On the use of the Serpent Monte Carlo code for few-group cross section generation

2011 ◽  
Vol 38 (6) ◽  
pp. 1399-1405 ◽  
Author(s):  
E. Fridman ◽  
J. Leppänen
Keyword(s):  
Monte Carlo ◽  
Cross Section ◽  
Monte Carlo Code

Application of continuous-energy Monte Carlo code as a cross-section generator of BWR core calculations

2005 ◽  
Vol 32 (8) ◽  
pp. 857-875 ◽  
Author(s):  
Masayuki Tohjoh ◽  
Masato Watanabe ◽  
Akio Yamamoto
Keyword(s):  
Monte Carlo ◽  
Cross Section ◽  
Monte Carlo Code ◽  
Continuous Energy

scholarly journals Microscopic cross section calculation methodology in the Serpent 2 Monte Carlo code

2021 ◽  
Vol 164 ◽  
pp. 108603
Author(s):  
Antti Rintala ◽  
Ville Valtavirta ◽  
Jaakko Leppänen
Keyword(s):  
Monte Carlo ◽  
Cross Section ◽  
Monte Carlo Code ◽  
Calculation Methodology

Wolf-Rayet Wind Models: Photometric and Polarimetric Variability

1999 ◽  
Vol 169 ◽  
pp. 57-61
Author(s):  
Cláudia V. Rodrigues ◽  
Antônio Mário Magalhães
Keyword(s):  
Monte Carlo ◽  
Cross Section ◽  
Broad Band ◽  
Variable Structure ◽  
Band Intensity ◽  
Stokes Parameters ◽  
Monte Carlo Code ◽  
Photometric Variability ◽  
Random Variation

AbstractWe have modelled the observed random variation in broad band intensity and polarization of some isolated Wolf-Rayet stars assuming that their winds have localized, enhanced density regions (blobs). Our model is based on a Monte Carlo code that treats all Stokes parameters of the radiation bundle. This study indicates that the blobs must have sizes comparable to the stellar dimension and be near the base of the envelope. These blobs can be interpreted as a variable structure of large geometric cross section causing the observed polarimetric and photometric variability.

MONTE CARLO CALCULATION OF SLOW ELECTRON BEAM TRANSPORT IN SOLIDS: REFLECTION COEFFICIENT THEORY IMPLICATIONS

2012 ◽  
Vol 26 (04) ◽  
pp. 1150022 ◽  
Author(s):  
A. BENTABET
Keyword(s):  
Monte Carlo ◽  
Electron Transport ◽  
Reflection Coefficient ◽  
Penetration Depth ◽  
Cross Section ◽  
Monte Carlo Code ◽  
Slow Electron ◽  
Backscattering Coefficient ◽  
Transport Cross Section ◽  
The Mean

The reflection coefficient theory developed by Vicanek and Urbassek showed that the backscattering coefficient of light ions impinging on semi-infinite solid targets is strongly related to the range and the first transport cross-section as well. In this work and in the electron case, we show that not only the backscattering coefficient is, but also most of electron transport quantities (such as the mean penetration depth, the diffusion polar angles, the final backscattering energy, etc.), are strongly correlated to both these quantities (i.e. the range and the first transport cross-section). In addition, most of the electron transport quantities are weakly correlated to the distribution of the scattering angle and the total elastic cross-section as well. To make our study as straightforward and clear as possible, we have projected different input data of elastic cross-sections and ranges in our Monte Carlo code to study the mean penetration depth and the backscattering coefficient of slow electrons impinging on semi-infinite aluminum and gold in the energy range up to 10 keV. The possibility of extending the present study to other materials and other transport quantities using the same models is a valid process.

scholarly journals CASINO: A new monte carlo code in C language for electron beam interactions-part II: Tabulated values of the mott cross section

Scanning ◽  
1997 ◽  
Vol 19 (1) ◽  
pp. 20-28 ◽  
Author(s):  
Dominique Drouin ◽  
Pierre Hovington ◽  
Raynald Gauvin
Keyword(s):  
Monte Carlo ◽  
Electron Beam ◽  
Cross Section ◽  
Monte Carlo Code ◽  
C Language

A Method of Optimized Utilization of Point-Wise Data Format in Monte Carlo Code

2010 ◽  
Author(s):  
Yuxuan Liu ◽  
Ganglin Yu ◽  
Kan Wang
Keyword(s):  
Monte Carlo ◽  
Cross Section ◽  
Cross Sections ◽  
Search Algorithm ◽  
Reactor Core ◽  
Hash Table ◽  
Monte Carlo Code ◽  
Data Format ◽  
Section Data ◽  
Grid Interval

Monte Carlo codes are powerful and accurate tools for reactor core calculation. Most Monte Carlo codes use the point-wise data format, in which the data are given as tables of energy-cross section pairs. When calculating the cross sections at an incident energy value, it should be determined which grid interval the energy falls in. This procedure is repeated so frequently in Monte Carlo codes that its contribution in the overall calculation time can become quite significant. In this paper, the time distribution of Monte Carlo method is analyzed to illustrate the time consuming of cross section calculation. By investigation on searching and calculating cross section data in Monte Carlo code, a new search algorithm called hash table is elaborately designed to substitute the traditional binary search method in locating the energy grid interval. The results indicate that in the criticality calculation, hash table can save 5%∼17% CPU time, depending on the number of nuclides in the material, as well as complexity of geometry for particles tracking.

Newly Developed Coupling Scheme in RMC With Internal Thermal Feedback and OTF Doppler-Broadening Method

2017 ◽  
Author(s):  
Ouwen Yexin ◽  
Shanfang Huang ◽  
Kan Wang
Keyword(s):  
Monte Carlo ◽  
Steady State ◽  
Cross Section ◽  
Large Scale ◽  
Nuclear Reactor ◽  
Simulation Analysis ◽  
Coupling Scheme ◽  
Monte Carlo Code ◽  
Doppler Broadening ◽  
Thermal Hydraulics

RMC (Reactor Monte Carlo)[1] is a self-developed Monte Carlo code for nuclear reactor analysis by Reactor Engineering Analysis Lab (REAL), Tsinghua University. On the basis of the self-developed subchannel module (RMC-TH) and Monte Carlo Cell Tally, the internal coupling interface is developed, which combines both input files to one and realizes the fast mesh correspondence process using the cell expansion technology for repeated structure with thermal-hydraulics feedback. It breaks through the bottleneck of geometrical extensibility for coupled code. On-the-fly Doppler broadening method is adopted as the way to consider the temperature effect on microscopic cross section, which only needs the 0 K cross section library so that the memory cost can be apparently reduced. Steady state simulation analysis are performed on PWR fuel pin and 17×17 assembly model, and the results show the feasibility, accuracy and efficiency of the coupling methodology. Therefore, a promising technology roadmap for the large-scale and geometrically universal nuclear reactor in both steady-state and transient conditions with thermal-hydraulic feedback are established. The roadmap can be further applied to neutronics-thermal-hydraulics-depletion coupling in multi-physics simulation process.

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