ABSOLUTE MEASUREMENTS OF THE FAST NEUTRON CAPTURE CROSS-SECTION OF URANIUM-238 (URANIUM-238, ANTIMONY-BERYLLIUM, SODIUM-BERYLLIUM, PHOTO-NEUTRONS). PDF Download
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Author: EIPING QUANG
Publisher:
ISBN:
Category :
Languages : en
Pages : 188
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Book Description
The absolute cross sections obtained for the $\sp{238}$U(n,$\gamma$)$\sp{239}$U reaction were 494 $\pm$ 11 and 138 $\pm$ 5 millibarns at 23 and 967 keV, respectively.
Author: EIPING QUANG
Publisher:
ISBN:
Category :
Languages : en
Pages : 188
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Book Description
The absolute cross sections obtained for the $\sp{238}$U(n,$\gamma$)$\sp{239}$U reaction were 494 $\pm$ 11 and 138 $\pm$ 5 millibarns at 23 and 967 keV, respectively.
![Evaluated Fast Neutron Cross Sections of Uranium-238. [0. 045 to 20. 0 MeV]. PDF](https://books.google.com/books/content/images/frontcover/RgCxAQAACAAJ?fife=w80-h100)
Author:
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Category :
Languages : en
Pages :
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An evaluated fast neutron data file of 238U is presented in the ENDF/B format. The incident energy range extends from 0.045 to 20.0 MeV. The content consists of: (1) neutron total cross sections, (2) fission cross sections, neutron emission spectra and associated properties, (4) neutron radiative-capture cross sections, (5) (n;2n') and (n;3n') processes, and (6) photon-production cross sections and spectra. The methodology of the file derivation is outlined. File content is graphically illustrated and uncertainty estimates are given. Comparisons with comparable portions of ENDF/B-IV are made and some large differences are noted. Some results of integral ''benchmark'' tests using this file are outlined. Many of the components of this file are those explicitly submitted for ENDF/B, Version V.
Author: W. P. Poenitz
Publisher:
ISBN:
Category : Fast neutrons
Languages : en
Pages : 67
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Author:
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ISBN:
Category : Dissertations, Academic
Languages : en
Pages : 796
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Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :
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Data files of all available data of absolute cross section measurements of U-233, U-235, U-238 and Pu-239, and of the ratios of U-233, U-238, and Pu-239 to U-235 were assembled at Argonne National Laboratory for use by the two Working Groups. The data files of absolute cross sections included also data measured relative to one of the standard cross sections H(n, n), Li-6(n, .cap alpha.), and B-10(n, .cap alpha.), and the ratio data files included ratios derived from absolute values which were measured in an identical type of experiment by the same group of experimenters. The subject files (e.g., U-235-Absolute, or U-238/U-235-Ratio, etc.) consisted of ''Sets.'' These sets contained the data from one experimental group which may have been published at different times. The assembling of the files was started with an extract from the CSISRS data files of the National Neutron Cross Section Center at the Brookhaven National Laboratory. Ratios were derived from quoted consistent sets of absolute cross sections, or from data which were actually measured as ratios but quoted as absolute values. The latter type of data was eliminated from the data files on absolute values. The files were improved by an extensive search for errors and data missing on the original CSISRS files at the time the extract was made. Other additions to the present subject files came from presentations made at this meeting and are described in the proceedings.
Author: L.P. Abagyan
Publisher:
ISBN:
Category : Cross sections
Languages : en
Pages : 29
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Author: JI-PENG CHIEN
Publisher:
ISBN:
Category :
Languages : en
Pages : 115
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Author: International Atomic Energy Agency
Publisher: IAEA Radiation Technology Repo
ISBN: 9789201251107
Category : Science
Languages : en
Pages : 145
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Book Description
This publication addresses recent developments in neutron generator (NG) technology. It presents information on compact instruments with high neutron yield to be used for neutron activation analysis (NAA) and prompt gamma neutron activation analysis in combination with high count rate spectrometers. Traditional NGs have been shown to be effective for applications including borehole logging, homeland security, nuclear medicine and the on-line analysis of aluminium, coal and cement. Pulsed fast thermal neutron analysis, as well as tagged and timed neutron analysis, are additional techniques which can be applied using NG. Furthermore, NG can effectively be used for elemental analysis and is also effective for analysis of hidden materials by neutron radiography. Useful guidelines for developing NG based research laboratories are also provided in this publication.
Author:
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ISBN:
Category : Aeronautics
Languages : en
Pages : 1330
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Author:
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ISBN:
Category : Technology & Engineering
Languages : en
Pages : 272
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