Abstract
Two techniques are described for neutron activation analysis of thallium in biological and geological materials, based on /sup 203/Tl(n,2n)/sup 202/Tl reaction in nuclear reactors. Co-precipitation with bismuth sulphide is used as a pre-concentration method of thallium in urine samples, and post-irradiation chemical separation is also performed. The detection limit is 0.5 ..mu..g/l, for 100 ml urine samples. For thallium determination in blendes a radiochemical separation is carried out after the irradiation. An extension of this technique is presented for glass and silicate rocks. Results for seven blende samples from different places of Argentina are shown. Analysis of two reference materials, the 614 glass from the National Bureau of Standards and the granodiorite GSP-1 from the U.S. Geological Survey were also performed. The results are in very good agreement with the certified or estimated values.
Cohen, I M;
Resnizky, S M;
Baro, G B
[1]
- Comision Nacional de Energia Atomica, Buenos Aires (Argentina). Gerencia de Radioisotopos y Radiaciones
Citation Formats
Cohen, I M, Resnizky, S M, and Baro, G B.
Activation analysis of thallium by /sup 203/Tl(n,2n)/sup 202/Tl reaction in nuclear reactors.
Switzerland: N. p.,
1982.
Web.
Cohen, I M, Resnizky, S M, & Baro, G B.
Activation analysis of thallium by /sup 203/Tl(n,2n)/sup 202/Tl reaction in nuclear reactors.
Switzerland.
Cohen, I M, Resnizky, S M, and Baro, G B.
1982.
"Activation analysis of thallium by /sup 203/Tl(n,2n)/sup 202/Tl reaction in nuclear reactors."
Switzerland.
@misc{etde_6877974,
title = {Activation analysis of thallium by /sup 203/Tl(n,2n)/sup 202/Tl reaction in nuclear reactors}
author = {Cohen, I M, Resnizky, S M, and Baro, G B}
abstractNote = {Two techniques are described for neutron activation analysis of thallium in biological and geological materials, based on /sup 203/Tl(n,2n)/sup 202/Tl reaction in nuclear reactors. Co-precipitation with bismuth sulphide is used as a pre-concentration method of thallium in urine samples, and post-irradiation chemical separation is also performed. The detection limit is 0.5 ..mu..g/l, for 100 ml urine samples. For thallium determination in blendes a radiochemical separation is carried out after the irradiation. An extension of this technique is presented for glass and silicate rocks. Results for seven blende samples from different places of Argentina are shown. Analysis of two reference materials, the 614 glass from the National Bureau of Standards and the granodiorite GSP-1 from the U.S. Geological Survey were also performed. The results are in very good agreement with the certified or estimated values.}
journal = []
volume = {72:1-2}
place = {Switzerland}
year = {1982}
month = {Jan}
}
title = {Activation analysis of thallium by /sup 203/Tl(n,2n)/sup 202/Tl reaction in nuclear reactors}
author = {Cohen, I M, Resnizky, S M, and Baro, G B}
abstractNote = {Two techniques are described for neutron activation analysis of thallium in biological and geological materials, based on /sup 203/Tl(n,2n)/sup 202/Tl reaction in nuclear reactors. Co-precipitation with bismuth sulphide is used as a pre-concentration method of thallium in urine samples, and post-irradiation chemical separation is also performed. The detection limit is 0.5 ..mu..g/l, for 100 ml urine samples. For thallium determination in blendes a radiochemical separation is carried out after the irradiation. An extension of this technique is presented for glass and silicate rocks. Results for seven blende samples from different places of Argentina are shown. Analysis of two reference materials, the 614 glass from the National Bureau of Standards and the granodiorite GSP-1 from the U.S. Geological Survey were also performed. The results are in very good agreement with the certified or estimated values.}
journal = []
volume = {72:1-2}
place = {Switzerland}
year = {1982}
month = {Jan}
}