A bulk shielding experiment was performed at the D-T neutron source FNS, using the assembly simulating shield blanket, vacuum vessel and toroidal field coil (superconducting magnet) of ITER. The objective was to investigate the influence on nuclear parameters due to the nuclei involved in the toroidal field coil and the effect of B4C/Pb. The analysis was performed by MCNP4-A and the DOT3.5 (P5S...

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...

In this work we present a predictive analytical model that encompasses the performance and scaling characteristics of a non-deterministic particle transport application, MCNP. Previous studies on the scalability of parallel Monte Carlo eigenvalue calculations have been rather general in nature [1]. It can be used for the simulation of neutron, photon, electron, or coupled transport, and has fou...

We present new results on neutron and gamma-ray pulse-height distributions (PHDs) measured with liquid scintillators from five plutonium-oxide samples of varying mass and burnup and a Cf isotopic source. We show that the analysis of the pulse-height distributions can be used to easily distinguish the fissile material (plutonium oxide) from the Cf source. Moreover, the slope of the measured puls...

In this research, a methodology consisting of an X-ray tube, one Pyrex-glass pipe, and two NaI detectors was investigated to determine the type flow regimes volume fractions gas-oil-water three-phase flows. Three prevalent patterns—namely annular, stratified, homogenous—in various percentages—10% 80% with step 10%—were simulated by MCNP-X code. After simulating all states collecting signals, Fa...

Introduction: Average glandular dose calculation in mammography with Mo-Rh target-filter and dose calculation for different situations is accurate and fast. Material and Methods: In this research, first of all, x-ray spectra of a Mo target bombarded by a 28 keV electron beam with and without a Rh filter were calculated using the MCNP code. Then, we used the Sobol-Wu parameters to write a FORTRA...

Determining the volume percentages of flows passing through oil transmission lines is one most essential problems in oil, gas, and petrochemical industries. This article proposes a detecting system made Pyrex-glass pipe between an X-ray tube NaI detector to record photons. geometry was modeled using MCNP version X algorithm. Three liquid-gas two-phase flow regimes named annular, homogeneous, st...

The modelling with the Geant4 toolkit of moderated 3He-filled proportional neutron counters is studied. The energy deposition spectra by the neutron capture products in the gas counter is compared with experimental results. On the other hand, efficiency calculation for polyethylene moderated proportional counters are compared with experimental and MCNPX results.Finally, the application of the G...