Quantitative information on photon scattering around brachytherapy sources is needed to develop dose calculation formalisms capable of predicting dosimetric parameters with minimal empiricism. Photon absorption and scatter around brachytherapy sources can be characterized using the tissue attenuation factor, defined as the ratio of dose in water to water kerma in free space. In this study, the ...

A novel multi-source energy harvester based on solar and radioisotope energy sources is designed and simulated in this work. We established the calculation formulas for the short-circuit current and open-circuit voltage, and then studied and analyzed the optimization thickness of the semiconductor, doping concentration, and junction depth with simulation of the transport process of β particles ...

The Message Passing Interface (MPI) technique is an old solution and improvement on the Monte Carlo N-Particle Transport (MCNP) method’s enormous computational time, which has not been evaluated based PHITS code—a recently developed simulation code. We conducted simulations Varian Clinac iX 6MV phase space data from IAEA. Venselaar et al.’s method criteria were used to validate simulation. PC c...

background and purpose: sample size and its determination is one of the most important problems in health researches. calculating sample size for prevalence studies is one of the common questions of sample size topics. minimum sample size with least complexity is desirable in order to achieve the basic goal of these studies. this study aims to compare two formulas of sample size calculation for...

Genetic algorithms (GA) are used to optimize the Fast Neutron Source (FNS) core fuel loading maximize a multiobjective function. The FNS has 150 material locations that can be loaded with one of three different materials resulting in over 3E+71 combinations. individual designs evaluated computationally intensive calls MCNP. To speed up optimization, convolutional neural networks (CNN) trained a...

Prompt-gamma activation analysis (PGAA) has been extended and validated to measure large irregularly shaped samples. The detailed sample geometry was implemented in the MCNP-model of setup accurate matrix-effect corrections were obtained.

Constant improvements of the computational power and methods as well demands accurate reliable measurements for reactor operation safety require a continuous upgrade instrumentation. In particular, nuclear sensors used in fission reactors (research or reactors) fusion facilities are operated under intense mixed neutron gamma-ray fields, need to be calibrated modeled provide selective measuremen...

The Paper describes basic information about MCNP calculations and experimental measurements at the VR-1 reactor and their evaluation. The preparation of calculations and verification of the experiments are integral part of the VR-1 reactor operation. The neutronics calculations and analyses are often necessary condition to gain the approval to experiments realization at the reactor VR-1. The pa...

This document presents the process for a new method developed characterization of delayed gamma-ray radiation fields in pulse reactors like Annular Core Research Reactor (ACRR). The environments used to test this ACRR Central Cavity were various standard irradiation configurations that amounts moderators and shielding. All environment same fission product source energy spectrum. required use si...