Content of Uranium in Urine of Uranium Miners in Relation to Personal Dosimetry of Long ? Lived Alpha Radionuclides

Kód výsledku v IS VaVaI

<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F86652052%3A_____%2F12%3A%230000032" target="_blank" >RIV/86652052:_____/12:#0000032 - isvavai.cz</a>

Výsledek na webu

<a href="http://www.irpa13glasgow.com/information/downloads" target="_blank" >http://www.irpa13glasgow.com/information/downloads</a>

DOI - Digital Object Identifier

—

Jazyk výsledku

angličtina

Název v původním jazyce

Content of Uranium in Urine of Uranium Miners in Relation to Personal Dosimetry of Long ? Lived Alpha Radionuclides

Popis výsledku v původním jazyce

Results of experimental study of aerosol served for model calculations of retention and excretion of uranium using the biokinetic ICRP models and data from personal dosimeters of individual miners as input data. For model calculations, input data assuming AMAD of inhaled aerosol 6?m, rapid fraction Fr = 0.14, rapid dissolution rate Fr= 0.49d-1 and slow dissolution rate ?r= 0.49d-1 for dissolution in lungs were used Results of model calculation of uranium content in the urine were compared with the experimental findings, the range of ratios was quite wide with log ? normal distribution with median 0.58 and GSD 1.8 when results of 18 hewers were used and median 0.44 and GSD 2.0 when results of 40 miners were used. It was found that modelled values were higher nearly for all individuals, so the actual doses from inhaled LLR were lower than assumed.

Název v anglickém jazyce

Content of Uranium in Urine of Uranium Miners in Relation to Personal Dosimetry of Long ? Lived Alpha Radionuclides

Popis výsledku anglicky

Results of experimental study of aerosol served for model calculations of retention and excretion of uranium using the biokinetic ICRP models and data from personal dosimeters of individual miners as input data. For model calculations, input data assuming AMAD of inhaled aerosol 6?m, rapid fraction Fr = 0.14, rapid dissolution rate Fr= 0.49d-1 and slow dissolution rate ?r= 0.49d-1 for dissolution in lungs were used Results of model calculation of uranium content in the urine were compared with the experimental findings, the range of ratios was quite wide with log ? normal distribution with median 0.58 and GSD 1.8 when results of 18 hewers were used and median 0.44 and GSD 2.0 when results of 40 miners were used. It was found that modelled values were higher nearly for all individuals, so the actual doses from inhaled LLR were lower than assumed.

Druh

A - Audiovizuální tvorba

CEP obor

DL - Jaderné odpady, radioaktivní znečištění a kontrola

OECD FORD obor

—

Projekt

—

Návaznosti

I - Institucionalni podpora na dlouhodoby koncepcni rozvoj vyzkumne organizace

Rok uplatnění

2012

Kód důvěrnosti údajů

S - Úplné a pravdivé údaje o projektu nepodléhají ochraně podle zvláštních právních předpisů

ISBN

—

Místo vydání

Glasgow

Název nakladatele resp. objednatele

International Radiation Protection Association

Verze

—

Identifikační číslo nosiče

—