Neutron Flux
Mostrando 1-12 de 32 artigos, teses e dissertações.
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1. A Nodal-iterative Technique for Criticality Calculations in Multigroup Neutron Diffusion Models
ABSTRACT In this work, a nodal and iterative technique to evaluate the effective multiplication factor as well as the neutron flux, in multigroup diffusion problems, is presented. An iterative scheme, similar to the source iteration method, is implemented to decouple the system of differential equations which is the fundamental mathematical model. Then, anal
Trends in Computational and Applied Mathematics. Publicado em: 2022
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2. An Extended Linear Discontinuous Method for One-group Fixed Source Discrete Ordinates Problems with Isotropic Scattering in Slab Geometry
RESUMO Atualmente, a obtenção de uma solução numérica precisa para problemas de fonte fixa em ordenadas discretas é relevante em muitas áreas da engenharia e das ciências. Neste trabalho, estendemos o método híbrido Elementos Finitos-Espectro Nodal (FEM-SGF), que foi originalmente desenvolvido para resolver problemas de autovalores de difusão, par
TEMA (São Carlos). Publicado em: 30/05/2019
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3. Caracterização dos campos neutrônicos obtidos por meio de armadilha de nêutrons no interior do núcleo do reator nuclear IPEN/MB-01 / Neutronic characterization of the fields obtained by means of neutron traps inside the nuclear reactor core IPEN/MB-01
Este trabalho apresenta os resultados dos valores de fluxo de nêutrons obtidos a partir da implantação de uma armadilha de nêutrons no núcleo do Reator IPEN/MB-01. Foram analisadas várias configurações de armadilhas implantadas no núcleo do reator IPEN/MB-01 de forma a se eleger a armadilha mais eficiente. Para a caracterização energética, foram
IBICT - Instituto Brasileiro de Informação em Ciência e Tecnologia. Publicado em: 08/06/2011
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4. Desenvolvimento e implementação de um novo sistema pneumático de transferência para irradiação de materiais no reator IEA-R1 / Development and implementation of a new pneumatic transfer system for materials irradiation at IEA-R1 reactor
Pneumatic Transfer Systems (PTS) are classified as mechanical equipment largely operated all over the world for transport of a huge sort of objects, samples and materials located at nearly terminals or even at separated ones. System applicability is often recognized in many activities, such as medicine (hospital settings, clinical analysis labs), industry (s
Publicado em: 2011
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5. Desenvolvimento de um simulador antropomórfico para simulação e medidas de dose e fluxo de nêutrons na instalação para estudos em BNCT / Development of an anthropomorfic simulator for simulation and measurements of neutron dose and flux in the facility for BNCT studies
A instalação do IPEN para pesquisas em BNCT (Terapia por Captura de Nêutrons em Boro) utiliza o canal de irradiação número 3 do reator IEA-R1, no qual tem-se um campo misto de radiação nêutrons e gama. As pesquisas em andamento necessitam que o campo de radiação, na posição de irradiação de amostra, tenha na composição os nêutrons térmicos
IBICT - Instituto Brasileiro de Informação em Ciência e Tecnologia. Publicado em: 11/08/2010
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6. DIGITAL SIMULATION SYSTEM OF NEUTRON PARAMETERS OF THE TRIGA IPR-R1 NUCLEAR RESEARCH REACTOR / SISTEMA DIGITAL PARA SIMULAÇÃO DOS PARÂMETROS NEUTRÔNICOS DO REATOR NUCLEAR DE PESQUISA TRIGA IPR-1
The IPR-R1 TRIGA Mark I nuclear research reactor, at the Nuclear Technology Development Center (CDTN), is a pool type reactor cooling by light water. TRIGA reactors (Training, Research, Isotope, General Atomics) were designed for research, training and radioisotope production. The International Atomic Energy Agency (IAEA) recommends the use of safety and fri
IBICT - Instituto Brasileiro de Informação em Ciência e Tecnologia. Publicado em: 29/07/2010
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7. Flux and dose rate evaluation of iter system using MCNP5
The International Thermonuclear Experimental Reactor (ITER) will perform Deuterium-Tritium (DT) plasma experiments and the neutrons production rate at 14.1 MeV will achieve the level of 10(13) n.cm-2.s-1. In this work, the neutron flux and the dose rate during ITER operation has been calculated using the one-dimensional model of the Monte Carlo code MCNP5 an
Brazilian Journal of Physics. Publicado em: 2010-03
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8. Thermal and epithermal neutron fluence rates in the irradiation facilities of the TRIGA IPR-R1 nuclear reactor
The TRIGA IPR-R1 nuclear reactor at the Centro de Desenvolvimento da Tecnologia Nuclear CDTN/CNEN, Belo Horizonte, Brazil, has three irradiation facilities: a rotary specimen rack outside the reactor core with 40 irradiation channels which provide large scale isotope irradiation; the central tube placed at the center of the reactor core which permits sample
Brazilian Journal of Physics. Publicado em: 2010-03
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9. Measurements of the neutron spectrum energy in the IPEN/MB-01 reactor core
This work presents the results of neutron spectrum measurements at central position of the IPEN/MB-01 reactor core. For this purpose has been used several activation foils (Au, Sc, U, Mg, Ti, Ni, and In Foils) that have been irradiated at central position of the reactor core (standard rectangular configuration 28 × 26 fuel rods) in the maximum power level (
Brazilian Journal of Physics. Publicado em: 2009-03
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10. Calibração dos canais nucleares do Reator IPEN/MB-01, obtida a partir da medida da distribuição espacial do fluxo de nêutrons térmicos no núcleo do reator através da irradiação de folhas de ouro infinitamente diluídas / CALIBRATION OF THE NUCLEAR POWER CHANNELS OF THE IPEN/MB-01 REACTOR OBTAINED FROM THE MEASUREMENTS OF THE SPATIAL THERMAL NEUTRON FLUX DISTRIBUTION IN THE REACTOR CORE THROUGH THE IRRADIATION OF INFINITELY DILUTED GOLD FOILS
Several nuclear parameters are obtained through the gamma spectrometry of targets irradiated in a research reactor core and this is the case of the activation foils which make possible, through the measurements of the activity induced, to determine the neutron flux in the place where they had been irradiated. The power level operation of the reactor is a par
Publicado em: 2008
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11. Medida da secção de choque térmica e da integral de ressonância da reação 41K(n,)42K / Thermal cross-section and resonance integral of the 41K(n,g)42K(n,g)43K reaction measurement
Pellets of potassium nitrate were irradiated in the IPEN/CNEN-SP (Instituto de Pesquisas Energeticas e Nucleares, Comissao de Energia Nuclear, Sao Paulo, SP) IEAR1m reactor core operating at 2 MW power in order to determine the 41K(n,g)42K reaction thermal cross-section and resonance integral. The neutron flux was monitored by Au-Al alloy foils, and the West
Publicado em: 2008
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12. Caracterização do campo de nêutrons na instalação para estudo em BNCT no Reator IEA-R1 / NEUTRON FIELD CHARACTERIZATION IN THE INSTALLATION FOR BNCT STUDY IN THE IEA R1 REACTOR.
This work aims to characterize the mixed neutron and gamma field, in the sample irradiation position, in a research installation for Boron Neutron Capture Therapy (BNCT), in the IPEN IEA-R1 reactor. The BNCT technique has been studied as a safe and selective option in the treatment of resistant cancerigenous tumors or considered non-curable by the convention
Publicado em: 2008