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Yields of activation products in 226Ra irradiation in the high-flux SM reactor
A target containing 3.16 mg of 226 RaCO 3 was irradiated in the neutron trap of the SM reactor for 25 effective days at a thermal neutron flux of 1.5 × 10 15 cm −2 s −1 . After the irradiation and storage for 17 days, the irradiated material was dissolved and the Ra activation products were chemical...
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Published in: | Radiochemistry (New York, N.Y.) N.Y.), 2012-08, Vol.54 (4), p.383-387 |
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Main Authors: | , , , , , , , |
Format: | Article |
Language: | English |
Subjects: | |
Citations: | Items that this one cites Items that cite this one |
Online Access: | Get full text |
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Summary: | A target containing 3.16 mg of
226
RaCO
3
was irradiated in the neutron trap of the SM reactor for 25 effective days at a thermal neutron flux of 1.5 × 10
15
cm
−2
s
−1
. After the irradiation and storage for 17 days, the irradiated material was dissolved and the Ra activation products were chemically isolated. The yields of
229
Th,
230
Th,
227
Ac, and
228
Th were determined by α- and γ-ray spectroscopy and by mass spectrometry. Formation of significant amounts of
228
Ra, not predicted by the calculations, was revealed. It was suggested that the short-lived isotope
227
Ra has a high neutron capture cross section [σ
eff
(
227
Ra) ≈ 1.5 × 10
3
b]. |
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ISSN: | 1066-3622 1608-3288 |
DOI: | 10.1134/S1066362212040121 |