Endf 6 Compatible Evaluation Of Neutron Induced Reaction Cross Sections For 182183184186w PDF Download
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Author | : |
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Total Pages | : 10 |
Release | : 2013 |
Genre | : |
ISBN | : 9789279285394 |
Download ENDF-6 Compatible Evaluation of Neutron Induced Reaction Cross Sections for 182,183,184,186W. Book in PDF, ePub and Kindle
An ENDF-6 compatible evaluation for neutron induced reactions in the resonance region has been completed for 182,183,184,186W. The parameters are the result of an analysis of experimental data available in the literature together with a parameter adjustment on transmission and capture data obtained at the time-of-flight facility GELINA. Complete evaluated data files in ENDF-6 format have been produced by joining the evaluations in the resonance region with corresponding files from the JEFF- 32T1 and ENDF/B-VII. 1 library. The evaluated files have been processed with the latest updates of NJOY. 99 to test their format and application consistency as well as to produce a continuous-energy data library in ACE format for use in Monte Carlo codes. The evaluated files will be implemented in the next release of the JEFF-3 library which is maintained by the Nuclear Energy Agency of the OECD.
Author | : Ivan Sirakov |
Publisher | : |
Total Pages | : 8 |
Release | : 2013 |
Genre | : |
ISBN | : 9789279284212 |
Download ENDF-6 Compatible Evaluation of Neutron Induced Reaction Cross Sections for [sup]106,108,110,111,112,113,114,116Cd Book in PDF, ePub and Kindle
An ENDF-6 compatible evaluation for neutron induced reactions in the resonance region has been completed for 106,108,110,111,112,113,114,116Cd. The parameters are the result of an analysis of experimental data available in the literature together with a parameter adjustment on transmission and capture data obtained at the time-of-flight facility GELINA. Complete evaluated data files in ENDF-6 format have been produced by joining the evaluations in the resonance region with corresponding files from the JEFF-3.1.2 nuclear data library (or with the JEFF-Beta-CAD proposed evaluation in case of 113Cd). These files were produced for use in the JEFF32T2 library. For neutron induced reactions in the unresolved resonance region the JENDL 4.0 evaluation for 111Cd and 113Cd was adopted. The evaluated files have been processed with the latest updates of NJOY. 99 to test their format and application consistency as well as to produce a continuous-energy data library in ACE format for use in Monte Carlo codes. The ACE files have been utilized to study the effect of the evaluated resonance parameters on results of integral experiments. The evaluated files will be implemented in the next release of the JEFF-3 library which is maintained by the Nuclear Energy Agency of the OECD.
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Release | : 2001 |
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Download Evaluation Of[sup 28,29,30]i Neutron Induced Cross Sections for ENDF/B-VI. Book in PDF, ePub and Kindle
Separate evaluations have been done for the three stable isotopes of silicon for ENDF/B-VI. The evaluations are based on analysis of experimental data, supplemented by results of nuclear model calculations. The computational methods and the parameters required as input to the nuclear model codes are reviewed. Discussion of the evaluated data given for resonance parameters, neutron induced reaction cross sections, associated angular and energy distributions, and gamma-ray production cross sections is included. Extensive comparisons of the evaluated cross sections to measured data are shown in this report. The evaluations include all necessary data to allow KERMA (Kinetic Energy Released in MAterials) and displacement cross sections to be calculated directly. These quantities are fundamental to studies of neutron heating and radiation damage.
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Total Pages | : 135 |
Release | : 1997 |
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Download Evaluation of {sup 28,29,30}Si Neutron Induced Cross Sections for ENDF/B-VI. Book in PDF, ePub and Kindle
Separate evaluations have been done for the three stable isotopes of silicon for ENDF/B-VI. The evaluations are based on analysis of experimental data, supplemented by results of nuclear model calculations. The computational methods and the parameters required as input to the nuclear model codes are reviewed. Discussion of the evaluated data given for resonance parameters, neutron induced reaction cross sections, associated angular and energy distributions, and gamma-ray production cross sections is included. Extensive comparisons of the evaluated cross sections to measured data are shown in this report. The evaluations include all necessary data to allow KERMA (Kinetic Energy Released in MAterials) and displacement cross sections to be calculated directly. These quantities are fundamental to studies of neutron heating and radiation damage.
Author | : Delin Zhou |
Publisher | : |
Total Pages | : 11 |
Release | : 1996 |
Genre | : Neutron cross sections |
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Download A Simultaneous Evaluation of Neutron Induced Reaction Cross Sections for 56Fe at En Book in PDF, ePub and Kindle
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Total Pages | : 73 |
Release | : 1990 |
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Download Calculated Cross Sections for Neutron Induced Reactions on Sup 19 F and Uncertainties of Parameters Book in PDF, ePub and Kindle
Nuclear model codes were used to calculate cross sections for neutron-induced reactions on 19F for incident energies from 2 to 20 MeV. The model parameters in the codes were adjusted to best reproduce experimental data and are given in this report. The calculated results are compared to measured data and the evaluated values of ENDF/B-V. The covariance matrix for several of the most sensitive model parameters is given based on the scatter of measured data around the theoretical curves and the long-range correlation error of measured data. The results of these calculations form the basis for the new ENDF/B-VI fluorine evaluation. 44 refs., 64 figs., 14 tabs.
Author | : M K Mehta |
Publisher | : World Scientific |
Total Pages | : 946 |
Release | : 1993-12-16 |
Genre | : |
ISBN | : 9814553727 |
Download Computation And Analysis Of Nuclear Data Relevant To Nuclear Energy And Safety Book in PDF, ePub and Kindle
This book focuses on the modern nuclear models and computer codes used in nuclear model calculations of nuclear data required for nuclear technology and nuclear safety applications.
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Release | : 1980 |
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Download Evaluation of Neutron Cross Sections to 40 MeV for 54 56Fe Book in PDF, ePub and Kindle
Cross sections for neutron-induced reactions on 54 56Fe were calculated by employing several nuclear models: optical, Hauser-Feshbach, preequilibrium and DWBA - in the energy range between 3 and 40 MeV. As a prelude to the calculations, the necessary input parameters were determined or verified through analysis of a large body of experimental data for both neutron- and proton-induced reactions in this mass and energy region. This technique also led to cross sections in which the simultaneous influence of available data types added to their consistency and reliability. Calculated cross sections as well as neutron and gamma-ray emission spectra were incorporated into an ENDF evaluation suitable for use to 40 MeV. 12 figures, 1 table.
Author | : Syed M. Qaim |
Publisher | : Springer Science & Business Media |
Total Pages | : 1041 |
Release | : 2012-12-06 |
Genre | : Science |
ISBN | : 3642581137 |
Download Nuclear Data for Science and Technology Book in PDF, ePub and Kindle
This book describes the Proceedings of the International Conference on Nuclear Data for Science and Technology held at Jillich in May 1991. The conference was in a series of application oriented nuclear data conferences organized in the past under the auspices of the Nuclear Energy Agency-Nuclear Data Committee (NEANDC) and with the support of the Nuclear Energy Agency-Committee on Reactor Physics (NEACRP). It was the fIrst international conference on nuclear data held in Germany, with the scientific responsibility entrusted to the Institute of Nuclear Chemistry of the Research Centre Jillich. The scientific programme was established by the International Programme Committee in consultation with the International Advisers, and the NEA and IAEA cooperated in the organization. A total of 328 persons from 37 countries and fIve international organizations participated. The scope of these Proceedings extends to a wide range of interdisciplinary topics dealing with measu rement, calculation, evaluation and application of nuclear data, with a major emphasis on numerical data. Both energy and non-energy related applications are considered and due attention is given to some fundamental aspects relevant to the understanding of nuclear data.
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Total Pages | : 1198 |
Release | : 1981 |
Genre | : Physics |
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Download Physics Briefs Book in PDF, ePub and Kindle