Measurement Of The Neutron Induced Fission Cross Section Of 232th Relative To 235u From 0 7 To 30 Mev 0 7 To 30 Mev
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Release | : 1977 |
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Download Measurement of the Neutron-induced Fission Cross Section of 232Th Relative to 235U from 0. 7 to 30 MeV. [0. 7 to 30 MeV]. Book in PDF, Epub and Kindle
Continuing fission cross section ratio studies at Lawrence Livermore Laboratory, one has measured the 232Th/235U fission cross-section ratio from 0.7 to 30 MeV. Using the threshold method, one obtained a value of 0.1081 +- 0.0022 for the average cross-section ratio in the interval from 1.75 to 4.00 MeV.
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Release | : 1976 |
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Download Measurements of the Neutron-induced Fission Cross Sections of 24°Pu and 242Pu Relative to 235U. [0. 02 to 30 MeV, Tables]. Book in PDF, Epub and Kindle
A continuation is given of the fission-cross-section ratio measurements in progress at the Lawrence Livermore Laboratory. Preliminary results are provided for the 24°Pu/235U and 242Pu/235U ratios from 0.02 to 30 MeV and 0.1 to 30 MeV, respectively. Using the threshold-cross-section method, the ratios were normalized to the values 1.368 +- 0.030 and 1.116 +- 0.025, respectively, from 1.75 to 4.00 MeV.
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Release | : 1977 |
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Download Measurement of the Neutron-induced Fission Cross-section of 243Am Relative to 235U from 0. 1 MeV to 30 MeV. Book in PDF, Epub and Kindle
Continuing studies of fission cross-section ratios at Lawrence Livermore Laboratory have led to the measurement of the 243Am/235U fission cross-section ratio from 0.1 to 30 MeV. A value of 1.429 +- 0.037 was obtained for the average cross-section ratio from 1.75 to 4.00 MeV by use of the threshold method. 2 figures, 1 table.
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Release | : 1976 |
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Download Measurement of the Neutron-induced Fission Cross Section of 244Pu Relative to 235U from 0. 2 to 30 MeV. Book in PDF, Epub and Kindle
Continuing fission cross section ratio studies at Lawrence Livermore Laboratory, preliminary results have been determined for the 244Pu/235U fission cross section ratio from 0.2 to 30 MeV. Using the threshold method, the value 0.980 +- 0.021 has been obtained for the average cross section ratio in the interval from 1.75 to 4.00 MeV.
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Release | : 1986 |
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Download The Fission Cross Sections of 23°Th, 232Th, 233U, 234U, 236U, 238U, 237Np, 239Pu and 242Pu Relative 235U at 14. 74 MeV Neutron Energy Book in PDF, Epub and Kindle
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.
Author | : J. W. Behrens |
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Total Pages | : 3 |
Release | : 1975 |
Genre | : Cross sections |
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Download Preview of a Measurement of the Neutron-induced Fission Cross Section of 241Pu Relative to 235U from 0.1 to 30 MeV Book in PDF, Epub and Kindle
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Release | : 1988 |
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Download Neutron Induced Fission Cross Section Ratios for 232Th Book in PDF, Epub and Kindle
Time-of-flight measurements of neutron induced fission cross section ratios for 232Th, /sup 235,238/U, 237Np, and 239Pu, were performed using the WNR high intensity spallation neutron source located at Los Alamos National Laboratory. A multiple-plate gas ionization chamber located at a 20-m flight path was used to simultaneously measure the fission rate for all samples over the energy range from 1 to 400 MeV. Because the measurements were made with nearly identical neutron fluxes, we were able to cancel many systematic uncertainties present in previous measurements. This allows us to resolve discrepancies among different data sets. In addition, these are the first neutron-induced fission cross section values for most of the nuclei at energies above 30 MeV. 8 refs., 3 figs.
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Release | : 1975 |
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Download Measurement of the Neutron-induced Fission Cross Section of 241Pu Relative to 235U from 0.001 to 30 MeV. Book in PDF, Epub and Kindle
The ratio of the neutron-induced fission cross sections of 241Pu relative to that of 235U was measured with fission ionization chambers at the LLL 100-MeV electron linear accelerator. The time-of-flight technique was used to measure the cross-section ratio as a function of neutron energy from 0.001 to 30 MeV. The continuous energy spectrum of the neutron source allowed us to cover the entire energy range in one measurement. Pulse height distributions were also measured as functions of energy over broad energy bands. These data were used to estimate the energy variation in the efficiency to be less than 0.75 percent. The threshold cross-section method normalized the ratio independent of other cross-section measurements to 1.268 +- 0.022 in the interval 1.75 to 4.00 MeV. The ratio was also taken to thermal neutron energy where it was normalized to evaluated thermal fission cross sections and the resulting ratio in the 1.75- to 4.00-MeV interval was 1.242 +- 0.021. Corrected for the impurities in the 241Pu sample, the average of these two values resulted in a $sup 241$Pu:235U fission cross-section ratio of 1.251 +- 0.016 for the normalization interval. Typical energy resolution is 5 percent at 20.0, 1.0, and 0.1 MeV. Most of the data have counting uncertainties smaller than 4 percent, expressed as a standard deviation. Systematic errors are discussed, and current results are compared with previous measurements. Tables of our data are included. (9 tables, 8 figures) (auth).
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Release | : 1979 |
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Download Fission Cross Section of 239Th and 232Th Relative to 235U. [Threshold to 10 MeV, Cross Sections]. Book in PDF, Epub and Kindle
The fission cross sections of 23°Th and 232Th were measured relative to 235U from near threshold to near 10 MeV. The weights of the thorium samples were determined by isotopic dilution. The weight of the uranium deposit was based on specific activity measurements of a 234U-235U mixture and low geometry alpha counting. Corrections were made for thermal background, loss of fragments in the deposits, neutron scattering in the detector assembly, sample geometry, sample composition and the spectrum of the neutron source. Generally the systematic errors were approx. 1%. The combined systematic and statistical errors were typically 1.5%. 17 references.
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Total Pages | : 1292 |
Release | : 1976 |
Genre | : Nuclear energy |
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