAMMERTECHNION para a analise de célula, ROLAIDS para o cálculo de auto blindagem dos actinídeos e CINDER-2 empregado para a fissão e transmutação dos actinídeos. O núcleo do reator simulado foi similar ao do RMB (Reator Multipropósito Brasileiro) composto por um arranjo de 5x5 posições com 23 elementos combustíveis e dois blocos de alumínio. Para o európio, foram utilizados os programas SERPENT e CITATION. Os cálculos de queima foram realizados considerando uma potência de 30 MW durante três ciclos do RMB de 97 dias. Os resultados obtidos mostram que a porcentagem em massa do molibdênio têm uma grande influência no comportamento neutrônico devido a seção de choque de absorção do molibdênio ser considerável. Portanto, foi escolhida a porcentagem de 7 % de Mo para os estudos com veneno queimável. Para o núcleo proposto, o európio mostrou-se melhor, pois apresenta uma queima mais gradual que o gadolínio. Foi realizada uma simulação com o programa SERPENT com adição de 6 % de silício, o que mostrou que a adição de Si não causa mudança significativa no ciclo de operação do reator. Para validação da metodologia de cálculo, foi elaborada uma especificação técnica e fabricadas 12 miniplacas combustíveis de UMo-Al sem veneno queimável. As miniplacas foram irradiadas no núcleo do reator IPEN/MB-01, em quatro configurações de núcleo, para obtenção da reatividade inserida. Os resultados simulados obtidos para a inserção de reatividade pelas miniplacas nos diversos núcleos analisados apresentaram alta concordância com os resultados experimentais. / This work presents the neutronic analysis of the UMo-Al dispersion fuel concerning uranium density increase and shows comparisons relatively to the U3Si2-Al fuel. The U3Si2-Al uranium density varied from 3.0 to 5.5 gU/cm3 while that of UMo-Al fuel varied from 4.0 to 7.5 gU/cm3. The molybdenum mass content in the former case varies from 7 to 10 % in mass. Here, it is also proposed the utilization of burnable poison nuclides in the UMo-Al fuel meat. Since the fuel is metallic, gadolinium and europium were chosen as candidates to cope with this task. A recently developed cell code at IPEN (HRC) composed of the coupling of the codes HAMMER-TECHNION for the cell analysis, ROLAIDS for the actinide self-shielding calculations and CINDER-2 for the actinide and fission transmutation was employed for the neutronic analyses of UMo-Al. The simulated reactor core was similar to the one of RMB (Brazilian Multipurpose Reactor) composed of an array of 5x5 positions with 23 fuel elements and 2 aluminum blocks. A second analysis of the europium case employed the SERPENTE and CITATION codes. The burnup calculations were performed considering a power of 30 MW during three cycles of RMB 97 days. The analyses revealed that the molybdenum content has a great impact in the core reactivity due to its high absorption cross section. A value of 7 % was found adequate for the molybdenum mass content. The analyses also reveal that europium is a better burnable poison than gadolinium for the core cycle length and power level under consideration. It was realized a simulation with the computer code SERPENT with addition of 6 % silicon in UMo-Al fuel. The silicon does not change significantly the reactor operation cycle. To validate the calculation methodology it was developed a technical specification and fabricated 12 UMo-Al fuel miniplates without burnable poison. The miniplates were irradiated in the IPEN-MB/01 reactor core for four core configurations, in order to obtain the inserted reactivity. The simulated results for the reactivity insertion by the fuel miniplates in the analyzed cores showed high agreement with the experimental results.

Orientador: Gustavo Paim Valença / Tese (doutorado) - Universidade Estadual de Campinas, Faculdade de Engenharia Quimica / Made available in DSpace on 2018-08-14T01:43:35Z (GMT). No. of bitstreams: 1 PaganoJunior_Luciano_D.pdf: 3596308 bytes, checksum: 5144d304934b8f4fef833acb8200cddf (MD5) Previous issue date: 2009 / Resumo : O efeito dos aditivos TiO2, Nb2O5, SiO2, Fe2O3 e Al(OH)3, em concentração de 0,5% em massa, na cinética sinterização do combustível nuclear UO2·7%Gd2O3 em atmosfera de H2 a 99,999% foi investigada por stepwise isothermal dilatometry. Este combustível, usado como veneno queimável em reatores nucleares de potência, apresenta uma barreira de difusão por volta de 1.573 K, o que dificulta a obtenção da densidade final requerida. O auxílio dos aditivos TiO2, Al(OH)3, Nb2O5 e Fe2O3 foi eficaz em adensar o material, o mesmo não acontecendo para a composição dopada com SiO2. A energia de ativação para o estágio intermediário de sinterização foi calculada pelo método stepwise isothermal dilatometry e mostrou uma correlação positiva com a densidade do corpo sinterizado. O método se revelou válido para parte do estágio intermediário de sinterização, entre 1.200 K e 1.700 K para as composições dopadas e sem aditivo, à exceção daquela com SiO2, e entre 1.500 K e 1.900 K para esta última. Esta correlação também não se mostrou válida para a composição dopada com SiO2, cujo efeito foi o de reduzir a densidade final. Seu comportamento anômalo pode ser explicado pela excessiva perda de Si, por volatilização de óxidos menores, no estágio inicial de sinterização, isto é, em temperatura menor que 1.173 K. Perda similar, mas não tão intensa, também foi observada para a composição dopada com Al(OH)3 para o intervalo de temperatura entre 1.173 K e 1.573 K. A redução da concentração de Si a valores residuais, da ordem de dezenas de partes por milhão, pode explicar o seu comportamento anômalo. A correlação positiva entre energia de ativação e densidade do corpo sinterizado pode ser explicada pelo papel inibidor dos aditivos TiO2, Nb2O5, Fe2O3 e Al(OH)3 nos mecanismos de difusão promotores do engrossamento. Desta forma, os mecanismos de adensamento são favorecidos na competição pela energia livre de superfície. O modelo coarsening densification transition temperature, originalmente proposto para o sistema UO2, se mostrou aplicável ao presente caso. O cálculo das ordens de reação, também pelo método stepwise isothermal dilatometry, mostrou que os mecanismos de difusão promotores do engrossamento predominam em baixas temperaturas, até 1.650 K para a composição dopada com SiO2, até 1.550 K para as composições dopadas com Nb2O5, , Fe2O3 e Al(OH)3 e sem aditivo, e até 1.450 K para aquela dopada com TiO2. A partir destas temperaturas de transição, os mecanismos de adensamento crescem de importância e, no final do intervalo de validade do método, passam a predominar. A análise microestrutural por difração de raios X das composições dopadas com TiO2, Nb2O5, SiO2 e Al(OH)3 indicou a presença de óxido de nióbio, provavelmente NbO ou NbO2, em corpos sinterizados a 2.023 K por 4 h. Foi identificado o acúmulo preferencial de Ti nos contornos de grãos do corpo sinterizado por espectroscopia por dispersão de energia. A análise de espectroscopia Mössbauer mostrou que o Nb não influencia diretamente a difusão de Gd+3 e não há Gd2O3 livre após a conclusão do processo de sinterização a 2.023 K por 4 h. / Abstract: The addition of 0.5wt% TiO2, Nb2O5, SiO2, Fe2O3 and Al(OH)3 in the UO2·7%Gd2O3 nuclear fuel and the effect on its sintering kinetics under a 99.999% H2 atmosphere were investigated by stepwise isothermal dilatometry. This fuel, used as burnable poison in nuclear power plants, presents a diffusion barrier around 1573 K that impairs densification. The aid of the sintering additives TiO2, Al(OH)3, Nb2O5 and Fe2O3 turned out to be effective to obtain the required final density, unlike the effect observed for the SiO2-doped composition. The activation energy for the intermediate sintering stage was calculated by stepwise isothermal dilatometry method and a positive correlation with the sintered body density was found. The method was valid for part of the intermediate sintering stage, in the range from 1200 K to 1700 K for the doped compositions and with no additive, except for the SiO2-doped one, whose validity range was between 1500 K and 1900 K. The energy-density correlation was not valid for the SiO2-doped composition, whose effect was to reduce the final density. This anomalous behavior may be attributed to the intense loss of Si mass, probably due to lower oxides volatilization, during the initial sintering stage at temperatures lower than 1173 K. Similar loss, but no so intense, was observed for the Al(OH)3-doped composition in the temperature interval from 1173 K to 1573 K. The Si concentration decrease to residual values of dozens of parts per million may explain its anomalous behavior. The positive correlation between activation energy and sintered body density may be explained by the inhibitor role played by the TiO2, Nb2O5, Fe2O3 and Al(OH)3 additives on the diffusion mechanisms that enhance the coarsening regime. As a consequence, the densification mechanisms are favored in the competition for the surface free energy. The coarsening-densification transition temperature model, originally suggested for the UO2 system, turned out to be valid for the UO2·7%Gd2O3 system. The reaction order calculation, also performed by the stepwise isothermal dilatometry method, showed that the coarsening diffusion mechanisms prevails at low temperatures, up to 1650 K for the SiO2-doped composition, up to 1550 K for the compositions doped with Nb2O5, Fe2O3, Al(OH)3 and no additive, and for the TiO2-doped one, up to 1450 K. From these temperatures on, the densification enhancing mechanisms become steadily more important and, in the end of method validity range, they become predominant. The microstructural analysis performed by X-ray diffraction of the TiO2, Nb2O5, SiO2 and Al(OH)3 doped compositions, sintered at 2023 K por 4 h, revealed the presence of niobium oxide, probably NbO or NbO2. It was identified Ti segregation at grain boundaries by energy-dispersive spectroscopy. The Mössbauer spectroscopy showed that Nb does not directly affect the Gd+3 diffusion and there is no free Gd2O3 after the sintering cycle is concluded at 2023 K for 4 h. O cálculo das ordens de reação, também pelo método stepwise isothermal dilatometry, mostrou que os mecanismos de difusão promotores do engrossamento predominam em baixas temperaturas, até 1.650 K para a composição dopada com SiO2, até 1.550 K para as composições dopadas com Nb2O5, , Fe2O3 e Al(OH)3 e sem aditivo, e até 1.450 K para aquela dopada com TiO2. A partir destas temperaturas de transição, os mecanismos de adensamento crescem de importância e, no final do intervalo de validade do método, passam a predominar. A análise microestrutural por difração de raios X das composições dopadas com TiO2, Nb2O5, SiO2 e Al(OH)3 indicou a presença de óxido de nióbio, provavelmente NbO ou NbO2, em corpos sinterizados a 2.023 K por 4 h. Foi identificado o acúmulo preferencial de Ti nos contornos de grãos do corpo sinterizado por espectroscopia por dispersão de energia. A análise de espectroscopia Mössbauer mostrou que o Nb não influencia diretamente a difusão de Gd+3 e não há Gd2O3 livre após a conclusão do processo de sinterização a 2.023 K por 4 h. / Doutorado / Desenvolvimento de Processos Químicos / Doutor em Engenharia Química

Ce travail de thèse s'inscrit dans le cadre du développement d'une solution innovante d'empoisonnement neutronique homogène, par insertion d'erbium, au cœur des gaines de combustible en alliage de zirconium utilisées dans les réacteurs à eau pressurisée. Dans cette étude réalisée par le CEA, la géométrie envisagée est une gaine triplex constituée d'un liner interne faiblement enrichi en erbium, compris entre deux couches d'alliage industriel base zirconium. Dans le cœur du réacteur, l'eau se dissocie à la surface de la gaine. Il est donc intéressant d'évaluer les interactions potentielles entre l'hydrogène et l'alliage Zr-Er du liner. Cela nécessite de connaître le système ternaire Er-H-Zr ainsi que les systèmes binaires associés. Ceci peut être obtenu par détermination expérimentale et grâce à la modélisation thermodynamique. Les deux techniques ont été utilisées au cours de cette thèse. Les systèmes binaires Er-Zr et H-Zr ont été déterminés expérimentalement et modélisés dans la littérature. Le système binaire Er-H en revanche était très mal connu. Nous avons étudié ce système expérimentalement. Il a ensuite été modélisé avec l'approche Calphad. Nous obtenons une nouvelle évaluation du système binaire Er-H, avec des limites de phases différentes de ce qui avait été proposé précédemment. Dans le but de déterminer les limites des domaines de phases et de mettre en évidence l'éventuelle existence d'un composé ternaire dans le système ternaire Er-H-Zr, une étude expérimentale a été menée. Une technique originale a été utilisée : le dosage chimique des éléments d'alliage a été fait par ERDA combinée à la RBS. Cette étude nous a permis de proposer une coupe isotherme expérimentale à 350°C de ce système ternaire. Concernant la modélisation, les trois systèmes binaires ont été rendus compatibles dans le but de calculer le diagramme de phases ternaire par projection des binaires. Le calcul obtenu est en bon accord avec la coupe isotherme expérimentale. Enfin, par le biais de campagnes d'essais de traction, nous avons évalué l'impact de l'ajout d'erbium et/ou d'hydrogène sur le comportement mécanique du zirconium de pureté industrielle. Nous avons ainsi mis en évidence un effet durcissant de l'erbium et de l'hydrogène sans pour autant que ces effets soient corrélés. Aucun de ces résultats n'est rédhibitoire pour l'utilisation de cet alliage Er-Zr en tant que liner dans le concept triplex / This work at CEA is being achieved in the framework of the development of an innovating concept including the neutronic solid burnable poison, such as erbium, inside the cladding of pressurized water reactors. These new claddings are constituted by a liner of a zirconium base alloy slightly enriched in erbium between two liners of industrial zirconium alloys. Into the reactor core, the water dissociates at the surface of the cladding. So it is interesting to evaluate the interactions between the hydrogen released and the Zr-Er alloy. To do so, the Er-H-Zr ternary system has to be determined such similarly to its associated binaries. This can be done by experimental determination and by thermodynamic modelling. Both techniques were used in this work. Er-Zr and H-Zr have already been studied experimentally and modelled, but the Er-H binary system is almost unknown. So, we studied it experimentally. Then, it has been modelled using the Calphad method. We obtain a new evaluation of the Er-H binary system with phases limits rather different than what has been proposed in the literature. In order to determine the phase limits and, the potential existence of a ternary compound in the Er-H-Zr ternary system, an experimental study has been carried out. An original technique has been used to obtain the chemical compositions: ERDA combined with RBS. In this study, we propose a new isothermal section at 350°C of the Er H-Zr ternary system. About the modelling, the compatibility of the three modelled binaries has been checked in order to optimize the ternary system by the projection of the three binaries. The calculation obtained is in good agreement with the experimental isothermal section at 350°C determined in our work. Finally, uniaxial tensile test campaigns have been conducted to evaluate the impact of erbium and/or hydrogen on the mechanical properties of an industrial zirconium pure alloy. We evidenced a hardening effect of erbium and hydrogen but these effects are not correlated. None of these results is prohibitive for the use of this Er Zr alloy as a liner in the triplex concept

Dans le cadre de ce travail, nous nous sommes intéressés à un concept innovant d’empoisonnement homogène des neutrons par insertion de terres rare (erbium et gadolinium) dans les gaines en alliage de zirconium pour les réacteurs à eau pressurisée. L’étude des équilibres entre phases des alliages erbium–zirconium et gadolinium–zirconium est indispensable comme préalable à la mise en oeuvre industrielle de ce procédé prometteur d’empoisonnement. Ce travail a consisté à déterminer expérimentalement le diagramme de phases du système erbium–zirconium. Nous avons, par le biais de différentes caractérisations, obtenu des données diagrammatiques. Avec celles-ci, nous proposons un nouveau tracé du diagramme de phases. Celui-ci est radicalement différent de celui disponible dans la littérature. Nous avons modélisé le système par l’approche CALPHAD. Nous avons également déterminé les limites de solubilité des solutions solides terminales du système gadolinium–zirconium. Les données obtenues expérimentalement sont en accord avec le tracé expérimental de la littérature et avec le modèle thermodynamique disponible. Afin de prendre en compte l’oxydation des gaines en service, nous nous sommes également intéressés aux systèmes erbium–oxygène–zirconium et gadolinium–oxygène–zirconium. Le premier système a fait l’objet d’une étude expérimentale. Nous avons mis en place un procédé de synthèse par métallurgie des poudres, incluant la synthèse de celles-ci à partir de métaux massifs. La caractérisation des échantillons ternaires nous a permis de proposer deux coupes isothermes (800°C et 1100°C). Pour le système gadolinium–oxygène–zirconium, nous avons prédit les équilibres entre phases à différentes températures à l’aide de calculs effectués à partir d’une base de données que nous avons construite avec les modèles thermodynamiques de la littérature des systèmes oxygène–zirconium, gadolinium–zirconium et sesquioxyde de gadolinium–zircone. Enfin, nous avons travaillé avec des alliages erbium–zirconium fabriqués en milieu industriel. Nous nous sommes intéressés à leurs propriétés mécaniques en traction, en lien avec leur microstructure. Nous avons mis en évidence l’effet durcissant de l’erbium, notamment à 325‰°C / This work is a contribution to the development of innovating concepts for fuel cladding in pressurized water nuclear reactors. This concept implies the insertion of rare earth (erbium and gadolinium) in the zirconium fuel cladding. The determination of the phase equilibrium in the systems is essential prior to the realisation of such a promising solution. This study consisted in the experimental determination of the erbium–zirconium phase diagram. For this, we used many different techniques to get diagram data like solubility limits and solidus, liquidus or invariant temperatures. With these data, we were able to give a new diagram, very different from the literature one. With the experimental data we collected, we also assessed the diagram, using the CALPHAD approach. In this work, we also determined the solubility limits of the gadolinium–zirconium system. Those limits had never been determined before, and the values we obtained are in excellent agreement with the experimental and with the assessed diagrams. Because these alloys are subjected to oxygen diffusion throughout their life, we focused our attention on the erbium–oxygen–zirconium and gadolinium–oxygen–zirconium system. The first system has been investigated experimentally.We used many different synthesis techniques, and we finally have opted for a powder metallurgy one. As raw material, we fabricated powder from erbium and zirconium bulk metals using hydrogen absorption/desorption. With the formed ternary pellets, we investigated the phase equilibria at 800°C and 1100°C. With the obtained data, we propose two isotherms at those two temperatures. For the gadolinium–oxygen–zirconium system, we calculated the phase equilibria at temperatures ranging from 800°C to 1100‰°C, using a homemade database compiled from literature assessments of the oxygen–zirconium, gadolinium–zirconium et gadolia-zirconia systems. We also determined the mechanical properties, in connexion with the microstructure, of industrial quality alloys in order to identify the influence of erbium content. We highlighted the hardening influence of erbium at 325‰°C

L’excès de réactivité neutronique dans les centrales nucléaires est compensé par des sys-tèmes actifs de contrôle du réacteur : acide borique et barres de contrôle. L’apport d’antiréactivité peut se faire passivement avec des poisons consommables, c'est-à-dire des absorbants de neutrons, en particulier du gadolinium (Gd).Dans le cadre d’une augmentation de l’enrichissement en U²³⁵ et de réduction de l’utilisation d’acide borique, cette thèse a pour objectif d’optimiser la distribution du ga-dolinium dans des céramiques d’UO₂ afin d’obtenir un apport optimisé d’antiréactivité dans un Réacteur à Eau sous Pression.Dans ce sens, le travail est orienté à trouver des nouveaux matériaux riches en gadolinium. Le diagramme de phase U-O-Gd a donc été exploré dans le domaine des fortes teneurs en Gd. Deux phases cubiques ont été trouvées et caractérisées : les phases C1 et C2. En vue d’une application industrielle, la phase C1 a été retenue comme candidate pour l’ajout du Gd dans les pastilles d’UO₂.La distribution optimale de cette phase C1 dans les assemblages de combustible nucléaire a été étudiée avec le code de calcul neutronique APOLLO2.8. Des études paramétriques ont été réalisées. Ces études neutroniques ont aboutit à un concept performant de pastille empoisonnée. Finalement, des pastilles prototype ont été fabriquées en laboratoire suivant ce concept. L’ensemble des résultats obtenus montre qu’un concept de pastille avec un dépôt superficiel neutrophage de phase C1 est une manière d’apporter de l’antiréactivité de manière optimisée dans le cadre de cycles longs. Ceci pourrait potentiellement être appliquée à l‘échelle industrielle. Un brevet a été déposé en ce sens. / Reactivity excess in Nuclear Power Plants is controlled by reactor’s active systems: boric acid dilution and control rods. Alternatively, negative reactivity insertion can be made in a passive way using burnable poisons, i.e. neutron absorbers, this is the case of gadolinium (Gd).In the industrial framework of U²³⁵ enrichment increase and boric acid restraint, the goal of this thesis is to optimize the distribution of gadolinium in UO₂ ceramics to obtain a high-performance provision of negative reactivity in Pressurized Water Reactors.In this sense, the work is focus on new gadolinium-rich materials. Thus, U-Gd-O phase diagram was explored in the field of high Gd contents. Two cubic phases were found and characterized: the C1 and C2 phases. With the aim of an industrial application, C1 phase was selected as candidate for Gd addition into UO₂ pellets.The optimal distribution of C1 phase within a nuclear fuel assembly was studied using APOLLO 2.8 neutron transport code. Parametrical calculations were performed. These neutronic studies have ends in a successful “concept of poisoned pellet”.Finally, some prototype pellets following this concept were made in laboratory to proof it feasibility.All the obtained results shows that the proposed concept of a neutrophage C1-phase coating on UO₂ pellets is a convenient way to reduce reactivity excess within the framework of long irradiation cycles. This concept could be potentially applied in industrial scale. Consequently a patent application process was initiated.

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, as the fuel used could not conceivably be as highly enriched. Nuclear-powered propulsion would allow ships to operate with low fuel costs, long refueling intervals, and minimal emissions; however, currently such systems remain largely confined to military vessels. This research project undertakes computational modeling of possible soluble-boron-free (SBF) reactor core designs for this application, with a view to informing design decisions in terms of choices of fuel composition, materials, core geometry and layout. Computational modeling using appropriate reactor physics (e.g. WIMS, MONK, Serpent and PANTHER), thermal-hydraulics etc. codes (e.g. COBRA-EN) is used for this project. With an emphasis on reactor physics, this study investigates possible fuel assembly and core designs for civil marine propulsion applications. In particular, it explores the feasibility of using uranium/thorium-rich fuel in a compact, long-life reactor and seek optimal choices and designs of the fuel composition, reactivity control, assembly geometry, and core loading in order to meet the operational needs of a marine propulsion reactor. In this reactor physics and 3D coupled neutronics/thermal-hydraulics study, we attempt to design a civil marine reactor core that fulfills the objective of providing at least 15 effective full-power-years (EFPY) life at 333 MWth. In order to unleash the benefit of thorium in a long life core, the micro-heterogeneous ThO2-UO2 duplex fuel is well-positioned to be utilized in our proposed civil marine core. Unfortunately, A limited number of studies of duplex fuel are available in the public domain, but its use has never been examined in the context of a SBF environment for long-life small modular rector (SMR) core. Therefore, we assumed micro-heterogeneous ThO2-UO2 duplex fuel for our proposed marine core in order to explore its capability. For the proposed civil marine propulsion core design, this study uses 18% U-235 enriched micro-heterogeneous ThO2-UO2 duplex fuel. To provide a basis for comparison we also evaluate the performance of homogeneously mixed 15% U-235 enriched all-UO2 fuel. This research also attempts to design a high power density core with 14 EFPY while satisfying the neutronic and thermal-hydraulics safety constraints. A core with an average power density of 100 MW/m3 has been successfully designed while obtaining a core life of 14 years. The average core power density for this core is increased by ∼50% compared to the reference core design (63 MW/m3 and is equivalent to Sizewell B PWR (101.6 MW/m3 which means capital costs could be significantly reduced and the economic attractiveness of the marine core commensurately improved. In addition, similar to the standard SMR core, a reference core with a power density of 63 MW/m3 has been successfully designed while obtaining a core life of ∼16 years. One of the most important points that can be drawn from these studies is that a duplex fuel lattice needs less burnable absorber than uranium-only fuel to achieve the same poison performance. The higher initial reactivity suppression and relatively smaller reactivity swing of the duplex can make the task of reactivity control through BP design in a thorium-rich core easier. It is also apparent that control rods have greater worth in a duplex core, reducing the control material requirements and thus potentially the cost of the rods. This research also analyzed the feasibility of using thorium-based duplex fuel in different cases and environments to observe whether this fuel consistently exhibit superior performance compared to the UO2 core in both the assembly and whole-core levels. The duplex fuel/core consistently exhibits superior performance in consideration of all the neutronic and TH constraints specified. It can therefore be concluded from this study that the superior performance of the thorium-based micro-heterogeneous ThO2-UO2 duplex fuel provides enhanced confidence that this fuel can be reliably used in high power density and long-life SBF marine propulsion core systems, offering neutronic advantages compared to the all-UO2 fuel. Last, but not least, considering all these factors, duplex fuel can potentially open the avenue for low-enriched uranium (LEU) SBF cores with different configurations. Motivated by growing environmental concerns and anticipated economic pressures, the overall goal of this study is to examine the technological feasibility of expanding the use of nuclear propulsion to civilian maritime shipping and to identify and propose promising candidate core designs.