Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
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).
Measurement of the Neutron-induced Fission Cross Section of 241Pu Relative to 235U from 0.001 to 30 MeV.
Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
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).
Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
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).
Preview of a Measurement of the Neutron-induced Fission Cross Section of 241Pu Relative to 235U from 0.1 to 30 MeV
Author: J. W. Behrens
Publisher:
ISBN:
Category : Cross sections
Languages : en
Pages : 3
Book Description
Publisher:
ISBN:
Category : Cross sections
Languages : en
Pages : 3
Book Description
Measurement of the Neutron-induced Fission Cross-section of 243Am Relative to 235U from 0. 1 MeV to 30 MeV.
Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
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.
Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
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.
ERDA Energy Research Abstracts
Author: United States. Energy Research and Development Administration
Publisher:
ISBN:
Category : Medicine
Languages : en
Pages : 988
Book Description
Publisher:
ISBN:
Category : Medicine
Languages : en
Pages : 988
Book Description
ERDA Research Abstracts
Author: United States. Energy Research and Development Administration
Publisher:
ISBN:
Category : Power resources
Languages : en
Pages : 780
Book Description
Publisher:
ISBN:
Category : Power resources
Languages : en
Pages : 780
Book Description
ERDA Energy Research Abstracts
Author: United States. Energy Research and Development Administration. Technical Information Center
Publisher:
ISBN:
Category : Force and energy
Languages : en
Pages : 788
Book Description
Publisher:
ISBN:
Category : Force and energy
Languages : en
Pages : 788
Book Description
Nuclear Science Abstracts
Author:
Publisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 1026
Book Description
Publisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 1026
Book Description
Publications of the National Bureau of Standards ... Catalog
Author: United States. National Bureau of Standards
Publisher:
ISBN:
Category :
Languages : en
Pages : 612
Book Description
Publisher:
ISBN:
Category :
Languages : en
Pages : 612
Book Description
Measurements of the Neutron-induced Fission Cross Sections of 24°Pu and 242Pu Relative to 235U. [0. 02 to 30 MeV, Tables].
Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
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.
Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
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.
Energy Research Abstracts
Author:
Publisher:
ISBN:
Category : Power resources
Languages : en
Pages : 548
Book Description
Publisher:
ISBN:
Category : Power resources
Languages : en
Pages : 548
Book Description