Download or read book Evaluation of the Fission and Capture Cross Sections of 24 Pu and 241Pu for ENDF 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 24°Pu and 241Pu 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 10−5 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 24°Pu and the 0.3-eV resonance in 241Pu. 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 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 Fission Cross Sections and Covariances 233U 235U 238U 239Pu 240Pu and 241Pu written by and published by . This book was released on 2000 with total page 88 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Nuclear Cross Sections and Technology written by Roald Amundsen Schrack and published by . This book was released on 1975 with total page 490 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Evaluations of Fission Product Capture Cross Sections for ENDF B V written by and published by . This book was released on 1979 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Capture cross section evaluations were made for the 36 most important fission product absorbers in a fast reactor system. These evaluations were obtained by use of a generalized least-squares approach with calculations being performed with the computer code FERRET. These results will provide the major revisions to the ENDF/B-IV Fission Product Cross Section File which will be released as part of ENDF/B-V. Input for the cross section adjustment calculations included both integral and differential experimental data results. The differential cross sections and their uncertainties were obtained from the CSIRS library. Integral measurement results came from CFRMF and STEK Assemblies 500, 1000, 2000, 3000, and 4000. Comparisons of these evaluations with recent capture measurements are presented. 14 figures.

Download or read book Proceedings written by and published by . This book was released on 1971 with total page 502 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book NBS Special Publication written by and published by . This book was released on 1980 with total page 1058 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Nuclear Cross Sections for Technology written by Joseph L. Fowler and published by . This book was released on 1980 with total page 1062 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Review of Cross Section Data Important to the Uranium plutonium Fuel Cycle in Thermal Reactors written by and published by . This book was released on 1978 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The present state of knowledge concerning the cross sections, etc., of the isotopes 235U, 238U, 239Pu, 24°Pu, and 241Pu is discussed. Most cross sections important to the design of U--Pu-fueled light-water reactors with current fuel--water ratios are known with reasonable accuracy. The three most serious discrepancies remaining are the following: the difference between integral measurements and differential calculations of 238U resonance capture, the discrepancy between irradiation experiments and other measurements of the ratio of capture to fission in 235U, and the uncertainty in the parameters of the 1 eV resonance of 24°Pu. 2 figures, 2 tables. (RWR).

Download or read book A Detailed Report on the Simultaneous Evaluation of the Fission Cross sections of U 235 Pu 239 and U 238 and the U 238 Capture Cross section in the Energy Range 100 EV to 20 MeV written by M. G. Sewerby and published by . This book was released on 1973 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book An Evaluation and Compilation of the Fission and Capture Cross Sections of 239Pu in the Energy Range 25 KeV 15 MeV written by N. M. Greene and published by . This book was released on 1970 with total page 48 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Review of Fast neutron Capture Cross Sections of the Higher Plutonium Isotopes and Am 241 written by and published by . This book was released on 1982 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The fast-neutron capture cross sections of Pu-240, 241, 242 and Am-241 are reviewed. These nuclides are important to core physics of reactors that contain Pu-239. There have been several significant measurements of these cross sections in recent years. These measurements were instigated by the need for these cross sections for reactor calculations involving high burn-up and build-up of the higher actinides. These recent measurements have satisfied the urgent need for these cross sections in the context of the accuracy needed relative to these of the major fissile isotopes. Problems that exist in the experimental measurements and their evaluation are discussed.

Download or read book Evaluation and Compilation of Pu 239 Cross Section Data for the ENDF written by P. Greebler and published by . This book was released on 1966 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:

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 Evaluation for ENDF written by and published by . This book was released on 1976 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Capture and fission cross sections for 235U in the ''unresolved resonance'' energy region were evaluated to permit determination of local-average resonance parameters for the ENDF/B-IV cross section file. Microscopic data were examined for infinitely dilute average fission and capture cross sections and also for intermediate structure unlikely to be reproduced by statistical fluctuations of resonance widths and spacings within known laws. Evaluated cross sections, averaged over lethargy intervals greater than 0.1, were obtained as an average over selected data sets after appropriate renormalization. Estimated uncertainties are given for these evaluated average cross sections. The ''intermediate'' structure fluctuations common to a few independent data sets were approximated by straight lines joining successive cross sections at 120 selected energy points; the cross sections at the vertices were adjusted to reproduce the evaluated average cross sections over the broad energy regions. Data sources and methods are reviewed, output values are tabulated, and some modified procedures are suggested for future evaluations. Evaluated fission and capture integrals for the resolved resonance region are also tabulated. These are not in agreement with integrals based on the resonance parameters of ENDF/B versions III and IV. 8 tables, 5 figures.

Download or read book Fission Total and Neutron Capture Cross Section Measurements at ORELA written by and published by . This book was released on 1998 with total page 6 pages. Available in PDF, EPUB and Kindle. Book excerpt: In support of the Nuclear Criticality Predictability Program established in response to the Defense Nuclear Facility Safety Board Recommendation 93-2, time-of-flight (TOF) measurements of the fission cross sections of 233U in the neutron energy range from 0.36 eV to several hundred keV have been initiated at the Oak Ridge Electron Linear Accelerator (ORELA). Also total and capture cross sections of Al, Cl, and K in the energy range from about 100 eV to several hundred keV have been measured or are under way. The goal is to derive accurate cross section representations for the materials involved in criticality calculations of fuel storage, transportation, etc., configurations. Additional high-resolution measurements of the total cross sections of 233U below a few keV neutron energy are being planned for 1998, as well as for the other involved material. Evaluated data files in ENDF-6 format will be processed into formats for use in criticality analysis and utilized in benchmark data testing. Finally the data will be submitted for inclusion in ENDF/B.

Download or read book Evaluation of the Cross Sections of Iron Endf b Mat 1101 written by D. C. Irving and published by . This book was released on 1970 with total page 13 pages. Available in PDF, EPUB and Kindle. Book excerpt: The neutron cross sections for iron have been evaluated and placed in the ENDF/B format with the material (MAT) number 1101. The total cross section was evaluated from recent experimental measurements and is compatible with measurements from very thick sample penetration made at the Tower Shielding Facility. Other data were taken from evaluations by J.J. Schmidt as contained in the UKAEA Nuclear Data File, DFN 64. (Author).