A non destructive technique based on gamma spectrometry and application of the Monte Carlo method for detector efficiency calibration, was used to assay radioactive content waste drums. Exploranium GR-130 miniSPEC portable gamma ray spectrometer was used to externally monitor radioactive waste drums containing ion exchange resin waste from the water demineralization system of GRR-1 open pool-ty...

Ionizing radiation effectively reduces the number of common microbial pathogens in fresh produce. However, the efficacy of the process for pathogens internalized into produce tissue is unknown. The objective of this study was to understand gamma irradiation of lettuce leaf structure exposed in a Cs irradiator using MCNP. The simulated Cs irradiator is a self-shielded device, and its geometry an...

This paper describes the mathematical efficiency calibration of the whole-body counter at Forschungszentrum Jülich using Monte Carlo codes and mathematical anthropomorphic phantoms. As a prerequisite for the Monte Carlo simulations a precise model of the 4 high-purity germanium (HPGe) detectors had to be developed. Because the technical data provided by the manufacturer were not sufficient for ...

Boron-neutron capture therapy (BNCT) is an experimental radiation treatment modality used for highly malignant tumor treatments. Prior to irradiation with low energetic neutrons, a B compound is located selectively in the tumor cells. The effect of the treatment is based on the high LET radiation released in the B(n,α)Li reaction with thermal neutrons. BNCT has been used experimentally for brai...

The accurate and efficient simulation of coupled neutron-photon problems is necessary for several important radiation detection applications. Examples include the detection of nuclear threats concealed in cargo containers and prompt gamma neutron activation analysis for nondestructive determination of elemental composition of unknown samples. In these applications, highresolution gamma-ray spec...

The true coincidence effect is studied in two High Purity Germanium (HPGe) detectors for a variety of isotopes, source geometries and to detector configurations, via computational tools based on Monte–Carlo simulations. Τhe upgraded patch MCNP code MCNP–CP the 2018 version PENELOPE, which take into account decay scheme each cascade emitter, are used calculate Full Energy Peak Efficiency (FEPE) ...

We describe the use of the MCNP-PoliMi code to simulate, on an event-by-event basis, the detection of neutrons by organic scintillators. This code keeps track of single neutron interactions, including the collision nucleus, the energy deposited, and the time distribution of collision events. We show that the total pulse-height response is given by the sum of many possible neutron histories, eac...

The axial distribution of energy deposited in bremsstrahlung conversion targets is modelled using the Monte Carlo N -Particle (MCNP) code. Systems comprising a disc-shaped target, segmented axially, and a point source of paraxial, monoenergetic electrons (2, 7, 10, or 14 MeV) are considered. Thick tantalum and aluminium targets and also tantalum targets of optimum thickness are modelled. Energy...