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

Publisher:

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.