You need JavaScript to view this

New processing techniques for radioisotopes at Oak Ridge National Laboratory; Production de radioisotopes: nouvelles techniques employees au Laboratoire national d'Oak Ridge; Novye tekhnologicheskie metody polucheniya radioizotopov v Okridzhskoj natsional'noj laboratorii; Nuevos metodos de preparacion de radioisotopos aplicados en el Oak Ridge National Laboratory

Conference:

Abstract

Recent developments in the radioisotope production programme at Oak Ridge National Laboratory include new processes and process improvements for the production of cerium-144, promethium-147, technetium-99 and strontium-90. Cerium-144 has been produced in kc quantities in a test run. A product recovery of more than 98% with a product purity of more than 99% was attained. The cerium was further processed to obtain pure cerium-144 oxide powder having an activity concentration of 235 c/g. The powder was pressed into pellets which were sintered to a dense ceramic form. Promethium-147 has been produced in kc quantities by a combination of precipitation and ion exchange techniques. A solvent extraction system for separating promethium- 147 from other rare earths has been tested on a tracer scale. Gram quantities of technetium-99 have been recovered from fission-product waste streams by a combination of precipitation and solvent extraction processes. The technetium product was produced with a chemical purity of more than 99.9% and radiochemical purity of more than 99.99%. The separation and purification of strontium-90 from gross contaminants by a continuous solvent-extraction flowsheet has been demonstrated on a tracer scale. Product quality of 98% strontium has been achieved from feed containing 95% inert calcium contaminant. The strontium-90  More>>
Authors:
Butler, T A; Lamb, E; Rupp, A F [1] 
  1. Oak Ridge National Laboratory, Oak Ridge, TN (United States)
Publication Date:
Jan 15, 1962
Product Type:
Conference
Resource Relation:
Conference: Conference on the Use of Radioisotopes in the Physical Sciences and Industry, Copenhagen (Denmark), 6-17 Sep 1960; Other Information: 6 figs, 2 tabs, 9 refs; Related Information: In: Radioisotopes in the Physical Sciences and Industry. Proceedings of the Conference on the Use of Radioisotopes in the Physical Sciences and Industry. V. II| 566 p.
Subject:
37 INORGANIC, ORGANIC, PHYSICAL AND ANALYTICAL CHEMISTRY; 07 ISOTOPES AND RADIATION SOURCES; CALCIUM; CERAMICS; CERIUM; CERIUM 144; FISSION PRODUCTS; IMPURITIES; ION EXCHANGE; ORNL; OXIDES; POWDERS; PRECIPITATION; PROMETHIUM 147; RADIOCHEMISTRY; SOLVENT EXTRACTION; STREAMS; STRONTIUM; STRONTIUM 90; STRONTIUM 98; TITANATES
OSTI ID:
22025690
Research Organizations:
International Atomic Energy Agency, Vienna (Austria); United Nations Educational, Scientific and Cultural Organization, Paris (France)
Country of Origin:
IAEA
Language:
English
Other Identifying Numbers:
Other: ISSN 0074-1884; TRN: XA12N1706112983
Submitting Site:
INIS
Size:
page(s) 407-418
Announcement Date:
Jan 16, 2013

Conference:

Citation Formats

Butler, T A, Lamb, E, and Rupp, A F. New processing techniques for radioisotopes at Oak Ridge National Laboratory; Production de radioisotopes: nouvelles techniques employees au Laboratoire national d'Oak Ridge; Novye tekhnologicheskie metody polucheniya radioizotopov v Okridzhskoj natsional'noj laboratorii; Nuevos metodos de preparacion de radioisotopos aplicados en el Oak Ridge National Laboratory. IAEA: N. p., 1962. Web.
Butler, T A, Lamb, E, & Rupp, A F. New processing techniques for radioisotopes at Oak Ridge National Laboratory; Production de radioisotopes: nouvelles techniques employees au Laboratoire national d'Oak Ridge; Novye tekhnologicheskie metody polucheniya radioizotopov v Okridzhskoj natsional'noj laboratorii; Nuevos metodos de preparacion de radioisotopos aplicados en el Oak Ridge National Laboratory. IAEA.
Butler, T A, Lamb, E, and Rupp, A F. 1962. "New processing techniques for radioisotopes at Oak Ridge National Laboratory; Production de radioisotopes: nouvelles techniques employees au Laboratoire national d'Oak Ridge; Novye tekhnologicheskie metody polucheniya radioizotopov v Okridzhskoj natsional'noj laboratorii; Nuevos metodos de preparacion de radioisotopos aplicados en el Oak Ridge National Laboratory." IAEA.
@misc{etde_22025690,
title = {New processing techniques for radioisotopes at Oak Ridge National Laboratory; Production de radioisotopes: nouvelles techniques employees au Laboratoire national d'Oak Ridge; Novye tekhnologicheskie metody polucheniya radioizotopov v Okridzhskoj natsional'noj laboratorii; Nuevos metodos de preparacion de radioisotopos aplicados en el Oak Ridge National Laboratory}
author = {Butler, T A, Lamb, E, and Rupp, A F}
abstractNote = {Recent developments in the radioisotope production programme at Oak Ridge National Laboratory include new processes and process improvements for the production of cerium-144, promethium-147, technetium-99 and strontium-90. Cerium-144 has been produced in kc quantities in a test run. A product recovery of more than 98% with a product purity of more than 99% was attained. The cerium was further processed to obtain pure cerium-144 oxide powder having an activity concentration of 235 c/g. The powder was pressed into pellets which were sintered to a dense ceramic form. Promethium-147 has been produced in kc quantities by a combination of precipitation and ion exchange techniques. A solvent extraction system for separating promethium- 147 from other rare earths has been tested on a tracer scale. Gram quantities of technetium-99 have been recovered from fission-product waste streams by a combination of precipitation and solvent extraction processes. The technetium product was produced with a chemical purity of more than 99.9% and radiochemical purity of more than 99.99%. The separation and purification of strontium-90 from gross contaminants by a continuous solvent-extraction flowsheet has been demonstrated on a tracer scale. Product quality of 98% strontium has been achieved from feed containing 95% inert calcium contaminant. The strontium-90 is further processed to form strontium titanate ceramic elements. (author) [French] Les faits recents a noter dans le programme de production de radioisotopes du laboratoire national d'Oak Ridge sont l'introduction de nouvelles methodes et l'amelioration des techniques existantes pour la production du eerium-144, du prometheum-147, du technetium-99 et du strontium-90. Le cerium-144 a ete obtenu en quantites de l'ordre du kilocurie, lors d'une experience. On a obtenu un taux d'extraction de plus de 98% et un produit d'une purete superieure a 99%. On a ensuite traite le cerium pour avoir de l'oxyde de cerium-144 pur en poudre ayant une activite de 235 c/g. La poudre a ete comprimee en pastilles, que l'on a ensuite agglomerees pour leur donner une consistance ceramique. Le prometheum-147 a ete produit en quantites de l'ordre du kilocurie par combinaison des techniques de precipitation et d'echanges d'ions. Un procede d'extraction par solvant pour separer le prometheum-147 d'autres terres rares a ete experimente sur de tres faibles quantites. Quelques grammes de technetium-99 ont ete recuperes dans les produits de fission des effluents par precipitation et extraction par solvant combinees. Le technetium avait une purete chimique superieure a 99,9% et une purete radiochimique superieure a 99,99%. La purification du strontium-90 par elimination des contaminants les plus importants, a l'aide d'un systeme d'extraction continu par solvant, a ete demontree sur de tres petites quantites. En partant d'un produit contenant 95% de calcium inerte, on a obtenu du strontium a 98% de purete. On a ensuite traite le strontium-90 pour obtenir des elements ceramiques de titanate de strontium. (author) [Spanish] Entre los adelantos mas recientes introducidos en el programa de preparacion de radioisotopos del Oak Ridge National Laboratory se cuenta el desarrollo de nuevos metodos y el mejoramiento de procedimientos ya establecidos para la obtencion de cerio-144, promecio-147, tecnecio-99 y estroncio-90. Se ha producido experimentalmente cerio-144 en escala de los kiloeuries. Se recupero mas del 98% de cerio con una pureza superior al 99%. Este cerio se siguio purificando hasta obtener oxido de cerio puro en forma pulverulenta de actividad especifica igual a 235 e/g. Este polvo se comprimio en pastillas y se sinterizo para obtener un material ceramico denso. El promecio-147 se obtuvo en cantidades de kiloeuries aplicando un metodo combinado de precipitacion e intercambio ionico. Se ensayo la extraccion de vestigios de elementos con disolventes para separar el promecio-147 de otras tierras raras. Gracias a una combinacion de procedimientos de precipitacion y de extraccion con disolventes, se han podido recuperar cantidades de tecnecio-99 del orden de algunos gramos, a partir de desechos de productos de fision. La pureza quimica del tecnecio obtenido es superior al 99,9%, en tanto que su pureza radioquimica sobrepasa el 99.99%. Trabajando tambien con vestigios, se ha demostrado la posibilidad de separar y purificar por extraccion continua pequenas cantidades de estroncio contenidas en otros materiales. Se obtuvo estroncio de 98% de pureza a partir de un material contaminado por un 95% de calcio inerte. El estroncio se transforma en titanato de estroncio, con el que se elaboran elementos ceramicos. (author) [Russian] Novejshaya progressivnaya programma proizvodstva radioizotopov v Okridzhskoj natsional'noj laboratorii vklyuchaet novye tekhnologicheskie protsessy i uluchsheniya ikh dlya proizvodstva tseriya-144, prometiya-147, tekhnetsiya-99 i strontsiya-90. TSerij-144 byl proizveden v kolichestve neskol'kikh kilokyuri pri probnoj postanovke proizvodstva. Produkt byl rekuperirovan bolee chem na 98 protsentov pri chistote produkta svyshe 99 protsentov. Posle ehtogo tserij byl obrabotan dlya polucheniya chistoj okisi tseriya-144 v vide poroshka s kontsentratsiej aktivnosti v 235 kyuri na gramm. Poroshok spressovyvalsya v tabletki, kotorye spekalis' v vide plotnogo keramicheskogo tela. Prometij-147 byl proizveden v kolichestve neskol'kikh kilokyuri po metodu osazhdeniya sovmestno s metodom ionnogo obmena. Dlya otdeleniya prometiya-147 ot drugikh redkikh zemel' byl isprobovan v masshtabe indikatorov metod izvlecheniya rastvoritelem. Iz produktov deleniya v stoke otkhodnykh materialov bylo rekuperirovano neskol'ko grammov tekhnetsiya-99 pri pomoshchi protsessa osazhdeniya sovmestno s protsessom izvlecheniya rastvoritelem. Tekhnetsij byl poluchen bolee chem s 99,9-protsentnoj khimicheskoj chistotoj i s radiokhimicheskoj chistotoj bolee chem 99,99%. V masshtabe indikatorov byla dokazana vozmozhnost' otdeleniya i ochistki strontsiya-90 ot obshchej massy zagryaznitelej putem nepreryvnogo promyvaniya tonkim ehkstragiruyushchim sloem rastvoritelya. Udalos' dostich' proizvodstva 98-protsentnogo strontsiya iz iskhodnogo materiala, soderzhavshego 95 % inertnogo kal'tsievogo zagryaznitelya. Dalee strontsij-90 pererabatyvalsya dlya polucheniya keramicheskikh ehlementov titanata strontsiya. (author)}
place = {IAEA}
year = {1962}
month = {Jan}
}