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Method of neptunium recovery into the product stream of the Purex second codecontamination step for LWR fuel reprocessing

Technical Report:

Abstract

The neptunium behavior in the second codecontamination step in Purex process of Power Reactor and Nuclear Fuel Development Corporation was experimentally studied, and the conditions for discharging neptunium in product stream were examined. Improved nitrous acid method was applied to the second codecontamination step. Nitrous acid (NaNO/sub 2/) was supplied to the 1st stage of extraction section at feed rate of 7.5 mM/hr, and hydrazine (hydrazine nitrate) was supplied to some stages near feed point at feed rate of 1.6 mM/hr, by using laboratory scale mixer-settlers having 6 ml of mixing volume and 17 ml of settling volume. Neptunium extraction behavior was analyzed by the code NEPTUN-I simulating neptunium concentration profile and by the code NEPTUN-II for calculating Np (V) and Np (VI) concentration. Batch experiments were performed for explaining the reduction reaction of Np (VI) in organic phase. After shaking the aqueous solution containing Np (VI) in 3 M nitric acid with the various volume ratios of TBP, both phases were separated, and the neptunium concentration was determined. In conclusion, the improved nitrous acid method was effective for the neptunium discharge in product stream when the flow ratio of organic phase to aqueous phase was increased to about three  More>>
Authors:
Tsuboya, T; Nemoto, S; Hoshino, T; Segawa, T [1] 
  1. Power Reactor and Nuclear Fuel Development Corp., Tokyo (Japan)
Publication Date:
Apr 01, 1973
Product Type:
Technical Report
Report Number:
PNCT-831-73-01
Reference Number:
AIX-08-342921; NTS-78-060376; EDB-78-067247
Resource Relation:
Related Information: In: Semi-annual progress report of Power Reactor and Nuclear Fuel Development Corporation, Tokai Works. Jul. -Dec. , 1972.
Subject:
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; NEPTUNIUM; SOLVENT EXTRACTION; DECONTAMINATION; FUEL REPROCESSING PLANTS; JAPAN; MIXER-SETTLERS; NITROUS ACID; OXIDATION; PUREX PROCESS; REDUCTION; ACTINIDES; ASIA; CHEMICAL REACTIONS; CLEANING; ELEMENTS; EXTRACTION; EXTRACTION APPARATUSES; HYDROGEN COMPOUNDS; INORGANIC ACIDS; METALS; NUCLEAR FACILITIES; REPROCESSING; SEPARATION PROCESSES; TRANSURANIUM ELEMENTS; 050800* - Nuclear Fuels- Spent Fuels Reprocessing
OSTI ID:
8551535
Country of Origin:
Japan
Language:
English
Submitting Site:
INIS
Size:
Pages: 60-70
Announcement Date:
Mar 15, 2013

Technical Report:

Citation Formats

Tsuboya, T, Nemoto, S, Hoshino, T, and Segawa, T. Method of neptunium recovery into the product stream of the Purex second codecontamination step for LWR fuel reprocessing. Japan: N. p., 1973. Web.
Tsuboya, T, Nemoto, S, Hoshino, T, & Segawa, T. Method of neptunium recovery into the product stream of the Purex second codecontamination step for LWR fuel reprocessing. Japan.
Tsuboya, T, Nemoto, S, Hoshino, T, and Segawa, T. 1973. "Method of neptunium recovery into the product stream of the Purex second codecontamination step for LWR fuel reprocessing." Japan.
@misc{etde_8551535,
title = {Method of neptunium recovery into the product stream of the Purex second codecontamination step for LWR fuel reprocessing}
author = {Tsuboya, T, Nemoto, S, Hoshino, T, and Segawa, T}
abstractNote = {The neptunium behavior in the second codecontamination step in Purex process of Power Reactor and Nuclear Fuel Development Corporation was experimentally studied, and the conditions for discharging neptunium in product stream were examined. Improved nitrous acid method was applied to the second codecontamination step. Nitrous acid (NaNO/sub 2/) was supplied to the 1st stage of extraction section at feed rate of 7.5 mM/hr, and hydrazine (hydrazine nitrate) was supplied to some stages near feed point at feed rate of 1.6 mM/hr, by using laboratory scale mixer-settlers having 6 ml of mixing volume and 17 ml of settling volume. Neptunium extraction behavior was analyzed by the code NEPTUN-I simulating neptunium concentration profile and by the code NEPTUN-II for calculating Np (V) and Np (VI) concentration. Batch experiments were performed for explaining the reduction reaction of Np (VI) in organic phase. After shaking the aqueous solution containing Np (VI) in 3 M nitric acid with the various volume ratios of TBP, both phases were separated, and the neptunium concentration was determined. In conclusion, the improved nitrous acid method was effective for the neptunium discharge in product stream when the flow ratio of organic phase to aqueous phase was increased to about three times.}
place = {Japan}
year = {1973}
month = {Apr}
}