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Download or read book EVALUATED NEUTRON CROSS SECTIONS OF $sup 240$Pu FOR THE ENDF/B FILE. written by and published by . This book was released on 1968 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book EVALUATED NEUTRON CROSS SECTIONS OF $sup 23$Na FOR THE ENDF/B FILE. written by and published by . This book was released on 1968 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:
![Download Evaluation of the Fission and Capture Cross Sections of [sup]240[/sup]Pu; and [sup]241[/sup]Pu for ENDF/B-V. [10/sup -5/ EV to 20 MeV]. PDF Online Free](https://books.google.com/books/content/images/frontcover/6xX_wQEACAAJ?fife=w200-h370)
Download or read book Evaluation of the Fission and Capture Cross Sections of [sup]240[/sup]Pu; and [sup]241[/sup]Pu for ENDF/B-V. [10/sup -5/ EV to 20 MeV]. written by and published by . This book was released on 1979 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Since there were appreciable new data which were not available for ENDF/B-IV, new evaluations for /sup 240/Pu and /sup 241/Pu were carried out for ENDF/B-V. The evaluation of the fission and capture cross sections is reviewed and problem areas are discussed. The neutron energy range of concern was from 10/sup -5/ eV to 20 MeV. Significant changes were made over the entire neutron energy region because of the new experimental data available. The problems in the evaluations due to discrepancies in the nuclear data are emphasized, particularly the 1-eV resonance in /sup 240/Pu and the 0.3-eV resonance in /sup 241/Pu. The evaluation of the fission and capture cross sections for ENDF/B-V represents an improvement over the previous evaluation; however, there continues to be a need for accurate experimental data. 7 figures.
Download or read book Evaluation of the Neutron Cross Sections for Pu-240 written by and published by . This book was released on 1987 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The present evaluation is proposed to supersede the ENDF/B-V, Revision 2 file for /sup 240/Pu. In this work, resonance parameters, cross sections, energy distributions, and angular distributions have been modified. These changes are outlined in detail and appropriate references included. 37 refs., 21 figs., 2 tabs.
Author : Dermott Edward Cullen
Publisher :
ISBN 13 :
Total Pages : 44 pages
Book Rating : 4.3/5 ( download)
Download or read book Program RECENT (version 79-1) written by Dermott Edward Cullen and published by . This book was released on 1979 with total page 44 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book EVALUATION OF NEUTRON CROSS SECTIONS FOR A COMPLETE SET OF Nd ISOTOPES. written by and published by . This book was released on 2007 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Neutron cross sections for a complete set of Nd isotopes, {sup 142,143,144,145,146,147,148,150}Nd, were evaluated in the incident energy range from 10−5 eV to 20 MeV. In the low energy region, including thermal and resolved resonances, our evaluations are based on the latest data published in the Atlas of Neutron Resonances. In the unresolved resonance region we performed additional evaluation by using the averages of the resolved resonances and adjusting them to the experimental data. In the fast neutron region, we used the nuclear reaction model code EMPIRE-2.19 validated against the experimental data. The results are compared to the existing nuclear data libraries, including ENDF/B-VI. 8, JENDL-3.3 and JEFF-3.1, and to the available experimental data. The new evaluations are suitable for neutron transport calculations and they were adopted by the new evaluated nuclear data file of the United States, ENDF/B-VII.0, released in December 2006.
Author : David T. Goldman
Publisher :
ISBN 13 :
Total Pages : 730 pages
Book Rating : 4.3/5 (91 download)
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 730 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book EVALUATION OF 238U NEUTRON CROSS SECTIONS FOR THE ENDF/B VERSION II FILE. written by and published by . This book was released on 1971 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:
![Download Evaluation Of[sup 28,29,30]i Neutron Induced Cross Sections for ENDF/B-VI. PDF Online Free](https://books.google.com/books/content/images/frontcover/tcyUDAEACAAJ?fife=w200-h370)
Download or read book Evaluation Of[sup 28,29,30]i Neutron Induced Cross Sections for ENDF/B-VI. written by and published by . This book was released on 2001 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: 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 :
Publisher :
ISBN 13 :
Total Pages : 135 pages
Book Rating : 4.:/5 (873 download)
Download or read book Evaluation of {sup 28,29,30}Si Neutron Induced Cross Sections for ENDF/B-VI. written by and published by . This book was released on 1997 with total page 135 pages. Available in PDF, EPUB and Kindle. Book excerpt: 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.
Download or read book Evaluated Neutron-induced Cross Sections for /sup 40/Ca from 20 to 40 MeV. written by and published by . This book was released on 1982 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Nuclear model codes were used to compute cross sections for neutron-induced reactions on /sup 40/Ca for incident energies from 20 to 40 MeV. The input parameters for the model codes were determined through analysis of experimental data in this energy region. Computed cross sections along with emission spectra for each product were combined into an Evaluated Nuclear Data File (ENDF) using the proposed format for charged-particle reactions. Discussion of the models used, the resulting calculations, and the final evaluated data file are presented.
Download or read book Evaluated (n, P) Cross Sections of /sup 46/Ti /sup 47/Ti and /sup 48/Ti written by and published by . This book was released on 1977 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Microscopic evaluated neutron cross sections for the reactions /sup 46/Ti(n;p)/sup 46/Sc, /sup 47/Ti(n;p)/sup 47/Sc and /sup 48/Ti(n;p)/sup 48/Sc are obtained from threshold (or zero energy) to 20 MeV. The results are presented in graphical and numerical (ENDF format) form. The microscopic evaluated cross sections are compared with measured fission-spectrum-averaged values.
Author : S. T. Perkins
Publisher :
ISBN 13 :
Total Pages : 48 pages
Book Rating : 4.3/5 ( download)
Download or read book Experimental and Evaluated Nuclear Plus Interference Cross Sections for Light Charged Particles written by S. T. Perkins and published by . This book was released on 1980 with total page 48 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author :
Publisher :
ISBN 13 :
Total Pages : 4 pages
Book Rating : 4.:/5 (893 download)
Download or read book New Evaluations of Neutron Cross Sections for Sup 14 N and Sup 16 O. written by and published by . This book was released on 1991 with total page 4 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author : M. R. Bhat
Publisher :
ISBN 13 :
Total Pages : 60 pages
Book Rating : 4.3/5 (91 download)
Download or read book Evaluated Neutron Cross Sections for the Stable Isotopes of Xenon written by M. R. Bhat and published by . This book was released on 1973 with total page 60 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author : Dermott Edward Cullen
Publisher :
ISBN 13 :
Total Pages : 76 pages
Book Rating : 4.3/5 ( download)
Download or read book Program GROUPLE (version 79-1) written by Dermott Edward Cullen and published by . This book was released on 1980 with total page 76 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author :
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ISBN 13 :
Total Pages : 5 pages
Book Rating : 4.:/5 (684 download)
Download or read book Assessment of the Available (Sup 233)U Cross Sections Evaluations in the Calculation of Critical Benchmark Experiments written by and published by . This book was released on 1993 with total page 5 pages. Available in PDF, EPUB and Kindle. Book excerpt: In this report we investigate the adequacy of the available 233U cross-section data for calculation of experimental critical systems. The 233U evaluations provided in two evaluated nuclear data libraries, the U.S. Data Bank [ENDF/B (Evaluated Nuclear Data Files)] and the Japanese Data Bank [JENDL (Japanese Evaluated Nuclear Data Library)] are examined. Calculations were performed for six thermal and ten fast experimental critical systems using the Sn transport XSDRNPM code. To verify the performance of the 233U cross-section data for nuclear criticality safety application in which the neutron energy spectrum is predominantly in the epithermal energy range, calculations of four numerical benchmark systems with energy spectra in the intermediate energy range were done. These calculations serve only as an indication of the difference in calculated results that may be expected when the two 233U cross-section evaluations are used for problems with neutron spectra in the intermediate energy range. Additionally, comparisons of experimental and calculated central fission rate ratios were also made. The study has suggested that an ad hoc 233U evaluation based on the JENDL library provides better overall results for both fast and thermal experimental critical systems.
