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Disposal of Low-Activity Liquid Effluents by Dilution; Elimination par Dilution d'Effluents Liquides Faiblement Radioactifs; 0423 0414 0410 041b 0414 ; Eliminacion de Efluentes Liquidos de Baja Radiactividad por Dilucion

Abstract

From the results already obtained in France by monitoring radioactivity in the neighbourhood of nuclear plant, some conclusions may be drawn regarding the choice of disposal procedures. I. Results obtained In 1957 we started a progressive study of the effect exerted by nuclear plant. In order to establish the proportion due to the nuclear centres, the study comprises determination of the levels of natural radioactivity and artificial contamination. Examples related to reference areas are quoted. The greater part of artificial radioactivity is apparently due to radioactive fall-out; this is not surprising, considering the quantities of radioactive isotopes disposed of in France to date. Some laboratory tests have been made. These have helped to determine certain mechanisms, have increased our knowledge of site pollution, and have enabled us to improve our sampling methods. II. Laboratory tests These were concerned with 1. adsorption phenomena similar to those occurring in rivers and streams in the course of effluent dilution: fixation on finely-divided minerals, e.g. mica and quartz. Radioisotopes such as Sr{sup 9}'0, Cs{sup 137} and Y{sup 90} appear to behave very differently: under average disposal conditions Sr{sup 90} seems to be the least adsorbed; 2. soil and plant contamination, utilizing columns and cubes  More>>
Authors:
Bovard, P.; Candillon, C. [1] 
  1. Service de Controle des Radiations et de Genie Radioactif, Commissariat a l'Energie Atomique, Saclay (France)
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: 3 figs., 14 tabs.; 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; ADSORPTION; CESIUM 137; DILUTION; MICA; NATURAL RADIOACTIVITY; NUCLEAR POWER PLANTS; QUARTZ; RADIOACTIVE WASTE DISPOSAL; RADIOACTIVE WASTE FACILITIES; RADIOACTIVE WASTE PROCESSING; RADIOACTIVE WASTES; SITE SELECTION; STRONTIUM 90; YTTRIUM 90
OSTI ID:
22192376
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:
French
Other Identifying Numbers:
Other: ISSN 0074-1884; TRN: XA13M3500016865
Submitting Site:
INIS
Size:
page(s) 301-318
Announcement Date:
Feb 20, 2014

Citation Formats

Bovard, P., and Candillon, C. Disposal of Low-Activity Liquid Effluents by Dilution; Elimination par Dilution d'Effluents Liquides Faiblement Radioactifs; 0423 0414 0410 041b 0414 ; Eliminacion de Efluentes Liquidos de Baja Radiactividad por Dilucion. IAEA: N. p., 1960. Web.
Bovard, P., & Candillon, C. Disposal of Low-Activity Liquid Effluents by Dilution; Elimination par Dilution d'Effluents Liquides Faiblement Radioactifs; 0423 0414 0410 041b 0414 ; Eliminacion de Efluentes Liquidos de Baja Radiactividad por Dilucion. IAEA.
Bovard, P., and Candillon, C. 1960. "Disposal of Low-Activity Liquid Effluents by Dilution; Elimination par Dilution d'Effluents Liquides Faiblement Radioactifs; 0423 0414 0410 041b 0414 ; Eliminacion de Efluentes Liquidos de Baja Radiactividad por Dilucion." IAEA.
@misc{etde_22192376,
title = {Disposal of Low-Activity Liquid Effluents by Dilution; Elimination par Dilution d'Effluents Liquides Faiblement Radioactifs; 0423 0414 0410 041b 0414 ; Eliminacion de Efluentes Liquidos de Baja Radiactividad por Dilucion}
author = {Bovard, P., and Candillon, C.}
abstractNote = {From the results already obtained in France by monitoring radioactivity in the neighbourhood of nuclear plant, some conclusions may be drawn regarding the choice of disposal procedures. I. Results obtained In 1957 we started a progressive study of the effect exerted by nuclear plant. In order to establish the proportion due to the nuclear centres, the study comprises determination of the levels of natural radioactivity and artificial contamination. Examples related to reference areas are quoted. The greater part of artificial radioactivity is apparently due to radioactive fall-out; this is not surprising, considering the quantities of radioactive isotopes disposed of in France to date. Some laboratory tests have been made. These have helped to determine certain mechanisms, have increased our knowledge of site pollution, and have enabled us to improve our sampling methods. II. Laboratory tests These were concerned with 1. adsorption phenomena similar to those occurring in rivers and streams in the course of effluent dilution: fixation on finely-divided minerals, e.g. mica and quartz. Radioisotopes such as Sr{sup 9}'0, Cs{sup 137} and Y{sup 90} appear to behave very differently: under average disposal conditions Sr{sup 90} seems to be the least adsorbed; 2. soil and plant contamination, utilizing columns and cubes of soil in situ. We found it necessary to standardize our samples so as to facilitate further analysis and make the results comparable. III. Site selection and ways and means of disposal From this group of still incomplete results and studies we are attempting to educe certain principles to govern site selection. Once the site has been chosen, the experience gained enables natural conditions to be turned to account. (author) [French] Des resultats deja fournis par la surveillance en France, de la radioactivite aux alentours des installations nucleaires, il est possible de tirer certains enseignements quant au choix des processus de rejet. I. Resultats obtenus Nous avons commence en 1957 une etude evolutive de l'incidence des installations nucleaires. Cette etude embrasse la determination des niveaux - de radioactivite naturelle - de contamination artificielle afin d'en degager la part revenant aux Centres Nucleaires. Des exemples sont cites faisant appel a des zones de reference. La plus grande partie de la radioactivite artificielle semble due aux retombees radioactives; ceci n'est pas surprenant si on examine les quantites d'isotopes radioactifs rejetees jusqu'a present en France. Un certain nombre d'essais de laboratoire ont ete effectues. Ils ont contribue a preciser certains mecanismes, ont accru notre connaissance de la pollution des sites et nous ont permis d'ameliorer nos methodes de prelevement. II. Essais de laboratoire Ils ont porte: 1. sur des 'phenomenes d'adsorption analogues a ceux produits dans les rivieres au cours de la dilution des effluents: fixation sur mineraux tres divises: mica, quartz. Des radioisotopes tels que {sup 90}Sr, {sup 137}Cs, {sup 90}Y semblent se comporter fort differemment: dans les conditions moyennes de rejet, le {sup 90}Sr serait le moins adsorbe. : 2. sur la contamination du sol et des vegetaux par l'emploi de colonnes et de cubes de sol en place. Ceci nous a conduit a standardiser nos prelevements, afin de faciliter les analyses ulterieures et de comparer utilement les resultats. III. Choix du site et modalites des rejets De ce faisceau de resultats et d'etudes encore incomplets, nous essayons de degager quelques principes quant au choix des sites. Le site une fois defini, l'experience acquise permet de tirer le meilleur parti des possibilites naturelles. (author) [Spanish] Con los resultados obtenidos en Francia vigilando la radiactividad en las proximidades de las instalaciones nucleares se pueden extraer determinadas conclusiones acerca de la eleccion de los procedimientos de evacuacion. I. Resultados obtenidos Los autores iniciaron en 1957 un estudio evolutivo de las instalaciones nucleares. El estudio comprende la determinacion de los niveles - de radiactividad natural - de contaminacion artificial con objeto de determinar la parte que corresponde a los centros nucleares. Se citan varios ejemplos correspondientes a zonas de referencia. La mayor parte de la radiactividad artificial parece deberse a las precipitaciones radiactivas atmosfericas; esto no es sorprendente si se tiene en cuenta la cantidad de isotopos radiactivos eliminados hasta ahora en Francia. Los autores han efectuado algunos ensayos de laboratorio. Gracias a ellos han podido precisar determinados mecanismos, han aumentado sus conocimientos sobre la contaminacion de los lugares y han podido mejorar sus metodos de muestreo. II. Ensayos de laboratorio Versaban sobre : 1. fenomenos de adsorcion analogos a los que se producen en los rios durante la dilucion de los efluentes: fijacion en minerales muy divididos: mica, cuarzo. Algunos radioisotopos como el {sup 90}Sr, el {sup 137}Cs y el {sup 90}Y parecen conducirse de muy diversa manera: en las condiciones normales de eliminacion, el {sup 90}Sr parece ser el menos adsorbido. (author) [Russian] Na osnovanii imejushhihsja vo Francii dannyh o radioaktivnosti v okres- nostjah jadernyh ustanovok vpolne vozmozhno izvlech' nekotorye uroki o vybore processa udalenija. I. Poluchennye rezul'taty V 1957 godu bylo nachato postojannoe izuchenie vlijanija jadernyh ustanovok. Jeto izuchenie ohvatyvaet opredelenie urovnej - estestvennoj radioaktivnosti - iskusstvennogo zagrjaznenija s tem, chtoby ustanovit' dolju zagrjaznenija, vyzyvaemuju jadernymi centrami. Privodjatsja primery po otdel'nym zonam. Predstavljaetsja, chto naibol'shaja chast' iskusstvennoj radioaktivnosti vyzyvaetsja radioaktivnymi osadkami; jeto neudivitel'no, esli prinjat' vo vnimanie kolichestvo radioaktivnyh izotopov, vybroshennyh do nastojashhego vremeni vo Francii. Byl proveden celyj rjad laboratornyh opytov. Oni pomogli utochnit' nekotorye mehanizmy, uvelichili znanija otnositel'no zagrjaznenija mestnosti i pozvolili uluchshit' metody otbora prob. II. Laboratornye opyty Oni kasalis: 1. javlenij absorbcii, analogichnyh tem, kotorye nabljudajutsja v rekah vo vremja razbavlenija othodov: fiksacija v razlichnyh mineralah: sljuda, kvarc. Takie radioizotopy, kak stroncij-90, cezij-137, ittrij-90-vedut sebja po raznomu: v obychnyh uslovijah udalenija othodov stroncij-90 javljaetsja naibolee trudno poglotimym jelementom. 2. zagrjaznenija pochvy i rastenij putem primenenija pochvennyh kolonn i kubov na mestah. Jeto pomoglo standartizirovat' otbory prob s cel'ju oblegchenija posledujushhih analizov i poleznogo sravnenija rezul'tatov. III. Vybor mest i sposobov udalenija Ispol'zuja jetot kompleks rezul'tatov i eshhe nepolnyh issledovanij, byla predprinjata popytka opredelit' nekotorye principy otnositel'no vybora mest. Posle vybora mesta, nakoplennyj opyt pozvoljaet ispol'zovat' nailuchshim sposobom estestvennye vozmozhnosti. (author)}
place = {IAEA}
year = {1960}
month = {Jul}
}