in this research, shielding and criticality safety calculations carried out for interim storage and transportation cask in the tehran research reactor. such dual purpose cask is being designed to the spent fuel elements of research reactors. the monte carlo mcnp5 code calculation was utilized for the criticality safety analysis and origen2.1code was used for shielding calculation. according to ...

The Fukushima accident sequence The earthquake and the subsequent tsunami that devastated part of Northeast Japan on March 11th, 2011, led to a series of accidents in the Fukushima Daichi nuclear plant, constructed and operated by Tokyo Electric Power Company (TEPCO). Only three of the six units of the plant (all of them boiling water reactors, BWR) were operating at that time. The sequence of ...

The Cesium (Cs-137) isotopic concentration due to irradiation of TRIGA Fuel Elements FE(s) is calculated andmeasured at the Atominstitute (ATI) of ViennaUniversity of Technology (VUT). The Cs-137 isotope, as proved burn-up indicator, was applied to determine the burn-up of the TRIGAMark II research reactor FE. This article presents the calculations andmeasurements of the Cs-137 isotope and its ...