Tables of Neutron-Induced Fission Cross Section for Various Pu, U, and Th Isotopes, Deduced from Measured Fission Probabilites

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Book Synopsis Tables of Neutron-Induced Fission Cross Section for Various Pu, U, and Th Isotopes, Deduced from Measured Fission Probabilites by : W. Younes

Download or read book Tables of Neutron-Induced Fission Cross Section for Various Pu, U, and Th Isotopes, Deduced from Measured Fission Probabilites written by W. Younes and published by . This book was released on 2003 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Cross sections for neutron-induced fission of {sup 231,233}Th, {sup 234,235,236,237,239}U, and {sup 240,241,243}Pu are presented in tabular form for incident neutron energies of 0.1 {le} E{sub n}(MeV) {le} 2.5. The cross sections were obtained by converting measured fission probabilities from (t, pf) reactions on mass-A targets to (n, f) cross sections on mass-A + 1 neutron targets, by using modeling to compensate for the differences in the reaction mechanisms. Data from Britt et al. were used for the {sup 234}U(t, pf) reaction, from Cramer et al. for the {sup 230,232}Th(t, pf), {sup 236,238}U(t, pf), and {sup 240,242}Pu(t, pf) reactions, and from Britt et al. for the {sup 233,235}U(t, pf) and {sup 239}Pu(t, pf) reactions. The fission probabilities P{sub (t, pf)}(E{sub x}), measured as a function of excitation energy E{sub x} of the compound system formed by the (t, p) reaction, are listed in the tables with the corresponding deduced cross sections as a function of incident neutron energy E{sub n}, {sigma}{sub (n, f)}(E{sub n}). The excitation energy and incident neutron energy are related by E{sub x} = E{sub n} + B{sub n}, where B{sub n}, where B{sub n} is the neutron binding energy. Comparison with ENDF/B-VI evaluations of the well-measured {sup 234,235,236}U(n, f) and {sup 240,241}Pu(n, f) cross sections confirms the accuracy of the present results within a 10% standard deviation above E{sub n} = 1 MeV. Below E{sub n} = 1 MeV, localized deviations of at most {+-} 20% are observed.

Nuclear Cross Sections and Technology

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Total Pages : 500 pages
Book Rating : 4.3/5 (91 download)

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Book Synopsis Nuclear Cross Sections and Technology by : Roald A. Schrack

Download or read book Nuclear Cross Sections and Technology written by Roald A. Schrack and published by . This book was released on 1975 with total page 500 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Nuclear Science Abstracts

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Total Pages : 554 pages
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Download or read book Nuclear Science Abstracts written by and published by . This book was released on 1974 with total page 554 pages. Available in PDF, EPUB and Kindle. Book excerpt:

ERDA Energy Research Abstracts

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Total Pages : 920 pages
Book Rating : 4.3/5 (243 download)

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Book Synopsis ERDA Energy Research Abstracts by : United States. Energy Research and Development Administration

Download or read book ERDA Energy Research Abstracts written by United States. Energy Research and Development Administration and published by . This book was released on 1976 with total page 920 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Energy Research Abstracts

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Total Pages : 436 pages
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Download or read book Energy Research Abstracts written by and published by . This book was released on 1982 with total page 436 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Romanian Reports in Physics

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Total Pages : 1074 pages
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INIS Atomindeks

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Total Pages : 960 pages
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Download or read book INIS Atomindeks written by and published by . This book was released on 1988 with total page 960 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Measurements of Neutron-induced Fission Cross-section Ratios Involving Isotopes of Uranium and Plutonium. [0. 001 to 30 MeV, Cross Sections].

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Book Synopsis Measurements of Neutron-induced Fission Cross-section Ratios Involving Isotopes of Uranium and Plutonium. [0. 001 to 30 MeV, Cross Sections]. by :

Download or read book Measurements of Neutron-induced Fission Cross-section Ratios Involving Isotopes of Uranium and Plutonium. [0. 001 to 30 MeV, Cross Sections]. written by and published by . This book was released on 1976 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: A procedure, called the threshold cross section method was applied to our experimental data involving four uranium (233U 234U, 236U, and 238U) and five plutonium (239Pu, 24°Pu, 241Pu, 242Pu, and 244Pu) isotopes to determine ratios of fission cross sections relative to 235U. The data were gathered using ionization fission chambers and the time-of-flight technique at the LLL 100-MeV electron linear accelerator: measurements span the neutron energy range of 0.001 to 30 MeV. Experimental uncertainties common to past measurements were either eliminated or significantly reduced in this study by use of the threshold method, thereby making higher accuracies possible. The cross section ratios are absolute in the sense that they do not depend on the work of others. Results from our ratios involving 233U, 235U, 238U, and 239Pu are used to illustrate this method.

ERDA Energy Research Abstracts

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Total Pages : 962 pages
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Book Synopsis ERDA Energy Research Abstracts by : United States. Energy Research and Development Administration. Technical Information Center

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Scientific and Technical Aerospace Reports

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Total Pages : 1338 pages
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Soviet Journal of Nuclear Physics

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Total Pages : 982 pages
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International Conference on Nuclear Data for Science and Technology

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Publisher : American Institute of Physics
ISBN 13 :
Total Pages : 1158 pages
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Book Synopsis International Conference on Nuclear Data for Science and Technology by : Robert C. Haight

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The Fission Cross Sections of 23°Th, 232Th, 233U, 234U, 236U, 238U, 237Np, 239Pu and 242Pu Relative 235U at 14. 74 MeV Neutron Energy

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Book Synopsis The Fission Cross Sections of 23°Th, 232Th, 233U, 234U, 236U, 238U, 237Np, 239Pu and 242Pu Relative 235U at 14. 74 MeV Neutron Energy by :

Download or read book The Fission Cross Sections of 23°Th, 232Th, 233U, 234U, 236U, 238U, 237Np, 239Pu and 242Pu Relative 235U at 14. 74 MeV Neutron Energy written by and published by . This book was released on 1986 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The measurement of the fission cross section ratios of nine isotopes relative to 235U at an average neutron energy of 14.74 MeV is described with particular attention to the determination of corrections and to sources of error. The results are compared to ENDF/B-V and to other measurements of the past decade. The ratio of the neutron induced fission cross section for these isotopes to the fission cross section for 235U are: 23°Th - 0.290 +- 1.9%; 232Th - 0.191 +- 1.9%; 233U - 1.132 +- 0.7%; 234U - 0.998 +- 1.0%; 236U - 0.791 +- 1.1%; 238U - 0.587 +- 1.1%; 237Np - 1.060 +- 1.4%; 239Pu - 1.152 +- 1.1%; 242Pu - 0.967 +- 1.0%. 40 refs., 11 tabs., 9 figs.

ERDA Energy Research Abstracts

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Total Pages : 1322 pages
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Book Synopsis ERDA Energy Research Abstracts by : United States. Energy Research and Development Administration

Download or read book ERDA Energy Research Abstracts written by United States. Energy Research and Development Administration and published by . This book was released on 1976 with total page 1322 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Nuclear Science and Engineering

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Total Pages : 956 pages
Book Rating : 4.:/5 (318 download)

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Download or read book Nuclear Science and Engineering written by and published by . This book was released on 1977 with total page 956 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Bromine: The element

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Total Pages : 556 pages
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Download or read book Bromine: The element written by and published by . This book was released on 1985 with total page 556 pages. Available in PDF, EPUB and Kindle. Book excerpt:

The 237U(n, F) Cross Section

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Total Pages : 10 pages
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Download or read book The 237U(n, F) Cross Section written by and published by . This book was released on 2003 with total page 10 pages. Available in PDF, EPUB and Kindle. Book excerpt: The purpose of this note is to combine existing information on the 237U(n, f) cross section to determine if some consistency can be obtained for the neutron induced fission excitation of 237U. The neutron induced fission cross section of the 6.8 day 237U was measured directly by McNally et al. in 1968 using the Pommard nuclear device test. At the same time critical assembly measurements were done at Los Alamos using the Flattop assembly. A previous measurement was also made at LASL in 1954 with two different neutron sources, each peaked near 200 keV. The results were 0.66 " 0.10 b and 0.70 " 0.07 b for the (n, f) cross section. More recently Younes and Britt have reanalyzed direct reaction charged particle data of Cramer and Britt that had determined the fission probability of the 238U compound nucleus as a function of nuclear excitation energy. They have combined fission probabilities with calculated neutron absorption cross sections, including corrections for the differences in angular momentum between the direct and neutron induced reactions. From this analysis they have extracted equivalent 237U(n, f) cross sections. The technique for extracting surrogate (n, f) cross sections from (t, pf) data has been demonstrated in a recent publication for the test case 235U(n, f). In addition to this experimental information, Lynn and Hayes have recently done a new theoretical study of the fission cross sections for a series of isotopes in this region. A summary plot of the data is shown in Fig. 1. Below 0.5 MeV the McNally, Cowan, and Younes-Britt results are in reasonable agreement. The average cross section in the Younes-Britt results, for En = 0.1 to 0.4 MeV, is 0.80 times the McNally values which is well within the errors of the McNally experiment. Above 0.5 MeV the McNally results diverge toward higher values. It should be noted that this divergence begins approximately at the 237Np threshold and that 237Np is the daughter of the 6.8 day 237U decay.