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- 저자 : Trkov (검색결과 4 건)
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STATUS AND PERSPECTIVE OF NUCLEAR DATA PRODUCTION, EVALUATION AND VALIDATION
TRKOV A. Korean Nuclear Society 2005 Nuclear Engineering and Technology Vol.37 No.1
A very important feature in the development of nuclear technology has been and will continue to be the flow of information from nuclear data production to the various applications fields in nuclear technology. Both, nuclear data and this communications flow are defined in this paper. Nuclear data result from specific technical activities including their production, evaluation, processing, verification, validation and applications. These activities are described, focusing on nuclear reactor calculations. Mathematical definitions of different types of nuclear data are introduced, and international forums involved in nuclear data activities are listed. Electronic links to various sources of information available on the web are specified, whenever possible.
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A. Trkov,I. Kodeli,G. Zerovnik,R. Capote,D. W. Muir 한국물리학회 2011 THE JOURNAL OF THE KOREAN PHYSICAL SOCIETY Vol.59 No.23
Taking the FNG-W benchmark with a D-T source in front of a large tungsten block as an example, the impact of the reaction cross-section covariance data on the predicted activities of monitor foils inside the block and the associated uncertainties were studied. Cross-material covariances between the isotopic cross sections of tungsten were obtained by including experimental measurements of the elemental total cross sections above the resonance range. Cross-material covariances of the elastic and the radiative capture reactions were considered. Since the original cross sections were evaluated accurately from the reasonably abundant isotopic data, the impact of introducing elemental data on the isotopic cross sections and their uncertainties were small. Correlations were observed mainly in the elastic channel, which has a relatively low sensitivity to the calculated monitor activities of the benchmark. Consequently, the impact on the predicted monitor sample activities was also small in terms of the absolute value and the uncertainty. The main achievement of the work was the demonstrated data consistency and the development of tools for including elemental data in isotopic cross section evaluation and the evaluation of cross-material covariances.
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Status and Perspective of Nuclear Data Production, Evaluation and Validation
A. Trkov 한국원자력학회 2005 Nuclear Engineering and Technology Vol.37 No.1
A very important feature in the development of nuclear technology has been and will continue to be the flow of information from nuclear data production to the various applications fields in nuclear technology. Both, nuclear data and this communications flow are defined in this paper. Nuclear data result from specific technical activities including their production, evaluation, processing, verification, validation and applications. These activities are described, focusing on nuclear reactor calculations. Mathematical definitions of different types of nuclear data are introduced, and international forums involved in nuclear data activities are listed. Electronic links to various sources of information available on the web are specified, whenever possible.
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Sirakov, I.,Capote, R.,Gritzay, O.,Kim, H. I.,Kopecky, S.,Kos, B.,Paradela, C.,Pronyaev, V. G.,Schillebeeckx, P.,Trkov, A. Springer 2017 European Physical Journal A Vol.53 No.10
<P>Cross sections for neutron interactions with U-238 in the energy region from 5 keV to 150 keV have been evaluated. Average total and capture cross sections have been derived from a least squares analysis using experimental data reported in the literature. The resulting cross sections have been parameterised in terms of average resonance parameters maintaining full consistency with results of optical model calculations by using a dispersive coupled channel optical model potential. The average compound partial cross sections have been expressed in terms of transmission coefficients by applying the Hauser-Feshbach statistical reaction theory including width-fluctuations. A generalized single-level representation compatible with the energy-dependent options of the ENDF-6 format has been applied using standard boundary conditions. The results have been transferred into a full ENDF-6 compatible data file.</P>
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