You need JavaScript to view this

Recovery of trans-plutonium elements; Recuperation des elements transplutoniens

Abstract

The object of this work is to study the recovery of americium and curium from the fission-product solution obtained from the processing of irradiated fuel elements made of natural metallic uranium alloyed with aluminium, iron and silicon; these elements have been subjected to an average irradiation of 4000 MW days/ton in a gas-graphite type reactor having a thermal power of 3.7 MW/ton of uranium. The process used consists of 3 extraction cycles and one americium-curium separation: - 1) extraction cycle in 40 per cent TBP: extraction of actinides and lanthanides; elimination of fission products; - 2) extraction cycle in 8 per cent D2EHPA: decontamination from the fission products, decontamination of actinides from lanthanides; - 3) extraction cycle in 40 per cent TBP: separation of the complexing agent and concentration of the actinides; - 4) americium-curium separation by precipitation. (authors) [French] Cette etude a pour objet, la recuperation de l'americium et du curium de la solution de produits de fission provenant du traitement de combustibles irradies a base d'uranium naturel metallique allie a l'aluminium, le fer, et le silicium, et ayant subi une irradiation moyenne de 4000 MWj/t dans une pile du type graphite-gaz, dont la puissance thermique est de 3.7  More>>
Authors:
Espie, J Y; Poncet, B; Simon, A [1] 
  1. Commissariat a l'Energie Atomique, Saclay (France). Centre d'Etudes Nucleaires
Publication Date:
Jul 01, 1970
Product Type:
Technical Report
Report Number:
CEA-R-3744
Resource Relation:
Other Information: 77 refs; PBD: 1970
Subject:
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; AMERICIUM COMPOUNDS; CURIUM COMPOUNDS; DECANTATION; DECONTAMINATION; EXTRACTION COLUMNS; FISSION PRODUCTS; FLOW RATE; FUEL REPROCESSING PLANTS; GCR TYPE REACTORS; HDEHP; PH VALUE; PRECIPITATION; RADIATION PROTECTION; RADIOACTIVE EFFLUENTS; RADIOLYSIS; RARE EARTHS; REGENERATION; SOLVENT EXTRACTION; SPECIFICATIONS; SPENT FUELS; TALSPEAK PROCESS; TBP
OSTI ID:
20528742
Research Organizations:
CEA Saclay, 91 - Gif-sur-Yvette (France)
Country of Origin:
France
Language:
French
Other Identifying Numbers:
TRN: FR04R3744095008
Availability:
Available from INIS in electronic form
Submitting Site:
FRN
Size:
[147] pages
Announcement Date:

Citation Formats

Espie, J Y, Poncet, B, and Simon, A. Recovery of trans-plutonium elements; Recuperation des elements transplutoniens. France: N. p., 1970. Web.
Espie, J Y, Poncet, B, & Simon, A. Recovery of trans-plutonium elements; Recuperation des elements transplutoniens. France.
Espie, J Y, Poncet, B, and Simon, A. 1970. "Recovery of trans-plutonium elements; Recuperation des elements transplutoniens." France.
@misc{etde_20528742,
title = {Recovery of trans-plutonium elements; Recuperation des elements transplutoniens}
author = {Espie, J Y, Poncet, B, and Simon, A}
abstractNote = {The object of this work is to study the recovery of americium and curium from the fission-product solution obtained from the processing of irradiated fuel elements made of natural metallic uranium alloyed with aluminium, iron and silicon; these elements have been subjected to an average irradiation of 4000 MW days/ton in a gas-graphite type reactor having a thermal power of 3.7 MW/ton of uranium. The process used consists of 3 extraction cycles and one americium-curium separation: - 1) extraction cycle in 40 per cent TBP: extraction of actinides and lanthanides; elimination of fission products; - 2) extraction cycle in 8 per cent D2EHPA: decontamination from the fission products, decontamination of actinides from lanthanides; - 3) extraction cycle in 40 per cent TBP: separation of the complexing agent and concentration of the actinides; - 4) americium-curium separation by precipitation. (authors) [French] Cette etude a pour objet, la recuperation de l'americium et du curium de la solution de produits de fission provenant du traitement de combustibles irradies a base d'uranium naturel metallique allie a l'aluminium, le fer, et le silicium, et ayant subi une irradiation moyenne de 4000 MWj/t dans une pile du type graphite-gaz, dont la puissance thermique est de 3.7 MW/t d'uranium. Le procede utilise comprend 3 cycles d'extraction et une separation americium-curium: - 1. cycle d'extraction dans le TBP a 40 pour cent: extraction des actinides et des lanthanides, elimination des produits de fission; - 2. cycle d'extraction dans le D2EHPA a 8 pour cent: decontamination en produits de fission, decontamination des actinides en lanthanides; - 3. cycle d'extraction dans le TBP a 40 pour cent: separation du complexant et concentration des actinides; - 4. separation americium-curium par precipitation. (auteurs)}
place = {France}
year = {1970}
month = {Jul}
}