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.

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...

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...

Response functions of a 3×3 in. NaI detector, which is mainly used in PGNAA applications, have been calculated by using MCNP-4C code. Calculated results are compared with measured data by using standard γ-ray sources to check their accuracy. γ-rays from radioisotope sources were used in the range from 0.081 to 4.438 MeV for this determination. Through the precise modeling of the detector struct...

Response functions of a 3×3 in. NaI detector, which is mainly used in PGNAA applications, have been calculated by using MCNP-4C code. Calculated results are compared with measured data by using standard -ray sources to check their accuracy. -rays from radioisotope sources were used in the range from 0.081 to 4.438 MeV for this determination. Through the precise modeling of the detector structur...