Author: Rosnie Akang
Publisher:
ISBN:
Category : Monte Carlo method
Languages : en
Pages : 95
Book Description
Neutron Field Perturbation in Large Sample Activation Analysis Using Monte Carlo Code
Author: Rosnie Akang
Publisher:
ISBN:
Category : Monte Carlo method
Languages : en
Pages : 95
Book Description
Publisher:
ISBN:
Category : Monte Carlo method
Languages : en
Pages : 95
Book Description
Monte Carlo Code Predicting Models for Neutron Activation Analysis and Explorative Study of Large Sample Neutron Activation Analysis
Author: Christian Amevi Adjei
Publisher:
ISBN:
Category : Nuclear engineering
Languages : en
Pages : 235
Book Description
Publisher:
ISBN:
Category : Nuclear engineering
Languages : en
Pages : 235
Book Description
The Analog Linear Interpolation Approach for Monte Carlo Simulation of Prompt Gamma-Ray Neutron Activation Analysis
Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
The Monte Carlo code (CEARPGA I) was developed to generate the elemental library spectra required for implementing the Monte Carlo Library Least-Squares algorithm for prompt gamma-ray neutron activation analysis (PGNAA). The existing big weight problem in which a few histories yield very large weights with very large variance has been investigated thoroughly. It has been found that the expected value splitting technique, a powerful variance reduction technique used in the code is the primary cause of this problem. Two Monte Carlo simulation approaches have been investigated to eliminate the big weight problem while still maintaining high efficiency. They are 1) score importance map with batch tracking and 2) analog linear interpolation. Both approaches were implemented separately in the corresponding Monte Carlo codes on the basis of CEARPGA I code and demonstrated to be feasible for solving the big weight problem. The analog linear interpolation approach was selected to incorporate into the new CEARPGA Monte Carlo code (CEARPGA II). A comparison of the results obtained by both CEAEPGA I and CEARPGA II codes as well as experimentally measured data shows that the big weight problem has been successfully eliminated, the accuracy of the simulation has improved greatly, and the simulated results agree very well with the measured data. In addition, some other important improvements have been made in the CEARPGA II to make it more accurate, efficient and powerful, including: 1) tracking pair production gamma rays, 2) incorporating neutron activation background spectra, 3) generating natural background spectra, 4) taking into account the non-linearity of NaI detectors, and 5) adopting a general geometry package.
Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
The Monte Carlo code (CEARPGA I) was developed to generate the elemental library spectra required for implementing the Monte Carlo Library Least-Squares algorithm for prompt gamma-ray neutron activation analysis (PGNAA). The existing big weight problem in which a few histories yield very large weights with very large variance has been investigated thoroughly. It has been found that the expected value splitting technique, a powerful variance reduction technique used in the code is the primary cause of this problem. Two Monte Carlo simulation approaches have been investigated to eliminate the big weight problem while still maintaining high efficiency. They are 1) score importance map with batch tracking and 2) analog linear interpolation. Both approaches were implemented separately in the corresponding Monte Carlo codes on the basis of CEARPGA I code and demonstrated to be feasible for solving the big weight problem. The analog linear interpolation approach was selected to incorporate into the new CEARPGA Monte Carlo code (CEARPGA II). A comparison of the results obtained by both CEAEPGA I and CEARPGA II codes as well as experimentally measured data shows that the big weight problem has been successfully eliminated, the accuracy of the simulation has improved greatly, and the simulated results agree very well with the measured data. In addition, some other important improvements have been made in the CEARPGA II to make it more accurate, efficient and powerful, including: 1) tracking pair production gamma rays, 2) incorporating neutron activation background spectra, 3) generating natural background spectra, 4) taking into account the non-linearity of NaI detectors, and 5) adopting a general geometry package.
Monte Carlo Methods and Their Application to Neutron Transport Problems
Author: Jerome Spanier
Publisher:
ISBN:
Category : Monte Carlo method
Languages : en
Pages : 72
Book Description
Publisher:
ISBN:
Category : Monte Carlo method
Languages : en
Pages : 72
Book Description
The Physics of Big Sample Instrumental Neutron Activation Analysis
Author: Ronaldus Martinus Wilhelmus Overwater
Publisher: Delft University Press
ISBN: 9789040710483
Category : Nuclear activation analysis
Languages : en
Pages : 177
Book Description
Publisher: Delft University Press
ISBN: 9789040710483
Category : Nuclear activation analysis
Languages : en
Pages : 177
Book Description
Monte Carlo Simulation of Correction Factors for Neutron Activation Foils
Author: Pham Ngoc Son
Publisher:
ISBN:
Category : Science
Languages : en
Pages : 0
Book Description
In the conventional neutron activation analysis, the elemental concentrations are normally determined from the comparison ratios between the measured specific activities of the sample and the standard reference material. An advantage in the comparison ratio method is that the systematic error due to neutron self-shielding and multi-scattering effects is canceled out, and the correction factors can be ignored but the preparation of reference standards to match the same conditions with those of various samples is the main difficulty. In the modern trend of neutron activation analysis, the K0-standardization method has been developed and applied in almost all the NAA laboratories. An important research work in the procedure under this method is the characteristic information regarding the neutron source, such as thermal and epithermal neutron fluxes, and epithermal spectrum shape-factor. These neutron spectrum parameters are experimentally determined by using the activation foils, in which the corrections for all neutron effects cause systematic errors should be taken into account. Using the MCNP5 code, a well-known Monte Carlo simulation program, the results of correction factors of thermal, epithermal and resonance neutron self-shielding factors for Au, Co, Mn, W activation foils are presented in this chapter.
Publisher:
ISBN:
Category : Science
Languages : en
Pages : 0
Book Description
In the conventional neutron activation analysis, the elemental concentrations are normally determined from the comparison ratios between the measured specific activities of the sample and the standard reference material. An advantage in the comparison ratio method is that the systematic error due to neutron self-shielding and multi-scattering effects is canceled out, and the correction factors can be ignored but the preparation of reference standards to match the same conditions with those of various samples is the main difficulty. In the modern trend of neutron activation analysis, the K0-standardization method has been developed and applied in almost all the NAA laboratories. An important research work in the procedure under this method is the characteristic information regarding the neutron source, such as thermal and epithermal neutron fluxes, and epithermal spectrum shape-factor. These neutron spectrum parameters are experimentally determined by using the activation foils, in which the corrections for all neutron effects cause systematic errors should be taken into account. Using the MCNP5 code, a well-known Monte Carlo simulation program, the results of correction factors of thermal, epithermal and resonance neutron self-shielding factors for Au, Co, Mn, W activation foils are presented in this chapter.
Development of Monte Carlo Code for Coincidence Prompt Gamma-ray Neutron Activation Analysis
Author: Xiaogang Han
Publisher:
ISBN:
Category :
Languages : en
Pages : 128
Book Description
Keywords: PGNAA, Coincidence measurement, Monte Carlo, MCNP.
Publisher:
ISBN:
Category :
Languages : en
Pages : 128
Book Description
Keywords: PGNAA, Coincidence measurement, Monte Carlo, MCNP.
Le Bastion de la foy chrestienne, propre povr rembarrer les ennemis de l'euangile
Monte Carlo Modelling of Systems for the Neutron Activation Analysis of Aluminium in Vivo
Author: Sameer Sa Natto
Publisher:
ISBN:
Category : Aluminum
Languages : en
Pages : 0
Book Description
Publisher:
ISBN:
Category : Aluminum
Languages : en
Pages : 0
Book Description
Monte Carlo Principles and Neutron Transport Problems
Author: Jerome Spanier
Publisher: Courier Corporation
ISBN: 0486462935
Category : Mathematics
Languages : en
Pages : 258
Book Description
This two-part treatment introduces the general principles of the Monte Carlo method within a unified mathematical point of view, applying them to problems in neutron transport. It describes several efficiency-enhancing approaches, including the method of superposition and simulation of the adjoint equation based on reciprocity. The first half of the book presents an exposition of the fundamentals of Monte Carlo methods, examining discrete and continuous random walk processes and standard variance reduction techniques. The second half of the text focuses directly on the methods of superposition and reciprocity, illustrating their applications to specific neutron transport problems. Topics include the computation of thermal neutron fluxes and the superposition principle in resonance escape computations.
Publisher: Courier Corporation
ISBN: 0486462935
Category : Mathematics
Languages : en
Pages : 258
Book Description
This two-part treatment introduces the general principles of the Monte Carlo method within a unified mathematical point of view, applying them to problems in neutron transport. It describes several efficiency-enhancing approaches, including the method of superposition and simulation of the adjoint equation based on reciprocity. The first half of the book presents an exposition of the fundamentals of Monte Carlo methods, examining discrete and continuous random walk processes and standard variance reduction techniques. The second half of the text focuses directly on the methods of superposition and reciprocity, illustrating their applications to specific neutron transport problems. Topics include the computation of thermal neutron fluxes and the superposition principle in resonance escape computations.