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The Permanent Disposal of Highly Radioactive Wastes by Incorporation into Glass; Elimination Permanente de Dechets Hautement Radioactifs par Incorporation dans le Verre; 041e 041a 041e 041d 0427 0414 ; La Evacuacion Permanente de Desechos de Elevada Radiactividad Incorporandolos en Vidrio

Conference:

Abstract

Development of a process for the incorporation of the high-level wastes from chemical processing operations into glass for permanent disposal has continued at Chalk River. The process has been demonstrated by making glass containing up to 50 curies of five- to six-year old mixed fission products per kg. The operation was batch wise, on a scale of four kg per batch. These operations showed that the fission products could be incorporated into glass safely and conveniently. Consideration of the many problems involved in the permanent storage or disposal of the highly radioactive glass has resulted in the conclusion that it should be buried in the ground or stored in artificial vaults. In such conditions, the disposal may always be-subjected to further control if required. If disposal is made directly to the ground, the principal method by which fission products can be released to the environment is by leaching from the glass into water. It is therefore considered important to know the rate at which fission products will be dispersed by this mechanism. Considerable data on leaching by water have been obtained in the laboratory. It has been found that the rates of release depend on the composition of the glass.  More>>
Authors:
Watson, L. C.; Aikin, A. M.; Bancroft, A. I. [1] 
  1. Atomic Energy of Canada Ltd. (Canada)
Publication Date:
Jul 01, 1960
Product Type:
Conference
Resource Relation:
Conference: Scientific Conference on the Disposal of Radioactive Wastes, Monaco (Monaco), 16-21 Nov 1959; Other Information: 9 refs., 9 tabs., 6 figs.; Related Information: In: Disposal of Radioactive Wastes. Vol. I. Proceedings of the Scientific Conference on the Disposal of Radioactive Wastes| 615 p.
Subject:
12 MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES; CHALK RIVER; ENVIRONMENTAL IMPACTS; ENVIRONMENTAL PROTECTION; FISSION PRODUCT RELEASE; FISSION PRODUCTS; GLASS; HIGH-LEVEL RADIOACTIVE WASTES; LEACHING; NONRADIOACTIVE WASTE DISPOSAL; POWER REACTORS; RADIOACTIVE WASTE FACILITIES; RADIOACTIVE WASTE PROCESSING; RADIOACTIVE WASTE STORAGE; REACTOR OPERATION
OSTI ID:
22192382
Research Organizations:
International Atomic Energy Agency, Vienna (Austria); United Nations Educational, Scientific and Cultural Organization, Paris (France); Food and Agriculture Organization, Rome (Italy)
Country of Origin:
IAEA
Language:
English
Other Identifying Numbers:
Other: ISSN 0074-1884; TRN: XA13M3506016871
Submitting Site:
INIS
Size:
page(s) 373-393
Announcement Date:
Feb 20, 2014

Conference:

Citation Formats

Watson, L. C., Aikin, A. M., and Bancroft, A. I. The Permanent Disposal of Highly Radioactive Wastes by Incorporation into Glass; Elimination Permanente de Dechets Hautement Radioactifs par Incorporation dans le Verre; 041e 041a 041e 041d 0427 0414 ; La Evacuacion Permanente de Desechos de Elevada Radiactividad Incorporandolos en Vidrio. IAEA: N. p., 1960. Web.
Watson, L. C., Aikin, A. M., & Bancroft, A. I. The Permanent Disposal of Highly Radioactive Wastes by Incorporation into Glass; Elimination Permanente de Dechets Hautement Radioactifs par Incorporation dans le Verre; 041e 041a 041e 041d 0427 0414 ; La Evacuacion Permanente de Desechos de Elevada Radiactividad Incorporandolos en Vidrio. IAEA.
Watson, L. C., Aikin, A. M., and Bancroft, A. I. 1960. "The Permanent Disposal of Highly Radioactive Wastes by Incorporation into Glass; Elimination Permanente de Dechets Hautement Radioactifs par Incorporation dans le Verre; 041e 041a 041e 041d 0427 0414 ; La Evacuacion Permanente de Desechos de Elevada Radiactividad Incorporandolos en Vidrio." IAEA.
@misc{etde_22192382,
title = {The Permanent Disposal of Highly Radioactive Wastes by Incorporation into Glass; Elimination Permanente de Dechets Hautement Radioactifs par Incorporation dans le Verre; 041e 041a 041e 041d 0427 0414 ; La Evacuacion Permanente de Desechos de Elevada Radiactividad Incorporandolos en Vidrio}
author = {Watson, L. C., Aikin, A. M., and Bancroft, A. I.}
abstractNote = {Development of a process for the incorporation of the high-level wastes from chemical processing operations into glass for permanent disposal has continued at Chalk River. The process has been demonstrated by making glass containing up to 50 curies of five- to six-year old mixed fission products per kg. The operation was batch wise, on a scale of four kg per batch. These operations showed that the fission products could be incorporated into glass safely and conveniently. Consideration of the many problems involved in the permanent storage or disposal of the highly radioactive glass has resulted in the conclusion that it should be buried in the ground or stored in artificial vaults. In such conditions, the disposal may always be-subjected to further control if required. If disposal is made directly to the ground, the principal method by which fission products can be released to the environment is by leaching from the glass into water. It is therefore considered important to know the rate at which fission products will be dispersed by this mechanism. Considerable data on leaching by water have been obtained in the laboratory. It has been found that the rates of release depend on the composition of the glass. For all the compositions tested the measurements showed that the rate of leaching of fission products from the glass decreased with time. After several months in water the rate of release of several compositions was about 10{sup -4} per cent per year from a two kg hemisphere of glass. The data obtained have been used to estimate the release of fission products from glass containing the large quantities of fission products which will accumulate from operation of power reactors. (author) [French] On poursuit a Chalk River les travaux de mise au point d'un procede permettant d'incorporer dans le verre, pour elimination permanente, des dechets hautement radioactifs provenant d'operations de traitement chimique! Aux fins de demonstration du procede, on a fabrique du verre contenant un melange de produits de fission ayant cinq ou six ans d'age et dont l'activite allait jusqu'a 50 curies par kilogramme. L'operation s'est faite en discontinu, par lots de quatre kilogrammes. On a constate que les produits de fission peuvent etre incorpores dans le verre commodement et sans danger. En etudiant les nombreux problemes que posent le stockage et l'elimination permanents du verre hautement radioactif, on est parvenu a la conclusion que ce verre devrait etre, soit enfoui dans le sol, soit entrepose dans des souterrains artificiels. Dans ces conditions, il est toujours possible, en cas de besoin, de' proceder a un nouveau controle de l'elimination. Lorsque l'enfouissement se fait directement dans le sol, les produits de fission peuvent surtout etre liberes dans le milieu ambiant par lixiviation du verre dans l'eau. On estime donc important de connaitre le rythme auquel les produits de fission se dispersent par ce mecanisme. Une documentation abondante sur la lixiviation par l'eau a ete recueillie en laboratoire. On a constate que le rythme de liberation depend de la composition du verre. Pour toutes les compositions mises a l'epreuve, les mesures montrent que le rythme de lixiviation des produits de fission incorpores dans le verre decroit avec le temps. Apres plusieurs mois d'immersion dans l'eau, le rythme auquel les substances radioactives se degageaient du verre de differentes compositions etait de 10{sup -4} pour cent par an environ, pour des hemispheres en verre pesant deux kilogrammes. Les donnees recueillies ont servi a evaluer les quantites de produits de fission qui s'echapperont du verre auquel auront ete incorporees les masses importantes de produits de fission qui s'accumuleront par suite du fonctionnement des reacteurs de puissance. (author) [Spanish] En Chalk River se ha continuado el estudio de un proceso para incorporar en vidrio para su evacuacion permanente los desechos de alto nivel radiactivo resultantes de los procesos de tratamiento quimico. Se ha, ensayado el sistema produciendo un vidrio que contiene hasta 50 curies de productos de fision de cinco a seis anos de edad por kilogramo. El procedimiento es intermitente y trabaja en partidas de cuatro kilogramos. Se ha demostrado que los productos de fision pueden ser incorporados al vidrio en forma eficaz y segura. El estudio de los muchos problemas que encierra el almacenaje permanente o la evacuacion del vidrio de alto nivel radiactivo ha llevado a la conclusion de que deberia ser enterrado en el suelo o almacenado en depositos subterraneos artificiales. En estas condiciones es siempre posible, caso de que sea necesario, proceder a un nuevo control de los desechos. Si la evacuacion se efectua enterrando los desechos, los productos de fision se liberan sobre todo mediante lixiviacion por las aguas subterraneas. Asi pues, es importante saber la velocidad con que los productos de fision se difundiran mediante este procedimiento. Se ha reunido buen numero de datos sobre la lixiviacion por agua en el laboratorio, y se ha encontrado que la velocidad de difusion depende de la composicion del vidrio. En todas las composiciones que se ensayaron las mediciones demostraron que la velocidad de lixiviacion de los productos de fision contenidos en el vidrio disminuye con el tiempo. Despues de varios meses de inmersion en agua la velocidad de difusion para vidrios de diversas composiciones era de 10{sup -4} por ciento aproximadamente por ano para una semiesfera de vidrio de dos kilogramos de peso. Los datos obtenidos han sido empleados para calcular la velocidad con que se difunden los productos de fision incorporados a vidrio en las grandes cantidades en que se acumularan como resultado del funcionamiento de los reactores generadores de energia. (author) [Russian] V Chok River prodolzhaetsja razrabotka processa zakljuchenija v steklo vysokoradioaktivnyh othodov, poluchaemyh v rezul'tate operacij po himicheskoj pererabotke, dlja okonchatel'nogo ih udalenija. Jetot process byl prodemonstrirovan proizvodstvom stekla, soderzhashhego do 50 kjuri smeshannyh rasshhepljajushhihsja produktov pjati-shestiletnej davnosti na kilogramm. Operacija provodilas' po ciklam po norme 4 kilogramma na cikl. Jeti operacii pokazali, chto rasshhepljajushhiesja produkty mogut byt' zakljucheny v steklo bezopasno i udobno. Rassmotrenie mnogih problem, svjazannyh s postojannym hraneniem ili okonchatel'nym udaleniem vysokoradioaktivnogo stekla privelo k vyvodu, chto ego sleduet zahoronjat' v zemlju ili hranit' v iskusstvennyh pogrebah, V takih uslovijah othody v sluchae neobhodimosti vsegda mogut byt' podvergnuty dopolnitel'nomu kontrolju. Esli othody pomeshhajutsja neposredstvenno v grunt, to osnovnym metodom, s pomoshh'ju kotorogo rasshhepljajushhiesja produkty mogut byt' vypushheny vo vneshnjuju sredu, javljaetsja vyshhelachivanie iz stekla v vodu. V svjazi s jetim schitajut vazhnym znat' skorost', pri kotoroj rasshhepljajushhiesja produkty budut rasseivat'sja jetim metodom. V laboratorii polucheno znachitel'noe kolichestvo dannyh o vyshhelachivanii s pomoshh'ju vody. Bylo najdeno, chto skorost' vyshhelachivanija zavisit ot sostava stekla. Izmerenija, provedennye pri ispytanii vseh sostavov stekla, pokazali, chto skorost' vyshhelachivanija rasshhepljajushhihsja produktov iz stekla so vremenem umen'shaetsja. Posle neskol'kih mesjacev prebyvanija v vode skorost' vysvobozhdenija iz stekla s razlichnym sostavom byla ravna primerno 10{sup -4} procenta v god ot dvuhkilogrammovoj stekljannoj polusfery. Poluchennye dannye byli ispol'zovany dlja opredelenija vysvobozhdenija rasshhepljajushhihsja produktov iz stekla, soderzhashhego bol'shie kolichestva rasshhepljajushhihsja produktov, kotorye budut akkumulirovat'sja v rezul'tate raboty jenergeticheskih reaktorov. (author)}
place = {IAEA}
year = {1960}
month = {Jul}
}