THE "REACTOR" NEUTRON CAPTURE CROSS SECTION OF Y91

1960 ◽  
Vol 38 (12) ◽  
pp. 1690-1701
Author(s):  
Gwen M. Milton ◽  
W. E. Grummitt
Keyword(s):  
Cross Section ◽  
Neutron Capture ◽  
Capture Cross Section ◽  
Specific Activity ◽  
High Specific Activity ◽  
Natural Uranium ◽  
Reactor Neutron ◽  
Capture Cross ◽  
Neutron Capture Cross Section ◽  
Chemical Purification

A high specific activity source of Y91, freed from natural uranium and rare earths, was irradiated in a high flux position in the NRX reactor. After further chemical purification, 3.6-hour Y92 was identified in the sample by measurement of the 3.6-Mev β-particle associated with its decay, using a scintillation spectrometer. Two such measurements have established the reactor neutron capture cross section of Y91 to be 1.4 ± 0.3 barns.

THE REACTOR NEUTRON CAPTURE CROSS SECTION OF 124Sb

1966 ◽  
Vol 44 (11) ◽  
pp. 2956-2959 ◽  
Author(s):  
R. Courtemanche ◽  
T. A. Eastwood ◽  
R. D. Werner
Keyword(s):  
Cross Section ◽  
Neutron Capture ◽  
Capture Cross Section ◽  
Reactor Neutron ◽  
Capture Cross ◽  
Neutron Capture Cross Section

THE REACTOR NEUTRON CAPTURE CROSS SECTION OF Ag110m

1963 ◽  
Vol 41 (8) ◽  
pp. 1321-1331
Author(s):  
R. G. Hart ◽  
R. L. Graham
Keyword(s):  
Neutron Flux ◽  
Cross Section ◽  
Neutron Capture ◽  
Capture Cross Section ◽  
Thermal Neutron Flux ◽  
Reactor Neutron ◽  
Capture Cross ◽  
Neutron Capture Cross Section ◽  
A Value ◽  
Measured Ratio

Natural silver has been irradiated for 75.3 days in a thermal neutron flux of 2.42 × 1014 cm−2 sec−1 and the complex beta-ray spectrum of the resulting activities of 249-day Ag110m and 7.5-day Ag111 have been studied with a magnetic spectrometer. From the measured ratio of the respective beta-ray intensities and using the currently accepted decay schemes of these nuclides a value of 82 ± 11 barns is obtained for the reactor neutron capture cross section of Ag110m. Possible causes of systematic error are discussed.

REACTOR NEUTRON-CAPTURE CROSS SECTION OF 18-MINUTE Rb88

1958 ◽  
Vol 36 (5) ◽  
pp. 731-736 ◽  
Author(s):  
J. C. Roy ◽  
P. J. Berry ◽  
L. P. Roy
Keyword(s):  
Beta Decay ◽  
Cross Section ◽  
Neutron Capture ◽  
Capture Cross Section ◽  
Activation Method ◽  
Reactor Neutron ◽  
Capture Cross ◽  
Neutron Capture Cross Section ◽  
The Cross ◽  
Thermal Cross Section

The reactor neutron-capture cross section of 18-minute Rb88 has been determined by an activation method. The yield of Rb89 formed by successive neutron capture in Rb87 was determined by counting the beta rays emitted by its daughter, 51-day Sr89. In these experiments Sr89 is also produced by the Sr88(n, γ)Sr89 reaction from the Sr88 contamination in the rubidium target and from Sr88 formed by the beta decay of Rb88. Corrections for the contributions from these sources to the yield of Sr89 have been measured experimentally. The reactor neutron-capture cross section of Sr88 has been measured to be 5.8 mb. for the conditions of the experiment. Taking 0.12 ± 0.3 barn for the thermal cross section of Rb87, the cross section of Rb88 was found to be 1.0 ± 0.3 barn for reactor neutrons.

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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