Abstract
A study for plutonium recovery at trace level from uranium solutions by ion exchange technique is presented. Plutonium retention > 99,5% onto strong anionic resin, AG-X8, from nitric acid solutions and a 92% recovery using 0,4 H NO{sub 3} at 60{sup 0} C as eluent, were obtained. Uranium interference on the plutonium sorption from mixed U-Pu nitrate solutions with low U/Pu ratio ({approx} 25) was not verified. However, for high U/Pu ratio solutions ({approx} 10000), uranium interferes on the plutonium retention onto resin, decreasing to 59%. Selecting the loaded conditions and using AG-X4 resin, 99% plutonium retention was achieved. The plutonium product is still contaminated with U and other purification cycle is recommended. A scheme for U-Pu first cycle separation is proposed. (author).
Citation Formats
Araujo, B.F. de, Matsuda, H T, Carvalho, E.I. de, and Araujo, I.C. de.
Plutonium removal by ion exchange chromatography; Separacao de tracos de plutonio por cromatografia de troca ionica.
Brazil: N. p.,
1991.
Web.
Araujo, B.F. de, Matsuda, H T, Carvalho, E.I. de, & Araujo, I.C. de.
Plutonium removal by ion exchange chromatography; Separacao de tracos de plutonio por cromatografia de troca ionica.
Brazil.
Araujo, B.F. de, Matsuda, H T, Carvalho, E.I. de, and Araujo, I.C. de.
1991.
"Plutonium removal by ion exchange chromatography; Separacao de tracos de plutonio por cromatografia de troca ionica."
Brazil.
@misc{etde_10108390,
title = {Plutonium removal by ion exchange chromatography; Separacao de tracos de plutonio por cromatografia de troca ionica}
author = {Araujo, B.F. de, Matsuda, H T, Carvalho, E.I. de, and Araujo, I.C. de}
abstractNote = {A study for plutonium recovery at trace level from uranium solutions by ion exchange technique is presented. Plutonium retention > 99,5% onto strong anionic resin, AG-X8, from nitric acid solutions and a 92% recovery using 0,4 H NO{sub 3} at 60{sup 0} C as eluent, were obtained. Uranium interference on the plutonium sorption from mixed U-Pu nitrate solutions with low U/Pu ratio ({approx} 25) was not verified. However, for high U/Pu ratio solutions ({approx} 10000), uranium interferes on the plutonium retention onto resin, decreasing to 59%. Selecting the loaded conditions and using AG-X4 resin, 99% plutonium retention was achieved. The plutonium product is still contaminated with U and other purification cycle is recommended. A scheme for U-Pu first cycle separation is proposed. (author).}
place = {Brazil}
year = {1991}
month = {Dec}
}
title = {Plutonium removal by ion exchange chromatography; Separacao de tracos de plutonio por cromatografia de troca ionica}
author = {Araujo, B.F. de, Matsuda, H T, Carvalho, E.I. de, and Araujo, I.C. de}
abstractNote = {A study for plutonium recovery at trace level from uranium solutions by ion exchange technique is presented. Plutonium retention > 99,5% onto strong anionic resin, AG-X8, from nitric acid solutions and a 92% recovery using 0,4 H NO{sub 3} at 60{sup 0} C as eluent, were obtained. Uranium interference on the plutonium sorption from mixed U-Pu nitrate solutions with low U/Pu ratio ({approx} 25) was not verified. However, for high U/Pu ratio solutions ({approx} 10000), uranium interferes on the plutonium retention onto resin, decreasing to 59%. Selecting the loaded conditions and using AG-X4 resin, 99% plutonium retention was achieved. The plutonium product is still contaminated with U and other purification cycle is recommended. A scheme for U-Pu first cycle separation is proposed. (author).}
place = {Brazil}
year = {1991}
month = {Dec}
}