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Solvent extraction process development for high plutonium fuel cycles

Conference:

Abstract

The purification of high plutonium bearing irradiated fuels using 30% TBP in dodecane diluent requires precise determination of concentration profiles during steady state, transient and process upset conditions. Mathematical models have been developed and a computer code is in use for determining Pu-U concentration profiles in a solvent extraction equipment in a typical reprocessing plant. The process parameters have been optimised for recovery of U and Pu and decontamination from the fission products. This computer code is used to analyse the extraction flow sheets of fuels of two typical Pu-U compositions encountered in Indian fast breeder programme. The analysis include the effect of uncertainty in equilibrium condition prediction by the model and the variation of flows of streams during plant operation. The studies highlight the margin available to avoid second organic phase formation and adjustments required in the process flowsheet. (author). 7 refs., 7 figs., 2 tabs.
Authors:
Anil Kumar, R; Selvaraj, P G; Natarajan, R; Raman, V R [1] 
  1. Reprocessing Group, Indira Gandhi Centre for Atomic Research, Kalpakkam (India)
Publication Date:
Jun 01, 1994
Product Type:
Conference
Report Number:
CONF-9406439-
Reference Number:
SCA: 050800; 400105; PA: AIX-29:018181; EDB-98:065804; SN: 98001952239
Resource Relation:
Conference: ACE-94: advances in chemical engineering in nuclear and process industries, Mumbai (India), 9-11 Jun 1994; Other Information: DN: 7 refs., 7 figs., 2 tabs.; PBD: Jun 1994; Related Information: Is Part Of Advances in chemical engineering in nuclear and process industries; PB: 628 p.
Subject:
05 NUCLEAR FUELS; 40 CHEMISTRY; CRITICALITY; DISTRIBUTION FUNCTIONS; FBR TYPE REACTORS; FLOWSHEETS; LIMITING VALUES; M CODES; PLUTONIUM; PURIFICATION; REPROCESSING; SOLVENT EXTRACTION; TBP; URANIUM
OSTI ID:
615553
Research Organizations:
Board of Research in Nuclear Sciences, Department of Atomic Energy, Mumbai (India).
Country of Origin:
India
Language:
English
Other Identifying Numbers:
TRN: IN9800294018181
Submitting Site:
INIS
Size:
pp. 568-573
Announcement Date:
Jan 24, 2004

Conference:

Citation Formats

Anil Kumar, R, Selvaraj, P G, Natarajan, R, and Raman, V R. Solvent extraction process development for high plutonium fuel cycles. India: N. p., 1994. Web.
Anil Kumar, R, Selvaraj, P G, Natarajan, R, & Raman, V R. Solvent extraction process development for high plutonium fuel cycles. India.
Anil Kumar, R, Selvaraj, P G, Natarajan, R, and Raman, V R. 1994. "Solvent extraction process development for high plutonium fuel cycles." India.
@misc{etde_615553,
title = {Solvent extraction process development for high plutonium fuel cycles}
author = {Anil Kumar, R, Selvaraj, P G, Natarajan, R, and Raman, V R}
abstractNote = {The purification of high plutonium bearing irradiated fuels using 30% TBP in dodecane diluent requires precise determination of concentration profiles during steady state, transient and process upset conditions. Mathematical models have been developed and a computer code is in use for determining Pu-U concentration profiles in a solvent extraction equipment in a typical reprocessing plant. The process parameters have been optimised for recovery of U and Pu and decontamination from the fission products. This computer code is used to analyse the extraction flow sheets of fuels of two typical Pu-U compositions encountered in Indian fast breeder programme. The analysis include the effect of uncertainty in equilibrium condition prediction by the model and the variation of flows of streams during plant operation. The studies highlight the margin available to avoid second organic phase formation and adjustments required in the process flowsheet. (author). 7 refs., 7 figs., 2 tabs.}
place = {India}
year = {1994}
month = {Jun}
}