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Title: Measurement of the neutron capture and fission cross sections of $sup 239$Pu and $sup 235$U, 0.02 eV to 200 keV, the neutron capture cross sections of $sup 197$Au, 10 to 50 keV, and neutron fission cross sections of $sup 233$U, 5 to 200 keV

Abstract

The neutron absorption and fission cross sections for $sup 239$Pu and $sup 235$U have been measured over the neutron energy range from 0.02 eV to 200 keV. In addition, the neutron capture cross section for $sup 197$Au was measured from 10 to 50 keV and the fission cross section of $sup 233$U was measured from 0.1 to 100 keV. Normalization of the $sup 239$Pu and $sup 235$U data was made over the energy region from 0.02 to 0.4 eV to the ENDF/B-III neutron cross sections for these isotopes, Mat 1159 and 1157, respectively. The capture cross section for $sup 197$Au was normalized using the saturated resonance method for the 4.9-eV resonance. For $sup 233$U fission, the normalization was made using the results of Weston et al. The neutron flux was measured using the $sup 10$B(n,$alpha$) reaction; the energy variation used for this reaction was that given in ENDF/B-III. A large liquid scintillator about 40 m from the neutron source was used to detect the prompt gamma-ray cascades resulting from neutron absorption in the sample. In general for $sup 239$Pu and $sup 235$U, these experiments indicated lower neutron fission cross sections than contained in ENDF/ B-III for energies above 10 keV.more » The measured values of the ratio $alpha$, neutron capture-to-neutron fission, for $sup 239$Pu agree within errors with those derived from ENDF/B-III, Mat 1159. For the present measurements, the uncertainty on $alpha$ for $sup 239$Pu is approximately 11 percent at 10 keV and increases to approximately 30 percent at 100 keV. The experimental results for the neutron capture cross section for $sup 197$Au are approximately 15 percent lower than the ENDF/B-III values. The measurements of the ratio of the neutron fission cross section for $sup 233$U to that for $sup 235$U are generally higher than the ENDF/B-III values by approximately 5 percent. 15 tables, 11 figures. (auth)« less

Authors:
; ; ;
Publication Date:
Research Org.:
Oak Ridge National Lab., TN
OSTI Identifier:
4093952
NSA Number:
NSA-33-027761
Resource Type:
Journal Article
Journal Name:
Nucl. Sci. Eng., v. 59, no. 2, pp. 79-105
Additional Journal Information:
Other Information: Orig. Receipt Date: 30-JUN-76
Country of Publication:
United States
Language:
English
Subject:
N69161* -Physics (Nuclear, Experimental)-Nuclear Properties & Reactions, A >= 220-Nuclear Reactions & Scattering-Spontaneous & Induced Fission:734; N68951 -Physics (Nuclear, Experimental)-Nuclear Properties & Reactions, 190 <= A <= 219-Nuclear Reactions & Scattering; 643406*; *GOLD 197 TARGET- NEUTRON REACTIONS; *GOLD 197- NEUTRON REACTIONS; *PLUTONIUM 239 TARGET- NEUTRON REACTIONS; *PLUTONIUM 239- NEUTRON REACTIONS; *URANIUM 235 TARGET- NEUTRON REACTIONS; *URANIUM 235- NEUTRON REACTIONS; CAPTURE- GAMMA RADIATION- GOLD 198- PLUTONIUM 240- URANIUM 236; CAPTURE-TO-FISSION RATIO; CROSS SECTIONS; RESONANCE FISSION- URANIUM 233- URANIUM 233 TARGET

Citation Formats

Gwin, R, Silver, E G, Ingle, R W, and Weaver, H. Measurement of the neutron capture and fission cross sections of $sup 239$Pu and $sup 235$U, 0.02 eV to 200 keV, the neutron capture cross sections of $sup 197$Au, 10 to 50 keV, and neutron fission cross sections of $sup 233$U, 5 to 200 keV. United States: N. p., 1976. Web.
Gwin, R, Silver, E G, Ingle, R W, & Weaver, H. Measurement of the neutron capture and fission cross sections of $sup 239$Pu and $sup 235$U, 0.02 eV to 200 keV, the neutron capture cross sections of $sup 197$Au, 10 to 50 keV, and neutron fission cross sections of $sup 233$U, 5 to 200 keV. United States.
Gwin, R, Silver, E G, Ingle, R W, and Weaver, H. 1976. "Measurement of the neutron capture and fission cross sections of $sup 239$Pu and $sup 235$U, 0.02 eV to 200 keV, the neutron capture cross sections of $sup 197$Au, 10 to 50 keV, and neutron fission cross sections of $sup 233$U, 5 to 200 keV". United States.
@article{osti_4093952,
title = {Measurement of the neutron capture and fission cross sections of $sup 239$Pu and $sup 235$U, 0.02 eV to 200 keV, the neutron capture cross sections of $sup 197$Au, 10 to 50 keV, and neutron fission cross sections of $sup 233$U, 5 to 200 keV},
author = {Gwin, R and Silver, E G and Ingle, R W and Weaver, H},
abstractNote = {The neutron absorption and fission cross sections for $sup 239$Pu and $sup 235$U have been measured over the neutron energy range from 0.02 eV to 200 keV. In addition, the neutron capture cross section for $sup 197$Au was measured from 10 to 50 keV and the fission cross section of $sup 233$U was measured from 0.1 to 100 keV. Normalization of the $sup 239$Pu and $sup 235$U data was made over the energy region from 0.02 to 0.4 eV to the ENDF/B-III neutron cross sections for these isotopes, Mat 1159 and 1157, respectively. The capture cross section for $sup 197$Au was normalized using the saturated resonance method for the 4.9-eV resonance. For $sup 233$U fission, the normalization was made using the results of Weston et al. The neutron flux was measured using the $sup 10$B(n,$alpha$) reaction; the energy variation used for this reaction was that given in ENDF/B-III. A large liquid scintillator about 40 m from the neutron source was used to detect the prompt gamma-ray cascades resulting from neutron absorption in the sample. In general for $sup 239$Pu and $sup 235$U, these experiments indicated lower neutron fission cross sections than contained in ENDF/ B-III for energies above 10 keV. The measured values of the ratio $alpha$, neutron capture-to-neutron fission, for $sup 239$Pu agree within errors with those derived from ENDF/B-III, Mat 1159. For the present measurements, the uncertainty on $alpha$ for $sup 239$Pu is approximately 11 percent at 10 keV and increases to approximately 30 percent at 100 keV. The experimental results for the neutron capture cross section for $sup 197$Au are approximately 15 percent lower than the ENDF/B-III values. The measurements of the ratio of the neutron fission cross section for $sup 233$U to that for $sup 235$U are generally higher than the ENDF/B-III values by approximately 5 percent. 15 tables, 11 figures. (auth)},
doi = {},
url = {https://www.osti.gov/biblio/4093952}, journal = {Nucl. Sci. Eng., v. 59, no. 2, pp. 79-105},
number = ,
volume = ,
place = {United States},
year = {Sun Feb 01 00:00:00 EST 1976},
month = {Sun Feb 01 00:00:00 EST 1976}
}