Nuclear Reactors
Mostrando 1-12 de 54 artigos, teses e dissertações.
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1. Analysis of Residual Stress by the Hole-Drilling Method and Hardness in Dissimilar Joints of Austenitic Stainless Steel AISI 316L and Inconel 718 Alloy by Autogenous GTAW Process
Stainless steel and nickel alloy have high corrosion resistance in high-temperature environments due to the high Cr content present in their chemical composition, being widely used in components of nuclear reactors, petrochemical industries, etc. Through proper processes and procedures, it becomes possible to join these alloys. However, this union can genera
Mat. Res.. Publicado em: 02/12/2019
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2. Desdoblamiento de la transformación martensítica en un acero F82H de activación neutrónica reducida
ABSTRACT One of the most promising solutions to global energy supply is nuclear fusion. This process, which is implemented in nuclear fusion reactors (from which one of the first designs was the Tokamak), involves deuterium-tritium plasmas at very high temperature, confined in vacuum chambers of toroidal shape under the influence of strong magnetic fields. T
Matéria (Rio J.). Publicado em: 19/07/2018
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3. Estudio del comportamiento en enfriamiento continuo del acero martensítico ferrítico de activación reducida F82H
ABSTRACT 9% Cr martensitic-ferritic steels are currently the privileged candidates to manufacture structural components of the so-called Generation IV nuclear fission reactors, because they exhibit very good thermophysical and mechanical properties under neutron irradiation. Along with them, the so-called Reduced Activation Ferritic-Martensitic steels (RAFM�
Matéria (Rio J.). Publicado em: 19/07/2018
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4. Diagrama de fases experimental Fe-Sn-Zr. Nuevos resultados del corte isotérmico de 800 °C
ABSTRACT The Zr-based alloys are extensively applied in the field of nuclear technology. Alloyed with Sn and Fe, Zr is the main element in the zircaloy-type alloys, currently vastly used as structural elements and as containers of burnable elements in nuclear reactors. This ternary metallurgical system is also a component of more recently developed alloys su
Matéria (Rio J.). Publicado em: 19/07/2018
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5. Identificación de precipitados en aleaciones U-Nb-Zr tratadas térmicamente a 850 ºC
ABSTRACT At the present, the international goal is to develop and qualify a very high U density fuel for high flux research reactors. The selected U-alloy must present an isotropic crystalline structure at the end of the fuel fabrication process. These types of structures exhibit stable behavior under irradiation. In particular, it is wanted to retain as met
Matéria (Rio J.). Publicado em: 19/07/2018
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6. Creep Parameters and Dislocation Substructure in AISI 316 Austenitic Stainless Steel From 600ºC to 800ºC
Stainless steels are well known by their corrosion resistance. The austenitic types, in particular, are also applied as structural components in engineering systems operating at high temperatures such as nuclear reactors, petrochemical furnaces and turbines. For these applications operational temperatures may go up to 800ºC. Under constant load applications
Mat. Res.. Publicado em: 06/07/2017
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7. International Co-operation in Science and Technology: Concepts, Politics, and Dynamics in the Case of Argentine-Brazilian Nuclear Co-operation
Abstract Abstract: This article discusses the political dynamic of agenda-setting in the subfield of international nuclear co-operation, within an analytical framework that integrates the literature on international co-operation in science and technology, international nuclear co-operation, and foreign policy analysis. It presents the emblematic case of Arg
Contexto int.. Publicado em: 2016-08
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8. Interdiffusion studies on hot rolled U-10Mo/AA1050
The U-Mo alloys are investigated with the goal to become nuclear material to fabricate high-density fuel elements for high performance research reactors. The enrichment level (20% 235U) suggests that the U-Mo alloys should be between 6 to 10 wt. (%), which can reach up to 9 gU.cm-3 in fuel density. Nevertheless, the U-Mo alloys are very reactive with Al. Int
Mat. Res.. Publicado em: 02/10/2012
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9. Condições de contorno albedo para cálculos globais de reatores nucleares térmicos com o modelo de ordenadas discretas a dois grupos de energia / Albedo boundary conditions for thermal nuclear reactors global calculations with two energy group discrete ordinates formulations
Como eventos de fissão induzida por nêutrons não ocorrem nas regiões nãomultiplicativas de reatores nucleares, e.g., moderador, refletor, e meios estruturais, essas regiões não geram potência e a eficiência computacional dos cálculos globais de reatores nucleares pode portanto ser aumentada eliminando os cálculos numéricos explícitos no interior
IBICT - Instituto Brasileiro de Informação em Ciência e Tecnologia. Publicado em: 28/11/2011
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10. Aplicação de métodos não destrutivos para qualificação de combustíveis tipo dispersão de U308-Al e U3Si2-Al no reator IEA-R1 / Application of non-destructive methods for qualification of the U3O8-Al and U3Si2-Al dispersion fuels in the IEA-R1 Reactor
IPEN/CNEN-SP manufactures fuels to be used in its nuclear research reactor the IEA-R1. To qualify those fuels, it is necessary to check if they have a good performance under irradiation. As Brazil doesnt have nuclear research reactors with high neutron fluxes, or suitable hot cells for carrying out post-irradiation examination of nuclear fuels, IPEN/CNEN-SP
IBICT - Instituto Brasileiro de Informação em Ciência e Tecnologia. Publicado em: 24/11/2011
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11. Procedimento de fabricação de elementos combustível a base de dispersão com alta concentração de urânio / Fabrication procedures for manufacturing high uranium concentration dispersion fuel elements
IPEN-CNEN/SP developed the technology to produce the dispersion type fuel elements for research reactors and made it available for routine production. Today, the fuel produced in IPEN-CNEN/SP is limited to the uranium concentration of 3.0 gU/cm3 for U3Si2-Al dispersion-based and 2.3 gU/cm3 for U3O8-Al dispersion. The increase of uranium concentration in fuel
IBICT - Instituto Brasileiro de Informação em Ciência e Tecnologia. Publicado em: 11/11/2011
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12. Implementation and qualification of neutronic calculation methodology in subcritical reactors driven by external neutron sources and applications / Implementação e qualificação de metodologia de cálculos neutrônicos em reatores subcríticos acionados por fontes externa de nêutrons e aplicações
This works had as goal to investigate calculational methodologies on subcritical source driven reactor, such as Accelerator Driven Subcritical Reactor (ADSR) and Fusion Driven Subcritical Reactor (FDSR). Intense R&D has been done about these subcritical concepts, mainly due to Minor Actinides(MA) and Long Lived Fission Products(LLFP) transmutation possibilit
IBICT - Instituto Brasileiro de Informação em Ciência e Tecnologia. Publicado em: 19/08/2011