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Removal of actinide elements from high level radioactive waste by trialkylphosphine oxide (TRPO). Cascade extraction verification with synthetic HAW solution

Abstract

The modified TRPO process for removing actinide elements from synthetic solution, which was taken from reprocessing of power reactor nuclear fuel, was verified by cascade experiment. Neptunium valence was adjusted in the process for improving neptunium removing efficiency. At 1 mol/L concentration of HNO{sub 3} of feed solution and after a few stages of extraction with 30% t=TRPO kerosene, over 99.9% of Am, Pu, Np and U could be removed from HAW (high level radioactive waste) solution. The stripping of actinides loaded in TRPO are accomplished by high concentration nitric acid, oxalic acid and sodium carbonate instead of amino carboxylic complexing agents used in previous process. The actinides stripped were divided into three groups, which are Am + RE, Np + Pu, and U, and the cross contamination between them is small. Behaviours of F.P. elements are divided into three types which are not extracted, little extracted and extracted elements. The extracted elements are rare earth and Pd, Zr and Mo which are co-extracted with actinides. The separation factor between actinides and other two types of F.P.elements will increase if more scrubbing sections are added in the process. The relative concentration profile of actinide elements and Tc in various stages  More>>
Authors:
Chongli, Song; Dazhu, Yang; Longhai, He; Jingming, Xu; Yongjun, Zhu [1] 
  1. Inst. of Nucl. Energy Technology, Tsinghua Univ., Beijing (China)
Publication Date:
Mar 01, 1992
Product Type:
Technical Report
Report Number:
CNIC-00583; TSHUNE-0030.
Reference Number:
SCA: 050800; 400105; PA: AIX-24:005115; SN: 93000930351
Resource Relation:
Other Information: PBD: Mar 1992
Subject:
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; 37 INORGANIC, ORGANIC, PHYSICAL AND ANALYTICAL CHEMISTRY; AMERICIUM; SOLVENT EXTRACTION; HIGH-LEVEL RADIOACTIVE WASTES; SIMULATION; NEPTUNIUM; ORGANIC PHOSPHORUS COMPOUNDS; PLUTONIUM; URANIUM; CARBONATES; ELECTROLYSIS; FISSION PRODUCTS; LIQUID WASTES; OXALIC ACID; REDUCTION; SODIUM COMPOUNDS; 050800; 400105; SPENT FUELS REPROCESSING; SEPARATION PROCEDURES
OSTI ID:
10120250
Research Organizations:
China Nuclear Information Centre, Beijing, BJ (China)
Country of Origin:
China
Language:
Chinese
Other Identifying Numbers:
Other: ON: DE93610902; ISBN 7-5022-0649-3; TRN: CN9201782005115
Availability:
OSTI; NTIS (US Sales Only); INIS
Submitting Site:
INIS
Size:
[12] p.
Announcement Date:
Jun 30, 2005

Citation Formats

Chongli, Song, Dazhu, Yang, Longhai, He, Jingming, Xu, and Yongjun, Zhu. Removal of actinide elements from high level radioactive waste by trialkylphosphine oxide (TRPO). Cascade extraction verification with synthetic HAW solution. China: N. p., 1992. Web.
Chongli, Song, Dazhu, Yang, Longhai, He, Jingming, Xu, & Yongjun, Zhu. Removal of actinide elements from high level radioactive waste by trialkylphosphine oxide (TRPO). Cascade extraction verification with synthetic HAW solution. China.
Chongli, Song, Dazhu, Yang, Longhai, He, Jingming, Xu, and Yongjun, Zhu. 1992. "Removal of actinide elements from high level radioactive waste by trialkylphosphine oxide (TRPO). Cascade extraction verification with synthetic HAW solution." China.
@misc{etde_10120250,
title = {Removal of actinide elements from high level radioactive waste by trialkylphosphine oxide (TRPO). Cascade extraction verification with synthetic HAW solution}
author = {Chongli, Song, Dazhu, Yang, Longhai, He, Jingming, Xu, and Yongjun, Zhu}
abstractNote = {The modified TRPO process for removing actinide elements from synthetic solution, which was taken from reprocessing of power reactor nuclear fuel, was verified by cascade experiment. Neptunium valence was adjusted in the process for improving neptunium removing efficiency. At 1 mol/L concentration of HNO{sub 3} of feed solution and after a few stages of extraction with 30% t=TRPO kerosene, over 99.9% of Am, Pu, Np and U could be removed from HAW (high level radioactive waste) solution. The stripping of actinides loaded in TRPO are accomplished by high concentration nitric acid, oxalic acid and sodium carbonate instead of amino carboxylic complexing agents used in previous process. The actinides stripped were divided into three groups, which are Am + RE, Np + Pu, and U, and the cross contamination between them is small. Behaviours of F.P. elements are divided into three types which are not extracted, little extracted and extracted elements. The extracted elements are rare earth and Pd, Zr and Mo which are co-extracted with actinides. The separation factor between actinides and other two types of F.P.elements will increase if more scrubbing sections are added in the process. The relative concentration profile of actinide elements and Tc in various stages as well as the distribution of actinides and F.P. elements in the process stream solutions are also presented.}
place = {China}
year = {1992}
month = {Mar}
}