Background: This study aims to calculate the air-kerma strength (SK), the dose rate constant (∧) and the dose rate profiles of a Gammamed 12i Ir-192 source by using the Monte Carlo technique and to compare the dose rate values with those calculated by the Abacus HDR treatment planning system (TPS). Materials and Methods: Air-kerma strength (in units of U; 1 U= μGy m2 h-1) and the dose ra...

Commercially there is a growing interest in applications of neutrons. Currently the majority of neutron sources are based at research institutions from either reactors or spallation sources. Smaller portable sources contain either fissile isotope or sealed fusors are available, although they either use or produce tritium, or other long lived decay products. As an alternative to the large facili...

A great number of radioactive cesium were released into sea water after Fukushima Accident. We modified the Regional Oceanic Modelling System (ROMS) to reproduce the dispersion process of the cesium in oceans. The simulated water concentration was in good agreement with observation. In order to explore the nuclear impact of these contaminant in ocean, we established a food web model to calculat...

We measured neutron-induced reaction cross-sections for Y(n,γ)Y and Y(n,α)Rb reactions with the average neutron energy region from 7.45 to 24.83 MeV by an activation and off-line γ-ray spectrometric technique using the MC-50 Cyclotron at Korea Institute of Radiological and Medical Sciences. The neutron-induced reaction cross-sections of Y as a function of neutron energy were taken from the TEND...

Since 2005 the nodal diffusion based code system, OSCAR-3, was used for reactor support calculations of operational cycles High Flux Reactor in Petten, The Netherlands. OSCAR uses a two-step deterministic calculation, which homogenized cross sections are generated lattice environments using neutron transport simulations, and then passed to core simulator model full reactor. Limitations OSCAR-3 ...

The use of germanium detectors for the identification and quantification of radionuclides in unknown and non-standard counting geometries has increased in the recent past with the need to clean up and verify sites used for radionuclide processing, smuggling detection and other purposes. The calculation of the amount of radionuclide present requires a knowledge of the efficiency of the detector ...