Intensity and resolution effects in converging multichannel collimators for SANS by Monte Carlo simulation

2003 ◽  
Vol 36 (5) ◽  
pp. 1262-1265 ◽  
Author(s):  
A. N. Falcão ◽  
F. M. A. Margaça ◽  
F. G. Carvalho
Keyword(s):  
Computer Simulation ◽  
Monte Carlo Simulation ◽  
Monte Carlo ◽  
Neutron Beam ◽  
Incident Neutron ◽  
Beam Direction ◽  
Channel Axis ◽  
Monte Carlo Computer Simulation ◽  
The Individual ◽  
Incident Neutron Beam

A study of the contribution of the individual channels of a converging multichannel collimator to the operation of the device is carried out by means of a Monte Carlo computer simulation. The simulation shows that the coupling between the divergence of the incident neutron beam and the inclination of the individual CMC channel axis relative to the beam direction modulates the channel performance as far as intensity and resolution of the transmitted neutrons are concerned. While this does not impair in any significant way the usefulness of the device, the results are helpful to the designer.

Monte Carlo simulation of a reactor-based neutron strain scanning diffractometer

2001 ◽  
Vol 34 (5) ◽  
pp. 613-624 ◽  
Author(s):  
C. R. Borlado ◽  
F. J. Mompean ◽  
Ru Lin Peng
Keyword(s):  
Monte Carlo Simulation ◽  
Monte Carlo ◽  
Neutron Beam ◽  
Beam Divergence ◽  
Incident Neutron ◽  
Monte Carlo Code ◽  
Instrumental Resolution ◽  
Simulation Results ◽  
Wavelength Distribution ◽  
Incident Neutron Beam

A Monte Carlo code for the simulation of neutron strain scanning experiments on a reactor-based two-axis diffractometer is described. In order to validate this code, several experiments have been performed. A comparison is made between experimental and simulated results for instrumental resolution, primary beam divergence and wavelength distribution in the incident neutron beam. Finally, the application of the simulation results to the analysis of a real neutron strain scanning experiment is outlined.

Monte Carlo computer simulation of small clusters of methane, ethane, and their mixture

1997 ◽  
Vol 106 (4) ◽  
pp. 1593-1599 ◽  
Author(s):  
Aleksey Vishnyakov ◽  
Elena M. Piotrovskaya ◽  
Elena N. Brodskaya
Keyword(s):  
Computer Simulation ◽  
Monte Carlo ◽  
Monte Carlo Computer Simulation ◽  
Small Clusters

Electricity supplier selection by a household in the Czech Republic in 2017 and 2018 – Monte Carlo simulation approach

2019 ◽  
Author(s):  
Martina Kuncova
Keyword(s):  
Monte Carlo Simulation ◽  
Monte Carlo ◽  
Czech Republic ◽  
Electricity Market ◽  
Electricity Consumption ◽  
Point Of View ◽  
The Czech Republic ◽  
Extra Effort ◽  
The Individual ◽  
Monte Carlo Simulation Model

The situation on the electricity retail market in the Czech Republic is not clear because of the number of suppliers and its products. Although the information about the prices for the electricity consumption for households is available on the web and each household can change the supplier nearly with no extra effort and cost, households are still often not familiar with the individual price items of the products. In this article the analysis of the Czech electricity market from the distribution rate D25d point of view is made for the years 2017-2018 when the household annual consumption is simulated via Monte Carlo simulation model. The aim of this paper is to select such a supplier and product that minimizes the total costs of the electricity for a household for the selected distribution rate and compare it with the results from the previous years.

Monte Carlo computer simulation of copper clusters

1999 ◽  
Vol 60 (4) ◽  
pp. 3053-3057 ◽  
Author(s):  
Şakir Erkoç ◽  
Riad Shaltaf
Keyword(s):  
Computer Simulation ◽  
Monte Carlo ◽  
Monte Carlo Computer Simulation ◽  
Copper Clusters

THE SPECTRUM OF NEUTRONS FROM THE IRRADIATION OF URANIUM BY 14-MEV NEUTRONS

1961 ◽  
Vol 39 (7) ◽  
pp. 957-966 ◽  
Author(s):  
R. L. Clarke
Keyword(s):  
Inelastic Scattering ◽  
Cross Section ◽  
Neutron Beam ◽  
Strong Evidence ◽  
Direct Interaction ◽  
Natural Uranium ◽  
Incident Neutron ◽  
Absolute Yield ◽  
Time Of Flight Method ◽  
Incident Neutron Beam

The spectrum and absolute yield of neutrons resulting from 14-Mev neutrons incident on natural uranium was observed at 90°± 16 to the incident neutron beam by a time-of-flight method. Further observations of the spectrum from 9 to 13.5 Mev were made for scattering angles at 30° and 60°. In addition to the expected neutrons resulting from evaporation and fission, strong evidence is seen for direct interaction inelastic scattering. The (n,n′) cross section is estimated to be 150 ± 70 millibarns.

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