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Titre du document / Document title

Treatment of wastes in the IFR fuel cycle

Auteur(s) / Author(s)

ACKERMAN J. P. (1) ; JOHNSON. T. R. (1) ; CHOW L. S. H. (1) ; CARLS E. L. (1) ; HANNUM W. H. (1) ; LAIDLER J. J. (1) ;

Affiliation(s) du ou des auteurs / Author(s) Affiliation(s)

(1) Argonne National Laboratory, Chemical Technology Division, Argonne, Illinois 60439, ETATS-UNIS

Résumé / Abstract

In both the reactor portion and the fuel-cycle portion of the Integral Fast Reactor (IFR), handling, treatment and disposal of wastes are simpler than in current fuel cycles. The vast majority (> 99.9%) of the very-long-lived radioactive TRU elements are not sent to the repository; rather, they are recycled. High-level waste volume from the IFR process (called 'the pyroprocess) is lower than that from either the direct disposal of spent fuel or from conventional PUREX-type reprocessing. The quantity of low-level waste is very low. In the pyroprocess, the actinides are recovered and separated from the bulk of the fission products by an electrorefining step wherein the actinides are electrotransported from chopped fuel elements and deposited at cathodes. The volatile fission products xenon, krypton, and tritium are collected for long-term storage and decay. Zirconium and the noble metal fission products (those that are less easily oxidized than zirconium) remain in the anode compartment, to be removed with the fuel cladding fragments and made into a metal waste form. The remaining fission products collect in the salt as chlorides. A process has been developed to periodically remove the contaminated salt from the electrorefiner, separate most of the fission products, and return the purified salt in a form that is ready for continuing use. To clean up the electrorefiner salt, the fission products are removed by ion exchange onto a column of Zeolite A. After the purification step, the column material and the contained fission products are converted to a mineral waste form for disposal. The processes and equipment for waste isolation and conversion to suitable disposal forms are described in this paper.

Revue / Journal Title

Progress in nuclear energy    ISSN  0149-1970 

Source / Source

1997, vol. 31, no 1-2 (226 p.)  (16 ref.), pp. 141-154

Langue / Language

Anglais

Editeur / Publisher

Elsevier, Kidlington, ROYAUME-UNI  (1977) (Revue)

Mots-clés anglais / English Keywords

Nuclear reactor

;

Fast reactor

;

Reprocessing

;

Radioactive waste

;

Electrorefining

;

Actinide

;

Nuclear fuel

;

Irradiated nuclear fuel

;

Fuel cycle

;

Mots-clés français / French Keywords

Réacteur nucléaire

;

Réacteur rapide

;

Retraitement

;

Déchet radioactif

;

Raffinage électrolytique

;

Actinide

;

Combustible nucléaire

;

Combustible irradié

;

Cycle combustible

;

Mots-clés espagnols / Spanish Keywords

Reactor nuclear

;

Reactor rápido

;

Reprocesamiento

;

Residuos radioactivos

;

Refinación electrolítica

;

Actínido

;

Combustible nuclear

;

Combustible irradiado

;

Ciclo combustible

;

Localisation / Location

INIST-CNRS, Cote INIST : 17686, 35400006135116.0080

Nº notice refdoc (ud4) : 2534011



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