Relevant bibliographies by topics / Pu02

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  2. Dissertations / Theses
  3. Book chapters
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Academic literature on the topic 'Pu02'

Author: Grafiati
Published: 18 September 2022

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Journal articles on the topic "Pu02"

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Li, Quan, Zhenghe Zhu, Hongyan Wang, and Gang Jiang. "Potential energy function for PuO2+, PuH2+ and PuN2+ ions." Journal of Molecular Structure: THEOCHEM 578, no. 1-3 (2002): 177–80. http://dx.doi.org/10.1016/s0166-1280(01)00700-x.

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Dulanská, Silvia, Boris Remenec, L’ubomír Mátel, and Igor Antalík. "Validation of 239,240Pu, 238Pu separation method using molecular recognition product AnaLig® Pu02 gel and extraction chromatography TRU® resin." Journal of Radioanalytical and Nuclear Chemistry 292, no. 1 (2011): 97–101. http://dx.doi.org/10.1007/s10967-011-1370-x.

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Dulanská, Silvia, Boris Remenec, Ľubomír Mátel, and Dušan Galanda. "The selective separation of Pu isotopes using molecular recognition technology product AnaLig® Pu02 gel and extraction chromatography TRU® resin." Journal of Radioanalytical and Nuclear Chemistry 287, no. 3 (2010): 841–45. http://dx.doi.org/10.1007/s10967-010-0836-6.

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Archibong, E. F., and A. K. Ray. "An ab initio study of PuO2 and of PuN2." Journal of Molecular Structure: THEOCHEM 530, no. 1-2 (2000): 165–70. http://dx.doi.org/10.1016/s0166-1280(00)00332-8.

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Dulanská, Silvia, Boris Remenec, L’ubomír Mátel, and Erik Durkot. "Rapid determination of 239,240Pu, 238Pu, 241Am and 90Sr in radioactive waste using combined SPE sorbents AnaLig® Pu02, AnaLig® Sr01 and TRU® Resin." Journal of Radioanalytical and Nuclear Chemistry 293, no. 1 (2012): 81–85. http://dx.doi.org/10.1007/s10967-012-1727-9.

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Chacon, Hernan, Heidis Cano, Joaquin Hernández Fernández, et al. "Effect of Addition of Polyurea as an Aggregate in Mortars: Analysis of Microstructure and Strength." Polymers 14, no. 9 (2022): 1753. http://dx.doi.org/10.3390/polym14091753.

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The addition of polymers in construction is a new tendency and an important step toward the production of structures with better functional properties. This work investigates the addition of polyurea (PU) as a polymeric material in mortars. Polymer mortars were manufactured with the addition of polyurea retained in different sieves (T50 and T100) and different concentrations (2% and 5%). The characterization of the, polyurea (PU)control mortar (PU0%) and manufactured polyurea mortars (PU2%T50, PU5%T50, PU2%T100, and PU5%T100) was conducted by means of morphological analysis, SEM, XRF, TGA, and a compressive strength test of hydraulic mortars. The results show that mortars with polyurea retained in sieve 100 with a particle size of 150 μm exhibit better thermal behavior and a greater resistance to compression with a concentration of 5% polyurea with respect to the other samples. The present work reveals that polyurea retained in sieve 100 can be considered as a polymeric additive for mortars, indicating that it could be a candidate for applications such as construction.
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Kitashiro, S., T. Iwasaka, T. Sugiura, et al. "Monitoring urine oxygen tension during acute change in cardiac output in dogs." Journal of Applied Physiology 79, no. 1 (1995): 202–4. http://dx.doi.org/10.1152/jappl.1995.79.1.202.

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To evaluate whether renal blood flow (RBF) can be monitored during acute change in cardiac index, ureter urine oxygen tension (PuO2) and bladder urine oxygen tension (PbO2) were measured in six mongrel dogs. PuO2, cardiac index, and RBF increased after dobutamine infusion and decreased after propranolol infusion. PuO2 had an excellent correlation with RBF (r = 0.94) and a fair correlation with cardiac index (r = 0.50) and mean blood pressure (r = 0.56); RBF had a fair correlation with mean blood pressure (r = 0.52, P < 0.05) but was not related to cardiac index. With multiple-regression analysis, PuO2 was found to be the significant factor related to RBF. PbO2 had a good correlation with PuO2 (r = 0.94) at control levels. Furthermore, when two dogs were added to evaluate relationships among PbO2, PuO2, and RBF, PbO2 had an excellent correlation with PuO2 (r = 0.92) and RBF (r = 0.91). These data indicate that PuO2 is a more sensitive predictor of RBF than cardiac index and mean blood pressure and that PbO2 can be a noninvasive indicator reflecting RBF during acute circulatory change in dogs.
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Shang, Zhijie, Yuxuan Wang, Lixun Chai, and Gengpu Yang. "Pumilio RNA Binding Family Member 2 Promotes the Proliferation and Metastasis of Lung Cancer Cells by Regulating Ca2+ Signaling Pathway via Targeting C-X-C Chemokine Receptor Type 4." Journal of Biomaterials and Tissue Engineering 11, no. 7 (2021): 1339–45. http://dx.doi.org/10.1166/jbt.2021.2692.

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The aim of the present study was to investigate the mechanism by which pumilio RNA binding family member 2 (PUM2), an RNA-binding protein (RBP) of C-X-C chemokine receptor type 4 (CXCR4), exerts its effects on the development of lung cancer. RT-qPCR and western blot analysis were utilized to measure the expression of PUM2 in several lung cancer cell lines. Cell Counting Kit-8 (CCK-8), colony formation assay, transwell- and wound healing assays were employed to determine the proliferation, invasion and migration of NCI-H520 cells, respectively. Next, the expression of CXCR4 was measured using western blot analysis, and the combination between PUM2 and CXCR4 was verified by RNA immunoprecipitation (RIP) assay and RNA pull down assay. Finally, whether the expression of PUM2 can affect the Ca2+ signaling pathway was confirmed by western blot assay. Results revealed that the expression level of PUM2 was notably upregulated in lung cancer cells, and knockdown of PUM2 significantly inhibited the proliferation, invasion and migration of NCI-H520 cells. PUM2 was confirmed to be the RBP of CXCR4, and PUM2 knockdown decreased the expression of CXCR4. In addition, PUM2 silencing inhibited the phosphorylation of CaMKII, ERK, and MEK. Taken together, these findings demonstrated that PUM2 could promote the proliferation and metastasis of lung cancer cells by regulating Ca2+ signaling pathway via targeting CXCR4, which may provide a novel insight for the future treatment of lung cancer.
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Schieweck, Rico, Elisa-Charlott Schöneweiss, Max Harner, et al. "Pumilio2 Promotes Growth of Mature Neurons." International Journal of Molecular Sciences 22, no. 16 (2021): 8998. http://dx.doi.org/10.3390/ijms22168998.

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RNA-binding proteins (RBPs) are essential regulators controlling both the cellular transcriptome and translatome. These processes enable cellular plasticity, an important prerequisite for growth. Cellular growth is a complex, tightly controlled process. Using cancer cells as model, we looked for RBPs displaying strong expression in published transcriptome datasets. Interestingly, we found the Pumilio (Pum) protein family to be highly expressed in all these cells. Moreover, we observed that Pum2 is regulated by basic fibroblast growth factor (bFGF). bFGF selectively enhances protein levels of Pum2 and the eukaryotic initiation factor 4E (eIF4E). Exploiting atomic force microscopy and in vitro pulldown assays, we show that Pum2 selects for eIF4E mRNA binding. Loss of Pum2 reduces eIF4E translation. Accordingly, depletion of Pum2 led to decreased soma size and dendritic branching of mature neurons, which was accompanied by a reduction in essential growth factors. In conclusion, we identify Pum2 as an important growth factor for mature neurons. Consequently, it is tempting to speculate that Pum2 may promote cancer growth.
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Siddiqui, A. H., and M. C. Brandriss. "A regulatory region responsible for proline-specific induction of the yeast PUT2 gene is adjacent to its TATA box." Molecular and Cellular Biology 8, no. 11 (1988): 4634–41. http://dx.doi.org/10.1128/mcb.8.11.4634.

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Deletion analysis of the promoter of the PUT2 gene that functions in the proline utilization pathway of Saccharomyces cerevisiae identified a PUT2 upstream activation site (UAS). It is contained within a single 40-base-pair (bp) region located immediately upstream of the TATA box and is both necessary and sufficient for proline induction. When placed upstream of a CYC7-lacZ gene fusion, the 40-bp sequence conferred proline regulation on CYC7-lacZ. A 35-bp deletion within the PUT2 UAS in an otherwise intact PUT2 promoter resulted in noninducible expression of a PUT2-lacZ gene fusion. When a plasmid bearing this UAS-deleted promoter was placed in a strain carrying a constitutive mutation in the positive regulatory gene PUT3, expression of PUT2-lacZ was not constitutive but occurred at levels below those found under noninducing conditions. In heterologous as well as homologous gene fusions, the PUT2 UAS appeared to be responsible for uninduced as well as proline-induced levels of expression. Although located immediately adjacent to the PUT2 UAS, the TATA box did not appear to play a regulatory role, as indicated by the results of experiments in which it was replaced by the CYC7 TATA box. A 26-bp sequence containing this TATA box was critical to the expression of PUT2, since a deletion of this region completely abolished transcriptional activity of the gene under both inducing and noninducing conditions. Our results indicate that the PUT2 promoter has a comparatively simple structure, requiring UAS and TATA sequences as well as the PUT3 gene product (directly or indirectly) for its expression.
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Dissertations / Theses on the topic "Pu02"

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Pizette, Patrick. "Simulation de la compaction de poudres céramiques par la méthode des éléments discrets : application à la mise en forme des combustibles nucléaires mixtes." Grenoble INPG, 2009. http://www.theses.fr/2009INPG0190.

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Le combustible nucléaire mixte (MOX) est élaboré sous forme de pastilles par compaction en matrice puis frittage d'un mélange de poudres d'oxydes d'uranium et de plutonium. Du fait de la variabilité des poudres et compte tenu de la nécessité industrielle de maintenir constants les paramètres de fabrication sur des quantités importantes de produit, l'opération de compaction peut être à l'origine de rejets des pastilles lors des contrôles. En particulier, la solidité et la maîtrise dimensionnelle des comprimés sont des enjeux majeurs du procédé. La méthode des éléments discrets (DEM), mise en œuvre ici, offre un outil puissant de compréhension et de simulation. Elle s'appuie sur une modélisation explicite du caractère particulaire des poudres. Deux représentations, à l'échelle des agrégats de cristallites et à l'échelle des cristallites sont considérées pour simuler la consolidation de la poudre. Une méthodologie à partir d'expériences numériques est proposée pour établir des lois de comportement susceptibles de renseigner un code par éléments finis. Enfin, la modélisation à l'échelle des cristallites permet d'identifier les principaux paramètres microstructuraux qui influent sur la solidité des comprimés<br>Nuclear mixed oxide fuel (MOX) is formed as pellets by cold compaction of a powder blend of oxides of uranium and plutonium followed by sintering. Because of the variability of incoming powders in the process and taking into account the need to maintain constant industrial settings for processing significant quantities of pellets, the compaction process may generate some rejection during controls. In particular, compact strength and dimensional precision are key features of the industrial process. The Discrete Element Method (DEM), which has been used here, offers a powerful tool for understanding and simulating the compaction stage. It relies on an explicit modeling of the particulate nature of the uranium oxide powders. Two models, at the length scale of the aggregate of crystallites and at the length scale of the crystallites are used to simulate the powder compaction. A methodology, based on numerical experiments, is proposed to generate constitutive laws to feed a finite element code. Finally, the modeling at the crystallite length scale is used to identify the main microstructural parameters that control the compact strength
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(UPC), Universidad Peruana de Ciencias Aplicadas. "Fundamentos de Marketing - PU42 201801." Universidad Peruana de Ciencias Aplicadas (UPC), 2018. http://hdl.handle.net/10757/623382.

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El curso Fundamentos de Marketing presenta al estudiante los conceptos básicos de Marketing con la finalidad de compartir la aplicación de las herramientas y estrategias utilizadas en la gestión de marcas, permitiéndoles aprovechar oportunidades para lograr satisfacer las necesidades del mercado en la compra y preferencia de productos y servicios. En un mundo donde las tendencias tecnológicas y de consumo son de cambio constante, se suma la abundante cantidad de información que recibimos diariamente relacionada a la oferta de productos. Por ese motivo, el curso desarrolla en los estudiantes habilidades que les permitirá establecer una adecuada interacción entre las marcas y sus públicos gracias al conocimiento del consumidor.
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Carrillo, Portocarrero Vanessa Rosana, Belaunde Carolina Angelica Christen, Bravo Karina Janeth García, et al. "Fundamentos de Publicidad - PU01 201801." Universidad Peruana de Ciencias Aplicadas (UPC), 2018. http://hdl.handle.net/10757/623385.

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Curso general de la Facultad de Comunicaciones, de carácter teórico, dirigido a los estudiantes de las carreras de Comunicación y Publicidad, Comunicación y Marketing (3er ciclo), Comunicación e Imagen Empresarial (4to ciclo) y Comunicación Audiovisual y Medios Interactivos (mención propia en Publicidad). Propósito: La vertiginosa evolución de las comunicaciones y el empoderamiento del consumidor conducen hoy a los fabricantes de productos y servicios a desarrollar modelos de publicidad cada vez más efectivos. Lograr que los compradores potenciales, encuentren, conozcan y se habitúen a sus productos y servicios es una de las principales tareas de la publicidad. Otro de los roles de la publicidad es generar soluciones creativas en función al conocimiento profundo de las personas, del perfil de la marca y de las características de los medios. "(...)La publicidad rodea nuestras vidas, nos persigue por todas partes, pero a pesar de estar presente y mostrarse tanto, oculta a los ojos del espectador cuáles son sus claves profesionales, cómo funciona, por qué funciona." Marçal Moliné. La Comunicación Activa (1997).
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Beaudoux, Xavier. "Dissolution réductrice d'oxydes de lanthanides et de PuO2 assistée par ultrasons." Thesis, Montpellier, 2015. http://www.theses.fr/2015MONTS046.

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Dans le cadre du programme nucléaire français, le combustible des réacteurs est constitué d'oxydes d'uranium ou d'oxydes mixtes d'uranium et de plutonium (appelé MOX). Des développements sont constamment effectués sur les procédés de retraitement de ces combustibles afin d'optimiser la récupération des matières valorisables et de minimiser le volume des déchets. Lors de la dissolution des MOX, la quantité de fines de dissolution résiduelles riches en Pu est parfois importante malgré l'utilisation de conditions chimiques dures (oxydantes et corrosives). La difficulté à dissoudre des lots de PuO2 déclarés non conformes lors de la fabrication du MOX peut également représenter un verrou technologique. Dans ce contexte, la sonochimie est envisagée comme alternative aux méthodes actuelles de dissolution de PuO2, ou de MOX enrichi en Pu. Dans un premier temps, des travaux de dissolution sonochimique ont été réalisés sur un analogue inactif de PuO2, à savoir CeO2. Les résultats obtenus ont ainsi permis d'orienter les expériences de dissolution de PuO2. En conditions réductrices et acides, beaucoup plus douces que celles utilisées industriellement, la dissolution totale de ces deux oxydes a été effectuée en quelques heures. Parallèlement, une étude connexe a montré qu'il est possible de dissoudre totalement des oxydes mixtes de lanthanides à base de Ce, par un procédé de dissolution sonocatalytique et réductrice en présence de nanoparticules de Pt. La dissolution est d'autant plus rapide que la teneur en lanthanides trivalents est importante au sein de l'oxyde. Enfin, une dernière partie a été consacrée à la dissolution sous agitation magnétique d'oxydes à base de Ce en présence ou non de métaux nobles, dans des milieux faiblement acides contenant des molécules naturelles réductrices. Dans ces conditions, une dissolution totale, rapide et sélective de ces oxydes a été observée. Ces deux dernières études présentent un intérêt dépassant le cadre du nucléaire et applicable au recyclage de matériaux industriels (pots catalytiques, piles à combustible…)<br>In the French nuclear program, the reactor fuel consists of uranium oxides or uranium plutonium mixed oxides (called MOX). Developments are constantly made on the resulting reprocessing of these fuels in order to optimize the recovery of reusable materials and to minimize the waste volume. In the case of MOX dissolution, the amount of Pu-rich dissolution residues is sometimes high despite the use of hard chemical conditions (oxidizing and corrosive). The difficulty to dissolve PuO2 batches declared non-standard during the fabrication of MOX can also be a technological barrier. In this context, sonochemistry can be considered as an alternative to current methods of dissolution of PuO2 or Pu enriched MOX. First, experiments of sonochemical dissolution were performed on an inactive analogue of PuO2, namely CeO2. The results were then used as a working basis for the dissolution of PuO2. Under reducing and acidic conditions, much milder than those used industrially, the complete dissolution of these two oxides was carried out within a few hours. Meanwhile, a related study showed that it is possible to completely dissolve lanthanide mixed oxides by a process of sonocatalytic and reductive dissolution in the presence of Pt. The dissolution rates increase with the trivalent lanthanide content within the oxide. Finally, the last part was devoted to the dissolution under magnetic stirring of Ce-based oxides in the presence or absence of noble metals, in weakly acidic media containing reducing natural molecules. Under these conditions, a complete, rapid and selective dissolution of these oxides was observed. These last two studies present an interest beyond the scope of nuclear chemistry, concerning the recycling of industrial materials (catalytic converters, fuel cells...)
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LEME, DIVA G. "Interdifusao cationica nos sistemas UO2-(U,Pu)O2 e UO2-PuO2." reponame:Repositório Institucional do IPEN, 1985. http://repositorio.ipen.br:8080/xmlui/handle/123456789/9845.

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Made available in DSpace on 2014-10-09T12:32:00Z (GMT). No. of bitstreams: 0<br>Made available in DSpace on 2014-10-09T13:56:54Z (GMT). No. of bitstreams: 1 02353.pdf: 2378392 bytes, checksum: 057496400e142b206f0a466480d00c7a (MD5)<br>Tese (Doutoramento)<br>IPEN/T<br>Instituto de Pesquisas Energeticas e Nucleares - IPEN/CNEN-SP
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Balboa, lópez Hector. "Simulation of thermomechanical properties of U-PuO2 nuclear fuel under irradiation." Thesis, Université Paris-Saclay (ComUE), 2018. http://www.theses.fr/2018SACLX108/document.

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L’objectif de cette thèse a été d’utiliser une approche numérique pour étudier l’impact des dommages d'irradiation sur la microstructure du combustible nucléaire composé d'un mélange d’oxyde de plutonium et d’uranium (MOX). Cette approche, réalisée à l'échelle atomique, repose sur l'utilisation de potentiels empiriques développés dans la littérature pour l'oxyde mixte $(U,Pu)O_2$ dans l’approximation des interactions d’ions rigides.Une première étape a été une analyse critique des propriétés structurales, thermodynamiques et mécaniques prédites par 5 potentiels de la littérature. Les calculs de dynamique moléculaire ont été réalisés à l'aide du code LAMMPS, sur l'ensemble de la gamme de composition de $UO_2$ à $PuO_2$ et à des températures comprises entre 300 K et le point de fusion. Nous montrons que les potentiels les plus satisfaisants sont ceux développés par Cooper et Potashnikov. Ces deux potentiels reproduisent correctement la stabilité thermodynamique des phases ainsi que l'évolution en température des paramètres de maille et de la chaleur spécifique. Cependant le comportement mécanique des oxydes est différent selon le potentiel choisi. Tout d'abord, on note que les constantes élastiques et le facteur d'anisotropie obtenus par le potentiel Cooper sont plus fidèles aux recommandations de la littérature. Ensuite, nous montons que la propagation d'une fracture induit une transformation de phase en pointe de fissure avec le potentiel de Cooper alors qu'une fissuration fragile est observée avec le potentiel Potashnikov.Une seconde étape a été l'étude des dommages d'irradiation dans les oxydes mixtes en se limitant à l'utilisation des deux potentiels de Cooper et de Potashnikov. Des calculs de dynamique moléculaire de cascades de déplacement ont été réalisés à différentes énergies, température et compositions en plutonium. Ensuite, afin d'évaluer les dommages d'irradiation sur des temps plus longs que ceux accessibles en dynamique moléculaire, la méthode d’accumulation de défauts a été utilisée. Pour les deux potentiels, l’évolution des dommages primaires avec l’augmentation de la dose suit globalement les mêmes étapes que celles trouvées précédemment dans $UO_2$. Tout d’abord, les défauts ponctuels sont créés. Par la suite, ils se regroupent et forment de petites boucles de Frank, qui après se transforment en dislocations parfaites. Cependant, la cinétique de la recombinaison de défauts ponctuels est significativement plus lente avec le potentiel de Cooper ce qui conduit à la création de petites régions désordonnées pour les cascades d'énergie élevée. L’effet de la teneur en plutonium est analysé. Nous montrons en particulier que la densité de dislocations crée diminue lorsque la teneur en plutonium augmente.Bien que la dynamique moléculaire a été décrite comme un microscope moléculaire en raison de sa capacité à décrire avec précision des systèmes atomiques, elle présente un inconvénient majeur, celui lié aux temps de l’ordre de la femto-seconde nécessaires pour résoudre les vibrations atomiques. Cela limite le temps total de simulation approximativement quelques nanosecondes. Afin de stimuler les processus, tels que la diffusion de cations, un autre outil de calcul est nécessaire. Les techniques de Monte Carlo (KMC) atomiques peuvent simuler de plus longtemps que la dynamique moléculaire . Cependant, pour que KMC fonctionne avec précision, il est nécessaire de connaître a priori tous les mécanismes de transition entre les états possibles. Pour cette raison, la method de Monte Carlo cinétique adaptative (aKMC) est choisie pour surmonter ces limitations. Cette méthode détermine les états de transition disponibles pendant la simulation. De cette manière, elle entraîne le système dans des états imprévus via des mécanismes complexes. La puissance de cet outil s'est révélée efficace pour découvrir la recombinaison de cations sur de plus longues périodes de temps que la DM<br>The objective of this doctoral research is to use a numerical approach to study the impact of irradiation damage on the microstructure of the mixed uranium-plutonium oxide fuel (MOX). This numerical approach comprises mainly the use of Molecular Dynamics (MD) using empirical potential. Several empirical potentials for $(U,Pu)O_2$ can be found in the literature. The results of these potentials can exhibit significant differences. For this reason an extensive assessment of the main empirical potential found in the literature had to be performed.Five empirical interatomic potentials were assessed in the approximation of rigid ions and pair interactions for the $(U_{1-y},Pu_y)O_2$ solid solution. Simulations were carried out on the structural, thermodynamics and mechanical properties over the full range of plutonium composition, meaning from pure $UO_2$ to pure $PuO_2$ and for temperatures ranging from 300 K up to the melting point. The best results are obtained by potentials referred as Cooper and Potashnikov. The first one reproduces more accurately recommendations for the thermodynamics and mechanical properties exhibiting ductile-like behaviour during crack propagation, whereas the second one gives brittle behaviour at low temperature.From our results from the empirical potentials assessment, we can move to the radiation damage using only two potentials (Cooper and Potashnikov). In order to know the main source of defect during irradiation, MD displacement cascades were simulated. This revealed the damage created due to varying projectile energies. In addition, the Frenkel pair accumulation method was chosen to investigate the dose effect. This method circumvents the highly computing time demanding accumulation of displacement cascade by directly creating their final states, i.e. mainly point defects. Overall, results obtained with both potentials show the same trend. However, kinetics of point defect recombination are significantly slower with Cooper potential implying creation of small disordered region with high energy displacement cascades. The evolution of the primary damage with increasing dose follows the same steps as those found previously in pure $UO_2$. First, point defects are created. Subsequently, they cluster and form small Frank loops, which in turn transform and grow into unfaulted loops. We demonstrate also that increasing temperatures accelerate the production of dislocations shifting their creation to lower doses. The effect of the plutonium content is also evidenced, especially with Cooper potential. It shows that the dislocation density decreases when the plutonium content increases.Although, MD has been described as a molecular microscope due to its ability to discribe accuratily systems of atoms, it has a large drawback that is the short time steps of the order of femto-seconds needed to resolve the atomic vibrations. This limits the time typically few microsecond. In order to invetigate processess, such as, cation diffusion and rare-event annihilation of defects after cascaces, another computational tool is required. Atomistic or object kinetic Monte Carlo (KMC) techniques can run for longer timescales than MD. However, for KMC to work accurately, all of the possible inter-state transition mechanisms and their associated rates need to be known a priori. For this reason, the adaptive kinetic Monte Carlo (AKMC) is chosen to overcome these limitations. This method determines the available transition states during simulation. In this way, it takes the system into unforeseen states via complex mechanisms. The power and range of this tool proved to be efficient to discover cation Frenkel pair recombination over a longer periods of time than MD
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JUILLET, FRANCK. "Etude de la dissolution d'oxydes refractaires (ceo2 et puo2) assistee par sonochimie." Paris 11, 1997. http://www.theses.fr/1997PA112040.

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La dissolution de puo2 est un sujet d'etude important pour le traitement des dechets de l'industrie nucleaire. Parmi les techniques nouvelles etudiees pour ameliorer les procedes existants, la sonochimie qui utilise les ultrasons pour promouvoir les reactions chimiques, semble interessante. La caracterisation de l'appareilage experimental (mesure de la puissance sonore et de la production d'eau oxygenee) a montre la dependance des effets observes a la geometrie et aux conditions operatoires. L'influence des variations de volume et de puissance sonore sur ces effets est decrite par la notion de densite de puissance. Selon leur frequence, les ultrasons induisent majoritairement des effets mecaniques aux basses frequences (20 khz) et des effets chimiques aux frequences elevees (500 et 1700 khz) dus a la production d'especes radicalaires. Les effets mecaniques des ultrasons de 20 khz ont ete mis en evidence lors de l'etude de la dissolution de ceo2 et puo2 en milieu aqueux. Sous l'action des ultrasons, la taille des grains de ceo2 diminue selon un mecanisme a deux etapes (fracture puis usure). Les effets mecaniques entrainent egalement une augmentation des vitesses initiales de dissolutions connues (ceo2 par h2o2 et puo2 par ag(ii)). Dans les milieux ou la dissolution de ceo2 ou puo2 est limitee, l'application des ultrasons de haute frequence permet d'accroitre leur solubilisation. Ce phenomene est lie a l'action des especes radicalaires generees par les ultrasons. Les solutes ou les gaz dissous permettent de favoriser la production d'especes soit reductrices soit oxydantes. Dans le cas de la dissolution sous ultrasons de puo2 en milieu hno3, le mecanisme de dissolution n'est pas modifie. L'accroissement de la cinetique de dissolution a ete attribue a la production de nox par les ultrasons. Cependant, les performances envisageables de la dissolution sonochimique de puo2 sont tres en deca de celles du procede electrolytique existant.
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La, Lumia Florian. "Granulation de suspensions concentrées UO2/PuO2 : application à l'élaboration de compacts granulaires denses par pressage et à leu caractérisation structurale post frittage." Thesis, Limoges, 2019. http://www.theses.fr/2019LIMO0076.

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Le procédé actuel de fabrication des combustibles nucléaires MOX (UO2-PuO2) est réalisé exclusivement par voie sèche (broyage-tamisage des poudres, pressage et frittage). Afin d’améliorer ce procédé, des recherches sont menées sur le développement d’un procédé de fabrication du MOX par voie liquide. Ce procédé vise à réduire l’empoussièrement des boîtes à gants, améliorer l’homogénéité U/Pu et diminuer la quantité de défauts (fissures, éclats) des pastilles frittées, afin de minimiser le taux de pastilles rebutées. Dans cette optique, le proceed voie liquide étudié consiste à préparer une suspension aqueuse à partir des poudres brutes d’oxydes (mélange d’eau, d’additifs organiques et de poudres), puis à lui faire subir une granulation. Les granules obtenus sont ensuite pressés et frittés. Le procédé de granulation étudié est un procédé innovant de granulation cryogénique, consistant à atomiser la suspension dans de l’azote liquide puis à lyophiliser les granules gelés ainsi formés. L’étape clé du procédé est la préparation de suspension aqueuse de poudres UO2-PuO2, qui doit être dispersée, homogène, stable et suffisamment fluide pour l’étape de granulation. Une étude préliminaire a été réalisée avec des poudres simulantes, choisies pour leurs propriétés en suspension : TiO2 et Y2O3 pour simuler respectivement UO2 et PuO2. Une fois maîtrisé avec les poudres simulantes, ce procédé a été étudié avec UO2 et PuO2 pour déterminer ses conditions optimales de mise en oeuvre. La dispersion de suspensions d’UO2 et/ou de PuO2 a été étudiée par acoustophorométrie et rhéologie afin d’optimiser leur formulation, ainsi que l’étape de granulation cryogénique. Enfin, des pastilles d’UO2 et d’UO2-PuO2 ont été formées à partir des granules, puis leur frittage et leur microstructure ont été étudiés<br>The current manufacturing process for MOX nuclear fuels (UO2-PuO2) is carried out by dry route exclusively (grinding, sieving, pressing and sintering). In order to improve this process, research is conducted to develop a liquid route MOX manufacturing process. It aims to reduce glove boxes dusting, increase U/Pu homogeneity and reduce the amount of defects (cracks, voids) in sintered pellets, in order to minimize scraps. In this scope, the liquid process studied consists in the preparation of an aqueous suspension from the raw oxide powders (mix of water, organic additives and powders), which is then granulated. The resulting granules are pressed into pellets and sintered. The granulation process studied is an innovative freeze granulation process that implies to spray the suspension in liquid nitrogen and then freeze-dry the frozen granules that are formed.The key step of the process is the preparation of aqueous suspension of UO2-PuO2 powders, which must be dispersed, homogeneous, stable and fluid enough for the granulation step. A preliminary study was carried out using surrogate powders, chosen for their properties in suspension: TiO2 and Y2O3 to surrogate UO2 and PuO2 respectively. Once mastered with surrogate powders, this process was studied with UO2 and PuO2 to determine its optimal working conditions. The dispersion of UO2 and/or PuO2 suspensions was studied by acoustophorometry and rheology in order to optimize their formulation, as well as the freeze granulation step. Finally, UO2 and UO2-PuO2 pellets were shaped from the granules, and their sintering and microstructure were studied
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FERNANDES, MARCO A. R. "Analise de experimentos criticos de UO2-PuO2 utilizando os sistemas NJOY/AMPX-II/HAMMER-TECHNION." reponame:Repositório Institucional do IPEN, 1990. http://repositorio.ipen.br:8080/xmlui/handle/123456789/10234.

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Made available in DSpace on 2014-10-09T12:36:20Z (GMT). No. of bitstreams: 0<br>Made available in DSpace on 2014-10-09T13:59:30Z (GMT). No. of bitstreams: 1 03995.pdf: 5942263 bytes, checksum: 59581ec48c0cba56318bd21dd195fa2d (MD5)<br>Dissertacao (Mestrado)<br>IPEN/D<br>Instituto de Pesquisas Energeticas e Nucleares - IPEN/CNEN-SP
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Hicks, Mark. "Reactivity and mechanistic studies of small molecules at model metal oxide surfaces : underpinning PuO2 safe storage." Thesis, Cardiff University, 2015. http://orca.cf.ac.uk/69894/.

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The nuclear fuel cycle represents the nuclear power generation process, from mining the uranium ore to the treatment of waste. The fuel cycle is divided into two parts, the front end of the process and the back end of the process, with the nuclear power station being in the middle1. The processes before reaching the nuclear power station consist of uranium exploration, mining, refining, isotope enriching and fuel element fabrication1. Uranium is mined in twenty countries, but 52% of the world supply of uranium comes from just 6 countries. These countries are Canada, Australia, Russia, Kazakhstan, Namibia and Niger. Uranium is mined in several different types of mine. These include an open pit mine, an underground mine or in-situ leaching mine. In an open pit mine the ore lies close to the surface and the overlying layer of rock is removed creating a large pit where the ore is easily extractable. An underground mine is used when the ore lies deeper under the surface and the construction of access shafts and tunnels under the ground are needed to gain access to the uranium ore. The uranium ore is sometimes contained in ground water or a porous material, such as sand. In this case, a process called in-situ leaching is used to extract the uranium ore. Either acid or alkali (depending on the nature of the groundwater) is added to the ground water to dissolve the ore, and the resulting solution is pumped out. The ore then undergoes a milling process to extract the uranium oxides needed for fuel fabrication. Milling is normally carried out close to the mine where the ore has been extracted. The ore is crushed and then leached with sulphuric acid in order to dissolve the uranium oxides.
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Book chapters on the topic "Pu02"

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Villars, P., K. Cenzual, J. Daams, et al. "(PuO2)2SiO4∙2H2O." In Structure Types. Part 9: Space Groups (148) R-3 - (141) I41/amd. Springer Berlin Heidelberg, 2010. http://dx.doi.org/10.1007/978-3-642-02702-4_554.

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Vrinda Devi, K. V., K. Biju, and K. B. Khan. "PuO2 Agglomerate Detectability in (Th,1%Pu)O2 Fuel—A Monte Carlo Simulation Study." In Thorium—Energy for the Future. Springer Singapore, 2019. http://dx.doi.org/10.1007/978-981-13-2658-5_23.

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Valério, Miguel. "Linear A du-pu2-re, Hittite tabarna and their alleged relatives revisited." In Journal of Language Relationship, edited by Vladimir Dybo, Kirill Babaev, Anna Dybo, Alexei Kassian, Sergei Kullanda, and Ilya Yakubovich. Gorgias Press, 2010. http://dx.doi.org/10.31826/9781463236984-008.

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Casarci, M., G. M. Gasparini, G. Grossi, and M. Rossi. "Application of the Teseo Process for Actinide Removal from Liquid Alpha Wastes Generated During UO2-PuO2 Fuel Fabrication Campaigns." In New Separation Chemistry Techniques for Radioactive Waste and Other Specific Applications. Springer Netherlands, 1991. http://dx.doi.org/10.1007/978-94-011-3654-9_11.

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Attwood, Teresa K., Alexander L. Mitchell, Anna Gaulton, Georgina Moulton, and Lydia Tabernero. "The PRINTS protein fingerprint database: functional and evolutionary applications." In Encyclopedia of Genetics, Genomics, Proteomics and Bioinformatics. John Wiley & Sons, Ltd, 2006. http://dx.doi.org/10.1002/047001153x.g306301.pub2.

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Mulder, Nicola J., and Rolf Apweiler. "InterPro." In Encyclopedia of Genetics, Genomics, Proteomics and Bioinformatics. John Wiley & Sons, Ltd, 2006. http://dx.doi.org/10.1002/047001153x.g306310.pub2.

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METIVIER, H., J. WAHRENDORF, D. NOLIBE, S. ANDRE, and R. MASSE. "INHALATION CARCINOGENESIS OF FINE PARTICLES OF PLUTONIUM OXIDE FORMED FROM THE COMBUSTION OF A PLUTONIUM-MAGNESIUM ALLOY. COMPARISON TO PURE MICROMETRIC PuO2." In Inhaled Particles VI. Elsevier, 1988. http://dx.doi.org/10.1016/b978-0-08-034185-9.50124-8.

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Conference papers on the topic "Pu02"

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Moran, G. Ruiz, M. Lamas Maceiras, and A. M. Rodriguez Torres. "Transcriptional regulation of ADE2 and PUT2 genes in Kluyveromyces lactis." In Proceedings of the III International Conference on Environmental, Industrial and Applied Microbiology (BioMicroWorld2009). WORLD SCIENTIFIC, 2010. http://dx.doi.org/10.1142/9789814322119_0141.

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Waris, Abdul, Indarta K. Aji, Novitrian, Syeilendra Pramuditya, and Zaki Su’ud. "UO2 and PuO2 utilization in high temperature engineering test reactor with helium coolant." In THE 4TH INTERNATIONAL CONFERENCE ON THEORETICAL AND APPLIED PHYSICS (ICTAP) 2014. AIP Publishing LLC, 2016. http://dx.doi.org/10.1063/1.4943735.

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Gupta, Narendra K. (Nick). "Thermal Analysis of the SAFKEG Package for Long Term Storage." In ASME 2005 Pressure Vessels and Piping Conference. ASMEDC, 2005. http://dx.doi.org/10.1115/pvp2005-71129.

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Interim plutonium storage for up to 10 years in the K-reactor building is currently being planned at Savannah River Site (SRS). SAFKEG package could be used to store Pu metal and oxide (PuO2) in the K-reactor complex with other packagings like 9975. The SAFKEG is designed for carrying Type-B materials across the DOE complex and meets the 10CFR71 requirements. Thermal analyses were performed to ensure that the temperatures of the SAFKEG components will not exceed their temperature limits under the K-reactor storage conditions. Thermal analyses of the SAFKEG packaging with three content configurations using BNFL 3013 outer container (Rocky Flats, SRS bagless transfer cans, and BNFL inner containers) were performed for storage of PuO2 and plutonium metal.
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Paffett, Mark T. "An Alternative Interpretation of the Existence and Importance of the PuO2+X⋅H2O Solid Solution." In PLUTONIUM FUTURES - THE SCIENCE: Third Topical Conference on Plutonium and Actinides. AIP, 2003. http://dx.doi.org/10.1063/1.1594601.

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Zuberek, Joanna, Janusz Stępiński, Anna Niedzwiecka, et al. "Synthesis of tetraribonucleotide cap analogue m7GpppAm2'pUm2'pAm2' and its interaction with eukaryotic initiation factor eIF4E." In XIIth Symposium on Chemistry of Nucleic Acid Components. Institute of Organic Chemistry and Biochemistry, Academy of Sciences of the Czech Republic, 2002. http://dx.doi.org/10.1135/css200205399.

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Zaiets, Vasyl. "Nuclear Fuel Burn-Up Depth in WWER Reactors With Various Burnable Absorbers." In 2012 20th International Conference on Nuclear Engineering and the ASME 2012 Power Conference. American Society of Mechanical Engineers, 2012. http://dx.doi.org/10.1115/icone20-power2012-54251.

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An overview of relationship between nuclear fuel burn-up depth and absorbers used is made. Gd2O3, PuO2, and mixture of transuranium elements as absorbers for NPP with WWER reactors are considered. The results of comparative design research of fuel burn-up under conditions of open and closed nuclear fuel cycle are represented.
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Chang, G. S. "Pu-Rich MOX Agglomerate-by-Agglomerate Model for Fuel Pellet Burnup Analysis." In 12th International Conference on Nuclear Engineering. ASMEDC, 2004. http://dx.doi.org/10.1115/icone12-49141.

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In support of potential licensing of the mixed oxide (MOX) fuel made from weapons-grade (WG) plutonium and depleted uranium for use in United States reactors, an experiment containing WG-MOX fuel is being irradiated in the Advanced Test Reactor (ATR) at the Idaho National Engineering and Environmental Laboratory (INEEL). The WG-MOX comprises five percent PuO2 and 95% depleted UO2. Based on the Post Irradiation Examination (PIE) observation, the volume fraction (VF) of MOX agglomerates in the fuel pellet is about 16.67%, and PuO2 concentration of 30.0 = (5 / 16.67 × 100) wt% in the agglomerate. A pressurized water reactor (PWR) unit WG-MOX lattice with Agglomerate-by-Agglomerate Fuel (AbAF) modeling has been developed. The effect of the irregular agglomerate distribution can be addressed through the use of the Monte Carlo AbAF model. The AbAF-calculated cumulative ratio of AGglomerate burnup to U-MAtrix burnup (AG/MA) is 9.17 at the beginning of life (BOL), and decreases to 2.88 at 50 GWd/t. The MCNP-AbAF-calculated results can be used to adjust the parameters in the MOX fuel fission gas release modeling.
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Gupta, Narendra K. "Failure Pressure Simulations for 3013 Inner Can Under Room Fire Conditions." In ASME 2003 Pressure Vessels and Piping Conference. ASMEDC, 2003. http://dx.doi.org/10.1115/pvp2003-2142.

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The 3013 container is widely used for long-term storage and transporting of the fissile material (PuO2) in the DOE complex. The design of 3013 container is governed by the DOE Standard 3013. Thermal and structural analyses were performed to assess the integrity of a closed 3013 inner can assembly during a postulated room fire transient. The inner can assembly is engulfed in a 932°F (500°C) 30-minute long room fire. The fire transient results in a can temperature of about 900°F and an upper bound internal pressure of 641 psi due to the evaporation of moisture and generation of gases in the stored PuO2. The structural analyses show that the inner can assembly can withstand a pressure of 641 psi and meet the ASME B&amp;PV Code stress acceptance criteria for one time accident loading. The failure pressures of the 3013 inner can at can metal temperatures of 900°F, 1200°F, and 1400°F are estimated to be 1435 psi, 1051 psi, and 705 psi respectively.
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Gupta, Narendra K. "Temperature Prediction in 3013 Containers in K-Area Material Storage (KAMS) Facility Using Regression Methods." In ASME 2008 Pressure Vessels and Piping Conference. ASMEDC, 2008. http://dx.doi.org/10.1115/pvp2008-61009.

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3013 containers are designed in accordance with the DOE-STD-3013-2004. These containers are qualified to store plutonium (Pu) bearing materials such as PuO2 for 50 years. DOT shipping packages such as the 9975 are used to store the 3013 containers in the K-Area Material Storage (KAMS) facility at Savannah River Site (SRS). DOE-STD-3013-2004 requires that a comprehensive surveillance program be set up to ensure that the 3013 container design parameters are not violated during the long term storage. To ensure structural integrity of the 3013 containers, thermal analyses using finite element models were performed to predict the contents and component temperatures for different but well defined parameters such as storage ambient temperature, PuO2 density, fill heights, weights, and thermal loading. Interpolation is normally used to calculate temperatures if the actual parameter values are different from the analyzed values. A statistical analysis technique using regression methods is proposed to develop simple polynomial relations to predict temperatures for the actual parameter values found in the containers. The analysis shows that regression analysis is a powerful tool to develop simple relations to assess component temperatures.
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Su, Xianghua, Quanhu Zhang, Suxia Hou, et al. "Nuclear Material Measurement Based on Fast Neutron Multiplicity Counter." In 2020 International Conference on Nuclear Engineering collocated with the ASME 2020 Power Conference. American Society of Mechanical Engineers, 2020. http://dx.doi.org/10.1115/icone2020-16151.

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Abstract Fast neutron multiplicity counting (FNMC) analysis method, as a new non-destructive analysis method for nuclear materials, plays an increasingly important role in the measurement of nuclear material properties. Based on the derivation of the FNMC analytical equation of Pu material, the method of solving the sample parameters was given. By analyzing the mechanism of interaction of neutrons and matter, the model used by Geant4 (version 10.4) software was determined, and a set of three-layer, fast neutron multiplicity counters with six liquid scintillation detectors per layer was constructed. Using the fast neutron multiplicity counter to analyze the measured parameters, the detection efficiency variation was less than 0.4% within the 150g sample mass range, and the PuO2 fluctuation was less than the metal Pu. By studying the detection efficiency and the multiplicity counting rate as a function of sample mass, within the 150g sample mass range, both basically meet the model assumptions of the FNMC analytical equation. The metal Pu and PuO2 samples were set separately, and the FNMC analysis equation was solved. When the sample mass was within 150g, the sample mass solution deviation was less than 10%. The results show that the built-in fast neutron multiplicity counter can better measure Pu sample properties.
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Reports on the topic "Pu02"

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Delegard, Calvin H. Ostwald Ripening and Its Effect on PuO2 Particle Size in Hanford Tank Waste. Office of Scientific and Technical Information (OSTI), 2011. http://dx.doi.org/10.2172/1027695.

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Daniel, G. LITERATURE REVIEW OF PUO2 CALCINATION TIME AND TEMPERATURE DATA FOR SPECIFIC SURFACE AREA. Office of Scientific and Technical Information (OSTI), 2012. http://dx.doi.org/10.2172/1036253.

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Kutepov, A. Theoretical Study on the Compounds NpM2, PuM2, AmM2 (M = Mn, Fe, Ni,Co) and on the System Pu-U. Office of Scientific and Technical Information (OSTI), 2005. http://dx.doi.org/10.2172/928207.

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Zhao, P., A. Kersting, Z. Dai, and M. Zavarin. Stability of Intrinsic Pu colloids in the Presence of Montmorillonite at 25 and 80C: High-fired and freshly prepared PuO2 oxides. Office of Scientific and Technical Information (OSTI), 2013. http://dx.doi.org/10.2172/1093423.

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