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1 - IAEA Nuclear Data Services

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- 144 -<br />

Neutron Capture Cross Sections<br />

H. Weigmann, J. Winter<br />

Capture Cross Sections<br />

The detector [12] for neutron capture cross section<br />

measurements which was described in the last Annual<br />

Progress Report has been used for measurements on<br />

240<br />

natural Mo, Pu, natural Cu, and natural Nd.<br />

Measurements__on_Natural_Mo<br />

<strong>Data</strong> for natural Mo have been obtained in the neutron<br />

energy range, from 10 eV to 25 keV [13]. An area analysis<br />

which contains a Monte-Carlo subroutine to calculate<br />

the multiple scattering contribution to the<br />

capture areas, has been applied to resonances with<br />

known isotopic assignment; it yields gr for small<br />

resonances and IV for large ones. Above 1 keV neutron<br />

energy, the observed capture rate has been averaged<br />

to give the mean capture cross section which is in<br />

good agreement with earlier measurements. Por the<br />

final attribution and analysis of some resonances to<br />

specific isotopes of Mo, measurements on separated<br />

isotopes are planned.<br />

240<br />

Measurements_on Pu<br />

Neutron radiative capture in<br />

240<br />

Pu has been studied<br />

in the neutron energy range from 38 eV to 820 eV [14].<br />

The resonance area analysis of the capture data has<br />

been combined with the transmission area analysis<br />

(see above) to obtain the resonance parameters.<br />

The radiative widths of 32 resonances have been determined<br />

yielding a mean value of = (23.2 _+ 2.0)<br />

meV. The observation of unusual large radiative widths<br />

for some resonances at the upper limit of the analysed<br />

energy range has been interpreted as being due to the<br />

presence of subthreshold fission in these resonances.<br />

This interpretation has been confirmed in a measure-

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