Neutron coincidence counting is a technique widely used for qualitative and quantitative analysis of nuclear material. Because different isotopes possess different coincident neutron characteristics, the coincident neutron signature can be used to identify and quantify a given material. In an effort to identify unknown nuclear samples in field inspections, a new portable neutron coincidence cou...

Structural properties of materials irradiated with gamma-rays, such as mechanical and physical properties, may be modified or reduced depending on the displacement damages. Apart from increasing decreasing that property, damage desirable not. This study investigates effects sterilization by gamma radiation polycaprolactone (PCL) scaffolds. Using a code-based simulation method, MCNPX provides in...

A novel simulation to calculate the neutronic parameters of TRIGA 2000 reactor using plate-type fuel has been performed. The plate used was produced by Indonesian Nuclear Industry (PT INUKI) with U3Si2-Al material. Neutronic based on INUKI’s dimension and current TRIGA’s configuration were simulated MCNPX. performed modeling complete reactor’s a fresh core state. We obtained kinetic parameter v...

radiotherapy dose calculations can be evaluated by monte carlo (mc) simulations with acceptable accuracy for dose prediction in complicated treatment plans. in this work, standard, livermore and penelope electromagnetic (em) physics packages of geant4 application for tomographic emission (gate) 6.1 were compared versus monte carlo n-particle extended (mcnpx) 2.6 in simulation of 6 mv photon lin...

This work illustrates a methodology based on photon interrogation and coincidence counting for determining the characteristics of fissile material. The feasibility of the proposed methods was demonstrated using the Monte Carlo-based MCNPX/MCNPPoliMi code system capable of simulating the full statistics of the neutron and photon field generated by the photon interrogation of fissile and non-fiss...

The Supercritical-Water-Cooled Reactor (SCWR) is the Generation IV reactor concept most closely related to current light water reactors (LWRs). The SCWR builds on the vast experience with today’s LWRs and supercritical coal-fired power plants. Water at supercritical state is used as moderator and coolant, and reaches a temperature of about 500 ◦C at the core outlet, which enables a much higher ...

Expected backgrounds in the final accelerator-to-target region of the European Spallation Source, to be built in Lund, Sweden, have been calculated using the MCNPX program. We consider the effects of losses from the beam, both along the full length and localised at the bending magnets, and also backsplash from the target. The prompt background is calculated, and also the residual dose, as a fun...

Objective: Different categories are available for estimating of radiation dose. Radioisotopes with the same energy and almost the same physical properties have similar effects. Monte Carlo technique is a computerized method based on mathematical simulation of physical processes. The main purpose of this study is to show that beta particles are not able to penetrate deep into the water. also dif...