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Assessment Of Neutron Cross Section Evaluations For The Bulk Of Fission Products
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Author :OECD Nuclear Energy Agency. Working Party on International Evaluation Co-operation Publisher : ISBN 13 : Total Pages :44 pages Book Rating :4.:/5 (225 download)
Book Synopsis Assessment of Neutron Cross-section Evaluations for the Bulk of Fission Products by : OECD Nuclear Energy Agency. Working Party on International Evaluation Co-operation
Download or read book Assessment of Neutron Cross-section Evaluations for the Bulk of Fission Products written by OECD Nuclear Energy Agency. Working Party on International Evaluation Co-operation and published by . This book was released on 2005 with total page 44 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Statistical Evaluation of Fission-product Absorption Cross Sections at Intermediate and High Energies by : P. Greebler
Download or read book Statistical Evaluation of Fission-product Absorption Cross Sections at Intermediate and High Energies written by P. Greebler and published by . This book was released on 1956 with total page 20 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Neutron Cross Sections and Technology by : David T. Goldman
Download or read book Neutron Cross Sections and Technology written by David T. Goldman and published by . This book was released on 1968 with total page 680 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Evaluation of Neutron Cross-sections for Fission Product Nuclei in the Energy Range Up Tp 50 MeV. by : V. P. Lunev
Download or read book Evaluation of Neutron Cross-sections for Fission Product Nuclei in the Energy Range Up Tp 50 MeV. written by V. P. Lunev and published by . This book was released on 1994 with total page 76 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Evaluation of Cross-Section Sensitivities in Computing Burnup Credit Fission Product Concentrations by : I. C. Gauld
Download or read book Evaluation of Cross-Section Sensitivities in Computing Burnup Credit Fission Product Concentrations written by I. C. Gauld and published by . This book was released on 2005 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: U.S. Nuclear Regulatory Commission Interim Staff Guidance 8 (ISG-8) for burnup credit covers actinides only, a position based primarily on the lack of definitive critical experiments and adequate radiochemical assay data that can be used to quantify the uncertainty associated with fission product credit. The accuracy of fission product neutron cross sections is paramount to the accuracy of criticality analyses that credit fission products in two respects: (1) the microscopic cross sections determine the reactivity worth of the fission products in spent fuel and (2) the cross sections determine the reaction rates during irradiation and thus influence the accuracy of predicted final concentrations of the fission products in the spent fuel. This report evaluates and quantifies the importance of the fission product cross sections in predicting concentrations of fission products proposed for use in burnup credit. The study includes an assessment of the major fission products in burnup credit and their production precursors. Finally, the cross-section importances, or sensitivities, are combined with the importance of each major fission product to the system eigenvalue (k{sub eff}) to determine the net importance of cross sections to k{sub eff}. The importances established the following fission products, listed in descending order of priority, that are most likely to benefit burnup credit when their cross-section uncertainties are reduced: {sup 151}Sm, {sup 103}Rh, {sup 155}Eu, {sup 150}Sm, {sup 152}Sm, {sup 153}Eu, {sup 154}Eu, and {sup 143}Nd.
Author :Brookhaven National Laboratory. Neutron Cross Section Evaluation Group. Sigma Center Publisher : ISBN 13 : Total Pages : pages Book Rating :4.:/5 (13 download)
Book Synopsis Newsletter by : Brookhaven National Laboratory. Neutron Cross Section Evaluation Group. Sigma Center
Download or read book Newsletter written by Brookhaven National Laboratory. Neutron Cross Section Evaluation Group. Sigma Center and published by . This book was released on 1960 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Neutron Standards and Applications by : Charles D. Bowman
Download or read book Neutron Standards and Applications written by Charles D. Bowman and published by . This book was released on 1977 with total page 388 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Conference on Neutron Cross Section Technology by : P. B. Hemmig
Download or read book Conference on Neutron Cross Section Technology written by P. B. Hemmig and published by . This book was released on 1966 with total page 572 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Neutron Cross Section Evaluation Group by : S. Pearlstein
Download or read book Neutron Cross Section Evaluation Group written by S. Pearlstein and published by . This book was released on 1964 with total page 47 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book A/CONF.15/P written by and published by . This book was released on 1958 with total page 22 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Evaluation of Neutron Cross-sections for Fission Productnuclei in the Energy Range Up to 50 MeV. by : V. P. Lunev
Download or read book Evaluation of Neutron Cross-sections for Fission Productnuclei in the Energy Range Up to 50 MeV. written by V. P. Lunev and published by . This book was released on 1994 with total page 76 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis NEUTRON CROSS SECTION EVALUATIONS OF FISSION PRODUCTS BELOW THE FAST ENERGY REGION. by :
Download or read book NEUTRON CROSS SECTION EVALUATIONS OF FISSION PRODUCTS BELOW THE FAST ENERGY REGION. written by and published by . This book was released on 2000 with total page 170 pages. Available in PDF, EPUB and Kindle. Book excerpt: Neutron cross section evaluations of the fission-product isotopes, 95Mo, 99Tc, 1°1Ru, 1°3Rh, 1°5Pd, 1°9Ag, 131Xe, 133Cs, 141Pr, 141Nd, 147Sm, 149Sm, 15°Sm, 151Sm, 152Sm, 153Eu, 155Gd, and 157Gd were carried out below the fast neutron energy region within the framework of the BNL-KAERI international collaboration. In the thermal energy region, the energy dependence of the various cross-sections was calculated by applying the multi-level Breit-Wigner formalism. In particular, the strong energy dependence of the coherent scattering lengths of 155Gd and 157Gd were determined and were compared with recent calculations of Lynn and Seeger. In the resonance region, the recommended resonance parameters, reported in the BNL compilation, were updated by considering resonance parameter information published in the literature since 1981. The s-wave and, if available, p-wave reduced neutron widths were analyzed in terms of the Porter-Thomas distribution to determine the average level spacings and the neutron strength functions. Average radiative widths were also calculated from measured values of resolved energy resonances. The average resonance parameters determined in this study were compared with those in the BNL and other compilations, as well as the ENDF/B-VI, JEF-2.2, and JENDL-3.2 data libraries. The unresolved capture cross sections of these isotopes, computed with the determined average resonance parameters, were compared with measurements, as well as the ENDF/B-VI evaluations. To achieve agreement with the measurements, in a few cases minor adjustments in the average resonance parameters were made. Because of astrophysical interest, the Maxwellian capture cross sections of these nuclides at a neutron temperature of 30 keV were computed and were compared with other compilations and evaluations.
Book Synopsis International Evaluation of Neutron Cross-section Standards by : A. L. Nichols
Download or read book International Evaluation of Neutron Cross-section Standards written by A. L. Nichols and published by . This book was released on 2007-01 with total page 173 pages. Available in PDF, EPUB and Kindle. Book excerpt: Cross-section standards are required to be of high quality and accuracy to form the foundation of a wide range of important nuclear measurements and evaluations for both energy and non-energy applications. They constitute the yardstick for all other nuclear physics measurements. These standards have been re-assessed and evaluated to make significant improvements in the data, and to take into account important new experimental data and improved evaluation techniques. The methods employed were the most sophisticated ever used in cross-section evaluations. These present standards are more accurate than all earlier versions, and the given errors are well justified in the context of contemporary data and evaluation methodology. --Publisher's description.
Book Synopsis Nuclear Data for Science and Technology by : K.H. Bockhoff
Download or read book Nuclear Data for Science and Technology written by K.H. Bockhoff and published by Springer Science & Business Media. This book was released on 2012-12-06 with total page 1049 pages. Available in PDF, EPUB and Kindle. Book excerpt: Proceedings of the International Conference, Antwerp, Belgium, September 6-10, 1982
Book Synopsis An International Evaluation of the Neutron Cross Section Standards by : A. D. Carlson
Download or read book An International Evaluation of the Neutron Cross Section Standards written by A. D. Carlson and published by . This book was released on 2006 with total page 9 pages. Available in PDF, EPUB and Kindle. Book excerpt: Work is reported here on the process and present results of an international evaluation of the neutron cross section standards. The evaluations include the H(n,n), 3He(n,p), 6Li(n,t), 10B(n,?), 10B(n,?1?), 197Au(n,?), 235U(n,f), and 238U(n,f) standard reactions as well as the 238U(n,?) and 239Pu(n,f) reactions. This evaluation was performed to include new experiments on the standards that have been made since the ENDF/B-VI evaluation was completed and to improve the evaluation process. Evaluations have been completed for the 6Li(n,t), 197Au(n,?) and 238U(n,?) cross sections. Also below 20 MeV the H(n,n), 235U(n,f), 238U(n,f) and 239Pu(n,f) cross sections are completed. Many of the cross sections being evaluated are used in neutron dosimetry for fluence determination. The general trend observed for the evaluations is an increase in the cross sections for most of the reactions from fractions of a percent to several percent compared with the ENDF/B-VI results.
Book Synopsis Neutron Nuclear Data Evaluation by : International Atomic Energy Agency
Download or read book Neutron Nuclear Data Evaluation written by International Atomic Energy Agency and published by . This book was released on 1973 with total page 148 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Nuclear Data for Science and Technology by : Syed M. Qaim
Download or read book Nuclear Data for Science and Technology written by Syed M. Qaim and published by Springer Science & Business Media. This book was released on 2012-12-06 with total page 1041 pages. Available in PDF, EPUB and Kindle. Book excerpt: 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.
