Relationship between capture coefficient and capture cross-section: Average velocity of a maxwellian distribution of carriers in a medium with an anisotropic effective mass tensor

1976 ◽  
Vol 9 (1) ◽  
pp. 79-81 ◽  
Author(s):  
C. R. Crowell
Keyword(s):  
Effective Mass ◽  
Cross Section ◽  
Average Velocity ◽  
Capture Cross Section ◽  
Maxwellian Distribution ◽  
Capture Cross ◽  
Capture Coefficient ◽  
Mass Tensor

Capture cross section of 242Pu

1970 ◽  
Vol 48 (6) ◽  
pp. 716-724 ◽  
Author(s):  
R. W. Durham ◽  
F. Molson
Keyword(s):  
Neutron Flux ◽  
Cross Section ◽  
Neutron Capture ◽  
Capture Cross Section ◽  
Maxwellian Distribution ◽  
Capture Cross ◽  
Neutron Capture Cross Section ◽  
Sample Tube ◽  
Isotopic Compositions ◽  
A Value

The neutron capture cross section of 242Pu has been measured by determining the 243Am product. Samples were irradiated in a neutron flux having essentially a Maxwellian distribution defined by the temperature (37.5 °C) of a water annulus around the sample tube. Plutonium and americium were separated from each other chemically and their concentrations and isotopic compositions obtained by low-geometry α counting and α spectrometry. A value for gσ0 of 18.7 ± 0.7 b was obtained where g represents the deviation from 1/v behavior.

Measurements of the neutron capture cross section of 243Am around 23.5 keV

2021 ◽  
pp. 1-6
Author(s):  
Yu Kodama ◽  
Tatsuya Katabuchi ◽  
Gerard Rovira ◽  
Atsushi Kimura ◽  
Shoji Nakamura ◽  
...  
Keyword(s):  
Cross Section ◽  
Neutron Capture ◽  
Capture Cross Section ◽  
Capture Cross ◽  
Neutron Capture Cross Section

THERMAL NEUTRON CAPTURE CROSS-SECTION OF Na23 AND Mn55

1953 ◽  
Vol 31 (3) ◽  
pp. 204-206 ◽  
Author(s):  
Rosalie M. Bartholomew ◽  
R. C. Hawkings ◽  
W. F. Merritt ◽  
L. Yaffe
Keyword(s):  
Thermal Neutron ◽  
Cross Section ◽  
Cross Sections ◽  
Neutron Capture ◽  
Half Life ◽  
Capture Cross Section ◽  
Thermal Neutron Capture ◽  
Capture Cross ◽  
Neutron Capture Cross Section ◽  
Capture Cross Sections

The thermal neutron capture cross sections of Na23 and Mn55 have been determined using the activation method. The values are 0.53 ± 0.03 and 12.7 ± 0.3 barns respectively with respect to σAul97 = 93 barns. These agree well with recent pile oscillator results. The half-life for Mn56 is found to be 2.576 ± 0.002 hr.

scholarly journals The 236U neutron capture cross-section measured at the n_TOF CERN facility

2017 ◽  
Vol 146 ◽  
pp. 11054
Author(s):  
M. Mastromarco ◽  
M. Barbagallo ◽  
M.J. Vermeulen ◽  
N. Colonna ◽  
S. Altstadt ◽  
...  
Keyword(s):  
Cross Section ◽  
Neutron Capture ◽  
Capture Cross Section ◽  
Capture Cross ◽  
Neutron Capture Cross Section
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