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Recovery of uranium from crude uranium tetrafluoride

Abstract

An innovative process has been developed for recovery of uranium from crude uranium tetrafluoride cake. The process is based on direct dissolution of uranium tetrafluoride in nitric acid in presence of aluminium hydroxide and use of solvent extraction for removal of fluorides and other bulk impurities to make uranium amenable for refining. It is a simple process requiring minimum process step and has advantage of lesser plant corrosion. This process can be applied for processing of uranium tetrafluoride generated from various sources like uranium by-product during thorium recovery from thorium concentrate, first stage product of uranium recovery from phosphoric acid by OPPA process and off grade uranium tetrafluoride material. The paper describes the details of the process developed and demonstrated on bench and pilot scale and its subsequent modification arising out of bulky solid waste generation. The modified process uses a lower quantity of aluminium hydroxide by allowing a lower dissolution of uranium per cycle and recycles the undissolved material to the next cycle, maintaining the overall recovery at high level. This innovation has reduced the solid waste generated by a factor of four at the cost of a slightly larger dissolution vessel and its increased corrosion rate. (author). 4  More>>
Authors:
Ghosh, S K; Bellary, M P; Keni, V S [1] 
  1. Chemical Engineering Division, Bhabha Atomic Research Centre, Mumbai (India)
Publication Date:
Jun 01, 1994
Product Type:
Conference
Report Number:
CONF-9406439-
Reference Number:
SCA: 050400; 400105; PA: AIX-29:018159; EDB-98:065777; SN: 98001952217
Resource Relation:
Conference: ACE-94: advances in chemical engineering in nuclear and process industries, Mumbai (India), 9-11 Jun 1994; Other Information: DN: 4 refs., 1 fig., 3 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; ALUMINIUM HYDROXIDES; DISSOLUTION; NITRIC ACID; PILOT PLANTS; PURIFICATION; REFINING; SODIUM HYDROXIDES; SOLVENT EXTRACTION; URANIUM; URANIUM TETRAFLUORIDE; WASTE MANAGEMENT
OSTI ID:
615521
Research Organizations:
Board of Research in Nuclear Sciences, Department of Atomic Energy, Mumbai (India).
Country of Origin:
India
Language:
English
Other Identifying Numbers:
TRN: IN9800272018159
Submitting Site:
INIS
Size:
pp. 272-281
Announcement Date:

Citation Formats

Ghosh, S K, Bellary, M P, and Keni, V S. Recovery of uranium from crude uranium tetrafluoride. India: N. p., 1994. Web.
Ghosh, S K, Bellary, M P, & Keni, V S. Recovery of uranium from crude uranium tetrafluoride. India.
Ghosh, S K, Bellary, M P, and Keni, V S. 1994. "Recovery of uranium from crude uranium tetrafluoride." India.
@misc{etde_615521,
title = {Recovery of uranium from crude uranium tetrafluoride}
author = {Ghosh, S K, Bellary, M P, and Keni, V S}
abstractNote = {An innovative process has been developed for recovery of uranium from crude uranium tetrafluoride cake. The process is based on direct dissolution of uranium tetrafluoride in nitric acid in presence of aluminium hydroxide and use of solvent extraction for removal of fluorides and other bulk impurities to make uranium amenable for refining. It is a simple process requiring minimum process step and has advantage of lesser plant corrosion. This process can be applied for processing of uranium tetrafluoride generated from various sources like uranium by-product during thorium recovery from thorium concentrate, first stage product of uranium recovery from phosphoric acid by OPPA process and off grade uranium tetrafluoride material. The paper describes the details of the process developed and demonstrated on bench and pilot scale and its subsequent modification arising out of bulky solid waste generation. The modified process uses a lower quantity of aluminium hydroxide by allowing a lower dissolution of uranium per cycle and recycles the undissolved material to the next cycle, maintaining the overall recovery at high level. This innovation has reduced the solid waste generated by a factor of four at the cost of a slightly larger dissolution vessel and its increased corrosion rate. (author). 4 refs., 1 fig., 3 tabs.}
place = {India}
year = {1994}
month = {Jun}
}