Mcnp Code
Mostrando 1-12 de 16 artigos, teses e dissertações.
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1. 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
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2. Bremsstrahlung de elétrons no microtron do IFUSP: medidas, simulação e proposta de aplicação ao estudo da ressonância fluorescente nuclear / Electron Bremssthahlung in the IFUSP microton: measurements, simulation and proposal for a nuclear resonance fluorescence observation setup
The results of the first experiments carried out in the new electron accelerator of the Linear Accelerator Laboratory (LAL) of the Physics Institute of Universidade de São Paulo are reported here. A 1.9 MeV beam line, which allows the use of the injector beam for experimental physics, was added to the original accelerator design. Electron bremsstrahlung spe
IBICT - Instituto Brasileiro de Informação em Ciência e Tecnologia. Publicado em: 20/06/2011
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3. Aplicabilidade e validação do Geant4 para fótons e elétrons em radioterapia / GEANT4 applicability and validation to Photons and Electrons in Radiotherapy
Due to the increasing use of ionizing radiation in medical applications, in recent decades, the simulation codes for radiation interacting with matter, based on Monte Carlo Method, have been constantly adapted to applications in medical physics. TheMonte Carlo method is a statisticalmethod of numerical simulation of problems using essentially a sequence of r
IBICT - Instituto Brasileiro de Informação em Ciência e Tecnologia. Publicado em: 14/06/2011
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4. Avaliação da metodologia de cálculo de dose em microdosimetria com fontes de elétrons com o uso de código MCNP5 / Evaluation of the methodology for dose calculation in microdosimetry with electrons sources using the MCNP5 code
Este trabalho realizou uma comparação entre alguns dos principais códigos de transporte que empregam a abordagem estocástica de Monte Carlo para aplicação em cálculos dosimétricos em Medicina Nuclear. Foram analisados com detalhes os diversos modelos físicos e numéricos utilizados pelo código MCNP5 em relação códigos como Penelope e EGS. A iden
IBICT - Instituto Brasileiro de Informação em Ciência e Tecnologia. Publicado em: 26/11/2010
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5. Projeto e construção de placas espalhadoras e degradadoras de energia para uso em radioterapia com feixes de elétrons para doenças de pele / Project and construction of energy degrading and scattering plates for electron beam radiotherapy for skin diseases
There are many radiosensitive epidermotropics diseases such as mycosis fungoids and the syndrome of Sézary, coetaneous neoplasics originated from type T lymphocytes. Several studies indicate the eradication of the disease when treated with linear accelerators emitting electron beams with energies between 4 to 10 MeV. However, this treatment technique presen
IBICT - Instituto Brasileiro de Informação em Ciência e Tecnologia. Publicado em: 24/06/2010
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6. Retrieval of GammaCell 220 irradiator isodose curves with MCNP simulations and experimental measurements
Gamma irradiator facilities can be used in a wide range of applications such as biological and chemical researches, sterilization of medical devices and products. Dose mapping must be performed in these equipments in order to establish plant operational parameters, as dose uniformity, source utilization efficiency and maximum and minimum dose positions. The
Brazilian Journal of Physics. Publicado em: 2010-03
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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. Avaliação do fluxo de nêutrons e da taxa de dose durante o funcionamento nominal do ITER
The ITER (International Thermonuclear Experimental Reactor) is a tokamak with elongated plasma and single null poloidal divertor. The nominal inductive operation produces a DT fusion power of 500 MW for a burn length of 400 s, with a pulse repetition period as short as 1,800 s. The main goal is to exhibit the use of fusion energy for peaceful purposes. The t
IBICT - Instituto Brasileiro de Informação em Ciência e Tecnologia. Publicado em: 14/07/2008
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9. Aplicação de método Monte Carlo para cálculos de dose em folículos tiroideanos
The Monte Carlo method is an important tool to simulate radioactive particles interaction with biologic medium. The principal advantage of the method when compared with deterministic methods is the ability to simulate a complex geometry. Several computational codes use the Monte Carlo method to simulate the particles transport and they have the capacity to s
Publicado em: 2008
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10. Desenvolvimento de um modelo computacional para avaliaÃÃes dosimÃtricas em ratos
Rats are commonly used as experimental models in preclinical tests in Nuclear Medicine. Therefore, it is of great importance to accomplish precise absorbed dose estimates in these small animals, for explanation and control of potential radiation toxicity, observed during the tests. In this work, a tomographic model of an adult male Wistar rat was developed s
Publicado em: 2008
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11. AvaliaÃÃo da eficÃcia do avental equivalente a 0,5 mm de chumbo em tomografia por emissÃo de PÃsitrons atravÃs de simulaÃÃes Monte Carlo / Evaluation of the effectiveness of 0.5 mm lead equivalent apron in positron emission tomography by Monte Carlo simulation
In Positron Emission Tomography (PET), medical staff is exposed to 511 keV photons, which is a result of the positron-electron annihilation process. This energy is about four times the 140 keV commonly found in studies based on Single Photon Emission Computed Tomography (SPECT). Despite these different energy levels, 0.5 mm lead equivalent aprons have being
Publicado em: 2008
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12. 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