You need JavaScript to view this

Separation of neptunium, plutonium and uranium by using butyraldehydes as reductants in reprocessing

Abstract

A new separation process of Np, Pu and U using n- and iso-butyraldehydes as reductants for Np(VI) and Pu(IV), respectively, in the reprocessing has been investigated. In the kinetics study of Np, Pu and U reduction, it was found that n-butyraldehyde reduced Np(VI) to Np(V) in the Purex solution but did not reduce Pu(IV) and U(VI), and iso-butyraldehyde reduced Np(VI) and Pu(IV) but did not reduce U(VI). Based on these results, a new selective separation process of Np, Pu and U was proposed. The main process consists of three steps: co-decontamination, Np separation and U/Pu partition steps. In the Np separation step, Np(VI) extracted together with Pu(IV) and U(VI) by the solvent of 30 % tri-n-bytyl phosphate/n-dodecane was selectively reduced to Np(V) by using n-butyraldehyde and was back-extracted from the solvent. In the U/Pu partition step, iso-butyraldehyde was used as a reductant for Pu(IV). The effectiveness of the new process was demonstrated in the flow sheet study using miniature mixer-settlers. In the Np separation step, 99.98 % of Np extracted together with U(VI) in the co-decontamination step was reduced by n-butyraldehyde and separated from U. In the U/Pu partition step, more than 99 % of Pu was reduced by iso-butyraldehyde  More>>
Authors:
Uchiyama, Gunzo; Hotoku, Shinobu; Fujine, Sachio; Maeda, Mitsuru [1] 
  1. Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment
Publication Date:
Oct 01, 1993
Product Type:
Technical Report
Report Number:
JAERI-M-93-198
Reference Number:
SCA: 050800; 400105; PA: JPN-93:012159; EDB-94:023303; ERA-19:008207; NTS-94:017592; SN: 94001140368
Resource Relation:
Other Information: PBD: Oct 1993
Subject:
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; 37 INORGANIC, ORGANIC, PHYSICAL AND ANALYTICAL CHEMISTRY; PUREX PROCESS; URANIUM; SEPARATION PROCESSES; NEPTUNIUM; PLUTONIUM; HIGH-LEVEL RADIOACTIVE WASTES; ALPHA-BEARING WASTES; REDUCTION; SOLVENT EXTRACTION; CHEMICAL REACTION KINETICS; TBP; MIXER-SETTLERS; REDUCING AGENTS; ALDEHYDES; 050800; 400105; SPENT FUELS REPROCESSING; SEPARATION PROCEDURES
OSTI ID:
10120916
Research Organizations:
Japan Atomic Energy Research Inst., Tokyo (Japan)
Country of Origin:
Japan
Language:
English
Other Identifying Numbers:
Other: ON: DE94737937; TRN: JP9312159
Availability:
OSTI; NTIS; INIS
Submitting Site:
JPN
Size:
32 p.
Announcement Date:
Jun 30, 2005

Citation Formats

Uchiyama, Gunzo, Hotoku, Shinobu, Fujine, Sachio, and Maeda, Mitsuru. Separation of neptunium, plutonium and uranium by using butyraldehydes as reductants in reprocessing. Japan: N. p., 1993. Web.
Uchiyama, Gunzo, Hotoku, Shinobu, Fujine, Sachio, & Maeda, Mitsuru. Separation of neptunium, plutonium and uranium by using butyraldehydes as reductants in reprocessing. Japan.
Uchiyama, Gunzo, Hotoku, Shinobu, Fujine, Sachio, and Maeda, Mitsuru. 1993. "Separation of neptunium, plutonium and uranium by using butyraldehydes as reductants in reprocessing." Japan.
@misc{etde_10120916,
title = {Separation of neptunium, plutonium and uranium by using butyraldehydes as reductants in reprocessing}
author = {Uchiyama, Gunzo, Hotoku, Shinobu, Fujine, Sachio, and Maeda, Mitsuru}
abstractNote = {A new separation process of Np, Pu and U using n- and iso-butyraldehydes as reductants for Np(VI) and Pu(IV), respectively, in the reprocessing has been investigated. In the kinetics study of Np, Pu and U reduction, it was found that n-butyraldehyde reduced Np(VI) to Np(V) in the Purex solution but did not reduce Pu(IV) and U(VI), and iso-butyraldehyde reduced Np(VI) and Pu(IV) but did not reduce U(VI). Based on these results, a new selective separation process of Np, Pu and U was proposed. The main process consists of three steps: co-decontamination, Np separation and U/Pu partition steps. In the Np separation step, Np(VI) extracted together with Pu(IV) and U(VI) by the solvent of 30 % tri-n-bytyl phosphate/n-dodecane was selectively reduced to Np(V) by using n-butyraldehyde and was back-extracted from the solvent. In the U/Pu partition step, iso-butyraldehyde was used as a reductant for Pu(IV). The effectiveness of the new process was demonstrated in the flow sheet study using miniature mixer-settlers. In the Np separation step, 99.98 % of Np extracted together with U(VI) in the co-decontamination step was reduced by n-butyraldehyde and separated from U. In the U/Pu partition step, more than 99 % of Pu was reduced by iso-butyraldehyde and separated from U. (author).}
place = {Japan}
year = {1993}
month = {Oct}
}