The verification and validation (V&V) of the Serpent 2 Monte Carlo code for 3-D reactor dosimetry applications is being carried out at VTT. Two code-to-code computational benchmark cases were calculated by MCNP 2. efficiency different variance reduction techniques was appraised. part currently includes two experimental benchmarks from SINBAD database: Pool Critical Assembly-Pressure Vessel ...

In this paper, we present a useful Monte Carlo (MC)-based methodology that can be utilized to calculate the absorbed dose and initial levels of complex DNA damage (such as double strand breaks-DSBs) in case an environmental ionizing radiation (IR) exposure incident (REI) i.e., nuclear accident. Our objective is assess doses by isolating only one component total released environment after REI wi...

The dose calculation accuracy of a commercial pencil beam IMRT planning system is evaluated by comparison with Monte Carlo calculations and measurements in an anthropomorphic phantom. The target volume is in the right lung and mediastinum and thus significant tissue inhomogeneities are present. The Monte Carlo code is an adaptation of the MCNP code and the measurements were made with TLD and fi...

Abstract The Cs 2 LiYCl 6 :Ce crystal (CLYC) is an inorganic scintillator which has been developed for the γ-ray and neutron measurement with high detection efficiency, resolution, no need unfolding technique. To enhance of fast neutron, CLYC 7 Li-enrichment (CLYC7) developed. In this work, response CLYC7 detector to obtained using 137 calibration source calculated Monte Carlo N-Particle transp...