scholarly journals Study on computational performance in generation of cross sections for nodal simulators using continuous-energy Monte Carlo calculations

2015 ◽  
Vol 52 (7-8) ◽  
pp. 945-952 ◽  
Author(s):  
Jaakko Leppänen ◽  
Riku Mattila
Keyword(s):  
Monte Carlo ◽  
Cross Sections ◽  
Monte Carlo Calculations ◽  
Continuous Energy ◽  
Computational Performance

Reactions of 88Sr with protons of energies7–85 MeV

1967 ◽  
Vol 45 (10) ◽  
pp. 1149-1160 ◽  
Author(s):  
D. R. Sachdev ◽  
N. T. Porile ◽  
L. Yaffe
Keyword(s):  
Monte Carlo ◽  
Compound Nucleus ◽  
Cross Sections ◽  
Experimental Results ◽  
Excitation Functions ◽  
Monte Carlo Calculations ◽  
High Energies ◽  
The Individual ◽  
Two Peaks ◽  
Evaporation Stage

Excitation functions for the (p,xn) (x = 1–5), (p,p3n), and (p,2pxn) (x = 1, 3, 4) reactions induced in 88Sr by protons of energy from 7 to 85 MeV have been measured by radiochemical methods. Cross sections for the individual isomeric species for the products of (p,2n), (p,3n), (p,4n), and (p,p3n) reactions are also presented.Excitation functions for each of the (p,2p3n) and (p,2p4n) reactions exhibit two peaks, the first of which is assigned to (p,α n) or (p,α 2n) reactions from threshold considerations. The experimental results are compared with Monte Carlo calculations using the codes of Chen et al. for the cascade stage and Dostrovsky et al. for the evaporation stage. The comparison suggests that the calculations of Chen et al. overestimate the extent of compound nucleus contribution at high energies.

Electron-beam spreading in thin foils at 40keV

1983 ◽  
Vol 41 ◽  
pp. 370-371
Author(s):  
T.A. Stephenson ◽  
M.H. Loretto ◽  
I.P. Jones ◽  
P. Augustus
Keyword(s):  
Monte Carlo ◽  
Single Crystal ◽  
Cross Sections ◽  
Single Crystal Silicon ◽  
Orientation Dependence ◽  
High Angle ◽  
Crystal Silicon ◽  
Beam Spreading ◽  
Monte Carlo Calculations ◽  
Thin Foils

Experiments have been performed to determine the effects of thickness, and crystallinity on beam spreading in thin foils. The experimental technique consists of measuring an incident and exit electron probe size as shown in Fig. 1. Beam spreading is defined as the difference between these two quantities. Results were compared with Monte Carlo calculations.Beam spreading experiments in single crystal silicon oriented positive of a 440 reflection have shown that the experimental measurements are adequately described by Monte Carlo calculations using Doyle and Turner elastic scattering cross-sections (Fig.2). The addition of an inelastic component via the Bethe continuous loss approximation produces an insignificant change. Adjustment for the generation and scattering of fast secondary electrons is reserved for future work.Two experiments were performed to elucidate the effects of crystallinity. The first involved single crystal silicon in which exit grobe size measurgments were performed with diffracting conditions s=+0.0027Å-1 and s=-0.0034Å-1 from 220 (Table 1). Since beam spreading is dependent on high angle scattering, these results are qualitatively consistent with the orientation dependence of high angle diffuse scattering.

One Step Method for Multigroup Adjoint Neutron Flux Through Continuous Energy Monte Carlo Calculation

2018 ◽  
Author(s):  
Xiaotong Shang ◽  
Guanlin Shi ◽  
Kan Wang
Keyword(s):  
Monte Carlo ◽  
Neutron Flux ◽  
Cross Sections ◽  
Monte Carlo Code ◽  
Event Analysis ◽  
Step Method ◽  
Kinetics Parameters ◽  
Transient Event ◽  
Continuous Energy ◽  
Deterministic Methods

The adjoint neutron flux is vital in the analysis of reactor kinetics parameters and reactor transient events. Both deterministic and Monte Carlo methods have been developed for the adjoint neutron flux calculation on the basis of multi-group cross sections which may vary significantly among different types of reactors. The iterated fission probability (IFP) method is introduced to calculate the neutron importance which is able to represent the adjoint neutron flux in continuous energy problem and have been applied to the calculation of kinetics parameters. However, the adjoint neutron flux can’t be obtained directly and applied to both Monte Carlo transient event analysis and deterministic methods. In this study, a method based on IFP is studied and implemented in Monte Carlo code RMC. The multi-group adjont neutron flux can be obtained directly through the discretization of energy and space with the modification of fission neutrons through continuous energy Monte Carlo calculations. The obtained multi-group adjoint neutron flux can be used in both Monte Carlo transient analysis and deterministic methods.

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