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Dynamic behaviour of solvent contactors in fuel reprocessing plants- an analysis

Abstract

Fuel reprocessing plants carry out separation of useful fissile and fertile materials from spent nuclear fuels by isolating highly radioactive fission products using solvent extraction method. In the fuel reprocessing step of nuclear fuel cycle, optimisation of process parameters in the PUREX flowsheet design is of great importance particularly on account of the need to realize high degree of recovery of fissile and fertile materials and to ensure proper control on concentrations of fissile element in process streams for avoidance of criticality. In counter-current solvent contactors of PUREX flowsheet there are a variety of processes conditions which may cause plutonium accumulations that requires attention to ascertain safe Pu concentrations within the contactors. A study was carried out using the PUREX process mathematical model Solvent Extraction Program Having Interacting Solutes (SEPHIS) for pulsed solvent contactors in PREFRE-1, Tarapur and PREFRE-2, Kalpakkam flowsheets for optimising the process parameters in plutonium purification cycles. The study was extended to predict the behaviour of contactors handling plutonium bearing solutions under certain anticipated deviations in the process parameters. Modifications wherever necessary were carried out to the original SEPHIS code. This paper discusses the results obtained during this analysis. (author). 2 figs., 2 tabs.
Authors:
Raju, R P; Siddiqui, H R; [1]  Murthy, K K; Kansra, V P [2] 
  1. Nuclear Waste Management Group, Bhabha Atomic Research Centre, Mumbai (India)
  2. Fuel Reprocessing Group, Bhabha Atomic Research Centre, Mumbai (India)
Publication Date:
Jun 01, 1994
Product Type:
Conference
Report Number:
CONF-9406439-
Reference Number:
SCA: 050800; 400105; PA: AIX-29:018145; EDB-98:065810; SN: 98001952203
Resource Relation:
Conference: ACE-94: advances in chemical engineering in nuclear and process industries, Mumbai (India), 9-11 Jun 1994; Other Information: DN: 2 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; FUEL REPROCESSING PLANTS; OPTIMIZATION; PLUTONIUM; PROCESS CONTROL; PUREX PROCESS; PURIFICATION; S CODES; SAFETY; SOLVENT EXTRACTION; SPENT FUELS
OSTI ID:
615516
Research Organizations:
Board of Research in Nuclear Sciences, Department of Atomic Energy, Mumbai (India).
Country of Origin:
India
Language:
English
Other Identifying Numbers:
TRN: IN9800258018145
Submitting Site:
INIS
Size:
pp. 132-138
Announcement Date:

Citation Formats

Raju, R P, Siddiqui, H R, Murthy, K K, and Kansra, V P. Dynamic behaviour of solvent contactors in fuel reprocessing plants- an analysis. India: N. p., 1994. Web.
Raju, R P, Siddiqui, H R, Murthy, K K, & Kansra, V P. Dynamic behaviour of solvent contactors in fuel reprocessing plants- an analysis. India.
Raju, R P, Siddiqui, H R, Murthy, K K, and Kansra, V P. 1994. "Dynamic behaviour of solvent contactors in fuel reprocessing plants- an analysis." India.
@misc{etde_615516,
title = {Dynamic behaviour of solvent contactors in fuel reprocessing plants- an analysis}
author = {Raju, R P, Siddiqui, H R, Murthy, K K, and Kansra, V P}
abstractNote = {Fuel reprocessing plants carry out separation of useful fissile and fertile materials from spent nuclear fuels by isolating highly radioactive fission products using solvent extraction method. In the fuel reprocessing step of nuclear fuel cycle, optimisation of process parameters in the PUREX flowsheet design is of great importance particularly on account of the need to realize high degree of recovery of fissile and fertile materials and to ensure proper control on concentrations of fissile element in process streams for avoidance of criticality. In counter-current solvent contactors of PUREX flowsheet there are a variety of processes conditions which may cause plutonium accumulations that requires attention to ascertain safe Pu concentrations within the contactors. A study was carried out using the PUREX process mathematical model Solvent Extraction Program Having Interacting Solutes (SEPHIS) for pulsed solvent contactors in PREFRE-1, Tarapur and PREFRE-2, Kalpakkam flowsheets for optimising the process parameters in plutonium purification cycles. The study was extended to predict the behaviour of contactors handling plutonium bearing solutions under certain anticipated deviations in the process parameters. Modifications wherever necessary were carried out to the original SEPHIS code. This paper discusses the results obtained during this analysis. (author). 2 figs., 2 tabs.}
place = {India}
year = {1994}
month = {Jun}
}