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1.
Radiat Prot Dosimetry ; 148(3): 358-65, 2012 Feb.
Artigo em Inglês | MEDLINE | ID: mdl-21498862

RESUMO

A convenient neutron source is made for calibration of neutron survey instruments and personal dosimeters that are used in various nuclear installations such as fuel reprocessing, waste management, fuel fabrication and oil and well logging facilities, etc. This source consists of a bare (241)Am-Be neutron source placed at the centre of a 15-cm radius stainless steel spherical shell filled with distilled water. This paper describes the standardisation of the source at Bhabha Atomic Research Centre, using De Pangher neutron long counter both experimentally and using the Monte Carlo simulation. The ratio of neutron yield of water moderated to the bare (241)Am-Be neutron source was found to be 0.573. From the simulation, the neutron-fluence-weighted average energy of water-moderated (241)Am-Be source (fluence-weighted average energy of 2.25 MeV, dose-weighted average energy of 3.55 MeV) was found to be nearly the same as that of a (252)Cf source (fluence-weighted average energy of 2.1 MeV, dose-weighted average energy of 2.3 MeV). This source can be used for calibration in addition to (252)Cf, to study the variation in response of neutron monitoring instruments.


Assuntos
Amerício/normas , Berílio/normas , Nêutrons , Exposição Ocupacional/análise , Monitoramento de Radiação/normas , Proteção Radiológica/normas , Água/química , Amerício/análise , Berílio/análise , Calibragem , Simulação por Computador , Humanos , Método de Monte Carlo , Exposição Ocupacional/prevenção & controle , Proteção Radiológica/instrumentação , Padrões de Referência
2.
Radiat Prot Dosimetry ; 150(1): 96-100, 2012 Jun.
Artigo em Inglês | MEDLINE | ID: mdl-22128358

RESUMO

A study was done on the tailored neutron energy spectra of (241)Am-Be neutron source due to the effect of moderators. The (241)Am-Be laboratory neutron source was used as the basic source and the emitted spectrum was modified using various neutron moderators. The various moderators used are high-density polythene, light water, heavy water, graphite, (56)Fe, BeO, Be, (6)Li and (7)Li. The absolute energy spectra and fluences in each case are calculated by using the Monte Carlo code FLUKA. This paper describes the simulation work done to design a moderated (241)Am-Be neutron source to produce various energy neutron spectra.


Assuntos
Amerício/análise , Amerício/química , Modelos Químicos , Modelos Estatísticos , Nêutrons , Radiometria/métodos , Simulação por Computador , Método de Monte Carlo , Doses de Radiação , Análise Espectral
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