Fuel Material Analysis Using Radioactive Thermal Neutron Capture

1979 ◽  
pp. 710-713 ◽  
Author(s):  
B. R. S. Pecequilo ◽  
A. A. Suarez
Keyword(s):  
Thermal Neutron ◽  
Neutron Capture ◽  
Thermal Neutron Capture ◽  
Material Analysis ◽  
Fuel Material

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.

Levels of 188Re nucleus populated in thermal neutron capture reaction

2016 ◽  
Vol 947 ◽  
pp. 76-126 ◽  
Author(s):  
J. Bērziņš ◽  
T. Krasta ◽  
L. Simonova ◽  
M. Balodis ◽  
V. Bondarenko ◽  
...  
Keyword(s):  
Thermal Neutron ◽  
Neutron Capture ◽  
Thermal Neutron Capture ◽  
Neutron Capture Reaction ◽  
Capture Reaction
Sign in / Sign up

Export Citation Format

Share Document