The Fission Cross Sections of 23°Th, 232Th, 233U, 234U, 236U, 238U, 237Np, 239Pu and 242Pu Relative 235U at 14. 74 MeV Neutron Energy
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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Published: 1986

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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.

The Fission Cross Section Ratios and Error Analysis for Ten Thorium, Uranium, Neptunium and Plutonium Isotopes at 14. 74 MeV Neutron Energy
The Fission Cross Section Ratios and Error Analysis for Ten Thorium, Uranium, Neptunium and Plutonium Isotopes at 14. 74 MeV Neutron Energy

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Published: 1987

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The error information from the recent measurements of the fission cross section ratios of nine isotopes, 23°Th, 232Th, 233U, 234U, 236U, 238U, 237Np, 239Pu, and 242Pu, relative to 235U at 14.74 MeV neutron energy was used to calculate their correlations. The remaining 36 non-trivial and non-reciprocal cross section ratios and their errors were determined and compared to evaluated (ENDF/B-V) values. There are serious differences but it was concluded that the reduction of three of the evaluated cross sections would remove most of them. The cross sections to be reduced are 23°Th - 13%, 237Np - 9.6% and 239Pu - 7.6%. 5 refs., 6 tabs.

Measurement of 233U Fission Spectrum-Averaged Cross Sections for Some Threshold Reactions
Measurement of 233U Fission Spectrum-Averaged Cross Sections for Some Threshold Reactions

Author: K. Kobayashi

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Published: 1994

Total Pages: 7

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The 233U fission spectrum-averaged cross sections for twelve threshold reactions were measured relative to the average cross section of 0.688±0.040 mb for the 27Al(n,?)24Na reaction. The reference value was obtained by calculation using the energy dependent cross section in the Japanese Evaluated Nuclear Data Library (JENDL) Dosimetry File and the Watt-type fission spectrum in ENDF/B-VI. General agreement was seen between the measured and the calculated fission-spectrum averaged cross sections. However, there exist discrepancies of more than 10 % between the measured and the calculated average cross sections for the 24Mg(n,p)24Na, 47Ti(n,p)47Sc, and 64Zn(n,p)64Cu reactions. The tendencies in the calculated-to-measured ratios are similar to those for 235U fission spectrum-averaged cross sections we previously measured.

Proceedings of the NEANDC/NEACRP Specialists Meeting on Fast Neutron Fission Cross Sections of U-233, U-235, U-238, and Pu-239, June 28--30, 1976, at Argonne National Laboratory
Proceedings of the NEANDC/NEACRP Specialists Meeting on Fast Neutron Fission Cross Sections of U-233, U-235, U-238, and Pu-239, June 28--30, 1976, at Argonne National Laboratory

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Published: 1976

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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.