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.

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.

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

THERMAL NEUTRON CAPTURE CROSS SECTION OF Ce142

1956 ◽  
Vol 34 (8) ◽  
pp. 1023-1026 ◽  
Author(s):  
L. P. Roy ◽  
L. Yaffe
Keyword(s):  
Thermal Neutron ◽  
Cross Section ◽  
Neutron Capture ◽  
Capture Cross Section ◽  
Activation Method ◽  
Thermal Neutron Capture ◽  
Capture Cross ◽  
Neutron Capture Cross Section ◽  
A Value ◽  
The Cross

The cross section of Ce142 has been determined by the activation method and found to be 0.95 ± 0.05 barns relative to a value of σCo59 = 36.3 barns. Disintegration rates were determined by a 4π counter. The value obtained agrees with that of Katcoff etal. (1949) also obtained by the activation method but differs markedly from that of Pomerance (1952).

PILE NEUTRON CAPTURE CROSS SECTION OF 33 HR. Ce143

1956 ◽  
Vol 34 (3) ◽  
pp. 238-245 ◽  
Author(s):  
L. P. Roy ◽  
L. Yaffe
Keyword(s):  
Neutron Flux ◽  
Cross Section ◽  
Neutron Capture ◽  
Capture Cross Section ◽  
Capture Cross ◽  
Neutron Capture Cross Section ◽  
Neutron Capture Reaction ◽  
Capture Reaction

Ce144 has been produced by the successive neutron capture reaction Ce142 (n, γ)Ce143(n, γ)Ce144. The pile neutron capture cross section of the 33 hr. Ce143 was determined by separating Pr144, the daughter of Ce144, from the rigorously-purified cerium at frequent intervals. The amount of Pr144 formed increased linearly with the square of the neutron flux in a manner consistent with that of a successive neutron capture reaction. The value for the pile neutron capture cross section of Ce143 was found to be 6.0 ± 0.7 barns.

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