Monte Carlo Code Predicting Models for Neutron Activation Analysis and Explorative Study of Large Sample Neutron Activation Analysis PDF Download
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Author: Christian Amevi Adjei
Publisher:
ISBN:
Category : Nuclear engineering
Languages : en
Pages : 235
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Author: Christian Amevi Adjei
Publisher:
ISBN:
Category : Nuclear engineering
Languages : en
Pages : 235
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Author: Rosnie Akang
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ISBN:
Category : Monte Carlo method
Languages : en
Pages : 95
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Author:
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Category :
Languages : en
Pages :
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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.
Author: Nickie J. J. Peters
Publisher:
ISBN:
Category : Electronic dissertations
Languages : en
Pages : 175
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A novel approach to parametric instrumental neutron activation analysis at MURR has been established. In particular, a detailed MCNP5 steady-state model of the MURR core was developed. The model, which was based on the most recent continuous-energy neutron data from the ENDF and JEFF neutron libraries, was used to compute the local continuous-energy neutron flux distribution. By coupling the computed flux spectrum to the energy-dependent ([nu], [upsilon]) cross-sections for a range of nuclides, their intrinsic reaction rates were predicted in irradiation channel ROW2. The model was initially benchmarked by measuring the intrinsic ([nu], [upsilon]) reaction rates for a set of mostly dilute single-element standards in ROW2. Predictions of the intrinsic reaction rates for many nuclides, including those with high epithermal sensitivity and non-1/v behavior, are within [plus-minus] 5% of the measured values. Using predicted ([nu], [upsilon]) reaction-rates, trace-elemental concentrations were determined in NIST standard reference materials, bovine liver, obsidian and coal fly ash. The agreements with the certified concentrations were generally within [plus-minus]5%. The new methodology has produced better results for a greater number of elements than [kappa]0. The model was also combined with MONTEBURNS and ORIGEN to test the feasibility of Mo99production at MURR from fissioning LEU. Results from a 5-gram low-enriched uranium target show predictions of Mo99 end-of-irradiation yields are within 3% of the measured value. This dissertation entails a complete study of the MCNP5 model and the new neutron activation analysis method.
Author: Xiaogang Han
Publisher:
ISBN:
Category :
Languages : en
Pages : 128
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Keywords: PGNAA, Coincidence measurement, Monte Carlo, MCNP.
Author:
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Category : Apologetics
Languages : en
Pages : 444
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Author: Pham Ngoc Son
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Category : Science
Languages : en
Pages : 0
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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.
Author: Sameer Sa Natto
Publisher:
ISBN:
Category : Aluminum
Languages : en
Pages :
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Author: Jerome Spanier
Publisher:
ISBN:
Category : Monte Carlo method
Languages : en
Pages : 72
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Author: Jerome Spanier
Publisher:
ISBN:
Category : Monte Carlo method
Languages : en
Pages : 22
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