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Human Internal Contamination with Strontium-90 Titanate; Contamination Interne du Corps Humain par le Titanate de Strontium 90; 0412 041d 0414 ; Contaminacion Interna del Cuerpo Humano con Titanato de Estroncio-90

Abstract

Strontium-90 has been used in multikilocurie quantities recently as a heat source for thermoelectric generators. The titanate was carefully selected for this purpose as the chemical form which best met requirements including inertness to corrosive attack in the event of accidental release to the environment. An industrial accidental exposure of one worker on 26 June 1963 to strontium-90 titanate powder, originally in the form of particles of about 120 {mu}m and less, provided an opportunity to attempt the assessment of the human body burden of this supposedly highly insoluble compound. Because of the physical and biological behaviour of the particles, it was assumed that the actual particle size which was dispersed and ingested and/or inhaled by the exposed person was in the range of 1 to 30 {mu}m. Three techniques were used to estimate the body burden. Whole-body radiation counting carried out by Dr. Charles H. Miller at Argonne National Laboratory, which only gave an upper limit because of the non-specific Bremsstrahlung spectrum from strontium-90, yttrium-90 indicated an initial total-body burden of 4.8 {mu}c. The second method, total urinary and faecal output collection, totalled 5.0 for the first 20 d. Combining that amount with an estimate of the amount retained  More>>
Authors:
Bradley, F. J.; Wald, N.; Wechsler, R. L. [1] 
  1. Graduate School of Public Health and School of Medicine, University of Pittsburgh, Pittsburgh, PA (United States)
Publication Date:
Nov 15, 1964
Product Type:
Conference
Report Number:
IAEA-SM-52/66
Resource Relation:
Conference: Symposium on the Assessment of Radioactive Body Burdens, Heidelberg (Germany), 11-16 May 1964; Other Information: 9 refs., 3 tabs., 4 figs.; Related Information: In: Assessment of Radioactivity in Man. Vol. II. Proceedings of the Symposium on the Assessment of Radioactive Body Burdens| 671 p.
Subject:
63 RADIATION, THERMAL, AND OTHER ENVIRONMENTAL POLLUTANT EFFECTS ON LIVING ORGANISMS AND BIOLOGICAL MATERIALS; BLOOD; BODY BURDEN; BREMSSTRAHLUNG; EXCRETION; MAGNESIUM SULFATES; PARTICLE SIZE; PARTICLES; RADIONUCLIDE KINETICS; STRONTIUM 90; THERMOELECTRIC GENERATORS; TITANATES; YTTRIUM 90; NESDPS Office of Nuclear Energy Space and Defense Power Systems
OSTI ID:
22200064
Research Organizations:
International Atomic Energy Agency, Vienna (Austria); International Labour Organisation, Geneva (Switzerland); World Health Organization, Geneva (Switzerland)
Country of Origin:
IAEA
Language:
English
Other Identifying Numbers:
Other: ISSN 0074-1884; TRN: XA13M3270020887
Submitting Site:
INIS
Size:
page(s) 401-415
Announcement Date:
Feb 27, 2014

Citation Formats

Bradley, F. J., Wald, N., and Wechsler, R. L. Human Internal Contamination with Strontium-90 Titanate; Contamination Interne du Corps Humain par le Titanate de Strontium 90; 0412 041d 0414 ; Contaminacion Interna del Cuerpo Humano con Titanato de Estroncio-90. IAEA: N. p., 1964. Web.
Bradley, F. J., Wald, N., & Wechsler, R. L. Human Internal Contamination with Strontium-90 Titanate; Contamination Interne du Corps Humain par le Titanate de Strontium 90; 0412 041d 0414 ; Contaminacion Interna del Cuerpo Humano con Titanato de Estroncio-90. IAEA.
Bradley, F. J., Wald, N., and Wechsler, R. L. 1964. "Human Internal Contamination with Strontium-90 Titanate; Contamination Interne du Corps Humain par le Titanate de Strontium 90; 0412 041d 0414 ; Contaminacion Interna del Cuerpo Humano con Titanato de Estroncio-90." IAEA.
@misc{etde_22200064,
title = {Human Internal Contamination with Strontium-90 Titanate; Contamination Interne du Corps Humain par le Titanate de Strontium 90; 0412 041d 0414 ; Contaminacion Interna del Cuerpo Humano con Titanato de Estroncio-90}
author = {Bradley, F. J., Wald, N., and Wechsler, R. L.}
abstractNote = {Strontium-90 has been used in multikilocurie quantities recently as a heat source for thermoelectric generators. The titanate was carefully selected for this purpose as the chemical form which best met requirements including inertness to corrosive attack in the event of accidental release to the environment. An industrial accidental exposure of one worker on 26 June 1963 to strontium-90 titanate powder, originally in the form of particles of about 120 {mu}m and less, provided an opportunity to attempt the assessment of the human body burden of this supposedly highly insoluble compound. Because of the physical and biological behaviour of the particles, it was assumed that the actual particle size which was dispersed and ingested and/or inhaled by the exposed person was in the range of 1 to 30 {mu}m. Three techniques were used to estimate the body burden. Whole-body radiation counting carried out by Dr. Charles H. Miller at Argonne National Laboratory, which only gave an upper limit because of the non-specific Bremsstrahlung spectrum from strontium-90, yttrium-90 indicated an initial total-body burden of 4.8 {mu}c. The second method, total urinary and faecal output collection, totalled 5.0 for the first 20 d. Combining that amount with an estimate of the amount retained in the body, an initial total-body burden of 5.2 {mu}c was obtained. The third technique, blood radioactivity determination, indicated an initial total-body burden of 6 {mu}c. The ratio of faecal to urinary output in the first 20 d was 15 to 1, and 94% of the total strontium-90 excretion was via the gastro-intestinal tract. It is of interest, however, that a significant fraction was evidently soluble. By the 20th post-incident day, it was estimated that the retained body burden was only 5% of the total intake. Methods used in that period to enhance faecal excretion by MgSO{sub 4} and urinary excretion by a combination of Ca-gluconate and NH{sub 4}CI are described. Subsequent excretion patterns and the current estimate of the retained body burden are presented. (author) [French] Le strontium 90 a ete recemment utilise en quantites de l'ordre de plusieurs kilocuries comme source de chaleur pour des generateurs thermoelectriques. Apres une etude approfondie, on a choisi a cette fin le titanate comme etant la forme chimique dont les proprietes satisfont le mieux aux exigences de la situation et qui notamment resiste bien a la corrosion en cas de liberation accidentelle dans l'environnement. A la suite de la contamination accidentelle d'un ouvrier par du titanate de strontium 90 en poudre - a l'origine sous forme de particules d'environ 120 M au maximum le 20 juin 1963, on a pu tenter d'evaluer la charge corporelle de ce compose, considere comme tres peu soluble. D'apres le comportement physique et biologique des particules, on a suppose que la dimension effective des particules dispersees puis absorbees par voie digestive ou respiratoire, ou par l'une et l'autre a la fois, etait comprise entre 1 et 30 {mu}. Trois techniques differentes ont ete utilisees pour l'evaluation de la charge corporelle. En recourant a l'anthropogammameme, qui en raison de la non-specificite du spectre du rayonnement de freinage du strontium 90 - yttrium 90 n'a donne qu'une limite superieure, Dr. Charles E. Miller, du Laboratoire national d'Argonne, a evalue la charge corporelle totale initiale a 4,8 {mu}c. Avec la deuxieme methode, fondee sur la collecte de la totalite des excreta elimines par voie urinaire et fecale, la charge corporelle totale a ete evaluee a 5,0 {mu}c pour les 20 premiers jours. En additionnant cette radioactivite a celle que l'on estime avoir ete retenue par l'organisme, on a obtenu une charge corporelle totale initiale de 5,2 {mu}c. Avec la troisieme methode, c'est-a-dire la determination de la radioactivite dans le sang, on a obtenu une charge corporelle initiale totale de 6 {mu}c. Le rapport elimination fecale/elimination urinaire a ete, pendant les 20 premiers jours, de 15 a 1,94% de la quantite totale de strontium 90 eliminee a ete evacuee par'l'intermediaire du tractus gastro-intestinal. Il y a lieu toutefois de noter qu une fraction significative de cette quantite etau manifestement soluble. Vingt jours apres l'accident, on a calcule que la retention ne representait que 5%de la radioactivite totale absorbee. Les auteurs decrivent les methodes'qui' ont ete utilisees au cours de cette periode pour stimuler l'elimination fecale au moyen de MgSO{sub 4} et l'elimination urinaire en combinant le gluconate de calcium et NH{sub 4}CI. Ils donnenj des indications sur le regime ulterieur de-relimination et sur les dernieres evaluations de la retention. (author) [Spanish] Recientemente el estroncio 90 viene utilizandose en cantidades de multikilocuries como fuente termica para generadores termoelectricos. El titanato fue cuidadosamente eiegido para este proposito como la forma quimica que reune las mejores condiciones, incluyendo la resistencia a la corrosion; para el'caso de una liberacion accidental al medio ambiente. El accidente sufrido por un obrero de la industria el 26 de junio de 1963 al exponerse a la accion de polvo de titanato de estroncic-90, originalmente en forma de particulas de unas 120 {mu} o menos, brindo la oportunidad de determinar la carga corporal de este compuesto; que se considera-como altamente insoluble. Debido al comportamiento fisico y biologico de las particulas, se supuso que el tamano real de las mismas, que se dispersaron fueron ingeridas o inhaladas, o ambas cosas, por la-persona expuesta, era del orden de 1 a 30 p. Se utilizaron tres tecnicas diferentes para estimar-la carga corporal. La antropogamma- metria lleyada a cabo por el Dr. Charles E. Miller en el Laboratorio Nacional de Argonne, que solo proporciono un limite superior debido a la inespecificidad del espectro de la radiacion de frenado (Bremsstrahlung) del estroncio-90 - itrio-90, indico una cantidad total de 4,8 {mu}c para la carga corporal inicial. El segundo metodo, basado en la recoleccion de toda'la orina y hecesarrojo un total de 5,0 {mu}c en los 20 primeros dias. Al combinar esta cantidad con una estimacion de la que qufedaba retenida en el cuerpo, se obtuvo una carga inicial de-5.2 Me. La'tercera tecnica, esto es, la determinacion de radiactividad en la sangre, indico una carga inicial de 6 {mu}c. La relacion de contenidos en heces y orina fue, durante los primeros 20 d, de 15 a 1, realizandose la excrecion del 94% de la totalidad del estroncio-90 por el tracto gastrointestinal. Es de destacar, sin embargo, que una buena parte era soluble. Al vigesimo dia del accidente, se calculo que la cantidad presente en el cuerpo era solamente un 5% del total inicial. Se describen los metodos empleados durante aquel periodo para estimular la excrecion fecal por medio de MgSO y-la urinaria por una combinacion de gluconato de calcio y NH Cl. Asimismo, se presentan esquemas de excrecion y evaluaciones actuales de la cantidad retenida por el cuerpo. (author) [Russian] Stroncij-90 ispol'zovalsja nedavno v bol'shih kolichestvah (neskol'ko kilokjuri) kak istochnik tepla dlja termojelektricheskih generatorov. Dlja jetoj celi posle tshhatel'nogo otbora byl vzjat titanat, kak himicheskaja forma, nailuchshim obrazom otvechajushhaja vsem trebovanijam, vkljuchaja inertnost'-k vlijaniju k rrozii v, sluchae, avarijnogo vysvobozhdenija v okruzhajushhuju sredu. Posle promyshlennogo avarijnogo obluchenija odnogo rabochego 26 ijunja 1963 goda poroshkom titanata stroncija-90,pervonachal'no v forme chastic okolo 120 mikron i-mel'che, sdelana popytka ocenit' soderzhanie vo vsem organizme, jetogo, kak-predpolagaetsja, v vysshej stepeni nerastvorimogo soedinenija. Uchityvaja fizicheskoe i biologicheskoe povedenie chastic,predpolozhili, chto fakticheskij razmer chasticy, kotoraja dispersirovalas, pogloshhalas' i/ili vdyhalas' obluchennym pacientom, sostavljal 1-30 mikron. Dlja ocenki soderzhanija radioaktivnosti v organizme ispol'zovalis' tri metoda. Pervyj metod- izmerenie obluchenija vsego organizma. Ono provodilos' d-rom Ch.Millerom v Argonskoj nacional'noj laboratorii, chto pozvolilo opredelit' tol'ko verhnij predel iz-za nejarko vyrazhennogo spektra tormoznogo izluchenija stroncij-90 - ittrij-90 i ukazalo na pervonachal'noe soderzhanie radioaktivnosti vo vsem organizme ravnoe'4,8 mkkjuri. Vtoroj metod - sbor vsego kolichestva mochi i- kala dal 5 mkkjuri dlja pervyh 20 dnej.: Putem soedinenija jetogo kolichestva s predpolagaemym kolichestvom, ostavshimsja v organizme,bylo polucheno pervonachal'noe1 soderzhanie radioaktivnosti vo vsem-organizme 5,2. mkkjuri. Tretij metod -opredelenie .radioaktivnosti krovi ukazal na pervonachal'noe soderzhanie radioaktivnosti vo vsem organizme ravnoe -6 mkkjuri. Sootnoshenie vydelenija izotopa s mochoj i kalom v pervye 20.dnej sostavljalo 15,: 1 i 94% vydeljajushhegosja stroncija-90 prohodilo cherez zheludochno-kishechnyj trakt. Odnako interesno otmetit', chto znachitel'naja frakcjja byla nesomnenno rastvorima. K 20 dnju posle avarii bylo podschitano', chto zaderzhka izotopa v organizme sostavljala tol'ko 5% ot obshhego pogloshhenija. Daetsja opisanie metodov, ispol'zovavshihsja v jetot'period, dlja uvelichenija vyvedenija s'kalom s pomoshh'ju- MgSO i vydelenija s mochoj putem kombinacii gljukonata kal'cija's NH{sub 4}Cl. Predstavleny posledujushhie sposoby vyvedenija -odnovremennaja ocenka ostavshegosja v organizme kolichestva izotopa. (author)}
place = {IAEA}
year = {1964}
month = {Nov}
}