The k(0)-standardization method on the (241)Am-Be isotopic neutron source has been studied and developed. In this paper, the characteristics of the neutron spectrum in an isotropic neutron field of (241)Am-Be isotopic neutron sources was experimentally determined by dual monitor method using measured cadmium ratios of (197)Au(n, γ)(198)Au and (98)Mo(n, γ)(99)Mo(β(-))(99m)Tc reactions. Applicati...

This work aimed to determine the irradiator thermal (under-cadmium) and fast (over-cadmium) neutron fluxes, of the Nuclear Experimental Laboratory of the Nuclear Engineering Center (CNEN-IPEN, São Paulo, Brazil), and the possibility of this irradiator use for Neutron Activation Analysis (NAA), by the absolute method. To establish the facility specifications, the neutron flux values along the ir...

Background: To evaluate the effects of hyperthermia (HT) on the frequency of chromosomal aberrations induced by a low dose of neutron or γ-rays in human peripheral blood lymphocytes. Materials and Methods: Blood samples were exposed to HT (41.5°C for 30 and 60min, 43°C for 15 and 30min), 10 cGy neutron or γ-rays, HT + neutron/γ, and neutron/γ + HT. After standard cell culture, harvestin...

Background: Neutron contamination is produced in electron beams of linac when tooth or dental materials are located in the path of beam. Objective: This study aims to determine the neutron dose contamination from different dental restoration materials in electron mode of a linac. Material and Methods: In this experimental study, the neutron dose contamination was calculated in the p...

 ABSTRACT Background: With respect to the difference in the interaction of thermal neutron and X rays with matter, using two radiography systems of thermal neutron and X rays will yield highly valuable information for studying the inner structure of biologic samples. Methods: The high sensitivity of thermal neutron to hydrogen, in particular, has led to recognizing this system as a useful tool ...

The distribution of neutron population in nuclear reactor is described by using transport equations. One of possible approximations of neutron transport equation is given by the neutron diffusion equation. The paper presents numerical solution method of one group neutron diffusion equation with one group of delayed neutrons.

beryllium chemical combination has a considerable effect on the design and fabrication of the241am9be neutron source. in this investigation the beryllium combinations were studied as a generator ofneutrons with various mass percentage, and the neutron yields were also calculated using the results of thealice and srim codes calculations per unit incident charge. the neutron yields of beryllium ...