RESUMEN
A long counter detector was manufactured by the Institute of Advanced Studies (IEAV) and was characterised in the neutron low scattering room at Brazilian National Ionising Radiation Metrology Laboratory (LNMRI/IRD) to deploy a secondary Standard for neutron fluence. The effective centre was measured experimentally with 252Cf+D2O, 252Cf, 241AmBe and 238PuBe neutron sources, having average energies from 0.55 to 4.16 MeV. The experimental arrangement and detector construction were carefully reproduced in Monte Carlo simulations, and the computational results were found to be in good agreement with those from experiment.
Asunto(s)
Americio/normas , Berilio/normas , Californio/normas , Laboratorios/normas , Neutrones , Plutonio/normas , Monitoreo de Radiación/normas , Protección Radiológica/normas , Americio/análisis , Berilio/análisis , Calibración , Californio/análisis , Método de Montecarlo , Plutonio/análisis , Dosis de RadiaciónRESUMEN
The calibration laboratory revises periodically the dosimetric properties of its calibration fields. For reference neutron fields based on radionuclide sources, it is due to presence of isotopic impurities in the source ingredients. Consequently, in long term, the admixtures and their decay products become significant. Neglecting the impact of such effect leads to inconsistencies between the neutron emission rate observed during the measurements and the emission rate derived from the decay curve of the main isotope. In the Radiation Protection Measurements Laboratory at the National Centre for Nuclear Research the neutron fields of the bare sources of 252Cf, 241AmBe and 239PuBe have been examined for nearly 30 years, regularly, in fixed geometry. Additionally, at the particular point of a calibration bench, determination of neutron fluence rate, ambient dose equivalent rate and its scattered component, total neutron and gamma dose rate, gamma to total dose ratio, radiation quality factor and total tissue kerma are occasionally determined. In this article, we would like to present recently achieved results and their comparison with the measurement data formerly presented. The growth of the neutron emission of 239PuBe source, as well as discrepancies between the decay curves of relevant isotopes and the emission rate of 252Cf and 241AmBe will be presented.
Asunto(s)
Americio/normas , Californio/normas , Laboratorios/normas , Neutrones , Plutonio/normas , Monitoreo de Radiación/normas , Protección Radiológica/normas , Americio/análisis , Calibración , Californio/análisis , Plutonio/análisis , Dosis de RadiaciónRESUMEN
When neutron survey metres are calibrated in neutron fields, the results for room- and air-scattered neutrons vary according to the distance from the source and the size, shape and construction of the neutron calibration room. ISO 8529-2 recommends four approaches for correcting these effects: the shadow-cone method, semi-empirical method, generalised fit method and reduced-fitting method. In this study, neutron scattering effects are evaluated and compared using the shadow-cone and semi-empirical methods for the neutron field of the Korea Atomic Energy Research Institute (KAERI). The neutron field is constructed using a 252Cf neutron source positioned in the centre of the neutron calibration room. To compare the neutron scattering effects using the two correction methods, measurements and simulations are performed using respectively KAERI's Bonner sphere spectrometer (BBS) and Monte Carlo N-Particle code at twenty different positions. Neutron spectra are measured by a europium-activated lithium iodide [6LiI(Eu)] scintillator in combination with the BBS. The calibration factors obtained using each methods show good agreement within 1.1%.
Asunto(s)
Californio/normas , Neutrones , Monitoreo de Radiación/normas , Conteo por Cintilación/instrumentación , Calibración , Californio/análisis , Simulación por Computador , Europio/química , Compuestos de Litio/química , Método de Montecarlo , Dosis de Radiación , República de Corea , Conteo por Cintilación/métodosRESUMEN
A HPGe detector has been used to measure the photon spectra from the majority of radionuclide neutron sources in use at NPL (252Cf, 241Am-Be, 241Am-Li, 241Am-B). The HPGe was characterised then modelled to produce a response matrix. The measured pulse height spectra were then unfolded to produce photon fluence spectra. Changes in the photon spectrum with time from a 252Cf source are evident. Spectra from a 2-year-old and 42-year-old 252Cf source are presented showing the change from a continuum to peaks from long-lived isotopes of Cf. Other radionuclide neutron source spectra are also presented and discussed. The new spectra were used to improve the photon to neutron dose equivalent ratios from some earlier work at NPL with GM tubes and EPDs.
Asunto(s)
Americio/normas , Berilio/normas , Californio/normas , Laboratorios/normas , Neutrones , Fotones , Monitoreo de Radiación/normas , Americio/análisis , Berilio/análisis , Calibración , Californio/análisis , Simulación por Computador , Método de Montecarlo , Dosis de RadiaciónAsunto(s)
Californio , Radioisótopos de Cesio , Radioisótopos , Animales , Calibración , Californio/normas , Californio/provisión & distribución , Radioisótopos de Cesio/provisión & distribución , Radioisótopos de Cesio/uso terapéutico , Humanos , Radioisótopos/normas , Radioisótopos/provisión & distribución , Radioisótopos/uso terapéutico , Radioterapia/normas , Estándares de Referencia , Seguridad/legislación & jurisprudencia , Estados UnidosRESUMEN
The authors established the simulated workplace neutron fields using a 252Cf source surrounded with cylindrical moderators at the Japan Nuclear Cycle Development Institute (JNC), Tokai Works. The moderators are annular cylinders made of polymethyl methacrylate and steel. The neutron energy spectrum at the reference calibration point was evaluated from the calculations by MCNP-4B and the measurements by the Bonner multisphere spectrometer and the hydrogen-filled proportional counters. The calculated neutron spectra were in good agreements with the measured ones. These fields can provide the realistic neutron spectra similar to those encountered around the glove-boxes of the fabrication process of MOX (PuO2-UO2 mixed oxide) fuel.