Abstract
Stripping behaviors of 30% TRPO-kerosene organic phase containing actinide elements in nitric acid, oxalic acid and sodium carbonate solutions were studied. The conditions for stripping actinide elements were given. The 5{approx}6 mol/L nitric acid of concentration can effectively re-extract americium and lanthanide, but third phase would be generated if nitric acid concentration is too high. Two times of stripping with 0.5 mol/L oxalic acid in crossflow can recover more than 99% of neptunium and plutonium, and 5% sodium carbonate can re-extract uranium. The cross contamination in these three groups is very little. A flowsheet of TRPO process for removing actinides from high level waste solution is proposed.
Chongli, Song;
Jingming, Xu;
Yongjun, Zhu
[1]
- Inst. of Nucl. Energy Technology,, Tsinghua Univ. (China)
Citation Formats
Chongli, Song, Jingming, Xu, and Yongjun, Zhu.
Removal of actinide elements from high level radioactive waste by trialkylphosphine oxide (TRPO). The stripping of actinide elements from loaded organic phase.
China: N. p.,
1992.
Web.
Chongli, Song, Jingming, Xu, & Yongjun, Zhu.
Removal of actinide elements from high level radioactive waste by trialkylphosphine oxide (TRPO). The stripping of actinide elements from loaded organic phase.
China.
Chongli, Song, Jingming, Xu, and Yongjun, Zhu.
1992.
"Removal of actinide elements from high level radioactive waste by trialkylphosphine oxide (TRPO). The stripping of actinide elements from loaded organic phase."
China.
@misc{etde_10120307,
title = {Removal of actinide elements from high level radioactive waste by trialkylphosphine oxide (TRPO). The stripping of actinide elements from loaded organic phase}
author = {Chongli, Song, Jingming, Xu, and Yongjun, Zhu}
abstractNote = {Stripping behaviors of 30% TRPO-kerosene organic phase containing actinide elements in nitric acid, oxalic acid and sodium carbonate solutions were studied. The conditions for stripping actinide elements were given. The 5{approx}6 mol/L nitric acid of concentration can effectively re-extract americium and lanthanide, but third phase would be generated if nitric acid concentration is too high. Two times of stripping with 0.5 mol/L oxalic acid in crossflow can recover more than 99% of neptunium and plutonium, and 5% sodium carbonate can re-extract uranium. The cross contamination in these three groups is very little. A flowsheet of TRPO process for removing actinides from high level waste solution is proposed.}
place = {China}
year = {1992}
month = {Mar}
}
title = {Removal of actinide elements from high level radioactive waste by trialkylphosphine oxide (TRPO). The stripping of actinide elements from loaded organic phase}
author = {Chongli, Song, Jingming, Xu, and Yongjun, Zhu}
abstractNote = {Stripping behaviors of 30% TRPO-kerosene organic phase containing actinide elements in nitric acid, oxalic acid and sodium carbonate solutions were studied. The conditions for stripping actinide elements were given. The 5{approx}6 mol/L nitric acid of concentration can effectively re-extract americium and lanthanide, but third phase would be generated if nitric acid concentration is too high. Two times of stripping with 0.5 mol/L oxalic acid in crossflow can recover more than 99% of neptunium and plutonium, and 5% sodium carbonate can re-extract uranium. The cross contamination in these three groups is very little. A flowsheet of TRPO process for removing actinides from high level waste solution is proposed.}
place = {China}
year = {1992}
month = {Mar}
}