The Solubility of Some Uranium Compounds in Simulated Lung Fluid

Cooke, N.; Fb, Holt

doi:10.1097/00004032-197407000-00009

Cited by 42 publications

(21 citation statements)

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“…The chemical forms of the uranium fractions of the ore dust were not specified. Earlier, Cooke and Holt (1974) performed similar studies on various uranium compounds and identified uranium trioxide (U0 3 ) as a class W compound, and uranium dioxide (U0 2 ) and ratios predicted by the ICRP model (ICRP 1979) for class D, W, and Y compounds. This comparison clearly showed that both the uranium and thorium fractions in uranium ore dust behaved according to class Y characteristics; the adoption of either Class W or Class D l ung parameters for uranium resulted in feces/urine ratios that were much lower than those observed in excreta of millworkers.…”

Section: Metabolic Pathway Modelingmentioning

confidence: 91%

Measurements of /sup 234/U, /sup 238/U and /sup 230/Th in excreta of uranium-mill crushermen

Fisher¹,

Jackson²,

Brodacynski³

et al. 1982

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Pacific tlorthwest Laboratory conducted a research progr<2m to measure uranium and thorium levels in excreta of uranium mill crushermen who .J.re routinely exposed to airborne uranium ore dust. The purpose o-f this work was to determine whether 230 rh was preferentially retained ovet' either 234 u or 238 u in the body.Urine and fecal samples were obtained from fourteen active crushermen with long histories of exposure to uranium ore dust. plus four retired crushermen and three control individuals for comparison. Radiochemical procedures were used to separate out the uranium and thorium fractions. which were then electroplated on stainless steel discs and assayed by alpha spectrometry.Significantly greater activity levels of 234 u and 238 u were measured in both urine and fecal samples obtained from uranium mill crushermen, indicuting that uranium in the inhaled ore dust was cleared from the body with a shorter biological half-time than the daughter product 230 Th. The measurements also indicated that uraniur.1 and thorium separate _j___Q_ vivo and have distinct1y different metabolic pathways and transfer rates in the body. The appropriateness of current TCRP retention and clearance parameters for 230 rh in ore dust is questioned.; i i ABSTRACT ACKNOWLEDGMENTS

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Section: Metabolic Pathway Modelingmentioning

confidence: 91%

Measurements of /sup 234/U, /sup 238/U and /sup 230/Th in excreta of uranium-mill crushermen

Fisher¹,

Jackson²,

Brodacynski³

et al. 1982

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“…Table 3.2. Leach et al 1973;Cook and Holt 1974;Pomroy and Noel 1981;Schieferdecker et al 1985;Price 1989;Stradling et al 1989b;Métivier et al 1992;Eidson 1994;Chazel et al 2000b;Ansoborlo et al 2002;Stradling et al 2002 Uranium West et al 1979;Eidson and Mewhinney 1980;Chalabreysse et al 1989;Stradling et al 1989aStradling et al , 2002Eidson 1990Eidson , 1994Métivier et al 1992;Barber and Forrest 1995;Ansoborlo et al 1998bAnsoborlo et al , 2002Chazel et al 1998 Uranium Stradling et al 1985Stradling et al , 2002Chalabreysse et al 1989;André et al 1989;Ansoborlo et al 1990Ansoborlo et al , 2002Eidson 1994;Chazel et al 2000a Uranium Galibin and Parfenov 1971;Cook and Holt 1974;Boback 1975;Eidson and Mewhinney 1980;Damon et al 1984;Stradling et al 1987Stradling et al , 2002Eidson 1994;Ansoborlo et al 2002 In vitro studies indicate dissolution rate varies with mixture of materials and preparation process. Differences found in dissolution rates of low-fired yellowcake (dried at less than 400° C) and high-fired (calcined) yellowcake (dried at 4...…”

Section: Application Of the Hrtm To Various Forms Of Uraniummentioning

confidence: 99%

Controlling intake of uranium in the workplace: Applications of biokinetic modeling and occupational monitoring data

Leggett¹,

Eckerman²,

McGinn³

et al. 2012

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This report provides methods to interpret and apply occupational uranium monitoring data. The methods are based on current international radiation protection guidance, current information on the chemical toxicity of uranium, and best available biokinetic models for uranium. Emphasis is on air monitoring data and three types of bioassay data: the concentration of uranium in urine; the concentration of uranium in feces; and the externally measured content of uranium in the chest. Primary Reference guidance levels for prevention of chemical effects and limitation of radiation effects are selected based on a review of current scientific data and regulatory principles for setting standards. Generic investigation levels and immediate action levels are then defined in terms of these primary guidance levels. The generic investigation and immediate actions levels are stated in terms of radiation dose and concentration of uranium in the kidneys. These are not directly measurable quantities, but models can be used to relate the generic levels to the concentration of uranium in air, urine, or feces, or the total uranium activity in the chest. Default investigation and immediate action levels for uranium in air, urine, feces, and chest are recommended for situations in which there is little information on the form of uranium taken into the body. Methods are prescribed also for deriving case-specific investigation and immediate action levels for uranium in air, urine, feces, and chest when there is sufficient information on the form of uranium to narrow the range of predictions of accumulation of uranium in the main target organs for uranium: kidneys for chemical effects and lungs for radiological effects. In addition, methods for using the information herein for alternative guidance levels, different from the ones selected for this report, are described. v FOREWORDThis report provides a detailed description of uranium biokinetics and bioassays applicable to evaluation of health risks from potential intakes in an occupational setting. The report addresses both the radiotoxicity and chemical (renal) toxicity of uranium. For reference occupational exposure scenarios, predictions of the time-dependent concentration of uranium in tissues and bioassay are based on biokinetic models currently recommended by the International Commission on Radiological Protection (ICRP). The ICRP's models and default assumptions for uranium were based primarily on data for human subjects exposed to uranium in controlled studies or in occupational or environmental settings. In addition, the ICRP considered an extensive database for uranium in laboratory animals. Sensitivity studies examine the robustness of these models and assumptions to ensure that radiation doses and accumulation of uranium in the kidneys are not underestimated. For example, analyses indicate that a default 5 µm activity median aerodynamic diameter particle size can lead to an underestimation of radiation dose as well as the concentration of uranium in the kidneys if inhal...

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“…Très tôt des tests de solubilité in vitro ont été développés (Kanapilly et al, 1973 ;Cooke et Holt, 1974 ;Eidson, 1994) utilisant pour la plupart des solutions simulant la composition chimique des liquides extracellulaires décrits par Gamble (1967). Toutefois, l'universalité de cette méthode est parfois mise en défaut compte tenu de la méthodologie appliquée (Fleischer, 1975 ;Carter, 1995).…”

Section: La Nature Des éTudes En Radiotoxicologieunclassified

Mieux connaître le devenir biologique des futurs matériaux nucléaires, une nécessité pour maintenir un bon niveau de radioprotection

Métivier¹,

Guillaumont

2007

Radioprotection

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RésuméUn important programme de recherches, appelé « Generation IV », est actuellement développé au niveau international pour préparer les réacteurs du futur et leurs AbstractTo better know the biological behaviour of future nuclear materials: a need to maintain a good level of protection against ionising radiation.An important program of research, called "Generation IV" is currently developed at an international level to prepare the launching of reactors for the future. Its objective is to satisfy the growing needs in electric power within the framework for a sustainable development. One of the major aspects of this program is the search and the development for new nuclear materials containing fissile/fertile isotopes. Unfortunately, one realizes today that for many compounds considered to be used to manufacture these materials, there are no radiotoxicologic data, allowing to the occupational physicist to evaluate the real risk in the event of contaminations and to prescribe adapted therapeutic de-corporation. An emergency revival of "workplace" studies, where are or will be handled these compounds or materials is mandatory. The lesson of the past showed that the prevision in radioprotection was rather difficult and that an experimental validation of the behaviour of hazardous heavy elements both in vitro and in vivo was necessary.Keywords: nuclear fuels / generation IV / internal dosimetry / biokinetics / DPUI 1 2 allée des Hautes Futaies, 91450 Soisy-sur-Seine, France. 2 Membre de l'Académie des sciences, 7 rue E. Branly, 91120 Palaiseau, France.Article published by EDP Sciences and available at http://www.edpsciences.org/radiopro or http://dx

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The Solubility of Some Uranium Compounds in Simulated Lung Fluid

Cited by 42 publications

References 0 publications

Measurements of /sup 234/U, /sup 238/U and /sup 230/Th in excreta of uranium-mill crushermen

Measurements of /sup 234/U, /sup 238/U and /sup 230/Th in excreta of uranium-mill crushermen

Controlling intake of uranium in the workplace: Applications of biokinetic modeling and occupational monitoring data

Mieux connaître le devenir biologique des futurs matériaux nucléaires, une nécessité pour maintenir un bon niveau de radioprotection

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